Text

301 ADAMS2B Final Exam Items Delay Release
	ML17241A216
Person / Time
Site:	Catawba
Issue date:	08/29/2017
From:	; NRC/RGN-II
To:	; Duke Energy Corp
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	Download: ML17241A216 (788)
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Catawba Nuclear Station NRC Exam June 2017 Scenario #1 Catawba 2017 NRC Exam Page 1 of 139 2017 INITIAL LICENSE NRC EXAM SCENARIO # 1 Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario #1 Catawba 2017 NRC Exam Page 2 of 139 Facility: Catawba NRC Exam 2017 Scenario No.: 1 Op Test No.: 2017301 Examiners: Operators: SRO RO BOP Initial Conditions: Unit 1 is at 75% power at the EOL. Unit 2 is at 100% power. Turnover: Unit 1 is at 75% power at the EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours0.125 days 0.0179 weeks 0.00411 months and is expected to be returned to service in 6 hours0.25 days 0.0357 weeks 0.00822 months . 1A Condensate Booster Pump is tagged out for emergent motor replacement. Direction for the crew is to decrease reactor power to 50% to secure a main feedwater pump in preparation for entering a Unit 1 Refueling Outage. A reactivity plan has been provided by Reactor Engineering for a 10% per hour decrease in reactor power. Event No. Malf. No. Event Type* Event Description 1 R - RO N BOP N SRO Decrease reactor power 2 CM004F C BOP C SRO 1B CFPT suction valve fails closed / 1B CFPT fails to auto trip 3 NC005F C RO C SRO TS - SRO NC PORV 1NC-32B fails open 4 NV020D C BOP TS SRO 1A NV pump trips 5 IPX001A IPX001B C RO C SRO 1A CFPT trips / Reactor fails to automatically trip 6 CA005 EP008B M ALL Loss of Secondary Heat Sink 7 EP008B CA005 C RO 1ETB Blackout / CAPT #1 fails to autostart 8 NI001A C BOP C - SRO 1A NI pump fails to auto start on initiation of Feed and Bleed * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario #1 Catawba 2017 NRC Exam Page 3 of 139 Scenario 1 Summary Initial Condition Unit 1 is at 75% power at the EOL. Unit 2 is at 100% power. Turnover: Unit 1 is at 75% power at the EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours0.125 days 0.0179 weeks 0.00411 months and is expected to be returned to service in 6 hours0.25 days 0.0357 weeks 0.00822 months . 1A Condensate Booster Pump is tagged out for emergent motor replacement. Direction for the crew is to decrease reactor power to 50% to secure a main feedwater pump in preparation for entering a Unit 1 Refueling Outage. A reactivity plan has been provided by Reactor Engineering for a 10% per hour decrease in reactor power. Event 1 BOP will perform an initial boration and RO will input desired load rate and target load into the main decrease at 10%/hour. Event 2 The 1B CFPT suction valve (1CM-140) will fail closed. 1B CFPT will not trip on low suction pressure or low suction flow. Following manual trip of the 1B CFPT, the crew will enter AP/1/A/5500/003 (Load Rejection) Case 1 (Switchyard Available) to address the turbine runback. Verifiable Action BOP will manually trip 1B CFPT. Event 3 NC PORV 1NC-32B will fail open. Crew will enter AP/1/A/5500/011 (Pressurizer Pressure Anomalies) to address this failure. Verifiable Action The RO will attempt to manually close 1NC-32B. This valve will not close and the RO will be required to close the PORV isolation valve, 1NC-31B, to isolate the failed open PORV. Event 4 1A NV pump will trip. The crew will enter AP/1/A/5500/012 (Loss of Charging or Letdown) to address this failure. Verifiable Action BOP will start the 1B NV pump and restore normal letdown to service per AP/1/A/5500/012. Event 5 A trip of the running Condensate Booster Pumps will cause 1A CFPT to trip on low suction pressure after 20 seconds. The RO will take the immediate actions of AP/1/A/5500/006 (Loss of S/G Feedwater) to manually trip Unit 1 reactor. Verifiable Action RO trips Unit 1 reactor. Event 6 A loss of secondary heat sink will occur following loss of all power to 1ETB (1A CA pump tagged out & 1B CA pump loss of power) and subsequent overspeed trip of CAPT #1. Verifiable Action RO will start CAPT #1 following failure of it to autostart. Crew will eventually enter EP/1/A/5000/FR-H.1 (Loss of Secondary Heat Sink), and establish NC system feed and bleed. Event 7 1ETB will lose all power and CAPT #1 will fail to autostart on the blackout. Verifiable Action RO will manually start CAPT #1.

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario #1 Catawba 2017 NRC Exam Page 4 of 139 Event 8 NI pumps will fail to autostart upon initiation of S/I for establishing NC system feed and bleed. Verifiable Action BOP initiates S/I, will manually start 1A NI pump, and then open 2 Pressurizer PORVs. Critical Task 1 Manually isolate failed open Pressurizer PORV (1NC-32B) prior to any RPS actuation. Critical Task 2 Manually trip the reactor from the control room prior to S/G dryout conditions (<12% W/R level) occurs on any S/G. Critical Task 3 Initiate Reactor Coolant System Bleed and Feed before Pressurizer PORVs 1NC-34A and 1NC-36B open automatically (NC system pressure of 2335 PSIG) due to heat up of the NC system. Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes 1. Total malfunctions (58) 6 2. Malfunctions after EOP entry (12) 2 3. Abnormal events (24) 4 4. Major transients (12) 1 5. EOPs entered/requiring substantive actions (12) 1 6. EOP contingencies requiring substantive actions (02) 1 7. Critical tasks (23) 3 Catawba Nuclear Station NRC Exam June 2017 Scenario #1 Catawba 2017 NRC Exam Page 5 of 139 EXERCISE GUIDE WORKSHEET 1. INITIAL CONDITIONS: 1.1 Reset to IC # 170 and load schedule file for NRC Scenario 1 START TIME:__________ Trigger Instructor Action Final Delay Ramp Delete In Event 2 VLV-CM004F (CM140 COND CF PMP 1B SUCTION ISOL FAIL TO POSITION) 0 :20 2 2 BST-JFB5940B (2/3 LO SUCT FLOW CFPT B TRIP) AS_IS 2 2 BST-JFB5943B (2/3 LO SUCT FLOW CFPT B TRIP) AS_IS 2 2 BST-JPB5972 (2/3 LO SUCT PRESS CFPT B TRIP) - PS AS_IS 2 2 BST-JPB5973 (2/3 LO SUCT PRESS CFPT B TRIP) - PS AS_IS 2 3 ANN-AD19-F04 (YN CRITICAL TROUBLE) ON 3 10 VLV-NC005F (NC32B PZR PORV FAIL TO POSITION) 1 3 4 OVR-NV020D (NV PMP 1A OFF PB) ON 4 5 LOA-CM040 (RACKOUT CBP 1B) RACK-OUT 5 5 LOA-CM041 (RACKOUT CBP 1C) RACK-OUT 5 LOA-CM039 (RACKOUT CBP 1A) RACK-OUT 5 MAL-IPX001A (AUTO REACTOR TRIP FAILURE TRN A) ACTIVE 5 MAL-IPX001B (AUTO REACTOR TRIP FAILURE TRN B) ACTIVE 5 MAL-CA005 (CA PUMP OVERSPEED TRIP) MECH-ANICAL 6 7 MAL-EP008B (LOSS OF 4160V BUS ETB) ACTIVE :10 7 MAL-NI001A (NI PUMP A FAILURE) AUTO 8 LOA-CA017 (RACKOUT CA PUMP 1A) RACK-OUT Catawba Nuclear Station NRC Exam June 2017 Scenario #1 Catawba 2017 NRC Exam Page 6 of 139 11 OVR-NV020D (NV PMP 1A OFF PB) OFF :01 13 LOA-CNT002 (H2 ANALYZERS) BOTH 10:00 15 VLV-NC004C (NC31B PZR PORV ISOL VLV FAIL PWR) ACTIVE 10:00 17 LOA-NV078 (SEAL WATER LOW FLOW LCL REFLASH ACK (AD7,C4)) ACKN 5:00 Ensure EVENT 7 = jpplp4(1) jpplp4(2) (Reactor Trip Either Train) Ensure EVENT 10 = x5ri017a (1AD-19 Acknowledge) Ensure EVENT 11 = x11i197i Ensure control rods are placed in MANUAL Ensure Red Collar is placed on 1A Condensate Booster Pump Ensure Red Collar is placed on 1A CA Pump Ensure all Pressurizer heaters are on for mixing Catawba Nuclear Station NRC Exam June 2017 Scenario #1 Catawba 2017 NRC Exam Page 7 of 139 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 the Control Board alignments. 3.2 Scenario EVENT 1, Power decrease to 50% BOOTH INSTRUCTOR ACTION IF contacted as SOC by the crew to inform of commencing power decrease, REPEAT the information. 3.3 Scenario EVENT 2, 1B CFPT suction valve 1CM-140 fails closed with failure of 1B CFPT to trip automatically BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause 1B CFPT suction valve 1CM-140 to fail closed. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1CM-140, REPEAT the information. BOOTH INSTRUCTOR ACTION IF an AO is contacted to complete shutdown of the CHDPs, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as the SOC reporting on runback of Unit 1, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection to sample and analyze gaseous effluents referring to SLC 16.11-6, REPEAT the information.

Catawba Nuclear Station NRC Exam June 2017 Scenario #1 Catawba 2017 NRC Exam Page 8 of 139 BOOTH INSTRUCTOR ACTION IF contacted as Primary Chemistry to sample for isotopic analysis of iodine between 2-6 hours0.25 days 0.0357 weeks 0.00822 months following a power change of > 15% in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period referring to Tech Spec 3.4.16, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF contacted as Reactor Engineering to report on Unit 1 runback, REPEAT the information. 3.4 Scenario EVENT 3, NC PORV 1NC-32B Fails Open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause an HVAC Panel Trouble Alarm. Once this alarm is acknowledged on 1AD-19, NC PORV 1NC-32B will fail open. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1NC-32B, REPEAT the information. BOOTH INSTRUCTOR ACTION IF an AO or the Unit Supervisor is contacted to create a clearance to remove power from 1NC-31B, REPEAT the information and INSERT Trigger 15. After 10 minutes, contact the control room and REPORT 1NC- 3.5 Scenario EVENT 4, 1A NV Pump Trip BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause 1A NV Pump Trip. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1A NV Pump, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as an AO to perform a post start check of 1B NV pump, REPEAT the information. After 5 minutes, contact the crew and REPORT BOOTH INSTRUCTOR ACTION When AP-room and REPORT Catawba Nuclear Station NRC Exam June 2017 Scenario #1 Catawba 2017 NRC Exam Page 9 of 139 BOOTH INSTRUCTOR ACTION IF contacted as an AO to acknowledge seal water low flow alarm on reflash panel 1, REPEAT the information and INSERT Trigger 17. After 5 minutes, contact the crew and REPORT 3.6 Scenario EVENT 5, Trip of Running Condensate Booster Pumps BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause a trip of the running condensate booster pumps. 3.7 Scenario EVENTS 6, 7, 8, Loss of Heat Sink, 1ETB Blackout, and NI Pumps Fail to Autostart On Initiation of Bleed and Feed BOOTH INSTRUCTOR ACTION IF the SWM is contacted to expedite the return of 1A CA pump, REPEAT the information. BOOTH INSTRUCTOR ACTION IF an AO is contacted to locally reset the Trip and Throttle valve, REPEAT the information. After 10 minutes, REPORT BOOTH INSTRUCTOR ACTION IF AO is dispatched to place the containment H2 Analyzers in service per OP/1/A/6450/010, REPEAT the information and INSERT Trigger 13. After 10 minutes contact the crew and REPORT been secured per G-1 Enclosure 11, and the H2 Analyzers have been placed in service BOOTH INSTRUCTOR ACTION IF an AO is contacted to restore power to 1NC-31B (1EMXD-F02C), REPEAT the information.

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 1 Event # 1 Page 10 of 139 Event

Description:

Power Reduction To 50% Scenario #1 Catawba 2017 NRC Exam Page 10 of 139 Note To Evaluator: The scenario begins with a power decrease to 50% by the crew. This will involve several procedures to accomplish. The following procedures are included in this guide: OP/1/A/6150/009 Enclosure 4.2 (Boration) OP/1/A/6150/008 Enclosure 4.16 (Control Bank Manual Operation At Power) OP/0/B/6300/001 Enclosure 4.2 (Load Changing) These procedures may be performed in any order by the crew. Instructions for continuing to the next Event are included at the end of OP/0/B/6300/001 Enclosure 4.2.

Description:

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 68 of 139 Note To Evaluator: Once the reactor is tripped, a blackout of 1ETB will occur. CAPT#1 will fail to start automatically, requiring the crew to manually start it to feed the S/Gs. Once started, it will experience a mechanical overspeed trip. Once S/G levels all decrease to below 11% N/R, a transition to FR-H.1 will occur. Crew will immediately transition to steps to initiate NC system Feed and Bleed due to no NV pumps being available. Once S/I is initiated, the 1A NI pump will fail to start requiring the crew to reset S/I and the D/G load sequencer and manually starting the 1A NI pump. The 1A NV pump will also start when S/I is initiated.

CAPT #1 Overspeed / 1ETB Blackout / NI Pumps Fail To Autostart on Initiation of F&B Scenario #1 Catawba 2017 NRC Exam Page 106 of 139 Scenario #1 Catawba 2017 NRC Exam Page 107 of 139 Attachment List Scenario 1 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/1/A/5500/003 Enclosure 3 (Rod Insertion Limit Boration) ATTACHMENT 4 - AP/1/A/5500/012 Enclosure 3 (Control Room Ventilation System Verification) ATTACHMENT 5 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page) ATTACHMENT 6 - EP/1/A/5000/ES-0.1 Enclosure 1 (Foldout Page) ATTACHMENT 7 - EP/1/A/5000/ES-0.1 Enclosure 2 (NC Temperature Control) ATTACHMENT 8 - EP/1/A/5000/G-1 Enclosure 16 (Control Room Ventilation Verification) ATTACHMENT 9 - EP/1/A/5000/FR-H.1 Enclosure 1 (Foldout Page) ATTACHMENT 10 - EP/1/A/5000/FR-H.1 Enclosure 4 (System Verification Following S/I Actuation) ATTACHMENT 11 - EP/1/A/5000/FR-H.1 Enclosure 9 (System Verification Following S/I Actuation)

Scenario #1 Catawba 2017 NRC Exam Page 108 of 139 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Manually isolate failed open Pressurizer PORV (1NC-32B) prior to any RPS actuation. 2 Manually trip the reactor from the control room prior to S/G dryout conditions (W/R S/G level < 12%) occurs on any S/G. 3 Initiate Reactor Coolant System Bleed and Feed before Pressurizer PORVs open automatically (NC system pressure of 2235 PSIG) due to heat up of the NC system. Comments:

Scenario #1 Catawba 2017 NRC Exam Page 109 of 139 ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 75 % EOL 177 PPM per OAC Controlling Procedure OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.2 (Power Decrease). The steps up to step 3.15 are complete. Other Information Needed to Assume the Shift Unit 1 is at 75% power at the EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours0.125 days 0.0179 weeks 0.00411 months and is expected to be returned to service in 6 hours0.25 days 0.0357 weeks 0.00822 months . 1A Condensate Booster Pump is tagged out for emergent motor replacement. Direction for the crew is to decrease reactor power to 50% to secure a main feedwater pump in preparation for entering a Unit 1 Refueling Outage. A reactivity plan has been provided by Reactor Engineering for a 10% per hour decrease in reactor power. AOs Available Seven AOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 315 degrees, speed = 3 mph Lower wind direction = 315 degrees, speed = 4.5 mph Forecast calls for clear skies over the next 24 hours1 days 0.143 weeks 0.0329 months .

Scenario #1 Catawba 2017 NRC Exam Page 110 of 139 ATTACHMENT 3 Scenario #1 Catawba 2017 NRC Exam Page 111 of 139 ATTACHMENT 4 Scenario #1 Catawba 2017 NRC Exam Page 112 of 139 ATTACHMENT 4 Scenario #1 Catawba 2017 NRC Exam Page 113 of 139 ATTACHMENT 4 Scenario #1 Catawba 2017 NRC Exam Page 114 of 139 ATTACHMENT 5 Scenario #1 Catawba 2017 NRC Exam Page 115 of 139 ATTACHMENT 5 Scenario #1 Catawba 2017 NRC Exam Page 116 of 139 ATTACHMENT 6 Scenario #1 Catawba 2017 NRC Exam Page 117 of 139 ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 118 of 139 ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 119 of 139 ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 120 of 139 ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 121 of 139 ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 122 of 139 ATTACHMENT 7 Scenario #1 Catawba 2017 NRC Exam Page 123 of 139 ATTACHMENT 8 Scenario #1 Catawba 2017 NRC Exam Page 124 of 139 ATTACHMENT 8 Scenario #1 Catawba 2017 NRC Exam Page 125 of 139 ATTACHMENT 8 Scenario #1 Catawba 2017 NRC Exam Page 126 of 139 ATTACHMENT 9 Scenario #1 Catawba 2017 NRC Exam Page 127 of 139 ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 128 of 139 ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 129 of 139 ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 130 of 139 ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 131 of 139 ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 132 of 139 ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 133 of 139 ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 134 of 139 ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 135 of 139 ATTACHMENT 10 Scenario #1 Catawba 2017 NRC Exam Page 136 of 139 ATTACHMENT 11 Scenario #1 Catawba 2017 NRC Exam Page 137 of 139 ATTACHMENT 11 Scenario #1 Catawba 2017 NRC Exam Page 138 of 139 ATTACHMENT 11 Scenario #1 Catawba 2017 NRC Exam Page 139 of 139 ATTACHMENT 11 Catawba Nuclear Station NRC Exam June 2017 Scenario #2 Catawba 2017 NRC Exam Page 1 of 136 2017 INITIAL LICENSE NRC EXAM SCENARIO # 2 Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario #2 Catawba 2017 NRC Exam Page 2 of 136 Facility: Catawba NRC Exam 2017 Scenario No.:

2 Op Test No.:

2017301 Examiners:

Operators:

SRO RO BOP Initial Conditions:

Unit 1 is at 100% power at the MOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 100% power at the MOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours0.125 days 0.0179 weeks 0.00411 months and is expected to be returned to service in 6 hours0.25 days 0.0357 weeks 0.00822 months . Direction for the crew is to initiate a VQ release fro-progress OP/1/A/6450/017 (Containment Air Release and Addition System) Enclosure 4.2 (Air Release Mode). Event No. Malf. No. Event Type* Event Description 1 N BOP N SRO VQ Release 2 SLIM05_02 C BOP C SRO Letdown Heat Exchanger Temperature Control Valve (1KC-132) Failure 3 SM002B C RO C SRO S/G PORV (1SV-13) Fails Open 4 EP006C IRX009 R RO N - BOP TS SRO 1B G PCB Trip / No Auto Rods 5 NC013D ISE008A ISE008B C BOP C SRO TS -SRO NC System Leak (S H Failure - Secure VQ) 6 NC013D M ALL LBLOCA 7 ISE002A ISE002B C BOP SI Fails to Automatically Actuate 8 CF006A C RO 1CF-33 (S/G 1A CF Cont Isol) Fails to Close on Feedwater Isolation 9 ND001A ND001B C - BOP ND Pumps Fail to Auto Start

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario #2 Catawba 2017 NRC Exam Page 3 of 136 Scenario 2 Summary Initial Condition Unit 1 is at 100% power at the MOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 100% power at the MOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours0.125 days 0.0179 weeks 0.00411 months and is expected to be returned to service in 6 hours0.25 days 0.0357 weeks 0.00822 months . Direction for the crew is to initiate a VQ release fro-progress OP/1/A/6450/017 (Containment Air Release and Addition System) Enclosure 4.2 (Air Release Mode). Event 1 Initiate VQ Release. Event 2 Letdown Heat Exchanger Temperature Control Valve (1KC-132) setpoint increases causing 1KC-132 to close and causing a letdown heat exchanger outlet high temperature alarm. Verifiable Action BOP will take 1KC-132 to manual and throttle it open to decrease letdown temperature.

If letdown temperature exceeds 1 36F, then letdown heat exchanger outlet three way valve (1NV-153A) will fail to go to the VCT position (will continue flow to NV demineralizers) and the BOP will be required to manually align to the VCT. Event 3 1B S/G PORV (1SV-13) will fail open. Crew may enter AP/1/A/5500/0 28 (Secondary Steam Leak) for guidance to isolate the leak. Alternatively, the crew may use OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines) guidance to address failure. Verifiable Action The RO will close 1SV-28A (S/G 1B PORV Isol) to isolate the leak.

RO may decrease turbine generator load to maintain reactor power < 100%. Event 4 1B Main Generator Breaker (GEN BKR 1B) will spuriously open resulting in a turbine runback. Control Rods will fail to automatically insert. Crew will enter AP/1/A/5500/003 (Load Rejection), Case I (Switchyard Available). Verifiable Action OATC will manually insert Control Rods as required. BOP will borate to restore Control Rod Insertion limits. SRO will address Tech Specs. Event 5 A Primary Coolant system leak will develop inside containment. Crew will enter AP/1/A/5500/0 10 (Reactor Coolant Leak), Case II (NC System Leak). Containment Ventilation Isolation Signal (S H) will fail to actuate on high containment radiation level (EMF-38, 39). Verifiable Action BOP will adjust charging to maintain Pressurizer level. BOP will secure Containment Air Release (VQ). SRO will address Tech Specs. Event 6 A Large Break LOCA will occur. Crew will enter EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) and transition to EP/1/A/5000/E-1 (Loss of Reactor or Secondary Coolant). Verifiable Action RO will manually trip the reactor. BOP will manually initiate Safety Injection.

Event 7 Safety Injection will fail to automatically actuate on High Containment Pressure or Low Pressurizer Pressure.

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario #2 Catawba 2017 NRC Exam Page 4 of 136 Verifiable Action BOP will manually actuate both trains of Safety Injection Event 8 1CF-33 (S/G 1A CF Cont Isol) fails to automatically close on Feedwater Isolation Signal. Verifiable Action RO will manually close valve. Event 9 Both ND Pumps will fail to automatically start on Safety Injection initiation. Verifiable Action SRO will direct reset of D/G sequencer and ECCS. BOP will manually start 1A and 1B ND Pumps. Critical Task 1 Manually actuate at least one train of SIS-actuated safeguards before transition to E-1 occurs (E-0 Step 27 RNO d). Critical Task 2 Manually start at least one low-head ECCS pump before transition out of E-0 (E-0 Step 27 RNO d). Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes 1.Total malfunctions (58)7 2.Malfunctions after EOP entry (12)3 3.Abnormal events (24)4 4.Major transients (12)1 5.EOPs entered/requiring substantive actions (12)1 6.EOP contingencies requiring substantive actions (02)0 7.Critical tasks (23)2 Catawba Nuclear Station NRC Exam June 2017 Scenario #2 Catawba 2017 NRC Exam Page 5 of 136 EXERCISE GUIDE WORKSHEET 1. INITIAL CONDITIONS: 1.1 Reset to IC # 158 and load Schedule file for Scenario 2. START TIME:__________ Trigger Instructor Action Final Delay Ramp Delete In Event 2 MAL-SLIM05_02 (1NVSS5590 KC-132 Raise Setpoint Pushbutton fail to position) Button Depress-ed :10 2 VLV-NV035A (NV153A L/D HX DIVERSION FAIL AUTO ACTIONS) ACTIVE 2 3 MAL-SM002B (S/G PORV SV13 FAILURE) 100 3 4 OVR-EP006B (GEN BKR 1B TRIP ENABLE PB) ON 4 4 OVR-EP006C (GEN BKR 1B TRIP PB) ON 4 MAL-IRX009 (RODS FAIL TO MOVE) AUTO 4 5 MAL-NC013D (NC COLD LEG D LEAK) 0.2 5 MAL-ISE008A (AUTO CNT VENT SIGNAL TRN A) BLOCK 5 MAL-ISE008B (AUTO CNT VENT SIGNAL TRN B) BLOCK 5 6 MAL-NC013D (NC COLD LEG D LEAK) 27.5 6 MAL-ISE002A (AUTO SI TRN A FAILS TO ACTUATE) ACTIVE 7 MAL-ISE002B (AUTO SI TRN B FAILS TO ACTUATE) ACTIVE 7 VLV-CF006A (CF33 CF CONT ISOL VLV 1CF033 FAIL AUTO ACTIONS) ACTIVE 8 MAL-ND001A (ND PUMP A FAILURE) AUTO 9 MAL-ND001B (ND PUMP B FAILURE) AUTO 9 LOA-CA017 (RACKOUT CA PUMP 1A) RACK-OUT 10 LOA-CNT002 H2 ANALYZERS BOTH 10:00 Catawba Nuclear Station NRC Exam June 2017 Scenario #2 Catawba 2017 NRC Exam Page 6 of 136 Ensure Red Collar is placed on 1A CA Pump 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 the Control Board alignments. 3.2 Scenario EVENT 1, Initiate VQ Release 3.3 Scenario EVENT 2, Letdown Heat Exchanger temperature control valve (1KC-132) failure BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause 1KC-132 to slowly close. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1KC-132 or 1NV-153A, REPEAT the information. 3.4 Scenario EVENT 3, 1B S/G PORV (1SV-13) Fails Open BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause 1B S/G PORV (1SV-13) to fail open. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1SV-13, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection notifying of steam leak from 1SV-13 failing open, REPEAT the information. 3.5 Scenario EVENT 4, Generator Breaker 1B Trip Catawba Nuclear Station NRC Exam June 2017 Scenario #2 Catawba 2017 NRC Exam Page 7 of 136 BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause Generator Breaker 1B to trip open. BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for Generator Breaker 1B or control rods failing to insert, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as an AO to complete shutdown of the CHDPs, REPEAT the information.. BOOTH INSTRUCTOR ACTION IF contacted as the SOC reporting on runback of Unit 1, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection to sample and analyze gaseous effluents referring to SLC 16.11-6, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as Primary Chemistry to sample for isotopic analysis of iodine between 2-6 hours0.25 days 0.0357 weeks 0.00822 months following a power change of > 15% in a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period referring to Tech Spec 3.4.16, REPEAT back the information. BOOTH INSTRUCTOR ACTION IF contacted as Reactor Engineering reporting on runback of Unit 1, REPEAT the information. 3.6 Scenario EVENT 5, NC System Leak BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 5 to cause an NC System Leak on loop 1D. BOOTH INSTRUCTOR ACTION IF contacted as Reactor Engineering reporting on need for shutdown of Unit 1, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as Station Management for further actions, REPORT 3.7 Scenario EVENT 6, Large Break LOCA Catawba Nuclear Station NRC Exam June 2017 Scenario #2 Catawba 2017 NRC Exam Page 8 of 136 BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 6 to cause a Large Break LOCA on loop 1D. BOOTH INSTRUCTOR ACTION IF contacted as an AO to secure all ice condenser AHUs per G-1 Enclosure 11 and to place the H2 Analyzers in service per OP/1/A/6450/010, REPEAT the information and INSERT Trigger 10. After 10 minutes, contact the control room and REPORT been secured per G-1 Enclosure 11 and the H2 Analyzers have been placed in service per BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection to frisk all Unit 1 S/G cation columns for activity, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as Secondary Chemistry to sample all Unit 1 S/Gs for activity, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as an AO to secure both D/Gs and place them in standby readiness per the OP, REPEAT the information.

Description:

Initiate a VQ Release Scenario #2 Catawba 2017 NRC Exam Page 16 of 136 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 2 Event # 1 Page 17 of 136 Event

1B S/G PORV (1SV

-13) Fails Open Scenario #2 Catawba 2017 NRC Exam Page 30 of 136

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

301 Scenario #

2 Event # 4 Page 31 of 136 Event

Description:

Generator Breaker 1B Trip / Control Rods Fail To Auto Insert Scenario #2 Catawba 2017 NRC Exam Page 31 of 136 Control Room Indications 1AD-- LIT 1AD-- LIT 1AD-- LIT Turbine Generator MW output RAPIDLY DECREASING Reactor Power

- DECREASING

LBLOCA / Failure of S/I to Actuate / 1CF-33 Fails to Close / Both ND Pumps Fail to Start Scenario #2 Catawba 2017 NRC Exam Page 93 of 136 Scenario #2 Catawba 2017 NRC Exam Page 94 of 136 Attachment List Scenario 2 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/1/A/5500/015 Case I (Failure Of Rods To Move) ATTACHMENT 4 - AP/1/A/5500/028 Enclosure 1 (Foldout Page) ATTACHMENT 5 - AP/1/A/5500/003 Enclosure 3 (Rod Insertion Limit Boration) ATTACHMENT 6 - AP/1/A/5500/010 Enclosure 2 (Case II NC System Leak Foldout Page) ATTACHMENT 7 - AP/1/A/5500/010 Enclosure 11 (Control Room Ventilation System Verification) ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page) ATTACHMENT 9 - EP/1/A/5000/E-0 Enclosure 5 (VX System Operation) ATTACHMENT 10 - EP/1/A/5000/E-0 Enclosure 2 (Control Room Ventilation Verification) ATTACHMENT 11 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control) ATTACHMENT 12 - EP/1/A/5000/G-1 Enclosure 1 (Spent Fuel Pool Monitoring) ATTACHMENT 13 - EP/1/A/5000/E-1 Enclosure 1 (Foldout Page)

Scenario #2 Catawba 2017 NRC Exam Page 95 of 136 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Manually actuate at least one train of SIS-actuated safeguards before transition to E-1 occurs (E-0 Step 27 RNO d). 2 Manually start at least one low-head ECCS pump before transition out of E-0 (E-0 Step 27 RNO d). Comments:

Scenario #2 Catawba 2017 NRC Exam Page 96 of 136 ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 100 % MOL 860 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). The steps for 100% power are complete. Other Information Needed to Assume the Shift Unit 1 is at 100% power at the MOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours0.125 days 0.0179 weeks 0.00411 months and is expected to be returned to service in 6 hours0.25 days 0.0357 weeks 0.00822 months . Direction for the crew is to initiate a VQ release completing the in-progress OP/1/A/6450/017 (Containment Air Release and Addition System) Enclosure 4.2 (Air Release Mode). AOs Available Seven AOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 315 degrees, speed = 3 mph Lower wind direction = 315 degrees, speed = 4.5 mph Forecast calls for clear skies over the next 24 hours1 days 0.143 weeks 0.0329 months .

Scenario #2 Catawba 2017 NRC Exam Page 97 of 136 ATTACHMENT 3 Scenario #2 Catawba 2017 NRC Exam Page 98 of 136 ATTACHMENT 3 Scenario #2 Catawba 2017 NRC Exam Page 99 of 136 ATTACHMENT 3 Scenario #2 Catawba 2017 NRC Exam Page 100 of 136 ATTACHMENT 3 Scenario #2 Catawba 2017 NRC Exam Page 101 of 136 ATTACHMENT 3 Scenario #2 Catawba 2017 NRC Exam Page 102 of 136 ATTACHMENT 3 Scenario #2 Catawba 2017 NRC Exam Page 103 of 136 ATTACHMENT 3 Scenario #2 Catawba 2017 NRC Exam Page 104 of 136 ATTACHMENT 4 Scenario #2 Catawba 2017 NRC Exam Page 105 of 136 ATTACHMENT 4 Scenario #2 Catawba 2017 NRC Exam Page 106 of 136 ATTACHMENT 5 Scenario #2 Catawba 2017 NRC Exam Page 107 of 136 ATTACHMENT 6 Scenario #2 Catawba 2017 NRC Exam Page 108 of 136 ATTACHMENT 7 Scenario #2 Catawba 2017 NRC Exam Page 109 of 136 ATTACHMENT 7 Scenario #2 Catawba 2017 NRC Exam Page 110 of 136 ATTACHMENT 7 Scenario #2 Catawba 2017 NRC Exam Page 111 of 136 ATTACHMENT 8 Scenario #2 Catawba 2017 NRC Exam Page 112 of 136 ATTACHMENT 8 Scenario #2 Catawba 2017 NRC Exam Page 113 of 136 ATTACHMENT 9 Scenario #2 Catawba 2017 NRC Exam Page 114 of 136 ATTACHMENT 10 Scenario #2 Catawba 2017 NRC Exam Page 115 of 136 ATTACHMENT 10 Scenario #2 Catawba 2017 NRC Exam Page 116 of 136 ATTACHMENT 10 Scenario #2 Catawba 2017 NRC Exam Page 117 of 136 ATTACHMENT 10 Scenario #2 Catawba 2017 NRC Exam Page 118 of 136 ATTACHMENT 10 Scenario #2 Catawba 2017 NRC Exam Page 119 of 136 ATTACHMENT 10 Scenario #2 Catawba 2017 NRC Exam Page 120 of 136 ATTACHMENT 10 Scenario #2 Catawba 2017 NRC Exam Page 121 of 136 ATTACHMENT 11 Scenario #2 Catawba 2017 NRC Exam Page 122 of 136 ATTACHMENT 11 Scenario #2 Catawba 2017 NRC Exam Page 123 of 136 ATTACHMENT 11 Scenario #2 Catawba 2017 NRC Exam Page 124 of 136 ATTACHMENT 11 Scenario #2 Catawba 2017 NRC Exam Page 125 of 136 ATTACHMENT 11 Scenario #2 Catawba 2017 NRC Exam Page 126 of 136 ATTACHMENT 12 Scenario #2 Catawba 2017 NRC Exam Page 127 of 136 ATTACHMENT 12 Scenario #2 Catawba 2017 NRC Exam Page 128 of 136 ATTACHMENT 12 Scenario #2 Catawba 2017 NRC Exam Page 129 of 136 ATTACHMENT 12 Scenario #2 Catawba 2017 NRC Exam Page 130 of 136 ATTACHMENT 12 Scenario #2 Catawba 2017 NRC Exam Page 131 of 136 ATTACHMENT 12 Scenario #2 Catawba 2017 NRC Exam Page 132 of 136 ATTACHMENT 12 Scenario #2 Catawba 2017 NRC Exam Page 133 of 136 ATTACHMENT 12 Scenario #2 Catawba 2017 NRC Exam Page 134 of 136 ATTACHMENT 13 Scenario #2 Catawba 2017 NRC Exam Page 135 of 136 ATTACHMENT 13 Scenario #2 Catawba 2017 NRC Exam Page 136 of 136 ATTACHMENT 13 Catawba Nuclear Station NRC Exam June 2017

Scenario #3 Catawba 2017 NRC Exam Page 1 of 171

2017 INITIAL LICENSE NRC SCENARIO # 3

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1

Scenario #3 Catawba 2017 NRC Exam Page 2 of 171 Facility: Catawba NRC Exam 2017 Scenario No.: 3 Op Test No.: 2017301 Examiners:

Operators: SRO RO BOP Initial Conditions: Unit 1 is at 50% power at the EOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 50% power at the EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours0.125 days 0.0179 weeks 0.00411 months and is expected to be returned to service in 6 hours0.25 days 0.0357 weeks 0.00822 months . Direction for the crew is to maintain present plant conditions. Event No. Malf. No. Event Type* Event Description 1 IDE003I C - RO C - SRO Condenser Dump Valve (1SB-27) Failure 2 EGB004C C - RO C - SRO Voltage Regulator Failure 3 KC027 C - BOP TS - SRO 1A2 KC Pump Trip 4 SG001B C - BOP TS - SRO 1B S/G Tube Leak / Automatic Blowdown Isolation Failure 5 SG001B N - BOP N - SRO R - RO AP/09 Rapid Downpower 6 SG001B M - ALL 1B S/G Tube Rupture 7 ISE007A ISE007B C - RO CF Isolation Failure 8 ISE038 C - BOP B Train Phase A Isolation Failure

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1

Scenario #3 Catawba 2017 NRC Exam Page 3 of 171 Scenario 3

- Summary Initial Condition Unit 1 is at 50% power at the EOL. Unit 2 is at 100% power.

Turnover: Unit 1 is at 50% power at the EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours0.125 days 0.0179 weeks 0.00411 months and is expected to be returned to service in 6 hours0.25 days 0.0357 weeks 0.00822 months .

Direction for the crew is to maintain present plant conditions.

Event 1 1SB-27 (SM Byp to Cond Ctrl #27) will fail open. Crew may enter AP/1/A/5500/028 (Secondary Steam Leak) for guidance to isolate the leak. Alternatively, the crew may use OMP 1-7 (Emergency/Abnormal Procedure Implementation Guidelines) guidance to address failure.

Verifiable Action

- The RO will place Steam Dump Control switches to "Off

-Reset".

Event 2 A failure on the Unit 1 Voltage Regulator will cause Generator Voltage to increase until the limiter becomes active and stops the increase. Crew may enter AP/1/A/5500/037 (Generator Voltage and Electric Grid Disturbances) Case I (Abnormal Generator or Grid Voltage).

Verifiable Action

- The RO will manually decrease voltage back to the requirements of the voltage schedule .

Event 3 1A2 KC pump will trip. Crew will enter AP/1/A/5500/021 (Loss of Component Cooling Water) and start an available KC pump.

Verifiable Action

- BOP will start an available KC pump.

Event 4 1B S/G Tube leak will develop. 1B S/G Blowdown will fail to isolate on 1EMF-33 (Condenser Air Ejector) Trip 2 actuation. Crew will enter AP/1/A/5500/010 (Reactor Coolant Leak), Case I (NC System Leak).

Verifiable Action

- BOP will manually isolate 1B S/G Blowdown, re-align condenser air ejector offgas to filtered ventilation, and adjust charging to maintain Pressurizer level. SRO will address Tech Specs.

Event 5 Crew will begin a rapid downpower per AP/1/A/5500/009 (Rapid Downpower) due to the SGTL.

Verifiable Action

- RO will input a Target and Load Rate into the turbine control panel and place the Main Turbine in 'GO'. BOP will perform a boration for a normal evolution.

Event 6 1B S/G Tube Leak will transition to a Rupture. Crew will enter EP/1/A/5000/E-0 (Reactor Trip or Safety Injection) and transition to EP/1/A/5000/E-3 (Steam Generator Tube Rupture)

Verifiable Action

- Crew will cooldown, depressurize, and terminate Safety Injection.

Event 7 Both trains of Automatic Feedwater Isolation will fail to actuate on Safety Injection.

Verifiable Action

- RO will manually actuate A and B Train Main Feedwater Isolation.

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1

Scenario #3 Catawba 2017 NRC Exam Page 4 of 171 Event 8 Phase A Isolation (Train B) will fail to automatically initiate on Safety Injection signal. Verifiable Action

- BOP will manually initiate B train Phase A Isolation signal.

Critical Task 1

- Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs.

Critical Task 2

- Establish/maintain an RCS temperature so that transition from E-3 does not occur because the RCS temperature is in either of the following conditions

Too high to maintain the minimum required subcooling

Below the RCS temperature that causes and extreme (red path) or a severe (orange path) challenge to the subcriticality and/or integrity status tree.

Critical Task 3

- Depressurize RCS to meet SI termination criteria before water release occurs from the ruptured S/G PORV (1125 PSIG) or safety (prior to S/G NR level reaching 100% and an associated S/G PORV (1125 PSIG) or Safety Valve open).

Critical Task 4

- Start a KC pump prior to any NCP motor bearing temperature exceeding 195°F.

Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Total malfunctions (5

-8) 7 2. Malfunctions after EOP entry (1

-2) 2 3. Abnormal events (2

-4) 4 4. Major transients (1

-2) 1 5. EOPs entered/requiring substantive actions (1

-2) 1 6. EOP contingencies requiring substantive actions (0-2) 0 7. Critical tasks (2

-3) 3

Catawba Nuclear Station NRC Exam June 2017

Scenario #3 Catawba 2017 NRC Exam Page 5 of 171 EXERCISE GUIDE WORKSHEET

1. INITIAL CONDITIONS:

1.1 Reset to IC # 23 and load Schedule for Scenario 3.

START TIME:__________

ü ü Trigger Instructor Action Final Delay Ramp Delete In Event 1 MAL-IDE003I (STEAM DUMP VLV SB27 FAIL TO POSITION) 100 :05 1 10 MAL-IDE003I (STEAM DUMP VLV SB27 FAIL TO POSITION) 100 :01 1 12 LOA-IDE009 (SB26

- INLET ISOL) 0 5:00 :05 1 2 OVR-EGB004C (VOLTAGE ADJUST RAISE PB) ON :10 2 3 LOA-KC028 (RACKOUT KC PMP 1A2) RACK-OUT 3 4 MAL-SG001B (S/G B TUBE LEAK) 75 :30 4 VLV-BB002 (BB73-S/G B BLOWDOWN CTRL VLV FAIL AUTO ACTIONS) ACTIVE 4 6 MAL-SG001B (S/G B TUBE LEAK) 400 :30 6 MAL-ISE007A (AUTO CF ISOL SIGNAL TRN A) BLOCK 7 MAL-ISE007B (AUTO CF ISOL SIGNAL TRN B) BLOCK 7 MAL-ISE003B (AUTO PHASE A ISOL SIGNAL TRN B) BLOCK 8 LOA-CA017 (RACKOUT CA PUMP 1A) RACK-OUT 14 LOA-CA011 (SA3

- S/G 1B TO CAPT ISOL) 0 4:30 :30 Ensure EVENT 10 = x02i184l x02i186l (Steam Dump Select OFF Either Train)

Ensure Red Collar is placed on 1A CA Pump

Catawba Nuclear Station NRC Exam June 2017

Scenario #3 Catawba 2017 NRC Exam Page 6 of 171

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 the Control Board alignments. 3.2 Scenario EVENT 1, Condenser Dump Valve (1SB-27) Fails Open

ü BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 1 to cause Condenser Dump Valve (1SB-27) to fail open.

ü BOOTH INSTRUCTOR ACTION IF contacted as an AO or Unit Supervisor to create a clearance to isolate 1SB-27, REPEAT the information and INSERT Trigger 12. After 5 minutes, contact the control room and REPORT "1SB-26 is manually closed to isolate 1SB-27." ü BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate a W/R and NCR for 1SB-27, REPEAT the information.

ü BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection notifying of steam leak from 1SB-27 failing open, REPEAT the information.

3.3 Scenario EVENT 2, Generator Voltage Regulator Failure

ü BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 2 to cause a Generator Voltage Regulator Failure.

ü BOOTH INSTRUCTOR ACTION IF contacted as TCC to monitor Real Time Contingency Analysis and report the results to the Control Room Supervisor, REPEAT the information.

Catawba Nuclear Station NRC Exam June 2017

Scenario #3 Catawba 2017 NRC Exam Page 7 of 171

ü BOOTH INSTRUCTOR ACTION IF contacted as SOC asking for voltage requirement, REPORT "Adjust voltage per the voltage operating schedule."

3.4 Scenario EVENT 3, 1A2 KC Pump Trip

ü BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause 1A2 KC pump to trip.

ü BOOTH INSTRUCTOR ACTION IF contacted as AO to perform a post start checkout of the KC pump, after 3 minutes REPORT "KC pump____ looks good for continued operation".

ü BOOTH INSTRUCTOR ACTION IF the SWM is contacted to initiate an NCR or W/R for 1A2 KC pump, REPEAT the information.

ü BOOTH INSTRUCTOR ACTION IF contacted as Unit 2 control room to verify that one KC heat exchanger is aligned to provide miniflow for the RN system, REPORT "2B KC heat exchanger outlet mode switch is in MINIFLOW".

3.5 Scenario Event 4, 1B S/G Tube Leak / Automatic BB isolation failure

ü BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 4 to cause a 1B S/G Tube Leak.

ü BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection to frisk all Unit 1 S/G cation columns for activity, REPEAT the information.

ü BOOTH INSTRUCTOR ACTION IF contacted as Secondary Chemistry to sample all Unit 1 S/Gs for activity, REPEAT the information.

ü BOOTH INSTRUCTOR ACTION IF contacted as Secondary Chemistry to inform of CM polishing demineralizers being bypassed, REPEAT the information.

ü BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection to notify of current size of the leak and to perform HP/0/B/1009/003, REPEAT the information.

Catawba Nuclear Station NRC Exam June 2017

Scenario #3 Catawba 2017 NRC Exam Page 8 of 171

ü BOOTH INSTRUCTOR ACTION IF contacted as Engineering to notify of the S/G Tube Leak, REPEAT the information.

3.6 Scenario Event 5, Rapid Downpower

3.7 Scenario Events 6, 7, 8, 1B S/G Tube Rupture / CF Isolation Failure / 'B' Train Phase A Failure

ü BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 6 to cause a 1B S/G Tube Rupture.

ü BOOTH INSTRUCTOR ACTION If dispatched as an AO to unlock and close 1SA-1, REPEAT the information and INSERT Trigger 14. After 5 minutes, contact the control room and REPORT "1SA-1 is unlocked and closed."

Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 301 Scenario # 3 Event # 1 Page 9 of 171 Event

Description:

Condenser Dump Valve (1SB-27) Fails Open

Scenario #3 Catawba 2017 NRC Exam Page 9of 171

Control Room Indications OAC Alarm for 1SB OPEN Main Steam Header Pressure - DECREASING Turbine Generator Electrical Load - DECREASING Reactor Power - INCREASING RED OPEN light for 1SB LIT

Generator Voltage Regulator Failure

Description:

1B S/G Tube Leak / Failure of BB to Automatically Isolate

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1B S/G Tube Leak / Failure of BB to Automatically Isolate

Scenario #3 Catawba 2017 NRC Exam Page 55 of 171

1B S/G Tube Rupture / CF Isolation Failure / 'B' Train Phase A Failure

Scenario #3 Catawba 2017 NRC Exam Page 73 of 171

ATTACHMENT 4 - AP/1/A/5500/021 Enclosure 1 (Foldout Page)

ATTACHMENT 5 - AP/1/A/5500/037 Enclosure 1 (Unit 1 Generator Capability Curves)

ATTACHMENT 6 - AP/1/A/5500/010 Enclosure 1 (Case I S/G Tube Leak Foldout Page)

ATTACHMENT 7 - AP/1/A/5500/009 Enclosure 1 (Foldout Page)

ATTACHMENT 8 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page) ATTACHMENT 9 - EP/1/A/5000/E-0 Enclosure 2 (Control Room Ventilation Verification)

ATTACHMENT 10 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control) ATTACHMENT 11 - EP/1/A/5000/G-1 Enclosure 1 (Spent Fuel Pool Monitoring)

ATTACHMENT 12 - EP/1/A/5000/E-3 Enclosure 1 (Foldout Page)

ATTACHMENT 13 - OP/1/A/6150/009 Enclosure 4.2 (Boration)

Scenario #3 Catawba 2017 NRC Exam Page 132 of 171 ATTACHMENT 1

CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Isolate feedwater into and steam flow from the ruptured S/G before a transition to ECA-3.1 occurs.

2 Establish/maintain an RCS temperature so that the transition from E-3 does not occur because the RCS temperature is in either of the following conditions:

Too high to maintain the minimum required subcooling

Below the RCS temperature that causes an extreme (Red Path) or a severe (Orange Path) challenge to the Subcriticality and/or Integrity status tree.

3 Depressurize RCS to meet S/I termination criteria before water release occurs from the ruptured S/G PORV or safety (prior to S/G N/R level reaching 100% and an associated S/G PORV or Safety Valve open).

4 Start a KC pump prior to any NCP motor bearing temperature exceeding 195°F.

Comments:

Scenario #3 Catawba 2017 NRC Exam Page 133 of 171 ATTACHMENT 2

SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 50 % EOL 256 PPM per OAC Controlling Procedure

OP/1/A/6100/003 (Controlling Procedure for Unit Operation), Enclosure 4.1 (Power Increase). The steps up through 3.50 are complete.

Other Information Needed to Assume the Shift

Unit 1 is at 50% power at the EOL. Unit 2 is at 100% power. 1A CA Pump is removed from service for PMs. 1A CA Pump has been inoperable for 3 hours0.125 days 0.0179 weeks 0.00411 months and is expected to be returned to service in 6 hours0.25 days 0.0357 weeks 0.00822 months . Direction for the crew is to maintain present plant conditions. AOs Available Seven AOs are available as listed on the status board METEOROLOGICAL CONDITIONS

Upper wind direction = 315 degrees, speed = 3 mph

Lower wind direction = 315 degrees, speed = 4.5 mph

Forecast calls for clear skies over the next 24 hours1 days 0.143 weeks 0.0329 months .

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Scenario #3 Catawba 2017 NRC Exam Page 170 of 171 ATTACHMENT 13

Scenario #3 Catawba 2017 NRC Exam Page 171 of 171 ATTACHMENT 13

Catawba Nuclear Station NRC Exam June 2017 Scenario #4 Catawba 2017 NRC Exam Page 1 of 118 2017 INITIAL LICENSE NRC EXAM SCENARIO # 4 Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario #4 Catawba 2017 NRC Exam Page 2 of 118 Facility: Catawba NRC Exam 2017 Scenario No.: 4 Op Test No.: 2017301 Examiners: Operators: SRO RO BOP Initial Conditions: Unit 1 is at 7x10-2 % power at the BOL. Unit 2 is at 100% power. Turnover: Unit 1 is at 7x10-2 % power at the BOL. Unit 2 is at 100% power. 1A Condensate Booster Pump is tagged out for emergent motor replacement. Direction for the crew is to swap operating RN pumps by starting the 1B RN pump and securing the 1A RN pump per OP/0/A/6400/006 C (Nuclear Service Water System) Enclosure 4.7 (Starting/Securing Additional RN Pumps). Initial conditions have been verified. Chemistry has been notified of the RN pump lineup being changed and has informed operations that RN Chemical Addition system has been aligned to support the RN pump swap. The Unit 1 Cation Bed Demineralizer is not in service. Unit 2 Mixed bed demineralizers have been bypassed per step 3.2.2. Crew is to begin at step 3.2.1 of Enclosure 4.7. Following the RN pump swap, the crew is to withdraw control rods to increase reactor power to ~14 % in preparation for placing the Main Turbine online. Event No. Malf. No. Event Type* Event Description 1 N BOP N SRO Swap RN pumps 2 R RO Increase reactor power 3 ENB008B C RO C SRO TS - SRO N36 Loss of Fission Chamber (Affects N32) 4A RL015 C BOP C SRO 4B SG004 TS-SRO 1A S/G N/R Level Channel 2 Fails High 5 WL017D C BOP C SRO 1A NCDT Pump trip 6 NCP003C C RO C - SRO 1C NC Pump High/High Vibration 7 EP003E EQB005A EQB006A M ALL Loss of All AC Power 8 EQB005A EQB006A C RO D/G Load Sequencers Fail To Actuate 9 RN003A RN003B RN003C RN003D C BOP C - SRO RN Pump fails to start on power restoration * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario #4 Catawba 2017 NRC Exam Page 3 of 118 Scenario 4 Summary Initial Condition Unit 1 is at 7x10-2 % power at the BOL. Unit 2 is at 100% power. Turnover: Unit 1 is at 7x10-2 % power at the BOL. Unit 2 is at 100% power. 1A Condensate Booster Pump is tagged out for emergent motor replacement. Direction for the crew is to swap operating RN pumps by starting the 1B RN pump and securing the 1A RN pump per OP/0/A/6400/006 C (Nuclear Service Water System) Enclosure 4.7 (Starting/Securing Additional RN Pumps). Initial conditions have been verified. Chemistry has been notified of the RN pump lineup being changed and has informed operations that RN Chemical Addition system has been aligned to support the RN pump swap. The Unit 1 Cation Bed Demineralizer is not in service. Unit 2 Mixed bed demineralizers have been bypassed per step 3.2.2. Crew is to begin at step 3.2.1 of Enclosure 4.7. Following the RN pump swap, the crew is to withdraw control rods to increase reactor power to ~14 % in preparation for placing the Main Turbine online. Event 1 BOP will perform OP/0/A/6400/006 C Enclosure 4.7 to swap operating RN pumps. Event 2 The RO will withdraw control rods to establish a positive startup rate to increase reactor power. Event 3 A loss of fission chamber will occur affecting both Intermediate Range channel N36 and Source Range channel N32. Crew will enter AP/1/A/5500/016 (Malfunction of Nuclear Instrumentation). SRO will address Tech Specs. Verifiable Action The RO will insert control rods to stabilize reactor power. The BOP will remove N32 and N36 from service. Event 4A Pressure Service Water (RL) pump will trip. Crew will enter AP/0/A/5500/038 (Loss of Conventional Low Pressure Service Water). Verifiable Action BOP will start . Event 4B Level Channel 2 will fail High. SRO will address Tech Specs. Event 5 1A NCDT pump will trip. Crew will use the Annunciator Response for 1AD-13 B/2 annunciator (NCDT Recirc Lo Flow) to start 1B NCDT pump. Verifiable Action BOP starts 1B NCDT pump. Event 6 1C NC pump will have a high vibration develop. The crew will use the Annunciator Response for 1AD-6 B/5 annunciator (NCP Hi-Hi Vibration) to determine that a reactor trip is required, and once reactor power is < 5%, that 1C NC pump should be secured. Verifiable Action RO will trip Unit 1 reactor.

Catawba Nuclear Station NRC Exam June 2017 Appendix D Scenario Outline Form ES-D-1 Scenario #4 Catawba 2017 NRC Exam Page 4 of 118 Event 7 Once the reactor is tripped, a Loss of All AC power will occur on Unit 1. Verifiable Action RO will manually control S/G levels and the BOP will initiate S/I on both trains to start the D/Gs. Event 8 Both trains D/G Load sequencers will fail to actuate. This will cause CAPT #1 to not receive a signal to start. Verifiable Action RO will manually start CAPT #1 to maintain S/G levels. Event 9 Once S/I is initiated on both trains, the RN pumps will fail to start automatically. Verifiable Action BOP will reset ECCS and D/G load sequencers on both trains and start RN pumps as required. Critical Task 1 Initiate Safety Injection (S/I) on both trains to start the Unit 1 Diesel Generators by the completion of EP/1/A/5000/ECA-0.0 Step 8. Critical Task 2 Manually start Nuclear Service Water (RN) pumps such that the EDG does not fail because of damage caused by engine overheating. (Reference Simulator Work Request # DSG-044 for the simulator programming for this critical task) Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes 1. Total malfunctions (58) 6 2. Malfunctions after EOP entry (12) 2 3. Abnormal events (24) 4 4. Major transients (12) 1 5. EOPs entered/requiring substantive actions (12) 1 6. EOP contingencies requiring substantive actions (02) 1 7. Critical tasks (23) 2 Catawba Nuclear Station NRC Exam June 2017 Scenario #4 Catawba 2017 NRC Exam Page 5 of 118 EXERCISE GUIDE WORKSHEET 1. INITIAL CONDITIONS: 1.1 Reset to IC # 159 and load schedule file for Scenario 4. START TIME:__________ Trigger Instructor Action Final Delay Ramp Delete In Event 3 MAL-ENB008B (I/R N36 LOSS OF FISSION CHAMBER (AFFECTS N32)) ACTIVE 3 4 LOA-RL015 (RACKOUT RL PUMP C) RACK-OUT 4 4 XMT-SG004 (LCF_5510 S/G 1A N/R LVL CH2 TO DCS/MCB/OAC (CFAA5510)) 100 5:00 4 5 OVR-WL017D (NCDT PMP 1A OFF PB) ON 5 5 OVR-WL017A (NCDT PMP 1A OFF LT) OFF 5 6 MAL-NCP003C (NCP C VIBRATION) 25 :15 6 7 MAL-EP003E (ZONE 1A and 1B LOCKOUT) ACTIVE 7 7 MAL-EQB006A (TRN B BLACKOUT SEQUENCER BLOCK) ACTIVE 7 7 MAL-EQB005A (TRN A BLACKOUT SEQUENCER BLOCK) ACTIVE 7 7 OVR-DG014D (D/G 1A PB (11/212) OFF PB) ON 7 7 OVR-DG016D (D/G 1B PB (11/407) OFF PB) ON 7 7 MAL-RN003A (RN PMP 1A FAILURE TO STRT) AUTO 9 7 MAL-RN003B (RN PMP 1B FAILURE TO STRT) AUTO 9 7 MAL-RN003C (RN PMP 2A FAILURE TO STRT) AUTO 9 7 MAL-RN003D (RN PMP 2B FAILURE TO STRT) AUTO 9 11 OVR-DG014D (D/G 1A PB (11/212) OFF PB) OFF Catawba Nuclear Station NRC Exam June 2017 Scenario #4 Catawba 2017 NRC Exam Page 6 of 118 12 OVR-DG016D (D/G 1B PB (11/407) OFF PB) OFF ANN-AD11-B03 (TRANSFORMER A TROUBLE) ON ANN-AD11-E03 (TRANSFORMER B TROUBLE) ON LOA-CM039 (RACKOUT CBP 1A) RACK-OUT 14 LOA-VI011 (EMERGENCY DIESEL VI & ISOL VLV) ON 10:00 Ensure EVENT 7 = jpplp4(1) jpplp4(2) (Reactor Trip Either Train) Ensure EVENT 11 = jpplsia Ensure EVENT 12 = jpplsib Ensure Red Collar is placed on 1A Condensate Booster Pump Catawba Nuclear Station NRC Exam June 2017 Scenario #4 Catawba 2017 NRC Exam Page 7 of 118 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 the Control Board alignments. 3.2 Scenario EVENT 1, Swap Operating RN pumps BOOTH INSTRUCTOR ACTION IF contacted as Primary Chemistry notifying of intention to bypass Unit 1 demineralizers while changing RN Pump configuration, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection notifying of intention to bypass Unit 1 demineralizers while changing RN Pump configuration, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as the AO at the RN pump house for post start check of 1B RN pump, REPORT BOOTH INSTRUCTOR ACTION IF contacted as Primary Chemistry notifying that Unit 1 demineralizers have been restored to service, REPEAT the information. BOOTH INSTRUCTOR ACTION IF contacted as Radiation Protection notifying that Unit 1 demineralizers have been restored to service, REPEAT the information. 3.3 Scenario EVENT 2, Withdrawing Control Rods To Increase Reactor Power 3.4 Scenario EVENT 3, N36 Loss of Fission Chamber (Affects N32) BOOTH INSTRUCTOR ACTION WHEN directed by the lead examiner, THEN INSERT SIMULATOR Trigger 3 to cause a loss of fission chamber to N36 and N32.

Description:

Loss of All AC / CAPT #1 Fails to Start on B/O / RN Pumps Fail to Start on S/I Scenario #4 Catawba 2017 NRC Exam Page 89 of 118 Scenario #4 Catawba 2017 NRC Exam Page 90 of 118 Attachment List Scenario 4 ATTACHMENT 1 - Crew Critical Task Summary ATTACHMENT 2 - Shift Turnover Information ATTACHMENT 3 - AP/0/A/5500/038 Enclosure 1 (Foldout Page) ATTACHMENT 4 - EP/1/A/5000/E-0 Enclosure 1 (Foldout Page) ATTACHMENT 5 - EP/1/A/5000/E-0 Enclosure 2 (Control Room Ventilation Verification) ATTACHMENT 6 - EP/1/A/5000/G-1 Enclosure 1 (Spent Fuel Pool Monitoring) ATTACHMENT 7 - EP/1/A/5000/E-0 Enclosure 4 (NC Temperature Control) ATTACHMENT 8 - EP/1/A/5000/ECA-0.0 Enclosure 1 (Foldout Page) ATTACHMENT 9 - EP/1/A/5000/ES-1.1 Enclosure 1 (Foldout Page)

Scenario #4 Catawba 2017 NRC Exam Page 91 of 118 ATTACHMENT 1 CREW CRITICAL TASK

SUMMARY

SAT UNSAT CT # CRITICAL TASK 1 Initiate Safety Injection (S/I) on both trains to start the Unit 1 Diesel Generators by the completion of EP/1/A/5000/ECA-0.0 Step 8. 2 Manually start Nuclear Service Water (RN) pumps such that the EDG does not fail because of damage caused by engine overheating. Comments:

Scenario #4 Catawba 2017 NRC Exam Page 92 of 118 ATTACHMENT 2 SHIFT TURNOVER INFORMATION Unit 1 Status Power Level Power History NCS Boron Xenon 7x10-2 % BOL 1969 PPM per OAC Controlling Procedure OP/1/A/6100/001 (Controlling Procedure for Unit Startup), Enclosure 4.1 (Unit Startup). The steps up to 3.180 are complete. Other Information Needed to Assume the Shift Unit 1 is at 7x10-2 % power at the BOL. Unit 2 is at 100% power. 1A Condensate Booster Pump is tagged out for emergent motor replacement. Direction for the crew is to swap operating RN pumps by starting the 1B RN pump and securing the 1A RN pump per OP/0/A/6400/006 C (Nuclear Service Water System) Enclosure 4.7 (Starting/Securing Additional RN Pumps). Initial conditions have been verified. Chemistry has been notified of the RN pump lineup being changed and has informed operations that RN Chemical Addition system has been aligned to support the RN pump swap. The Unit 1 Cation Bed Demineralizer is not in service. Unit 2 Mixed bed demineralizers have been bypassed per step 3.2.2. Crew is to begin at step 3.2.1 of Enclosure 4.7. Following the RN pump swap, the crew is to withdraw control rods to increase reactor power to ~14 % in preparation for placing the Main Turbine online. AOs Available Seven AOs are available as listed on the status board METEOROLOGICAL CONDITIONS Upper wind direction = 315 degrees, speed = 3 mph Lower wind direction = 315 degrees, speed = 4.5 mph Forecast calls for clear skies over the next 24 hours1 days 0.143 weeks 0.0329 months .

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JPM A

Catawba Nuclear Station JPM A 2017 NRC Exam PAGE 2 OF 9 EVALUATION SHEET Task: Emergency Borate the Reactor Coolant System Alternate Path:

Yes Facility JPM #:

NV-017 Safety Function: 1 Title: Reactivity Control K/A 00 4 A 2.14 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Emergency Boration Rating(s):

3.8 / 3.9 CFR: 41.5 / 43/5 / 45/3 / 45/5 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

EP/1/A/5000/FR

-S.1 (Nuclear Power Generation/ATW) rev. 02 2 Task Standard:

One NV pump running with its suction aligned to the FWST and isolated from the VCT. Validation Time:

5 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM A 2017 NRC Exam PAGE 3 OF 9 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

1 50 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given

. Instructor Action Final Delay Ramp Delete In Event MAL-IPX0 0 3A (REACTOR TRIP BKR A FAILURE) ACTIVE MAL-IPX0 0 3B (REACTOR TRIP BKR B FAILURE) ACTIVE VLV-NV043F (NV236B BORIC ACID TO CHG PMP VLV FAIL TO POSITION) 0 MAL-MT007 (LOSS OF TURBINE LUBE OIL PRESSURE) ACTIVE Instructor will act as the OATC and be manually inserting control rods when the simulator is placed in RUN.

Catawba Nuclear Station JPM A 201 7 NRC Exam PAGE 4 OF 9 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A valid reactor trip signal has been received

. The reactor will NOT trip automatically or manually

. A Red Path for Subcriticality is in effect

. The OATC is inserting rods manually

. INITIATING CUES:

The Control Room Supervisor instructs you to initiate emergency boration, per EP/1/A/5000/FR

-S.1, (Nuclear Power Generation/ATWS

), step 4. EXAMINER NOTE

After reading cue, provide the applicant with a copy of EP/1/A/5000/FR

-S.1.

Catawba Nuclear Station JPM A 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 9 START TIME: _______

STEP 1: 4. Initiate emergency boration of NC System as follows:

a. Ensure at least one NV pump

- ON. STANDARD: Applicant verifies red "ON" light lit for "NV PMP 1A" or "1B" (1MC-10). COMMENTS:

___ SAT

___ UNSAT STEP 2 4. b. OPEN 1NV

-236B (Boric Acid To NV Pumps Suct).

STANDARD: Applicant depresses the red "OPEN" pushbutton for 1NV

-236B and verifies the red "OPEN" light remains dark and the green "CLSD" light remains lit on 1M C-10. 1NV-236B remains closed.

Examiner Note: This begins the alternate path of this JPM.

COMMENTS: ___ SAT

___UNSAT STEP 3 4. c. Ensure both boric acid transfer pump switches - IN THE "ON" POSITION.

STANDARD: Applicant rotates the switches for "B/A XFER PMP 1A" and "B/A XFER PMP 1B" to the "ON" position.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM A 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 9 STEP 4 4. d. Verify emergency boration flow

- GREATER THAN OR EQUAL TO 30 GPM.

STANDARD: Applicant verifies "EMER BORATE FLOW" (1NVP5440) indicates 0 gpm (1MC-5) and transitions to the RNO.

COMMENTS: ___ SAT

___ UNSAT STEP 5 4. d. RNO d. Align NV pump suction to FWST as follows: 1) OPEN the following valves:

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

STANDARD: Applicant depresses the red "OPEN" pushbuttons for 1NV

-252A and 1NV-253B and verifies the red "OPEN" light is lit and green "CLSD" light is dark for both valves.

Examiner Note: This step is critical to align borated water to the suction of the charging pumps. Only ONE of the valves opened meets the Critical Step criteria.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM A 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 9 STEP 6 4. d. RNO d. 2) CLOSE the following valves:

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

STANDARD: Applicant depresses the green "CLOSE" pushbutton for 1NV

-188A and 1NV-189B and verifies the green "CLSD" light lit and red "OPEN" light dark for both valves.

Examiner Note: This step is critical to prevent borated water from going to the VCT instead of the suction of the charging pumps as long as one of the valves is closed. Closing only ONE of the valves meets the intent of the Critical Step criteria.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 7 4. e. Verify the following charging line isolation valves

- OPEN: 1NV-312A (Chrg Line Cont Isol) follows:

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

STANDARD: Applicant verifies the red "OPEN" lights lit and green "CLSD" lights dark on 1NV-312A and 1NV

-314B. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM A 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 9 STEP 8 4. f. Verify Pzr pressure

- LESS THAN 2335 PSIG.

STANDARD: Applicant verifies PZR pressure instruments (1NCP5161, 1NCP5150, 1NCP5170 and 1NCP5171) indicate less than 2335 psig (1MC

-10). COMMENTS: END OF TASK

___ SAT

___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A valid reactor trip signal has been received

. The reactor will NOT trip automatically or manually

. A Red Path for Subcriticality is in effect

. The OATC is inserting rods manually

. INITIATING CUES:

The Control Room Supervisor instructs you to initiate emergency boration, per EP/1/A/5000/FR

-S.1, (Nuclear Power Generation/ATWS

), step 4.

Catawba Nuclear Station JPM B 2017 NRC Exam PAGE 1 OF 8

JPM B

Catawba Nuclear Station JPM B 2017 NRC Exam PAGE 2 OF 8 EVALUATION SHEET Task: Perform E-0 Actions To Ensure A Complete Containment Isolation Alternate Path:

Yes Facility JPM #:

N/A Safety Function:

2 Title: Engineering Safety Features Actuation System K/A 0 13 A4.01 Ability to manually operate and/or monitor in the control room: ESFAS

-initiated equipment which fails to actuate.

Rating(s):

4.5 / 4.8 CFR: 41.7 / 45.5 to 45.8 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

EP/1/A/5000/

E-0 (Reactor Trip or Safety Injection) Rev 42 Task Standard:

At least one train of Phase A containment isolation initiated and either 1WL

-825A or 1WL

-827B manually closed.

Validation Time:

5 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM B 2017 NRC Exam PAGE 3 OF 8 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

151 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN

. Instructor Action Final Delay Ramp Delete In Event MAL-NC013D (NC COLD LEG D LEAK) 27.5 :10 1 MAL-ISE003A (AUTO PHASE A ISOL SIGNAL TRN A)

BLOCK MAL-ISE003B (AUTO PHASE B ISOL SIGNAL TRN B)

BLOCK VLV-WL009A (WL825A CONT SUMP PMP DISCH ISOL IN FAIL AUTO ACTIONS)

ACTIVE VLV-WL010A (WL827B CONT SUMP PMP DISCH ISOL OUT FAIL AUTO ACTIONS)

ACTIVE When applicant is ready, INSERT EVENT 1.

Catawba Nuclear Station JPM B 201 7 NRC Exam PAGE 4 OF 8 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned

task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

You are the OATC The BOP has stepped out of the control room The CRS is performing an IPTE brief on Unit 2 INITIATING CUES:

Monitor your control boards EXAMINER NOTE

After reading cue, and applicant has walked down the control boards, have the simulator operator INSERT EVENT 1. This will cause a safety injection on Unit 1. All E

-0 immediate action steps will be met without any operator action. Once the applicant has announced that the Immediate Actions are complete, hand them a copy of E

-0 beginning at step 6.

EXAMINER CUE: "The CRS has validated that the immediate actions are complete and directs you to continue performance of E-0 , beginning at Step 6."

Catawba Nuclear Station JPM B 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 8 START TIME: _______

STEP 1: 6. Announce "Unit 1 Safety Injection".

STANDARD: Applicant uses the plant paging system to make the announcement.

COMMENTS:

___ SAT

___ UNSAT STEP 2 7. Determine required notifications:

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

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

STANDARD: Applicant acknowledges the step and continues with E-0. COMMENTS:

___ SAT

___UNSAT STEP 3 8. Verify all Feedwater Isolation status lights (1SI

-5) - LIT. STANDARD: Applicant verifies all Feedwater Isolation status lights lit on 1SI

-5. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM B 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 8 STEP 4 9. Verify Phase A Containment Isolation status as follows:

a. Phase A "RESET" lights

- DARK. STANDARD: Applicant determines that the Phase A RESET lights are lit and transitions to the RNO.

COMMENTS: ___ SAT

___ UNSAT STEP 5 9.a.RNO. Initiate Phase A Isolation.

STANDARD: Applicant depresses both of the red INITIATE pushbuttons for Train A and Train B and verifies the yellow RESET lights extinguish.

Examiner Note: It is critical for the applicant to at least initiate one train of Phase A to ensure that at least one valve in every penetration other than from the containment sump is isolated. The containment sump penetration will have to be manually isolated in the RNO for the following step.

Examiner Note: This begins the alternate path for this JPM. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM B 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 8 STEP 6 9.b. Monitor Light Panel Group 5 St lights on energized train(s)

- LIT. STANDARD: Applicant determines that Group 5 St lights C/3 and C/10 are dark and transitions to the RNO.

Examiner Note: It may take up to 60 seconds for all other valves to indicate isolated.

COMMENTS:

___ SAT ___ UNSAT STEP 7 9.b.RNO. Align valves as necessary to ensure each penetration isolated by at least one isolation valve.

STANDARD: Applicant depresses the green CLOSE pushbuttons for 1WL

-825A and 1WL-827B and verifies the green CLSD light lit and red OPEN light dark for each valve.

Examiner Note: It is critical for the applicant to close 1 of these valves to ensure the containment sump penetration is isolated.

Examiner Cue: Once valves have been closed, "This JPM is complete."

COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

You are the OATC The BOP has stepped out of the control room The CRS is performing an IPTE brief on Unit 2 INITIATING CUES:

Monitor your control boards

Catawba Nuclear Station JPM C 201 7 NRC Exam PAGE 1 OF 14

JPM C

Catawba Nuclear Station JPM C 201 7 NRC Exam PAGE 2 OF 14 EVALUATION SHEET Task: Establish NC system Bleed and Feed per EP/1/A/5000/FR

-H.1 Alternate Path:

Yes Facility JPM #:

NC-046 Safety Function:

4P Title: Reactor Coolant System K/A WE05EA1.1 Ability to operate and/or monitor the following as they apply to the (Loss of Secondary Heat Sink): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Rating(s):

4.1 / 4.0 CFR: 41.7 / 4 5.5 / 45.6 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

EP/1/A/5000/FR

-H.1 (Response to Loss of Secondary Heat Sink) rev. 4 2 Task Standard:

Aligns S/I feed path using NI and NV pumps and opens 1NC

-32B and 1NC

-34A PZR PORVs to establish NC system bleed path Validation Time:

10 minutes Time Critical: Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM C 201 7 NRC Exam PAGE 3 OF 14 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

1 52. 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given

. Instructor Action Final Delay Ramp Delete In Event MAL-CA003A CAPT SA2 FAILS TO START Active MAL-CA003B CAPT SA5 FAILS TO START Active MAL-CA004A FAILURE OF CA PUMP A TO START Both MAL-CA004B FAILURE OF CA PUMP B TO START Both MAL-NI001B NI PUMP B FAILURE Auto OVR-ISE043 SAFETY INJECTION INITIATE PB TRN B Off MAL-ISE002B (AUTO SI TRN B FAILS TO ACTUATE) Active VLV-NI001F (NI9A B.I.T. DISCHARGE ISOL VLV FAIL TO POSITION) 0 REV. 0 PAGE 4 0F 14 Catawba Nuclear Station JPM C 201 7 NRC Exam PAGE 4 OF 14 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A reactor trip has occurred on Unit 1 due to a loss of both Main Feedwater pumps. The CA system will not function.

Attempts to restart the Main CF pumps have been unsuccessful.

EP/1/A/5000/FR

-H.1 (Response to Loss of Secondary Heat Sink) has been entered due to a "RED PATH" for the Heat Sink critical safety function while performing EP/1/A/5000/ES

-0.1 (Reactor Trip Response).

Bleed and Feed initiation criteria ha ve been met. INITIATING CUES:

The CRS instructs you to initiate NC system bleed and feed beginning at step 19 of EP/1/A/5000/FR

-H.1. Inform the CRS when the bleed and feed path has been initiated and verified.

EXAMINER NOTE

After reading cue, provide the applicant with a copy of EP/1/A/5000/FR

-H.1.

Catawba Nuclear Station JPM C 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 14 START TIME: _______

STEP 1: 19. Perform Steps 20 through 24 quickly to establish NC heat removal by NC bleed and feed.

STANDARD: Applicant acknowledges this step.

COMMENTS:

___ SAT

___ UNSAT STEP 2 20. Ensure all NC pumps

- OFF. STANDARD: Applicant ensures the NC pumps are off.

COMMENTS:

___ SAT ___UNSAT Catawba Nuclear Station JPM C 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 14 STEP 3 21. Initiate S/I.

STANDARD: Applicant depresses the red train 'A' and 'B' "SAFETY INJECTION INITIATE" pushbuttons and verifies the red "SAFETY INJECTION ACTUATED" status light is lit on 1SI

-13 or "ECCS TRN A

" yellow reset light is dark on 1MC

-11. Examiner Note: This step is critical to start the NI pump and align the valves required for initiating an NC system feed path.

Examiner Note: This begins the alternate path for this JPM.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 4 22. Verify NC System feed path as follows:

a. Verify the following pumps

- ON: At least one NV pump At least one NI pump.

STANDARD: Applicant determines that at least one NV pump and one NI pump are running. Examiner Note:

Applicant may start 1B NI pump and 1B NV pump at this time due to it being a failed auto action. If not, the procedure will direct starting these pumps in the upcoming steps.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM C 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 14 STEP 5 22 b. Verify "NV S/I FLOW" - INDICATING FLOW.

STANDARD: Applicant determines that 1NVP6080 (NV S/I FLOW) on 1MC

-3 indicates 0 GPM and transitions to the RNO.

COMMENTS:

___ SAT

___ UNSAT STEP 6 22 b. RNO Perform the following:

1) Ensure the following pumps

- ON: NV Pumps NI Pumps. STANDARD: Applicant ensures that all NV pumps and NI pumps are running by depressing the red ON pushbuttons for any non

-running pump, and verifying the red ON lights are lit and green OFF lights are dark for all pumps. COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station JPM C 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 14 STEP 7 22 b. RNO 2) IF at least one NV pump in service, THEN perform the following:

a) Ensure the following valves

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

STANDARD: Applicant verifies the red OPEN lights lit and green CLSD lights dark on 1NV-252A and 1NV-253B. COMMENTS: ___ SAT

___ UNSAT STEP 8 22 b. RNO 2) b) Ensure the following valves

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

. STANDARD: Applicant determines that the green CLSD light is lit and red OPEN light is dark on 1NV

-188A. Applicant determines that the green CLSD light is dark for 1NV-189B, and depresses the green CLOSE pushbutton and verifies the green CLSD light is lit and the red OPEN light is dark COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station JPM C 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 14 STEP 9 22 b. RNO 2) c) Ensure the following valves

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

STANDARD: Applicant determines the red OPEN light is dark and green CLSD light is lit on 1NI-9A and 1NI-10B. Applicant depresses the red OPEN pushbutton for 1NI

-9A but the valve will not open. Applicant depresses the red OPEN pushbutton for 1NI

-10B and verifies the red OPEN light is lit and the green CLSD light is dark

. Examiner Note: This step is critical to align an NC (Reactor Coolant) system Feed path. COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT STEP 10 22 b. RNO 3) IF NI Pump 1A is in service, THEN ensure the following valves

- OPEN: 1NI-103A (NI Pump 1A Suct) 1NI-118A (NI Pump 1A C-Leg Inj Isol) 1NI-162A (NI To C

-Legs Inj Hdr Isol) 1NI-100B (NI Pmps Suct From FWST). STANDARD: Applicant determines that the red OPEN lights are lit and green CLSD lights are dark on valves 1NI

-103A, 1NI-118A, 1NI-162A, and 1NI

-100B. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM C 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 14 STEP 11 22 b. RNO 4) IF NI Pump 1B is in service, THEN ensure the following valves

- OPEN: 1NI-135B (NI Pump 1B Suct) 1NI-150B (NI Pump 1B C

-Leg Inj Isol) 1NI-162A (NI To C

-Legs Inj Hdr Isol) 1NI-100B (NI Pmps Suct From FWST). STANDARD: Applicant verifies that the red OPEN light is lit and green CLSD light is dark on valves 1NI

-135B, 1NI-150B, 1NI-162A, and 1NI

-100B. COMMENTS: ___ SAT

___ UNSAT STEP 12 22 b. RNO 5) IF no feed path can be aligned, THEN perform the following:

STANDARD: Applicant determines that a feed path does exist and this step is N/A.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM C 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 11 0F 14 STEP 13 23. Establish NC System bleed path as follows: a. Ensure all Pzr PORV isolation valves

- OPEN. STANDARD: Applicant determines the RED lights are lit and GREEN lights are dark on valves 1NC

-31B, 1NC-35B, and 1NC

-33A. COMMENTS: ___ SAT

___ UNSAT STEP 14 23 b. Select "OPEN" on the following PZR PORVs: 1NC-34A (PZR PORV) 1NC-32B (PZR PORV).

STANDARD: Applicant rotates switches for 1NC

-34A and 1NC

-32B, clockwise to the OPEN position and verifies RED lights are lit and GREEN lights are dark on both valves.

Examiner Note:

This step is critical because it establishes an NC (Reactor Coolant) system Bleed path.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM C 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 12 0F 14 STEP 15 23 c. Align N 2 to Pzr PORVs by opening the following valves:

1NI-438A (Emer N2 From CLA A To 1NC

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

-32B). STANDARD: Applicant depresses the red OPEN pushbutton and verifies red OPEN light lit and green CLSD light dark on valves 1NI

-438A and 1NI

-439B. COMMENTS: ___ SAT

___ UNSAT STEP 16 23 d. Verify power to all Pzr PORV isolation valves

- AVAILABLE.

STANDARD: Applicant verifies indicating lights lit on 1NC

-31B, 1NC-35B, and 1NC

-33A. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM C 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 13 0F 14 STEP 17 24. Verify the following valves

- OPEN: 1NC-31B (PZR PORV Isol) 1NC-32B (PZR PORV) 1NC-33A (PZR PORV Isol) 1NC-34A (PZR PORV).

STANDARD: Applicant verifies lights on 1NC

-31B, 1NC-3 2B, 1NC-33A and 1NC-34A indicate OPEN

. COMMENTS: END OF TASK

___ SAT

___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A reactor trip has occurred on Unit 1 due to a loss of both Main Feedwater pumps. The CA system will not function.

Attempts to restart the Main CF pumps have been unsuccessful.

EP/1/A/5000/FR

-H.1 (Response to Loss of Secondary Heat Sink) has been entered due to a "RED PATH" for the Heat Sink critical safety function while performing EP/1/A/5000/ES

-0.1 (Reactor Trip Response).

Bleed and Feed initiation criteria have been met.

INITIATING CUES:

The CRS instructs you to initiate NC system bleed and feed beginning at step 19 of EP/1/A/5000/FR

-H.1. Inform the CRS when the bleed and feed path has been initiated and verified.

Catawba Nuclear Station JPM D 2017 NRC Exam PAGE 1 OF 14

JPM D

Catawba Nuclear Station JPM D 2017 NRC Exam PAGE 2 OF 14 EVALUATION SHEET Task: Realign CA Suction Source Alternate Path:

Yes Facility JPM #:

CA-085 Safety Function:

4S Title: Auxiliary / Emergency Feedwater System K/A 0 54 A A 1.0 1 Ability to operate and/or monitor the following as they apply to the Loss of Main Feedwater (MFW): AFW controls, including the use of alternate AFW sources.

Rating(s):

4.5 / 4.4 CFR: 41.7 / 45.5 / 45.6 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

AP/1/A/5500/006 (Loss of S/G Feedwater) Rev 42 Task Standard:

CA suction supply aligned to the RN system while maintaining total CA flow <

600 gpm per AP/1/A/5500/006 Case II.

Validation Time:

10 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM D 2017 NRC Exam PAGE 3 OF 14 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

153. 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given

. Instructor Action Final Delay Ramp Delete In Event XMT-CM004 (LCS_5840 UST LVL RECORDER BLUE) 8.5 VLV-CM012F (CM370 COND C VACUUM BRKR FAIL TO POSTION) 0 VLV-CM011F (CM369 COND B VACUUM BRKR FAIL TO POSTION) 0 VLV-CM010F (CM368 COND A VACUUM BRKR FAIL TO POSTION) 0 OVR-FWP012C (CFPT 1A TRIP_RESET TRIP PB) ON OVR-FWP015C (CFPT 1B TRIP_RESET TRIP PB) ON VLV-CA002F (CA4 CA PMP SUCT FROM UST HDR ISOL FAIL TO POSITION) 1 Ensure CA System Valve Control is reset.

Catawba Nuclear Station JPM D 2017 NRC Exam PAGE 4 OF 14 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A reactor trip has occurred.

The crew has performed applicable actions of EP/1/A/5000/E

-0 (Reactor Trip or Safety Injection) and transitioned to EP/1/A/5000/ES

-0.1 (Reactor Trip Response).

While performing actions of ES

-0.1, 1AD-8, B/1 (UST LO LEVEL) alarmed.

Using guidance contained in Enclosure 1 (Foldout Page), the crew has implemented AP/1/A/5500/006 (Loss of S/G Feedwater), Case II (Loss of Normal CA Supply).

INITIATING CUES:

The Control Room Supervisor instructs you to perform the actions of AP/06 Case II, beginning at Step 7.

EXAMINER NOTE

After reading cue, provide the applicant with a copy of AP/1/A/5500/006 Case II with steps 1

-6 completed.

Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 14 START TIME: _______

STEP 1: 7. IF AT ANY TIME UST level is less than 10% (5,000 gal), THEN perform the following

a. Close 1CA-4 (CA Pmps Suct From UST)

. STANDARD: Applicant determines that UST level is <10% on chart recorder and depresses the green "CLOSE" pushbutton on 1CA

-4 and verifies the red "OPEN" light remains lit (1CA

-4 will not close).

COMMENTS:

___ SAT

___ UNSAT STEP 2 7. b. IF 1CA-4 will not close, THEN dispatch operator to unlock and close 1CS

-19 (CA Pumps Supply From Upper Surge Tank) (TB1

-627, 1D-30) (Key #633).

STANDARD: Applicant contacts an AO and dispatches them to unlock and close 1CS-19. Booth Operator Cue: "Operator has been dispatched to unlock and close 1CS-19." Examiner Note: It is only critical for the applicant to dispatch an operator to manually close 1CS

-19 by the end of the scenario to isolate the suction from the UST. This valve will not be closed during the performance of this JPM. COMMENTS:

CRITICAL STEP ___ SAT

___UNSAT Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 14 STEP 3 8. Maintain total CA flow less than 600 GPM in subsequent steps. STANDARD: Applicant uses CA flow control valves to throttle total CA flow to less than 600 GPM.

Examiner Note:

This step is critical to preserve the remaining inventory of available makeup water while aligning an alternate source.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 4 9. Monitor Enclosure 1 (Foldout Page)

. STANDARD: Applicant acknowledges step and continues

. Examiner Cue:

"Another operator will monitor Enclosure 1."

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 14 STEP 5 10. Break condenser vacuum as follows:

a. Open "COND A

-B-C VAC BKR VLVS" STANDARD: Applicant depresses the red "OPEN" pushbutton for "COND A

-B-C VAC BKR VLVS" and notes that the red "OPEN" light remains dark (vacuum breaker valves will not open). Applicant transitions to the RNO.

Examiner Note: This begins the alternate path for this JPM.

COMMENTS: ___ SAT

___ UNSAT STEP 6 10.a.RNO. Dispatch two (2) operators to break vacuum. REFER TO Enclosure 3 (Local Actions To Break Condenser Vacuum). STANDARD: Applicant dispatches two AOs to break condenser vacuum per Enclosure 3.

Booth Operator Cue: "Operators have been dispatched to break condenser vacuum per Enclosure 3."

COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 14 STEP 7 10.b.1) Verify condenser vacuum indication

- AVAILABLE.

STANDARD: Applicant verifies that condenser vacuum indication is available on both 1MC-1 and 1MC-13 control boards.

COMMENTS: ___ SAT

___ UNSAT NOTE It may take up to 10 minutes for condenser vacuum to reach 0 inches HgVac.

STEP 8 10.b.2) Verify one of the following:

"CONDENSER VACUUM" (1MC

-13) - 0"IN HGV" OR Dispatched operator reports no air flow into condenser.

STANDARD: Applicant verifies condenser vacuum is not broken and operators were unsuccessful in breaking vacuum. Applicant transitions to the RNO.

Booth Operator Cue: "Dispatched operators report that they are unable to manually open Condenser Vacuum Breaker valves."

COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 14 STEP 9 10.b.2)RNO. Shift CA pump suction to RN as follows:

a) IF Train A RN essential header is available, THEN open the following valves:

1RN-250A (RN Hdr A To CA Pmp Suct Isol) 1CA-116A (CA Pump #1 Suct Frm RN Isol) 1CA-15A (CA Pump 1A Suct Frm RN Isol).

STANDARD: Applicant determines Train A RN essential header is available and rotates the switches for 1RN-250A, 1CA-116A, and 1CA

-15A to the "OPEN" position and verifies the red "OPEN" indicating light is lit.

Examiner Note:

This step is critical to ensure a makeup source of water is available to supply S/Gs for reactor decay heat removal.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 14 STEP 10 10.b.2)RNO.b)

IF Train B RN essential header is available, THEN open the following valves:

1RN-310B (RN Hdr B To CA Pmp Suct Isol) 1CA-85B (CA Pump #1 Suct Frm RN Hdr B) 1CA-18B (CA Pump 1B Suct Frm RN Isol). STANDARD: Applicant determines Train B RN essential header is available and rotates the switches for 1RN

-310B, 1CA-85B, and 1CA

-18B to the "OPEN" position and verifies the red "OPEN" indicating light is lit.

Examiner Note

This step is critical to ensure a makeup source of water is available to supply S/Gs for reactor decay heat removal.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 1 1 10.b.2)RNO.c) Ensure 1CA

-6 (CA Pmps Suct From CACST)

- CLOSED. STANDARD: Applicant determines that 1CA-6 is closed (normal position of this valve is closed with power removed).

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 11 0F 14 STEP 12 10.b.2)RNO.d)

IF 1CA-6 will not close, THEN dispatch operator to unlock and close 1CS

-69 (U1 CACST To U1

& U2 CA Supplies) (SB

-625, T-25) (Key #633).

STANDARD: Applicant determines that this step does not apply.

COMMENTS: ___ SAT

___ UNSAT STEP 13 10.b.2)RNO.e) Ensure 1CA

-4 (CA Pmps Suct From UST)

- CLOSED. STANDARD: Applicant depresses the green "CLOSE" pushbutton and verifies that the red "OPEN" light remains illuminated (1CA

-4 will not close and an AO was previously dispatched to unlock and close 1CS

-19). COMMENTS:

___ SAT

___ UNSAT

Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 12 0F 14 STEP 14 10.b.2)RNO.f)

IF 1CA-4 will not close, THEN dispatch operator to unlock and close 1CS

-19 (CA Pumps Supply From Upper Surge Tank) (TB1

-627, 1D-30) (Key #633). STANDARD: Applicant determines that an operator has been previously dispatched to perform this action.

Examiner Note: It is only critical for the applicant to dispatch an operator to manually close 1CS

-19 by the end of the scenario to isolate the suction from the UST. This valve will not be closed during the performance of this JPM. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 15 10.b.2)RNO.g) Maintain S/G N/R levels between 11%

- 50%. STANDARD: Applicant acknowledges the step and attempts to adjust CA flow as required. Examiner Cue:

"Another operator will maintain S/G levels."

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM D 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 13 0F 14 STEP 16 10.b.2)RNO.h) GO TO Step 17. STANDARD: Applicant acknowledges the step Examiner Cue:

"This JPM is complete

." COMMENTS: END OF TASK

___ SAT

___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK) DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A reactor trip has occurred.

The crew has performed applicable actions of EP/1/A/5000/E

-0 (Reactor Trip or Safety Injection) and transitioned to EP/1/A/5000/ES

-0.1 (Reactor Trip Response). While performing actions of ES

-0.1, 1AD-8, B/1 (UST LO LEVEL) alarmed.

Using guidance contained in Enclosure 1 (Foldout Page), the crew has implemented AP/1/A/5500/006 (Loss of S/G Feedwater), Case II (Loss of Normal CA Supply).

INITIATING CUES:

The Control Room Supervisor instructs you to perform the actions of AP/06 Case II, beginning at Step 7.

Catawba Nuclear Station JPM E 201 7 NRC Exam PAGE 1 OF 9

JPM E

Catawba Nuclear Station JPM E 201 7 NRC Exam PAGE 2 OF 9 EVALUATION SHEET Task: Operate Containment Cooling System Fans Alternate Path:

No Facility JPM #:

VV-001 Safety Function: 5 Title: Containment Cooling System K/A 022 A4.01 Ability to manually operate and/or monitor in the control room: CCS fans.

Rating(s):

3.6 / 3.6 CFR: 41.7 / 4 5.5 to 45.8 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

AP/1/A/5500/028 (Secondary Steam Leak)

Task Standard:

Place all Containment Cooling Fans in operation in "Max" cooling mode in accordance with AP/1/A/5500/028 (Secondary Steam Leak) Step 9. Validation Time:

5 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM E 201 7 NRC Exam PAGE 3 OF 9 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

1 54. 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given

. Instructor Action Final Delay Ramp Delete In Event MAL-SM007B (STM LINE BRK INSIDE CONTAINMENT LOOP B) 20000 Ensure LCVU's 1A, 1B, and 1D are in service.

Ensure UCVU 1B is in service.

DO NOT PLACE SIMULATOR IN "RUN" UNTIL APPLICANT IS READY TO BEGIN.

Catawba Nuclear Station JPM E 201 7 NRC Exam PAGE 4 OF 9 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you

have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

AP/1/A/5 500/028 (Secondary Steam Leak) has been entered due to indications of a steam leak.

INITIATING CUES:

The CRS has directed you to perform AP/1/A/5500/028, step 9.

No personnel are in Containment.

EXAMINER NOTE

After reading the cue, provide the applicant with a copy of AP/1/A/5500/028, step 9

.

Catawba Nuclear Station JPM E 201 7 NRC Exam PAGE 5 0F 9 START TIME:

_______ STEP/STANDARD SAT/UNSAT STEP 1: 9. Attempt to identify and isolate the leak as follows:

a. Verify the following conditions NORMAL:

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

STANDARD: Applicant determines conditions are not normal and transitions to RNO.

COMMENTS:

___ SAT

___ UNSA T STEP 2: 9.aRNO a. Perform the following:

1) Evacuate containment.

STANDARD: Applicant initiates the Containment Evacuation Alarm and may request the WCC to review the Containment Entry Logbook

. Examiner Cue:

"If asked, WCC reports no personnel are listed in Containment Entry Logbook."

COMMENTS:

___ SAT ___UNSAT Catawba Nuclear Station JPM E 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 9 STEP 3: 9.aRNOa. 2) Perform the following:

a) Start all lower containment ventilation units in low speed. STANDARD: Applicant rotates switch VV LCVU 1C from "OFF" to "LOW" Examiner Note: This step is critical to ensure all Lower Containment Ventilation Units are providing cooling and available to be used in Max cooling mode in order to minimize Containment pressure.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT STEP 4: 9.aRNOa.2) b) Start all upper containment ventilation units.

STANDARD: Applicant rotates the following switches from "OFF" to "NORM":

VV UCVU 1A VV UCVU 1C VV UCVU 1D Examiner Note: This step is critical to ensure all Upper Containment Ventilation Units are providing cooling and available to be used in Max cooling mode in order to minimize Containment pressure.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM E 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 9 STEP 5: 9.aRNOa.2) c) Place all upper and lower containment ventilation units in "MAX" cooling.

STANDARD: Applicant verifies the following switches are in the "MAX" position.

VV LCVU 1A MAX VV LCVU 1B MAX VV LCVU 1C MAX VV LCVU 1D MAX Applicant rotates the following switches from "NORM" to "MAX":

VV UCVU 1A VV UCVU 1B VV UCVU 1C VV UCVU 1D Examiner Note: This step is critical to ensure all Containment Ventilation Units are providing maximum cooling in order to minimize Containment pressure.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 6: 9.aRNOa.3)

IF AT ANY TIME containment pressure reaches 1.2 PSIG, THEN perform the following:

STANDARD: Applicant acknowledges the continuous action statement and continues to step 4.

COMMENTS: ___ SAT ___ UNSAT Catawba Nuclear Station JPM E 201 7 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 9 STEP 7: 9.aRNOa.4)

GO TO Step 10. STANDARD: Examiner Cue: "Another operator will complete this procedure. JPM Complete" COMMENTS: END OF TASK

___ SAT

___ UNSAT EXAMINER NOTE

The applicant may choose to also place Lower Containment Ventilation Units in Hi Speed per the ARP associated with 1AD

-19 B/12 (LOWER CONT PRESS 0.5 PSIG INITIATE HI SPEED). This is not included in the standard of this JPM.

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

AP/1/A/5500/028 (Secondary Steam Leak) has been entered due to indications of a steam leak.

INITIATING CUES:

The CRS has directed you to perform AP/1/A/5500/028, step 9.

No personnel are in Containment.

Catawba Nuclear Station JPM F 2017 NRC Exam PAGE 1 OF 11

JPM F

Catawba Nuclear Station JPM F 2017 NRC Exam PAGE 2 OF 11 EVALUATION SHEET EVALUATION SHEET Task: Reset Radiation Monitor Trip Setpoints Alternate Path:

No Facility JPM #:

WE-EMF-001 Safety Function:

7 Title: Process Radiation Monitoring System K/A 073 A4.02 Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel Rating(s):

3.7 / 3.7 CFR: 41.7 / 45.5 to 45.8 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

OP/0/A/6500/080 (EMF RP86A Output Modules) rev. 17, Enclosure 4.2 (EMF RP86A Trip Setpoint Adjustment)

Task Standard:

EMF50L TRIP 1 setpoint set to 6.3 E3 CPM and the TRIP 2 setpoint set to 9.0 E3 CPM per OP/0/A/6500/080 (EMF RP86A Output Modules) Enclosure 4.2 (EMF RP86A Trip Setpoint Adjustment).

Validation Time:

10 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM F 201 7 NRC Exam PAGE 3 OF 11 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC #

1 55. 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Ensure copy of EMF

-50 setpoint log page has been replaced.

9. Place simulator in FREEZE until Examiner cue is given

. Instructor Action Final Delay Ramp Delete In Event

Catawba Nuclear Station JPM F 201 7 NRC Exam PAGE 4 OF 11 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is at 100% power.

INITIATING CUES:

Following a discussion with Glenn from RP concerning a premature gaseous release termination, the Control Room Supervisor directs you to set EMF 50L setpoints using OP/0/A/6500/080 (EMF RP86A Output Modules) Enclosure 4.2 (EMF RP86A and RM1000 Trip Setpoint Adjustment) to the following values:

Trip 1 = 6300 CPM Trip 2 = 9000 CPM OAC Program EMFLIB is currently not available.

EXAMINER NOTE: After reading the cue, provide the applicant with a copy of OP/0/A/6500/080 (EMF RP86A Output Modules) Enclosure 4.2 (EMF RP86A and RM1000 Trip Setpoint Adjustment).

Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 11 START TIME: _______

NOTE: 1. If desired, EMF setpoints adjustments may be performed from the "EMF SETPOINT" screen of OAC EMF Library (EMFLIB) Application. EMFLIB is user friendly, no procedure instructions are provided for this application.

2. The Trip Lamps can only be cleared if the activity level has decreased below the Trip Setpoint.

3. The setpoints given on release permits are already rounded to 3 significant digits and are entered into the EMF as is

. Setpoints for non

-release conditions are rounded up or down to 3 significant digits using standard mathematical rules for rounding. STEP 1 3.1 IF necessary, press the clear key [CLR] to reset trip lamps STANDARD: Applicant verifies trip lamps dark or depresses the [CLR] key to clear alarms. COMMENTS:

___ SAT

___ UNSAT STEP 2 3.2 Press the function key [FUN] to bring up the "SELECT FUNCTION" screen.

STANDARD: Applicant depresses the [FUN] key to bring up the "SELECT FUNCTION" screen.

This step is critical, due to being the only way to get to the select function screen, which is required to input new Trip 1 and Trip 2 values. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 11 STEP 3 3.3 Adjust Trip 1 Setpoint as follows:

3.3.1 Press [1] for Trip 1 setting display screen.

STANDARD: Applicant depresses the [1] to bring up the Trip 1 setting display screen.

This step is critical to bring up the screen that the new Trip 1 setting will be input into.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 4 3.3.2 Key in the desired Trip 1 setpoint.

STANDARD: Applicant keys in 6300 CPM using the numeric keypad.

This step is critical to input the new Trip 1 setpoint required to meet the task standard. This new setpoint is checked in the next step. The critical requirement is for the new trip setpoint of 6300 CPM to be entered by the end of this JPM.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 11 STEP 5 3.3.3 Ensure the following:

3.3.3.1 Setpoint is correctly displayed in the "ENTER" block on the setpoint display screen.

3.3.3.2 Setpoint is greater than the current EMF reading.

STANDARD: Applicant ensures 6300 CPM is displayed in the ENTER block and that the setpoint is greater than the current reading on the EMF.

COMMENTS: ___ SAT

___ UNSAT NOTE: Once the enter key [ENT] is pressed, the change in Trip 1 alarm setpoint is active.

STEP 6 3.3.4 Press the enter key [ENT]. This value is now displayed under "TRIP 1" and the "ENTER" block is cleared.

STANDARD: Applicant presses the [ENT] key and verifies the correct value under the "Trip 1" on the display.

This step is critical to input the new Trip 1 setpoint. Again the critical requirement is to have the Trip 1 setpoint set to 6300 CPM by the end of the JPM.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 11 STEP 7 3.3.5 Press the clear key [CLR] to return to the "SELECT FUNCTION" screen.

STANDARD: Applicant presses the [CLR] key to return to the "SELECT FUNCTION" screen. COMMENTS: ___ SAT

___ UNSAT STEP 8 3.4 Adjust Trip 2 Setpoint as follows:

3.4.1 Press [2] for Trip 2 setting display screen.

STANDARD: Applicant presses [2] to bring up the Trip 2 setting display screen

.

This step is critical to get to the required screen to input the new Trip

2 setpoint. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 9 3.4.2 Key in the desired Trip 2 setpoint.

STANDARD: Applicant enters 9000 CPM using the numeric keypad.

This step is critical to input the new Trip 2 setpoint required to meet the task standard. This new setpoint is checked in the next step. The critical requirement is for the new trip setpoint of 9000 CPM to be entered by the end of this JPM.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 11 STEP 10 3.4.3 Ensure the following:

3.4.3.1 Setpoint is correctly displayed in the "ENTER" block on the setpoint display screen.

3.4.3.2 Setpoint is greater than the current EMF reading.

STANDARD: Applicant ensures 9000 CPM is displayed in the ENTER block and that the entered setpoint is greater than the current reading on the EMF.

COMMENTS: ___ SAT

___ UNSAT NOTE: Once the enter key [ENT] is pressed, the change in Trip 2 alarm setpoint is active.

STEP 11 3.4.4 Press the enter key [ENT]. This value is now displayed under "TRIP 2" and the "ENTER" block is cleared.

STANDARD: Applicant presses the [ENT] key and verifies the correct value under the "Trip 2" on the display.

This step is critical to input the new Trip 2 setpoint. Again the critical requirement is to have the Trip 2 setpoint set to 9000 CPM by the end of the JPM.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM F 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 11 STEP 12 3.5 Press the clear key [CLR] twice to return to the normal display screen.

STANDARD: Applicant presses the [CLR] key twice to return to the normal display screen. EXAMINER CUE: "Another operator will complete the procedure. This JPM is complete."

COMMENTS: END OF TASK

___ SAT

___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is at 100% power.

INITIATING CUES:

Following a discussion with Glenn from RP concerning a premature gaseous release termination, the Control Room Supervisor directs you to set EMF 50L setpoints using OP/0/A/6500/080 (EMF RP86A Output Modules) Enclosure 4.2 (EMF RP86A and RM1000 Trip Setpoint Adjustment) to the following values:

Trip 1 = 6300 CPM Trip 2 = 9000 CPM OAC Program EMFLIB is currently not available.

Catawba Nuclear Station JPM G 2017 NRC Exam PAGE 1 OF 11

JPM G

Catawba Nuclear Station JPM G 2017 NRC Exam PAGE 2 OF 11 EVALUATION SHEET Task: Isolate Cold Leg Accumulators Following a Shutdown LOCA Alternate Path:

Yes Facility JPM #:

N/A Safety Function:

3 Title: Emergency Core Cooling System (ECCS)

K/A 006 A1.13 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including: Accumulator pressure (level, boron concentration)

Rating(s):

3.5 / 3.7 CFR: 41.5 / 45.5 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

AP/1/A/5500/027 (Shutdown LOCA), Enclosure 14 (Isolating Cold Leg Accumulators)

Task Standard:

AP/1/A/5500/027 (Shutdown LOCA) Enclosure 14 (Isolating Cold Leg Accumulators) is performed and 1A & 1D Cold Leg Accumulators are isolated and 1NI-83 fully opened to vent 1B & 1C Cold Leg Accumulators to containment.

Validation Time:

15 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM G 2017 NRC Exam PAGE 3 OF 11 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC #

156. 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop

-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given.

Instructor Action Final Delay Ramp Delete In Event ANN-AD11-B03 (TRANSFORMER A TROUBLE) ON ANN-AD11-E03 (TRANSFORMER B TROUBLE) ON MAL-NC013B (NC COLD LEG B LEAK) 0.5 VLV-NI008F (NI65B ACCUM ISOL VLV FAIL TO POSITION) 1 VLV-NI011F (NI76A ACCUM ISOL VLV FAIL TO POSITION) 1 PAGE 4 0F 11 Catawba Nuclear Station JPM G 2017 NRC Exam PAGE 4 OF 11 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is in Mode 4.

Unit 1 shutdown was in progress for a refueling outage, when pressurizer pressure and level began to decrease uncontrollably.

The CRS has entered AP/1/A/5500/027 (Shutdown LOCA) to address the reactor coolant system leak.

Power to all CLA discharge isolation valves has been restored per EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 9 (Power Alignment for CLA Valves).

INITIATING CUES:

The CRS has directed you to isolate the Unit 1 Cold Leg Accumulators by performing AP/1/A/5500/027 (Shutdown LOCA) Enclosure 14 (Isolating Cold Leg Accumulators).

EXAMINER NOTE

After reading the cue, provide the applicant with a copy of AP/1/A/5500/027 Enclosure 14.

Catawba Nuclear Station JPM G 2017 NRC Exam PAGE 5 0F 11 START TIME: _______

STEP/STANDARD SAT/UNSAT STEP 1: 1. Dispatch operator to restore power to all CLA discharge isolation valves. REFER TO EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 9 (Power Alignment for CLA Valves)

. STANDARD: Per initiating cue, the applicant should realize that this step is complete. Also valve indication for each of the CLA discharge isolation valves is available, due to power already being aligned by the AO.

COMMENTS: ___ SAT

___ UNSA T STEP 2: 2. Ensure S/I

- RESET a. ECCS. b. D/G load sequencers

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

STANDARD: Applicant verifies that the yellow ECCS and D/G load sequencer RESET lights are lit. Applicant acknowledges the If at any time statement.

COMMENTS:

___ SAT ___UNSAT Catawba Nuclear Station JPM G 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 11 STEP 3: 3. WHEN power is aligned, THEN perform the following:

a. CLOSE the following valves:

1NI-54A (C-Leg Accum A Disch Isol) 1NI-65B (C-Leg Accum B Disch Isol) 1NI-76A (C-Leg Accum C Disch Isol) 1NI-88B (C-Leg Accum D Disch Isol)

STANDARD: Applicant depresses the green CLOSE pushbutton for the valves listed, and verifies the green CLSD light lit and red OPEN light dark for valves 1NI

-54A & 1NI-88B. Applicant also verifies the red OPEN light lit and green CLSD light dark for valves 1NI

-65B & 1NI-76A and transitions to the RNO.

The critical part of this step is to close isolation valves 1NI

-54A & 1NI-88B. The other 2 Cold Leg Accumulators will be vented to containment in subsequent steps in the RNO.

EXAMINER NOTE: This begins the alternate path of this JPM.

EXAMINER NOTE: The applicant should determine from the initiating cue that power has been aligned. If necessary, inform "Power has been aligned"

. COMMENTS:

CRITICAL STE P ___ SAT

___ UNSAT Catawba Nuclear Station JPM G 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 11 STEP 4: 3.RNOa. Perform the following:

1) Ensure containment isolation signals

- RESET: Phase A Phase B STANDARD: Applicant verifies that the yellow RESET lights are lit for both trains Phase A and Phase B isolations.

COMMENTS: ___ SAT

___ UNSAT STEP 5: 3.RNOa. 2) Ensure 1VI

-77B (VI Cont Isol)

- OPEN STANDARD: Applicant determines that the red OPEN light lit and green CLSD light dark for 1VI

-77B. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM G 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 11 STEP 6: 3.RNOa. 3) IF VI pressure is less than 85 PSIG, THEN dispatch operator to ensure proper VI compressor operation.

STANDARD: Applicant determines that VI pressure is ~ 90 PSIG. This step is N/A.

COMMENTS: ___ SAT

___ UNSAT STEP 7: 3.RNOa.4)

Vent any CLA which cannot be isolated as follows:

a) OPEN 1NI

-47A (C-Leg Accum N2 Sup Cont Isol) STANDARD: Applicant depresses the red OPEN pushbutton for 1NI

-47A and verifies the red OPEN light lit and green CLSD light dark.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM G 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 11 STEP 8: 3.RNOa.4) b) Place breaker 1CB

-1 (behind 1MC

-6)(Key #11) to - ON STANDARD: Applicant lifts breaker 1CB

-1 fully up to the ON position.

This step is critical to place power on Cold Leg Accumulator Nitrogen supply isolation valves for 1B and 1C CLAs which will be opened in the next step to allow venting the accumulators to containment.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 9: 3.RNOa.4) c) OPEN valve for CLA(s) to be vented:

1NI-50 (C-Leg Accum A N2 Supply Isol) 1NI-61 (C-Leg Accum B N2 Supply Isol) 1NI-72 (C-Leg Accum C N2 Supply Isol) 1NI-84 (C-Leg Accum D N2 Supply Isol)

STANDARD: Applicant depresses the red OPEN pushbutton and verifies the red OPEN light lit and green CLSD light dark for 1NI

-61 and 1NI

-72. This step is critical due to not being able to isolate these CLAs. If these CLAs are not vented to reduce the N2 overpressure, it could

cause a hard bubble to form in the reactor coolant system as reactor coolant pressure continues to decrease.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM G 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 11 STEP 10: 3.RNOa.4) d) CLOSE 1NI

-47A. STANDARD: Applicant depresses the green CLOSE pushbutton and verifies the green CLSD light lit and red OPEN light dark for 1NI

-47A. This step is critical to allow venting the 1B and 1C CLAs.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT STEP 11: 3.RNOa.4) e) OPEN 1NI

-83 (C-Leg Accums N2 Vent Ctrl) to depressurize affected CLA(s).

STANDARD: Applicant rotates potentiometer for 1NI

-83 clockwise to full open to begin venting the 1B and 1C CLAs.

This step is critical to vent the 1B and 1C CLAs.

NOTE TO EVALUATOR: The time to fully vent the 1B & 1C CLAs would be approximately 30 minutes. The critical steps for this JPM have been met at this point and the JPM may be terminated at your discretion.

EVALUATOR CUE:

"Another operator will continue to vent the 1B and 1C Cold Leg Accumulators. This JPM is complete."

COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is in Mode 4.

Unit 1 shutdown was in progress for a refueling outage, when pressurizer pressure and level began to decrease uncontrollably.

The CRS has entered AP/1/A/5500/027 (Shutdown LOCA) to address the reactor coolant system leak.

Power to all CLA discharge isolation valves has been restored per EP/1/A/5000/G

-1 (Generic Enclosures), Enclosure 9 (Power Alignment for CLA Valves).

INITIATING CUES:

The CRS has directed you to isolate the Unit 1 Cold Leg Accumulators by performing AP/1/A/5500/027 (Shutdown LOCA) Enclosure 14 (Isolating Cold Leg Accumulators).

Catawba Nuclear Station JPM H 2017 NRC Exam PAGE 1 OF 14

JPM H

Catawba Nuclear Station JPM H 2017 NRC Exam PAGE 2 OF 14 EVALUATION SHEET Task: Restore Normal Power to 1ETA From The Control Room Alternate Path:

No Facility JPM #:

DG3-003 Safety Function:

6 Title: Emergency Diesel Generator (ED/G) System K/A 0 64 A4.07 Ability to manually operate and/or monitor in the control room: Transfer ED/G (with load) to grid.

Rating(s):

3.4 / 3.4 CFR: 41.7 / 45.5 to 45.8 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator X In-Plant Perform X Simulate References

OP/1/A/6350/002 Rev 17 9 Task Standard:

1ETA power being supplied from offsite through 1ATC and 1A D/G secured from the control room without a reverse power trip in accordance with OP/1/A/6350/002 (Diesel Generator Operation) Enclosure 4.17 (Shutdown of D/G 1A After An Automatic Start)

. Validation Time:

12.5 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM H 2017 NRC Exam PAGE 3 OF 14 SIMULATOR OPERATOR INSTRUCTIONS:

1. ENSURE NRC Examination Security has been established.

2. Reset to IC

157. 3. Enter the password.

4. Select "Yes" on the INITIAL CONDITION RESET pop-up window.

5. Ensure simulator setup per table below.

6. Place simulator in RUN and acknowledge any alarms.

7. ENSURE "Extra Operator" is present in the simulator.

8. Place simulator in FREEZE until Examiner cue is given

. Instructor Action Final Delay Ramp Delete In Event Catawba Nuclear Station JPM H 2017 NRC Exam PAGE 4 OF 14 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is recovering from a blackout per AP/1/A/5500/007 Case I (Loss of Normal Power to an Essential Train).

1ATC is energized and available to supply 1ETA.

D/G 1A Mode Select Switch is in the "CTRL

-RM" position.

D/G 1A Load Sequencer has been reset.

INITIATING CUES:

The Control Room Supervisor instructs you to parallel D/G 1A to 1ETA's normal power source (1ATC) and shutdown D/G 1A per OP/1/A/6350/002 (Diesel Generator Operation) Enclosure 4.17 (Shutdown of D/G 1A After an Automatic Start)

Step 3.2. Initial Conditions are complete.

Concurrent Verification has been waived.

EXAMINER NOTE

After reading cue, provide the applicant with a copy of OP/1/A/6350/002 Enclosure 4.17 with the initial conditions completed.

Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 14 START TIME: _______

STEP 1: 3.2 IF shutting down the diesel from the Control Room, perform the following:

3.2.1 IF both the normal (ETA Norm Fdr Frm ATC) AND alternate (ETA Alt Fdr Frm SATA) incoming feeder breakers are open, perform the following:

CAUTION: It is essential for the Operator to read and understand the following steps before attempting to re

-synchronize the D/G and bus to the normal or alternate power source. Quick response to any changes in load and power factor when the breaker closes is required to reduce the likelihood of a reverse power D/G Breaker trip. 3.2.1.1 Adjust voltage using "D/G 1A Volt Adjust" to allow "D/G 1A Volts" to be one half to two divisions (50 to 200 volts) higher than "Line Volts".

STANDARD: Applicant uses the D/G voltage control pushbuttons to set D/G 1A VOLTS 50 to 200 volts higher than LINE VOLTS on 1MC

-8. COMMENTS:

___ SAT ___ UNSAT

Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 14 STEP 2: 3.2.1.2 Place the "D/G 1A Sync" Switch in the "ON" position.

STANDARD: Applicant rotates the D/G 1A Sync switch clockwise to the ON position. Examiner Note: This step is critical to ensure that D/G 1A is in sync with the grid prior to closing the 1ETA normal incoming breaker.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 3 3.2.1.3 Adjust D/G speed using "D/G 1A Gov Ctrl" such that the Synchroscope is moving slowly in the "FAST" direction, (approximately 1 revolution per 30 seconds).

STANDARD: Applicant uses the D/G 1A Gov Ctrl pushbuttons to ensure that the Synchroscope is rotating slowly in the FAST direction.

Examiner Note: This step is critical to prevent a reverse power trip once the Normal Feeder breaker to 1ETA is closed.

COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 14 STEP 4 CAUTION: The following three steps shall be performed prior to signing off either step to reduce the likelihood of a reverse power D/G Breaker trip.

3.2.1.4 As the indicator reaches 1.5 min. before the vertical (synchronized) position, close one of the following breakers: o ETA Norm Fdr Frm ATC OR o ETA Alt Fdr Frm SATA STANDARD: Once the Synchroscope indicator reaches the 1.5 min. before the vertical position, the applicant will depress the red CLOSE pushbutton and verify the red CLSD light lit and green OPEN light dark on the "ETA Norm Fdr Frm ATC" breaker. The applicant will then immediately perform the next step to prevent a reverse power D/G Breaker trip.

Examiner Note: This step is critical to parallel 1A D/G to the normal offsite circuit to meet the task standard.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 14 STEP 5 3.2.1.5 Stabilize the D/G with a positive load and a lagging power factor.

STANDARD: Applicant depresses the D/G 1A Gov Ctrl RAISE pushbutton to ensure that D/G 1A picks up a positive load.

Examiner Note: This step is critical to ensure the 1A D/G is stabilized with a positive load to prevent a reverse power D/G Breaker trip.

Examiner Note: As long as the applicant ensured that D/G 1A volts were 50 to 200 volts higher than line volts, power factor will be lagging, and depending on how much higher D/G 1A volts were than line volts, may be severely lagging.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 14 STEP 6 3.2.1.6 IF the power factor meter indicates severely leading, (pegs high)

AND power output decreases to 0 KW (pegs low), THEN IMMEDIATELY trip D/G 1A Bkr To ETA.

STANDARD: Applicant determines that this step is not applicable and continues.

COMMENTS:

___ SAT ___ UNSAT STEP 7 3.2.1.7 Place the "D/G 1A Sync" Switch in the "OFF" position.

Record time ____________

STANDARD: Applicant rotates the D/G 1A Sync Switch counterclockwise to the OFF position. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 14 STEP 8 3.2.2 Verify one of the following breakers is closed:

o ETA Norm Fdr Frm ATC OR o ETA Alt Fdr Frm SATA

STANDARD: Applicant verifies the red CLSD light lit for the ETA Norm Fdr Frm ATC breaker. COMMENTS:

___ SAT

___ UNSAT STEP 9 3.2.3 IF D/G 1A Bkr To ETA is open, go to Step 3.2.7.

STANDARD: Applicant determines that D/G 1A Bkr To ETA is closed by verifying the red CLSD light lit and this step is not applicable.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 11 0F 14 STEP 10 3.2.4 IF D/G load is <

2000 KW, WHILE maintaining power factor at approximately .95 lagging using "D/G 1A Volt Adjust", adjust generator load using "D/G 1A Gov Ctrl" per the following: {PIP 96

-1185} CAUTION: The following two steps shall be performed prior to signing off either step to reduce the likelihood of a reverse power D/G Breaker trip.

3.2.4.1 Reduce D/G load to 200 KW

3.2.4.2 Trip D/G 1A Bkr To ETA.

STANDARD: Applicant depresses the D/G 1A Gov Ctrl LOWER pushbutton to decrease D/G 1A load to 200 KW while depressing the D/G 1A Volt Adjust LOWER pushbutton to maintain power factor at .95 lagging. Once 200 KW load is attained, the applicant depresses the green OPEN pushbutton for D/G 1A Bkr To ETA and verifies the green OPEN light is lit.

Examiner Note: If applicant loaded 1A D/G to > 2000 KW, step 3.2.5 will have them lower load to 2000 KW and after 15 minutes at this load, will have them decrease load to 200 KW and trip the D/G 1A breaker. If this is the case, once the applicant decreases D/G 1A load to 2000 KW, provide the following cue: "15 minutes have elapsed".

Examiner Note: Step 3.2.6 should be not applicable.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 12 0F 14 STEP 11 3.2.7 Allow diesel to idle unloaded for a minimum of 5 minutes or until the following conditions are met:

o Jacket water outlet temperature is

< 170 F. o Lube oil temperature is

< 170 F. o Turbocharger exhaust temperatures have stabilized.

STANDARD: Applicant acknowledges step and continues.

Examiner Cue: "5 minutes has elapsed."

COMMENTS: ___ SAT

___ UNSAT STEP 12 3.2.8 Ensure one of the following conditions is met

o The D/G Sequencer is "RESET".

OR o Power has been removed from the D/G Sequencer.

STANDARD: Applicant determines based off the initiating cue that D/G 1A load sequencer has been RESET and continues with the procedure.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM H 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 13 0F 14 STEP 13 3.2.9 Depress D/G 1A "OFF" pushbutton

. Record time _________

STANDARD: Applicant depresses the D/G 1A green OFF pushbutton.

Examiner Note: This step is critical to shutdown 1A D/G to meet the JPM standard.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT STEP 14 3.2.10 WHEN the engine stops, dispatch Operators as necessary to verify the following:

STANDARD: Applicant describes contacting and dispatching an AO to perform this step. Examiner Cue:

"An AO has been dispatched. Another operator will complete the remaining steps. This JPM is complete."

COMMENTS:

END OF TASK

___ SAT

___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is recovering from a blackout per AP/1/A/5500/007 Case I (Loss of Normal Power to an Essential Train).

1ATC is energized and available to supply 1ETA.

D/G 1A Mode Select Switch is in the "CTRL

-RM" position.

D/G 1A Load Sequencer has been reset.

INITIATING CUES:

The Control Room Supervisor instructs you to parallel D/G 1A to 1ETA's normal power source (1ATC) and shutdown D/G 1A per OP/1/A/6350/002 (Diesel Generator Operation) Enclosure 4.17 (Shutdown of D/G 1A After an Automatic Start) Step 3.2.

Initial Conditions are complete.

Concurrent Verification has been waived.

Catawba Nuclear Station JPM I 2017 NRC Exam PAGE 1 OF 10

JPM I

Catawba Nuclear Station JPM I 2017 NRC Exam PAGE 2 OF 10 EVALUATION SHEET Task: Place the 2A Hydrogen Analyzer in Service Alternate Path:

No Facility JPM #:

VX-024 Safety Function: 5 Title: Hydrogen Recombiner and Purge Control System (HRPS)

K/A 0 28 A 1.0 1 Ability to predict and/or monitor changes in parameter (to prevent exceeding design limits) associated with operating the HRPS controls including: Hydrogen concentration Rating(s):

3.4 / 3.8 CFR: 41.5 / 45.5 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator In-Plant X Perform X Simulate References

EP/2/A/5000/E

-1 (Loss of Reactor or Secondary Coolant) Rev 26 OP/2/A/6450/010 (Containment Hydrogen Control Systems) Rev 26 Task Standard:

Hydrogen Analyzer Train 2A in service monitoring upper containment via selection of Position "1".

Validation Time:

15 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM I 2017 NRC Exam PAGE 3 OF 10 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A large break LOCA has occurred on Unit 2.

The procedure currently in use is EP/2/A/5000/E

-1 (Loss of Reactor or Secondary Coolant). Containment Hydrogen Analyzer 2B is tagged for maintenan ce. INITIATING CUES:

The Control Room Supervisor directs you to place Containment Hydrogen Analyzer 2A in service to Position "1" for sampling Upper Containment per OP/2/A/6450/010 (Containment Hydrogen Control Systems) Enclosure 4.9, step 3.1.

All initial conditions are complete.

Peer check has been waived.

EXAMINER NOTE

After reading cue, provide the applicant with a copy of OP/2/A/6 450/0 10 Enclosure 4.

9 with the initial conditions completed.

Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 4 0F 10 START TIME: _______

STEP 1: 3.1 Place Hydrogen Analyzer Train A OR Train B in service.

3.1.1 IF aligning Hydrogen Analyzer Train A, proceed as follows: 3.1.1.1 Obtain Hydrogen Analyzer Control Panel Train A (2ELCP0251) key (Key #225) from WCC.

STANDARD: Applicant determines from the initiating cue that A train needs to be aligned and obtains the key #225

. Examiner Note

Key not required to be obtained to complete this JPM task. Once key is identified give cue.

Examiner Cue

"Key 225 has been obtained."

COMMENTS:

___ SAT ___ UNSAT

Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 10 NOTE: Steps 3.1.1.2

- 3.1.1.5 will be performed at Hydrogen Analyzer Control Panel 2A HACP

-2A 2ELCP0251 (AB

-579, DD-61). STEP 2: 3.1.1.2 Select the desired sample location by positioning the "HYDROGEN ANALYZER SAMPLE VALVES PORTS" switch: Position "1" (for sampling Upper Containment)

Position "2" (for sampling operating level)

Position "3" (for sampling Steam Generator 1B cavity) Position "ALL" for sampling ALL 3 locations) STANDARD: Applicant describes placing the HYDROGEN ANALYZER SAMPLE VALVES PORTS" switch in position "1".

Examiner Cue: Once switch is located by applicant and operation described, "Switch is in position "1"."

Examiner Note: This step is critical to be able to sample upper containment per the JPM standard.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 10 STEP 3 3.1.1.3 Verify the "POS 1: H2 ANALYZER POS 2: POST ACCIDENT SAMPLE PANEL" switch is in "POS. 1".

STANDARD: Applicant describes verifying the switch is in "POS 1".

Examiner Cue: Once located by applicant, "Switch is in position 1."

COMMENTS: ___ SAT ___ UNSAT Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 10 STEP 4 3.1.1.4 Insert key in "HYDROGEN ANALYZER CONT ISOLATION VALVES" key switch and turn to "OPEN" position. STANDARD: Applicant describes inserting the key and turning the key to the "OPEN" position. Examiner Cue: Once applicant describes inserting the key and operation of the switch, "Key switch is in the OPEN position."

Examiner Note: This step is critical to open the containment isolation valves in order to be able to sample upper containment

. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 5 3.1.1.5 Verify the following indicating lights are lit:

"H2 SAMPLE CONT. ISOLATION VALVES OPEN" Sample location(s) selected in Step 3.1.1.2.

STANDARD: Applicant describes verifying the red OPEN light LIT for H2 Sample Containment Isolation Valves and the "Upper Containment Sample Selected" light lit

. Examiner Cue: Once the light s are located, "Red OPEN light is lit

" and "Upper Containment Sample Selected light is lit." COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 10 NOTE: Steps 3.1.1.6

- 3.1.1.7 will be performed inside A Train Hydrogen Analyzer Control Unit (PAMS) 2MIMT5320A (AB

-579, DD-61). STEP 6 3.1.1.6 Verify the "STANDBY/OFF" switch is in the "STANDBY" position. STANDARD: Applicant describes verifying the "STANDBY/OFF" switch is in the "STANDBY" position.

Examiner Cue: Once switch is located, "Switch is in the "STANDBY" position."

COMMENTS:

___ SAT ___ UNSAT STEP 7 3.1.1.7 Place the "ON/OFF" switch in the "ON" position.

STANDARD: Applicant describes moving the ON/OFF switch up to the "ON" position.

Examiner Cue: Once operation of switch is described, "Switch is in the "ON" position and the green "ON" light is lit."

Examiner Note: This step is critical to turn the Hydrogen Analyzer on.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM I 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 10 STEP 8 3.1.1.8 Monitor H 2 concentration at either of the following locations:

"Hydrogen Analyzer Control Unit "2MIMT5320A" (AB-579, DD-61) "CONTAINMENT TRN A H2 ANAL" meter (2MIP5320) located on 2MC7.

STANDARD: Applicant describes calling the control room to inform them that the hydrogen analyzers are in service and can be read on the local unit or on 2MC-7. Examiner Cue: "Hydrogen concentration will be monitored on 2MC

-7. This JPM is complete."

COMMENTS:

END OF TASK

___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A large break LOCA has occurred on Unit 2.

The procedure currently in use is EP/2/A/5000/E

-1 (Loss of Reactor or Secondary Coolant). Containment Hydrogen Analyzer 2B is tagged for maintenance.

INITIATING CUES:

The Control Room Supervisor directs you to place Containment Hydrogen Analyzer 2A in service to Position "1" for sampling Upper Containment per OP/2/A/6450/010 (Containment Hydrogen Control Systems) Enclosure 4.9, step 3.1.

All initial conditions are complete.

Peer check has been waived.

Catawba Nuclear Station JPM J 2017 NRC Exam PAGE 1 OF 8

JPM J

Catawba Nuclear Station JPM J 2017 NRC Exam PAGE 2 OF 8 EVALUATION SHEET Task: Align Seal Injection to the Unit 1 NC Pumps Alternate Path:

No Facility JPM #:

New Safety Function: 4S Title: Service Water System K/A 0 76 A 2.0 1 Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS Rating(s):

3.5 / 3.7 CFR: 41.5 / 4 3.5 / 45.3 / 45.13 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator In-Plant X Perform X Simulate References

AP/0/A/5500/020 (Loss of Nuclear Service Water) Rev 43 Task Standard:

Standby Makeup Pump #1 in service providing seal injection to the Unit 1 NC Pumps. Validation Time:

1 0 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM J 2017 NRC Exam PAGE 3 OF 8 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A Loss of RN has occurred on Unit 1.

Control room has entered AP/0/A/5500/020 (Loss of Nuclear Service Water).

An operator has aligned the alternate power supply to 1EMXS per AP/20 Enclosure 4 (Align Alternate Power Supply To 1EMXS OR 2EMXS).

INITIATING CUES:

The Control Room Supervisor directs you to place standby makeup pump #1 in service to provide seal injection to the Unit 1 NC pumps per AP/20 Enclosure 6 (Align Seal Injection to the Unit 1 NC Pumps)

. You are directed to use the local procedure to perform this task.

Peer checks have been waived.

EXAMINER NOTE

Once the applicant has located the local copy of the procedure, hand the applicant a copy of AP/0/A/5500/020 Enclosure 6.

Catawba Nuclear Station JPM J 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 4 0F 8 START TIME: _______

STEP 1: 1. Ensure 1NV

-876 (Stdby M/U To Cont Equip Sump 1A)

- CLOSED. STANDARD: Applicant verifies the green CLSD light lit and the red OPEN light dark for 1NV-876. Examiner Cue

Once located, "Green light is lit

." COMMENTS:

___ SAT ___ UNSAT STEP 2: 2. IF annunciator 0AD

-11, C/1 (ESS MCC 1EMXS LOSS OF VOLTAGE) LIT, THEN: STANDARD: Applicant verifies 0AD

-11, C/1 annunciator is dark and that step 2 is not applicable.

Examiner Cue: Once the alarm window is located, "Alarm is dark

." COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station JPM J 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 8 STEP 3 3. IF "UNIT 1 SSF CONTROLS ENGAGED" DARK, THEN: STANDARD: Applicant verifies the UNIT 1 SSF CONTROLS ENGAGED light is LIT. Examiner Cue: Once located by applicant, "Unit 1 SSF Controls Engaged light is lit

." COMMENTS: ___ SAT ___ UNSAT STEP 4 4. IF "UNIT 1 SSF CONTROLS ENGAGED" LIT, THEN: a. Ensure the following valves

- OPEN: 1NV-865A (Stdby M/U Pump Suct Frm Xfer Tube) 1NV-872A (Stdby M/U Pmp Filt Otlt).

STANDARD: Applicant describes depressing the red OPEN pushbuttons on 1NV

-865A and 1NV

-872A and verifying the red OPEN light is lit and green CLSD light is dark for both valves.

Examiner Cue: Once applicant describes operation of each valve , "Red indicating light is lit

." Examiner Note: This step is critical to align a suction and discharge path for Standby Makeup Pump #1

. COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station JPM J 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 8 STEP 5 4.b. CLOSE 1NV

-89A (NC Pmps Seal Ret Cont Isol).

STANDARD: Applicant depresses the green CLOSE pushbutton on 1NV

-89A and verifies the green CLSD light lit and red OPEN light dark.

Examiner Cue: Once the valve control switch is located and operation described, "Green light is lit."

Examiner Note: This step is critical to ensure any voids in the seal leakoff line are collapsed prior to initiating flow from the standby makeup pump.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 6 5. Ensure 1NV

-877 (Stdby M/U To NC Pump Seal Inj)

- OPEN.

STANDARD: Applicant describes verifying the red OPEN light lit and green CLSD light dark for 1NV

-877. Examiner Cue: Once the valve control switch is located, "Red light is lit." COMMENTS: ___ SAT ___ UNSAT Catawba Nuclear Station JPM J 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 8 STEP 7 6. Start "STDBY M/U PUMP #1" by depressing "ON" pushbutton on SSF console.

STANDARD: Applicant depresses the red ON pushbutton on switch for STDBY M/U PUMP #1 and verifies the red ON light lit and green OFF light dark

. Applicant may also check for Unit 1 standby makeup flow on SSF console. Examiner Cue: Once operation of switch is described, "Red ON light lit." If Unit 1 standby makeup flow is checked, "26 GPM indicated."

Examiner Note: This step is critical to place Standby Makeup Pump #1 in service to provide seal injection flow to the Unit 1 NC Pumps

. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 8 7. Notify Control Room Supervisor of status of "STDBY M/U PUMP #1". STANDARD: Applicant contacts the control room and reports that Standby Makeup Pump #1 is in service.

Examiner Cue:

"Another operator will finish the procedure. This JPM is complete."

COMMENTS:

END OF TASK

___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

A Loss of RN has occurred on Unit 1.

Control room has entered AP/0/A/5500/020 (Loss of Nuclear Service Water).

An operator has aligned the alternate power supply to 1EMXS per AP/20 Enclosure 4 (Align Alternate Power Supply To 1EMXS OR 2EMXS).

INITIATING CUES:

The Control Room Supervisor directs you to place standby makeup pump #1 in service to provide seal injection to the Unit 1 NC pumps per AP/20 Enclosure 6 (Align Seal Injection to the Unit 1 NC Pumps).

You are directed to use the local procedure to perform this task.

Peer checks have been waived.

Catawba Nuclear Station JPM K 2017 NRC Exam PAGE 1 OF 13

JPM K

Catawba Nuclear Station JPM K 2017 NRC Exam PAGE 2 OF 13 EVALUATION SHEET Task: Align Swing Inverter 1EIE to 1ERPA Alternate Path:

No Facility JPM #:

EPL-010 Safety Function: 6 Title: AC Electrical Distribution System K/A 0 62 A 2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Types of loads that, if de-energized, would degrade or hinder plant operation.

Rating(s):

3.4 / 3.9 CFR: 41.5 / 4 3.5 / 45.3 / 45.13 Preferred Evaluation Location:

Preferred Evaluation Method: Simulator In-Plant X Perform X Simulate References

OP/1/A/6350/008 (125 VDC/120 VAC Vital Instrument and Control Power System) Enclosure 4.

37 Rev 7 3 Task Standard:

1ERPA energized with power from swing inverter 1EIE.

Validation Time: 20 minutes Time Critical:

Yes No X ===========================================================================

Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS Catawba Nuclear Station JPM K 2017 NRC Exam PAGE 3 OF 13 READ TO APPLICANT DIRECTION TO APPLICANT: I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power.

AC Panelboard 1ERPA is currently being supplied by 1VRD with inverter 1EIA shutdown per OP/1/A/6350/008 (125 VDC/120 VAC Vital Instrument and Control Power System) Enclosure 4.9 (1EIA Shutdown and Return to Service).

INITIATING CUES:

The Control Room Supervisor directs you to align Swing Inverter 1EIE to supply AC Panelboard 1ERPA per OP/1/A/6350/008 Enclosure 4.37 (Placing in Service and Removing from Service 1EIE) beginning at step 3.3.

Initial conditions are complete.

Breaker padlock keys #275 and #277 have been obtained.

All required PPE for this task has been obtained.

Independent Verification requirements have been waived for this JPM.

EXAMINER NOTE

After reading cue, provide the applicant with a copy of OP/1/A/6350/008 Enclosure 4.

37 with steps through step 3.2 complete.

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 4 0F 13 START TIME: _______

NOTE: Perform either Step 3.3 or 3.4 as per desired supply for 1EIE.

STEP 1: 3.3 IF Step 2.3 indicates that 1EDA is to supply 1EIE, align as follows: NOTE: 1EDA-F01E is padlock interlocked with 1EDC

-F01D; only one breaker can be "ON".

3.3.1 Remove the padlock (key #275) on 1EDA

-F01E (Channel A Feeder

-Swing Inverter 1EIE).

STANDARD: Applicant describes opening the padlock on 1EDA

-F01E and removing it. Examiner Cue: Once lock is located, "Padlock removed."

Examiner Note: This step is critical to be able to operate the breaker in the next step to energize inverter 1EIE.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 5 0F 13 STEP 2: 3.3.2 Place 1EDA-F01E (Channel A Feeder

-Swing Inverter 1EIE) in the "ON" position.

STANDARD: Applicant describes rotating breaker 1EDA

-F01E clockwise to the ON position. Examiner Cue: Once breaker is located by applicant and operation described, "Breaker is ON

." Examiner Note: This step is critical to provide power to swing inverter 1EIE

. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 3 3.3.3 Place the padlock (unlocked) near 1EDA

-F01E (Channel A Feeder-Swing Inverter 1EIE).

STANDARD: Applicant describes placing the padlock.

Examiner Cue: Once described by applicant, "Padlock placed

." COMMENTS: ___ SAT ___ UNSAT Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 6 0F 13 NOTE: Step 3.3.5 must be performed immediately after Step 3.3.4 is completed. Failure to close the "DC INPUT" breaker immediately after the "PRE

-CHARGE" pushbutton is released may result in blown inverter input fuses.

STEP 4 3.3.4 Hold the "PRE

-CHARGE" toggle switch on 1EIE in the "EDA-LEFT" position until the "PRE

-CHARGE" indicator lamp has been illuminated for a minimum of 5 seconds.

STANDARD: Applicant describes holding the toggle switch on 1EIE in the EDA

-LEFT position and verifies the PRE

-CHARGE light lit for a minimum of 5 seconds and then releases the toggle switch.

Examiner Cue: Once applicant describes holding the PRE

-CHARGE switch in the proper position, "PRE-CHARGE indicator lamp has been illuminated for 5 seconds." COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 7 0F 13 STEP 5 3.3.5 Place 1EIE B1 (1EIE DC Input From 1EDA) on 1EIE in the "ON" position.

STANDARD: Applicant describes placing breaker 1EIE B1 in the ON position.

Examiner Cue: Once the breaker is located and proper operation described, "Breaker is ON

." Examiner Note: This step is critical to provide power to swing inverter 1EIE.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 6 3.4 IF Step 2.3 indicates that 1EDC is to supply 1EIE, align as follows: STANDARD: Applicant determines that this step is not app licable. COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 8 0F 13 STEP 7 3.5 Place the sync selector switch on 1EME (MANUAL BYPASS SWITCH FOR SWING INVERTER 1EIE) in the "SYNC ON" position. STANDARD: Applicant describes placing the sync selector switch on 1EME to the "SYNC ON" position.

Examiner Cue: Once operation of switch is described, "Switch is in the "SYNC ON" position."

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT NOTE: Inverter fans are located in the top of the Inverter cabinet. A visual verification of the fans running requires that the upper cabinet door be opened.

STEP 8 3.6 Visually verify that both fans in 1EIE are running. STANDARD: Applicant describes opening the upper cabinet door and verifying that both fans are running

. Examiner Cue:

"Both fans are running

." COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 9 0F 13 NOTE: Inverter output voltage may be higher than specified range until inverter warms up.

STEP 9 3.7 IF inverter output voltage has NOT settled to 118

- 125 VAC within 15 minutes, contact IAE to adjust voltage.

STANDARD: Applicant checks inverter output voltage and determines that this step is not applicable.

Examiner Cue: Once inverter output voltage found, "Voltage reads 120 Volts."

COMMENTS: ___ SAT ___ UNSAT STEP 10 3.8 Verify the following on 1EIE:

"INVERTER OUTPUT VOLTAGE" 118

- 125.5 V "INVERTER OUTPUT FREQUENCY" 59.4

- 60.3 Hz STANDARD: Applicant checks inverter output voltage and frequency within limits given. Examiner Cue: Once inverter output voltage found, "Voltage reads 120 Volts."

Once inverter output frequency found, "Frequency reads 60 Hz."

COMMENTS:

___ SAT ___ UNSAT

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 10 0F 13 STEP 11 3.9 Place 1EIE B2 (1EIE Inverter AC Output) on 1EIE in the "ON" position.

STANDARD: Applicant describes placing breaker 1EIE B2 to the ON position.

Examiner Cue: Once operation of breaker is described, "Breaker is in the "ON" position."

Examiner Note: This step is critical to be able to power 1ERPA from swing inverter 1EIE.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT NOTE: 1. Inverter "IN SYNC" lights may take up to 60 minutes to illuminate as inverter circuits warmup if inverter has been shutdown for

> 8 hours0.333 days 0.0476 weeks 0.011 months . 2. Both "IN SYNC" lamps listed in following step are powered from the same source.

STEP 12 3.10 Verify at least one of the following "IN SYNC" lights is illuminated:

1EME (MANUAL BYPASS SWITCH FOR SWING INVERTER 1EIE) 1EIE (TRAIN A VITAL SWING INVERTER)

STANDARD: Applicant describes verifying the IN SYNC lights lit

. Examiner Cue: Once the lights are located, "Light is lit."

COMMENTS: ___ SAT ___ UNSAT Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 11 0F 13 NOTE: Procedure may continue before completing following step.

STEP 13 3.11 IF one of the above listed "IN SYNC" lights is NOT illuminated, initiate a work request to repair.

STANDARD: Applicant determines that this step is not applicable.

COMMENTS: ___ SAT ___ UNSAT STEP 14 3.12 Place the "MANUAL BYPASS SWITCH" on 1EME (MANUAL BYPASS SWITCH FOR SWING INVERTER 1EIE) to the "INVERTER TO LOAD" position.

STANDARD: Applicant describes placing the manual bypass switch to the INVERTER TO LOAD position.

Examiner Cue: Once operation of the manual bypass switch is described, "Manual Bypass Switch is in the INVERTER TO LOAD position."

Examiner Note: This step is critical to power 1ERPA from swing inverter 1EIE.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

Catawba Nuclear Station JPM K 2017 NRC Exam STEP/STANDARD SAT/UNSAT PAGE 12 0F 13 NOTE: Perform either Step 3.13 or 3.14 as per Step 2.2, applicable shutdown inverter.

STEP 15 3.13 IF Step 2.2 indicates 1EIA is shutdown, verify the output Volts and Amps on 1EIE indicate approximately the same as the AC System output Volts and Amps on the following:

1EME (MANUAL BYPASS SWITCH FOR SWING INVERTER 1EIE) output Volts and Amps 1EMA (MANUAL BYPASS SWITCH FOR INVERTER 1EIA) output Volts and Amps STANDARD: Applicant checks inverter output voltage and amps and compares them with 1EME and 1EMA

. Examiner Cue: Once applicant describes how to perform the step , "Voltage is reading 120 Volts and Amps are reading 37 Amps on 1EIE, 1EME, and 1EMA

. Another operator will complete the procedure. This JPM is complete.

" COMMENTS: END OF TASK

___ SAT ___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is operating at 100% power.

AC Panelboard 1ERPA is currently being supplied by 1VRD with inverter 1EIA shutdown per OP/1/A/6350/008 (125 VDC/120 VAC Vital Instrument and Control Power System) Enclosure 4.9 (1EIA Shutdown and Return to Service).

INITIATING CUES:

The Control Room Supervisor directs you to align Swing Inverter 1EIE to supply AC Panelboard 1ERPA per OP/1/A/6350/008 Enclosure 4.37 (Placing in Service and Removing from Service 1EIE) beginning at step 3.3.

Initial conditions are complete.

Breaker padlock keys #275 and #277 have been obtained.

All required PPE for this task has been obtained.

Independent Verification requirements have been waived for this JPM.

Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam PAGE 1 OF 13 JPM A.1-1 RO / SRO

Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam PAGE 2 OF 13 EVALUATION SHEET Task: Perform Manual Shutdown Margin Calculation Alternate Path:

N/A Facility JPM #:

RB-127 Safety Function:

N/A K/A 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc

. Importance:

3.9 / 4.2 CFR: 41.10 / 4 3.5 / 45.12 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

OP/0/A/6100/006 (Reactivity Balance Calculation)

ROD Book Rev 780 Task Standard:

Using OP/0/A/6100/006 Enclosure 4.3, calculates shutdown margin to be 1 0 63 - 1 0 97 pcm and determines that adequate shutdown margin does not exist.

This JPM must be complete within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months completion time required by T.S.

3.1.4. Validation Time:

1 5 minutes Time Critical:

Yes X No Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Time Critical (<1 hour)

Time Start: __________

Time Finish: __________

Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 13 Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam PAGE 3 OF 13 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The Reactor Eng Analysis and Calc Toolkit (REACT)

- CNS is inoperable.

During performance of PT/0/A/4150/030 (RCCA Bank Repositioning), it was determined that Control Rods H4 and K14 were immovable and untrippable

. IAE is investigating.

Unit 1 conditions:

o Mode 1 at 100% RTP o Cycle burnup is 240 EFPD o Control Bank 'D' position is 216 steps withdrawn o All other rods are at 226 steps withdrawn o Current Boron Concentration is 1200 ppmB INITIATING CUES:

The Shift Manager has directed you to perform a shutdown margin calculation using OP/0/A/6100/006 (Reactivity Balance Calculations)

. Calculation is to be performed for current date and time.

Initial conditions have been verified.

Independent Verification has been waived.

This JPM is time critical.

Calculated shutdown margin for current conditions __________ pcm Adequate shutdown margin exists (YES/NO) ___________

EXAMINER NOTE

After reading cue, provide applicant with a copy of OP/0/A/6 100/0 06.

Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 OF 13 START TIME: _______

STEP / STANDARD SAT / UNSAT STEP 1: 3.1 Determine the following information:

NOTE: "Quantity of Misaligned Rods" refers to rods that are misaligned but remain trippable. Only the total number of rods is required. (R.M.)

STANDARD: From the cue, the applicant records the information per the table above.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 OF 13 STEP 2: 3.2 IF using the REACT program to complete the calculation, perform the following:

STANDARD: Applicant determines based of the initiating cue that this step is not applicable.

COMMENTS:

___ SAT ___ UNSAT NOTE: 1. A dropped rod is considered trippable. (R.M.)

2. All values are assumed positive unless otherwise indicated by parentheses. If parentheses precede the value [i.e. ( ) _________ pcm], the sign provided with data must be recorded.

The calculations account for these sign conventions. (R.M.)

STEP 3: 3.3 IF performing the calculation manually, perform the following:

3.3.1 Determine available reactivity worth of trippable RCCAs for conditions in Step 3.1:

NOTE: Interpolation is NOT required in Step 3.3.1.1. Reactivity worth may be determined by choosing the lowest reactivity worth from Section 5.7 of the R.O.D. Manual associated with cycle burnups that bound the present cycle burnup recorded in Step 3.1. (R.M.)

3.3.1.1 Determine Total Available Rod Worth _______ pcm (Section 5.7 of R.O.D. manual)

STANDARD: Applicant determines Total Available Rod Worth is 4949 pcm from R.O.D. Book Section 5.7 (5149 pcm per table

- 200 pcm additional stuck rod worth penalty from note below the table)

. Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 OF 13 STEP 4: 3.3.1.2 IF only one RCCA is untrippable, determine reactivity worth penalty for untrippable RCCA core location of Step 3.1.10 (Section 5.8 of R.O.D. manual). __________ pcm STANDARD: Applicant determines that this step is not applicable.

COMMENTS:

___ SAT ___ UNSAT STEP 5: 3.3.1.3 IF there are multiple untrippable RCCAs, perform the following:

A. Determine untrippable RCCA of Step 3.1.10 with the highest reactivity worth penalty (Section 5.8 of R.O.D. manual). Core Location ______

STANDARD: Applicant determines that RCCA Core Location H4 has the highest reactivity worth penalty.

COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 OF 13 STEP 6: 3.3.1.3 B. Record reactivity worth of the untrippable RCCA of Step 3.3.1.3.A (Section 3.8 of R.O.D. Manual). _________ pcm STANDARD: Applicant determines the reactivity worth of rod H4 per R.O.D. Section 5.8 is 473 pcm.

Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT STEP 7: 3.3.1.3 C. Determine maximum stuck rod worth during cycle (Section 5.7 of the R.O.D. manual).

___________ pcm STANDARD: Applicant determines maximum stuck rod worth from R.O.D. manual section 5.7 is 885 pcm.

Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 OF 13 STEP 8: 3.3.1.3 D. Calculate total untrippable RCCA reactivity worth penalty below:

STANDARD: Applicant calculates the Total untrippable RCCA worth penalty to be 1358 pcm. Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT STEP 9: 3.3.1.4 Record Total Untrippable RCCA Penalty from Step 3.3.1.2 or Step 3.3.1.3D, whichever is applicable.

__________ pcm STANDARD: Applicant records 1358 pcm from step 3.3.1.3 D.

COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 9 OF 13 NOTE: Interpolation is NOT required in Step 3.3.1.5. Reactivity worth may be determined by choosing the highest reactivity worth from Section 5.6.3 of the R.O.D. Manual associated with rod positions that bound the present rod position. (R.M.)

STEP 10: 3.3.1.5 Determine Inserted Rod Worth for present bank positions:

STANDARD: Applicant calculates Inserted Worth of Present rod positions to be 12 pcm. COMMENTS: ___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 10 OF 13 STEP 11: 3.3.1.6 Calculate available reactivity worth of trippable RCCAs:

STANDARD: Applicant calculates Available Reactivity Worth of Trippable RCCAs.

Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT STEP 12: 3.3.1.7 Calculate total misaligned RCCA reactivity worth below:

STANDARD: Applicant determines that this step does not apply.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 11 OF 13 NOTE: Interpolation of Power Defect is NOT required for Step 3.3.2. Bounding burnups and power levels may be used to select the highest Power Defect from Section 5.9 of the R.O.D. manual. (R.M.) STEP 13: 3.3.2 Calculate SDM for present conditions:

STANDARD: Applicant calculates Present SDM to be +1 063 pcm. Acceptable range of 1 0 63 - 1 097 pcm (if interpolation of power defect (1970 pcm) is performed).

Examiner Note: It is not critical for the applicant to record the "+" sign in the above calculation. If the applicant were to incorrectly record a "

-" sign in the parentheses above, then this critical step would not be met.

Examiner Note: This step is critical to ensure accurate result for final calculation and to determine whether required SDM for present plant conditions is met.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-1 June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 12 OF 13 STEP 14: Adequate shutdown margin exists (YES/NO).

STANDARD: Applicant determines that 1300 pcm of SDM is required for the current plant conditions and that an actual SDM of 1 0 63 - 1 0 97 pcm is not adequate. Applicant records NO for 2 nd part of answer.

Examiner Note: This step is critical to determine that adequate SDM does not exist for the current plant conditions.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed.

All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The Reactor Eng Analysis and Calc Toolkit (REACT)

- CNS is inoperable.

During performance of PT/0/A/4150/030 (RCCA Bank Repositioning), it was determined that Control Rods H4 and K14 were immovable and untrippable.

IAE is investigating.

Unit 1 conditions:

o Mode 1 at 100% RTP o Cycle burnup is 240 EFPD o Control Bank 'D' position is 216 steps withdrawn o All other rods are at 226 steps withdrawn o Current Boron Concentration is 1200 ppmB INITIATING CUES:

The Shift Manager has directed you to perform a shutdown margin calculation using OP/0/A/6100/006 (Reactivity Balance Calculations).

Calculation is to be performed for current date and time.

Initial conditions have been verified.

Independent Verification has been waived.

This JPM is time critical.

Calculated shutdown margin for current conditions __________ pcm

Adequate shutdown margin exists (YES/NO) ___________

.3 OP/0/A/6100/006Shutdown Margin - Untrippable / Misaligned RCCA(s) - Modes 1 & 2 Page 1 of 7 1.Limit and Precauti onsNOTE: All curves/tables used in this procedure are found in Unit One (Two) Reactor Operating Data (R.O.D.) manual. (R.M.)

1.1 This procedure is reactivity management related because it is used to verify proper balance and manipulation of reactivity using various tools (REACT, R.O.D. Manual, etc.). 1.2 Ensure all data used by this procedure are for the correct unit.

1.3 NC System T-AVG shall be maintained within +/-1 °F of T-REF in Modes 1 and 2 to reduce uncertainties in calculations.

1.4 SDM shall be 1300 pcm in Modes 1, 2, 3, and 4. (Tech Spec 3.1.1 and Enclosure 4.3, 4.4, 4.5 or 4.6) 1.5 REACT and manual calculations may NOT yield equal results due to minor differences in methods (i.e. interpolation). Reactor Engineering may be contacted if questions arise.

1.6 Independently performed calculations may NOT yield exactly the same results due to data taken at different times. The CRS and Reactor Engineering may be contacted if questions arise.

2.Initial Conditions None .3 OP/0/A/6100/006Shutdown Margin - Untrippable / Misaligned RCCA(s) - Modes 1 & 2 Page 2 of 7 3.Procedure 3.1 Determine the following information: NOTE: "Quantity of Misaligned Rods" refers to rods that are misaligned but remain trippable. Only the total number of rods is required. (R.M.) StepDescription ReferenceValue 3.1.1 Unit N/A 3.1.2 Date/Time N/A 3.1.3 Present Power P1385 % 3.1.4 NC System Boron Concentration Latest sample ppm 3.1.5 Current burnup P1457 EFPD 3.1.6 Present control bank position OAC or Control Board ______ SWD onControl Bank______3.1.7 Present shutdown bank position OAC or Control Board A _____ B _____

C _____ D _____

E _____ 3.1.8 Quantity of misaligned rods N/A 3.1.9 Number of untrippable RCCAs N/A 3.1.10 Untrippable RCCA(s) core location(s)

N/A 3.2 IF using the REACT program to complete the calculation, perform the following:

3.2.1 Access "Reactor Eng Analysis and Calc Toolkit (REACT) - CNS" from DAE.

3.2.2 Select "View" then "Reactivity Balance Calculations" on toolbar.

3.2.3 Select "SDM - Mode 1 or 2" tab in Reactivity Balance Calculations window.

_____ _____ .3 OP/0/A/6100/006Shutdown Margin - Untrippable / Misaligned RCCA(s) - Modes 1 & 2 Page 3 of 7 CAUTION: All inputs must be checked carefully and corrected as needed before calculating results. The correct Unit must be specified. NOTE: Untrippable control rods are input by clicking "Select Inoperable Rods" and any inserted shutdown banks are input using "Shutdown Banks Inserted" tab. (R.M.)

3.2.4 Enter appropriate values from Step 3.1 in "Input Data" section for the following: "Shutdown Margin" tab "Shutdown Banks Inserted" tab 3.2.5 Obtain results as follows:

3.2.5.1 Click "Calculate" button.

3.2.5.2 Print program results.

3.2.5.3 Label printout appropriately.

3.2.5.4 Attach printout to this enclosure.

3.2.6 Sign below to document performance: Performed by_________________________Date/Time:______/______

3.2.7 Ensure that an independent calculation per this enclosure has been separately performed. NOTE: Independently performed calculations may NOT yield exactly the same results due to data taken at different times. The CRS and Reactor Engineering may be contacted if questions arise.

3.2.8 Verify that both performances of this enclosure yield equivalent results _____ _____ _____ _____ .3 OP/0/A/6100/006Shutdown Margin - Untrippable / Misaligned RCCA(s) - Modes 1 & 2 Page 4 of 7 3.2.9 Perform one of the following base d on results of the calculations:

3.2.9.1 IF Effective Shutdown Margin for a Present Position is greater than the Required Shutdown Margin, notify the CRS that Effective Shutdown Margin is acceptable. OR 3.2.9.2 IF Effective Shutdown Margin for a Present Position is less than the Required Shutdown Margin, notify the CRS to apply the applicable Technical Specification Action.

3.2.10 Submit both performances of this enclosure to the Control Room Supervisor for review. NOTE: 1. A dropped rod is considered trippable. (R.M.) 2.All values are assumed positive unless otherwise indicated by parentheses. Ifparentheses precede the value [i.e. ( )______________ pcm], the sign provided with data must be recorded. The calculations account for these sign conventions. (R.M.)

3.3 IF performing the calculation manually, perform the following:

3.3.1 Determine available reactivity worth of trippable RCCAs for conditions in

Step 3.1: NOTE: Interpolation is NOT required in Step 3.3.1.1. Reactivity worth may be determined by choosing the lowest reactivity worth from Section 5.7 of the R.O.D Manual associated with cycle burnups that bound the present cycle burnup recorded in Step 3.1. (R.M.)

3.3.1.1 Determine Total Available Rod Worth ____________ pcm (Section 5.7 of R.O.D. manual) 3.3.1.2 IF only one RCCA is untrippable, determine reactivity worth penalty for untrippable RCCA core location of Step 3.1.10 (Section 5.8 of R.O.D. manual). ____________ pcm 3.3.1.3 IF there are multiple untrippable RCCAs, perform the following:

A. Determine untrippable RCCA of Step 3.1.10 with the highest reactivity worth penalty (Section 5.8 of ROD Manual).

Core Location _________

_____ _____ _____ _____ _____ _____ _____ _____ _____ .3 OP/0/A/6100/006Shutdown Margin - Untrippable / Misaligned RCCA(s) - Modes 1 & 2 Page 5 of 7 B. Record reactivity worth of the untrippable RCCA of Step 3.3.1.3.A (Section 5.8 of ROD Manual).

_____________ pcm C. Determine maximum stuck rod worth during cycle (Section 5.7 of the R.O.D. manual). _____________ pcm D. Calculate total untrippable RCCA reactivity worth penalty below: DescriptionReference ValueA.Number of Untrippable RCCAs Step 3.1.9 B. Highest Worth Penalty Step 3.3.1.3 B pcm C. Max Stuck Rod Step 3.3.1.3 C pcm Total untrippable RCCA Worth Penalty for Multiple RCCAs { [ (A) - 1] X (C) } + (B) pcm 3.3.1.4 Record Total Untrippable RCCA Penalty from Step 3.3.1.2 or Step 3.3.1.3D, whichever is applicable. ______________ pcm NOTE: Interpolation is NOT required in Step 3.3.1.5. Reactivity worth may be determined by choosing the highest reactivity worth from Section 5.6.3 of the R.O.D Manual associated with rod positions that bound the present rod position. (R.M.)

3.3.1.5 Determine Inserted Rod Worth for present bank positions: DescriptionReference ValueA. HFP, Eq Xenon IRW for current

control bank position and current cycle burnup Step 3.1.6

Step 3.1.5 (Section 5.6.3 of R.O.D. manual)

__________ pcm B. HFP, Eq Xenon IRW for current shutdown bank positions and current cycle burnup Step 3.1.7 Step 3.1.5 (Section 5.6.3 of R.O.D. manual)

SD E ________ pcm SD D ________ pcm SD C ________ pcm SD B ________ pcm SD A ________ pcm Inserted Worth of Present Position Sum of above pcm _____ _____ .3 OP/0/A/6100/006Shutdown Margin - Untrippable / Misaligned RCCA(s) - Modes 1 & 2 Page 6 of 7 3.3.1.6 Calculate available reactivity worth of trippable RCCAs: DescriptionReference ValueA. Total Available Rod Worth Step 3.3.1.1 pcm B. Untrippable RCCAs Penalty Step 3.3.1.4 pcm C. Inserted Worth of Present Position Step 3.3.1.5 pcm Available Reactivity Worth of Trippable RCCAs (A) - (B) - (C) pcm 3.3.1.7 Calculate total misaligned RCCA reactivity worth below: DescriptionReference ValueA. Quantity of Misaligned Rods Step 3.1.8 B. Maximum Dropped or Misaligned Rod Worth Section 5.7 of ROD Manual pcm Total misaligned RCCA Reactivity

Worth (A) X (B) pcm NOTE: Interpolation of Power Defect is NOT required for Step 3.3.2. Bounding burnups and power levels may be used to select the highest Power Defect from Section 5.9 of the R.O.D. manual. (R.M.)

3.3.2 Calculate SDM for present conditions: DescriptionReference ValueA. Available reactivity worth of Trippable RCCAs Step 3.3.1.6 pcm B. Total misaligned RCCA reactivity Worth Step 3.3.1.7 pcm C. Total Power Defect at present thermal power (Step 3.1.3) and current cycle burnup (Step 3.1.5)

Section 5.9 of R.O.D. manual pcm D. Transient Flux Redistribution Allowance Section 5.7 of R.O.D. manual Present SDM (A) - (B) - (C) - (D) ( )pcm _____ _____ _____ .3 OP/0/A/6100/006Shutdown Margin - Untrippable / Misaligned RCCA(s) - Modes 1 & 2 Page 7 of 7 3.3.3 Sign below to document performance: Performed by_________________________Date/Time:______/______

3.3.4 Ensure that an independent calculation per this enclosure has been separately performed NOTE: Independently performed calculations may NOT yield exactly the same results due to data taken at different times. The CRS and Reactor Engineering may be contacted if questions arise.

3.3.5 Verify that both performances of this enclosure yield equivalent results 3.3.6 Perform one of the following based on results of the calculations:

3.3.6.1 IF present SDM is 1300 pcm per the applicable Technical Specification via COLR, notify the CRS that present SDM is acceptable. OR 3.3.6.2 IF present SDM is < 1300 pcm notify the CRS to apply the applicable Technical Specification Action.

_____ _____ _____ _____ _____

Catawba Nuclear Station Admin. JPM A.1

-2 R June 201 7 NRC Exam PAGE 1 OF 11 JPM A.1-2R RO

Catawba Nuclear Station Admin. JPM A.1

-2 R June 201 7 NRC Exam PAGE 2 OF 11 EVALUATION SHEET Task: Calculate Boric Acid and Water Addition to FWST Alternate Path:

N/A Facility JPM #:

2016 NRC Exam JPM A.1

-2R Safety Function:

N/A K/A 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Importance:

4.3 / 4.4 CFR: 41.10 / 4 3.5 / 45.2 / 45.6 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

OP/1/A/6200/0 14 (Refueling Water System

), Enclosure 4.4 (FWST Makeup From Blender)

Task Standard:

Applicant determines required boric acid addition of 368.8 gallons (368-370 acceptable) and reactor makeup water addition of 3402.2 gallons (3401-3403 acceptable) to complete the required FWST makeup. Validation Time:

1 5 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 11 Catawba Nuclear Station Admin. JPM A.1

-2R June 201 7 NRC Exam PAGE 3 OF 11 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

It has been discovered that an incorrect valve lineup decreased FWST level to 9 5%. Current conditions as follows:

o The valve lineup has been immediately corrected securing the level decrease. o Current FWST level is 95

%. o Current FWST boron concentration is 2740 ppm B. o Unit 1 BAT boron concentration is 7500 ppmB. o Unit 2 BAT boron concentration is 7300 ppmB

. o Unit 1 RMWST boron concentration is 4 ppmB

. INITIATING CUES:

Using OP/1/A/6200/014 (Refueling Water System), determine the required amount of Boric Acid and RMWST water necessary to perform an FWST makeup from the blender as follows: Consider any initial conditions complete.

Final FWST level of 9 6% at 2720 ppmB

. S. Jackson (Primary Chemistry) has been notified and directed use of the Unit 1 BAT. Concurrent Verification is waived for this task.

Boric Acid RMWST Water

EXAMINER NOTE

After reading cue, provide applicant with a copy of OP/1/A/6200/014

.

Catawba Nuclear Station Admin. JPM A.1

-2 R June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 OF 11 START TIME: _______

STEP / STANDARD SAT / UNSAT NOTE: To prevent an inadvertent reduction in the shutdown margin during NC fill evolutions, makeup to the FWST shall be performed with a water source having a Boron concentration which is greater than or equal to the required NC system Boron concentration.

STEP 1: 3.1 Notify Chemistry that the following Boric Acid Tank will be used for Tech Spec blending calculations {PIP 91

- 0449}:

Person notified _______________________

_____________ Boric Acid Tank #1

_____________ Boric Acid Tank #2 STANDARD: From the cue, applicant records S. Jackson as Chemistry person notified and checks Boric Acid Tank #1.

COMMENTS:

___ SAT ___ UNSAT STEP 2: 3.2 Document current boron concentration in the Boric Acid Tank as specified by Chemistry in Step 3.1 {PIP 91

- 0449}: _____________ ppmB STANDARD: From the cue, applicant determines that BAT #1 will be used and records 7500 ppmB. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 OF 11 NOTE: The final boron concentration used in the next step shall comply with COLR requirements for the current mode of operation.

STEP 3: 3.3 Determine the boron concentration of the makeup water to the FWST (C f) to attain the final boron concentration, C FW. 3.3.1 Initial volume of FWST _______ = V

i. STANDARD: Using supplied information applicant enters the initial level of 37 3 , 875 gallons. COMMENTS:

___ SAT ___ UNSAT STEP 4: 3.3.2 Final volume of FWST after makeup _______ = V FW. STANDARD: Using supplied information applicant enters the final level of 37 7 , 646 gallons. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 OF 11 STEP 5: 3.3.3 Compute the total gallons of makeup water to be added to the FWST _________ = V f.. STANDARD: Applicant calculates, and records, makeup volume of 3, 771 gallons. 377, 646 - 37 3 , 875 = 3, 771 Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 6: 3.3.4 Initial boron concentration of water in the FWST

______ = C

i. STANDARD: From the cue, applicant records initial FWST boron concentration of 2740 ppmB.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 OF 11 STEP 7: 3.3.5 Solve for the desired makeup water boron concentration, Cf.

C f = C FW V FW - C i V i C f = __________

V f STANDARD: Applicant calculates desired concentration of makeup water to be 737.1 ppmB Cf = (2720 x 377 646) - (2740 x 37 3875) / 3 771 = 737.1 ppmB (737-738 ppmB acceptable)

Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT STEP 8: 3.4 Determine the amount of boric acid and reactor makeup water to add as follows:

3.4.1 Boron Concentration of water in BAT _________ = C

1. STANDARD: From the cue, applicant records Unit 1 BAT boron concentration of 7500 ppmB. COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 OF 11 STEP 9: 3.4.2 Boron concentration of water in RMWST

__________ = C 2.: STANDARD: From the cue, applicant records Unit 1 RMWST boron concentration of 4 ppmB. COMMENTS: ___ SAT ___ UNSAT STEP 10: 3.4.3 Total gallons of makeup water to be added to FWST

________ = V f from Step 3.3.3.:

STANDARD: Applicant records total makeup volume of 3,771 from step 3.3.3.

COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 9 OF 11 STEP 11: 3.4.4 Solve for the amount of boric acid to be added (V

1) using C f obtained in Step 3.3.5.

V 1 = V f (C f - C 2)

V 1 = ___________

C 1 - C 2 STANDARD: Applicant calculates boric acid total of 368.8 gallons.

V 1 = 3771 (737.1 - 4) / (7500

- 4) = 368.8 (368-370 acceptable

) Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT STEP 12: 3.4.5 If V 1 is negative, contact the OWPM Staff for instruction on adjusting the boron concentration in the FWST.

STANDARD: Applicant determines that this step does not apply.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1

-2 R June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 10 OF 11 STEP 13: 3.4.6 Solve for the amount of RMWST water to be added (V 2). V 2 = V f - V 1 V 2 = _________ gal.

STANDARD: Applicant calculates required RMWST water to be 3402.2 gallons.

3771 - 368.8 = 3402.2 (3401-3403 acceptable

) Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you. INITIAL CONDITIONS:

It has been discovered that an incorrect valve lineup decreased FWST level to 95%. Current conditions as follows:

o The valve lineup has been immediately corrected securing the level decrease. o Current FWST level is 95%

. o Current FWST boron concentration is 2740 ppmB

. o Unit 1 BAT boron concentration is 7500 ppmB

. o Unit 2 BAT boron concentration is 7300 ppmB

. o Unit 1 RMWST boron concentration is 4 ppmB

. INITIATING CUES:

Using OP/1

/A/6200/014 (Refueling Water System), determine the required amount of Boric Acid and RMWST water necessary to perform an FWST makeup from the blender as follows

Consider any initial conditions complete.

Final FWST level of 96% at 2720 ppmB.

S. Jackson (Primary Chemistry) has been notified and directed use of the Unit 1 BAT. Concurrent Verification is waived for this task.

Boric Acid RMWST Water

Catawba Nuclear Station Admin. JPM A.1

-2S June 201 7 NRC Exam PAGE 1 OF 13 JPM A.1-2S S RO

Catawba Nuclear Station Admin. JPM A.1

-2S June 201 7 NRC Exam PAGE 2 OF 13 EVALUATION SHEET Task: Calculate Boric Acid and Water Addition to FWST and determine Tech Spec actions.

Alternate Path: N/A Facility JPM #:

2016 NRC Exam JPM A.1

-2S Safety Function:

N/A K/A 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Importance:

4.3 / 4.4 CFR: 41.10 / 4 3.5 / 45.2 / 45.6 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

OP/1/A/6200/0 14 (Refueling Water System

), Enclosure 4.4 (FWST Makeup From Blender)

Task Standard:

Applicant determines required boric acid addition of 368.8 gallons (368

-370 acceptable) and reactor makeup water addition of 3402.2 gallons (3401

-3403 acceptable) to complete the required FWST makeup and determines the following SLC/TS required LCO entries

1000 - SLC 16-9.12 Condition D and TS 3.5.4 Condition B, 1100

- SLC 16-9.12 Condition D and TS 3.5.4 Condition B and Condition C.

Validation Time:

3 0 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 13 Catawba Nuclear Station Admin. JPM A.1

-2S June 201 7 NRC Exam PAGE 3 OF 13 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is in Mode 3 during a refueling outage. The following events have occurred at the given times:

0945: 1AD-9 B/8 "FWST AT MAKEUP LEVEL" annunciator received. Operators are dispatched to investigate decreasing Unit 1 FWST level.

100 0: Unit 1 BOP reports that FWST volume is 377,536.9 gallons.

1015: An improperly executed FW system clearance is discovered and determined to be the cause of FWST level decrease.

Current conditions are as follows:

o The valve lineup has been immediately corrected securing the level decrease

. o Current FWST level is 9 5%. o Current FWST boron concentration is 2740 ppm B. o Unit 1 BAT boron concentration is 7500 ppmB

. o Unit 2 BAT boron concentration is 7300 ppmB

. o Unit 1 RMWST boron concentration is 4 ppmB

. o Total Blender Makeup flowrate = 90 gpm INITIATING CUES:

Using OP/1

/A/6200/014 (Refueling Water System), perform an FWST makeup from the blender as follows:

Consider any initial conditions complete.

Final FWST level of 96% at 2720 ppmB.

S. Jackson (Primary Chemistry) has been notified and directed use of the Unit 1 BAT. Concurrent Verification is waived for this task.

Boric Acid RMWST Water

1. Assuming the required makeup begins at time 1030, determine which Active SLC and TS LCO entries (if any) will be required at 1000 and 1100

. 1000:

1100:

PAGE 4 0F 13 Catawba Nuclear Station Admin. JPM A.1

-2S June 201 7 NRC Exam PAGE 4 OF 13 EXAMINER NOTE

After reading cue, provide applicant with a copy of OP/1/A/6200/014

.

Catawba Nuclear Station Admin. JPM A.1-2S June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 OF 13 QUESTION 1 START TIME: _______

STEP / STANDARD SAT / UNSAT NOTE: To prevent an inadvertent reduction in the shutdown margin during NC fill evolutions, makeup to the FWST shall be performed with a water source having a Boron concentration which is greater than or equal to the required NC system Boron concentration.

STEP 1: 3.1 Notify Chemistry that the following Boric Acid Tank will be used for Tech Spec blending calculations {PIP 91

- 0449}:

Person notified _______________________

_____________ Boric Acid Tank #1 _____________ Boric Acid Tank #2 STANDARD: From the cue, applicant records S. Jackson as Chemistry person notified and checks Boric Acid Tank #1.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1-2S June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 OF 13 STEP 2: 3.2 Document current boron concentration in the Boric Acid Tank as specified by Chemistry in Step 3.1 {PIP 91

- 0449}: _____________ ppmB STANDARD: From the cue, applicant determines that BAT #1 will be used and records 7500 ppmB. COMMENTS:

___ SAT

___ UNSAT NOTE The final boron concentration used in the next step shall comply with COLR requirements for the current mode of operation.

STEP 3: 3.3 Determine the boron concentration of the makeup water to the FWST (C f) to attain the final boron concentration, C FW.

3.3.1 Initial volume of FWST _______ = V

i. STANDARD: Using supplied information applicant enters the initial level of 37 3 , 875 gallons. COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1-2S June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 OF 13 STEP 4: 3.3.2 Final volume of FWST after makeup _______ = V FW. STANDARD: Using supplied information applicant enters the final level of 37 7 , 646 gallons. COMMENTS:

___ SAT

___ UNSAT STEP 5: 3.3.3 Compute the total gallons of makeup water to be added to the FWST

_________ = V f.. STANDARD: Applicant calculates, and records, makeup volume of 3, 771 gallons. 377, 6 46 - 37 3 , 875 = 3, 771 Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1-2S June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 OF 13 STEP 6: 3.3.4 Initial boron concentration of water in the FWST

______ = C

i. STANDARD: From the cue, applicant records initial FWST boron concentration of 2740 ppmB.

COMMENTS:

___ SAT

___ UNSAT STEP 7: 3.3.5 Solve for the desired makeup water boron concentration, Cf.

C f = C FW V FW - C i V i C f = __________

V f STANDARD: Applicant calculates desired concentration of makeup water to be 737.1 ppmB Cf = (2720 x 377 646) - (2740 x 37 3875) / 3 771 = 737.1 ppmB (737-738 ppmB acceptable)

Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1-2S June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 9 OF 13 STEP 8: 3.4 Determine the amount of boric acid and reactor makeup water to add as follows:

3.4.1 Boron Concentration of water in BAT _________ = C

1. STANDARD: From the cue, applicant records Unit 1 BAT boron concentration of 7500 ppmB. COMMENTS:

___ SAT

___ UNSAT STEP 9: 3.4.2 Boron concentration of water in RMWST

__________ = C 2.: STANDARD: From the cue, applicant records Unit 1 RMWST boron concentration of 4 ppmB. COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1-2S June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 10 OF 13 STEP 10: 3.4.3 Total gallons of makeup water to be added to FWST

________ = V f from Step 3.3.3.

STANDARD: Applicant records total makeup volume of 3, 771 from step 3.3.3.

COMMENTS: ___ SAT ___ UNSAT STEP 11: 3.4.4 Solve for the amount of boric acid to be added (V

1) using C f obtained in Step 3.3.5.

V 1 = V f (C f - C 2)

V 1 = ___________

C 1 - C 2 STANDARD: Applicant calculates boric acid total of 368.8 gallons.

V 1 = 3771 (737.1

- 4) / (7500

- 4) = 368.8 (368

-370 acceptable)

Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1-2S June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 11 OF 13 STEP 12: 3.4.5 If V 1 is negative, contact the OWPM Staff for instruction on adjusting the boron concentration in the FWST.

STANDARD: Applicant determines that this step does not apply.

COMMENTS: ___ SAT ___ UNSAT STEP 13: 3.4.6 Solve for the amount of RMWST water to be added (V 2).

V 2 = V f - V 1 V 2 = _________ gal.

STANDARD: Applicant calculates required RMWST water to be 3402.2 gallons.

3771 - 368.8 = 3402.2 (3401

-3403 acceptable)

Examiner Note: This step is critical to ensure accurate result for final calculation.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.1-2S June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 12 OF 13 QUESTION 2 1000: SLC 16

-9.12 Condition D

/ LCO 3.5.4, Condition B The minimum volume requirement of SLC 16-9.12 (Boration Systems Borated Water Sources

- Operating) is not met. Therefore, Condition D (RWST non-functional) entry will be required. The Required Action associated with this condition is to declare the RWST inoperable and enter the applicable conditions of TS 3.5.4 Immediately.

T he 377,537 gallons) is not met. Therefore, TS 3.5.4, Condition B (RWST inoperable for reasons other than Condition A) entry will be required. The Required Action associated with this condition is to Restore RWST to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

NOTE: The applicant may also determine SLC 16

-9.8 (Boration Systems Flow Paths

- Operating), Condition A (One required Boration System Flow Path non-functional) applies if familiar with the associated plant testing procedure. This procedure requires the FWST to be functional in order to meet the acceptance criteria. However , the surveillance requirements of this SLC do not list this particular requirement so this determination will not be critical to this task.

1100: SLC 16-9.12 Condition D

/ LCO 3.5.4, Conditions B & C With an initial volume of 37 3 , 875 gallons and an available makeup rate of 90 gpm (beginning at 1030), the total FWST volume at 1100 will be 376, 575 gallons which remains below the required minimum of SR 3.5.4.2.

37 3 , 875 (initial volume) + {90 gpm x 30 min} = 376, 575 gallons Therefore, SLC 16-9.12 Condition D and TS 3.5.4 Condition B will remain in effect AND TS 3.5.4 Condition C (Required Action and associated Completion Time not met) must be entered.

Examiner Note: Determination of SLC 16

-9.12 and TS 3.5.4 required actions (only) are critical to ensure proper actions are entered to address th is adverse condition.

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit 1 is in Mode 3 during a refueling outage. The following events have occurred at the given times:

0945: 1AD-9 B/8 "FWST AT MAKEUP LEVEL" annunciator received. Operators are dispatched to investigate decreasing Unit 1 FWST level.

1000: Unit 1 BOP reports that FWST volume is 377,536.9 gallons.

1015: An improperly executed FW system clearance is discovered and determined to be the cause of FWST level decrease.

Current conditions are as follows:

o The valve lineup has been immediately corrected securing the level decrease.

o Current FWST level is 95%.

o Current FWST boron concentration is 2740 ppmB.

o Unit 1 BAT boron concentration is 7500 ppmB.

o Unit 2 BAT boron concentration is 7300 ppmB.

o Unit 1 RMWST boron concentration is 4 ppm B. o Total Blender Makeup flowrate = 90 gpm INITIATING CUES:

1. Using OP/1/A/6200/014 (Refueling Water System), determine the required amount of Boric Acid and RMWST water necessary to perform an FWST makeup from the blender as follows:

Consider any initial conditions complete.

Final FWST level of 96% at 2720 ppmB.

S. Jackson (Primary Chemistry) has been notified and directed use of the Unit 1 BAT. Concurrent Verification is waived for this task.

Boric Acid RMWST Water

2. Assuming the required makeup begins at time 1030, determine which Active SLC and TS LCO entries (if any) will be required at 1000 and 1100.

1000: 1100:

Catawba Nuclear Station Admin. JPM A.

2 June 2017 NRC Exam PAGE 1 OF 7 JPM A.2 RO / SRO

Catawba Nuclear Station Admin. JPM A.

2 June 2017 NRC Exam PAGE 2 OF 7 EVALUATION SHEET Task: Use Flow Diagrams

, Electrical Prints and Load Lists To Determine Leak Isolation Boundary Alternate Path:

N/A Facility JPM #:

2012 NRC Exam Safety Function:

N/A K/A 2.2.4 1 Ability to obtain and interpret station electrical and mechanical drawings.

Importance:

3.5 / 3.9 CFR: 41.1 0 / 4 5.12 / 45.1 3 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

Flow diagram s of the CM system (CN 15 90-1.5, CN 1590

-1.7), Load List for 1MXB, 6.9 KV bus one line electrical drawings Task Standard:

Mechanical and electrical isolation boundary determined for work on 1CM-327 per JPM A.

2 key. Validation Time:

30 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish:

__________ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 7 Catawba Nuclear Station Admin. JPM A.

2 June 2017 NRC Exam PAGE 3 OF 7 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The 1B Condensate Booster Pump has been shutdown in accordance with OP/1/A/6250/001 (Condensate and Feedwater System) and is to be tagged out for removal and replacement of 1CM

-327 (1B Condensate Booster Pump Suction Header Relief Valve).

INITIATING CUES:

The SM has directed you to use the provided materials to determine the required boundary for isolation for this work.

You are to use the valves closest to the work being performed for isolation to minimize drain and fill time.

Identify components, including the required position, for creation of a Clearance for replacement of 1CM

-327, including:

o Mechanical isolations o Electrical isolations o Applicable Vent and Drain path Record your answer in the table on the following page.

EXAMINER NOTE

After reading cue, provide applicant with a cop y of CM flow diagram s (CN 15 90-1.5 and CN 1590

-1.7), load list for 1MXB, and 6.9 KV Switchgear one line diagrams (CN 1702-1.1, CN 1702

-1.2, CN 1702

-1.3, and CN 1702

-1.4).

Catawba Nuclear Station Admin. JPM A.

2 June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 OF 7 START TIME: _______

STEP 1: Determine clearance boundary for 1CM

-327 boundary

.

STANDARD: Applicant identifies clearance boundary per table on the next page.

Note that only one vent valve or one drain valve is needed to meet the critical step.

Examiner Note: This step is critical to be able to correctly isolate the 1B Condensate Booster Pump for replacement of 1CM-327. COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.

2 June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 OF 7 Component Position 1TB-11 Racked Out 1CM-93 Closed 1CM-94 Closed 1CM-96 Closed 1CM-97 Closed 1CM-58 Closed 1CM-306 Closed 1MXB F01D Off/Open 1MXB-R01B Off/Open *1CM-334 (Drain) Open *1CM-335 (Drain) Open *1CM-424 (Drain)

Open *1CM-916 (Vent)

Open *1CM-330 (Vent)

Open *1CM-917 (Vent)

Open STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task.

To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The 1B Condensate Booster Pump has been shutdown in accordance with OP/1/A/6250/001 (Condensate and Feedwater System) and is to be tagged

out for removal and replacement of 1CM

-327 (1B Condensate Booster Pump Suction Header Relief Valve).

INITIATING CUES:

The SM has directed you to use the provided materials to determine the required boundary for isolation for this work.

You are to use the valves closest to the work being performed for isolation to minimize drain and fill time.

Identify components, including the required position, for creation of a Clearance for replacement of 1CM

-327, including:

o Mechanical isolations o Electrical isolations o Applicable Vent and Drain path Record your answer in the table on the following page.

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

Answer Component Position Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam PAGE 1 OF 14 JPM A.3 R RO

Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam PAGE 2 OF 14 EVALUATION SHEET Task: Calculate Total RL Discharge Flow Alternate Path:

N/A Facility JPM #:

WL-002 Safety Function: 9 K/A 2.3.11 Ability to control radiation releases Importance:

3.8 / 4.3 CFR: 41.11 / 4 3.4 / 45.10 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination)

Task Standard:

Total RL Discharge Flow calculated to be 48,608 gpm (48,608 to 5 0 , 179 gpm acceptable range)

Validation Time:

22 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 14 Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam PAGE 3 OF 14 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

An LWR is in progress from Waste Monitor Tank "A".

The RL discharge header flow instrumentation is inoperable.

PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination) is in progress. INITIATING CUES:

The CRS directs you to calculate and record the total RL discharge flow per Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT/0/A/4250/011.

The following plant indications are noted:

Unit 1 Power 100% Unit 2 Power NO Mode 0RLP5030 (RL Discharge Pressure) 67 psig 0RNP7380 (Lake Elevation) 568 feet C1P5856 (RN Calculate Total Flow)

Out of service C1P5854 (RN Train A Calculated Total Flow) 14130 gpm C1P5855 (RN Train B Calculated Total Flow) 4840 gpm C1P5853 (Unit 1 Cooling Tower Evaporation) 12260 gpm RL Pumps A and B are in service RN discharge is aligned to RL discharge header OAC Databook is not available EXAMINER NOTE

After reading cue, provide applicant with a copy of PT/0/A/4250/011 Enclosures 13.2 and 13.7

.

Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 OF 14 START TIME: _______

STEP / STANDARD SAT / UNSAT STEP 1: 1.1 Obtain Total RL Supply (A) as follows

1.1.1 IF 0RLP5030 (Conventional LP Service Wtr Press) is NOT available contact engineering for optional indications and elevation corrections.

STANDARD: Applicant determines per initiating cue that this step is not applicable.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 OF 14 STEP 2: 1.1.2 Perform the following calculations to obtain Total Discharge Head:

STANDARD: Applicant Calculates Total Discharge Head of 167.6 feet. (167

-16 8 Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 OF 14 STEP 3: 1.1.3 Using Total Discharge Head from Step 1.1.2 obtain the RL Pump Flow value using one of the following:

Enclosure 13.7 OR OAC Databook in "Secondary Systems Databook Calcs" using "RL Total Discharge Head vs. RL Pump Flow Rate".

STANDARD: Applicant determines that Enclosure 13.7 should be used to determine RL pump flow value since the OAC Databook is not available per th e initiating cue. Applicant determines RL pump flow to be 34,036 gpm.

(34,036 - 35,244 gpm Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 OF 14 STEP 4: 1.1.4 Once RL Pump Flow value is obtained, calculate Total RL Supply based on number of RL pumps in operation:

STANDARD: Applicant calculates Total RL Supply to be 68,072 gpm. (68,072 - 70,488 gpm Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 5: 1.1.5 Enter Total RL Supply (A) value in Step 1.4.

STANDARD: Applicant records value for (A) in Step 1.4.

COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 OF 14 STEP 6: 1.2 IF RN discharge is aligned to the RL discharge header, obtain Total RN Flow (B) as follows:

1.2.1 IF OAC point C1P5856 (RN Calculated Total Flow) is available, perform the following:

STANDARD: Applicant determines per initiating cue that OAC point C1P5856 is not available and that this step is not applicable.

COMMENTS:

___ SAT ___ UNSAT STEP 7: 1.2.2 IF OAC points C1P5854 (RN Train A Calculated Total Flow) AND C1P5855 (RN Train B Calculated Total Flow) are available, perform the following to obtain total RN flow:

STANDARD: Applicant records values for RN trains A and B calculated flow from values given in the initiating cue.

COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 9 OF 14 STEP 8: 1.2.3 IF either C1P5854 (RN Train A Calculated Total Flow)

OR C1P5855 (RN Train B Calculated Total Flow) is NOT available, perform the following to obtain total RN flow:

STANDARD: Applicant determines that this step is not applicable.

COMMENTS: ___ SAT ___ UNSAT STEP 9: 1.2.4 Perform the following calculations to obtain Total RN Flow:

STANDARD: Applicant calculates Total RN Flow (B) to be 18,970 gpm.

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 10 OF 14 STEP 10: 1.2.5 Enter Total RN Flow (B) in Step 1.4.

STANDARD: Applicant records value in Step 1.4.

COMMENTS:

___ SAT ___ UNSAT NOTE: Normal Cooling Tower evaporation loss @ 100% power is 9,000 to 14,000 gpm/unit.

STEP 1 1: 1.3 Obtain Total Cooling Tower Evaporation (C) as follows:

1.3.1 IF a Unit 1 NC Pump is NOT inservice AND Unit 1 is in Mode 5, 6, or No Mode, enter 0 for Unit 1 Cooling Tower Evaporation in Step 1.3.3.

STANDARD: Applicant determines that this step is not applicable

. COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 11 OF 14 STEP 12: 1.3.2 IF a Unit 2 NC Pump is NOT inservice AND Unit 2 is in Mode 5, 6, or No Mode, enter 0 for Unit 2 Cooling Tower Evaporation in Step 1.3.3.

STANDARD: Applicant determines per initiating cue that Unit 2 is in No Mode and enters 0 for Unit 2 evaporation in Step 1.3.3.

COMMENTS: ___ SAT

___ UNSAT STEP 1 3: 1.3.3 Calculate Cooling Tower Total Evaporation as follows:

STANDARD: Applicant calculates Total Evaporation (C) to be 12,260 gpm

. Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 12 OF 14 STEP 14: 1.3.4 Enter Total Evaporation (C) in Step 1.4.

STANDARD: Applicant enters value for Total Evaporation (C) in Step 1.4.

COMMENTS: ___ SAT

___ UNSAT STEP 1 5: 1.4 Perform the following to obtain Calculated Total RL Disch Flow: STANDARD: Applicant calculates the Calculated Total RL Disch Flow to be 74,782 gpm. (74,782 - 77,198 gpm Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

Catawba Nuclear Station Admin. JPM A.3 R June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 13 OF 14 NOTE: Due to problems with current RL instrumentation (PIP C 4540) and discrepancies between calculated and OAC RL flow (PIP C 1399), a safety factor is applied to the Calculated Total RL Disch Flow of Step 1.4 to ensure conservative Total RL Disch Flow rates are used for dilution purposes. This is a temporary conservative action for use till RL discharge flow instrumentation problems are resolved.

STEP 16: 1.5 Apply dilution safety factor to obtain Total RL Discharge Flow from the Calculated Total RL Discharge Flow from Step 1.4 as follows:

STANDARD: Applicant calculates Total RL Disch Flow to be 48,608 gpm. (48,608 - 50 ,1 79 gpm Acceptable)

Examiner Note: This step is critical to correctly determine Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIO NS: An LWR is in progress from Waste Monitor Tank "A".

The RL discharge header flow instrumentation is inoperable.

PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination) is in progress. INITIATING CUES:

The CRS directs you to calculate and record the total RL discharge flow per Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT/0/A/4250/011.

The following plant indications are noted:

Unit 1 Power 100% Unit 2 Power NO Mode 0RLP5030 (RL Discharge Pressure) 67 psig 0RNP7380 (Lake Elevation) 568 feet C1P5856 (RN Calculate Total Flow)

Out of service C1P5854 (RN Train A Calculated Total Flow) 14130 gpm C1P5855 (RN Train B Calculated Total Flow) 4840 gpm C1P5853 (Unit 1 Cooling Tower Evaporation) 12260 gpm RL Pumps A and B are in service RN discharge is aligned to RL discharge header OAC Databook is not available

Total RL Discharge Flow (Step 1.5): _____________ gpm

Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam PAGE 1 OF 15 JPM A.3 S S RO

Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam PAGE 2 OF 15 EVALUATION SHEET Task: Calculate Total RL Discharge Flow Alternate Path:

N/A Facility JPM #:

WL-00 1 Safety Function: N/A K/A 2.3.11 Ability to control radiation releases

. Importance:

3.8 / 4.3 CFR: 41.11 / 4 3.4 / 45.10 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

PT/0/A/4250/011 (RL Temperature and Discharge Flow Determination)

Task Standard:

Total RL Discharge Flow calculated to be 48,608 gpm (48,608 to 5 0 , 179 gpm acceptable range) and determination that sufficient dilution flow exists for LWR #2017025 approv al. Validation Time:

30 minutes Time Critical:

Yes No X Applicant:

Time Start: ______

____ NAME___________________________

Docket #_______________

Time Finish: ________

__ Performance Rating:

SAT ____ UNSAT ____

Performance Time

_____ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 15 Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam PAGE 3 OF 15 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The RL discharge header flow instrumentation is inoperable.

An LWR package has been delivered to the control room for approval.

INITIATING CUES:

You are directed to calculate and record the total RL discharge flow per Enclosure 13.2 (Total Discharge Flow Calculation Sheet) of PT/0/A/4250/011

and determine whether sufficient dilution flow exists to approve the LWR

. The following plant indications are noted:

Unit 1 Power 100% Unit 2 Power NO Mode 0RLP5030 (RL Discharge Pressure) 67 psig 0RNP7380 (Lake Elevation) 568 feet C1P5856 (RN Calculate Total Flow)

Out of service C1P5854 (RN Train A Calculated Total Flow) 14130 gpm C1P5855 (RN Train B Calculated Total Flow) 4840 gpm C1P5853 (Unit 1 Cooling Tower Evaporation) 12260 gpm RL Pumps A and B are in service RN discharge is aligned to RL discharge header OAC Databook is not available EXAMINER NOTE

After reading cue, provide applicant with a copy of PT/0/A/4250/011 Enclosures 13.2 and 13.7 and copy of LWR #2017025

.

Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 OF 15 START TIME: _______

STEP / STANDARD SAT / UNSAT STEP 1: 1.1 Obtain Total RL Supply (A) as follows

1.1.1 IF 0RLP5030 (Conventional LP Service Wtr Press) is NOT available contact engineering for optional indications and elevation corrections.

STANDARD: Applicant determines per initiating cue that this step is not applicable.

COMMENTS:

___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 OF 15 STEP 2: 1.1.2 Perform the following calculations to obtain Total Discharge Head:

STANDARD: Applicant Calculates Total Discharge Head of 167.6 feet. (167

-168 Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 6 OF 15 STEP 3: 1.1.3 Using Total Discharge Head from Step 1.1.2 obtain the RL Pump Flow value using one of the following:

Enclosure 13.7 OR OAC Databook in "Secondary Systems Databook Calcs" using "RL Total Discharge Head vs. RL Pump Flow Rate".

STANDARD: Applicant determines that Enclosure 13.7 should be used to determine RL pump flow value since the OAC Databook is not available per the initiating cue. Applicant determines RL pump flow to be 34,036 gpm. (34,036 - 35,244 gpm Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS: CRITICAL STEP ___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 7 OF 15 STEP 4: 1.1.4 Once RL Pump Flow value is obtained, calculate Total RL Supply based on number of RL pumps in operation:

STANDARD: Applicant calculates Total RL Supply to be 68,072 gpm. (68,072

- 70,488 gpm Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

CRITICAL STEP ___ SAT ___ UNSAT STEP 5: 1.1.5 Enter Total RL Supply (A) value in Step 1.4.

STANDARD: Applicant records value for (A) in Step 1.4. COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 8 OF 15 STEP 6: 1.2 IF RN discharge is aligned to the RL discharge header, obtain Total RN Flow (B) as follows:

1.2.1 IF OAC point C1P5856 (RN Calculated Total Flow) is available, perform the following:

STANDARD: Applicant determines per initiating cue that OAC point C1P5856 is not available and that this step is not applicable.

COMMENTS:

___ SAT ___ UNSAT STEP 7: 1.2.2 IF OAC points C1P5854 (RN Train A Calculated Total Flow) AND C1P5855 (RN Train B Calculated Total Flow) are available, perform the following to obtain total RN flow:

STANDARD: Applicant records values for RN trains A and B calculated flow from values given in the initiating cue.

COMMENTS:

___ SAT ___ UNSAT Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 9 OF 15 STEP 8: 1.2.3 IF either C1P5854 (RN Train A Calculated Total Flow)

OR C1P5855 (RN Train B Calculated Total Flow) is NOT available, perform the following to obtain total RN flow:

STANDARD: Applicant determines that this step is not applicable.

COMMENTS: ___ SAT ___ UNSAT STEP 9: 1.2.4 Perform the following calculations to obtain Total RN Flow:

STANDARD: Applicant calculates Total RN Flow (B) to be 18,970 gpm.

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS: CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 10 OF 15 STEP 10: 1.2.5 Enter Total RN Flow (B) in Step 1.4.

STANDARD: Applicant records value in Step 1.4.

COMMENTS:

___ SAT ___ UNSAT NOTE: Normal Cooling Tower evaporation loss @ 100% power is 9,000 to 14,000 gpm/unit.

STEP 11: 1.3 Obtain Total Cooling Tower Evaporation (C) as follows:

1.3.1 IF a Unit 1 NC Pump is NOT inservice AND Unit 1 is in Mode 5, 6, or No Mode, enter 0 for Unit 1 Cooling Tower Evaporation in Step 1.3.3.

STANDARD: Applicant determines that this step is not applicable.

COMMENTS: ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 11 OF 15 STEP 12: 1.3.2 IF a Unit 2 NC Pump is NOT inservice AND Unit 2 is in Mode 5, 6, or No Mode, enter 0 for Unit 2 Cooling Tower Evaporation in Step 1.3.3.

STANDARD: Applicant determines per initiating cue that Unit 2 is in No Mode and enters 0 for Unit 2 evaporation in Step 1.3.3.

COMMENTS: ___ SAT

___ UNSAT STEP 13: 1.3.3 Calculate Cooling Tower Total Evaporation as follows:

STANDARD: Applicant calculates Total Evaporation (C) to be 12,260 gpm.

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 12 OF 15 STEP 14: 1.3.4 Enter Total Evaporation (C) in Step 1.4.

STANDARD: Applicant enters value for Total Evaporation (C) in Step 1.4.

COMMENTS: ___ SAT

___ UNSAT STEP 15: 1.4 Perform the following to obtain Calculated Total RL Disch Flow: STANDARD: Applicant calculates the Calculated Total RL Disch Flow to be 74,782 gpm. (74,782

- 77,198 gpm Acceptable)

Examiner Note: This step is critical to be able to correctly calculate Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 13 OF 15 NOTE: Due to problems with current RL instrumentation (PIP C 4540) and discrepancies between calculated and OAC RL flow (PIP C 1399), a safety factor is applied to the Calculated Total RL Disch Flow of Step 1.4 to ensure conservative Total RL Disch Flow rates are used for dilution purposes. This is a temporary conservative action for use till RL discharge flow instrumentation problems are resolved.

STEP 16: 1.5 Apply dilution safety factor to obtain Total RL Discharge Flow from the Calculated Total RL Discharge Flow from Step 1.4 as follows:

STANDARD: Applicant calculates Total RL Disch Flow to be 48,608 gpm. (48,608

- 50,179 gpm Acceptable)

Examiner Note: This step is critical to correctly determine Total RL Discharge Flow to meet the JPM standard.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT

Catawba Nuclear Station Admin. JPM A.3 S June 2017 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 14 OF 15 STEP 17: Determine whether LWR #2017025 should be approved.

STANDARD: Applicant determines that the RL Low Flow Interlock would be set for 45,000 gpm and that sufficient dilution flow exists to approve the LWR.

Examiner Note: This step is critical to correctly determine that Total RL Flow is greater than the RL Low Flow Interlock

Setpoint and that sufficient dilution flow exists to approve the LWR.

COMMENTS:

END OF TASK CRITICAL STEP ___ SAT

___ UNSAT

STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

The RL discharge header flow instrumentation is inoperable.

An LWR package has been delivered to the control room for approval.

INITIATING CUES:

You are directed to calculate and record the total RL discharge flow per 3.2 (Total Discharge Flow Calculation Sheet) of PT/0/A/4250/011 and determine whether sufficient dilution flow exists to approve the LWR.

The following plant indications are noted:

Unit 1 Power 100% Unit 2 Power NO Mode 0RLP5030 (RL Discharge Pressure) 67 psig 0RNP7380 (Lake Elevation) 568 feet C1P5856 (RN Calculate Total Flow)

Out of service C1P5854 (RN Train A Calculated Total Flow) 14130 gpm C1P5855 (RN Train B Calculated Total Flow) 4840 gpm C1P5853 (Unit 1 Cooling Tower Evaporation) 12260 gpm RL Pumps A and B are in service RN discharge is aligned to RL discharge header OAC Databook is not available

Total RL Discharge Flow (Step 1.5): _____________ gpm

Sufficient dilution flow for LWR #2017025 approv al? (YES/NO) _____________

3.2 PT/0/A/4250/011Total Discharge Flow Calculation Sheet Page 1 of 3 1.Procedure 1.1 Obtain Total RL Supply (A) as follows:

1.1.1 IF 0RLP5030 (Conventional LP Service Wtr Press) is NOT available contact engineering for optional indicati ons and elevation corrections. Engineer contacted: _____________________________ NOTE: Engineering specified optional indications and elevation corrections may be substituted for 0RLP5030 (Conventional LP Service Wtr Pre ss) and the 3.9 psi elevation correction of following step to obtain Total Discharge Head.

1.1.2 Perform the following calculations to obtain Total Discharge Head:

psi 3.9 0RLP5030 Pressure Disch RL+=ig________ps psi 3.9 _________ Pressure Disch RL=+=Lake Elevation = ______________ 0RNP7380 (Lake Wylie Level) or obtained from hydro central per Step 1.1.4.2 of Enclosure 13.1 or

Step 1.1.2.2 of Enclosure 13.8.

t_________f)________ft

-(571.75ft/psig) 2.311 x _____psig (_________

=+ HeadDisch Total Elev Lake PressureDisch RL 1.1.3 Using Total Discharge Head from Step 1.1.2 obtain the RL Pump Flow value using one of the following: Enclosure 13.7 (RL Pumps Head / Capacity Table) OR OAC Databook in "Secondary Systems Databook Calcs" using "RL Total Discharge Head vs. RL Pump Flow Rate".

1.1.4 Once RL Pump Flow value is obtained, calculate Total RL Supply based on number of RL pumps in operation: __________________ X ________________ = ___________gpm (A) RL Pump Flow Value # of pumps in operation Total RL Supply 1.1.5 Enter Total RL Supply (A) value in Step 1.4.

____________________ _____ 3.2 PT/0/A/4250/011Total Discharge Flow Calculation Sheet Page 2 of 3 1.2 IF RN discharge is aligned to the RL discharge header, obtain Total RN Flow (B) as follows: 1.2.1 IF OAC point C1P5856 (RN Calculated Total Flow) is available, perform the following:

1.2.1.1 Record the current value of C1P5856 (RN Calculated Total Flow) C1P5856 ___________ gpm 1.2.1.2 Enter above value as Total RN Flow (B) in Step 1.4.

1.2.1.3 N/A Step 1.2.2 thru Step 1.2.5.

1.2.2 IF OAC points C1P5854 (RN Train A Calculated Total Flow)

AND C1P5855 (RN Train B Calculated Total Flow) are available, perform the following to obtain total RN flow:

1.2.2.1 Record the value of C1P5854 (R N Train A Calculated Total Flow) below: C1P5854 ___________ gpm (RN Pump Train A Flow) 1.2.2.2 Record the value of C1P5855 (RN Train B Calculated Total Flow) below: C1P5855 ___________ gpm (RN Pump Train B Flow) 1.2.3 IF either C1P5854 (RN Train A Calculated Total Flow)

OR C1P5855 (RN Train B Calculated Total Flow) is NOT available, perform the following to obtain total RN flow:

1.2.3.1 Calculate RN Pump Train A flow: gpm__________

__________

=+ flow A Train Pump RN 2RNP7520 1RNP7520 =+1.2.3.2 Calculate RN Pump Train B flow: gpm__________

__________

=+ flow BTrain Pump RN 2RNP7510 1RNP7510 =+1.2.4 Perform the following calculations to obtain Total RN Flow:

(B) ___gpm__________

________________

=+ Flow RN Total Flow BTrain Pump RN Flow A Train Pump RN =+1.2.5 Enter Total RN Flow (B) in Step 1.4.

____________________ _____ _____ _____ _____ _____ _____ 3.2 PT/0/A/4250/011Total Discharge Flow Calculation Sheet Page 3 of 3 NOTE: Normal Cooling Tower evaporation loss @ 100% power is 9,000 to 14,000 gpm/unit.

1.3 Obtain Total Cooling Tower Evaporation (C) as follows:

1.3.1 IF a Unit 1 NC Pump is NOT inservice AND Unit 1 is in Mode 5, 6, or No Mode, enter 0 for Unit 1 Cooling Tower Evaporation in Step 1.3.3.

1.3.2 IF a Unit 2 NC Pump is NOT inservice AND Unit 2 is in Mode 5, 6, or No Mode, enter 0 for Unit 2 Cooling Tower Evaporation in Step 1.3.3.

1.3.3 Calculate Cooling Tower Total Evaporation as follows:

(C) _gpm__________

_____________

__________

____________

__________

=+n Evaporatio Total n EvaporatioTower Cooling 2Unit n EvaporatioTower Cooling 1Unit =+

1.3.2) Step or (C2P5853

1.3.1) Step or (C1P5853 1.3.4 Enter Total Evaporation (C) in Step 1.4.

1.4 Perform the following to obtain Calculated Total RL Disch Flow:

___gpm__________

_____________

-_____________

_____________

=+ Flow Disch RLTotal Calculated (C) on EvaporatiTotal -(B) RN Flow Total (A)Supply RLTotal=+NOTE: Due to problems with current RL instrumentation (PIP C-10-4540) and discrepancies between calculated and OAC RL flow (PIP C-12-1399), a safety factor is applied to the Calculated Total RL Disch Flow of Step 1.4 to ensure conservative Total RL Disch Flow rates are used for dilution purposes. This is a temporary conservative action for use till RL discharge flow instrumentation problems are resolved.

1.5 Apply dilution safety factor to obtain Total RL Discharge Flow from the Calculated Total RL Discharge Flow from Step 1.4 as follows: ________________________ X 0.65 = _______________________ gpm Calculated Total RL Disch Flow Total RL Disch Flow Step 1.4 Calculated By _________________________________ _________________ Operator/Initials Date/TimeVerified By _________________________________ _________________ Operator/Initials Date/Time

_____ _____ _____ _______________ 3.7 PT/0/A/4250/011RL Pumps Head / Capacity Table Page 1 of 1 Head FlowHeadFlowHeadFlowHead Flow1005719214646803175.5024110200151851015699714746524175.7523824201149651025680014846238176.0023544202147371035660214945942176.2523271203144991045640315045636176.5023005204142521055620215145318176.7522747205139971065599915244984177.0022496206137331075579515344633177.2522252207134601085559015444262177.5022016208131801095538315543867177.7521787209128911105517515643444178.0021566210125951115496615742987178.2521352211122921125475515842493178.5021146212119821135454315941954178.7520947213116651145433016041365179.0020756214113421155411616140717179.2520571215110121165390016240004179.5020394216106771175368316339219179.7520224217103351185346516438354180.002006121899881195324616537405180.251990421996351205302516636368180.501975422092771215280416735244180.751961122189141225258116834036181.001947322285461235235716932755181.2519341223817412452132170.0031416181.5019215224779612551906170.2531074181.7519095225741412651679170.5030731182.0018980226702812751451170.7530386182.2518870227663812851222171.0030040182.5018764228624312950991171.252969318318568229584513050760171.502934518418224230544313150527171.752899818517935231503613250293172.002865218617689232462713350058172.252830618717475233421313449821172.502796218817286234379613549583172.752762018917112235337613649343173.002728119016949236295213749102173.252694419116791237252513848859173.502661119216635238209513948613173.752628119316476239166214048365174.002595519416314240122614148114174.25256341951614624178614247860174.50253181961597124234414347603174.7525008197 1578814447341175.0024703198 1559614547075175.2524403199 15395 Catawba Nuclear Station Admin. JPM A.

4 June 201 7 NRC Exam PAGE 1 OF 6 JPM A.4 SRO

Catawba Nuclear Station Admin. JPM A.

4 June 201 7 NRC Exam PAGE 2 OF 6 EVALUATION SHEET Task: Classify an Event and fill out the Emergency Notification Form Alternate Path:

N/A Facility JPM #: NEW Safety Function:

N/A K/A 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation

. Importance:

2.7 / 4.5 CFR: 41.10 / 4 3.5 / 45.11 Preferred Evaluation Location:

Preferred Evaluation Method:

Simulator Classroom X Perform X Simulate References

RP/0/A/5000/001 (Classification of Emergency)

NEI Rev 6 EAL Wallchart RP/0/A/5000/006 A (Notifications to States and Counties from the Control Room) Task Standard:

Using NEI Rev 6 EAL Wallchart and RP/0/A/5000/001, applicant classifies the event as a Site Area Emergency (SA9.1) in < 15 minutes, and then completes the Emergency Notification Form in

< 15 minutes

. Validation Time:

30 minutes Time Critical:

Yes X No Applicant:

Time Start:

__________ NAME___________________________

Docket #_______________

Time Finish: ________

__ Time Critical 1 (<15 min): Time Start: __________

Time Finish: __________

Time Critical 2 (<15 min): Time Start: __________

Time Finish: __________

Performance Rating:

SAT ____ UNSAT ____

Performance Time ___

__ Examiner: _____________________________

_____________________________/________

NAME SIGNATURE DATE ===========================================================================

COMMENTS PAGE 3 0F 6 Catawba Nuclear Station Admin. JPM A.

4 June 201 7 NRC Exam PAGE 3 OF 6 READ TO APPLICANT DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task.

To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Both Units are at 100% RTP.

A tornado warning has been issued for York County.

The following events have occurred

o AO on rounds contacts the control room to report a tornado sighted in the Switchyard.

o A Loss of Offsite Power (LOOP) occurs on Unit 2.

o A lighting pole has punctured the FWST on Unit 1 and water is spilling out into the missile shield.

INITIATING CUES:

You are the Emergency Coordinator.

Classify this event per RP/0/A/5000/001 (Emergency Classification).

Emergency Coordinator Judgment is NOT to be used when making this classification

. Fill out the Emergency Notification Form per RP/0/A/5000/006 A (Notifications to the States And Counties From the Control Room).

This JPM is time critical.

EXAMINER NOTE

After reading cue, provide applicant with a copy of RP/0/A/5000/001 ,

RP/0/A/5000/006 A, and NEI Rev 6 EAL wallcharts.

Catawba Nuclear Station Admin. JPM A.

4 June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 4 OF 6 START TIME: _______

STEP / STANDARD SAT / UNSAT Time Critical 1 Start:

____________

STEP 1: Classify the Event:

Unit 2 is in an Unusual Event (SU1.1) due to the loss of offsite power capability for > 15 minutes. Note 1 states "The Emergency Coordinator should declare the event promptly upon determining that time limit has been exceeded, or will likely be exceeded."

Unit 1 is in an Alert (SA9.1) due to a tornado strike on site and the event has caused VISIBLE DAMAGE to a SAFETY SYSTEM component or structure needed for the current operating mode.

Since Unit 1 is in a higher classification than Unit 2, the emergency classification for the site will be an Alert (SA9.1).

STANDARD: Applicant determines from NEI Rev 6 EAL Wallchart, that Catawba is in an Alert SA9.1.

Time Critical 1 Finish: ____________

Examiner Note: This step is critical to determine the proper Emergency Action Level prior to notification of the States and Counties.

This time critical must be complete in

< 15 minutes.

COMMENTS:

CRITICAL STEP ___ SAT

___ UNSAT Catawba Nuclear Station Admin. JPM A.

4 June 201 7 NRC Exam STEP / STANDARD SAT / UNSAT PAGE 5 OF 6 Time Critical 2 Start: ____________

STEP 2: Fill out Emergency Notification Form:

STANDARD: Applicant properly fills out the emergency notification form within 15 minutes. Time Critical 2 Finish: ____________

Examiner Note: This step is critical to ensure timely and accurate notification of the States and Counties.

Th is time critical must be complete in

< 15 minutes.

COMMENTS: END OF TASK CRITICAL STEP ___ SAT

___ UNSAT STOP TIME ________

APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO APPLICANT:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Both Units are at 100% RTP. A tornado warning has been issued for York County.

The following events have occurred:

o AO on rounds contacts the control room to report a tornado sighted in the Switchyard.

o A Loss of Offsite Power (LOOP) occurs on Unit 2.

o A lighting pole has punctured the FWST on Unit 1 and water is spilling out into the missile shield.

INITIATING CUES:

You are the Emergency Coordinator.

Classify this event per RP/0/A/5000/001 (Emergency Classification).

Emergency Coordinator Judgment is NOT to be used when making this classification.

Fill out the Emergency Notification Form per RP/0/A/5000/006 A (Notifications to the States And Counties From the Control Room).

This JPM is time critical.

Declared EAL: _______________

Declaration Time: ______________

NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM EM-78 / Nuclear Power Facility Emergency Notification Form / March 2016 revision MESSAGE # ________ Confirmation Phone #: __________________

AUTHENTICATION CODE #:

___________

Lines 1 - 6 are required for INITIAL Notifications 1.EVENT: DRILL ACTUAL DECLARATION TERMINATION (ONLY Lines 1, 2, & 4 required) 2.AFFECTED SITE

3.EMERGENCY CLASSIFICATION UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.EAL #______________Declaration Date: ____/____/____

Time: ________ Termination D ate: ____/____/____

Time: ________(mark "N/A" for EAL # &Descr iption) EAL DE SCRIPTION:

_________________________________________________________________________________

______________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

5.RELEASE TO THE ENVIRONMENT (caused by the emergency)

NONE IS OCCURRING HAS OCCURRED 6.PROTECTIVE ACTION RECOMMENDATIONS

NONE EVACUATE: ___________________________________________________________________________________

SHELTER: _________________________

___________________________________________________________

CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH ORO PLANS AND POLICIES OTHER:________________________________________________________________________________________

Lines 7-11 are NOT required for INITIAL notifications. Lines 7-11 may be provided separately for follow-up notifications. 7.PROGNOSIS:

Upgrade in classification or PAR change is likely before the next follow

-up notification Yes No 8.SITE UNIT (S) STATUS:AFFECTED UNIT YES Unit 1 - _________% Power Shutdown: Date ___/_____/____Time _________

YES Unit 2 - _________% Power Shutdown: Date ___/_____/____Time _________

9.METEOROLOGICAL DATA:Wind direction from: ________ degrees Wind Speed: _______ mphPrecipitation: _______ inches Stability Class:

A B C D E F G Lines 10 - 11 are completed for follow

-up notifications, IF Line 5 IS OCCURRING or HAS OCCURRED is selected 10.AIRBORNE RELEASE CHARACTERIZATION:

GROUND MIXED ELEVATED MAGNITUDE UNITS: Ci Ci/sec Ci/secNoble Gases: ____________ Iodines: ____________ Particulates: ____________11.DOSE PROJECTION

Projection period: __________

HoursEstimated Release Duration

________Hours Performed: Date ___/_____/____

Time: _________ DISTANCE TEDE (mr em) Thyroid CDE (mr em) Site Boundary 2 Miles 5 Miles 10 Miles 12.REMARKS (As Applicable)

_________________________________________________________________________

______________________________________________________________________________________________________ _____________________________________________________________________________________________________ 13.APPROVED BY

________________________

_TITLE: ___________________Date ___/_____/____Time _______

___14.NOTIFIED BY

____________________________________________________Date ___/_____/____Time _______

___15.RECEIVED BY (ORO use only): _______________________________________Date ___/_____/____Time __________

GOVERNMENT AGENCIES NOTIFIED

1. 2. 8. 7. 3. 4. 5. 6. Record the name, date, time, and agencies notified as applicable.

(name) (date)(time) (date)(time) (date) (time) (date)(time) (date)(time) (date)(time) (date)(time) (date)

(time) York County WP/EOC Gaston County WP/EOC Mecklenburg County WP/EOC

North Carolina EOC/WP North Carolina Alt. WP

(name) (name) (name) (name) (name) (name) (name) North Carolina Alt. EOC South Carolina WP South Carolina Alt. WP

9. (date)(time) (name) South Carolina EOC

NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM EM-78 / Nuclear Power Facility Emergency Notification Form / March 2016 revision MESSAGE # ________ Confirmation Phone #: __________________

AUTHENTICATION CODE #:

___________

Lines 1 - 6 are required for INITIAL Notifications 1.EVENT: DRILL ACTUAL DECLARATION TERMINATION (ONLY Lines 1, 2, & 4 required) 2.AFFECTED SITE

3.EMERGENCY CLASSIFICATION UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 4.EAL #______________Declaration Date: ____/____/____

Time: ________ Termination D ate: ____/____/____

Time: ________(mark "N/A" for EAL # &Descr iption) EAL DESCRIPTION:

_______________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________________

5.RELEASE TO THE ENVIRONMENT (caused by the emergency)

NONE IS OCCURRING HAS OCCURRED 6.PROTECTIVE ACTION RECOMMENDATIONS

NONE EVACUATE: ___________________________________________________________________________________

SHELTER: _________________________

___________________________________________________________

CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH ORO PLANS AND POLICIES OTHER:________________________________________________________________________________________

Lines 7-11 are NOT required for INITIAL notifications. Lines 7-11 may be provided separately for follow-up notifications. 7.PROGNOSIS:

Upgrade in classification or PAR change is likely before the next follow

-up notification Yes No 8.SITE UNIT (S) STATUS:AFFECTED UNIT YES Unit 1 - _________% Power Shutdown: Date ___/_____/____Time _________

YES Unit 2 - _________% Power Shutdown: Date ___/_____/____Time _________

9.METEOROLOGICAL DATA:Wind direction from: ________ degrees Wind Speed: _______ mphPrecipitation: _______ inches Stability Class:

A B C D E F G Lines 10 - 11 are completed for follow

-up notifications, IF Line 5 IS OCCURRING or HAS OCCURRED is selected 10.AIRBORNE RELEASE CHARACTERIZATION:

GROUND MIXED ELEVATED MAGNITUDE UNITS: Ci Ci/sec Ci/secNoble Gases: ____________ Iodines: ____________ Particulates: ____________11.DOSE PROJECTION

Projection period: __________

HoursEstimated Release Duration

________Hours Performed: Date ___/_____/____

Time: _________ DISTANCE TEDE (mr em) Thyroid CDE (mr em) Site Boundary 2 Miles 5 Miles 10 Miles 12.REMARKS (As Applicable)

_________________________________________________________________________

______________________________________________________________________________________________________ _____________________________________________________________________________________________________ 13.APPROVED BY

________________________

_TITLE: ___________________Date ___/_____/____Time _______

___14.NOTIFIED BY

____________________________________________________Date ___/_____/____Time _______

___15.RECEIVED BY (ORO use only): _______________________________________Date ___/_____/____Time __________

GOVERNMENT AGENCIES NOTIFIED

1. 2. 8. 7. 3. 4. 5. 6. Record the name, date, time, and agencies notified as applicable.

(name) (date)(time) (date)(time) (date) (time) (date)(time) (date)(time) (date)(time) (date)(time) (date)

(time) York County WP/EOC Gaston County WP/EOC Mecklenburg County WP/EOC

North Carolina EOC/WP North Carolina Alt. WP

(name) (name) (name) (name) (name) (name) (name) North Carolina Alt. EOC South Carolina WP South Carolina Alt. WP

9. (date)(time) (name) South Carolina EOC

ML17241A216

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