ML22199A271

Ile ES-D-1s Simulator Scenario Outlines

ML22199A271
Person / Time
Site:	Braidwood
Issue date:	02/22/2022
From:	Randy Baker NRC/RGN-III/DRS/OLB
To:	Exelon Generation Co LLC, Exelon Generation Co
Baker R
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ML20140A264	List: ML22199A247 ML22199A253 ML22199A263 ML22199A269 ML22199A270 ML22199A271
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Download: ML22199A271 (10)

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20-1 NRC 1 Page 1 of 2 Simulation Facility Braidwood Scenario No.:

NRC 1 Operating Test No.: 20-1 NRC Examiners:

Applicant:

SRO ATC BOP Initial Conditions:

IC-31 Turnover Unit 1 is at 90%, steady state, Equilibrium Xenon, BOL. On-line risk is Green. Instrument Maintenance is currently testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E & 3.3.2 Conditions A and D have been entered (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago). Instrument Maintenance is currently troubleshooting loop 1B OTDT setpoint circuitry. Tech Spec 3.3.1 Conditions A and E have been entered (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago). Following turnover, perform 1BwOSR 3.6.6.2, sections 1 &

3 for the 1B RCFC, as a PMT for an EMD breaker swap completed last shift. FIN is troubleshooting the 1RE01PA and 1RE01PB, RCDT Pumps 1A & 1B, auto start feature (pumps started at lower than expected RCDT level). Both pumps are available for manual operation, if required, and their control switches are in STOP at 1PM05J.

Event No.

Malf. No.

Event Type*

Event Description Preload IMF RX06C 0 IRF RX051A BYPASS IRF RX051B BYPASS IMF RX24B 0 IRF RX018A BYPASS IRF RX018C BYPASS IMF SI12A IMF SI01B Fail 1LT-519, 1A SG NR level channel, low Bypass 1LT-519 SG HI-2 level (P-14) turbine trip Bypass 1LT-519 SG LO-2 level Rx trip/AF pump start Fail loop 1B OTDT setpoint low Bypass loop 1B OTDT trip Bypass loop 1B OTDT runback 1A SI pump auto start failure 1B SI pump fails to start/run 1

None N-BOP N-SRO 1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3 2

IMF RM02N C-BOP C, T-SRO VC rad monitor, 0PR33J, operate failure 3

IMF FW35A C-BOP C-SRO 1A HD pump trip 4

IOR ZDI1CV181 OPEN SSF Gate GFXDI1CV181==1 DOR ZDI1CV181 C-ATC C-SRO RCP 1A Standpipe PW supply valve, 1CV181, fails open (manual closure available) 5 IMF RX18K 530 IMF RX18O 530 T-SRO Loop 1C Tave channel fails low 6

None R-ATC N-BOP R-SRO Tech Spec LCO 3.0.3 ramp 7

IMF CV28B C-ATC C-SRO 1B RCP #2 seal failure 8

IMF TH06A 2000 M-ALL Small Break LOCA 9

Preload C-ATC C-SRO 1A SI pump fails to auto start, manual start is successful

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient

20-1 NRC 1 Page 2 of 2 SCENARIO OVERVIEW Unit 1 is at 90%, steady state, Equilibrium Xenon, BOL. On-line risk is Green. Instrument Maintenance is currently testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E & 3.3.2 Conditions A and D have been entered (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago). Instrument Maintenance is currently troubleshooting loop 1B OTDT setpoint circuitry. Tech Spec 3.3.1 Conditions A and E have been entered (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago).

Following turnover perform 1BwOSR 3.6.6.2, sections 1 & 3 for the 1B RCFC, as a PMT for an EMD breaker swap completed last shift. FIN is troubleshooting the 1RE01PA and 1RE01PB, RCDT Pumps 1A

& 1B, auto start feature (pumps started at lower than expected RCDT level). Both pumps are available for manual operation, if required, and their control switches are in STOP at 1PM05J.

After completing shift turnover, the crew will perform 1BwOSR 3.6.6.2 RCFC breaker swap PMT sections 1 and 3. The BOP will perform sections 1 and 3 of 1BwOSR 3.6.6.2 for the B train RCFCs.

Once the crew has completed the RCFC surveillance, rad monitor 0PR33J will go into operate failure. The crew will respond to the VC rad monitor failure per BwAR 2-0PR33J. The BOP will reference BwOP AR/PR-11 and dispatch an EO to the rad monitor. The SRO will enter Tech Spec 3.3.7 Condition A.

The SRO will direct the BOP to place the 0B VC train in emergency mode per BwOP VC-5.

Following the completion of BwOP VC-5 to place MCR ventilation in emergency mode, the 1A HD pump will trip. The BOP will respond utilizing BwAR 1-17-D2 and start the standby 1B HD pump. The crew will respond using 1BwOA SEC-1.

Following the 1A HD pump trip, the 1A RCP Standpipe PW supply valve, 1CV181, fails open (manual closure available). The ATC will respond per BwAR 1-7-A6 and will close 1CV181 to stop filling the 1A RCP standpipe.

After 1CV181 is manually closed, loop 1C Tave channel will fail low. The crew will enter 1BwOA INST-2, Attachment A. The crew will perform 1BwOA INST-2 actions. The SRO will enter Tech Spec 3.3.1 Conditions A and E and LCO 3.0.3 (2 failed OTDT channels).

After the Tave failure Tech Specs are determined, the crew will brief a Tech Spec LCO 3.0.3 plant shutdown. The crew will begin shutting down Unit 1 per 1BwGP 100-4 and will utilize 1BwGP 100-4T1/3.

Once sufficient reactivity controls have been observed, the 1B RCP #2 seal will fail open. The crew will enter 1BwOA RCP-1, determine that continued RCP operation is allowed, and manually control RCDT level at 1PM05J by manual operation of a RCDT pump.

After the crew has manually started an RCDT pump, a small break LOCA will occur. The ATC will determine that PZR level is lowering greater than 2% per minute and recommend to the SRO that a reactor trip and SI are required. The SRO will order a manual reactor trip and SI and order the crew to perform the immediate actions of 1BwEP-0. The 1A SI pump will not auto start, and the ATC will manually start the pump. The 1B SI pump will trip on starting. The crew will dispatch an EO to investigate the failure of the 1B SI pump.

Scenario completion criteria is performing the Check if RH pumps should be stopped step in 1BwEP-1.

Critical Tasks:

1. Manually start the 1A SI pump prior to transitioning out of 1BwEP-0. (Westinghouse - CT-7) (K/A number - EPE009EA1.13, Importance - 4.4/4.4)

2. Trip RCPs when RCP trip criteria are met (RCS pressure < 1425 psig and high head SI flow > 100 gpm or SI pump discharge flow > 200 gpm) prior to transition out of 1BwEP-1. (Westinghouse - CT-

16) (K/A Number - EPE009EA1.09, Importance - 3.6/3.6)

20-1 NRC 2 Page 1 of 3 Simulation Facility Braidwood Scenario No.:

NRC 2 Operating Test No.: 20-1 NRC Examiners:

Applicant:

SRO ATC BOP Initial Conditions:

IC-18 Turnover Unit 1 is at 75%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Instrument Maintenance is currently testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E & 3.3.2 Conditions A and D have been entered. Following completion of turnover, the crew is to perform 1BwOS FW-M2, TURBINE DRIVEN MAIN FEEDWATER PUMP OIL RESERVOIR HI/LO LEVEL ALARM SURVEILLANCE, as a PMT for repairs on the 1B TDFWP oil level alarm system.

Event No.

Malf. No.

Event Type*

Event Description Preload IMF FW43 IMF FW44 IMF RD05G13 15 IMF RD05H12 15 IMF RD05H10 24 IMF RD05J13 25 IMF TC03 IMF MS01A 100 IMF MS01B 100 IMF MS01C 100 IMF MS01D 100 SSF Gate RP:52HRTA==

FALSE IMF RP09A IMF RX06C 0 IRF RX051A BYPASS IRF RX051B BYPASS 1A AF pump fails to start 1B AF pump fails to start Stuck rod G13 Stuck rod H12 Stuck rod H10 Stuck rod J13 Main turbine auto trip failure 1A-1D MSIVs failed open Inadvertent FWI on reactor trip Fail 1LT-519, 1A SG NR level channel, low Bypass 1LT-519 SG HI-2 level (P-14) turbine trip Bypass 1LT-519 SG LO-2 level Rx trip/AF pump start 1

None N-BOP N-SRO 1BwOS FW-M2 FW pump oil reservoir Hi/Lo alarm surveillance 2

IMF CH03A C-BOP C-SRO 1A CRDM Exhaust Fan trip 3

IMF RD02H08 C-ATC C, T-SRO Dropped rod H-8 4

None R-ATC N-BOP R-SRO Power reduction for dropped rod recovery

20-1 NRC 2 Page 2 of 3 5

IMF SLIM12ManPB PRESSED IMF SLIM12OutDecPB PRESSED IRF OV12 TRUE I-ATC I-SRO Master Pressurizer Level Controller (1LK-0459) output fails LOW Loss of power to 1LK-0459 6

IOR ZDI0VC01CA TRIP DOR ZDI0VC01CA C-BOP C, T-SRO 0A MCR Supply Fan trip 7

IMF RD02M04 Preload M-ALL Dropped rod M-4 Inadvertent FWI on reactor trip 8

Preload C-BOP C-SRO Main Turbine Auto Trip failure 9

Preload C-ATC C-SRO Four stuck rods requiring emergency boration 10 IMF FW19B 3.5 M-ALL 1B SG feedline break / loss of heat sink

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient

20-1 NRC 2 Page 3 of 3 SCENARIO OVERVIEW Unit 1 is at 75%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Instrument Maintenance is currently testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E & 3.3.2 Conditions A and D have been entered. Following completion of turnover, the crew is to perform 1BwOS FW-M2, TURBINE DRIVEN MAIN FEEDWATER PUMP OIL RESERVOIR HI/LO LEVEL ALARM SURVEILLANCE, as a PMT for repairs on the 1B TDFWP oil level alarm system.

After completing shift turnover and relief, the crew will perform 1BwOS FW-M2, TURBINE DRIVEN MAIN FEEDWATER PUMP OIL RESERVOIR HI/LO LEVEL ALARM SURVEILLANCE, as a PMT for repairs on the 1B TDFWP oil level alarm system.

Once the crew completes the 1B TDFWP surveillance, the 1A CRDM exhaust fan will trip. This will require the BOP to respond using BwARs 0-33-A5/B5. The BOP will send an operator to the breaker to investigate, and the BOP will swap the CRDM exhaust fans per BwOP VP-9/10.

Following the restoration of CRDM exhaust fans, rod H-8 will drop. Rods will initially step out to respond to the transient. The ATC will receive numerous alarms related to the dropped rod and will place rod control in manual. The SRO will enter 1BwOA ROD-3, RESPONSE TO A DROPPED OR MISALIGNED ROD, and enter Tech Spec 3.1.4 Condition B. 1BwOA ROD-3 will require power to be reduced to < 70% to recover the dropped rod. The crew will brief and begin to ramp to < 70%.

After sufficient reactivity controls have been observed, the Master Pressurizer Level Controller (1LK-0459) output will fail low prior to losing power. The crew will take manual control of the 1CV121 controller and manually control charging flow to restore PZR level. The SRO will establish a critical parameter for pressurizer level being in manual control.

When the crew has completed taking the actions for the Master Pressurizer Level Controller failure, the 0A MCR Supply Fan will trip. The crew will send an EO to investigate the cause. Upon receiving the report that local indications include motor damage, the crew will start the 0B VC train as directed by BwAR 0-33-A8, MCR SUP FAN 0A TRIP DP HIGH LOW, and BwOP VC-1. The SRO will enter Tech Spec 3.7.10 Condition A.

After the 0A MCR Supply Fan failure is addressed, rod M-4 will drop. The ATC will diagnose the dropped rod and corresponding change in Tave and recommend a reactor trip the SRO. The SRO will order the ATC to trip the reactor and verify reactor trip. The SRO will enter 1BwEP-0 and direct the performance of immediate actions. When the reactor trips, one control bank rod and three shutdown bank rods will not fully insert.

Feedwater will isolate immediately on the reactor trip vs. on low Tave due to a SSPS card failure. The turbine will fail to automatically trip, requiring a manual trip. Both AF pumps will fail to start and cannot be manually started. The crew will transition to 1BwEP ES-0.1, REACTOR TRIP RESPONSE, and initiate emergency boration for the 4 stuck rods. An automatic SI signal may be generated if the main turbine is not manually tripped expeditiously.

Once the crew has established emergency boration or after an SI actuates, a 1B SG feedline break inside Cnmt will occur. The MSIVs will fail to close automatically or on manual steamline isolation signals.

The crew will transition to 1BwFR-H.1 due to a loss of heat sink at step 15 of 1BwEP-0 or based on STA status tree results. When Wide Range SG levels are < 43% (adverse Cnmt), the crew will initiate RCS bleed and feed.

Scenario completion criteria is establishing RCS Bleed and Feed.

Critical Tasks:

1. Manually trip the main turbine before a severe challenge (ORANGE path) develops to either subcriticality or integrity critical safety function or before transition to 1BwCA-2.1, whichever happens first. (Westinghouse -

CT-13) (K/A Number - EPE007EA1.07, Importance - 4.3/4.3)

2. Establish RCS bleed and feed before either PZR PORV opens automatically as a result of a loss of heat sink. (Westinghouse - CT-44) (K/A Number - EPEE05EA1.1, Importance - 4.1/4.0)

20-1 NRC 3 Page 1 of 3 Simulation Facility Braidwood Scenario No.:

NRC 3 Operating Test No.: 20-1 NRC Examiners:

Applicant:

SRO ATC BOP Initial Conditions:

IC-22 Turnover Unit 1 is at 100%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Instrument Maintenance is currently testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E & 3.3.2 Conditions A and D have been entered. Following turnover, perform 1BwOS TRM 3.3.g.3 as a PMT for repairs conducted by the FIN team to fix a faulty limit switch on the left side RSV L2 (1MS5001B, #2 Left Side Reheat Stop Valve). The SM has determined that main turbine load does not have to be reduced. EOs are briefed and standing by at 1HD06J and at 1MS5001B to conduct a local observation.

Event No.

Malf. No.

Event Type*

Event Description Preload IMF RX06C 0 IRF RX051A BYPASS IRF RX051B BYPASS Fail 1LT-519, 1A SG NR level channel, low Bypass 1LT-519 SG HI-2 level (P-14) turbine trip Bypass 1LT-519 SG LO-2 level Rx trip/AF pump start 1

None N-BOP N-SRO Perform 1BwOS TRM 3.3.g.3 (PMT for repairs conducted on the left side RSV L2 (1MS5001B, #2 Left Side Reheat Stop Valve))

2 None R-ATC N-BOP R-SRO Load Dispatcher orders a 100 MWe emergency load drop due to a grid disturbance 3

IOR ZDI1CV8324A CLS C-ATC C-SRO 1CV8324A, Charging to 1A Regen HX Isol Valve, fails closed (loss of normal charging and letdown) 4 IMF RX06A 0 (30 min ramp)

I-BOP I, T-SRO 1A SG NR level channel, 1LT-517, fails low 5

IMF ED04A C-BOP C, T-SRO Unit 1 Loss of Offsite Power 6

IMF RX15dec LOWER I-ATC I, T-SRO Master Pressurizer Pressure controller, 1PK-0455A, setpoint fails low 7

IMF EG08A IMF ED07B M-ALL Loss of All AC Power - 1A DG failure / Bus 142 fault 8

IMF TH04D 225 C-ATC C-SRO Small RCS leak

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient

20-1 NRC 3 Page 2 of 3 SCENARIO OVERVIEW Unit 1 is at 100%, steady state, Equilibrium Xenon, MOL. On-line risk is Green. Instrument Maintenance is currently testing 1LT-519, 1A SG NR level channel. Tech Spec 3.3.1 Conditions A and E & 3.3.2 Conditions A and D have been entered. Following turnover, perform 1BwOS TRM 3.3.g.3 as a PMT for repairs conducted by the FIN team to fix a faulty limit switch on the left side RSV L2 (1MS5001B, #2 Left Side Reheat Stop Valve). The SM has determined that main turbine load does not have to be reduced.

EOs are briefed and standing by at 1HD06J and at 1MS5001B to conduct a local observation.

After completing shift turnover, the crew will perform 1BwOS TRM 3.3.g.3 (PMT for repairs conducted on the left side RSV L2 (1MS5001B, #2 Left Side Reheat Stop Valve)). The BOP will perform a left side RSV L2 (1MS5001B) PMT per 1BwOS TRM 3.3.g.3.

After the crew has completed 1BwOS TRM 3.3.g.3, the Load Dispatcher will call and order a 100 MWe emergency load drop. The crew will take prompt action per 1BwGP 100-4T6/1BwOA PWR-1 to lower main generator load by 100 MWe at 6.7 MWe/minute. The ATC will borate the RCS. The crew has 15 minutes to begin the ramp and 15 minutes to complete the ramp.

After sufficient reactivity controls are observed, 1CV8324A, Charging to 1A Regen HX Isol Valve, will fail closed. The ATC will notify the SRO of a loss of normal charging and will isolate letdown per 1BwPR 1-9-LD since 1CV8389A closed on interlock when 1CV8324A closed. The crew will use either BwOP CV-22 or 1BwOA PRI-15 to restore normal charging. Letdown will be restored per 1BwOA ESP-2 with the 1B Regen HX on-line.

After normal charging and letdown have been restored, 1A SG NR level channel, 1LT-517, will fail low. Ovation will detect the second 1A SG NR level channel failure causing an OVATION ALTERNATE ACTION that will swap the 1A FRV and bypass valve controllers to manual. The BOP will respond per 1BwPR 1-15-FRV and will manually adjust the 1A FRV controller to restore 1A SG NR level to normal. The SRO will enter 1BwOA INST-2. The SRO will enter Tech Spec 3.0.3, 3.3.1 Conditions A and E and 3.3.2 Conditions A and D. NOTE: If the crew takes no action for this failure, an automatic reactor trip will occur.

After the plant is stable from the 2nd 1A SG NR level channel failure, a Unit 1 Loss of Offsite Power (LOOP) will occur. The crew will respond utilizing 1BwOA ELEC-4, request Unit 2 to perform 1/2BwOSR 3.8.1.1 and restore ESF equipment to standby. The SRO will enter Tech Spec 3.8.1 Condition A on Unit 1.

After the LOOP Tech Specs are determined, the Master Pressurizer Pressure controller (1PK-0455A) setpoint will fail low. Both PZR spray valves, 1RY455B/C, will open and PZR pressure will drop. The ATC will take manual control of 1PK-0455A or both PZR spray valve controllers per 1BwPR 1-12-RY and lower demand to close the PZR spray valves and energize the PZR heaters. The SRO will enter Tech Spec 3.4.1 Condition A when PZR pressure drops below 2209 psig. NOTE: If the crew takes no action for this failure, a reactor trip and SI will occur.

After the SRO has evaluated Tech Specs for the Master PZR Pressure controller failure and PZR pressure is stable, a Loss of All AC Power will occur. The 1A DG will seize and bus 142 will fault causing a Loss of All AC Power. The SRO will enter 1BwCA-0.0 and direct crew actions to restore power to Bus 141. The SRO will transition to 1BwCA-0.2 due to a small RCS leak and restore vital equipment including at least one CV pump.

Scenario completion criteria is starting one CV pump in 1BwCA-0.2.

20-1 NRC 3 Page 3 of 3 Critical Tasks:

1. Energize ESF bus 141 from Unit 2 within 10 minutes of the Loss of All AC Power. (Westinghouse -

CT-24) (K/A number - EPE055EA1.07, Importance - 4.3/4.5)

2. Isolate RCP seal injection before a CV pump is started. (Westinghouse - CT-27)

(K/A number - 003A4.01, Importance - 3.3/3.2)

Potential Critical Tasks:

1. Manually control 1A SG NR level to prevent a reactor trip. (K/A number - 059A4.08, Importance -

3.0/2.9)

2. Manually control PZR pressure to prevent a reactor trip. (K/A number - 010A4.01, Importance -

3.7/3.5)

20-1 NRC 4 Page 1 of 2 Simulation Facility Braidwood Scenario No.:

NRC 4 Operating Test No.: 20-1 NRC Examiners:

Applicant:

SRO ATC BOP Initial Conditions:

IC-46 Turnover Unit 1 is at 1x10-8 amps, steady state, Xenon free, BOL. On-line risk is Green. Following turnover, the crew will raise reactor power to 2-3% per 1BwGP 100-2 step 27 and then prepare for rolling the main turbine per 1BwGP 100-2 step 33. Another NSO is assigned to commence the step F.33.e surveillances.

Event No.

Malf. No.

Event Type*

Event Description Preload SSF Gate RP:52HRTA==FALSE IMF ED04B Loss of offsite power on reactor trip (30 seconds delay) 1 None R-ATC R-SRO Withdraw control rods to 2%-3% power 2

None N-BOP N-SRO Perform preparations for rolling the main turbine 3

IMF CV02A C-BOP C-SRO 0A PW pump trip 4

IMF TH08.01 T-SRO High RCS activity 5

IOR ZDI1VP05CA STOP DOR ZDI1VP05CA C-BOP C-SRO 1A Reactor Cavity vent fan trip 6

TH03B 30 60 C-ATC T-SRO 1B SG tube leak 7

IRF OV06 TRUE IMF CV45 OPEN I-ATC I-SRO Spurious automatic make-up relay actuation with Boric Acid flow controller power failure 8

IMF TH03B 420 M-ALL 1B SGTR 9

Preload C-ALL LOOP on main generator trip

• (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient

20-1 NRC 4 Page 2 of 2 SCENARIO OVERVIEW Unit 1 is at 1x10-8 amps, steady state, Xenon free, BOL. On-line risk is Green. Following turnover, the crew will raise reactor power to 2-3% per 1BwGP 100-2 step 27 and then prepare for rolling the main turbine per 1BwGP 100-2 step 33. Another NSO is assigned to commence the step F.33.e surveillances.

After completing shift turnover, the crew will raise reactor power to 2%-3%. The ATC will use 1BwGP 100-2 step 27 to withdraw rods with the BOP providing peer checks and the SRO providing oversight. Reactor power will be slowly raised by withdrawing rods. Reactor power will be stabilized at 2%-3%.

Once the crew has stabilized reactor power at 2%-3%, the crew will perform turbine roll preps. The BOP will perform 1BwGP 100-2 step 33 to prepare for rolling the main turbine.

After 1BwGP 100-2 step 33 is completed, the 0A PW pump will trip. The BOP will respond and start the 0B PW pump per BwAR 0-38-A5. The 0B PW pump will be required for reactivity control during the plant startup.

After the 0A PW pump failure is addressed, high RCS activity will occur. The crew will enter 1BwOA PRI-4 to address the high RCS activity. The SRO will enter Tech Spec 3.4.16 Condition A.

After the SRO has evaluated Tech Specs for the high RCS activity, the 1A Reactor Cavity Vent Fan will trip. The BOP will respond utilizing BwAR 0-33-C5 and BwOP VP-7 to start the 1B Reactor Cavity Vent Fan.

After the 1B Reactor Cavity Vent Fan is started, a 1B SG tube leak will occur. The crew will enter 1BwOA SEC-8, STEAM GENERATOR TUBE LEAK. The crew will determine the estimated leak size and determine that a unit shutdown is required using 1BwGP 100-4, POWER DESCENSION. The SRO will enter Tech Spec 3.4.13 Condition B.

After the SGTL has been addressed, the Boric Acid flow controller, 1FK-0110, will fail and a spurious automatic make-up will start due to a failure in the Ovation logic and relaying. This will require the ATC to stop the automatic makeup by placing the makeup control system to stop.

After the spurious auto makeup action is completed, the 1B SG tube leak will worsen to a 420 GPM tube rupture. The crew should note that pressurizer level is dropping at greater than 2% per minute and perform a reactor trip and SI. The crew will enter1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.

When the reactor is tripped, a loss of offsite power (LOOP) will occur 30 seconds later. The crew will transition to 1BwEP-3, SGTR. The crew will utilize the SG PORVs to conduct the RCS cooldown and RCS depressurization will occur via the PZR PORVs due to the LOOP.

Scenario completion criteria is completion of the first RCS depressurization in 1BwEP-3.

Critical Tasks:

1.

Isolate feedwater flow into and steam flow from the 1B SG before transition to 1BwCA 3.1 occurs.

(ERG Critical Task number - CT-18) (K/A number - EPE038EA1.32, importance - 4.6/4.7)

2.

Establish/maintain RCS temperature so that transition from 1BwEP-3 does not occur because the RCS temperature is too high (1BwCA-3.1) or too low (1BwFR-P.1).

(ERG Critical Task number - CT-19) (K/A number - EPE038EA1.36, importance - 4.3/4.5)

3.

Depressurize RCS to meet SI termination criteria prior to water release from the 1B SG PORV or safety valve.

(ERG Critical Task number - CT-20) (K/A number - EPE038EA1.04, importance - 4.3/4.1)