ML23356A149

Spare Scenario (Not Used)

ML23356A149
Person / Time
Site:	Seabrook
Issue date:	02/28/2023
From:	NRC Region 1
To:	NextEra Energy Seabrook
References
Download: ML23356A149 (1)

Text

Form 3.3-1 Scenario Outline Facility:

Seabrook Station Scenario #:

Spare (Not Used)

Scenario Source:

New Op. Test #:

2023 Examiners:

See crew rotations Applicants/

See crew rotations Operators:

Initial Conditions: 100% power.

Core burnup is 10,000 MWD/MTU. Boron concentration is 1032 ppm and CBD is at 230 steps.

Turnover: Maintain current power. SW-P-41D removed from service for maintenance.

Critical Tasks:

1. Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs. (PWROG CT-18)

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 (PWROG CT-19):

Too high to maintain 60°F of subcooling requiring transition to ECA-3.1.

OR Too low causing Red or Orange path on the sub criticality and/or the integrity CSF.

Event No.

Malf.

No.

Event Type*

Event Description 1

See SEG for sim malf.

codes BOP C, MC US C SCCW pump trips, standby fails to start and must be manually started.

2 PSO I, MC US I, TS Controlling pressurizer level channel, RC-LT-459 fails low.

3 PSO C US C, TS 20 gpm steam generator tube leak on A SG.

4 PSO R BOP C US C Plant down power to <50% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

5 PSO M BOP M US M A SG tube leak propagates into 500 gpm tube rupture, requiring manual reactor trip and safety injection. (CT-1) (CT-2) 6 BOP C, MC US C Main generator breaker fails to open on the turbine trip and must be manually opened.

7 PSO C, MC US C SI-P-6A fails to automatically start and must be manually started.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control

SIMULATOR EXERCISE GUIDE SEG Page 1 of 22 SITE:

Seabrook Station Revision #: 0 SEG TITLE:

2023 NRC Sim Exam SPARE SEG TYPE:

Training Evaluation PROGRAM:

LOCT LOIT Other:

DURATION:

90 minutes Developed by:

Mark Martellotta 7/14/22 Instructor/Developer Date Validated by:

Kevin Thibodeau 8/23/22 Reviewer Date Approved by:

Mike Magri 11/28/22 Training Supervision Date (Not Used)

2023 NRC Sim Exam SPARE SEG Page 2 of 22 OVERVIEW / SEQUENCE OF EVENTS The crew will take the watch at 100% power. SW-P-41D D Ocean Service Water Pump is tagged out for motor replacement. The crew will be directed to maintain power.

The A SCCW pump will trip. The standby pump will fail to auto start and should be started by the BOP.

The Crew should enter ON1237.01, Loss of Secondary Component Cooling.

RC-LT-459, the controlling channel for pressurizer level will fail low causing letdown to isolate. The PSO should reduce charging to minimum. The crew should enter OS1201.07, Pressurizer Level Instrument Failure to swap controlling channels and restore letdown. RC-LT-459 failure requires entry into TS 3.3.1, Table 3.3-1, Item 11, action 6A and 3.3.6 action a, table 3.3-10, item 5.

A 20 gpm steam generator tube leak (SGTL) will occur on the A SG. The PSO should lower letdown flow to stabilize pressurizer level. The 20 gpm SGTL requires entry into TS action statement 3.4.6.2c action a. The crew should enter OS1227.01, Steam Generator Tube Leak and once the leak is quantified, they should reduce plant power to less than 50% within one hour by implementing OS1231.04, Rapid Down Power. During the down power the SGTL will propagate into a 500 gpm tube rupture, requiring the crew to start the second charging pump and eventually trip the reactor and actuate SI.

On the turbine trip the main generator breaker will fail to automatically open and must be manually opened by the BOP.

Following the reactor trip and SI, SI-P-6A will fail to automatically start and must be manually started by the PSO.

The crew will process through E-0 to E-3, performing the required RCS cooldown. The exam will terminate once the cooldown is complete.

2023 NRC Sim Exam SPARE SEG Page 3 of 22 Procedure flow path: ON1237.01, OS1201.07, OS1227.02, OS1231.04, E-0, E-3 Event # Description

1.

SCCW pump trips, standby fails to start and must be manually started.

2.

Controlling pressurizer level channel, RC-LT-459 fails low.

3.

20 gpm steam generator tube leak on A SG.

4.

Plant down power to <50% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

5.

A SG tube leak propagates into 500 gpm tube rupture, requiring manual reactor trip and safety injection.

6.

Main generator breaker fails to open on the turbine trip and must be manually opened.

7.

SI-P-6A fails to automatically start and must be manually started.

2023 NRC Sim Exam SPARE SEG Page 4 of 22 Scenario Spare Critical Tasks CT-1: Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs.

(PWROG CT-18)

Initiating Cue:

Step 3 of E-3.

Performance Feedback:

A MSIV, A ASDV, SB-V-9, MSD-V-44 and MS-V-393 are all closed.

Success Path:

Student closes valves per step 3 of E-3.

Measurable Performance Standard:

A SG is isolated with A MSIV, A ASDV, SB-V-9, MSD-V-44 and MS-V-393 closed before a transition to ECA-3.1 occurs. This is a preferred boundary condition.

Safety Significance:

Failure to isolate the ruptured SG causes a loss of differential pressure between the ruptured SG and the intact SGs. The fact that the crew allows the differential pressure to dissipate and, as a result, are then forced to transition to a contingency procedure constitutes an incorrect performance that necessitates the crew taking compensating action that would complicate the event mitigation strategy.

CT-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 60°F of subcooling requiring transition to ECA-3.1, or too low causing Red or Orange path on the sub criticality and/or the integrity CSF. (PWROG CT-19)

Initiating Cue:

Step 7 of E-3.

Performance Feedback:

Core exit temperatures are at required value as determined by step 7 of E-3.

Success Path:

Use condenser Steam Dumps to reach target temperature.

Measurable Performance Standard:

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 60°F of subcooling requiring transition to ECA-3.1, or too low causing Red or Orange path on the sub criticality and/or the integrity CSF. This is a preferred boundary condition.

Safety Significance:

Failure to establish and maintain the correct RCS temperature during a SGTR leads to a transition from E-3 to an ECA procedure. The failure constitutes an incorrect performance that necessitates the crew taking compensating action that would complicate the event mitigation strategy.

"Per NUREG-1021, ES-3.3, if an applicants actions or inactions create a challenge to plant safety, those actions or inactions may form the basis for a Critical Task identified in the post scenario review.

2023 NRC Sim Exam SPARE SEG Page 5 of 22 SIMULATOR SET UP INSTRUCTIONS Reset the sim to a 100% power IC (IC 30)

Run simulator long enough for alarms to come in and reset and plant to stabilize.

Place CS for SW-P-41D in PTL and place white tag on CS.

Run scenario file NRC_LOIT\Demo exams\2023 Exam Spare containing the following:

2023 Exam Spare setup

SCCW Pump fails to auto start IMF mfSCC005 f

`

SW-P-41D tagged out ICR cSWP41D.CRF t

4

MGB fails to open, can be opened manually IMF mfED036 f

1 aet ED\Trip Gen Brkr Manually

SI-P-6A fails to start, can be manually started IMF mfSI003 f

1

Exam run pause pause

SCCW Pump A spurious trip ICM cSCCP34A.CMF t

4 pause pause

RC-LT-459 fails low ICM trRCLT459.CMF t

1 pause pause

20 gpm A SGTL IMF mfSG001A r

10 f:20 pause pause

A SGTR 500 gpm MMF mfSG001A r

30 f:500

2023 NRC Sim Exam SPARE SEG Page 6 of 22 TURNOVER INFORMATION Provide the crew with the turnover sheet.

Ensure that the ODI 56 for MOL is in the Simulator.

2023 NRC Sim Exam SPARE SEG Page 7 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 1 SCCW pump trips, standby fails to start and must be manually started.

Continue the scenario by selecting Continue twice.

When crew dispatches NSO to report SCCW temperature, delay approximately 10 minutes and report SCCW temperature indicated on the instructor workstation.

If crew contacts NSO for to check SCCW head tank level, after a brief time delay report back that SCCW tank level is 50% and stable.

BOP C, MC; US C The A SCCW pump will trip. The standby pump C will fail to auto start. The BOP should start the standby pump via Skill of the Operator as defined in OP 9.2, with the VPRO for F5159 or the AOP.

Initial Alarms:

UA-54 SCCW PUMP TRIP F4303 SCCW SUPPLY HEADER PRESS LOW F5159 SCCW PUMP A TRIP The crew should enter ON1237.01, Loss of Secondary Component Cooling.

Step 1 Check SCCW Pump Status AT LEAST ONE RUNNING One pump is expected to be running.

Step 2 Check SCCW Pump Status TWO PUMPS RUNNING The BOP should start the standby pump if not started previously.

Step 3 Check SCCW Temperature - BETWEEN 77°F AND 95°F (performed locally by NSO)

Step 4 Check SCCW System Integrity (performed locally by NSO)

Head tank level is stable and D155 is reset.

Step 5 Return To Procedure And Step In Effect Once the crew has completed the AOP or at the discretion of the lead examiner, proceed to event 2.

2023 NRC Sim Exam SPARE SEG Page 8 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 2 Controlling pressurizer level channel, RC-LT-459 fails low.

Continue the scenario by selecting Continue twice.

PSO I, MC; US I, TS On the failure of RC-LT-459, letdown will isolate. The crew may elect to take manual control of charging flow and reduce flow to seals only before entering the abnormal procedure via Skill of the Operator as defined in OP 9.2.

Initial Alarms:

F4323 PZR CONTROL HEATERS TRIPPED D4435 PRESSURIZER LEVEL DEVIATION LOW D4461 PZR LVL LOW &HTR INTERLOCK ACTUATED UA-52 PZR LEVEL DEVIATION LO

2023 NRC Sim Exam SPARE SEG Page 9 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE The crew should enter OS1201.07, PZR Level Instrument Failure.

Step 1 Check pressurizer level channels.

PSO should identify that LT-459 has failed low.

Step 2 Realign pressurizer level instruments.

PSO should manually control level at program, select an alternate channel for control and recorder.

Step 3 Verify pressurizer heaters on.

PSO should reset the control group heaters.

Step 4 Check if letdown was isolated.

PSO should determine that RC-LCV-459 is closed.

Step 5 Check if normal letdown can be established.

PSO should increase charging flow, verify pressurizer level is >17%

and establish normal letdown per Attachment A.

Attachment A PSO will:

Verify CC-V-341 is open and CS-TK-130 is in auto Close both CS-HCV-189 and 190 Open CS-V-149 and 150 Place CS-PK-131 in manual at 10% open Open RC-LCV-459, 460 and CS-V-145 and Establish letdown flow by opening either CS-HCV-189 or 190 Once flow is established and letdown pressure is 350 psig, 131 will be placed back into automatic Step 6 Align pressurizer level control.

PSO should return pressurizer level to program, before restoring automatic control.

Step 7 Verify redundant bistables not tripped.

PSO or BOP should verify bistable status on UL-6.

Step 8 US Verify Technical Specification compliance.

2023 NRC Sim Exam SPARE SEG Page 10 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Tech Specs When crew contacts outside work groups for assistance with placing bistables in BTI or trip, acknowledge the communication.

Technical Specifications:

RC-LT-459 failure requires entry into TS 3.3.1, Action As shown in Table 3.3-1.; Functional Unit 11; Action 6A: With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Item b applies only for surveillance testing.

TS 3.3.3.6 action a, table 3.3-10 item 5:

With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channels shown in Table 3.3-10, restore the inoperable channel(s) to OPERABLE status within 30 days, or submit a Special Report to the Commission pursuant to Specification 6.8.2 within the next 14 days outlining the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation to OPERABLE status.

US should contact I&C for assistance with placing bistables in BTI or trip.

Once the crew has completed the AOP or at the discretion of the lead examiner, proceed to event 3.

2023 NRC Sim Exam SPARE SEG Page 11 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 3 20 gpm steam generator tube leak on A SG.

Continue the scenario by selecting Continue twice.

When crew notifies Chemistry to implement CS0905.08, repeat this information. No action is required.

PSO C; US C, TS Initial alarms:

B8443 PRI TO SEC LEAK RATE OF CHANGE HI-HI B8442 PRI TO SEC LEAK RATE OF CHANGE HI RM6481 MAIN STEAM LINE LOOP 1 ALARM RM6505 CONDSR AIR EVACUATION ALARM PSO should note lowering pressurizer level. If not, alarms will alert the crew to the SG leak.

The PSO may place CS-FK-121 in manual and lower letdown flow to stabilize pressurizer level via Skill of the Operator as defined in OP 9.2.

Crew should enter OS1227.02, Steam Generator Tube Leak.

Step 1 Check RCP Status.

PSO should note that RCPs are running and proceed to step 2.

Step 2 Check If Pressurizer Level Can Be Maintained.

PSO should control charging and letdown to stabilize level.

PSO should determine flow balance based on charging and letdown mismatch. BOP should perform a mass balance to determine RCS leak rate.

Step 3 Try To Identify Affected SG.

US should notify Chemistry to implement Response to Primary to Secondary Leak procedure.

Crew should utilize indications to determine A SGTL.

2023 NRC Sim Exam SPARE SEG Page 12 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Step 4 Check If VCT Level Can Be Maintained.

PSO determines VCT level can be maintained.

Step 5 Determine Steam Generator Tube Leakage.

PSO should determine that leak is in excess of 1 gpm (approximately 20 gpm).

Step 5 RNO directs the crew to perform power decrease to 50% within one hour and to refer to ER-1.1.

Tech Specs Technical Specifications:

The 20 gpm leak requires entry into TS action statement 3.4.6.2c action a: With any PRESSURE BOUNDARY LEAKAGE or with primary to secondary leakage not within the limit, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

2023 NRC Sim Exam SPARE SEG Page 13 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 4 Plant down power to <50%

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

When crew contact SM to make ODI 56 notifications, repeat this information. No action is required.

PSO R; BOP C; US C Crew should utilize OS1234.01, Rapid Down Power as down power rate is in excess of 10%/hr.

Crew may use ODI 56 to determine reactivity plan.

Step 1 Perform Notifications Per ODI.61, Redeclaration/Joint Owner Notification Guidelines.

US should call SM to make ODI.61 notifications.

Step 2 US Perform Down Power Briefing Per ATTACHMENT A, as time permits Step 3 PSO Align Rod Control System and verifies rods are in auto.

Step 4 Determine Boration Value For Desired Power Level PSO should use ODI56 to obtain boration levels.

2023 NRC Sim Exam SPARE SEG Page 14 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE When NSO is directed to swap heater drains to flow control mode, wait approximately 5 minutes and perform the flowing:

Local Panels Fischer Porter Heater Drains Take HD-LY-4508-A or B from auto to manual and back to auto.

Once this is done report back that heater drains are now in flow control mode.

Step 5 Perform boration PSO should use attachment to perform boration.

The PSO will setup the dilution controls to the values determined by their reactivity plan.

o PSO will place the blender mode start switch to stop.

o PSO will place the blender mode selector switch to borate.

o PSO using 1-CS-FIQ-111 will SET "MAKEUP TARGET" to the desired quantity.

o PSO using 1-CS-FIQ-111 will SET "MAKEUP FLOW RATE" to the desired flow rate.

o PSO will leave step back off.

Step 6 Reduce turbine load to the desired power limit.

o BOP will place the turbine control on hold.

o BOP will enter the desired power level.

o BOP will adjust the turbine ramp rate.

Various strategies for unloading the turbine are acceptable provide power can be reduced to <50%

within one hour.

Once the effects of the boration are observed, the US should direct the turbine load to be reduced.

BOP should direct the NSO to transfer heater drains to the flow control mode.

Once the crew has begun to unload the turbine, at the discretion of the lead examiner proceed to event 5.

2023 NRC Sim Exam SPARE SEG Page 15 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 5 A SG tube leak propagates into 500 gpm tube rupture, requiring manual reactor trip and safety injection.

Continue the scenario by selecting Continue twice.

PSO M; BOP M; US M SGTL will rapidly develop into a tube rupture. Crew should note the decreasing pressurizer level.

PSO should note decreasing pressurizer level and pressure and attempt to reduce letdown flow and increase charging flow.

PSO should start the second charging pump per OS1227.02 per continuous action step 2b or OAS page item 1.

PSO should determine that pressurizer level cannot be maintained with two charging pumps and per continuous action step 2b or OAS page item 1 of OS1227.02, trip the reactor and actuate SI.

Once the reactor is tripped and SI actuated, crew should enter E-0, Reactor Trip or Safety Injection and perform immediate actions.

Step 1 Verify Reactor Trip PSO verifies the reactor is tripped Step 2 Verify Turbine Trip BOP verifies that the turbine is tripped and manually opens Main Generator breaker.

Step 3 Verify Power to AC Emergency Busses BOP verifies both E busses are energized Step 4 Check if SI is actuated PSO determines SI is actuated on both trains Step 5 Perform ESF Actuation Verification per Attachment A PSO should perform attachment A.

2023 NRC Sim Exam SPARE SEG Page 16 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Event 6 Main generator breaker fails to open on the turbine trip and must be manually opened.

BOP C, MC; US C, MC On the reactor trip the main generator breaker will fail to automatically trip and the BOP should open the breaker during immediate actions.

Event 7 SI-P-6A fails to automatically start and must be manually started.

PSO C, MC; US C, MC On the SI, SI-P-6A will fail to automatically start and must be manually started by the PSO. This may be done via Skill of the Operator as defined in OP 9.2 or with Attachment A.

2023 NRC Sim Exam SPARE SEG Page 17 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Continuing with E-0 Step 6 Monitor RCS Temperature STABLE AT OR TRENDING TO 557°F BOP should determine that RCS trending to 557°F on the steam dumps.

Step 7 Check if RCS is Isolated.

PSO should verify that CS-V-145 is closed.

PSO should validate that PORVs and pressurizer sprays are closed.

If spray are open, PSO should verify that they are functioning properly. There is no spray failure.

Step 8 Check if RCPs Should be Stopped It is not expected that the RPCs will need to be tripped.

Step 9 Check if SG Pressure Boundary is Faulted BOP should determine that no SGs are faulted.

Step 10 Check If SG U Tubes Are Intact BOP should determine that A SG is ruptured.

Crew should transition to E-3, Steam generator tube rupture.

2023 NRC Sim Exam SPARE SEG Page 18 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE CT1 E-3 Step 1 Check If RCPs Should Be Stopped. It is not expected that the RCPs will be tripped.

Step 2 Identify Ruptured SGs BOP should use indications to determine the A SG is ruptured.

Critical Task 1: Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs.

Step 3 Isolate Flow From Ruptured SG(s)

BOP verifies that the A ASDV is closed with setpoint at 1125 psig.

BOP should close MS-V-393 (A SG to TDEFW Pump Turbine Isolation)

PSO verifies SB-V-9 (A SGBD Isolation) is closed PSO should close MSD-V-44 (A MS Upstream Drain).

BOP should close the A MSIV.

2023 NRC Sim Exam SPARE SEG Page 19 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE If the crew directs NSO to fill the CST, repeat the communication. No action will be taken.

Step 4 Check ruptured SG level BOP should check A SG narrow range level and if >6% open EFW pump mini flow valves and isolate flow if not previously done.

Step 5 Check Ruptured SG(s) Isolated From Intact SG BOP should verify that the A SG is isolated from intact SGs.

Note: if crew had not previously isolated the A SG pressure will lower, requiring transition to ECA-3.1.

Step 6 Check Ruptured SG(s) Pressure GREATER THAN 350 PSIG.

Step 7 Initiate RCS cooldown Crew should determine required core exit temperature and use the condenser SDs to commence the cool down.

PSO should depressurize the RCS and block the steamline safety injection per Attachment B.

In Attachment B the PSO will depressurize the RCS to <1950 psig with the pressurizer sprays, block the low steamline pressure SI and maintain pressure less than 1925 psig with the master pressure controller.

Note: it is expected that the cooldown will continue and the crew will proceed with step 8 per 7d RNO.

Step 8 Check Intact SG Levels BOP should continue to maintain intact SG levels

2023 NRC Sim Exam SPARE SEG Page 20 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Step 9 Check PZR PORVs And Block Valves PSO should verify pressurizer PORVs are closed, block valves are powered and open.

Step 10 PSO Reset SI.

Step 11 PSO Reset Containment Isolation Phase A and Phase B.

Step 12 BOP/PSO should check IA supply and CC isolation valves open. No action is required.

Step 13 PSO should check RCS pressure >300 psig and stop the RHR pumps.

Step 14 Crew will check if the cooldown should be stopped based on CETC temperatures. If so the crew should stop the cooldown, establish a critical parameter for RCS temperature and maintain temperature stable.

CT2 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 60F of subcooling requiring transition to ECA-3.1.

OR Too low causing Red or Orange path on the sub criticality and/or the integrity CSF Note: Cool down will continue until the target temperature is reached. The crew will stop the cooldown at step 7e or 14b depending on pace of processing the EOP and target temperature.

Step 15 Check Ruptured SG Pressure Stable or Increasing Crew should not transition to ECA-3.1 here as the A SG pressure will be stable.

2023 NRC Sim Exam SPARE SEG Page 21 of 22 SIMULATOR EXERCISE GUIDE SCENARIO INSTRUCTIONS TIME/NOTES INSTRUCTOR ACTIVITY EXPECTED STUDENT RESPONSE Step 16 Check RCS Subcooling Greater than 60°F.

Crew should not transition to ECA-3.1 here as subcooling will be high.

Step 17 Depressurize the RCS to Minimize Break Flow and Refill PZR.

PSO will use normal pressurizer sprays to depressurize the RCS.

Depressurization will continue until one of the four termination criteria are met:

RCS pressure < ruptured SG pressure and pressurizer level >7%.

RCS pressure within 300 psig of ruptured SG pressure and pressurizer level >37%.

Pressurizer level >75%.

RCS subcooling <40°F.

(It is expected that the second criteria above will be met first, although this is not required.)

Crew will transition to step 20.

Step 20 Check if ECCS Flow Should be Terminated.

Crew will evaluate criteria for terminating SI.

Once target depressurization is complete in step 17 or at the discretion of the lead Examiner, terminate the exam.

• • • END OF SCENARIO ***

2023 NRC Sim Exam SPARE SEG Page 22 of 22 QUANTITATIVE ATTRIBUTES Malfunctions:

Before EOP Entry:

1. SCCW pump trips, standby fails to start and must be manually started.

2. Controlling pressurizer level channel, RC-LT-459 fails low.

3. 20 gpm steam generator tube leak on A SG.

After EOP Entry:

1. Main generator breaker fails to open on the turbine trip and must be manually opened.

2. SI-P-6A fails to automatically start and must be manually started.

Abnormal Events:

1. SCCW pump trips, standby fails to start and must be manually started.

2. Controlling pressurizer level channel, RC-LT-459 fails low.

3. 20 gpm steam generator tube leak on A SG.

Major Transients:

1. A SG tube leak propagates into 500 gpm tube rupture, requiring manual reactor trip and safety injection.

Critical Tasks:

1. Isolate feedwater flow into and steam flow from the ruptured SG before a transition to ECA-3.1 occurs. (PWROG CT-18)

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 60°F of subcooling requiring transition to ECA-3.1, OR too low causing Red or Orange path on the sub criticality and/or the integrity CSF. (PWROG CT-19)

Technical Specifications:

1. RC-LT-459 failure requires entry into TS 3.3.1, Table 3.3-1, Item 11, action 6A and 3.3.6 action a, table 3.3-10, item 5.

2. 20 gpm SGTL requires entry into TS action statement 3.4.6.2c action a.