Text

2011 Braidwood Station Initial License Examination Proposed Scenarios
	ML11356A183
Person / Time
Site:	Braidwood
Issue date:	07/01/2011
From:	; NRC/RGN-III
To:	; Exelon Generation Co, Exelon Nuclear
Shared Package
ML11167A131	List: ML113420113; ML11355A170; ML11356A124; ML11356A183;
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	Download: ML11356A183 (143)
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Simulation Facility Braidwood Scenario Operating Test No.: 2011 NRC No.: Exam NRC 11-spare Examiners: Applicant:

______________________ ____________________ SRO

______________________ ____________________ ATC

______________________ ____________________ BOP Initial Conditions: IC-18 Turnover: Unit 1 is at 75% power, steady state, equilibrium xenon, MOL. RCS boron concentration is 645 ppm. Online risk is green. 1B HD pump has been OOS for breaker contact work for the past 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . 1A CW pump is OOS for impeller work. Expected back in service in one week. 1PR11J filter change planned early in shift.

Event Malf. No. Event Event No. Type* Description Preload IOR ZDI1CW01PA PTL 1A CW PP OOS IOR ZDI1HD01PB PTL 1B HD Pump OOS IRF ED051C OPEN 1CW001A OOS IRF ED075C OPEN IMF RP14A SI auto actuation failure (Train A)

IMF RP14B SI auto actuation failure (Train B)

IMF TC03 Turbine auto trip failure trgset 2 "ZDISIA1 .eq. 1" trgset 3 " ZDISIA2 .eq. 1" trgset 4 " ZDISIA1 .eq. 1" trgset 5 " ZDISIA2 .eq. 1" trg 2 "DMF RP14A" trg 3 "DMF RP14B" trg 4 "DMF RP14B" trg 5 "DMF RP14A" 1 None N-BOP 1PR11J filter change TS-US 2 IMF RX13A 100 10 I-ATC, PZR level channel 1LT-459 fails high (Tech Spec)

US TS-US 3 IMF CV23A 80 180 C-ATC 1A letdown HX tube leak (or BOP),

US 4 IMF EG03 90 96 180 C-BOP, Generator voltage regulator failure US 5 IMF FW35A C-BOP, 1A Heater Drain Pump trip requiring turbine runback US R-ATC, US 6 IMF TH01 0.5 30 M-ALL PZR vapor space LOCA 7 preload Turbine auto trip failure SI auto actuation failure

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

SCENARIO OVERVIEW Unit 1 is at 75% power, steady state, equilibrium xenon, MOL. RCS boron concentration is 645 ppm.

Online risk is green. 1B HD pump has been OOS for breaker contact work for the past 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . 1A CW pump is OOS for impeller work. Expected back in service in one week. 1PR11J filter change planned early in shift.

After completing shift turnover and relief, a Radiation Protection Technician will contact the main control room and request the crew shutdown 1PR11J sample pump to support daily filter replacement. The Unit Supervisor will enter Tech Spec 3.4.15, condition B. Approximately two minutes later, the RP Technician will request restart of the 1PR11J skid. 1PR11J will be restarted. LCO 3.4.15 may be exited after filter change completion and monitor is operating normally for 90 minutes.

After changing the 1PR11J filter, PZR level channel 1LT-459 will fail high. 1CV121, charging header flow control valve, will lower charging flow and pressurizer level will lower. The ATC will take manual control of PZR level and stabilize PZR level. 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment C, will be implemented. The ATC will restore PZR level control to automatic after PZR level is restored to normal and an operable PZR level control channel is selected. Technical Specifications 3.3.1, conditions A and K apply.

After the 1LT-459 failure is addressed, the 1A letdown heat exchanger will develop a tube leak. Letdown flow and VCT level will lower and CC surge tank level and radiation will rise. The crew will implement 1BwOA PRI-6, COMPONENT COOLING SYSTEM MALFUNCTION, and locate and isolate the leakage.

The crew will align the 1B letdown heat exchanger in accordance with BwOP CV-22, OPERATION OF LETDOWN AND REGEN HEAT EXCHANGERS.

After the letdown heat exchanger tube is addressed, the generator voltage regulator output will fail high, causing the main generator to be overexcited. The BOP will turn the voltage regulator to off/test and manually lower main generator excitation using the base adjuster.

After the voltage regulator failure is addressed, 1A Heater Drain Pump will trip. 1BwOA SEC-1, SECONDARY PUMP TRIP, Attachment C, will be entered. The BOP will initiate a turbine load reduction to 780 MW at 20 MW/minute. The ATC will borate the RCS as necessary to stabilize RCS temperature.

After the 1A HD pump trip has been addressed, a weld breaks on the PZR causing a PZR vapor space LOCA. When the reactor trips, the turbine will not automatically trip. The crew will manually trip the turbine.

The crew will take actions in accordance with 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION. While performing the actions of 1BwEP-0, the crew should note the failure of SI to automatically actuate. The crew should manually actuate SI. The crew will transition to 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, after determining that the RCS is not intact.

The scenario is complete when the crew has determined RCS subcooling in 1BwEP-1.

Critical Tasks

1. Manually trip the main turbine prior to completion of step 2 of 1BwEP-0.

(ERG Critical Task number - E-0--Q) (K/A number - 045000A4.01 importance - 3.1/2.9)

2. Manually actuate Safety Injection prior to transition to 1BwEP-1.

Comments:

NRC 11-spare Page 2 of 24

(ERG Critical Task number - E-0--D) (K/A number - 000040AA1.01 importance - 4.6/4.6)

Comments:

NRC 11-spare Page 3 of 24

SIMULATOR SETUP GUIDE:

Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.

Establish the conditions of IC-18, 75% power, MOL, steady state, equilibrium xenon.

Complete items on Simulator Ready for Training Checklist.

Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.

Place simulator in RUN (allow simulator to run during board walk down and turnover).

Place 1B HD pump C/S in PTL.

Place 1A CW pump C/S in PTL.

Wait until 1CW001A valve is fully closed, THEN Run caep 11-spare SETUP from disk and verify the following actuate:

IOR ZDI1CW01PA PTL

IOR ZDI1HD01PB PTL

IRF ED051C OPEN

IRF ED075C OPEN

IMF RP14A

IMF RP14B

IMF TC03

trgset 2 "ZDISIA1 .eq. 1"

trgset 3 " ZDISIA2 .eq. 1"

trgset 4 " ZDISIA1 .eq. 1"

trgset 5 " ZDISIA2 .eq. 1"

trg 2 "DMF RP14A"

trg 3 "DMF RP14B"

trg 4 "DMF RP14B"

trg 5 "DMF RP14A"

Place info tags on 1B HD pump C/S and 1A CW pump C/S

Provide students with turnover sheets, 1BwOS NR-1, and critical parameter sheet.

Comments:

NRC 11-spare Page 4 of 24

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: 1PR11J filter change As rad protection, contact the MCR by phone (X-2209) shortly after completion of shift turnover and request shutdown of 1PR11J to obtain sample (change of particulate and iodine filter cartridges. The rad protection procedure governing the filter change is RP-BR-911).

Two minutes after 1PR11J is shutdown, contact the MCR by phone and request startup of 1PR11J. If asked, report the bypass/normal switch on 1PS36J CASP panel is in bypass. Following start of 1PR11J, provide MCR feedback that 1PR11J is operating properly.

Acknowledge as SM LCO 3.4.15, condition B entry for 1PR11J.

Events 2: PZR level channel 1LT-459 fails high.

Insert IMF RX13A 100 10 to fail 1LT-459 high over a 10 second period.

As SM, if requested support for tripping bistables in AEER, report that AEER bistables are not to be tripped until work analyst and NSO support can be obtained (in approx. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) and that the abnormal operating procedure should be continued. AEER bistable tripping will be conducted later.

If lead examiner desires the bistables tripped, participate in brief and perform the following:

As extra NSO contact Unit 1 (X-2209)

Insert the following:

MRF RP20 OPEN (open protection cabinet #1 door)

MRF RX029 TRIP (trip PZR hi water level Rx trip bistable LB459A)

MRF RP20 CLOSE (close protection cabinet #1 door)

Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.

Comments:

NRC 11-spare Page 5 of 24

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 3: 1A letdown HX tube leak.

Insert IMF CV23A 80 180 to initiate a 80 gpm tube leak in the 1A letdown HX over a 3 minute period.

Acknowledge as Chemistry request to sample CC system for activity.

If dispatched as Equipment Operator to swap letdown heat exchangers in accordance with BwOP CV-22, report 1B letdown HX was previously filled and vented, then perform and report the following when directed by the crew:

MRF CC39 100 (open 1CC9452C, 1B letdown HX CC inlet isolation valve).

Verify RF CC43 50 (throttle 1CC9452D, 1B letdown HX CC outlet isolation valve).

Verify RF CV64 100 (open 1CV8467B, 1B letdown HX outlet isolation valve).

MRF CC37 0 (close 1CC9452A, 1A letdown HX CC inlet isolation valve).

MRF CC40 0 (close 1CC9452B, 1A letdown HX CC outlet isolation valve).

MRF CV63 0 (close 1CV8467A, 1A letdown HX outlet isolation valve).

If dispatched as Equipment Operator to drain the CC surge tank, run caep NRC 11-spare EVENT 4 DRAIN CCST from disk and verify the following actuate:

IRF CC15 100

IRF CC16 100

trgset 29 "CCLSRGTNKP(1) < 56"

trg 29 "MRF CC15 0"

trgset 30 "CCLSRGTNKP(1) < 56"

trg 30 "MRF CC16 0" Acknowledge as Chemistry request to sample letdown for placing letdown mixed bed demin back on line.

Acknowledge as Shift Manager the failures, request for maintenance support, and IR request.

Event 4: Main generator voltage regulator failure Insert IMF EG03 90 96 180 (start malfunction at 90 and ramp to 96 in 180 sec.) for main generator voltage regulator failed.

Acknowledge as SM voltage regulator failure, on line risk assessment, requests for maintenance and OAD support, and IR request.

Acknowledge as Power Team failure of generator voltage regulator.

Comments:

NRC 11-spare Page 6 of 24

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 5: 1A Heater Drain Pump trip Insert IMF FW35A As SM, acknowledge the failure, 1BwOA SEC-1 entry, request for E Plan evaluation, and requests for on line risk assessment, maintenance support, and IR initiation.

If dispatched as EO, report 1A Heater Drain pump is seized and report ground overcurrent flag at breaker cubicle.

If dispatched as Equipment Operator, report you will complete pump vent alignment per BwOP HD-2 for tripped pump.

Events 6: PZR vapor space LOCA/ turbine auto trip failure / SI auto actuation failure Insert IMF TH01 0.5 30 Acknowledge as Shift Manager procedure changes, Emergency Plan evaluations, STA request, and requests for support personnel.

After STA requested, as STA report CSF status: yellow on core cooling if RCS subcooling is unacceptable, yellow on inventory when PZR level > 92%

Comments:

NRC 11-spare Page 7 of 24

Scenario NRC 11-spare Event 1 No: No.

Event 1PR11J filter change

==

Description:==

Time Position Applicants Actions or Behavior CUE

Request from RP to shutdown 1PR11J for filter change BOP

Refer to BwOP AR/PR-19, ROUTINE SKID MOUNTED PROCESS RADIATION MONITOR OPERATIONS

Notify US of 1PR11J filter change request.

Secure 1PR11J

Select Grid 2 on RM-11

Select 1PR11J

Depress flow button to secure 1PR11J.

US

Recognize entry conditions for TS LCO 3.4.15, condition B.

o Inform SM of TS 3.4.15 entry CUE

Request from RP to startup 1PR11J following filter change BOP

Refer to BwOP AR/PR-19

Start 1PR11J

Select Grid 2 on RM-11

Select 1PR11J

Depress flow button to start 1PR11J

Verify flow indicated on 1PR11J

Notify US of completion of 1PR11J filter change US o Inform SM of TS 3.4.15 exit 90 minutes after 1PR11J is restarted and no associated alarms have occurred.

NOTE: After the actions for 1PR11J are complete and with lead examiner concurrence, enter next event.

Comments:

NRC 11-spare Page 8 of 24

Scenario NRC 11-spare Event 2 No: No.

Event PZR level channel 1LT-459 fails high.

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator 1-12-A3, PZR LEVEL HIGH RX TRIP STPT ALERT

Annunciator 1-12-C3, PZR LEVEL CONT DEV HIGH HTRS ON

Annunciator 1-9-D3, CHG LINE FLOW HIGH LOW

PZR level and charging flow lowering.

ATC

Determine PZR level and/or charging header flow lowering at 1PM05J.

Identify 1LI-459 is failing high.

Report failure to US.

Perform the following at 1PM05J:

Place 1LK-459, PZR master level controller, OR 1FK-121, CV pumps flow control valve, in manual.

Raise demand on 1LK-459 OR 1FK-121 sufficiently to raise charging flow and PZR level.

Operate 1LK-459 OR 1FK-121 in manual to restore PZR level to normal operating band and maintain 8-13 gpm RCP seal injection flow.

Reference BwARs 1-12-A3/1-12-C3/1-9-D3.

CREW

Reference BwARs 1-12-A3/1-12-C3/1-9-D3.

Identify entry conditions for 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL.

US

Notify Shift Manager of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Implement 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment C, PRESSURIZER LEVEL CHANNEL FAILURE, and direct operator actions of 1BwOA INST-2 to establish the following conditions:

o Direct BOP/RO to stop load ramp/dilution.

ATC

Check PZR level at 1PM05J:

PZR level - normal on 1LI-460 & 1LI-461.

Manually restore PZR level using 1LK-459 or 1FK-121.

Select operable PZR level control channel:

Place PZR level control select C/S to CH 461/460.

Select operable PZR level channel for PZR level recorder at 1PM05J:

Verify PZR level channel to recorder select switch in 460.

Check letdown and PZR heaters at 1PM05J:

Check PZR level > 17% on 1LI-460 & 1LI0461.

Comments:

NRC 11-spare Page 9 of 24

Scenario NRC 11-spare Event 2 No: No.

Event PZR level channel 1LT-459 fails high.

==

Description:==

Time Position Applicants Actions or Behavior

Check letdown flow established:

o Check valve alignment.

o Letdown flow approximately 120 gpm on 1FI-132.

Check PZR heaters:

PZR heaters available in auto.

Check PZR level control in auto at 1PM05J:

Verify/place the following components in AUTO:

1LK-459, master PZR level controller.

1FK-121, CV pumps flow control valve.

BOP

Perform the following:

o Request operations support for tripping bistables.

o Assist US by making notifications.

o Refer to BwARs.

US

Determine TS 3.3.1, conditions A and K are applicable.

Determine TS 3.3.3 and 3.3.4 are NOT applicable - minimum channels operable requirement is met.

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

EVALUATOR NOTE: After the actions for the pressurizer level channel failure are complete and with lead examiners concurrence, insert the next event.

Comments:

NRC 11-spare Page 10 of 24

Scenario NRC 11-spare Event 3 No: No.

Event 1A letdown HX tube leak.

==

Description:==

Time Position Applicants Actions or Behavior CUE o Annunciator 1-2-A5, CC SURGE TANK LEVEL HIGH/LOW

1PR09J, CC HX OUTLET RAD MONITOR, alarming at the RM-11 console.

Letdown flow lowering on 1FI-132 at 1PM05J.

CC surge tank level rising on 1LI-670 & 1LI-676 at 1PM06J.

1CC017, CC surge tank vent valve, CLOSED at 1PM06J.

CREW

Reference BwARs.

Identify entry conditions for 1BwOA PRI-6, COMPONENT COOLING MALFUNCTION.

US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Implement 1BwOA PRI-6, COMPONENT COOLING MALFUNCTION, and direct operator actions of 1BwOA PRI-6 to establish the following conditions:

BOP

Check CC surge tank level at 1PM06J:

CC surge tank level > 13% and rising on 1LI-670 & 1LI-676.

US

Determine 1BwOA PRI-6, Attachment B, ABNORMAL CC SURGE TANK LEVEL, needs to be implemented.

BOP

Check CC surge tank level at 1PM06J:

CC surge tank level > 13% and rising on 1LI-670 & 1LI-676.

o Dispatch operators to drain CC surge tank.

CREW

Check for leakage from RCP thermal barrier at 1PM05J:

Annunciator 1-7-E4, RCP THERM BARR CC WTR FLOW HIGH/LOW - NOT LIT.

Seal injection flows stable on 1FI142A - 1FI-145A.

CREW

Isolate CC system inleakage:

1PR09J, CC HX OUTLET RAD MONITOR, radiation level rising and/or alarming at the RM-11 console.

Notify chemistry to sample CC system.

Determine leak exists in letdown heat exchanger.

Letdown flow lowering on 1FI-132 at 1PM05J.

VCT level lowering on 1LI-112/1LR-185 at 1PM05J.

o Place 1CV-112A, letdown to VCT or HUT divert valve, in the HUT position to divert letdown to the HUT.

ATC o Isolate normal CV letdown at 1PM05J in accordance with BwOP CV-17, ESTABLISHING AND SECURING NORMAL AND RH LETDOWN FLOW:

Comments:

NRC 11-spare Page 11 of 24

Scenario NRC 11-spare Event 3 No: No.

Event 1A letdown HX tube leak.

==

Description:==

Time Position Applicants Actions or Behavior o Close 1CV8149A, B, & C, letdown orifice isolation valves.

o Close 1CV459 & 1CV460, letdown line isolation valves.

o Close 1CV8152 & 1CV8160, letdown line CNMT isolation valves.

o Place 1FK-121, CV pumps flow control valve, in manual and lower demand on 1FK-121 while concurrently adjusting 1CV182, charging header backpressure control valve, to control RCP seal injection 8-13 gpm per RCP.

o Close 1CV8105 & 1CV8106, charging line CNMT isolation valves.

Monitor RMCS during automatic VCT makeup:

Proper flow indicated on PW/Total Flow (1FT-0111) and Boric Acid Flow (1FT-0110).

EVALUATOR NOTE: The crew may elect to leave the 1A letdown heat exchanger isolated place excess letdown on line. The steps for placing excess letdown on line are on page 15.

Swap letdown heat exchangers in accordance with BwOP CV-22, OPERATION OF LETDOWN & REGEN HEAT EXCHANGERS:

Contact operators to locally align and vent 1B letdown HX.

Open 1CV8401B, letdown HX 1B inlet valve, at 1PM05J.

Close 1CV8401A, letdown HX 1A inlet valve at 1PM05J.

Contact operators to locally close 1CC9452A & B, letdown HX 1A CC inlet and outlet isolation valves.

o Contact operators to locally close 1CV8467A.

ATC/ o Perform the following at 1PM05J to establish normal letdown flow through the 1B BOP letdown heat exchanger in accordance with BwOP CV-17, ESTABLISHING AND SECURING NORMAL AND RH LETDOWN FLOW: (N/A if excess letdown established)

Verify/close 1CV8149A, B, & C, letdown orifice isolation valves.

o Contact operators to locally verity CC locally aligned to 1B letdown HX.

Place 1PK-131, letdown line pressure controller, in manual and raise demand to 40%.

Place 1CC-130A, letdown HX outlet temperature controller, in manual and raise demand to 60%.

Open 1CV459 & 1CV460, letdown line isolation valves.

Open 1CV8324A, charging to regen HX 1A isolation valve.

Open 1CV8389A, letdown to regen HX 1A isolation valve.

Open 1CV8152 & 1CV8160, letdown line CNMT isolation valves.

Verify OFF light is lit above BTRS mode selector C/S.

Verify/open 1CV8401B, letdown HX 1B inlet valve.

Comments:

NRC 11-spare Page 12 of 24

Scenario NRC 11-spare Event 3 No: No.

Event 1A letdown HX tube leak.

==

Description:==

Time Position Applicants Actions or Behavior

Verify/closed 1CV8147, PZR aux spray valve.

Verify/open 1CV8145, charging to loop 1A isolation valve.

Open 1CV8105 & 1CV8106, charging line CNMT isolation valves.

Control 1FK-121, CV pumps flow control valve, in manual to raise letdown flow to 100 gpm while concurrently adjusting 1CV182, charging header backpressure control valve, to control RCP seal injection 8-13 gpm per RCP.

Open 1CV8149A/B/C, letdown orifice isolation valves, as necessary to establish desired letdown flow while concurrently and controlling 1PK-131, letdown line pressure controller, in manual to maintain letdown pressure 360-380 psig.

Control 1CC130A, letdown HX outlet temperature controller, in manual to maintain letdown temperature 90-115°F.

Place 1FK-121, 1PK-131 & 1CC130A in auto.

Verify 1PR06J in service at the RM-11 console.

BOP o Perform the following at 1PM05J to establish excess letdown flow in accordance with BwOP CV-15, EXCESS LETDOWN OPERATIONS: (N/A if normal letdown established)

Verify/open 1CV8100 & 1CV8112, seal water return CNMT isolation valves, at 1PM05J.

Open 1CC9437A & 1CC9437B, CC to excess letdown HX isolation valves, at 1PM06J.

Verify/close (at 0% demand) 1HCV-CV123, excess letdown HX flow control valve, at 1PM05J.

Verify/place in VCT position 1CV8143, excess letdown to seal filter or RCDT valve, at 1PM05J.

Open 1RC8037A, B, C, & D, RCS loop drain valves, at 1PM05J.

Open 1CV8153A & 1CV8153B, excess letdown HX 1A & 1B inlet isolation valves, at 1PM05J.

Raise demand on 1HCV-CV123, excess letdown HX flow control valve, while maintaining excess letdown outlet temperature < 165°F on 1TI-122A at 1PM05J.

US

Inform SM/Maint of 1A letdown HX leak, IR, EAL evaluation, and contact maintenance to investigate/correct letdown HX leak.

o Evaluate tech spec 3.4.13 for applicability.

EVALUATOR NOTE: After the actions for letdown heat exchanger leak are complete and with lead examiners concurrence, enter next event.

Comments:

NRC 11-spare Page 13 of 24

Scenario NRC 11-spare Event 4 No: No.

Event Generator voltage regulator failure

==

Description:==

Time Position Applicants Actions or Behavior CUES

Annunciator GENERATOR FIELD FORCING (1-19-B6)

1IIMP023, Exciter Field Current, rising.

1VIMP006, Main Generator Output VARS, rising.

CREW

Refer to BwARs

Determine generator voltage regulator failing.

US

Direct/Ensure BOP takes manual control of generator voltage regulator and lowers generator field current.

o Inform SM of voltage regulator failure.

o Direct BOP/RO to stop load ramp/dilution BOP

Perform the following at 1PM01J:

Place voltage regulator to off.

Place base adjuster to lower.

Lower exciter field to < 100 amps prior to main generator trip.

CREW

Refer to 1BwGP 100-3A6 and 1BwGP 100-3A7 for generator MW, and generator VARS within limits BOP

Maintain generator field current, generator MW, and generator VARS within limits by operating the base adjuster.

US

Contact SM to perform risk assessment, initiate IR, and contact additional personnel to investigate/correct instrument failure.

Notify Power Team of voltage regulator failure.

EVALUATOR NOTE: After the actions for voltage regulator failure are complete and with lead examiner concurrence, enter next event.

Comments:

NRC 11-spare Page 14 of 24

Scenario NRC 11-spare Event 5 No: No.

Event 1A Heater Drain Pump trip

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator HD PUMP TRIP (1-17-D2)

HD Tank level rising

HD Pump discharge valves opening BOP

Recognizes 1A HD pump tripped o Refer to BwAR 1-17-D2 as time permits

Reports failure to US

Recognizes one Heater Drain Pump running CREW

Identify entry conditions for 1BwOA SEC-1, SECONDARY PUMP TRIP US

Acknowledge 1A HD pump trip

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct failure

Implement 1BwOA SEC-1, SECONDARY PUMP TRIP Attachment C "HD PUMP TRIP" and direct operator actions of 1BwOA SEC-1 to establish the following conditions.

BOP

Recognizes standby HD pump NOT AVAILABLE

Check HD pump status

ONLY 1C HD pump running

Initiate turbine load reduction to 780 MW at 20 MW/min

Initiate HD runback on OWS graphic 5512

Verify turbine load lowering BOP

Check HD Tank level

Level > 72% and rising

Maintain HD tank level o Verify 1HD046A &B in AUTO o Open 1CB113A-D o Manually open 1HD117, HD tank overflow valve o Lower turbine load as necessary to maintain HD tank level <72%

Check 1HD117, HD tank overflow valve in auto and closed o Lower turbine load as necessary to close 1HD117

Check 1C HD pump parameters

1C HD pump amps < 168 amps

1C HD pump flow < 2950 KLB/HR o Lower turbine load as necessary to restore 1C HD pump parameters Comments:

NRC 11-spare Page 15 of 24

Scenario NRC 11-spare Event 5 No: No.

Event 1A Heater Drain Pump trip

==

Description:==

Time Position Applicants Actions or Behavior

Deactivate turbine runback.

US/

Check PDMS operable ATC

Annunciator PDMS INOPERABLE not lit (1-10-E8)

1BwOS PDMS-1A not implemented

Annunciator PDMS LIMIT EXCEEDED not lit (1-10-D7)

ATC

Control I near target

Operate control rods in manual to restore I near target

Monitor RCS parameters o If RCS pressure lowers < 2209 psig, notify US to enter TS 3.4.1, RCS DNB Limits o If control rods < low - 2 rod insertion limit, notify US to enter TS 3.1.6, Control Bank Insertion Limits ATC

Initiate RCS boration

Determine required boric acid volume (approximate band: 50 gal - 300 gal) o Determine from ReMa

Determine desired boric acid flow rate

Set 1FK-110 BA Flow Control to desired boration rate

Set 1FY-0110 BA Blender Predet Counter to desired volume.

Place MAKE-UP MODE CONT SWITCH to STOP position

Place MODE SELECT SWITCH to BORATE position

Place MAKE-UP MODE CONT SWITCH to START

Verify proper operation of valves and BA transfer pump (1CV110B open, Boric Acid Transfer Pump running, 1CV110A throttles open, proper BA flow indicated on recorder).

o Turn on PZR backup heaters in accordance with BwOP RY-14, PRESSURIZER BACKUP HEATER OPERATION.

OR Batch addition of Boric Acid:

Open 1CV110B

Open 1CV110A

Start the BA Transfer pump

When desired amount of BA has been added, stop the BA Transfer Pump

Close 1CV110A

Close 1CV110B o May flush boric acid lines per BwOP CV-6 step. F.5.

BOP

Verify running CB pump recirc valves in auto Comments:

NRC 11-spare Page 16 of 24

Scenario NRC 11-spare Event 5 No: No.

Event 1A Heater Drain Pump trip

==

Description:==

Time Position Applicants Actions or Behavior

1CB113A-D on running pumps

Dispatch operators to perform BwOP HD-2 for 1A HD pump

Shutdown CD/CB pump (if started during procedure performance)

US

Notify chemistry to monitor secondary plant chemistry

Notify SM to perform risk assessment

Check reactor power change > 15% in one hour o Notify chemistry to perform TS 3.4.16 sampling o Notify rad protection to perform RETS 12.4.1.A sampling o Refer to BwOP FW-26 to evaluate FW venturi fouling o Determine TS 3.1.6, condition A entry required if control rods below low - 2 rod insertion limit The next event to be inserted when the Lead Examiner is satisfied the crew has adequately addressed the HD pump trip. Suggest the malfunction be inserted during latter part of the turbine runback when crew is attempting to find a turbine load that allows HD tank overflow valve to be closed.

Comments:

NRC 11-spare Page 17 of 24

Scenario NRC 11-spare Event 6&7 No: No.

Event PZR vapor space LOCA/turbine auto trip failure/ auto SI failure

==

Description:==

Time Position Applicants Actions or Behavior CUE o Annunciator 1-12-C1, PZR PRESS CONT DEV LOW/ HTRS ON

Lowering PZR pressure.

CREW

Identify entry conditions for 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.

Trip reactor.

US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Enter/Implement 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, and direct operator actions of 1BwEP-0 to establish the following conditions:

ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J:

Verify reactor trip.

Rod bottom lights - ALL LIT.

Reactor trip & Bypass breakers - OPEN.

Neutron flux - DROPPING.

BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J or Operator Work Station drop 210 (DEH computer terminal located behind Unit 1 desk):

Verify Turbine Trip.

All Turbine throttle valves - OPEN.

All Turbine governor valves - OPEN.

[CT]

Manually trip the turbine:

E-0--Q o Depress turbine trip pushbutton at 1PM02J.

o Select turbine trip at Operator Work Station drop 211 at 1PM02J.

o Select turbine trip at Operator Work Station drop 210 (DEH computer terminal located behind Unit 1 desk).

BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J:

Verify power to 4KV busses.

ESF Buses - BOTH ENERGIZED (141 & 142).

CREW Perform immediate operator actions of 1BwEP-0 at 1PM04J, 1PM05J, & 1PM06J:

o Check SI actuated at 1PM05J and 1PM06J:

o Annunciator 1-11-C1, PZR PRESS LO SI/RX TRIP - LIT.

o STEAMLINE LOW PRESS SI/RX TRIP - LIT.

Comments:

NRC 11-spare Page 18 of 24

Scenario NRC 11-spare Event 6&7 No: No.

Event PZR vapor space LOCA/turbine auto trip failure/ auto SI failure

==

Description:==

Time Position Applicants Actions or Behavior o SI ACTUATED Bypass Permissive - LIT.

o SI equipment automatically actuated:

o 1A or 1B SI pump - NOT RUNNING.

o 1SI8801A or B, CV pump cold leg injection valve - OPEN.

o Check if SI required:

o PZR pressure cannot be maintained > 1829 psig.

o Steamline pressure < 640 psig.

o Containment pressure > 3.4 psig.

[CT]

Manually actuate SI.

E-0--D US

Direct BOP to perform Attachment B of 1BwEP-0 EVALUATOR NOTE: US and RO will continue in 1BwEP-0 while BOP is performing Attachment B:

EVALUATOR NOTE: RCPs should be tripped when the crew identifies RCP trip criteria per 1BwEP-0 OAS.

BOP

Verify FW isolated at 1PM04J:

FW pumps - TRIPPED.

Isolation monitor lights - LIT.

FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C.

Verify DGs running at 1PM01J:

DGs - BOTH RUNNING.

1SX169A/B OPEN.

Dispatch operator locally to check operation

Verify Generator Trip at 1PM01J:

OCB 1-8 and 7-8 open.

PMG output breaker open.

Verify Control Room ventilation aligned for emergency operations at 0PM02J:

VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT.

Operating VC train equipment - RUNNING.

0B Supply fan

0B Return fan

0B M/U fan

0B Chilled water pump

0B Chiller

Operating VC train dampers - ALIGNED.

M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED.

0B VC train M/U filter light - LIT.

Comments:

NRC 11-spare Page 19 of 24

Scenario NRC 11-spare Event 6&7 No: No.

Event PZR vapor space LOCA/turbine auto trip failure/ auto SI failure

==

Description:==

Time Position Applicants Actions or Behavior

0VC09Y - OPEN

0VC313Y - CLOSED

Operating VC train Charcoal Absorber aligned for train B.

0VC44Y - CLOSED

0VC05Y - OPEN

0VC06Y - OPEN

Control Room pressure greater than +0.125 inches water on 0PDI-VC038.

Verify Auxiliary Building ventilation aligned at 0PM02J:

Two inaccessible filter plenums aligned.

Plenum A:

0VA03CB - RUNNING

0VA023Y - OPEN

0VA436Y - CLOSED

Plenum C:

0VA03CE RUNNING

0VA067Y - OPEN

0VA052Y - CLOSED

Verify FHB ventilation aligned at 0PM02J:

0VA04CB - RUNNING

0VA055Y - OPEN

0VA062Y - OPEN

0VA435Y - CLOSED

Notify US Attachment B complete ATC

Verify ECCS pumps running at 1PM05J/1PM06J:

BOTH CV pumps - RUNNING.

BOTH RH pumps - RUNNING.

BOTH SI pumps - RUNNING.

ATC

Verify RCFCs running in Accident Mode:

Accident Mode lights - ALL LIT at 1PM06J.

ATC /

Verify Phase A isolation:

BOP

Group 3 CNMT isolation monitor lights - ALL LIT at 1PM06J.

ATC /

Verify Cnmt Vent isolation:

BOP

Group 6 Cnmt Vent Isol monitor lights - ALL LIT at 1PM06J.

ATC /

Verify AF system at 1PM06J:

BOP

AF pumps - BOTH RUNNING.

Comments:

NRC 11-spare Page 20 of 24

Scenario NRC 11-spare Event 6&7 No: No.

Event PZR vapor space LOCA/turbine auto trip failure/ auto SI failure

==

Description:==

Time Position Applicants Actions or Behavior

1B AF pump - RUNNING.

AF isolation valves - OPEN.

1AF13A-H

AF flow control valves - THROTTLED

1AF005A-H - throttled ATC /

Verify CC pumps at 1PM06J:

BOP

CC pumps - BOTH RUNNING.

ATC /

Verify SX pumps at 1PM06J:

BOP

BOTH SX pump - RUNNING.

ATC /

Check if Main Steamline Isolation required at 1PM06J:

BOP

All SG pressure > 640 psig.

Containment pressure < 8.2 psig ATC/

Check if CS is required at 1PM06J:

BOP

CNMT pressure has not risen > 20 psig.

BOP/

Verify Total AF flow at 1PM06J:

ATC

AF flow > 500 gpm.

S/G NR levels - NOT rising in an uncontrolled manner.

ATC/ Note: the following task may have been performed earlier per note on page 18 BOP

Verify ECCS valve alignment at 1PM06J:

Group 2 Cold Leg Injection monitor lights required for injection - ALL LIT.

Verify ECCS flow at 1PM05J:

High Head SI flow >100 gpm (1FI-917).

RCS pressure > 1700 psig.

ATC

Check PZR PORVs and spray valves at 1PM05J:

PORV isolation valves:

1RY8000A & B - ENERGIZED

PORV relief paths:

1RY455A & 456- C/S in AUTO

1RY8000A & B - OPEN

1RY455B & 1RY455C - CLOSED Comments:

NRC 11-spare Page 21 of 24

Scenario NRC 11-spare Event 6&7 No: No.

Event PZR vapor space LOCA/turbine auto trip failure/ auto SI failure

==

Description:==

Time Position Applicants Actions or Behavior ATC

Maintain RCS temperature control at 1PM05J:

RCPs - NONE RUNNING: (If RCPs were tripped per OAS page)

Verify RCS average temperature stable at or trending to 557oF.

o Throttle AF flow.

ATC NOTE: this step may have been performed earlier per OAS summary page of 1BwEP-0.

Check status of RCPs at 1PM05J:

RCPs - NONE RUNNING: (If RCPs were tripped per OAS page).

Hi Head SI flow > 100 gpm

RCS Pressure < 1425 psig

STOP ALL RCPs BOP/

Check if SG secondary pressure boundaries are intact at 1PM04J:

ATC

Check pressure in all SGs:

None dropping in an uncontrolled manner.

None completely depressurized.

ATC/

Check secondary radiation normal BOP

Check Secondary trends at RM-11 or PPC:

1PR08J SG Blowdown.

1PR27J SJAE/GS.

1AR 22/23A-D Main steam lines.

BOP

Check if RCS is intact

CNMT Area Rad monitors - ABOVE ALERT Setpoint CREW Transition to 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.

Comments:

NRC 11-spare Page 22 of 24

Scenario NRC 11-1 Event 8 No: No.

Event PZR vapor space LOCA

==

Description:==

Time Position Applicants Actions or Behavior US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Request STA evaluation of status trees.

Enter/Implement 1BwEP-1 and direct operator actions of 1BwEP-1 to establish the following conditions:

ATC NOTE: this step may have been performed earlier per OAS summary page of 1BwEP-0.

Check status of RCPs at 1PM05J:

RCPs - NONE RUNNING: (If RCPs were tripped per OAS page)

Hi Head SI flow > 100 gpm

RCS Pressure < 1425 psig

STOP ALL RCPs ATC/

Check if SG secondary pressure boundaries are intact at 1PM04J:

BOP

Check pressure in all SGs:

None dropping in an uncontrolled manner.

None completely depressurized.

ATC/

Check intact SG levels at 1PM04J:

BOP

SG levels maintained between 10% (31%) and 50%.

S/G NR levels - NOT rising in an uncontrolled manner.

ATC/

Check secondary radiation normal BOP

Reset Phase A.

OPEN 1SD005A-D at 1PM11J

Contact Chemistry for SG sampling.

Check Secondary trends at RM-11 or PPC:

1PR08J SG Blowdown.

1PR27J SJAE/GS.

1AR 22/23A-D Main steam lines.

ATC

Check PZR PORVs and isolation valves at 1PM05J:

PORV isolation valves - 1RY8000B Energized but not responding.

PORVs - BOTH OPEN

PORV isolation valves - 1RY8000A previously CLOSED ATC/

Check if ECCS flow should be reduced at 1PM05J:

BOP

RCS subcooling - NOT acceptable.

Comments:

NRC 11-spare Page 23 of 24

Scenario NRC 11-1 Event 8 No: No.

Event PZR vapor space LOCA

==

Description:==

NOTE: Scenario is terminated at this point (Final)

Comments:

NRC 11-spare Page 24 of 24

Simulation Facility Braidwood Scenario Operating Test No.: 2011 NRC No.: EXAM NRC 11-5 Examiners: ______________________ Applicant: ____________________ SRO

______________________ ____________________ ATC

______________________ ____________________ BOP Initial Conditions: IC-13 Turnover: The unit is at 17% power, xenon building in, BOL, at 1BwGP 100-3 step 22. The main Turbine is at 1775 rpm ready for turbine trip test. Online risk is green. Following completion of turnover, the Shift Manager directs the crew to perform 1BwGP 100-3, step F.22.a through F.22.p, turbine trip test. 1BwOS TRM 3.3.g.3 and 3.3.g.4 will be performed concurrently by another operator who has also been briefed to take over at step F.22.q. for the turbine synchronization.

Event Malf. No. Event Event No. Type* Description Preload IOR ZDI1WO056A OPEN Fail 1WO056A open IRF RP29 OUT Slave relay for train A Phase A valves IRF RP37 OUT Slave relay for train A CS valves IMF MS01A 100 MSIVs fail to close IMF MS01B 100 IMF MS01C 100 IMF MS01D 100 IMF CC02B 200 1B CC pump pressure switch failed high IMF CS01B 1B CS pump trip IMF PN0686 OFF Turn off Drop 2 Sys. Trouble alarm 1 None N-BOP, US Turbine Overspeed trip test 2 IMF CV05 600 5 I-ATC, US Letdown line pressure controller 1PK-CV131 output fails high 3 IMF RX06K 0 15 I-BOP, US 1C SG NR level transmitter 1LT-539 fails low TS-US 4 IMF CC01B C-BOP, 1A component cooling pump trip with 1B TS-US component cooling pump discharge pressure switch failure 5 IMF MS07D 4.0 30 M-ALL Uncontrolled depressurization of all steam generators 6 Preload CS system failure to actuate

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

SCENARIO OVERVIEW The unit is at 17% power, xenon building in, BOL, at 1BwGP 100-3 step 22. The main Turbine is at 1775 rpm ready for turbine trip test. Online risk is green. Following completion of turnover, the Shift Manager directs the crew to perform 1BwGP 100-3, step F.22.a through F.22.p, turbine trip test. 1BwOS TRM 3.3.g.3 and 3.3.g.4 will be performed concurrently by another operator who has also been briefed to take over at step F.22 q. for the turbine synchronization.

After completing shift turnover and relief, the BOP will perform the turbine trip test per 1BwGP 100-3, step F.22.a thru F.22.p.

After the turbine trip test is complete, letdown pressure controller 1PK-131 output will fail high. The letdown PCV will close and letdown pressure will rise lifting the letdown line relief valve. The ATC will take manual control of letdown pressure controller and restore letdown pressure. The crew may isolate letdown due to the lifting letdown relief valve. If letdown is isolated, it will be restored per BwOP CV-17. US may choose to enter tech spec 3.4.13 and then exit when relief resets, or remain in tech spec until a RCS leakrate can verify no leakage.

After the 1PK-131 failure is addressed, 1C SG NR level transmitter 1LT-539 will fail low. 1FW530A, Feedwater Regulating Bypass Valve, will open fully and 1C SG level will rise. The BOP will take manual control of 1C SG level and stabilize 1C SG level. 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment E, will be implemented. The BOP will restore 1C SG level control to automatic after 1C SG level is restored to normal and an operable 1C SG NR level controlling channel is selected. Technical specifications 3.3.1, conditions A and E and 3.3.2, conditions A and D are applicable.

After the 1LT-539 failure is addressed, the 1A component cooling water pump will trip. When the 1A CC pump trips, the 1B and 0 CC pumps will not automatically start on low system discharge pressure due the 1B CC pump discharge pressure switch being failed high. The crew will manually start a standby CC pump, either the 1B or 0 CC pump, to restore system flow and dispatch operators to investigate the malfunctions.

If the 1A CC pump control switch is placed in PTL prior to manually starting a standby pump, the U-0 CC pump will automatically start. Technical specification 3.7.7, condition B applies until the 1A CC pump is placed in PTL (U-0 CC pump then becomes operable).

After the 1A CC pump trip is addressed, the 1D MS line ruptures inside containment. While performing the actions of 1BwEP-0, the crew should note the failure of a Phase A slave relay and manually align valves to close the WO containment penetrations. When containment pressure reaches 20 psig, Phase B actuates but the CS pumps do not start. The crew should manually realign the train A CS valves, which will start the 1A CS pump. Operators should transition to 1BwEP-2 and recognize that the MSIVs have failed to close and that an uncontrolled depressurization of all SGs is in progress. The crew should transition to 1BwCA-2.1 where they will throttle AF flow to the SGs, terminate SI and restore normal charging and letdown. An entry into 1BwFR-P.1 may be required as directed by the status trees.

Completion criteria is checking RCS subcooling per step 21 in 1BwCA-2.1 or completion of 1BwFR-P.1, step 21.

Critical Tasks

1. Manually close Phase A valves before transition out of 1BwEP-0 (UFSAR 15.1) (K/A number -

013000A4.01, importance - 4.5/4.8)

2. Manually actuate one train of containment spray prior to transition out of 1BwEP-0.

(ERG Critical Task number - E-0--E) (K/A number - 013000A4.01, importance - 4.5/4.8)

3. Manually lower AF flow to 45 gpm for each SG prior to completion of step 2 of 1BwCA-2.1.

(ERG Critical Task number - ECA-2.1--A) (K/A number - 0WE12EA1.3 importance - 3.4/3.9)

NRC 11-5 Page 2 of 22

SIMULATOR SETUP GUIDE:

Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.

Establish the conditions of IC-13, 17% power, xenon building.

Complete items on Simulator Ready for Training Checklist.

Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.

Place simulator in RUN and allow simulator to run during board walk down and turnover.

Run caep NRC 11-5 SETUP from disk and verify the following actuate:

IOR ZDI1WO056A OPEN

IRF RP29 OUT

IRF RP37 OUT

IMF MS01A 100

IMF MS01B 100

IMF MS01C 100

IMF MS01D 100

IMF CC02B 200

IMF CS01B

Verify SER and printer are clear of data.

Provide students with turnover sheets, 1BwOS NR-1, critical parameter sheet, Op Aids, Pre-Job Brief Forms.

NRC 11-5 Page 3 of 22

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Turbine Overspeed trip test.

Acknowledge as Shift Manager commencement and completion of test.

If contacted to coordinate performance of 1BwOS TRM 3.3.g.3 and 1BwOS TRM 3.3.g.4, inform crew that another extra NSO will perform the surveillances.

If contacted about zeroing of governor valve position limits, inform crew that governor valves positions have previously been zeroed and it will not be necessary to re-perform.

If contacted about continuing with turbine start up, inform crew that another NSO is being briefed for proceeding at step F.22.q.

Event 2: Letdown line pressure controller 1PK-CV131 output fails high.

Insert IMF CV05 600 5 for 1PK-131 failure.

If dispatched as EO to investigate 1PT-131, wait three minutes and report no visible damage to 1PT-131.

If dispatched as EO to align excess letdown to the top of the VCT, insert the following:

MRF CV26 100 to open 1CV8482

MRF CV27 0 to close 1CV8484 Acknowledge as SM 1PK-131 failure, on line risk assessment, requests for maintenance support, and IR requests.

Event 3: 1C SG NR level transmitter 1LT-539 fails low.

Insert IMF RX06K 0 15 to fail 1LT-539 low over a 15 second period.

As SM, if requested support for tripping bistables in AEER, report that AEER bistables are not to be tripped until work analyst and NSO support can be obtained (in approx. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) and that the abnormal operating procedure should be continued. AEER bistable tripping will be conducted later.

If lead examiner desires the bistables tripped, participate in brief and perform the following:

To trip the required bistables, participate in brief and perform the following:

As extra NSO contact Unit 1 (X-2209).

Insert the following:

MRF RP20 OPEN (open protection cabinet #1 door).

MRF RX063 TRIP (trip SG 3 P14 bistable LB539A).

MRF RX064 TRIP (trip SG 3 Lo-2/AF pump start bistable LB539B).

MRF RP20 CLOSE (close protection cabinet #1 door).

Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.

Acknowledge as Shift Manager on line risk assessment, request for IR, evaluation for reactivity screening, QNE and personnel notifications, and evaluation of continuing power operation.

NRC 11-5 Page 4 of 22

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 4: 1A component cooling pump trip with 1B component cooling pump discharge pressure switch failure.

Insert IMF CC01B to trip the 1A CC pump.

If dispatched as Equipment Operator to 1A CC pump and/or breaker, report phase A overcurrent present at pump breaker/no visible damage to pump locally.

If dispatched as Equipment Operator to 1B or 0 CC pump, report pump parameters normal.

If dispatched as Equipment Operator to 1PS-CC673B, report no visible damage to pressure switch.

Acknowledge as Equipment Operator/Field Supervisor request to align 0 CC pump to Bus 141.

Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.

Events 5 & 6: Uncontrolled depressurization of all SGs Insert IMF MS07D 4.0 30 to fault the 1D SG inside containment.

Acknowledge as Shift Manager procedure changes, Emergency Plan evaluations, STA request, and requests for support personnel.

If dispatched as local operator to investigate the breaker for 1WO056A (valve located inside containment),

wait approximately 2 minutes and report that the breaker is closed (MCC 132X2 Cub. 2).

After STA requested, as STA report CSF status: yellow on heat sink until AF flow lowered < 500 gpm, then report red on heat sink. Do not report orange path on containment pressure NRC 11-5 Page 5 of 22

Scenario NRC 11-5 Event 1 No: No.

Event Turbine Overspeed Trip Test

==

Description:==

Time Position Applicants Actions or Behavior CUE o From turnover, perform Turbine Overspeed Trip Test per 1BwGP 100-3 steps F.22.a thru p.

US

Directs BOP to perform turbine overspeed trip test.

o Perform pre-job brief per HU-AA-1211 PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY, AND POST JOB BRIEFINGS for load ramp.

CREW o Review Precautions, and Limitations and Actions, if not already performed during pre-job brief.

BOP

Test turbine overspeed trip at 1PM02J or OWS drop 210 by performing the following:

Select ENABLE ETS 1800 RPM TRIP TEST.

Select EXECUTE.

Verify TRIP SETPOINT window value changes to 1800.0.

Select SETPOINT.

Enter 1805 into REF DEMAND window.

Verify 1805 appears in REF DEMAND window.

Select ENTER.

Enter 20 (or less) into the RATE window.

Select ENTER.

Verify correct value appears in RATE window.

Select EXIT.

o Notify US and RO of pending test.

Select GO/HOLD.

Verify GO/HOLD button illuminates.

Verify HOLD illuminated RED.

Select GO.

Verify GO illuminates RED.

Verify turbine trips at approx. 1800 RPMs.

Verify all turbine control valves have CLOSED.

When turbine speed is less than 1700 RPMs perform the following:

Select LIMITERS field.

Select VPL up arrow until display indicates 120%.

Select EXIT.

Select REARM FROM TRIP (LATCH)

Select LATCH.

Comments:

NRC 11-5 Page 6 of 22

Scenario NRC 11-5 Event 1 No: No.

Event Turbine Overspeed Trip Test

==

Description:==

Time Position Applicants Actions or Behavior

Verify TURBINE TRIPPED field turns grey.

Verify TURBINE LATCHED and REARM FROM TRIP fields turn green.

Verify turbine speed stabilizes.

Select SETPOINT.

Enter 1700 into REF DEMAND window.

Verify 1700 appears in REF DEMAND window.

Select ENTER.

Enter 50 (or less) into the RATE window.

Select ENTER.

Verify correct value appears in RATE window.

Select EXIT.

Select GO/HOLD.

Verify GO/HOLD button illuminates.

Verify HOLD illuminated RED.

Select GO.

Verify GO illuminates RED.

Verify turbine acceleration stops at approx. 1700 RPMs.

Verify GO indicator red goes off.

o Notify US of completion of overspeed trip test.

ATC o Peer check actions of BOP operator.

o Monitor remainder of MCB.

US

Acknowledge report.

o Notify SM 1BwOP GP 100-3 is complete through step F.22.p.

EVALUATOR NOTE: After turbine overspeed trip test is complete and with lead examiners concurrence, enter next event.

Comments:

NRC 11-5 Page 7 of 22

Scenario NRC 11-5 Event 2 No: No.

Event 1PK-CV131 output fails high

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator LP LTDWN RLF TEMP HIGH (1-9-B1)

Annunciator LTDWN HX OUTLT PRESS HIGH (1-8-B5)

1FI-132, letdown line flow, lowering.

1PI-131, letdown line pressure, rising.

CREW

Refer to BwARs

Recognize 1PK-131 failed.

US o Direct/Ensure RO takes manual control of 1PK-131 and returns letdown pressure to normal.

Inform SM of 1PK-131 failure.

o Direct RO to isolate letdown.

ATC

Perform the following at 1PM05J:

Place 1PK-131, letdown line pressure control valve, in manual.

Raise demand on 1PK-131.

Lower letdown line pressure sufficiently to close letdown line relief valve and restore letdown flow to normal.

Maintain letdown flow and pressure by operating 1PK-131 in manual.

o May take manual control of 1TK-130 US

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

o May choose to enter tech spec 3.4.13 and then exit when relief resets, or remain in tech spec until a RCS leakrate can verify no leakage.

EVALUATORS NOTE: The crew may elect to isolate letdown based on letdown relief valve lifting. The steps for isolating letdown and restoring normal letdown are in italics on the next page.

Comments:

NRC 11-5 Page 8 of 22

Scenario NRC 11-5 Event 2 No: No.

Event 1PK-CV131 output fails high

==

Description:==

Time Position Applicants Actions or Behavior ATC/ o Isolate letdown BOP o Close 1CV8149A, B, & C o Close 1CV459 & 1CV460 o Place 1CV121 in manual and control RCP seal injection 8-13 gpm per RCP o Close 1CV8105/8106 o Monitor RMCS during automatic VCT makeup o Proper flow indicated on PW/Total Flow (1FT-0111) and Boric Acid Flow (1FT-0110).

ATC/ o Establish normal letdown per BwOP CV-17 BOP o Verify/close 1CV8149A/B/C o Place 1CV131 manual at 30% demand o Place 1CC130 in manual at 60% demand o Open 1CV459/460 o Verify open 1CV8324B & 1CV8389B o Open 1CV8152/8160 o Verify/open 1CV381A/B open o Open 1CV8105/8106 o Adjust charging flow to approx. 100 gpm w/seal injection 8-10 gpm per RCP o Open 1CV8149A/B/C, control 1CV131 to maintain letdown press. 360-380 psig o Control 1CC130 to maintain letdown temperature 90-115°F o Place controllers in auto o Verify 1PR06J in service ATC o Verify proper operation of RMCS during VCT makeup o Proper flow indicated on PW/Total Flow (1FT-0111) and Boric Acid Flow (1FT-0110).

o Restore PZR level to program Initiate the next event when the lead examiner approves.

Comments:

NRC 11-5 Page 9 of 22

Scenario NRC 11-5 Event 3 No: No.

Event 1C SG NR level transmitter 1LT-539 fails low

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator 1-15-C9, S/G 1C LEVEL DEVIATION HIGH LOW

Annunciator 1-15-C5, S/G 1C LVL LO-2 RX TRIP ALERT

SG 1C feed flow and NR level rising.

BOP

Determine SG 1C feed flow and/or NR level rising at 1PM04J.

Identify 1LI-539 indicates low SG NR level at 1PM04J.

Reference BwARs 1-15-C5 & 1-15-C9.

CREW

Identify entry conditions for 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL.

US

Notify Shift Manager of SG level channel failure.

Implement 1BwOA INST-2 OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment E, NARROW RANGE SG LEVEL CHANNEL FAILURE, and direct operator actions of 1BwOA INST-2 to establish the following conditions:

BOP

Stabilize 1C SG level at 1PM04J:

Place 1FK-530D, FW Reg Bypass Valve 1FW530 controller, in manual.

Lower demand on 1FK-530 sufficiently to lower feedwater flow to restore 1C SG level.

Operate 1FK-530D in manual to stabilize 1C SG level in the normal operating band.

Select operable 1C SG NR level channel. (per BwAR or 1BwOA INST-2)

Place 1C SG water level channel select C/S to L-558.

Establish automatic level control by placing 1FK-530D in auto.

ATC

Perform the following:

Monitor reactor power at 1PM05J.

Assist US by making notifications.

Refer to BwARs.

US

Determine AMS channel NOT affected.

Determine TS 3.3.1 conditions A and E are applicable.

Determine TS 3.3.2 conditions A and D are applicable.

Contact SM to perform risk assessment, initiate IR, and contact maintenance to Comments:

NRC 11-5 Page 10 of 22

Scenario NRC 11-5 Event 3 No: No.

Event 1C SG NR level transmitter 1LT-539 fails low

==

Description:==

Time Position Applicants Actions or Behavior investigate/correct instrument failure, and make other notifications.

EVALUATOR NOTE: After the actions for SG level channel failure are complete and with lead examiners concurrence, enter next event.

Comments:

NRC 11-5 Page 11 of 22

Scenario NRC 11-5 Event 4 No: No.

Event 1A component cooling pump trip with 1B component cooling pump discharge pressure

==

Description:==

switch failure Time Position Applicants Actions or Behavior CUE

Annunciator 1-2-A4, CC PUMP TRIP

Annunciator 1-2-A7, SEAL WTR HX CC FLOW LOW

Annunciator 1-2-B5, CC PUMP DSCH PRESS LOW

Annunciator 1-2-D7, CNMT PEN CLG FLOW HIGH LOW

Annunciators 1-7-A4/B4/C4/D4, RCP 1A/B/C/D THERM BARR CC WTR FLOW LOW

Annunciators 1-7-A5/B5/C5/D5, RCP 1A/B/C/D BRNG CC WTR FLOW LOW

Annunciator 1-7-E4, RCP THERM BARR CC WTR FLOW HIGH LOW

1A CC pump run amber trip light lit at 1PM06J.

BOP

Determine 1A CC pump has tripped.

o Place 1A CC pump in PTL

Report failure to US.

Determine 1B or 0 CC pump needs to be started.

Dispatch operator to investigate 1A CC pump trip.

Refer to BwARs.

EVALUATOR NOTE: The unit supervisor may elect to implement 1BwOA PRI-6, COMPONENT COOLING MALFUNCTION, based on CC system annunciator status.

1BwOA PRI-6 steps are in italics on the next page.

US

Direct BOP to start 1B or 0 CC pump.

BOP

Start 1B or 0 CC pump at 1PM04J.

o Refer to BwOP CC-1 and BwOP CC-2 for CC pump start/stop follow up actions.

ATC

Perform the following:

Monitor RCP operation while CC pump evolutions in progress.

Assist US by making notifications.

Refer to BwARs.

US

Determines TS 3.7.7 condition B is applicable (entered and exited).

Inform SM/Maint of 1B CC pump pressure switch failure, IR, and contact maintenance to investigate/correct instrument failure.

EVALUATOR NOTE: After the actions for CC pump trip and discharge pressure switch failure are complete and with lead examiners concurrence, enter next event.

Comments:

NRC 11-5 Page 12 of 22

Scenario NRC 11-5 Event 4 No: No.

Event 1A component cooling pump trip with 1B component cooling pump discharge pressure

==

Description:==

switch failure Time Position Applicants Actions or Behavior CREW o Identify entry conditions for 1BwOA PRI-6, COMPONENT COOLING MALFUNCTION.

US o Notify SM of plant status and procedure entry.

o Request evaluation of Emergency Plan conditions.

o Implement 1BwOA PRI-6, COMPONENT COOLING MALFUNCTION, and direct operator actions of 1BwOA PRI-6 to establish the following conditions:

BOP o Check CC surge tank level at 1PM04J:

o 1LI-670 and 1LI-676 greater than 13% and stable o Check CC pumps at 1PM04J:

o CC pumps - NONE running o Manually start 1B or 0 CC pump o Check annunciator 1-2-B5, CC PUMP DSCH PRESS LOW - NOT LIT o Check CC system temperature at 1PM04J:

o Annunciator 1-2-D5, CC PUMP SUCT TEMP HIGH - NOT LIT o 1TI-674 and 1TI-676 less than 105°F o Check RCP cooling:

o RCPs - ALL running o All block 7 annunciators clear o 1PR09J and 0PR09J trends normal for plant conditions at RM-11 or HMI terminal o 1CC685, RCP thermal barrier isolation valve - OPEN o Check RCP temperatures acceptable for RCP operation.

o Check letdown temperature o Letdown in service o Annunciator 1-8-C5, LTDWN HX OUTLET TEMP HIGH - NOT LIT o Annunciator 1-9-E2, LTDWN TEM HIGH - NOT LIT o Check CC surge tank level o 1LI-670 and 1LI-676 between 50% and 65%.

US o Determines TS 3.7.7 condition B is applicable.

o Inform SM/Maint of 1B CC pump pressure switch failure, IR, and contact maintenance to investigate/correct instrument failure.

Comments:

NRC 11-5 Page 13 of 22

Scenario NRC 11-5 Event 5&6 No: No.

Event Steam leak inside containment/uncontrolled depressurization of all SGs

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator STEAM LINE LOW PRESS SI/RX TRIP (1-11-D1)

Annunciator S/G 1D LOW PRESS STEAMLINE ISOL ALERT (1-15-D1)

Rx Trip breakers open US

Notifies SM of plant status and procedure entry o Requests evaluation of Emergency Plan conditions

Enter/Implement 1BwEP-0 and direct operator actions of 1BwEP-0 ATC Perform immediate operator actions of 1BwEP-0:

Verify reactor trip

Rod bottom lights - ALL LIT

Reactor trip & Bypass breakers - OPEN

Neutron flux - DROPPING BOP Perform immediate operator actions of 1BwEP-0:

Verify Turbine Trip

All Turbine throttle valves - CLOSED

All Turbine govenor valves - CLOSED BOP Perform immediate operator actions of 1BwEP-0:

Verify power to 4KV busses

ESF Buses - BOTH ENERGIZED ATC Perform immediate operator actions of 1BwEP-0:

Check SI status

Annunciator CNMT PRESS HIGH SI/RX TRIP (1-11-E1) - LIT

Manually actuate SI US

Direct BOP to perform Attachment B of 1BwEP-0 EVALUATOR NOTE: US and RO will continue in 1BwEP-0 while BOP is performing Attachment B:

Comments:

NRC 11-5 Page 14 of 22

Scenario NRC 11-5 Event 5 No: No.

Event Steam leak inside containment/uncontrolled depressurization of all SGs

==

Description:==

Time Position Applicants Actions or Behavior BOP

Verify FW isolated at 1PM04J:

FW pumps - TRIPPED.

Isolation monitor lights - LIT.

FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C.

Verify DGs running at 1PM01J:

DGs - BOTH RUNNING.

1SX169A/B OPEN.

Dispatch operator locally to check operation

Verify Generator Trip at 1PM01J:

OCB 1-8 and 7-8 are closed.

o Open OCB 1-8 and 7-8 at 0PM03J.

PMG output breaker open.

Trip all running HD pumps (none running).

Verify Control Room ventilation aligned for emergency operations at 0PM02J:

VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT.

Operating VC train equipment - RUNNING.

0B Supply fan

0B Return fan

0B M/U fan

0B Chilled water pump

0B Chiller

Operating VC train dampers - ALIGNED.

M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED.

0B VC train M/U filter light - LIT.

0VC09Y - OPEN

0VC313Y - CLOSED

Operating VC train Charcoal Absorber aligned for train B.

0VC44Y - CLOSED

0VC05Y - OPEN

0VC06Y - OPEN

Control Room pressure greater than +0.125 inches water on 0PDI-VC038.

Verify Auxiliary Building ventilation aligned at 0PM02J:

Two inaccessible filter plenums aligned.

Plenum A:

0VA03CB - RUNNING

0VA023Y - OPEN Comments:

NRC 11-5 Page 15 of 22

Scenario NRC 11-5 Event 5 No: No.

Event Steam leak inside containment/uncontrolled depressurization of all SGs

==

Description:==

Time Position Applicants Actions or Behavior

0VA436Y - CLOSED

Plenum C:

0VA03CF RUNNING

0VA072Y - OPEN

0VA438Y - CLOSED

Verify FHB ventilation aligned at 0PM02J:

0VA04CB - RUNNING

0VA055Y - OPEN

0VA062Y - OPEN

0VA435Y - CLOSED

Notify US Attachment B complete ATC/

Verify ECCS pumps running BOP

Both CV pumps - RUNNING

Both RH pumps - RUNNING

Both SI pumps - RUNNING ATC/

Verify RCFCs running in Accident Mode - Group 2 RCFC Accident Mode lights - LIT BOP

Verify Phase A isolation - Group 3 Cnmt Isol monitor lights - NOT ALL LIT

[CT]

Close 1WO020A o Close 1WO056B o Close 1WO006A

Verify Cnmt Vent isolation - Group 6 Cnmt Vent Isol monitor lights - LIT

Verify AF system:

AF pumps - BOTH RUNNING

AF isolation valves - OPEN

1AF13A-H

AF flow control valves - THROTTLED

1AF005A-H

Verify CC pumps - U-0 and 1B RUNNING

Verify SX pumps- BOTH RUNNING ATC/

Check Main Steamlines Should Be Isolated BOP

CNMT pressure > 8.2 psig

Verify MS isolation

MSIVs open

Manually actuate MS isolation

MSIVs remain open Comments:

NRC 11-5 Page 16 of 22

Scenario NRC 11-5 Event 5 No: No.

Event Steam leak inside containment/uncontrolled depressurization of all SGs

==

Description:==

Time Position Applicants Actions or Behavior BOP/

Check if CS is required ATC

CNMT pressure > 20 psig

Group 6 CS monitor lights - NOT ALL LIT

Manually actuate CS and Phase B Isolation

Group 6 CS monitor lights remain - NOT ALL LIT, Go to attachment C US

Implement 1BwEP-0, Attachment C, MANUAL CS ACTUATION Comments:

NRC 11-5 Page 17 of 22

Scenario NRC 11-5 Event 6 No: No.

Event Failure of both trains of CS to automatically actuate

==

Description:==

Time Position Applicants Actions or Behavior ATC/

Check CS alignment BOP

Check 1CS001A - OPEN

[CT]

Check 1CS007A - OPEN E-0--E

Manually open 1CS007A

Check 1CS019A - OPEN

Place 1A CS pump test switch in test

Manually open 1CS019A

Place 1A CS pump test switch in normal

Check 1CS010A - OPEN

Check CS pumps - AT LEAST ONE RUNNING

1A CS pump running o Place 1B CS pump in PTL US

Return to main body, step 14.c.

ATC/

Check if CS is required BOP

Group 6 phase B monitor lights - ALL LIT

Verify/Stop all RCPs (may have been done previously)

Check CS eductor suction flow - 1FI-CS013 > 15 gpm

Check CS eductor additive flow - 1FI-CS015 > 5 gpm ATC/

Verify Total AF flow:

BOP

AF flow > 500 gpm

Control feed flow to maintain NR level 31% - 50%

Check status of S/G NR levels - not rising in an uncontrolled manner ATC/

Verify ECCS valve alignment BOP

Group 2 Cold Leg Injection monitor lights required for injection - LIT RO/

Verify ECCS flow BOP

High Head SI flow >100 gpm (1FI-917)

RCS pressure < 1700 psig

SI pump flow > 200 gpm

RCS pressure > 325 psig Comments:

NRC 11-5 Page 18 of 22

Scenario NRC 11-5 Event 6 No: No.

Event Failure of both trains of CS to automatically actuate

==

Description:==

Time Position Applicants Actions or Behavior ATC

Check PZR PORVs and SPRAYs:

PORVs CLOSED.

PORV isolation valves - 1RY8000A and 1RY8000B ENERGIZED

PORV relief paths - PORVs in AUTO, PORV isolation valves OPEN

Normal Spray valves CLOSED.

ATC

Maintain RCS temperature control

Check RCPs - NONE RUNNING

RCS Tcold temperature is NOT stable at or trending to 557o

Stop dumping steam

Throttle AF flow while maintaining > 500 gpm

MSIVs open - verify closed (will not close)

Note: RCPs may have been previously stopped by crew after recognizing a Phase B isolation has occurred per the OAS page of 1BwEP-0.

ATC/ o Check status of RCPs BOP

RCPs - NONE RUNNING CREW Determine status of SG secondary pressure boundary:

Check if SG secondary pressure boundaries are intact:

All SG pressures dropping in an uncontrolled manner CREW Transitions to 1BwEP-2, FAULTED STEAM GENERATOR ISOLATION Comments:

NRC 11-5 Page 19 of 22

Scenario NRC 11-5 Event 5 No: No.

Event Uncontrolled depressurization of all steam generators

==

Description:==

Time Position Applicants Actions or Behavior US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Request STA evaluation of status trees.

Enter/Implement 1BwEP-2, FAULTED STEAM GENERATOR ISOLATION, and direct operator actions of 1BwEP-2 to establish the following conditions:

BOP

Check Main Steamline Isolation at 1PM06J:

1MS001A-D, MSIV 1A-D - OPEN.

Manually actuate MS isolation at 1PM05J and/or 1PM06J.

1MS001A-D, MSIV 1A-D - will not close.

Verify 1MS101A-D, MSIV 1A-D bypass valves - CLOSED.

CREW

Determine NO SG pressure boundaries are intact.

Check if any SG secondary pressure boundary is intact at 1PM04J:

ALL SG pressures dropping in an uncontrolled manner.

CREW

Identify entry conditions for 1BwCA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS.

Comments:

NRC 11-5 Page 20 of 22

Scenario NRC 11-5 Event 5 No: No.

Event Uncontrolled depressurization of all steam generators

==

Description:==

Time Position Applicants Actions or Behavior US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Request STA evaluation of status trees.

Enter/Implement 1BwCA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, and direct operator actions of 1BwCA-2.1 to establish the following conditions:

BOP

Check Main Steamline Isolation at 1PM06J:

1MS001A-D, MSIV 1A-D - OPEN.

Manually actuate MS isolation at 1PM05J and/or 1PM06J.

1MS001A-D, MSIV 1A-D - will not close.

Place 1MS001A-D C/Ss to CLOSE at 1PM06J.

Verify 1MS101A-D, MSIV 1A-D bypass valves - CLOSED.

Verify 1MS018A-D, SG 1A-D PORVs - CLOSED.

All rows of FW isolation monitor lights - lit at 1PM04J.

Verify 1SD002A-H, SG blowdown isolation valves - closed at 1PM06J or 1PM11J.

Verify 1SD005A-D, SG blowdown sample isolation valves - closed at 1PM06J or 1PM11J.

BOP

Control feed flow to minimize RCS cooldown:

RCS cooldown rate at 1PM05J - greater than100°F in one hour.

[CT]

Throttle 1AF005A-H as necessary to lower feed flow to 45 gpm per SG.

ECA-

SG NR levels at 1PM04J - less than 50%.

2.1--A

RCS hot leg temperatures at 1PM05J - dropping.

EVALUATOR NOTE: The crew will transition to 1BwFR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, when the STA reports a RED path exists on the heat sink status tree. 1BwFR-H.1 will not be implemented due to total feed flow being less than 500 gpm due to operator action. Actions for addressing 1BwFR-H.1 are listed below.

CREW

Identify entry conditions for 1BwFR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK.

US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Determine 1BwFR-H.1 does not need to be implemented due to total feed flow being Comments:

NRC 11-5 Page 21 of 22

Scenario NRC 11-5 Event 5 No: No.

Event Uncontrolled depressurization of all steam generators

==

Description:==

Time Position Applicants Actions or Behavior less than 500 gpm due to operator action.

Transition back to 1BwCA-2.1.

EVALUATOR NOTE: At this point the scenario is terminated Comments:

NRC 11-5 Page 22 of 22

Simulation Facility Braidwood Scenario Operating Test No.: 2011 NRC No.: EXAM NRC 11-4 Examiners: ______________________ Applicant: _____________________ SRO

______________________ _____________________ ATC

______________________ _____________________ BOP Initial Conditions: IC-21 Turnover: Unit 1 is operating at 99.5% power, steady state, equilibrium xenon. Online risk is green. 1C CD/CB pump is OOS for bearing replacement. The 1C CD/CB pump is expected back in service in four days. Following completion of turnover, the crew is to perform 1BwOS MS-Q1, UNIT 1 MAIN STEAM DUMP VALVE STROKE SURVEILLANCE.

Event Malf. No. Event Event No. Type* Description Preload IOR ZDI1CD05PC PTL 1C CD/CB Pump OOS IOR ZDI1CD05PCB PTL IOR ZDI1CB113C CLS 1 None N-BOP, US Steam Dump Valve Stroke Surv.

2 IMF RX29D 100 30 I-BOP, US 1FW540 controller fails high in auto 3 IMF RX17 -4.25 C-ATC, US Rod control failure 4 IMF SW01A C-BOP, US 1A SX Pump Trip TS-US 5 IMF RX21A 2500 30 I-ATC, US 1PT-455 fails high TS-US 6 IMF TC14D 0 R-ATC, US #4 Governor valve servo failure closed 7 In caep file below M-ALL 1D Steam Generator Tube Rupture 8 IMF TH11A 0 Loss of RCS pressure control IMF TH03D 450 60 TRGSET 1 "ZLO1IA066(2)==0" IOR ZDI1IA066 (1 0) CLS IOR ZAO1PIRY018 (1 60) 0 30 IMF PN1555 (1 70) ON IMF TH11B 0

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

SCENARIO OVERVIEW Unit 1 is operating at 100% power, steady state, equilibrium xenon. Online risk is green. 1C CD/CB pump is OOS for bearing replacement. The 1C CD/CB pump is expected back in service in four days. Following completion of turnover, the crew is to perform 1BwOS MS-Q1, UNIT 1 MAIN STEAM DUMP VALVE STROKE SURVEILLANCE.

After completing shift turnover and relief, the BOP will perform 1BwOS MS-Q1, UNIT 1 MAIN STEAM DUMP VALVE STROKE SURVEILLANCE.

After completing 1BwOS MS-Q1, 1FW540 Feed Reg Valve Controller 1FK-540 will fail to 100% demand.

The 1FW540 valve will fail open and 1D SG level will rise. The crew will take actions to stabilize the plant by taking manual control of the 1FK-540.

After the 1FK-540 failure is addressed, the rod control summing amplifier will malfunction, resulting in uncontrolled inward rod motion. After checking turbine power stable, the RO will place rod control in Manual to stop the inward rod motion. 1BwOA ROD-1, UNCONTROLLED ROD MOTION, will be implemented. Rods will remain in Manual control for the remainder of the scenario.

After the rod control failure has been addressed, the 1A Essential Service Water pump will trip due to overcurrent. The crew will implement 1BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION, and start the 1B Essential Service Water pump. Technical Specifications 3.7.8, condition A applies. On-line risk remains yellow. The 1A SX pump will remain unavailable for the rest of the scenario.

After the Essential Service Water malfunction has been addressed, the controlling pressurizer pressure channel will fail high. The ATC will identify the failure and take manual control to restore pressurizer pressure. The US will enter 1BwOA INST 2, OPERATION WITH A FAILED INSTRUMENT CHANNEL-Attachment B. Tech Specs 3.3.1 conditions A, E, and K, 3.3.2 conditions A and D, and 3.3.4 condition A will be entered.

After the pressurizer pressure channel failure has been addressed, the #4 turbine governor valve servo will fail, causing the #4 governor valve to close. Turbine load will lower approximately 70 Mw. The ATC will borate the RCS as necessary and/or move rods in to stabilize RCS temperature. On-line risk remains yellow.

After the governor valve malfunction has been addressed, a 450 gpm Steam Generator Tube Rupture will occur on the 1D SG. The crew will implement 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.

When SI actuates, a solenoid failure will cause 1IA066 to fail closed, resulting a loss of Instrument Air to containment. IA to containment will remain unavailable for the remainder of the scenario. The crew will transition to 1BwEP-3, STEAM GENERATOR TUBE RUPTURE, based on secondary radiation trends on the 1D SG. After determining RCS pressure control is unavailable, the crew will transition to 1BwCA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL.

The scenario is complete when the crew has terminated high head SI in 1BwCA-3.3.

Critical Tasks

1. Isolate feedwater flow into and steam flow from the ruptured SG prior to completing step 4 of 1BwEP-3.

(ERG Critical Task number - E-3--A) (K/A number - 000038EA2.01 importance - 4.1/4.7)

2. Cool down to establish RCS subcooling margin, but prevent entry into 1BwFR-P.1.

(ERG Critical Task number - E-3--B) (K/A number - 000038EA1.36 importance - 4.3/4.5)

3. Terminate high head SI prior to completing step 9 of 1BwCA-3.3.

(ERG Critical Task number - CA-3.3--A) (K/A number - 000038EA1.30 importance - 4.0/3.8)

NRC 11-4 Page 2 of 26

SIMULATOR SETUP GUIDE:

Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.

Establish the conditions of IC-21, 100% power, steady state, equilibrium xenon.

Complete items on Simulator Ready for Training Checklist.

Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.

Place simulator in RUN and allow simulator to run during board walk down and turnover.

Start 1B CD/CB pump.

Secure 1C CD/CB pump.

Place CD/CB Pumps Standby Select C/S in OFF.

Place 1C CD/CB Pump in PULL OUT, 1C CD/CB Pump Lube Oil Pump in PULL OUT, and 1CB113C in CLOSED.

Place info tags on 1C CD/CB pump, 1C CD/CB Lube Oil pump, and 1CB113C C/Ss.

Lower reactor power to 99.5% by reducing turbine load approx. 5 MW.

Run caep NRC 11-4 SETUP from disk and verify the following actuate:

IOR ZDI1CD05PC PTL

IOR ZDI1CD05PCB PTL

IOR ZDI1CB113C CLS

Verify SER and printer are clear of data.

Provide students with turnover sheets, 1BwOS NR-1, critical parameter sheet, Op Aids, Pre-Job Brief Forms, and copy of 1BwOS FW-W1.

NRC 11-5 Page 3 of 26

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Perform 1BwOS MS-Q1.

When requested, as Equipment Operator report you are standing by at the steam dump isolation valves ready to isolate the steam dumps and condenser spray valves.

Note: valve positions can be monitored from SIM Graphic Display FW1 and MS6 Acknowledge as EO request to locally close 1MS003A-M and 1CB038A-M / 1CB006, then run NRC 11-4 to CLOSE valves EVENT 1 from disk and verify the following:

MRF MS09 0

MRF MS10 0

MRF MS11 0

MRF MS12 0

MRF MS13 0

MRF MS14 0

MRF MS15 0

MRF MS16 0

MRF MS17 0

MRF MS18 0

MRF MS19 0

MRF MS20 0

MRF FW001 0

MRF FW002 0

MRF FW003 0

MRF FW004 0

MRF FW005 0

MRF FW006 0

MRF FW007 0

MRF FW008 0

MRF FW009 0

MRF FW010 0

MRF FW011 0

MRF FW012 0 Report as EO that 1MS003A-M and 1CB038A-M / 1CB006 are locally closed.

Acknowledge as EO request to locally open 1MS003A-M and 1CB038A-M / 1CB006, then run CAEP NRC 09-4 to OPEN valves EVENT 1 from disk and verify the following:

MRF MS09 100

MRF MS10 100

MRF MS11 100

MRF MS12 100

MRF MS13 100

MRF MS14 100

MRF MS15 100

MRF MS16 100

MRF MS17 100

MRF MS18 100 NRC 07-1 Page 4 of 26

MRF MS19 100

MRF MS20 100

MRF FW001 100

MRF FW002 100

MRF FW003 100

MRF FW004 100

MRF FW005 100

MRF FW006 100

MRF FW007 100

MRF FW008 100

MRF FW009 100

MRF FW010 100

MRF FW011 100

MRF FW012 100 Report as EO that 1MS003A-M and 1CB038A-M / 1CB006 are locally open.

Acknowledge as Shift Manager commencement and completion of procedure.

Event 2: 1FW540 controller fails high in auto Insert IMF RX29D 100 30 to fail 1FK-540 high over a 30 second period.

If dispatched as EO to investigate, wait one minute and report no visible damage to 1FW540 Valve. Valve appears to be failing open in auto and responding correctly in manual (if asked for feedback to manual ops).

Acknowledge as Shift Manager the failure, request for maintenance support, and IR request.

Ensure control rods are in automatic prior to inserting the next event.

Event 3: Uncontrolled inward control rod motion.

If control rods are in manual, as SM direct crew to restore automatic rod control.

Insert IMF RX17 -4.25 to cause uncontrolled inward rod motion.

If dispatched as Equipment Operator to rod control cabinets, report no abnormal indications present.

As SM acknowledge the failure, on line risk assessment, request for maintenance support, and IR requests.

If consulted as SM for status of manual or auto rod control, direct crew to perform actions in accordance with 1BwOA ROD-1.

NRC 07-1 Page 5 of 26

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 4: 1A SX pump trip Insert IMF SW01A for 1A SX pump trip.

If dispatched as EO to investigate 1A SX pump breaker, wait 2 minutes and report phase A overcurrent flag on 1A SX pump breaker cubicle (Bus 141, cubicle 2).

If dispatched as EO to investigate 1A SX pump, wait 3 minutes and report no damage visible at pump and pump is NOT rotating backwards. Report 1B SX pump is running with normal parameters if dispatched to check 1B SX pump.

If contacted as Unit 2 to swap Unit 2 SX pumps for chem. Feed alignment, acknowledge request.

If contacted as Rad Waste operator, report no abnormal aux building sump indications.

As SM, acknowledge the trip of 1A SX pump, LCO 3.7.8 condition A entry, and requests for on line risk assessment, maintenance support, and IR initiation.

Event 5: Pressurizer pressure channel 1PT-455 fails high Insert IMF RX21A 2500 30 As SM, acknowledge the failure, LCO 3.3.1 conditions A, E, & K entry, LCO 3.3.2, condition A & D entry, and LCO 3.3.4 condition A entry, requests for on line risk assessment, maintenance support, and IR initiation.

As SM, if requested support for tripping bistables in AEER, report that AEER bistables are not to be tripped until work analyst and NSO support can be obtained (in approx. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) and that the abnormal operating procedure should be continued. AEER bistable tripping will be conducted later.

If lead examiner desires the bistables tripped, participate in brief and perform the following:

As assist NSO contact Unit 1 (X-2209)

Insert the following:

MRF RP20 OPEN (open protection cabinet #1 door)

MRF RX032 TRIP (trip PRZ HI PRESS RX TRIP bistable PB455A)

MRF RX034 TRIP (trip PRZ LO PRESS RX TRIP bistable PB455C)

MRF RX035 TRIP (trip PRZ LO PRESS SI bistable PB455D)

MRF RX033 TRIP (trip PRZ ENABLE BLOCK P-11 bistable PB455B)

MRF RX013 TRIP (trip OTDT RX TRIP bistable TB411C)

MRF RX135 TRIP (trip OTDT RUNBACK bistable TB411D)

MRF RP20 CLOSE (close protection cabinet #1 door)

NRC 07-1 Page 6 of 26

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 6: #4 governor valve servo failure.

Insert IMF TC14D 0 If dispatched as EO to investigate #4 GV failure, wait 2 minutes and report #4 GV is closed and no visible damage present.

Acknowledge as Power Team loss of load due to Governor Valve failure.

Acknowledge as chemistry/rad protection requests for RCS samples.

Acknowledge as SM the GV failure and requests for on line risk assessment, maintenance support, and IR initiation.

Acknowledge as Power Team load reduction and estimated duration of derate.

Events 7& 8: 1D Steam Generator Tube Rupture, loss of RCS pressure control Run caep NRC 11-4 EVENTS 7 & 8 from disk and verify the following actuate:

IMF TH11A 0

IMF TH03D 450 60

TRGSET 1 "ZLO1IA066(2) == 0"

IOR ZDI1IA066 (1 0) CLS

IOR ZAO1PIRY018 (1 60) 0 30

IMF PN1555 (1 70) ON

IMF TH11B 0 Acknowledge as Shift Manager procedure changes, Emergency Plan evaluations, STA request, and requests for support personnel.

After STA requested, as STA report CSF status: Yellow on inventory when pressurizer level < 17%, yellow on heat sink when ruptured SG level > 88%.

If containment entry requested to attempt to repair 1IA066, acknowledge request but do not make air available to containment.

As Equipment Operator, acknowledge request to fill 1B AF pump day tank.

As Shift Manager, acknowledge request for environs teams when 1D SG PORV open.

NRC 07-1 Page 7 of 26

Scenario NRC 11-4 Event 1 No: No.

Event Perform 1BwOS MS-Q1

==

Description:==

Time Position Applicants Actions or Behavior CUE o From turnover, perform 1BwOS MS-Q1, UNIT 1 MAIN STEAM DUMP VALVE STROKE SURVEILLANCE.

US

Direct BOP to perform 1BwOS MS-Q1.

BOP

Refer to 1BwOS MS-Q1.

Record initial data on step F.1.2.

Notify Equipment Operator to locally close 1MS003A thru M and 1CB038A thru M or 1CB006.

o Acknowledge report from EO that requested valves are closed.

Perform the following at 1PM02J:

Place 1PK-507 controller in MANUAL.

Verify the controller demand is 0%.

Place steam dump MODE SELECT switch in STM PRESS position.

Verify 1MS004A-M CLOSED lamps are illuminated.

Raise 1PK-507 controller steam pressure demand to 100%.

Verify 1MS004A-M CLOSED lamps are NOT illuminated.

Verify 1MS004A-M OPEN lamps are illuminated.

Lower 1PK-507 controller steam pressure demand to 0%.

Verify 1MS004A-M OPEN lamps are NOT illuminated.

Verify 1MS004A-M CLOSED lamps are illuminated.

Notify Equipment Operator to locally open 1MS003A thru M and 1CB038A thru M or 1CB006.

o Acknowledge report from EO that requested valves are open.

At 1PM05J, verify C7 bypass permissive light is NOT illuminated.

Perform the following at 1PM02J:

Place steam dump MODE SELECT switch in RESET then TAVE position.

Verify all steam dump valves remain closed.

Place 1PK-507 controller in AUTO.

Inform US 1BwOS MS-Q1 complete.

ATC o Peer check actions of BOP operator.

o Monitor remainder of MCB.

US

Acknowledge report.

o Notify SM 1BwOS MS-Q1 is complete.

EVALUATOR NOTE: After 1BwOS MS-Q1 is complete and with lead examiner concurrence, enter next event.

Comments:

NRC 11-4 Page 8 of 26

Scenario NRC 11-4 Event 2 No: No.

Event 1FW540 controller fails high in auto

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator 1-15-D3, S/G 1D FLOW MISMATCH STM FLOW LOW

Annunciator 1-15-D9, S/G 1D LEVEL DEVIATION HIGH LOW

1FK-540 controller output failed high.

1FI-540A/541A FW Flow Indication rising.

1D SG level indicators 1LI547/548/549/559 indicate rising level.

BOP

Perform the following at 1PM04J:

Determine 1D SG level rising.

Identify 1FK-540 is failing high.

Report failure to US.

o Initiate 5MW power reduction.

CREW

Reference BwARs

Recognize 1FK-540 output failed high US

Direct/Ensure BOP takes manual control of 1FK-540 and returns 1D S/G level to normal.

Inform SM of 1FK-540 failure.

o Direct BOP/RO to stop load ramp/dilution.

BOP

Perform the following at 1PM04J:

Place 1FK-540, 1FW540 1D FRV Controller, in manual.

Lower demand on 1FK-540.

Monitor 1D S/G level and return level to normal.

Maintain 1D S/G flow by operating 1FK-540 in manual.

US

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

Initiate the next event when the lead examiner approves.

Comments:

NRC 11-4 Page 9 of 26

Scenario NRC 11-4 Event 3 No: No.

Event Uncontrolled inward control rod motion

==

Description:==

Time Position Applicants Actions or Behavior CUE

Control rod inward motion.

RODS IN light lit at 1PM05J.

1SI-412, rod speed indicator, indicates approximately 48 steps per minute.

ATC

Identify control rods incorrectly inserting.

Report failure to US.

Determine turbine power stable at 1PM06J or OWS drop 210.

Place rod bank select switch to manual at 1PM05J to attempt to stop uncontrolled rod insertion.

CREW

Identify entry conditions for 1BwOA ROD-1, UNCONTROLLED ROD MOTION.

US

Notify SM of plant status and procedure entry.

Enter/implement 1BwOA ROD-1, UNCONTROLLED ROD MOTION " and direct operator actions of 1BwOA ROD-1 to establish the following conditions:

CREW

Check turbine power stable at 1PM06J or OWS drop 210.

Check rod control status at 1PM05J:

Verify/place rod bank select switch in manual.

Verify rods stopped moving.

US

Determine applicable Tech Spec entries.

o If pressurizer pressure drops below 2209 psig, then LCO 3.4.1 Cond. A applies.

o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct rod control malfunction.

EVALUATOR NOTE: After the actions for the rod control malfunction are complete and with lead examiners concurrence, insert the next event.

Comments:

NRC 11-4 Page 10 of 26

Scenario NRC 11-4 Event 4 No: No.

Event 1A essential service water pump trip

==

Description:==

Time Position Applicants Actions or Behavior EVALUATOR NOTE: The crew may start the stand-by SX pump per the annunciator response OR elect to enter 1BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION, to address the 1A essential service water pump trip. Actions for 1BwOA PRI-8 are in italics below and on the next page.

CUE

Annunciator SX PUMP TRIP (1-2-A1)

Annunciator SX PUMP DSCH HDR PRESS LOW (1-2-A2)

1A SX pump trip light - LIT.

BOP

Determine 1A SX pump tripped.

o Reference BwARs.

o Place 1A SX pump C/S in PTL BOP

Start 1B SX pump at 1PM06J per 1BwAR 1-2-A1, SX PUMP TRIP.

Verify 1SX001B OPEN

Verify 1SX016B OPEN

Verify 1SX027B OPEN

Place 1B SX pump control switch to start and hold until the lube oil pressure interlock is met and 1B SX pump starts.

o Verify annunciator SX PUMP DSCH HDR PRESS LOW (1-2-A2) is NOT LIT.

US

Determines TS 3.7.8 condition A is applicable.

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

o Inform Unit 2 to swap SX pumps for proper Chem Feed alignment.

CREW o Identify entry conditions for 1BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION.

o Dispatch operators to investigate status of 1A SX pump and breaker.

US o Notify SM of plant status and procedure entry.

o Request evaluation of Emergency Plan conditions.

o Enter/Implement 1BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION and direct operator actions of 1BwOA PRI-8 to establish the following conditions:

o Direct BOP to start 1B SX pump per BwAR 1-2-A1.

CREW o Check for excessive leakage in aux building:

o Contact RWCR to monitor aux building sumps.

o Annunciator SX PUMP SUCT VLV PIT LEVEL HIGH (1-2-D2) - NOT LIT.

BOP o Check status of SX pumps at 1PM06J:

o Start 1B SX pump if not already started using BwAR.

o Check status of SX system at 1PM06J:

o Annunciator SX PUMP SUCT PRESS LOW (1-2-C1) - NOT LIT.

o Annunciator SX STRN DP HIGH (1-2-C2) - NOT LIT.

o Annunciator SX PUMP DSCH HDR PRESS LOW (1-2-A2) - NOT LIT.

o Annunciator SX PUMP DSCH HDR TEMP HIGH LOW (1-2-B2) - NOT LIT.

o 1A SX pump NOT rotating backwards.

Comments:

NRC 11-4 Page 11 of 26

Scenario NRC 11-4 Event 4 No: No.

Event 1A essential service water pump trip

==

Description:==

Time Position Applicants Actions or Behavior o Check for SX leakage into containment at 1PM06J:

o Annunciator CNMT DRAIN LEAK DETECT FLOW HIGH (1-1-A2) - NOT LIT.

o Check CC outlet temperatures < 105°F at 1PM06J.

o Check RCP cooling at 1PM05J:

o Annunciator RCP THERM BARR CC WTR TEMP HIGH (1-7-E3) - NOT LIT.

o Annunciator RCP BRNG CC WTR TEMP HIGH (1-7-E5) - NOT LIT.

US o Determines TS 3.7.8 condition A is applicable.

o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

EVALUATOR NOTE: After the actions for the 1A SX pump trip are complete and with lead examiners concurrence, insert the next event.

Comments:

NRC 11-4 Page 12 of 26

Scenario NRC 11-4 Event 5 No: No.

Event Pressurizer pressure channel 1PT-455 fails high

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator PZR PRESS HIGH RX TRIP STPT ALERT (1-12-A2)

Annunciator PZR PORV OR SAFETY VALVE OPEN (1-12-B2)

Annunciator PZR PRESS CONT DEV HIGH (1-12-D2)

Annunciator PZR PORV DSCH TEMP HIGH (1-9-C6)

PZR pressure indicators 1PI-456, 457, and 458 lowering

PZR PORV 1RY-455A open light lit at 1PM05J.

ATC

Identify 1PT-455 is failing high.

Identify 1RY455A is open.

Report failure to US.

Perform the following at 1PM05J:

o Select an Operable controlling channel per the BwAR OR o Perform the following actions per 1BwOA INST-2

Place 1RY455A, PZR PORV, C/S in close prior to reactor trip or SI occurring.

Place 1PK-455A, master PZR pressure controller, in manual.

Lower demand on 1PK-455A sufficiently to close PZR spray valves and energize PZR heaters prior to reactor trip or SI occurring.

Operate 1PK-455 in manual to restore PZR pressure to normal operating band.

Monitor reactor response to RCS pressure transient.

CREW o Refer to BwARs

Identify entry conditions for 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions

Enter/Implement 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment B PRESSURIZER PRESSURE CHANNEL FAILURE and direct operator actions of 1BwOA INST -2 to establish the following conditions.

o Direct BOP/RO to stop load ramp/dilution ATC

Check PZR pressure at 1PM05J:

PZR pressure - low on 1PI-456, 457, & 458.

o Manually restore PZR pressure using 1PK-455A.

o Select operable PZR pressure control channel

Place PZR pressure control select C/S to CH-457/CH-458.

Check PZR PORVs - CLOSED

Check PZR spray valves - NORMAL

Check PZR heaters - NORMAL Comments:

NRC 11-4 Page 13 of 26

Scenario NRC 11-4 Event 5 No: No.

Event Pressurizer pressure channel 1PT-455 fails high

==

Description:==

Time Position Applicants Actions or Behavior ATC

Check PZR pressure control in auto

PZR PORVs in auto

PZR spray valves in auto

Place Master PZR pressure controller in auto

Select operable channels to recorders

PZR pressure recorder selected to CH456, CH457, or CH458

Loop T recorder selected to 1B, 1C, or 1D

Check P11 interlock

RCS pressure > 1930 psig - P11 NOT lit US o Perform pre-job brief per HU-AA-1211 for bistable tripping o Complete 1BwOL 3.3.1, Attachment A, INSTRUMENT CONDITION TRACKING LOG US

Determine TS 3.3.1 conditions A, E, & K are applicable.

Determine TS 3.3.2 conditions A & D are applicable

Determine TS 3.3.4 condition A is applicable

If PZR pressure drops below 2109 psig. determine TS 3.4.1 condition A is applicable

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

o Dequip entry for P-11 The next event is to be inserted following the above actions by the US and Lead Examiner concurrence.

Comments:

NRC 11-4 Page 14 of 26

Scenario NRC 11-4 Event 6 No: No.

Event #4 governor valve servo failure

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator TAVE CONT DEV HIGH (1-14-D1)

#4 governor valve closed indication at 1PM02J or OWS drop 210.

Generator MW lowering at 1PM02J or OWS drop 210.

RCS Tave rising at 1PM05J.

CREW

Refer to BwARs ATC/

Determine turbine load rejection in progress from 1PM02J or OWS drop210.

BOP

Reference BwARs.

Dispatch operators to investigate #4 GV.

US

Notify SM of #4 GV malfunction.

o Direct operators to restore RCS Tave / Delta I.

NOTE: The crew may decide to borate the rods back out based upon Delta I concerns.

ATC o Initiate RCS boration per BwOP CV-6 at 1PM05J.

o Determine required boric acid volume.

o Determine desired boric acid flow rate.

o Set 1FK-110 BA Flow Control to desired boration rate.

o Set 1FY-0110 BA Blender Predet Counter to desired volume.

o Place MAKE-UP MODE CONT SWITCH to STOP position.

o Place MODE SELECT SWITCH to BORATE position.

o Place MAKE-UP MODE CONT SWITCH to START.

o Verify proper operation of valves and BA transfer pump (1CV110B open, Boric Acid Transfer Pump running, 1CV110A throttles open, proper BA flow indicated on recorder).

OR o Batch addition of Boric Acid:

o Open 1CV110B.

o Open 1CV110A.

o Start the BA Transfer pump.

o When desired amount of BA has been added, stop the BA Transfer Pump.

o Close 1CV110A.

o Close 1CV110B.

o Turn on PZR backup heaters in accordance with BwOP RY-14, PRESSURIZER BACKUP HEATER OPERATION.

US

Contact SM to perform risk assessment, initiate IR, and contact maintenance, OAD, SED to investigate/correct component.

Check reactor power change < 15% in one hour.

o Refer to BwOP FW-26 to evaluate FW venturi fouling.

Comments:

NRC 11-4 Page 15 of 26

Scenario NRC 11-4 Event 6 No: No.

Event #4 governor valve servo failure

==

Description:==

Time Position Applicants Actions or Behavior o Contact Power Team and inform Power Team of load reduction and estimated duration of power derate.

o Review Tech Spec 3.4.1 for applicability o Review RIL per COLR EVALUATOR NOTE: After the actions for the governor valve failure are complete and with lead examiners concurrence, insert the next event.

Comments:

NRC 11-4 Page 16 of 26

Scenario NRC 11-4 Event 7&8 No: No.

Event 1D Steam Generator Tube Rupture/loss of RCS pressure control

==

Description:==

Time Position Applicants Actions or Behavior CUE o Annunciator CHARGING LINE FLOW HIGH LOW (1-9-D3).

RM-11 Rad Monitor ALERT/HI RAD Alarms.

o 1PR08J SG Blowdown.

o 1PR27J SJAE/GS.

o 1AR 22/23A & 1AR22/23D, 1A & 1D main steam line.

PZR pressure lowering in an uncontrolled manner.

o Level rise/FW flow drop noted on 1B S/G.

CREW Identify entry conditions for 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.

ATC

Initiate a manual reactor trip.

Initiate a manual SI.

US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Enter/Implement 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, and direct operator actions of 1BwEP-0 to establish the following conditions:

ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J:

Verify reactor trip.

Rod bottom lights - ALL LIT.

Reactor trip & Bypass breakers - OPEN.

Neutron flux - DROPPING.

BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J or Operator Work Station drop 210 (DEH computer terminal located behind Unit 1 desk):

Verify Turbine Trip.

All Turbine throttle valves - CLOSED.

All Turbine governor valves - CLOSED.

BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J:

Verify power to 4KV busses.

ESF Buses - BOTH ENERGIZED (141 & 142).

CREW Perform immediate operator actions of 1BwEP-0 at 1PM04J, 1PM05J, & 1PM06J:

Check SI actuated at 1PM05J and 1PM06J:

Annunciator 1-11-C1, PZR PRESS LO SI/RX TRIP - LIT.

SI ACTUATED Bypass Permissive - LIT.

SI equipment automatically actuated:

1A and 1B SI pump -RUNNING.

Comments:

NRC 11-4 Page 17 of 26

Scenario NRC 11-4 Event 7&8 No: No.

Event 1D Steam Generator Tube Rupture/loss of RCS pressure control

==

Description:==

Time Position Applicants Actions or Behavior

1SI8801A and B, CV pump cold leg injection valves - OPEN.

Manually actuate SI.

US

Direct BOP to perform Attachment B of 1BwEP-0 EVALUATOR NOTE: US and ATC will continue in 1BwEP-0 while BOP is performing Attachment B:

BOP Verify FW isolated at 1PM04J:

FW pumps - TRIPPED.

Isolation monitor lights - LIT.

FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C.

Verify DGs running at 1PM01J:

DGs - BOTH RUNNING.

1SX169A/B OPEN.

Dispatch operator locally to check operation

Verify Generator Trip at 1PM01J:

OCB 1-8 and 7-8 open.

PMG output breaker open.

Secure all HD running pumps.

Verify Control Room ventilation aligned for emergency operations at 0PM02J:

VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT.

Operating VC train equipment - RUNNING.

0B Supply fan

0B Return fan

0B M/U fan

0B Chilled water pump

0B Chiller

Operating VC train dampers - ALIGNED.

M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED.

0B VC train M/U filter light - LIT.

0VC09Y - OPEN

0VC313Y - CLOSED

Operating VC train Charcoal Absorber aligned for train B.

0VC44Y - CLOSED

0VC05Y - OPEN

0VC06Y - OPEN

Control Room pressure greater than +0.125 inches water on 0PDI-VC038.

Verify Auxiliary Building ventilation aligned at 0PM02J:

Two inaccessible filter plenums aligned.

Plenum A:

0VA03CB - RUNNING Comments:

NRC 11-4 Page 18 of 26

Scenario NRC 11-4 Event 7&8 No: No.

Event 1D Steam Generator Tube Rupture/loss of RCS pressure control

==

Description:==

Time Position Applicants Actions or Behavior

0VA023Y - OPEN

0VA436Y - CLOSED

Plenum C:

0VA03CF RUNNING

0VA072Y - OPEN

0VA438Y - CLOSED

Verify FHB ventilation aligned at 0PM02J:

0VA04CB - RUNNING

0VA055Y - OPEN

0VA062Y - OPEN

0VA435Y - CLOSED

Notify US Attachment B complete ATC/

Verify ECCS pumps running at 1PM05J/1PM06J:

BOP

Both CV pumps - RUNNING.

Both RH pumps - RUNNING.

Both SI pumps - RUNNING.

ATC/

Verify RCFCs running in Accident Mode at 1PM06J:

BOP

Group 2 RCFC Accident Mode lights - ALL LIT.

ATC/

Verify Phase A isolation at 1PM06J:

BOP

Group 3 Cnmt Isol monitor lights - ALL LIT.

ATC/

Verify Cnmt Vent isolation at 1PM06J:

BOP

Group 6 Cnmt Vent Isol monitor lights - ALL LIT.

BOP

Verify AF system at 1PM06J:

AF pumps - BOTH RUNNING.

AF isolation valves - OPEN:

1AF13A-H

AF flow control valves - THROTTLED:

1AF005A-H ATC/

Verify CC pumps at 1PM06J:

BOP

CC pumps - BOTH RUNNING.

ATC/

Verify SX pumps at 1PM06J:

BOP

SX pumps - 1B RUNNING.

Comments:

NRC 11-4 Page 19 of 26

Scenario NRC 11-4 Event 7&8 No: No.

Event 1D Steam Generator Tube Rupture/loss of RCS pressure control

==

Description:==

Time Position Applicants Actions or Behavior ATC/

Check if Main Steamline Isolation required at 1PM04J and1PM06J:

BOP

SG pressures - ALL > 640 psig.

CNTM pressure - < 8.2 psig.

ATC/

Check if CS is required at 1PM06J:

BOP

CNMT pressure remained < 20 psig.

BOP/

Verify Total AF flow at 1PM04J and 1PM06J:

ATC

AF flow > 500 gpm.

SG levels maintained between 10% and 50%.

Check status of S/G NR levels.

o 1D S/G level rising in an uncontrolled manner.

Close 1AF013D & H.

ATC/

Verify ECCS valve alignment at 1PM06J:

BOP

Group 2 Cold Leg Injection monitor lights required for injection - LIT.

Verify ECCS flow at 1PM05J:

High Head SI flow >100 gpm (1FI-917).

o RCS pressure > 1700 psig.

o SI pump discharge flow < 200 gpm.

ATC

Check PZR PORVs and spray valves at 1PM05J:

PORV isolation valves:

1RY8000A & B - ENERGIZED

PORV relief paths:

1RY455A & 456- C/S in AUTO

1RY8000A & B - OPEN

1RY455B & 1RY455C - CLOSED ATC

Maintain RCS temperature control at 1PM05J:

RCPs - ALL RUNNING:

Verify RCS average temperature stable at or trending to 557oF.

o Throttle AF flow.

ATC

Check status of RCPs at 1PM05J

All RCPs - RUNNING.

Check RCP trip criteria:

Phase B isolation NOT actuated.

RCS pressure > 1425 psig - continue on in 1BwEP-0.

Comments:

NRC 11-4 Page 20 of 26

Scenario NRC 11-4 Event 7&8 No: No.

Event 1D Steam Generator Tube Rupture/loss of RCS pressure control

==

Description:==

Time Position Applicants Actions or Behavior BOP/

Check if SG secondary pressure boundaries are intact at 1PM04J:

ATC

Check pressure in all SGs:

None dropping in an uncontrolled manner.

None completely depressurized.

CREW

Determine 1B S/G tubes are NOT intact:

RM-11 ALERT/HI RAD Alarms:

o 1PR08J SG Blowdown o 1PR27J SJAE/GS o 1AR 22/23D 1D Main Steam Line CREW Transition to 1BwEP-3, STEAM GENERATOR TUBE RUPTURE.

Comments:

NRC 11-4 Page 21 of 26

Scenario NRC 11-4 Event 7&8 No: No.

Event 1D Steam Generator Tube Rupture/loss of RCS pressure control

==

Description:==

Time Position Applicants Actions or Behavior US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Request STA evaluation of status trees.

Enter/Implement 1BwEP-3, STEAM GENERATOR TUBE RUPTURE, and direct operator actions of 1BwEP-3 to establish the following conditions:

BOP/

Check status of RCPs at 1PM05J:

ATC

All RCPs - RUNNING.

Check RCP trip criteria at 1PM05J:

High head ECCS flow > 100 gpm

RCS pressure > 1425 psig - continue on in 1BwEP-3.

BOP/

Identify ruptured SG 1D:

ATC 1D Main steam line rad monitor ABNORMAL for plant conditions.

[CT]

Isolate ruptured SG at 1PM04J & 1PM06J:

E-3--A

Verify 1MS018D in AUTO o Check 1MS018D CLOSED o Verify closed when SG pressure < 1115 psig.

o Notify SM to dispatch Environmental Monitoring Teams.

o Announce condition on plant page.

Verify 1SD002C & D CLOSED.

Place 1MS001D, Loop 1B MSIV, C/S to CLOSE.

Verify 1MS101D, 1D MSIV Bypass Valves - CLOSED.

Check PORVs on 1A, 1B, & 1C SGs available for RCS cool down.

BOP/

Perform the following at 1PM04J:

ATC

Check 1D SG level - Narrow Range > 10%.

Check 1D SG pressure > 320 psig.

CREW

Initiate RCS cooldown:

[CT]

Determine required core exit temperature:

E-3--B

Lowest 1D SG pressure at 1PM04J.

Average of 10 highest CETCs at 1PM05J.

Check P-11 status at 1PM05J:

RCS pressure < 1930 psig:

Verify P-11 Bypass Permissive light - LIT.

Place BOTH Steam Line SI Reset/Block C/S to BLOCK.

RCS pressure > 1930 psig:

Comments:

NRC 11-4 Page 22 of 26

Scenario NRC 11-4 Event 7&8 No: No.

Event 1D Steam Generator Tube Rupture/loss of RCS pressure control

==

Description:==

Time Position Applicants Actions or Behavior

Continue RCS cooldown and block steamline SI in accordance with above steps when RCS pressure < 1930 psig.

Dump steam to condenser at maximum rate:

Check C-9 Bypass Permissive - NOT LIT at 1PM05J.

Check 1A, 1B, & 1C MSIVs - OPEN at 1PM06J.

Perform the following at 1PM04J:

Place 1PK-507, MS Header Pressure Controller, in MANUAL.

Lower 1PK-507, MS Header Pressure Controller, demand to 0%.

Place Steam Dump Mode Selector C/S to STM PRESS.

Raise demand on 1PK-507, MS Header Pressure Controller, to initiate RCS cooldown.

When P-12 permissive is LIT, bypass P-12 interlock to continue cool down by placing steam dump switches to BYP-INTLK.

Check average of 10 highest CETCs:

o CETC < required temperature determined in step 6a - stop RCS cooldown by lowering demand on MS Header Pressure Controller and throttling AF flow.

o CETC > required temperature determined in step 6a - continue with 1BwEP-3 steps 7-13 and stop RCS cooldown when CETC < required temperature.

Check 1A, 1B, & 1C SG levels at 1PM04J:

Control SG levels between 30% - 50%.

Check narrow range levels not increasing in an uncontrolled manner.

ATC Note: RO may note depressurized PORV accumulator and report that PORV unavailable.

Check PZR PORVs and isolation valves at 1PM05J:

PORV isolation valves:

1RY8000A/B - ENERGIZED

PORVs:

1RY455A/456 - CLOSED

PORV isolation valves:

1RY8000A/B - OPEN BOP/

Reset SI at 1PM06J:

ATC

Depress both SI reset pushbuttons.

Verify SI actuated permissive light - NOT LIT.

Verify auto SI blocked permissive light - LIT.

Reset CNMT isolations at 1PM06J:

Reset phase A isolation.

Comments:

NRC 11-4 Page 23 of 26

Scenario NRC 11-4 Event 7&8 No: No.

Event 1D Steam Generator Tube Rupture/loss of RCS pressure control

==

Description:==

Time Position Applicants Actions or Behavior

Check Station Air Compressors - one running.

Open 1IA065, Instrument Air Outside Isolation Valve.

1IA066, Instrument Air Inside Isolation Valve, will NOT open.

Verify all AC buses energized at 1PM01J:

All 4 KV ESF buses energized.

All 4KV non-ESF buses energized.

All 6.9 KV buses energized.

Check if RH pumps should be stopped at 1PM06J:

1SI8812A & B open.

RCS pressure > 325 psig.

Stop both RH pumps and place in standby.

Check average of 10 highest CETCs:

o CETC < required temperature determined in step 6a - stop RCS cooldown by lowering demand on MS Header Pressure Controller and throttling AF flow.

o CETC > required temperature determined in step 6a - continue cooldown and DO NOT proceed further in with 1BwEP-3 until CETC < required temperature.

Maintain CETC < required temperature.

Check 1D SG pressure at 1PM04J - stable or rising.

Check RCS subcooling acceptable per Figure 1BwEP 3-2.

ATC

Attempt to depressurize RCS:

Determine normal PZR spray at 1PM05J - NOT available (1IA066 will not open)

Check PZR PORVs at 1PM05J:

1RY455A is unavailable (air accumulator de-pressurized).

Attempt to open 1RY456.

Determine 1RY456 will not open.

ATC/

Try to establish aux spray:

BOP o Verify at least one SI and one CV pump running.

o Terminate Hi Head ECCS:

o Reset SI recirc sump isol valves/CV pump miniflow valves.

o Verify CV pump miniflow valves OPEN - 1CV8110, 1CV8111, 1CV8114, &

1CV8116.

[CT] o Close CV pump cold leg injection valves - 1SI8801A & B. (critical tasks may be CA-3.3 performed later in 1BwCA-3.3)

--A o Place 1CV182 at 0%.

o Open 1CV8105 & 1CV8106.

o Determine aux spray unavailable without IA to CNMT.

CREW Transition to 1BwCA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL.

NOTE: IF the above critical task was performed, the scenario can be terminated here at the discretion of the lead evaluator.

Comments:

NRC 11-4 Page 24 of 26

Scenario NRC 11-4 Event 7&8 No: No.

Event 1B Steam Generator Tube Rupture/loss of RCS pressure control

==

Description:==

Time Position Applicants Actions or Behavior US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Enter/Implement 1BwCA-3.3 and direct operator actions of 1BwCA-3.3 to establish the following conditions:

EVALUATOR NOTE: If 1D SG level is > 88% in the next step, the crew will proceed to 1BwCA-3.3, step 7. 1BwCA-3.3 step 7 actions begin below.

BOP

Check 1D SG NR level:

o Greater than 88%, GO TO Step 7 (CHECK IF ECCS FLOW CAN BE TERMINATED).

o Less than 88% NR, continue with next step.

CREW

Determine normal PZR spray unavailable until IA can be restored to CNMT.

CREW o Attempt to restore PZR PORV:

BOP

Check intact SG levels - Narrow range levels > 10%:

Maintain narrow range levels between 30% and 50%.

Check narrow range levels not increasing in an uncontrolled manner.

RO

Check PZR level:

o Less than 14%, return to step 1 of 1BwCA-3.3.

o Greater than 14%, continue to next procedure step.

EVALUATOR NOTE: 1BwCA-3.3, step 7 actions are contained in the row below.

CREW o Check if ECCS flow can be terminated: (Step 7)

Subcooling - acceptable per Iconics or Attachment A and Fig 1BwCA-3.3-1.

Secondary heat sink established.

RVLIS Plenum 15% or greater.

Ruptured SG 1D rising in an uncontrolled manner or off scale high.

BOP

Stop BOTH SI pumps.

Stop 1 CV pump.

CREW

Terminate high head ECCS:

[CT]

CV pump suction aligned to RWST - 1CV112D & E open.

CA-3.3

Reset SI recirc sump isol valves/CV pump miniflow valves.

--A

Verify CV pump miniflow valves OPEN-1CV8110, 1CV8111, 1CV8114, & 1CV8116.

Comments:

NRC 11-4 Page 25 of 26

Scenario NRC 11-4 Event 7&8 No: No.

Event 1B Steam Generator Tube Rupture/loss of RCS pressure control

==

Description:==

Time Position Applicants Actions or Behavior

Close CV pump cold leg injection valves - 1SI8801A & B. (critical tasks may have been performed earlier in 1BwEP-3)

EVALUATOR NOTE: At this point the scenario is terminated.

Comments:

NRC 11-4 Page 26 of 26

Simulation Facility Braidwood Scenario Operating Test No.: 2011 NRC No.: Exam NRC 11-3 Examiners: ______________________ Applicant: ____________________ SRO

______________________ ____________________ ATC

______________________ ____________________ BOP Initial Conditions: IC-21 Turnover: Unit 1 is operating at 100% power, steady state, equilibrium xenon. Online risk is yellow.

Control rods are in manual for troubleshooting by Instrument Maintenance. Auto rod control is not available.

Event Malf. No. Event Event No. Type Description Preload IMF FW44 1B AF pump fails to start IMF RP15D 1B SI pump fails to automatically start MRF RP84 OPEN trgset 1 ZLO52BRKA(2) == 1 IMF CV01B (1 0) 1B CV pump trips when Rx trips trg 1 IMF FW19C 3.5 0 10 Feed line break inside containment when Rx trips IMF RX17 0 Rod control failure requiring rods in manual.

1 None N-BOP, Lower reactive load 1 KV.

US 2 IMF ED15A R-ATC, Grid disturbance requiring turbine load reduction IMF ED015I US 3 IOR ZDI1CV110B CLS C-ATC, 1CV110B valve fails closed requiring ramp with IOR ZDO1CV110B(1) OFF US rods only IOR ZDO1CV110B(2) OFF 4 IMF FW17 100 I-BOP, HDT Level Controller Failure in Auto US 5 IRF ED025 OPEN TS-US Loss of DC to inverter 113 6 IMF ED07A C-ATC, Loss of bus 141 BOP TS-US 7 IMF RP09A M Inadvertent FWI Preload (ALL) Feed line break inside containment 8 Preload 1B CV pump trip when Rx trips 9 Preload Loss of heat sink (1B AF pp)

(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient NRC 11-3

SCENARIO OVERVIEW Unit 1 is operating at 100% power, steady state, equilibrium xenon. Online risk is yellow. Control rods are in manual for troubleshooting by Instrument Maintenance. Auto rod control is not available.

After completing shift turnover and relief, the BOP will lower Unit 1 reactive load 1 KV in accordance with BwOP MP-23.

After lowering reactive load, a grid disturbance will cause 345 KV lines 0103 and 0104 to be lost. One minute later, the Transmission System Operations Reliability Coordinator will contact the main control room and direct Unit 1 to initiate an emergency load reduction of 100 MW within 20 minutes to alleviate an overload condition on grid transmission lines. The state estimator alarm is not present.

During the initial boric acid addition, 1CV110B valve will fail closed (blown fuse), forcing the crew to complete the load ramp with control rods only.

After the load ramp is complete, HDT Level Controller, 1LK-HD009A, will fail to 100% demand. The 1HD046A/B valves will full open and HDT level will drop. The BOP will take actions to stabilize the plant by taking manual control of the 1LK-HD009A.

After the HDT Level Controller failure is addressed, a loss of DC to instrument inverter 113 will occur. The crew will follow the annunciator response BwAR 1-4-C5. The crew will determine from field report that the instrument inverter DC input has failed. Technical Specification 3.8.7, condition A applies.

Following completion of inverter 113 actions,, a ground fault will occur on bus 141. 1BwOA ELEC-3 will be entered and the operators will start redundant equipment on bus 142 and investigate the status of bus 141.

Tech Spec 3.8.9 applies.

Following completion of 1BwOA ELEC-3 actions, an inadvertent FWI occurs. When the crew manually trips the reactor, a feed line break on the 1C SG inside containment will occur. SI will actuate. The crew will enter 1BwEP-0 to stabilize the plant. The 1B SI pump fails to auto start and must be manually started due to a failure of its actuation relay. The 1B AF pump will not start (engine will seize) resulting in a transition to 1BwFR-H.1 at step 15 of 1BwEP-0. The 1B CV pump trips when the reactor trips. Bleed and feed will be required due to the status of the CV pumps.

Completion criteria is establishing startup feedwater pump flow to the non-faulted SGs.

Critical Tasks

1. Manually start the 1B SI pump before transition out of 1BwEP-0 (ERG Critical Task number - E-0J) (K/A number 006000A4.01 4.1/3.9)

2. Initiate RCS bleed and feed before attempting to establish main feedwater flow or condensate flow to any SG (ERG Critical Task number - FR-H.1--F) (K/A number 000E05EA1.1 importance 4.1/4.0)

NRC 11-3 Page 2 of 22

SIMULATOR SETUP GUIDE:

Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.

Establish the conditions of IC-21, 100% power, steady state, equilibrium xenon.

Complete items on Simulator Ready for Training Checklist.

Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.

Place simulator in RUN (allow simulator to run during board walk down and turnover).

Place Control Rods in MANUAL

Run caep NRC 11-3 SETUP from disk and verify the following actuate:

IMF FW44

IMF RP15D

MRF RP84 OPEN

trgset 1 ZLO52BRKA(2) == 1

IMF CV01B (1 0)

trg 1 IMF FW19C 3.5 0 10

IMF RX17 0

Secure 1A VP chiller and 1A VP WO pump.

Start 1B VP chiller and 1B VP WO pump.

Raise MVARS to 250 MW out.

Provide students with turnover sheets, 1BwOS NR-1, and critical parameter sheet.

NRC 11-3 Page 3 of 22

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Lower reactive load 1KV.

As TSO (Kerry Koch), call TSO tie line (white phone) and request Braidwood Station to lower switchyard voltage 2KV.

Acknowledge as Shift Manager commencement and completion of procedure.

If contacted as Unit 2 to coordinate lowering reactive load, report Unit 2 main generator reactive load is 250 MVARS. Following adjustment of reactive load, report Unit 2 main generator reactive load is 200 MVARS.

Report that Unit 2 will log the reactive load change.

If contacted, acknowledge as Transmission System Operation (TSO) (Kerry Koch) completion of reactive load adjustment.

Event 2: Grid disturbance requiring load reduction.

NOTE: Insert Event 3 when first boration is initiated.

Run caep NRC 11-3 EVENT 2 from disk and verify the following actuate:

IMF ED15A

IMF ED15I One minute after inserting the above malfunctions, contact Unit 1 on the TSO phone as Reliability Coordinator Bruce Larsen and direct Unit 1 to initiate an emergency load reduction of 100 MW within 20 minutes due to an overload condition on grid transmission lines. Inform Unit 1 that Unit 2 has been contacted and Unit 2 is also initiating a 100 MW load drop in response to the grid emergency.

As Nuclear Engineer, inform examinees Beacon Prediction is available for Emergency Offsite Line Drop Ramp in Operator Aid Book. Examinees are to use Beacon Prediction for load drop.

If dispatched as Equipment Operator to the relay house to investigate the breaker trips and/or transmission system status, acknowledge request.

If contacted as TSO for cause of grid conditions, report LaSalle Station had fault in switchyard with local breaker backup failures which resulted in a loss of 345 KV lines 0103 and 0104. The state estimator alarm is not present.

If requested as extra NSO to perform Offsite Power Availability Surveillance, report Unit 2 will perform the surveillance. Wait 15 minutes and report surveillance acceptance criteria are met.

Acknowledge as Shift Manager initiation of load reduction, failures, request for maintenance support, and IR request.

Acknowledge as chemistry/rad protection requests for RCS samples (if required).

Acknowledge as Power Team initiation of ramp.

NRC 11-3 Page 4 of 22

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 3: 1CV110B valve fails closed.

When the ATC begins the first boration for the unit load reduction, run caep NRC 11-3 EVENT 3 from disk and verify the following actuate:

IOR ZLI1CV110B CLS

IOR ZLO1CV110B(1) OFF

IOR ZLO1CV110B(2) OFF If asked as SM about ramping the unit without boration capability, insist that the unit continue to ramp on rods only, until the valve failure can be fixed. TSO reports no other stations are available to perform the load drop.

As SM, acknowledge the failure and requests for on line risk assessment, maintenance support, and IR initiation.

If dispatched as EO to 1DC12J to investigate, wait 10 minutes and report the fuses for 1CV110B are blown.

As SM report that system engineering is present to replace the fuses, wait until ramp is complete, replace the fuses by deleting the following:

DOR ZLO1CV110B(1) OFF

DOR ZLO1CV110B(2) OFF

DOR ZLI1CV110B CLS Event 4: HDT Level Controller Failure.

Insert IMF FW17 100 If dispatched as EO to investigate, wait one minute and report no visible damage to 1HD046A or B Valves.

Report local operation of valves same as MCR indication. (if asked for feedback to manual ops). Report local tank level same as MCR indication.

Event 5: Loss of DC to inverter 113 Insert IRF ED025 OPEN for loss of DC to inverter 113.

When dispatched as Equipment Operator to instrument inverter 113, wait two minutes and report DC input breaker to Inverter 113, B1 is tripped open and Low DC Voltage light P16 is lit.

If requested to close the DC input breaker locally, report breaker will not close.

If dispatched as Equipment Operator /NSO to instrument bus 113, wait one minute and report instrument bus 113 appears normal.

Acknowledge as SM entry into TS 3.8.7 and on line risk status. Acknowledge requests for an IR and System Engineering/Maintenance support.

NRC 11-3 Page 5 of 22

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 6: Loss of bus 141

Insert IMF ED07A If dispatched as EO to bus 141 report acrid smell in Div. 11 ESF switchgear room but no fire.

Acknowledge as SM request for E-plan evaluation, Tech Spec 3.8.9 entry for unit 1, and 3.8.1 for both units request for on line risk assessment. (on line risk will be red)

Acknowledge Tech Spec 3.8.4 entry and exit.

Acknowledge request for U-2 admin NSO to perform 1/2BwOSR 3.8.1.1 If requested as FS/EO to cross-tie 125 VDC bus 111 to 125 VDC bus 211 wait five minutes and insert the following:

MRF ED111 CLOSE If dispatched as EO to depress 1A DG emergency stop push button insert the following:

MRF EG19 TRIP Event 7: Inadvertent Feed Water Isolation

Insert IMF RP09A Event 8: Feed line break in containment / Loss of Heat Sink/CV pump trip Acknowledge as SM procedure changes, E Plan evaluations, and STA request.

After STA requested, as STA report CSF status - Red path on heat sink (until feed flow established). Yellow on heat sink once feed flow established, Yellow on inventory when head voids due to bleed and feed.

If dispatched as EO, report 1B CV pump has phase C overcurrent flag.

If dispatched as EO, report 1B AF pump has large lube oil leak and engine damage.

Acknowledge as U2 NSO request to remove FW isolation fuses insert the following:

MRF FW150 REMOVED

MRF FW151 REMOVED

MRF RP78 REMOVED

MRF RP79 REMOVED Acknowledge as EO start startup FW pump aux oil pump and insert the following:

MRF FW149 START Acknowledge request as EO to close containment isolation valves.

MRF CH11 0 to close 1WO006A

MRF CH13 0 to close 1WO020A

MRF CV17 0 to close 1CV8100 NRC 11-3 Page 6 of 22

Scenario NRC 11-3 Event 1 No: No.

Event Lower reactive load 1KV

==

Description:==

Time Position Applicants Actions or Behavior CUE o From turnover, lower Switchyard voltage 2KV (1KV from each unit) in accordance with BwOP MP-23, ADJUSTING REACTIVE LOAD.

US Directs BOP to perform BwOP MP-23.

BOP

Refer to BwOP MP-23.

Verify MVAR change will not exceed Generator Capability Curve in 1BwGP 100-3A6.

Contact Unit 2 to coordinate MVAR adjustment.

Perform the following at 1PM01J:

Place voltage adjust C/S to lower. (may be done intermittently)

Monitor 1VI-MP006, main generator output VARS.

Release voltage adjust C/S when 1VI-MP006 has dropped 50 MVARS.

Inform US BwOP MP-23 is complete.

US

Acknowledge report.

o Notify SM BwOP MP-23 is complete.

o Notify TSO BwOP MP-23 is complete.

ATC o Peer check actions of BOP operator.

o Monitor remainder of MCB.

EVALUATOR NOTE: After BwOP MP-23 is complete and with lead examiners concurrence, enter next event.

Comments:

NRC11-3 Page 7 of 22

Scenario NRC 11-3 Event 2 No: No.

Event Grid disturbance requiring turbine load reduction.

==

Description:==

Time Position Applicants Actions or Behavior CUE

Call from TSO Reliability Coordinator directing Unit 1 to initiate an emergency load reduction of 100 MW within 20 minutes due to an overload condition on grid transmission lines.

Numerous annunciators on 0PM03J.

345 KV bus tie breakers 1-3, 1-8, 9-10, and 9-15 open at 0PM03J.

345 KV lines 0103 and 0104 deenergized at 0PM03J.

US

Acknowledge request to lower power 100 MW at 5 Mw/min.

Implement actions of 1BwGP 100-4, POWER DESCENSION.

o Perform pre-job brief per HU-AA-1211 PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY, AND POST JOB BRIEFINGS for load ramp.

o Initiate 1BwGP 100-4T2, LOAD SWING INSTRUCTION SHEET.

CREW o Review applicable Precautions, and Limitations and Actions.

o Review Tech Spec 3.8.1 EVALUATOR NOTE: Immediately after initial boration is started, insert the next event.

ATC

Verify rod position and boron concentration.

Initiate boration, if required. (BwOP CV-6)

Determine required boric acid volume.

o Perform boration boundary calculation per 1BwGP 100-4T2.

o Refer to operator aid for ramp.

Determine desired boric acid flow rate.

Perform the following at 1PM05J:

o Set 1FK-110 BA Flow Control to desired boration rate.

o Set 1FY-0110 BA Blender Predet Counter to desired volume.

o Place MAKE-UP MODE CONT SWITCH to STOP position.

o Place MODE SELECT SWITCH to BORATE position.

o Place MAKE-UP MODE CONT SWITCH to START.

o Verify proper operation of valves and BA transfer pump (1CV110B open, Boric Acid Transfer Pump running, 1CV110A throttles open, proper BA flow indicated on recorder).

Comments:

NRC11-3 Page 8 of 22

Scenario NRC 11-3 Event 2 No: No.

Event Grid disturbance requiring turbine load reduction.

==

Description:==

Time Position Applicants Actions or Behavior OR o Batch addition of Boric Acid:

o Open 1CV110B.

o Open 1CV110A.

o Start the BA Transfer pump.

o When desired amount of BA has been added, stop the BA Transfer Pump.

o Close 1CV110A.

o Close 1CV110B.

o Turn on PZR backup heaters (BwOP RY-13).

BOP

Lower turbine load at 1PM02J or Operator Work Station drop 210 (DEH computer terminal located behind Unit 1 desk).by performing the following:

Select SETPOINT.

Enter MW value that is 100 MW below current value in REF window into REF DEMAND window.

Select ENTER.

Enter 3.0 MW/min into the RATE window.

Select ENTER.

Select EXIT.

o Notify US and RO of pending ramp.

Select GO/HOLD.

Verify GO/HOLD button illuminates.

Verify HOLD illuminated RED.

Select GO.

Verify GO illuminates RED.

Verify main turbine load begins to lower.

ATC/

Monitor reactor power and turbine load lowering:

BOP

Monitor NIs, Tave, I, Pzr press/level at 1PM05J.

Monitor MWe and DEHC system response at 1PM02J or Operator Work Station drop 210 (DEH computer terminal located behind Unit 1 desk).

o Return Reactor Makeup System to automatic at current boron concentration.

Comments:

NRC11-3 Page 9 of 22

Scenario NRC 11-3 Event 3 No: No.

Event 1CV110B valve fails closed requiring ramp with rods only

==

Description:==

Time Position Applicants Actions or Behavior CUE o Boric acid flow stops o Annunciator BA FLOW DEVIATION (1-9-A6)

ATC

Identify/report loss of boric acid flow

Refer to BwAR 1-9-A6 o Identify/report 1CV110B valve failure o Dispatch operator to 1DC12J to inspect fuses US

Notify SM of 1CV110B valve failure o Direct BOP to stop load ramp BOP o Stop turbine load ramp o Select GO/HOLD.

o Assist US & RO o Refer to BwARs ATC o MAKE-UP MODE CONT SWITCH to STOP o Close 1CV110A US o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct component.

o Recommence ramp using rods only.

o If PZR pressure drops below 2109 psig. LCO 3.4.1 applies.

BOP o Initiate turbine load reduction:

o When ready to begin load reduction, depress GO o Verify load reduction occurring ATC/

Monitor reactor power and load reduction BOP

Monitor NIs, Tave, I, Pzr press/level

Monitor MWe, Turb loading, EHC ATC

Maintain Tave/Tref within desired band:

At 1PM05J - insert rods manually at desired intervals.

NOTE: After the unit load ramp is complete and with lead examiners concurrence, enter next event Comments:

NRC11-3 Page 10 of 22

Scenario NRC 11-3 Event 4 No: No.

Event HDT Level Controller Failure

==

Description:==

Time Position Applicants Actions or Behavior CUE

1LK-HD009A output failed high

Rising Flow on 1LI-HD004/5/6

Lowering level on 1LI-HD009

Annunciator HDT LEVEL HIGH LOW (1-17-E4)

CREW

Refer to BwARs

Recognize 1LK-HD009A output failed high US

Direct/Ensure BOP takes manual control of 1LK-HD009A and returns HDT level to normal.

Inform SM of 1LK-HD009A failure.

BOP

Perform the following at 1PM03J:

Place 1LK-HD009A, HDT Level Controller, in manual.

Lower demand on 1LK-HD009A.

Monitor HDT level and 1HD046A/B positions to return HDT level to normal.

Maintain HDT flow by operating 1LK-HD009A in manual.

o Dispatch EO to 1HD046A/B valves.

US o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

Initiate the next event when the lead examiner approves.

Comments:

NRC11-3 Page 11 of 22

Scenario NRC 11-3 Event 5 No: No.

Event Loss of DC to instrument inverter 113

==

Description:==

Time Positio Applicants Actions or Behavior n

CUE

Annunciator BUS 113 INVERTER TROUBLE (1-4-C5)

ATC/

Determine instrument inverter 113 trouble.

BOP

Reference BwAR.

CREW

Dispatch operators to investigate status of inverter and instrument bus.

US o Notify SM of plant status.

US

Determines TS 3.8.7 condition A is applicable.

Contact SM to perform risk assessment, initiate IR, and contact additional personnel to investigate/correct instrument failure.

o Perform what if brief for loss of inverter EVALUATOR NOTE: After the tech spec entry is complete and with lead examiner concurrence, insert the next event.

Comments:

NRC11-3 Page 12 of 22

Scenario NRC 11-3 Event 6 No: No.

Event Loss of bus 141

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator (1-21-A7) "BUS 141 FD BRKR 1412 TRIP"

Annunciator (1-21-C7) "BUS 141 OVERLOAD OR VOLT LOW"

Annunciator (1-21-C8) "DG 1A TROUBLE/FAIL TO START"

Bus 141 bus alive light not lit CREW

Determine Bus 141 De-energized.

Reference BwARs

Identify entry conditions for 1BwOA ELEC-3 "LOSS OF 4KV ESF BUS" US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions

Implement 1BwOA ELEC-3 "LOSS OF 4KV ESF BUS" to establish the following conditions:

Determines TS 3.8.9 condition A & B are applicable.

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

ATC/

Ensure the following B train equipment started/running BOP

1B CV pump o 1B CC pump

1B SX pump o 1B/D RCFCs o 0B VC train

Isolate bus 141 by placing the following breakers in PTL:

o ACB 1413 FIRST, then:

o ACB 1411, 1412, 1414

Bus 141 lockout alarm (1-21-A7) LIT

111 Batt Chrg trouble alarm (1-21-E8) LIT o Dispatch operator to crosstie ESF DC Bus 111 with ESF DC Bus 211 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

Refer to Tech Specs

Perform 1BwOSR 3.8.1.1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

Unit 2 contacted to perform 2BwOSR 3.8.1.1 w/i 1 hr

Review 3.8.1, 3.8.9 o Review 3.8.4

Operator dispatched to emergency trip 1A D/G Comments:

NRC11-3 Page 13 of 22

Scenario NRC 11-3 Event 6 No: No.

Event Loss of bus 141

==

Description:==

Time Position Applicants Actions or Behavior

Dispatch operators to locally investigate bus 141 EVALUATOR NOTE: After the actions for the bus 141 failure are complete and with lead examiners concurrence, insert the next event.

Comments:

NRC11-3 Page 14 of 22

Scenario NRC 11-3 Event 7 No: No.

Event Inadvertent FWI & Feed line break inside containment

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator (1-15-E7) "FWIV NOT FULL OPEN"

FWI monitor lights - ALL lit CREW

Recognize FWI and conditions require a manual reactor trip.

US

Direct a manual Rx trip

Implement 1BwEP-0 "REACTOR TRIP OR SI"

Direct operator actions of 1BwEP-0 to establish the following conditions:

ATC Perform immediate operator actions of 1BwEP-0 at 1PM05J:

Verify reactor trip.

Rod bottom lights - ALL LIT.

Reactor trip & Bypass breakers - OPEN.

Neutron flux - DROPPING.

BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J or OWS drop 210:

Verify Turbine Trip.

All Turbine throttle valves - CLOSED.

All Turbine governor valves - CLOSED.

BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J:

Verify power to 4KV busses.

Bus 141 deenergized

Bus 142 energized CREW (If manual SI not previously performed) Recognize and respond to conditions requiring a Safety Injection in accordance with 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION, Step 4:

1C SG pressure cannot be maintained > 640 psig.

Manually actuate SI from 1PM05J and 1PM06J.

The crew may transition to 1BwEP ES-0.1 "REACTOR TRIP RESPONSE" if SI conditions are not met in accordance with 1BwEP-0 "REACTOR TRIP or SI."

Recognition of SI requirements during performance of 1BwEP ES-0.1 will require re-entering 1BwEP-0 at step 1 (Page 17 continues the actions of 1BwEP-0).

Recognition of 1BwFR-H.1 entry requirements during performance of 1BwEP ES-0.1 will require entering 1BwFR-H.1.

1BwFR-H.1 actions start on page 20.

Comments:

NRC11-3 Page 15 of 22

Scenario NRC 11-3 Event 7 No: No.

Event Feed line break inside containment & Loss of heat sink

==

Description:==

Time Position Applicants Actions or Behavior US o Transition to 1BwEP ES-0.1 "REACTOR TRIP RESPONSE" from 1BwEP-0 o Notify SM of plant status and procedure entry.

o Request evaluation of Emergency Plan conditions.

o Request STA evaluation of status trees.

o Enter/Implement 1BwES-0.1 and direct operator actions of 1BwEP-1 to establish the following conditions:

ATC o RCS temperature stable at/trending to 557°F o All rod bottom lights are lit o PZR level > 17%

o Charging and Letdown in Service o PZR Level Trending to Program o PZR pressure > 1829 psig o PZR pressure stable or trending to 2235 psig.

o Check FW status o RCS temp <564 °F o FWI monitor lights lit o Trip Running FW Pumps o Check FW flow to SGs >500 gpm o Check SG levels Comments:

NRC11-3 Page 16 of 22

Scenario NRC 11-3 Event 8&9 No: No.

Event Feed line break inside containment & Loss of heat sink/1B CV pump trip

==

Description:==

Time Position Applicants Actions or Behavior Note: If the crew had previously transitioned to 1BwEP ES- 0.1, Reactor Trip Response, then immediate actions of 1BwEP-0 should be re-performed when SI is actuated or recognized.

EVALUATOR NOTE: US and RO will continue in 1BwEP-0 while BOP is performing Attachment B:

BOP

Verify FW isolated at 1PM04J:

FW pumps - TRIPPED.

Isolation monitor lights - LIT.

FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C.

Verify DGs running at 1PM01J:

DGs - BOTH RUNNING.

1SX169A/B OPEN.

Dispatch operator locally to check operation

Verify Generator Trip at 1PM01J:

OCB 1-8 and 7-8 open.

PMG output breaker open.

Verify Control Room ventilation aligned for emergency operations at 0PM02J:

VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT. (train A rad monitors de-energized) o Dispatch EO to secure VL, VW and VV supply fans.

Operating VC train equipment - RUNNING.

0B Supply fan

0B Return fan

0B M/U fan

0B Chilled water pump

0B Chiller

Operating VC train dampers - ALIGNED.

M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED.

0B VC train M/U filter light - LIT.

0VC09Y - OPEN

0VC313Y - CLOSED Comments:

NRC11-3 Page 17 of 22

Scenario NRC 11-3 Event 8&9 No: No.

Event Feed line break inside containment & Loss of heat sink/1B CV pump trip

==

Description:==

Time Position Applicants Actions or Behavior

Operating VC train Charcoal Absorber aligned for train B.

0VC44Y - CLOSED

0VC05Y - OPEN

0VC06Y - OPEN

Control Room pressure greater than +0.125 inches water on 0PDI-VC038.

Verify Auxiliary Building ventilation aligned at 0PM02J:

Two inaccessible filter plenums aligned.

Plenum A:

0VA03CB - RUNNING

0VA023Y - OPEN

0VA436Y - CLOSED

Plenum C:

0VA03CF RUNNING

0VA072Y - OPEN

0VA438Y - CLOSED

Verify FHB ventilation aligned at 0PM02J:

0VA04CB - RUNNING

0VA055Y - OPEN

0VA062Y - OPEN

0VA435Y - CLOSED

Notify US Attachment B complete ATC

Verify ECCS pumps running at 1PM05J/1PM06J:

CV pumps - NONE RUNNING (1B tripped):

1B RH pump - RUNNING.

SI pump - NONE RUNNING

[CT]

START 1B SI PP E-0--J

RCFCs running in accident mode (0B train ONLY running)

RCFC accident mode status light lit

CNMT Phase A valves closed (train A valves not all closed)

Manually actuate Phase A

Dispatch EO to close de-energized valves outside containment

Verify Cnmt Vent isolation:

Group 6 Cnmt Vent Isol monitor lights - ALL LIT.

Comments:

NRC11-3 Page 18 of 22

Scenario NRC 11-3 Event 8&9 No: No.

Event Feed line break inside containment & Loss of heat sink/1B CV pump trip

==

Description:==

Time Position Applicants Actions or Behavior

Verify AF system:

AF pumps - Neither RUNNING.

Attempt manual start of 1B AF pump o Dispatch EO to check 1B AF pump

AF isolation valves - 1AF13A-H OPEN.

AF flow control valves - 1AF005A-H THROTTLED.

Verify CC pumps - 1B RUNNING.

Verify SX pumps - 1B RUNNING ATC/

Check if Main Steamline Isolation required BOP

1C S/G pressures < 640 psig

CNMT pressure > 8.2 psig

MSIV & MSIV bypass valves - CLOSED CREW o Determine and Announce containment is adverse when pressure rises above 5 psig.

BOP/

Check CS not required ATC

CNMT pressure remained < 20 psig BOP/

Verify Total AF flow:

ATC

AF flow < 500 gpm

SG levels < 31%

o May CLOSE 1AF005C & 1AF013G to isolate CST gravity flow to 1C SG FW line break.

CREW Identify entry conditions for 1BwFR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK Comments:

NRC11-3 Page 19 of 22

Scenario NRC 11-3 Event 9 No: No.

Event Feed line break inside containment/loss of heat sink

==

Description:==

Time Position Applicants Actions or Behavior US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions

Request STA evaluation of status trees

Enter/Implement 1BwFR-H.1 and direct operator actions of 1BwFR-H.1 to establish the following conditions ATC

Check if secondary heat sink is required

RCS pressure > faulted SG pressure

RCS temperature > 350°F ATC

Check CV pump status

CV pumps - NONE RUNNING

GO TO step 15 (bleed and feed)

ATC

Establish RCS feed path

Actuate SI BOP

Verify RCS feed path

1B SI pump - RUNNING

Group 2 cold leg injection monitor lights required for operating ECCS pumps - LIT ATC

Establish RCS bleed path

[CT]

PORV isolation valves - 1RY8000A deenergized & open, 1RY8000B energized &

FR-H.1- open

-F

Open BOTH PZR PORVs (1RY455A & 1RY456)

ATC

Verify adequate RCS bleed path

PZR PORVs - BOTH OPEN

PORV isolation valves - BOTH OPEN ATC /

Verify ESF equipment actuations BOP Comments:

NRC11-3 Page 20 of 22

Scenario NRC 11-3 Event 9 No: No.

Event Feed line break inside containment/loss of heat sink

==

Description:==

Time Position Applicants Actions or Behavior CREW

Maintain RCS heat removal

Maintain ECCS flow

Maintain PZR PORVs - BOTH OPEN BOP

Reset SI

Reset Cnmt isolations

Reset Phase A

Restore I/A to Cnmt BOP

Check if CS should be stopped

CS pumps - NONE RUNNING ATC

Verify cold leg recirc capability

1B RH pump - RUNNING

1SI8811B - ENERGIZED BOP/

Try to establish AF to at least one SG ATC

Check blowdown isolation and sample valves closed

1SD005 A-D & 1SD002A-H

Review attachment B

Check annunciator AF PUMPS SUCT VLVS ARMED (1-3-E7) - NOT LIT

Check 1AF004A & B - OPEN

Check AF pumps - NONE RUNNING o Dispatch operator to 1B AF pump

AF isolation valves - OPEN

1AF13A-H

AF flow control valves - THROTTLED

1AF005A-H

Check AF flow - NOT ESTABLISHED ATC /

Prepare FW system for restoration BOP

CD/CB pumps - at least ONE RUNNING

Place FW valves in manual at 0% demand

1FW510 - 540

1FW510A - 540A Comments:

NRC11-3 Page 21 of 22

Scenario NRC 11-3 Event 9 No: No.

Event Feed line break inside containment/loss of heat sink

==

Description:==

Time Position Applicants Actions or Behavior

1FW034A - D ATC /

Defeat FW isolation BOP

Dispatch operators to remove FW isolation fuses

FW isolation fuses removed

1PA27J

1PA28J ATC /

Establish main FW flow to at least one SG BOP

Open 1FW035A/B/D

Check FW pumps available

CD/CB pumps - at least TWO RUNNING

Check startup FW pump prepared for operation

Dispatch operator to startup FW pump

Bus 159 - ENERGIZED

Locally start aux oil pump

Open startup FW pump disch valve - 1FW059

Open startup FW pump recirc valve - 1FW076 (place C/S in modulate)

Verify close main FW pump recirc valves - 1FW012A, B, & C

Start startup FW pump US

Review Attachment B prior to initiating FW flow ATC /

Establish main FW flow to at least one SG BOP

Throttle 1FW034A/B to desired flow rate

Maintain hotwell level > 7 inches

Check SG WR levels rising Note: The scenario may be terminated at this point (final)

Comments:

NRC11-3 Page 22 of 22

Simulation Facility Braidwood Scenario Operating Test No.:2011 NRC No.: Exam NRC 11-2 Examiners: Applicant:

______________________ ____________________ SRO

______________________ ____________________ ATC

______________________ ____________________ BOP Initial Conditions: IC-21 Turnover: Unit 1 is operating at 100% power, steady state, equilibrium xenon. Online risk is yellow. 1B SX pump is OOS for change out of the aux lube oil pump for the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . LCOAR 1BwOL 3.7.8 has been initiated. Expected back in service next shift. Following completion of turnover, the crew is to perform 1BwOS FW-W1, UNIT 1 TURBINE DRIVEN MAIN FEEDWATER PUMP STOP VALVE SURVEILLANCE. Power Team has requested Unit 1 lower power to 1125 MW at 3 MW/min due to grid demand following completion of 1BwOS FW-W1. Heavy rains have been experienced at the Braidwood site over the past few days and are forecasted to continue.

Event Malf. No. Event Event No. Type* Description Preload IOR ZDI1SX01PB PTL 1B SX pump OOS IOR ZLO1SX01PBC OFF 1B SX aux lube oil pump OOS IMF MS01C 100 1MS001C fails to close from MSI switches trgset 1 "ZDI1MS001C(1) ==

1" trg 1 "DMF MS01C" 1 None N-BOP, US 1BwOS FW-W1 2 None R-ATC, US Lower power at 3 Mw/Min 3 IMF CV01B C-ATC, US 1B CV pump trip (Tech Spec)

TS, US 4 IMF RX10A 0 15 I-ATC, US Turbine impulse pressure channel 1PT-505 TS-US fails Low (Tech Spec) 5 IMF FW35C C-BOP, US 1C HD Pump Trip (standby pump available) 6 IMF RX05 0 30 I-BOP, US Steam line pressure detector 1PT-507 fails low 7 MRF ED042D OPEN M-ALL Dual unit loss of Offsite AC power MRF ED042E OPEN (unit 1 loss of all AC power)

MRF ED042H OPEN IOR ZLO1HSDG0201 OFF IMF ED15C IMF ED15G IMF ED15J IMF EG08A 8 Preload 1C MSIV Fails to Close From MSI Switches

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

SCENARIO OVERVIEW Unit 1 is operating at 100% power, steady state, equilibrium xenon. 1B SX pump is OOS for change out of the aux lube oil pump for the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . LCOAR 1BwOL 3.7.8 has been initiated. Expected back in service next shift. Following completion of turnover, the crew is to perform 1BwOS FW-W1, UNIT 1 TURBINE DRIVEN MAIN FEEDWATER PUMP STOP VALVE SURVEILLANCE. Power Team has requested Unit 1 lower power to 1125 MW at 3 MW/min due to grid demand following completion of 1BwOS FW-W1. Heavy rains have been experienced at the Braidwood site over the past few days and are forecasted to continue.

After completing shift turnover and relief, the crew will perform 1BwOS FW-W1, UNIT 1 TURBINE DRIVEN MAIN FEEDWATER PUMP STOP VALVE SURVEILLANCE.

After completing 1BwOS FW-W1, the crew will lower power to 1125 MW at 3 MW/min due to grid demand. The crew will commence a power reduction at 3 MW/min.

After a measurable change in power, 1B CV pump will trip. The crew will implement 1BwOA PRI-15, LOSS OF NORMAL CHARGING. The crew will start the 1A CV pump to restore normal charging.

Technical Specifications 3.5.2 condition A and TRM 3.1.d, condition A apply.

After the 1B CV pump trip is addressed, First Stage Turbine Impulse Pressure channel 1PT-505 will fail low. The ATC will diagnose the failure of 1PT-505 and take manual control of rods after verifying turbine load stable. 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment D, will be entered. TS 3.3.1 conditions A and P will be entered. The ATC will return rod control to automatic after verifying Tave and Tref are within 1°F.

After the 1PT-505 failure is addressed, the 1C Heater Drain pump will trip due to overcurrent. The crew will implement 1BwOA SEC-1, SECONDARY PUMP TRIP, and start the 1B Heater Drain pump. Technical Specifications do not apply. On-line risk remains yellow. The 1C Heater Drain pump will remain unavailable for the rest of the scenario.

After the 1C Heater Drain pump has been addressed, steam line pressure detector 1PT-507 will fail low over a 30 second period. Both main feedwater pumps speed will lower, reducing feedwater flow and causing all steam generator levels to begin lowering. The crew will take actions to stabilize the plant by taking manual control of the main feedwater pumps. 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment J, will be implemented. 1PT-507 will remain unavailable for the remainder of the scenario. On-line risk remains yellow.

After the 1PT-507 failure is addressed, a loss of all offsite power will occur for both Units. When the 1A DG engine attempts to start, the engine will seize. A loss of DC control power to the 1B DG will prevent it from starting, resulting in a loss of all AC power to Unit 1. Transition will be made to 1BwCA-0.0, LOSS OF ALL AC POWER. The 1C MSIV will fail to close from either MSI switch and will have to be closed from the C/S. A limited crosstie to Unit 2 will be required due to the failure of 2B DG to energize bus 142. The crew must restore power to Unit 1 within 10 minutes. After power is restored to Bus 141, SX will be cross-tied between units per 1BwCA-0.0, Attachment C.

The scenario is complete when the crew has restored CV pump flow in 1BwCA-0.0, step 23e.

Critical Tasks

1. Restore power to Bus 141 within 10 minutes of loss of all AC power.

(UFSAR 15.0.8/Table 15.0-7) (K/A number - 000055EA2.03 importance 3.9/4.7)

2. Isolate RCP seal injection before a CV pump is started in 1BwCA-0.0.

(ERG Critical Task number - ECA-0.0--H) (K/A number - 003000A4.01 importance - 3.3/3.2)

NRC 11-2 Page 2 of 24

SIMULATOR SETUP GUIDE:

Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.

Establish the conditions of IC-21, 100% power, steady state, equilibrium xenon.

Complete items on Simulator Ready for Training Checklist.

Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.

Place simulator in RUN and allow simulator to run during board walk down and turnover.

Place 1B SX pump in PTL.

Run caep DEMO NRC 11-2 SETUP from disk and verify the following actuate:

IOR ZDI1SX01PB PTL

IOR ZLO1SX01PBC OFF

IMF MS01C 100

trgset 1 "ZDI1MS001C(1) == 1"

trg 1 "DMF MS01C"

Place info tags on 1B SX pump and 1SX001B.

Update PARAGON to reflect 1B SX pump OOS.

Post Yellow safety status sign.

VERIFY/START 1B CV Pump, SECURE and place in standby 1A CV Pump.

VERIFY 1C HD Pump is RUNNING.

Provide students with turnover sheets, 1BwOS NR-1, 1BwOS FW-W1 and critical parameters sheet.

NRC 11-2 Page 3 of 24

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Perform 1BwOS FW-W1, UNIT 1 TURBINE DRIVEN MAIN FEEDWATER PUMP STOP VALVE SURVEILLANCE.

If dispatched as Equipment Operator to observe main feedwater pump stop valve operation, report stop valves respond normally as they are tested.

Acknowledge as SM commencement and completion of surveillance.

Event 2: Lower power at 3 MW/min Acknowledge as chemistry/rad protection requests for RCS samples (if required).

Acknowledge as Power Team initiation of ramp.

Event 3: 1B CV pump trip Insert IMF CV01B for 1B CV pump.

If dispatched as Equipment Operator to 1B CV pump and/or pump breaker, wait three minutes and report 1B CV pump appears normal and/or report phase A overcurrent flag at breaker cubicle.

Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.

Event 4: Turbine Impulse Pressure channel 1PT-505 failed low.

Insert IMF RX10A 0 15 As SM, acknowledge the failure, 1BwOA INST-2 entry, request for E Plan evaluation, LCO 3.3.1 conditions A

& P entry, and requests for on line risk assessment, maintenance support, and IR initiation.

As SM, if requested support for tripping bistables in AEER, report that AEER bistables are not to be tripped until work analyst and NSO support can be obtained (in approx. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) and that the abnormal operating procedure should be continued. AEER bistable tripping will be conducted later.

NRC 11-2 Page 4 of 24

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 5: 1C Heater Drain Pump Trip.

Insert IMF FW35C to trip 1C HD Pump.

As SM acknowledge the failure, on line risk assessment, request for maintenance support, IR request, evaluation for reactivity screening, request for personnel notifications, and evaluation for restoration of full power operation.

If dispatched as Equipment Operator, report 1C HD pump is seized and report ground overcurrent flag at breaker cubicle.

If dispatched as Equipment Operator, report you will complete pump vent alignment per BwOP HD-2 for tripped pump.

If dispatched as Equipment Operator, report standby pump start was successful and you will complete BwOP HD-1 for started pump.

Event 6: Steam line pressure detector 1PT-507 fails low.

Insert IMF RX05 0 30 for 1PT-507 failed low.

If dispatched as EO to investigate 1PT-507, wait two minutes report no visible damage to 1PT-507.

Acknowledge as SM 1PT-507 failure, on line risk assessment, request for maintenance support, and IR requests.

Event 7: Dual unit loss of offsite power.

Run caep NRC 11-2 EVENT 7 from disk and verify the following actuate:

MRF ED042H OPEN

MRF ED042E OPEN

MRF ED042D OPEN

IOR ZLO1HSDG0201 OFF

IMF ED15C

IMF ED15G

IMF ED15J

IMF EG08A Record time loss of all AC power occurred: ______:______:______.

Record time AC power restored to Bus 141: ______:______:______.

Calculate time to restore AC power: ______:______:______.

After STA requested, as STA report CSF status - Yellow on inventory if pressurizer level < 17%.

NRC 11-2 Page 5 of 24

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 7: Dual unit loss of offsite power (continued)

When requested as EO to start the U1 D/Gs, report that 1A D/G is seized, 1B DG does not have control power, and 1BwOA ELEC-3 was ineffective.

Acknowledge as EO request to depress U1 DG emergency stop push buttons and insert the following:

MRF EG19 TRIP

MRF EG20 TRIP As Unit 2 operator, report ONLY Bus 241 is energized from 2A DG, acknowledge request to perform 2BwCA-0.3, and acknowledge request to monitor crosstie current as loads are started.

4 min. 19 sec. after request 2BwCA-0.3, insert the following to align Unit 2 4KV ESF buses to Unit 1:

MRF ED006 CLOSE to close ACB 2414.

Acknowledge as EO request to monitor 1B AF pump and request to maintain 1B AF pump day tank level.

Acknowledge as EO request to isolate RCP seals, wait three minutes and insert the following to isolate the RCS seal injection filters. Report RCP seal isolation to MCR.

MRF CV41 0 to close 1CV8384A

MRF CV42 0 to close 1CV8384B (should already be closed)

If asked as Unit 2 for 2SX016A and 2SX027A status, report 2SX016A and 2SX027A are open/energized.

Acknowledge request as EO to close 1SX016B and 2SX016B. Perform the following to close 1SX016B.

Open Monitor window and Input: SWV1SX016B=0 Wait three minutes and report 1SX016B and 2SX016B are closed.

If dispatched as EO to check 1SX005 position locally, wait two minutes and report 1SX005 is open.

If asked as Unit 2 for 2SX005 status, report 2SX005 is closed.

Acknowledge request as EO to throttle SX to the CC HXs. Insert the following to close 0SX007 and 1SX007.

MRF SW01 0

MRF SW02 0 Wait two minutes and report 0SX007 is closed, 1SX007 is closed and 2SX007 is 20% open.

NRC 11-2 Page 6 of 24

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 7: Dual unit loss of offsite power (continued)

If requested as Unit 2 to open 2SX005, Insert the following to open 2SX005.

MRF SW07 100 Wait one minute and report 2SX005 is open.

If asked as Unit 2 for 2SX033 and 2SX034 status, report 2SX033 and 2SX034 are open.

If dispatched as EO to throttle 0SX007 to 10% open, Insert the following to throttle 0SX007.

MRF SW01 10 Wait 30 sec and report 0SX007 is 10% open.

Acknowledge request as Unit 2 to monitor 2A SX pump amps and discharge pressure.

If asked as Unit 2 for crosstie loading capability, report adequate capacity exists prior to starting Unit 1 loads.

Acknowledge as EO request to isolate CC surge tank auto makeup and insert the following to isolate CC surge tank makeup:

MRF CC51 0 to close 1CC185

MRF CC52 0 to close 1CC184 Acknowledge as EO request to drain CC surge tank to normal level and insert the following as needed to initiate CC surge tank drain:

MRF CC15 100 to open 1CC2020B

MRF CC16 100 to open 1CC2020A NRC 11-2 Page 7 of 24

Scenario NRC 11-2 Event 1 No: No.

Event 1BwOS FW-W1

==

Description:==

Time Position Applicants Actions or Behavior CUE

From turnover perform 1BwOS FW-W1, UNIT 1 TURBINE DRIVEN MAIN FEEDWATER PUMP STOP VALVE SURVEILLANCE.

US

Direct BOP to perform 1BwOS FW-W1.

BOP

Refer to 1BwOS FW-W1.

Update data sheet D-2 as each test is performed.

Test 1B main FW pump at 1PM04J:

Depress left LP stop valve TEST pushbutton.

Observe left LP stop valve OPEN lamp goes out.

Observe left LP stop valve TEST button illuminates.

Observe left LP stop valve OPEN lamp illuminates.

Depress high pressure stop valve TEST pushbutton.

Observe high pressure stop valve OPEN lamp goes out.

Observe high pressure stop valve CLOSED and TEST buttons illuminate.

Observe high pressure stop valve CLOSED button goes out.

Test 1C main FW pump at 1PM04J:

Depress left LP stop valve TEST pushbutton.

Observe left LP stop valve OPEN lamp goes out.

Observe left LP stop valve TEST button illuminates.

Observe left LP stop valve OPEN lamp illuminates.

Depress high pressure stop valve TEST pushbutton.

Observe high pressure stop valve OPEN lamp goes out.

Observe high pressure stop valve CLOSED and TEST buttons illuminate.

Observe high pressure stop valve CLOSED button goes out.

Inform US 1BwOS FW-W1 complete.

US

Acknowledge report.

o Notify SM 1BwOS FW-W1 complete.

EVALUATOR NOTE: After 1BwOS FW-W1 is complete and with lead examiners concurrence, insert the next event.

Comments:

NRC 11-2 Page 8 of 24

Scenario NRC 11-2 Event 2 No: No.

Event Lower power to 1125 MW at 3 MW/min

==

Description:==

Time Position Applicants Actions or Behavior US

Implement actions of 1BwGP 100-4, POWER DESCENSION or BwOP EH-15 DEHC OPERATIONS.

o Perform pre-job brief per HU-AA-1211 PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY, AND POST JOB BRIEFINGS for load ramp.

CREW o Review Precautions, and Limitations and Actions, if not already performed during pre-job brief.

ATC

Verify rod position and boron concentration.

Initiate boration, if required. (BwOP CV-6)

Determine required boric acid volume.

o Refer to operator aid REMA for reactivity guidlines.

o Auto addition of Boric Acid:

Determine desired boric acid flow rate.

Perform the following at 1PM05J:

Set 1FK-110 BA Flow Control to desired boration rate.

Set 1FY-0110 BA Blender Predet Counter to desired volume.

Place MAKE-UP MODE CONT SWITCH to STOP position.

Place MODE SELECT SWITCH to BORATE position.

Place MAKE-UP MODE CONT SWITCH to START.

Verify proper operation of valves and BA transfer pump (1CV110B open, Boric Acid Transfer Pump running, 1CV110A throttles open, proper BA flow indicated on recorder).

o Turn on PZR backup heaters in accordance with BwOP RY-13, PRESSURIZER BACKUP HEATER OPERATION.

OR o Batch addition of Boric Acid:

Open 1CV110B.

Open 1CV110A.

Start the BA Transfer pump.

When desired amount of BA has been added, stop the BA Transfer Pump.

Close 1CV110A.

Close 1CV110B.

o Turn on PZR backup heaters (BwOP RY-13).

Comments:

NRC 11-2 Page 9 of 24

Scenario NRC 11-2 Event 2 No: No.

Event Lower power to 1125 MW at 3 MW/min

==

Description:==

Time Position Applicants Actions or Behavior BOP

Lower turbine load at 1PM02J or OWS drop 210 by performing the following::

Select SETPOINT.

Enter desired MW into REF DEMAND window

Select ENTER.

Enter 3 MW/min into the RATE window.

Select ENTER.

Select EXIT.

o Notify US and RO of pending ramp.

Select GO/HOLD.

Verify GO/HOLD button illuminates.

Verify HOLD illuminated RED.

Select GO.

Verify GO illuminates RED.

Verify main turbine load begins to lower.

ATC/

Monitor reactor power and turbine load lowering:

BOP

Monitor NIs, Tave, I, Pzr press/level at 1PM05J.

Monitor MWe and DEHC system response at 1PM02J or OWS drop 210.

During boration, monitor the following at 1PM05J and HMI:

o Monitor VCT level.

o Verify RCS boron concentration rising.

o Monitor BA predet counter.

o Verify boration auto stops at preset value.

o Return Reactor Makeup System to automatic at current boron concentration.

After measurable change in power and lead examiner concurrence, insert the next event.

Comments:

NRC 11-2 Page 10 of 24

Scenario NRC 11-2 Event 3 No: No.

Event 1B CV pump trip.

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator 1-9-A3 CHG PUMP TRIP

Annunciator 1-9-D3 CHG LINE FLOW HIGH/LOW

Annunciator 1-7-B2 RCP SEAL WATER INJ FLOW LOW

Annunciator 1-9-A1 REGEN HX LTDWN TEMP HIGH

PZR level lowering.

Trip/yellow disagreement light on 1B CV pump C/S.

ATC

Identify 1B CV pump has tripped at 1PM05J.

Report failure to US.

o May isolate letdown per BwAR by closing 1CV8149A/B/C CREW

Reference BwARs as time permits.

o Identify entry conditions for 1BwOA PRI-15, LOSS OF NORMAL CHARGING.

Dispatch operator to investigate cause of 1B CV pump trip.

o Place unit ramp on hold.

NOTE: The crew may elect to start the stand-by CV pump using Immediate Actions of BwAR 1-9-A3 OR by entering 1BwOA PRI-15. The required actions for each method are described below.

ATC IF crew chooses to use BwAR 1-9-A3 to start 1A CV pump, required actions begin here.

o Determine NO indications of gas binding of tripped pump.

o NO fluctuation of pump amps prior to trip.

o NO fluctuation of pump discharge flow prior to trip.

o NO fluctuation of charging flow prior to trip.

Verify suction source 1CV112B and 1CV112C OPEN

Verify recirc path 1CV8111 and 1CV8114 OPEN

Place 1A CV pump C/S to start.

US IF crew chooses to enter 1BwOA PRI-15 to start 1A CV pump, required actions begin here.

Notify Shift Manager of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

o Implement 1BwOA PRI-15, LOSS OF NORMAL CHARGING, and direct operator actions of 1BwOA PRI-15 to establish the following conditions:

o Direct BOP/ATC to stop load ramp/dilution.

Comments:

NRC 11-2 Page 11 of 24

Scenario NRC 11-2 Event 3 No: No.

Event 1B CV pump trip.

==

Description:==

Time Position Applicants Actions or Behavior o Enter Tech Spec 3.4.1 if PZR pressure < 2209 psig.

ATC Perform the following at 1PM05J:

Check CV pump status:

Identify NEITHER CV pump is running

Place 1B CV pump C/S in PULL OUT.

Isolate normal letdown:

Place 1CV8149A, B, & C, letdown orifice isolation valves, C/Ss to CLOSE.

Place 1CV459 & 1CV460, letdown isolation valves, C/Ss to CLOSE.

Check VCT status:

Check 1CV112B & 1CV112C, VCT suction valves, OPEN.

Maintain VCT level greater than 20%.

Check VCT level > 20% on 1LI-112 or 1LR-185.

Operate RMCS in automatic or manual to maintain VCT level > 20%.

Check annunciator 1-9-C2, VCT TEMP HIGH - NOT lit.

ATC/ Perform the following at 1PM05J:

BOP o Acknowledge RM-11 alarm caused by isolating flow to 1PR06J, Gross Failed Fuel Monitor.

Check for gas binding of previously running CV pump by verifying the following trends NOT fluctuating prior to pump trip (may use PPC trends):

RCP #1 seal leak off flows.

CV pump flow.

CV pump discharge pressure.

CV pump amps.

Restore normal charging flow:

Check 1CV8111 & 1CV8114, 1B CV pump miniflow isolation valves - OPEN.

Check RCS pressure approximately 2235 psig.

Place 1A CV pump C/S to start.

Check CV System Alignment:

Verify 1CV8146, charging to RC 1B loop isolation valve - OPEN.

Verify 1CV8324A, charging to regen HX 1A isolation valve - OPEN.

Verify 1CV8105 AND 1CV8106, charging line CNMT isolation valves - OPEN.

Check charging flow established (Charging flow may be at minimum for RCP seal injection due to letdown isolation).

Determine normal letdown is isolated.

o Monitor RMCS during automatic VCT makeup:

Comments:

NRC 11-2 Page 12 of 24

Scenario NRC 11-2 Event 3 No: No.

Event 1B CV pump trip.

==

Description:==

Time Position Applicants Actions or Behavior

Proper flow indicated on PW/Total Flow (1FT-0111) and Boric Acid Flow (1FT-0110).

CREW

Identify entry conditions for 1BwOA ESP-2, REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS.

US o Notify Shift Manager of plant status and procedure entry.

Implement 1BwOA ESP-2, REESTABLISHING CV LETDOWN DURING ABNORMAL CONDITIONS, and direct operator actions of 1BwOA ESP-2 to establish the following conditions:

BOP Perform the following at 1PM05J:

Check letdown Isolated:

Verify 1CV8149A, B, & C, letdown orifice isolation valves - CLOSED.

Verify 1CV459 & 1CV460, letdown isolation valves - CLOSED.

BOP Perform the following at 1PM05J:

Check letdown flow path:

Verify 1CV8401A, letdown to letdown HX 1A isolation valve, - OPEN.

Verify 1CV8324A, charging to regen HX 1A isolation valve - OPEN.

Verify 1CV8389A, letdown to regen HX 1A isolation valve - OPEN.

Verify 1CV8152 & 1CV8160, letdown line CNMT isolation valves - OPEN.

Verify BTRS mode select switch OFF.

Align letdown controllers:

Place 1PK-131, letdown line pressure controller, in MANUAL and raise demand to 40%.

Place 1CC130A, letdown HX outlet temperature controller, in MANUAL and raise demand to 60%.

Verify charging flow established:

Verify 1CV8105 AND 1CV8106, charging line CNMT isolation valves - OPEN

Adjust 1CV182, charging header backpressure control valve, to establish 8-13 gpm RCP seal injection flow.

Place 1FK-121, in manual and operate 1FK-121 in manual to establish 100 gpm charging flow on 1FI-121A.

Establish letdown flow:

Place 1CV459 & 1CV460, letdown isolation valves, C/Ss to OPEN.

Place 1CV8149A, B, & C, letdown orifice isolation valves, C/Ss to OPEN as necessary to establish 120 gpm letdown flow.

Comments:

NRC 11-2 Page 13 of 24

Scenario NRC 11-2 Event 3 No: No.

Event 1B CV pump trip.

==

Description:==

Time Position Applicants Actions or Behavior

Lower demand on 1PK-131, letdown line pressure controller, to raise letdown pressure to approximately 360 psig on 1PI-131.

Operate 1FK-121 in manual to restore PZR level to normal operating band and maintain 8-13 gpm RCP seal injection flow.

Lower demand on 1CC130A, to control letdown temperature between 90° to 115°F on 1TI-130.

Place 1PK-131, letdown line pressure controller, in AUTO.

Place 1CC130A, letdown HX outlet temperature controller, in AUTO.

At the RM-11, verify 1PR06J cursor is GREEN.

US Note: these actions are applicable for both methods of starting 1A CV pump.

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

Determine TS 3.5.2, condition A is applicable.

Determine TRM 3.1.d, condition A is applicable.

EVALUATOR NOTE: After the actions for charging pump trip are complete and with lead examiner concurrence, enter next event.

Comments:

NRC 11-2 Page 14 of 24

Scenario NRC 11-2 Event 4 No: No.

Event Turbine Impulse Pressure Channel 1PT-505 failed low

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator TAVE CONT DEV HIGH (1-14-D1)

1PI-505, First Stage Pressure, indication lowering.

Control rod inward motion

1TR-0412, Auct Tave/Tref recorder, Tref indication lowering

1SI-412, Rod Speed, indicates 72 step per minute ATC/

Recognizes 1PT-505 has failed low BOP

Report failure to US o Place rod control in manual o Refer to BwAR 1-14-D1 as time permits BOP o Verifies turbine load not lowering CREW

Identify entry conditions for 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions

Implement 1BwOA INST-2 "OPERATION WITH A FAILED INSTRUMENT CHANNEL", Attachment D "TURBINE IMPULSE PRESSURE CHANNEL FAILURE" and direct operator actions of 1BwOA INST -2 to establish the following conditions.

Direct RO to place rod control in manual o If Pzr Pressure drops below 2209 psig, enter LCO 3.4.1 until pressure is > 2209 psig.

ATC/

Restore steam dumps BOP

C-7 NOT lit

Place 1PK-507 in manual

Lower 1PK-507 demand to 0%

Place steam dump mode select switch to STM PRESS mode

Place 1PK-507 in auto o Check Reactor Power <100%

ATC/

Defeat 1PT-505 BOP

Place 1PS505Z, Turbine Impulse Pressure Defeat Switch, to DEFEAT P-505 US/ATC

Check if rod control can be placed in auto o C5 NOT lit o Tave/Tref stable and within 1°F (check T0494 < 1°F).

Comments:

NRC 11-2 Page 15 of 24

Scenario NRC 11-2 Event 4 No: No.

Event Turbine Impulse Pressure Channel 1PT-505 failed low

==

Description:==

Time Position Applicants Actions or Behavior o If control rods need to be adjusted to restore Tave - Tref within 1°F, perform the following:

o Conduct reactivity brief for restoring control rods per OP-AP-300-1004, Reactivity Change Determination Form o Obtain SM concurrence for reactivity change o Adjust Tave - Tref within 1°F using control rods

Place Rod control in auto ATC/

Check P13 interlock BOP

Turbine power > 10% - P13 NOT lit US

Determine TS 3.3.1 conditions A and P are applicable.

Contact SM to perform risk assessment, initiate IR, perform reactivity screening and contact personnel to investigate/correct instrument failure.

The next event is to be inserted following the above actions by the US and Lead Examiner concurrence.

Comments:

NRC 11-2 Page 16 of 24

Scenario NRC 11-2 Event 5 No: No.

Event 1C Heater Drain Pump Trip

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator HD PUMP TRIP (1-17-D2) o Annunciator HD TANK LEVEL HIGH LOW (1-17-E4)

HDT level indicator 1LI-HD009 rising at 1PM03J.

1C HD Pump flow indication 1FI-HD006 drops at 1PM03J.

1A HD Pump flow indication 1FI-HD004 rises at 1PM03J.

ATC/

Recognize 1C HD pump has tripped.

BOP

Report pump trip to US.

Reference BwARs.

o Dispatch operators to investigate.

CREW

Identify entry conditions for 1BwOA SEC-1, SECONDARY PUMP TRIP.

US

Acknowledge 1C HD pump trip.

Contact Shift Manager to perform risk assessment, initiate IR, and contact maintenance to investigate/correct failure.

Implement 1BwOA SEC-1, SECONDARY PUMP TRIP Attachment C, HD PUMP TRIP, and direct operator actions of 1BwOA SEC-1 to establish the following conditions:

BOP

Start the 1B HD Pump (may have been done per BwAR actions).

Recognize two pumps running again.

Monitor HD tank level at 1PM03J.

Restore Plant Conditions

1HD117 in auto and closed.

Running HD pumps parameters acceptable

HD Flow ATC

Check PDMS operable

1-10-E8 NOT lit.

1-10-D7 NOT lit.

ATC/

Dispatch EO to perform BwOP HD-1 on standby pump that was started and BwOP BOP HD-2 on tripped pump.

EVALUATOR NOTE: After the actions for the HD Pump trip are complete and with lead examiners concurrence, insert the next event.

Comments:

NRC 11-2 Page 17 of 24

Scenario NRC 11-2 Event 6 No: No.

Event Steam line pressure detector 1PT-507 fails low.

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciators S/G 1A/B/C/D FLOW MISMATCH FW FLOW LOW (1 A4/B4/C4/D4)

Annunciators S/G 1A/B/C/D LEVEL DEVIATION HIGH/LOW (1-15-A9/B9/C9/D9)

BOTH main feedwater pump speed/flow - LOWERING.

1PI-507, S/G HDR PRESS, - LOWERING CREW

Refer to BwARs

Determine 1PT-507 failing low at 1PM04J.

Identify entry conditions for 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL.

o Dispatch operators to investigate 1PT-507 failure.

US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions

Implement 1BwOA INST-2 "OPERATION WITH A FAILED INSTRUMENT CHANNEL", Attachment J "FW PUMP SPEED CONTROL MALFUNCTION" and direct operator actions of 1BwOA INST -2 to establish the following conditions.

o Direct BOP/RO to stop load ramp/dilution BOP Perform the following at 1PM04J:

Place 1SK-509A, Master FW pump speed controller in manual.

Raise demand on 1SK-509A.

Raise FW pump speed sufficiently to restore SG levels and FW header DP to normal.

Maintain SG levels by operating 1SK-509A in manual.

o Aligns steam dumps back to Tave mode.

Note to evaluator: The crew may ask for Shift Manager direction regarding Steam Dump mode of operation. The procedures for 1PT-505 failure and 1PT-507 failure conflict for which mode steam dumps are left in. Since the steam dumps will not work in Tave on the load reject controller nor will they work in Stm Press mode, they should be returned to Tave mode since they will still work on the plant trip controller.

ATC Perform the following at 1PM05J:

Monitor reactor power response to SG under and overfeeding transient.

Comments:

NRC 11-2 Page 18 of 24

Scenario NRC 11-2 Event 6 No: No.

Event Steam line pressure detector 1PT-507 fails low.

==

Description:==

Time Position Applicants Actions or Behavior US

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

o If PZR pressure dropped below 2109 psig during transient, LCO 3.4.1 applies.

Comments:

NRC 11-2 Page 19 of 24

Scenario NRC 11-2 Event 7 No: No.

Event Dual unit loss of offsite power. (U-1 loss of all AC power)

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator LOSS OF OFFSITE POWER (1-20-A1)

Annunciator DG1A TROUBLE/FAIL TO START (1-21-C8)

BOTH 4KV ESF bus alive lights NOT LIT.

Annunciator SAT 141-1/142-2 BUS 4 TRIP (0-35-E1)

Annunciator SAT 241-1/242-2 BUS 14 TRIP (0-36-E1)

CREW

Determine Loss of All AC Power has occurred.

US

Enter/Implement 1BwCA-0.0, "LOSS OF ALL AC POWER", and direct operator actions of 1BwCA-0.0 to establish the following conditions:

Direct operator actions of 1BwCA-0.0.

Notifies SM of plant status and procedure entry.

Requests evaluation of Emergency Plan conditions.

Record time loss of all AC power occurred. ______:______:______

ATC Perform immediate operator actions of 1BwCA-0.0:

Manually trip reactor at 1PM05J or 1PM06J.

Verify reactor trip at 1PM05J:

Reactor trip & Bypass breakers - OPEN

Neutron flux - DROPPING BOP Perform immediate operator actions of 1BwCA-0.0:

Manually Isolate Steamlines at 1PM05J or 1PM06J:

Actuate main steamline isolation.

Verify all MSIVs and MSIV Bypass valves - CLOSED. (1MS001C will NOT be Closed) o Actuate main steamline isolation from alternate MSI Switch.

Close 1MS001C with C/S at 1PM06J BOP

Verify AF flow at 1PM06J:

AF flow >500 gpm (1B AF train only)

RO

Verify RCS isolated at 1PM05J:

BOTH PZR PORVs closed.

1CV8149A, B & C closed.

1CV459 and 1CV460 closed.

Comments:

NRC 11-2 Page 20 of 24

Scenario NRC 11-2 Event 7 No: No.

Event Dual unit loss of offsite power. (U-1 loss of all AC power)

==

Description:==

Time Position Applicants Actions or Behavior

1CV8153A & B closed.

BOP

Try to restore power to any/both Unit 1 4KV ESF buses at 1PM01J:

DGs - NONE RUNNING.

Attempt Manual Start of 1A/B DG

Manually Actuate SI from 1PM05J and 1PM06J.

BOP/

Prepare for Unit 2 crosstie:

US

Dispatch operator to depress emergency stop push buttons on both U1 DGs.

Reset SI at 1PM06J.

US

Check status of Unit 2 ESF buses at 1PM01J:

Bus 241 - ENERGIZED from 2A DG.

Notify Unit 2 to implement 2BwCA-0.3, RESPONSE TO OPPOSITE UNIT LOSS OF ALL AC POWER.

Bus 242 - DEENERGIZED

GO TO 1BwCA-0.0, Step 14 (limited crosstie).

BOP/

Energize bus 141 using limited Unit 2 crosstie (DG 2A) at 1PM01J:

US

Bus 241 energized from 2A DG.

Check Bus 141 - NOT FAULTED:

ACB 1413 (DG feed) in PULL OUT.

ACB 1411 (Non-ESF bus tie) in PULL OUT.

ACB 1412 (SAT feed) in PULL OUT.

ACB 1414 (Reserve feed) in PULL OUT.

Verify Bus 141 alarms NOT LIT:

Annunciator BUS 141 FD BRKR ACB 1412 TRIP (1-21-A7).

Annunciator BRKR 1414 CROSS-TIE OVERCURRENT (1-21-B8).

Annunciator DG 1A OVERLOAD (1-21-B9).

ATC/

Energize bus 141 using limited Unit 2 crosstie (DG 2A) at 1PM01J: (Contd)

BOP

Place ESF loads in PULL OUT: (may have been performed per BwAP 340-1 prudent operator actions)

BOTH CENT CHG pumps

BOTH RH pumps

BOTH SI pumps

1A AF pump Comments:

NRC 11-2 Page 21 of 24

Scenario NRC 11-2 Event 7 No: No.

Event Dual unit loss of offsite power. (U-1 loss of all AC power)

==

Description:==

Time Position Applicants Actions or Behavior

ALL RCFCs (HI and LO)

BOTH CS pumps

ALL CC pumps (1A, 1B, and 0)

BOTH SX pumps

BOTH MCR chillers

Check ACB 2414 closed (reserve feed light lit.).

Synch and Close Bus 141/241 reserve feeder breaker:

Close ACB 1414

Check Bus 141 energized.

[CT]

Check Bus 131X energized.

UFSAR 15.0.8/

Table

Record time AC power restored: ______:______:______

15.0-7

Time power restored - time power lost = ______:______:______ (<10 minutes)

Check VC Train 0A fans - RUNNING:

Start 0A supply fan, 0A return fan, & 0A makeup fan.

Notify TSO to implement an emergency AC restoration program.

GO TO step 16.

ATC/

Check AF pump status at 1PM06J:

BOP

1B AF pump - RUNNING.

Check SG levels at 1PM05J:

Maintain NR levels between 10% (31%) and 50%.

o Throttle 1AF005E/F/G/H

Dispatch operator to monitor 1B AF pump.

Place 1A & 1D SG PORVs in AUTO.

ATC/

Isolate RCP seals:

BOP

Dispatch operator to locally close 1CV8384A & B.

[CT]

Close 1CC9438 at 1PM06J.

ECA-

Close 1CV8100 at 1PM05J.

0.0--H ATC/

Verify Equipment loaded on bus 141 at 1PM06J:

BOP

Annunciator 125V DC BATT CHGR 111 TROUBLE - NOT LIT (1-21-E8)

Annunciator Bus 111 INVERTER TROUBLE NOT LIT (1-4-A5)

Annunciator Bus 113 INVERTER TROUBLE NOT LIT (1-4-C5)

Comments:

NRC 11-2 Page 22 of 24

Scenario NRC 11-2 Event 7 No: No.

Event Dual unit loss of offsite power. (U-1 loss of all AC power)

==

Description:==

Time Position Applicants Actions or Behavior NOTE: All critical tasks are complete at this point. The scenario may be terminated here at the lead evaluators discretion.

US

Restore Unit 1 SX cooling:

Enter/Implement 1BwCA-0.0, "LOSS OF ALL AC POWER", ATTACHMENT C, STATION BLACKOUT - ALTERNATE SX COOLING, and direct operator actions of 1BwCA-0.0 ATTACHMENT C to establish the following conditions:

ATC/

Prepare RCFC train for SX crosstie:

BOP

Contact Unit 2 to verify 2SX016A & 2SX027A - OPEN

Dispatch operators to locally close 1SX016B AND 2SX016B.

Prepare CC HX for SX crosstie:

Unit 0 CC HX - in service to Unit 1

1SX005 previously open at 1PM06J or open locally.

Contact Unit 2 to verify 2SX005 closed.

Close 1SX004 at 1PM06J.

Dispatch operators to throttle CC HX SX flow:

Close 0SX007.

2SX007 - 20% open.

Crosstie unit SX systems:

Close 1SX016A & 1SX027A at 1PM06J.

Verify 1SX005 previously open at 1PM06J or open locally.

Contact Unit 2 to open 2SX005.

Verify open 1SX033 & 1SX034 at 1PM06J.

Contact Unit 2 to verify open 2SX033 & 2SX034.

Establish minimum SX cooling for Unit 1 CC system:

Dispatch operator to throttle 0SX007 - 10% open.

Local operator to adjust 0SX007 & 2SX007 to maintain the following:

2A SX pump amps < 191 AMPS

2A SX pump discharge pressure > 90 PSIG

Unit 1 & Unit 2 CC HX outlet temperatures < 105°F.

GO TO main body, step 20b.

ATC/

Start 0A VC chilled water pump at 0PM02J.

BOP

Start 0A VC chiller at 0PM02J.

Dispatch operators to start 1A & 1B DG per 1BwOA ELEC-3.

Restore CC system at 1PM06J:

1CC9438 - CLOSED

Start 1A CC pump.

Prepare to restore CV pump at 1PM05J:

Comments:

NRC 11-2 Page 23 of 24

Scenario NRC 11-2 Event 7 No: No.

Event Dual unit loss of offsite power. (U-1 loss of all AC power)

==

Description:==

Time Position Applicants Actions or Behavior

Open 1CV112D

Close 1CV112B

Close 1CV8106

Reset SI recirc sump and CV pump miniflow isolation valves.

Verify/open 1CV8111 & 1CV8114

1SI8801A & B - CLOSED

Check seal injection filter isolated:

1CV8384A & B CLOSED

Start 1A CV pump at 1PM05J.

o Open 1SI8801A at 1PM05J as needed to maintain PZR level > 25% (41%).

NOTE: Scenario is terminated at this point (Final)

Comments:

NRC 11-2 Page 24 of 24

Simulation Facility Braidwood Scenario Operating Test No.: NRC 2011 No.: Exam NRC 11-1 Examiners: ______________________ Applicant: ____________________ SRO

______________________ ____________________ ATC

______________________ ____________________ BOP Initial Conditions: IC-18 Turnover: Unit 1 is at 75% power, steady state, equilibrium xenon, MOL. Online risk is green. 1B CW PP is OOS for intake bay inspection. Following completion of turnover, the shift manager requests the BOP to swap GC pumps per BwOP GC-5, in preparation for an OOS on 1GC01PA next shift. TSO has requested Unit 1 prepare to raise turbine load to full power at 0.4 MW/min due to grid demand.

Event Malf. No. Event Event No. Type* Description Preload IOR ZDI1CW01PB 1B CW PP OOS PTL MRF ED093B OPEN 1CW001B OOS IMF RP02A Reactor trip breaker A fails to open IMF RP02B Reactor trip breaker B fails to open IMF RD09 Auto Rod Speed Failure (8 steps/min)

IRF RP49 OUT prevents 1A CV train valves from auto positioning on SI signal TRGSET 1 PZR PORV 1RY456 fails open THPPRZR .GT. 2315 IMF TH11B (1 0) 100 IOR ZDI1RY8000B 1RY8000B fails open AUTO 1 None N-BOP, US Swap stator cooling pumps.

2 None R-ATC, US Raise power at 0.4 Mw/Min 3 IMF FW16 1500 30 I-BOP, US 1PT-508 FW Htr Dsch Press fails high 4 IMF TH11A 5 C-ATC, 1RY455A partially opens TRGSET 2 TS-US 1RY8000A block valve breaker trips ZLO 1RY8000A(2)==0 MRF ED058C (2 5)

OPEN 5 IMF CV16 100 10 I-RO, US VCT level channel 1LT-112 failure.

6 IMF ED11D TS-US Loss of instrument bus 114 (Tech Spec)

DMF TH11A 5 IRF ED019 OPEN 7 IMF ED07C Bus 143 Deenergized 8 Preload M-All ATWS 9 Preload PZR PORV 1RY456 fails open

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

SCENARIO OVERVIEW Unit 1 is at 75% power, steady state, equilibrium xenon, MOL. Online risk is green. 1B CW PP is OOS for intake bay inspection. Following completion of turnover, the shift manager requests the BOP to swap GC pumps per BwOP GC-5, in preparation for an OOS on 1GC01PA next shift. TSO has requested Unit 1 prepare to raise turbine load to full power at 0.4 MW/min due to grid demand.

After completing shift turnover and relief, the BOP will swap stator cooling pumps per BwOP GC-5.

After swapping stator cooling pumps, Power Team will request Unit raise turbine load to full power at 0.4 MW/min due to grid demand. The crew will commence a power ascension at 0.4 mw/min.

After a measurable change in power, feedwater line pressure detector 1PT-508 will fail high over a 30 second period. Both main feedwater pumps speed will lower, reducing feedwater flow and causing all steam generator levels to begin lowering. The crew will take actions to stabilize the plant by taking manual control of the main feedwater pumps. 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL, Attachment J, will be implemented. 1PT-508 will remain unavailable for the remainder of the scenario.

After the 1PT-508 failure is addressed, PZR PORV 1RY455A will open to the intermediate position, resulting in a slow RCS pressure drop. The ATC will isolate the PZR PORV by closing 1RY8000A, PORV block valve. Once 1RY8000A is closed, its breaker will trip open, removing power from 1RY8000A.

1RY455A will remain unavailable for the remainder of the scenario. Tech spec 3.4.11, conditions B and C apply. If pressure drops below 2209 psig, Tech Spec 3.4.1 will apply.

After the PZR PORV failure is addressed, VCT level transmitter 1LT-112 will fail high, causing letdown to divert to the HUT. The RO will take manual control and close the letdown divert valve. Tech Spec 3.3.9 does not apply in Mode 1. The instrument failure will prevent RMCS for operating in automatic mode. 1LT-112 will remain unavailable for the remainder of the scenario.

After the VCT level channel has been addressed, a loss of instrument bus 114 will occur. The crew will enter 1BwOA ELEC-2, LOSS OF INSTRUMENT BUS, and determine that instrument bus 114 is damaged and cannot be energized from the CVT. Tech Spec 3.8.9 will apply.

After the instrument bus 114 failure is addressed, bus 143 is lost causing the loss of 1A and 1C CW pumps. Condenser vacuum is lost and a manual reactor trip or an automatic turbine trip - reactor trip signal is generated. The turbine trips but the reactor does not trip, placing the plant in an ATWS condition.

1BwEP-0 is entered with a transition to 1BwFR S-1. A failure of rod control to automatically insert rods at >

48 steps/minute forces the Unit NSO to manually insert control rods. The RWST will be used as the borated water source since the BA transfer pump has lost power. RCS pressure rises and PZR PORV 1RY456 opens to reduce pressure.

Although RCS pressure starts dropping, PZR PORV 1RY456 remains open creating a loss of reactor coolant. 1BwFR-S.1 is completed and 1BwEP-0 is reentered with a failure of high head injection valves (1SI8801A/B) and charging line Cnmt isolation valves (1CV8105/6) to automatically reposition. The crew will take action to manually open 1SI8801A/B and close 1CV8105/6.

Completion criteria is transition to 1BwEP ES-1.2.

Critical Tasks

1. Insert negative reactivity into the core by initiating RCCA insertion at greater than or equal to 48 steps per minute prior to completion of step 1 of 1BwFR-S.1.

(ERG Critical Task number - FR-S.1--C) (K/A number - 000029EA1.09 importance - 4.0/3.6)

2. Establish high head injection flow before transition out of 1BwEP-0.

(ERG Critical Task number - E-0--I) (K/A number - APE008AA2.10, importance - 3.6/3.6)

NRC 11-1 Page 2 of 25

SIMULATOR SETUP GUIDE:

Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.

Establish the conditions of IC-18, 75% power, steady state, equilibrium xenon.

Complete items on Simulator Ready for Training Checklist.

Verify/remove any Equipment Status Tags and Danger Tags not applicable to the scenario.

Place simulator in RUN (allow simulator to run during board walk down and turnover).

Turn ON two sets of pressurizer back-up heaters and stabilize RCS pressure.

Shut down the 1B CW pump and allow enough time for 1CW001B to fully close.

Run caep NRC 11-1 SETUP from disk and verify the following actuate:

IOR ZDI1CW01PB PTL

MRF ED093B OPEN

IMF RP02A

IMF RP02B

IMF RD09 8

IRF RP49 OUT

TRGSET 1

THPPRZR .GT. 2315

IMF TH11B (1 0) 100

IOR ZDI1RY8000B AUTO

Place 1B CW pump C/S in PTL.

Place info tags on 1B CW pump C/S.

Provide students with turnover sheets, 1BwOS NR-1, critical parameter sheet, and beacon load follow sheets.

Replace procedures requiring new drafts for PPC mod in simulator procedure books.

NRC 11-1 Page 3 of 25

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Swap stator cooling pumps.

If dispatched as EO to observe stator cooling pump swap, report 1B stator cooling pump is ready for start, the pump has stable operating parameters once running, and no signs of leakage at the stator water skid.

If dispatched as EO to acknowledge stator panel alarm, insert the following:

MRF TP15 ACK to acknowledge 1PL01J.

Acknowledge as SM commencement and completion of procedure.

Event 2: Raise power at 0.4 MW/min As Power Team, contact the MCR by phone and request Unit 1 raise power to 100% at 0.4 MW/min due to grid demand.

Acknowledge as chemistry/rad protection requests for RCS samples (if required).

Acknowledge as Power Team initiation of ramp.

Event 3: Feed line pressure detector 1PT-508 fails high.

Insert IMF FW16 1500 30 for 1PT-508 failed low.

If dispatched as EO to investigate 1PT-508, wait two minutes report no visible damage to 1PT-508.

Acknowledge as SM 1PT-508 failure, on line risk assessment, request for maintenance support, and IR requests.

Event 4: 1RY455A partially opens/1RY8000A block valve breaker trips.

Run caep NRC 11-1 EVENT 4 from disk and verify the following actuate:

IMF TH11A 5

TRGSET 2 ZLO1RY8000A(2) = = 0

MRF ED058C (2 5) OPEN If dispatched as Equipment Operator, report 1RY8000A breaker (131X2B A5 front and rear) is tripped. If breaker reclosure is requested, the breaker will not close.

Acknowledge as Shift Manager the failure(s), LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.

NRC 11-1 Page 4 of 25

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 5: VCT level channel 1LT-112 failure.

Insert IMF CV16 100 10 to fail VCT level transmitter 1LT-112 high over a 10 second period.

If dispatched as EO to investigate 1LT-112, wait 2 minutes and report no visible damage to 1LT-112.

As SM, acknowledge failure of 1LT-112, dequip entry, and requests for on line risk assessment, maintenance support, and IR initiation.

Event 6: Loss of instrument bus 114 Run caep NRC 11-1 EVENT 6 from disk and verify the following actuate:

IMF ED11D

IRF ED019 OPEN When dispatched as EO/NSO to instrument bus 114, wait one minute and report instrument bus 114 has faint acrid smell coming from bus panel, there are burn marks on bus panel door but no active fire exists.

When dispatched as Equipment Operator to instrument inverter 114, wait two minutes and report inverter 114 output breaker is tripped open. Inverter 114 otherwise appears normal.

If dispatched as Equipment Operator to fail open 1AF005E-H, perform the following:

IMF FW45E 100 IMF FW45F 100 IMF FW45G 100 IMF FW45H 100 Report to NSO that 1AF005E-H are failed open.

Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.

Event 7: Bus 143 Deenergized Insert IMF ED07C If dispatched as EO to bus 143 report acrid smell in Div. 11 ESF switchgear room but no fire.

NRC 11-1 Page 5 of 25

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 8: ATWS If dispatched as EO to locally trip Unit 1 reactor, wait until 1BwFR-S.1 step 7 (CHECK IF REACTOR SUBCRITICAL) is complete, then delete the following malfunctions to locally open Unit 1 reactor trip breakers:

DMF RP02A

DMF RP02B If reactor trip breakers do not open when above malfunctions deleted, insert the following remote functions to open the reactor trip breakers:

IRF RP01 TRIP

IRF RP02 TRIP If dispatched as EO/FS to verify dilution paths isolated, wait 15 minutes and report the following: 1CV8441, 1CV8435, & 1CV8453 are locked closed. 1AB8629A is closed.

Event 9: PZR PORV 1RY456 fails open (preload)

If dispatched as EO to locally close 1RY8000B at the breaker, wait 5 minutes and report 1RY8000B is not responding to local control.

Acknowledge as SM procedure changes, E Plan evaluations, and STA request.

NRC 11-1 Page 6 of 25

Scenario NRC 11-1 Event 1 No: No.

Event Swap stator cooling pumps

==

Description:==

Time Position Applicants Actions or Behavior CUE o From turnover, swap stator cooling pumps per BwOP GC-5, SWITCHING STANDBY AND OPERATING GC PUMPS.

US Directs BOP to perform BwOP GC-5.

o Peer check actions of BOP operator.

BOP

Refer to BwOP GC-5.

Start 1B stator water pump at 1PM02J.

Allow both pumps to run in parallel for 5 minutes (per step D.1).

Note: When examinee indicates that a 5 minute parallel run is required, evaluator may time compress parallel run and give cue that 5 minutes has elapsed o Notify EO to perform leak check at skid and acknowledge local alarm.

Stop 1A stator water pump at 1PM02J.

Inform US BwOP GC-5 complete.

US

Acknowledge report.

o Notify SM BwOP GC-5 is complete.

ATC o Peer check actions of BOP operator.

o Monitor remainder of MCB.

NOTE: After BwOP GC-5 is complete and with lead examiners concurrence, enter next event.

Comments:

NRC 11-1 Page 7 of 25

Scenario NRC 11-1 Event 2 No: No.

Event Raise power at 0.4 MW/min

==

Description:==

Time Position Applicants Actions or Behavior CUE o Call from Power Team to raise power 100 MW at 0.4 Mw/min.

US

Acknowledge request to raise power 100 MW at 0.4 Mw/min.

Implement actions of 1BwGP 100-3.

o Perform pre-job brief per HU-AA-1211 PRE-JOB, HEIGHTENED LEVEL OF AWARENESS, INFREQUENT PLANT ACTIVITY, AND POST JOB BRIEFINGS for load ramp.

US

Direct raising load 100% at 0.4 MW/min.

o Initiate load swing instruction sheet, 1BwGP 100-4T2.

CREW o Review applicable Precautions, and Limitations and Actions. (may have been done in PJB prior to starting demo)

ATC o Verify rod position and boron concentration.

o Perform dilution boundary calculation per 1BwGP 100-4T2 (may have been previously completed).

Initiate dilution, if required (BwOP CV-5).

Determine required PW volume:

o Effects of previously performed dilutions.

o Braidwood Boration Dilution Tables.

o REMA form.

Determine required PW flow rate.

Perform the following at 1PM05J:

o Add PW in auto dilute mode o Set 1FK-111 PW/Total Flow Cont POT to the desired PW flow rate.

o Set 1FY-0111 PW Control Predet Counter to desired PW volume.

o Place MAKE-UP CONT SWITCH to STOP position.

o Set MODE SELECT to DIL/ALT DIL position.

o Place MAKE-UP CONT Switch to START.

o Verify proper operation of valves and PW makeup pump (1CV111B open, 1CV111A throttled, 1CV110B open (ALT DIL only), PW pump running, PW flow on recorder).

OR Comments:

NRC 11-1 Page 8 of 25

Scenario NRC 11-1 Event 2 No: No.

Event Raise power at 0.4 MW/min

==

Description:==

Time Position Applicants Actions or Behavior RO o Batch addition of PW:

o Open 1CV111B.

o Open 1CV110B.

o Open 1CV111A.

o When desired amount of primary water added:

o Close 1CV111A.

o Verify/Close 1CV111B.

o Verify/Close 1CV110B.

BOP

Raise turbine load at 1PM02J or OWS drop 210 by performing the following:

Select SETPOINT.

Enter desired MW into REF DEMAND window.

Select ENTER.

Enter 0.4 MW/min into the RATE window.

Select ENTER.

Select EXIT.

o Notify US and RO of pending ramp.

Select GO/HOLD.

Verify GO/HOLD button illuminates.

Verify HOLD illuminated RED.

Select GO.

Verify GO illuminates RED.

Verify main turbine load begins to rise.

ATC/

Monitor reactor power and load ascension:

BOP

Monitor NIs, Tave, I, Pzr press/level at 1PM05J or HMI.

Monitor MW and DEHC system response at 1PM02J or OWS drop 210.

During dilution, monitor the following at 1PM05J and HMI:

VCT level.

RCS Tave rising/RCS boron concentration lowering.

o PW/Total flow predet counter responding correctly.

o Verify dilution auto stops at preset value.

o Return Reactor Makeup System to automatic.

After measurable change in power and lead examiner approves, initiate the next event.

Comments:

NRC 11-1 Page 9 of 25

Scenario NRC 11-1 Event 3 No: No.

Event FW Htr Dsch Press 1PT-508 fails high.

==

Description:==

Time Position Applicants Actions or Behavior CUE o Control rods inward motion o Annunciators (1-15-A9 thru D9) "S/G 1_ LEVEL DEVIATION HIGH LOW" o Steam flow / FW flow mismatch on all SGs o 1B MFP speed lowering o 1C MFP speed lowering o Master, 1B and 1C MFP speed controllers demand lowering o 1PI-508 meter indication rising.

o 1PI-509 meter indication rising.

CREW

Refer to BwARs

Determine 1PT-508 failing high at 1PM04J.

Identify entry conditions for 1BwOA INST-2, OPERATION WITH A FAILED INSTRUMENT CHANNEL.

o Dispatch operators to investigate 1PT-508 failure.

US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions

Implement 1BwOA INST-2 "OPERATION WITH A FAILED INSTRUMENT CHANNEL", Attachment J "FW PUMP SPEED CONTROL MALFUNCTION" and direct operator actions of 1BwOA INST -2 to establish the following conditions.

o Direct BOP/RO to stop load ramp/dilution BOP

Perform the following at 1PM04J:

Place 1SK-509A, Master FW pump speed controller in manual.

Raise demand on 1SK-509A.

Raise FW pump speed sufficiently to restore SG levels and FW header DP to normal.

Maintain SG levels by operating 1SK-509A in manual.

ATC

Perform the following:

Monitor reactor power response to SG under and overfeeding transient.

US

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

Comments:

NRC 11-1 Page 10 of 25

Scenario NRC 11-1 Event 4 No: No.

Event 1RY455A partially opens/1RY8000A block valve breaker trips

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator 1-12-B2, PZR PORV OR SAF VLV OPEN o Annunciator 1-12-C1 PZR PRESS CONT DEV LOW HTRS ON

Annunciator 1-12-C6 PZR PORV DSCH TEMP HIGH

1RY455A open and closed lights lit.

PZR pressure dropping on 1PI-455 - 458.

ATC

Perform the following at 1PM05J:

Recognize 1RY455A PORV has opened prior to reaching lift setpoint.

o Place 1RY455A, PZR PORV, C/S to CLOSE.

o Determine 1RY455A will not close.

Place 1RY8000A, PZR PORV block valve, C/S to close.

o Report failure to US.

o Recognize/reports DNB LCO 3.4.1 pressure exceeded (<2209 psig) if applicable.

o Recognize loss of indication of 1RY8000A breaker following valve closure.

o Report when DNBR LCO can be exited, if applicable.

o Dispatch operator to investigate 1RY8000A breaker.

BOP o Perform the following:

o Dispatch operators to 1RY8000A breaker.

o Assist US by making notifications.

o Refer to BwARs.

US

Acknowledge PORV failure and concur with actions to close PORV and/or PORV block valve.

Determine LCO 3.4.11 Condition B and C are applicable.

o TRM 3.4.d does not apply.

Acknowledge DNB LCO status (if applicable).

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

EVALUATOR NOTE: After the actions for PZR PORV failure are complete and with lead examiners concurrence, enter next event.

Comments:

NRC 11-1 Page 11 of 25

Scenario NRC 11-1 Event 5 No: No.

Event VCT level channel 1LT-112 failure

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator VCT LEVEL HIGH-HIGH LOW (1-9-A2)

VCT level indicator 1LI-112 rising at 1PM05J.

1CV112A, Letdown to VCT or HUT Divert Valve - HUT light lit at 1PM05J.

VCT level recorder 1LT-0185 indication lowering at 1PM05J.

ATC/

Determine 1LT-112 has failed high.

BOP

Reference BwAR.

o Dispatch operators to investigate 1LT-112.

US

Notify SM of plant status.

ATC

Take manual control of VCT level at 1PM05J:

o Place 1CV112A in manual and lower demand to close 1CV112.

o Place 1CV112A control switch in VCT.

o Determine RMCS auto makeup - NOT AVAILABLE.

o Place RMCS in manual at 1PM05J:

o Place RMCS mode C/S to MAN.

o Place RMCS makeup C/S to START.

o Place RMCS to OFF to enable 37% low level alarm.

US o Determines TS 3.3.9 is NOT applicable.

Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct instrument failure.

EVALUATOR NOTE: After the actions for the VCT level channel malfunction are complete and with lead examiners concurrence, insert the next event.

Comments:

NRC 11-1 Page 12 of 25

Scenario NRC 11-1 Event 6 No: No.

Event

Description:

Loss of instrument bus 114 Time Position Applicants Actions or Behavior CUE

Annunciator 1-4-D5, BUS 114 INVERTER TROUBLE

Annunciator 1-4-A3, PROCESS I & C CAB PWR SUP FAILURE

Annunciator 1-4-B3, SOLID STATE PROT CAB GENERAL WARNING

Numerous block 4,10, & 13 annunciators.

PR N44 deenergized.

ATC/

Determine instrument inverter 114 deenergized.

BOP

Reference BwARs.

CREW

Identify entry conditions for 1BwOA ELEC-2, LOSS OF INSTRUMENT BUS.

o Dispatch operators to investigate status of inverter and instrument bus.

US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Enter/Implement 1BwOA ELEC-2 LOSS OF INSTRUMENT BUS and direct operator actions of 1BwOA ELEC-2 to establish the following conditions:

o Direct BOP/ATC to stop load ramp/dilution.

RO

Check control channels operable at 1PM05J:

PZR pressure

PZR level

TAVE

Delta T BOP

Check control channels operable at 1PM05J/1PM04J:

PIMP

SG level

Steam flow

Feed flow BOP

Dispatch operator to check instrument bus 114 and inverter 114:

Instrument bus 114 is damaged.

o Instrument inverter 114 is NOT damaged.

CREW

Determine Instrument Bus 114 cannot be energized.

US

Implement 1BwOA ELEC-2, Attachment D, INSTRUMENT BUS 114 ACTIONS.

Comments:

NRC 11-1 Page 13 of 25

Scenario NRC 11-1 Event 6 No: No.

Event

Description:

Loss of instrument bus 114 Time Position Applicants Actions or Behavior US

Refer to 1BwOA ELEC-2, Table D, LOSS OF INSTRUMENT BUS 114 EFFECTS.

Brief crew on loss of instrument bus 114 effects.

Direct actions of 1BwOA INST-1 NUCLEAR INSTRUMENTATION MALFUNCTION, Attachment A.

Dispatch operators to fail air to 1AF005E-H.

Determine TS 3.8.9, condition B is applicable EVALUATOR NOTE: After the crew recognizes instrument bus 114 cannot be reenergized and the tech spec call has been made, the scenario can continue by inserting the next event. If desired by evaluator the crew can perform steps below of 1BwOA INST-1. When crew requests assistance for tripping bistables, cue will be that no extra NSOs are currently available.

RO/ o Place Rod Bank Select in MANUAL BOP o Check annunciator 1-10-B5 - LIT o Place N44 Rod Stop Bypass switch in BYPASS at 1PM07J o Check Tave - Tref deviation within 1 deg. F.

o Check SG levels normal and stable.

o Defeat N44 Functions at 1PM07J o Place upper section current comparator defeat switch in PR N44 position.

o Place lower section current comparator defeat switch in PR N44 position.

o Place power mismatch bypass switch in PR N44 position.

o Place rod stop bypass switch in PR N44 position.

o Check annunciator 1-10-C3 - LIT o Reset PR N44 rate trip at 1PM07J o Place computer points in TEST, N0047, N0048, U1143 o Remove computer point from scan N0052A o Place N44 input to DEH in test o Remove N44 control power fuses at 1PM07J o Select LOOP delta T recorder to operable channel o Check Tave - Tref within 1 deg. F o Place rods in auto Comments:

NRC 11-1 Page 14 of 25

Scenario NRC 11-1 Event 7 No: No.

Event Bus 143 De-energized

==

Description:==

Time Position Applicants Actions or Behavior CUE

All CW pumps tripped

BP Annunciator C-9 (5.6) "CNDSR NOT AVAILABLE"

Annunciator 1-11-A9, TURB TRIP ABOVE P-8 RX TRIP

Condenser pressure rising.

ATC/

Identify/report loss of bus 143 BOP

Identify report loss of all CW pumps

Identify report condenser pressure rising US

Notify SM of plant status

Direct operator to trip reactor ATC o Initiate a manual reactor trip US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions

Enter/Implement 1BwEP-0 and direct operator actions of 1BwEP-0 ATC Perform immediate operator actions of 1BwEP-0:

Verify reactor trip

Rod bottom lights - NONE LIT

Reactor trip & Bypass breakers - CLOSED

Neutron flux - NOT DROPPING

Manually trip the reactor

1PM05J

1PM06J

PR channels > 5%

US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions

Enter/Implement 1BwFR-S.1 and direct operator actions of 1BwFR-S.1 Comments:

NRC 11-1 Page 15 of 25

Scenario NRC 11-5 Event 8 No: No.

Event ATWS

==

Description:==

Time Position Applicants Actions or Behavior ATC Perform immediate operator actions of 1BwFR-S.1:

Verify reactor trip

Rod bottom lights - NONE LIT

Reactor trip & Bypass breakers - CLOSED

Neutron flux - NOT DECREASING

Manually trip the reactor

1PM05J

1PM06J

Determine control rods NOT inserting automatically

[CT]

Manually insert control rods at greater than or equal to 48 steps per minute prior to FR-S.1- completion of step 1 of 1BwFR-S.1.

-C BOP Perform immediate operator actions of 1BwFR-S.1:

Verify Turbine Trip

All Turbine throttle valves - CLOSED

All Turbine governor valves - CLOSED BOP

Check AF pumps running

AF pump run lights status (May be LIT or NOT LIT) o Manually start the 1A AF pump if it did not yet have an auto start signal.

o Manually start the 1B AF pump (loss of bus 114 prevents auto start)

RO/

Initiate emergency boration of the RCS BOP

CV pumps - ONE RUNNING

Open 1CV8104 o Attempt start boric acid transfer pump (no power to pump)

Open 1CV112D or 1CV112E

Close 1CV112B or 1CV112C

Check PZR pressure < 2335 psig BOP

Verify CNMT vent isolation

Group 6 CNMT vent isolation monitor lights - LIT Comments:

NRC 11-1 Page 16 of 25

Scenario NRC 11-5 Event 8 No: No.

Event ATWS

==

Description:==

Time Position Applicants Actions or Behavior ATC

Check If The Following Trips Have Occurred

Reactor Trip has NOT occurred.

Dispatch operator to locally trip reactor

Turbine Trip

All Turbine throttle valves - CLOSED

All Turbine governor valves - CLOSED ATC

Check if reactor is subcritical o PR channels > 5% (continue in 1BwFR S-1) o PR channels < 5% (transition to 1BwEP-0)

IR channels startup rate - NEGATIVE NOTE: The reactor will be locally tripped sometime after the previous step (step 7 of 1BwFR-S.1).

NOTE: If Reactor power is >5% at this point the remaining steps below will be completed in 1BwFR S-1.

ATC/

Check SG levels BOP

At least one SG level > 10% (31%)

SG levels maintained between 10% (31%) and 50%

1SD002A-H - CLOSED

Verify dilution paths isolated

1CV111A & B - CLOSED

BTRS mode selector switch - OFF

Dispatch operator to locally verify dilution paths isolated

Stop reactivity insertion from RCS cooldown

Check RCS temperature -NOT DROPPING IN AN UNCONTROLLED MANNER

Check SG pressures - NOT DROPPING IN AN UNCONTROLLED MANNER OR COMPLETELY DEPRESSURIZED.

ATC/

Check CETCs < 1200°F BOP

Verify reactor subcritical

PR channels < 5%

IR channels - NEGATIVE SUR

Return to 1BwEP-0 Comments:

NRC 11-1 Page 17 of 25

Scenario NRC 11-1 Event 9 No: No.

Event

Description:

PZR PORV 1RY456 fails open Time Position Applicants Actions or Behavior BOP Perform immediate operator actions of 1BwEP-0 at 1PM02J or OWS drop 210:

Verify Turbine Trip.

All Turbine throttle valves - CLOSED.

All Turbine governor valves - CLOSED.

BOP Perform immediate operator actions of 1BwEP-0 at 1PM01J:

Verify power to 4KV busses.

ESF Buses - BOTH ENERGIZED (141 & 142).

CREW (If manual SI not previously performed) Recognize and respond to conditions requiring a Safety Injection in accordance with 1BwEP-0 REACTOR TRIP OR SAFETY INJECTION, Step 4:

PZR pressure cannot be maintained > 1829 psig.

Manually actuate SI from 1PM05J and 1PM06J.

CREW

Check SI Status at 1PM05J:

o SI First OUT annunciator - LIT.

o SI ACTUATED Permissive Light - LIT.

o SI Equipment - AUTOMATICALLY ACTUATED.

o BOTH SI pumps - RUNNING.

o CV pump to cold leg isolation valves 1SI8801A/B - CLOSED.

US

Direct BOP to perform Attachment B of 1BwEP-0 EVALUATOR NOTE: US and RO will continue in 1BwEP-0 while BOP is performing Attachment B:

EVALUATOR NOTE: The examinees may elect to re-align train A high head injection valves before directed in 1BwEP-0. OP-AA-101-111, ROLES AND RESPONSIBILITIES OF ON SHIFT PERSONNEL, step 4.6.2.5, directs operators to manually initiate safety systems automatic actions when operating parameters exceed the systems automatic initiation setpoints and the initiation does not occur.

BOP

Verify FW isolated at 1PM04J:

FW pumps - TRIPPED.

Isolation monitor lights - LIT.

FW pumps discharge valves - CLOSED (or going closed) 1FW002A-C.

Verify DGs running at 1PM01J:

DGs - BOTH RUNNING.

Comments:

NRC 11-1 Page 18 of 25

Scenario NRC 11-1 Event 9 No: No.

Event

Description:

PZR PORV 1RY456 fails open Time Position Applicants Actions or Behavior

1SX169A/B OPEN.

Dispatch operator locally to check operation

Verify Generator Trip at 1PM01J:

OCB 1-8 and 7-8 open.

PMG output breaker open.

Verify Control Room ventilation aligned for emergency operations at 0PM02J:

VC Rad Monitors - LESS THAN HIGH ALARM SETPOINT.

Operating VC train equipment - RUNNING.

0B Supply fan

0B Return fan

0B M/U fan

0B Chilled water pump

0B Chiller

Operating VC train dampers - ALIGNED.

M/U fan outlet damper - 0VC08Y NOT FULLY CLOSED.

0B VC train M/U filter light - LIT.

0VC09Y - OPEN

0VC313Y - CLOSED

Operating VC train Charcoal Absorber aligned for train B.

0VC44Y - CLOSED

0VC05Y - OPEN

0VC06Y - OPEN

Control Room pressure greater than +0.125 inches water on 0PDI-VC038.

Verify Auxiliary Building ventilation aligned at 0PM02J:

Two inaccessible filter plenums aligned.

Plenum A:

0VA03CB - RUNNING

0VA023Y - OPEN

0VA436Y - CLOSED

Plenum C:

0VA03CE RUNNING

0VA067Y - OPEN

0VA052Y - CLOSED

Verify FHB ventilation aligned at 0PM02J:

0VA04CB - RUNNING

0VA055Y - OPEN

0VA062Y - OPEN

0VA435Y - CLOSED Comments:

NRC 11-1 Page 19 of 25

Scenario NRC 11-1 Event 9 No: No.

Event

Description:

PZR PORV 1RY456 fails open Time Position Applicants Actions or Behavior

Notify US Attachment B complete ATC

Verify ECCS pumps running at 1PM05J/1PM06J:

BOTH CV pumps - RUNNING.

Manually start 1B CV pump.

1A CV pump - RUNNING.

Check RH pumps - RUNNING.

Manually start 1B RH pump.

1A RH pump - RUNNING.

Check SI pumps - RUNNING.

Manually start 1B SI pump.

1A SI pump - RUNNING.

ATC/

Verify RCFCs running in Accident Mode:

BOP

1A & 1C RCFC Accident Mode lights - LIT at 1PM06J.

1B & 1D RCFC Accident Mode lights - NOT LIT at 1PM06J.

Stop 1B & 1D high speed RCFCs at 1PM06J.

Close 1SX112B and 1SX114B, CNMT chiller 1B SX inlet & outlet valves at 0PM02J.

Verify/open 1SX147B, CNMT chiller 1B SX bypass valve at 0PM02J.

Verify/open 1SX016B and 1SX027B, RCFC 1B & 1D SX inlet & outlet isolation valves at 1PM06J.

Start 1D & 1D low speed RCFCs at 1PM06J.

ATC/

Verify Phase A isolation:

BOP

Group 3 CNMT isolation monitor lights - NOT ALL LIT at 1PM06J.

Manually actuate CNMT isolation phase A at 1PM05J and/or 1PM06J.

Manually close CNMT isolation phase A valves.

o 1CV8112, 1CV8160, 1RY8028 & 1RY8033 at 1PM05J.

o 1WO006B, 1WO020B, & 1WO056A at 1PM06J.

o 1PR001B, 1FP010, 1PS229A & 1PS229B at 1PM11J.

o 1RE9160B, 1RE9170 & 1RF027 at 1PM11J.

ATC/

Verify Cnmt Vent isolation at 1PM06J:

BOP

Group 6 Cnmt Vent Isol monitor lights - ALL LIT.

ATC/

Verify AF system at 1PM06J:

BOP

1B AF pump - NOT RUNNING.

Manually start 1B AF pump.

1A AF pump - RUNNING.

Comments:

NRC 11-1 Page 20 of 25

Scenario NRC 11-1 Event 9 No: No.

Event

Description:

PZR PORV 1RY456 fails open Time Position Applicants Actions or Behavior

AF isolation valves - OPEN.

1AF13A-H

AF flow control valves - THROTTLED

1AF005E-H failed open due to loss of instrument bus 114.

o Dispatch operator to locally control 1AF005E-H.

o Throttle 1AF013E-H from 1PM06J ATC/

Verify CC pumps at 1PM06J:

BOP

BOTH CC pump - RUNNING.

Manually start 1B CC pump.

ATC/

Verify SX pumps at 1PM06J:

BOP

BOTH SX pumps - RUNNING.

Manually start 1B SX pump.

ATC/

Check if Main Steamline Isolation required at 1PM06J:

BOP

All SG pressure > 640 psig.

Containment pressure < 8.2 psig ATC/

Check if CS is required at 1PM06J:

BOP

CNMT pressure has not risen > 20 psig.

BOP/ ATC

Verify Total AF flow at 1PM06J:

AF flow > 500 gpm.

S/G NR levels - NOT rising in an uncontrolled manner.

ATC/ BOP Note: the following task may have been performed earlier per note on page 18

Verify ECCS valve alignment at 1PM06J:

[CT]

Group 2 Cold Leg Injection monitor lights required for injection - NOT ALL LIT.

E-0--I

Manually OPEN 1SI8801A/B

Manually CLOSE 1CV8105/06

Verify ECCS flow at 1PM05J:

High Head SI flow >100 gpm (1FI-917).

RCS pressure > 1700 psig.

Comments:

NRC 11-1 Page 21 of 25

Scenario NRC 11-1 Event 9 No: No.

Event

Description:

PZR PORV 1RY456 fails open Time Position Applicants Actions or Behavior ATC

Check PZR PORVs and SPRAY VALVES at 1PM05J:

1RY456 PORV OPEN

1RY8000B can NOT be CLOSED CREW Transition to 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT.

Comments:

NRC 11-1 Page 22 of 25

Scenario NRC 11-1 Event 9 No: No.

Event PZR PORV 1RY456 fails open

==

Description:==

Time Position Applicants Actions or Behavior US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Request STA evaluation of status trees.

Enter/Implement 1BwEP-1 and direct operator actions of 1BwEP-1 to establish the following conditions:

ATC NOTE: this step may have been performed earlier per OAS summary page of 1BwEP-0.

Check status of RCPs at 1PM05J:

All RCPs - ALL RUNNING.

Hi Head SI flow > 100 gpm

RCS Pressure < 1425 psig

STOP ALL RCPs ATC/

Check if SG secondary pressure boundaries are intact at 1PM04J:

BOP

Check pressure in all SGs:

None dropping in an uncontrolled manner.

None completely depressurized.

ATC/

Check intact SG levels at 1PM04J:

BOP

SG levels maintained between 10% (31%) and 50%.

S/G NR levels - NOT rising in an uncontrolled manner.

ATC/

Check secondary radiation normal BOP

Reset Phase A.

OPEN 1SD005A-D at 1PM11J

Contact Chemistry for SG sampling.

Check Secondary trends at RM-11 or PPC:

1PR08J SG Blowdown.

1PR27J SJAE/GS.

1AR 22/23A-D Main steam lines.

ATC

Check PZR PORVs and isolation valves at 1PM05J:

PORV isolation valves - 1RY8000B Energized but not responding.

PORVs - BOTH OPEN

PORV isolation valves - 1RY8000A previously CLOSED Comments:

NRC 11-1 Page 23 of 25

Scenario NRC 11-1 Event 9 No: No.

Event PZR PORV 1RY456 fails open

==

Description:==

NOTE: If subcooling is ACCEPTABLE in the following step, the crew will transition to 1BwEP ES-1.1. When Charging pump is stopped in 1BwEP ES-1.1 RCS pressure will drop and transition will be made to 1BwEP ES-1.2, then the scenario may be terminated.

ATC/

Check if ECCS flow should be reduced at 1PM05J:

BOP

RCS subcooling - NOT acceptable.

ATC/

Check if CS should be stopped BOP

CS pumps - NONE RUNNING ATC/

Check if RH pumps should be stopped at 1PM06J:

BOP

Reset SI

RCS pressure > 325 psig o If RCS pressure is STABLE, perform the following

Check RH pumps suction aligned to RWST

STOP BOTH RH pumps ATC/

Check for Faulted SG Indications BOP

SG Pressures - ALL STABLE

RCS Pressure - STABLE BOP

Check if DGs should be stopped

4KV busses - Energized from offsite power (EXCEPT BUS 143 which is FAULTED)

Stop DG 1A & 1B at 1PM01J ATC/

Evaluate Plant Status BOP

RH Trains - BOTH AVAILABLE

Aux Bldg Rads - ALL NORMAL

Check trends at RM-11 or PPC:

US

Place H2 Monitors in service o Contact U-2 for assist NSO to place U-1 H2 monitors in service.

o Contact SM for consulting with TSC BOP

Shutdown 0A VC chiller at 0PM02J ATC/

Energize Source Range Detectors BOP

Place Boron Dilution Alert Switches in NRMAL at 1PM05J

Place Scaler Timer Power Switch to ON at 1PM07J ATC/

Check if RCS cooldown and depressuization is required BOP

RCS pressure > 325 psig Comments:

NRC 11-1 Page 24 of 25

Scenario NRC 11-1 Event 9 No: No.

Event PZR PORV 1RY456 fails open

==

Description:==

CREW Transition to 1BwEP ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION.

NOTE: Scenario is terminated at this point (Final)

Comments:

NRC 11-1 Page 25 of 25

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