Text

2009 Braidwood Initial License Examination Proposed Simulator Scenarios
	ML100700255
Person / Time
Site:	Braidwood
Issue date:	10/05/2009
From:	Palagi B; Operations Branch III
To:	; Exelon Generation Co
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Simulation Facility Braidwood Scenario Operating Test No. 2009-1 No.:

NRC 09-1 Examiners: ______________________ Applicant: ____________________ SRO

______________________ ____________________ RO

______________________ ____________________ BOP Initial Conditions: IC-18 Turnover: Unit 1 is at 75% power, steady state, equilibrium xenon, MOL. Online risk is green. 1C CD/CB pump is OOS for an alignment and vibration problem. Expected back in service in one week. The CV Cation demin is scheduled to be placed on line for 30 minutes later in the shift. 1PR11J filter change planned early in shift.

Event Malf. No. Event Event No. Type* Description Preload IMF RH01A RHR pump 1A trip IMF RP15F RHR pump 1B auto start failure IRF RP85 OPEN IMF RP01 Auto Rx trip failure IMF RH04B 1SI8811B fails to auto open IOR ZDI1CD05PC PTL 1C CD/CB pump OOS IOR ZDI1CD05PCB 1C CD/CB AOP OOS PTL IOR ZDI1CB113C CLS 1CB113C INFO Carded closed 1 None N-BOP 1PR11J filter change TS-US 2 IMF NI08H (500 10) C-RO, US PR NI N-44 fails high TS-US 3 IOR ZDIRM10 IN C-RO, US Rod control failure IMF RX17 -4.25 4 IMF TH18B 1B RCP shaft break 5 Preload C-RO, US Failure of Rx to auto trip 6 IMF TH06B 540000 M-ALL Large break RCS LOCA (1B RCS cold leg) 7 Preload C-RO 1A RH pump trip 8 Preload C-BOP 1SI8811A fails to auto 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. 1C CD/CB pump is OOS for an alignment and vibration problem. Expected back in service in one week. The CV Cation demin is scheduled to be placed on line for 30 minutes later in the 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 five 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 15 minutes.

After changing the 1PR11J filter, a failure of power range N-44 lower detector will occur. The crew should take actions per 1BwOA INST-1 including defeating the channel functions. Technical Specifications 3.3.1 applies.

After the Power Range 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 shutdown bank D position to stop the inward rod motion. 1BwOA ROD-1, UNCONTROLLED ROD MOTION, will be implemented. Rods will remain in shutdown bank D position for the remainder of the scenario.

After the rod control failure has been addressed, the 1B RCP shaft will fail. RCS flow in the 1B loop will drop until a reactor trip is required due to low RCS loop flow. The auto Rx trip function will fail requiring a manual reactor trip. The 1B RCP will dislodge components into the RCS, followed shortly by a large break LOCA in RCS loop 1B due to the dislodged RCP components. The crew will take actions per 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION. 1A RH pump will trip when starting. The crew must manually start 1B RH pump to establish low head ECCS flow. The crew will transition to 1BwEP-1 after determining that the RCS is not intact.

When the RWST level reaches the low-2 setpoint the crew will transition to 1BwEP ES-1.3, TRANSFER TO COLD LEG RECIRCULATION. Upon transition to 1BwEP ES-1.3, 1SI8811B will not automatically open due to failure of relay K648. The crew will align the 1B RH pump for cold leg recirculation per attachment A of 1BwEP ES-1.3 to ensure long term core cooling.

Completion criteria is performance of 1BwEP ES-1.3, step 3.

Critical Tasks

1. Manually trip reactor prior to completion of step 1 of 1BwEP-0.

(ERG Critical Task number - E-0--A) (K/A number - 000007EA1.06 importance - 4.4/4.5)

2. Manually start 1B RH pump prior to completion of step 6 of 1BwEP-0.

(ERG Critical Task number - E-0--H) (K/A number - 000011EA1.13 importance - 4.1/4.2)

3. Align 1B RH Pump suction to the containment sump prior to completion of step 3 of 1BwEP ES-1.3.

(ERG Critical Task number - ES-1.3--A) (K/A 011000EA1.11 Importance 4.2/4.2)

Braidwood NRC 09-1 Page 2

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, BOL, 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 1C CD/CB pump and 1C CD/CB pump aux oil pump C/Ss in PTL.

Place 1CB113C C/S in close.

Place CD/CB Pump Standby Selector C/S to OFF.

Run caep NRC 09-1 SETUP from disk and verify the following actuate:

IMF RH01A

IMF RP15F

IMF RP01

IMF RH04B

IOR ZDI1CD05PC PTL

IOR ZDI1CD05PCB PTL

IOR ZDI1CB113C CLS

IRF RP85 OPEN

Place INFO card on 1C CD/CB pump & 1C CD/CD pump aux oil pump.

Place INFO card on 1CB113C C/S.

Verify/Set I Target Curve slopes to +2% of I.

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

Braidwood NRC 09-1 Page 3

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.

Event 2: Power range N-44 fails high.

Insert IMF NI08H 500 10 Acknowledge as SM entry into TS 3.3.1 conditions A, D & E.

Acknowledge as SM request for writing IR, performing risk assessment and making appropriate notifications.

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.

AT THE CONCLUSION OF THE SCENARIO,

ENSURE THE FOLLOWING COMPUTER POINTS ARE TAKEN OUT OF TEST AND RETURNED TO SCAN: N0047, N0048, U1143, N0052A

ENSURE THE N44 INPUT TO DEH IS REMOVED FROM TEST Ensure control rods are returned to 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.

Run caep NRC 09-1 EVENT 4_6 from disk and verify the following actuate:

IOR ZDIRMIO IN IMF RX17 -4.25 trgset 1 "ZDIBKSEL(5) == 1" trg 1 "DOR ZDIRMIO" trgset 2 "ZDIBKSEL(4) == 1" trg 2 "DOR ZDIRMIO" trgset 3 "ZDIBKSEL(3) == 1" trg 3 "DOR ZDIRMIO" Braidwood NRC 09-1 Page 4

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.

INSTRUCTOR/SIMULATOR RUN AID GUIDE Events 4 & 6: 1B RCP shaft break & Large break LOCA (1B RCS cold leg) after reactor trip.

Run caep NRC 09-1 EVENT 4_6 from disk and verify the following actuate:

IMF TH18B

TRGSET 1 "ZLO52BRKA(2) == 1"

IMF TH06B (1 10) 540000 10 Acknowledge as SM procedure changes, E Plan evaluations, and STA request.

After STA requested, as STA report CSF status.

Event 7: 1A RH pump trip If dispatched as EO to investigate 1A RH pump, report ground overcurrent flag at breaker cubicle.

Event 8: 1SI8811B fails to auto open Acknowledge as SM procedure changes, E Plan evaluations, and STA request.

After STA requested, as STA report CSF status.

AT THE CONCLUSION OF THE SCENARIO,

ENSURE THE FOLLOWING COMPUTER POINTS ARE TAKEN OUT OF TEST AND RETURNED TO SCAN: N0047, N0048, U1143, N0052A

ENSURE THE N44 INPUT TO DEH IS REMOVED FROM TEST Braidwood NRC 09-1 Page 5

Scenario NRC 09-1 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 15 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:

Braidwood NRC 09-1 Page 6

Scenario NRC 09-1 Event 2 No: No.

Event Power range N-44 fails high.

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator PWR RNG FLUX RATE RX TRIP ALERT (1-10-C3)

Annunciator PWR RNG CHANNEL DEV (1-10-C4)

Annunciator PWR RNG LOWER DET FLUX DEV HIGH (1-10-B4)

Control rod inward motion RO/

Determine PR channel N-44 failing high BOP

Place control rods in manual o Reference BwARs as time permits CREW

Identify entry conditions for 1BwOA INST-1, NUCLEAR INSTRUMENTATION MALFUNCTION US

Implement 1BwOA INST-1, NUCLEAR INSTRUMENTATION MALFUNCTION, Attachment A "PR CHANNEL FAILURE" and direct operator action

Notify SM of PR N-44 failure o Notify SM to evaluate for E-plan RO/

Check rod control status BOP

Rod bank select switch in manual

Check for rod stop

Annunciator PWR RNG FLUX HIGH ROD STOP (1-10-B5) - LIT

Place rod stop bypass switch to N-44 at 1PM07J RO

Verify/restore TAVE - TREF to within 1°F o Withdraw control rods o Adjust RCS boron concentration o Adjust turbine load BOP

Check SG levels normal and stable BOP

Bypass/defeat PR channel functions at 1PM07J

N-44 upper current comparator

N-44 lower current comparator

N-44 power mismatch bypass o N-44 rod stop bypass

N-44 channel current comparator Comments:

Braidwood NRC 09-1 Page 7

Scenario NRC 09-1 Event 2 No: No.

Event Power range N-44 fails high.

==

Description:==

Time Position Applicants Actions or Behavior BOP

Reset flux rate trip alarm for N44 RO/

Place computer points in test BOP

N0047

N0048

U1143

Place computer point in removed from scan

N0052A

Place N44 input to DEH in Test BOP

Remove control power fuses on PR N-44 to trip bistables RO

Select operable channel (other than 1D) to loop T recorder

Check if rod control can be placed in auto

C-5 not lit

TAVE - TREF within 1°F

Place control rods in auto US

Determines TS 3.3.1 conditions A, D, and E are applicable.

o Enter dequip for P-10

Contact SM to perform risk assessment, initiate IR, evaluate reactivity screening, make notifications and contact appropriate personnel to investigate/correct instrument failure.

NOTE: After the actions for N-44 are complete and with lead examiner concurrence, enter next event. Ensure rods are back in auto prior to inserting the next event.

Comments:

Braidwood NRC 09-1 Page 8

Scenario NRC 09-1 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.

RO

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:

o Direct BOP & RO to stop ramp.

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 still moving.

Cycle in hold out switch in both directions.

Verify rods still moving.

Determine rods were previously in auto

Place rod bank select switch in Shutdown Bank D.

Verify rods stopped moving.

US

Determine no TS actions apply.

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:

Braidwood NRC 09-1 Page 9

Scenario NRC 09-1 Event 4&5 No: No.

Event 1B RCP shaft failure/auto reactor trip failure

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator LOOSE PARTS MONITORING SYSTEM TROUBLE (1-13-E9)

Annunciator RCP 1B BRKR OPEN OR FLOW LOW ALERT (1-13-B3)

Annunciator RCP LOW FLOW ABOVE P8 RX TRIP (1-11-C5) (RED FIRST OUT) o RCS loop 1B flow lowering RO

Identify/report Red First Out condition and failure of auto reactor trip

[CT]

Manually trip reactor from 1PM05J or 1PM06J E-0--A US

Determine 1B RCP degraded flow requires reactor trip

Direct manual reactor trip CREW

Identify entry conditions for 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION 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 RO Perform immediate operator actions of 1BwEP-0:

Verify reactor trip

Rod bottom lights - ALL LIT

Reactor trip & Bypass breakers - OPEN

Neutron flux - DROPPING o Trip 1B RCP after reactor trip is verified.

BOP Perform immediate operator actions of 1BwEP-0:

Verify Turbine Trip

All Turbine throttle valves - CLOSED

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

Verify power to 4KV busses

ESF Buses - BOTH ENERGIZED (141 & 142)

Comments:

Braidwood NRC 09-1 Page 10

Scenario NRC 09-1 Event 6&7 No: No.

Event Large break RCS LOCA/1A RH pump trip

==

Description:==

Time Position Applicants Actions or Behavior CREW

Check SI Status o SI First OUT annunciator - LIT o SI ACTUATED Permissive Light - LIT o SI Equipment - AUTOMATICALLY ACTUATED o Either SI pumps - RUNNING o Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B

Recognize SI Actuated

Manually actuate SI from 1PM05J and 1PM06J RO o Determine RCP trip required o CNMT phase B actuated o RCS pressure < 1425 psig & High head SI flow (1FI-917) > 100 gpm o Trip ALL RCPs US o 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:

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.

Trip all running HD 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 Comments:

Braidwood NRC 09-1 Page 11

Scenario NRC 09-1 Event 6&7 No: No.

Event Large break RCS LOCA/1A RH pump trip

==

Description:==

Time Position Applicants Actions or Behavior

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:

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 RO/

Verify ECCS pumps running BOP

Both CV pumps - RUNNING

[CT]

NEITHER RH pump - RUNNING E-0--H

Manually start 1B RH pump prior to completion of step 6 of 1BwEP-0.

o Place 1A RH pump in pull out

Both SI pumps - RUNNING Comments:

Braidwood NRC 09-1 Page 12

Scenario NRC 09-1 Event 6 No: No.

Event Large break RCS LOCA

==

Description:==

Time Position Applicants Actions or Behavior RO

Perform the following at 1PM06J:

Verify RCFCs running in Accident Mode:

Group 2 RCFC Accident Mode lights - ALL LIT.

Verify Phase A isolation:

Group 3 Cnmt Isol monitor lights - ALL LIT.

Verify Cnmt Vent isolation:

Group 6 Cnmt Vent Isol monitor lights - ALL LIT.

Verify AF system:

AF pumps - Both RUNNING.

AF isolation valves - 1AF13A-H OPEN.

AF flow control valves - 1AF005A-H THROTTLED.

Verify CC pumps - BOTH RUNNING.

Verify SX pumps - BOTH RUNNING.

Check if Main Steamline Isolation - required:

o All S/G pressures > 640 psig (at 1PM04J).

o CNMT pressure > 8.2 psig.

Verify MSIVs & MSIV bypass valves - CLOSED.

Check if CS is required.

CNMT pressure has risen > 20 psig.

Group 6 CS monitor lights - ALL LIT.

Group 6 phase B lights - ALL LIT.

Verify/Stop ALL RCPs (at 1PM04J).

CS eductor suction flow - > 15 gpm on 1FI-CS013 & 1FI-CS014.

CS eductor additive flow - > 5 gpm on 1FI-CS015 & 1FI-CS016.

BOP/

Verify Total AF flow:

RO

AF flow > 500 gpm

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

Verify ECCS valve alignment BOP

Determine Group 2 Cold Leg Injection monitor lights required for injection - All lit Comments:

Braidwood NRC 09-1 Page 13

Scenario NRC 09-1 Event 6 No: No.

Event Large break RCS LOCA

==

Description:==

Time Position Applicants Actions or Behavior RO/

Verify ECCS flow BOP

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

RCS pressure < 1700 psig

SI pumps discharge flow > 200 gpm

RCS pressure < 325 psig

1B RH pump discharge flow > 1000 gpm RO

Check PZR PORVs and SPRAY VALVES at 1PM05J:

1RY455 & 1RY456 CLOSED

PORV isol valves - 1RY8000A & 1RY8000B BOTH ENERGIZED

PORV relief path - Both PORVs in AUTO, Both isolation valves - OPEN.

Normal PZR Spray Valves CLOSED RO

Maintain RCS temperature control at 1PM05J:

Check RCPs - NONE RUNNING.

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

MSIVs closed.

RO

Check status of RCPs at 1PM05J:

o All RCPs - NONE RUNNING.

o Any RCPs still running - TRIP All RCPs BOP/

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

RO

Check pressure in all SGs:

None dropping in an uncontrolled manner.

None completely depressurized.

BOP/

Check S/G tubes are intact at RM-11 console:

RO

1PR08J SG Blowdown.

1PR27J SJAE/GS.

1AR22/23A-D Main steam Lines.

Comments:

Braidwood NRC 09-1 Page 14

Scenario NRC 09-1 Event 6&7 No: No.

Event Large break RCS LOCA/1A RH pump trip

==

Description:==

Time Position Applicants Actions or Behavior CREW

Determine RCS in NOT intact:

o CNMT area rad monitors > alert alarm setpoint at RM-11 console.

o CNMT pressure > 3.4 psig (1PI-CS 934-937) at 1PM06J.

o CNMT floor drain sump level > 46 inches (1LI-PC002/003) at 1PM06J.

CREW Transition to 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT 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:

Examiners note: When RWST level reaches the low-2 setpoint, the crew will transition to 1BwEP ES-1.3 to align ECCS for cold leg recirc. 1BwEP ES-1.3 actions begin on page 18.

Comments:

Braidwood NRC 09-1 Page 15

Scenario NRC 09-1 Event 8 No: No.

Event 1SI8811B fail to auto open.

==

Description:==

Time Position Applicants Actions or Behavior RO

Check Status of RCPs:

RCPs - NONE RUNNING RO/ BOP

Check if SG secondary pressure boundaries are intact:

Check pressure in all SGs:

None dropping in an uncontrolled manner

None completely depressurized

Check intact SG levels

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

SG NR levels - NOT rising in an uncontrolled manner

Check secondary radiation normal.

Reset Phase A

Depress BOTH Phase A Reset Pushbuttons at 1PM06J

OPEN 1SD005A-D at 1PM11J

At RM-11 or HMI Check secondary rad trends on :

1PR08J SG Blowdown

1PR27J SJAE/GS

1AR22/23A-D Main steam lines RO

Check at least ONE PZR PORV relief path available:

PORV isol valves - BOTH ENERGIZED

PORV relief path - BOTH PORVs in AUTO, 1RY8000A & B - OPEN CREW

Check if ECCS flow should be reduced

RCS subcooling - NOT acceptable

Check if CS should be stopped

Both CS pumps - RUNNING

Reset CS

Spray add tank lo-2 level light - NOT LIT

CS termination requirements

CNMT pressure < 15 psig

Spray operating time < 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

Check if RH pumps should be stopped

Reset SI

Depress BOTH SI Reset Pushbuttons at 1PM06J

Verify SI ACTUATED BP light NOT lit at 1PM05J

Verify AUTO SI BLOCKED BP light NOT lit at 1PM05J

RCS pressure < 325 psig - go to 1BwEP-1, step 9.

CUE

Annunciator RWST LEVEL LO-2 (1-6-B7)

RWST level <46%.

Comments:

Braidwood NRC 09-1 Page 16

Scenario NRC 09-1 Event 8 No: No.

Event 1SI8811B fail to auto open.

==

Description:==

Time Position Applicants Actions or Behavior CREW Transition to 1BwEP ES-1.3, TRANSFER TO COLD LEG RECIRCULATION US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions

Request STA monitor status trees - BwFRs should not be implemented during steps 1 thru 6 of 1BwEP ES-1.3

Enter/Implement 1BwEP ES-1.3 and direct operator actions of 1BwEP ES-1.3 to establish the following conditions:

RO/ BOP

Establish CC flow to RH HXs

1CC9473A & B - OPEN

CC pumps - TWO RUNNING

Open 1CC9412A & B

CC to RH HX flows - 1FI-0689 & 1FI-0688 > 5000 gpm

Check CNMT floor level - 1LI-PC006 & 1LI-PC007 > 8 inches (13 inches)

Align RH pumps suction to CNMT sumps

Place SVAG valve C/Ss to close

Check RH pumps

1B RH pump - RUNNING

1A RH pump tripped (PTL)

Check CNMT sump isolation valves

1SI8811A - OPEN

1SI8811B - CLOSED - go to attachment A, step 1.

CREW Note: If RWST level drops < 9% during manual realignment of ECCS pumps to containment sump, any pump taking suction from RWST should be stopped, unless a suction flowpath also exists from the containment sump.

Comments:

Braidwood NRC 09-1 Page 17

Scenario NRC 09-1 Event 8 No: No.

Event 1SI8811B fail to auto open

==

Description:==

Time Position Applicants Actions or Behavior BOP/ RO

Check if 1A RH pump needs to be aligned to CNMT sump

1SI8811A - OPEN

CLOSE 1SI8812A

Check if 1B RH pump needs to be aligned to CNMT sump

1SI8811B - CLOSED

[CT]

Check train B recirc flowpath from CNMT sump available ES-1.3--

1B RH pump - RUNNING A

1SI8811B - energized

Manually align 1B RH Pump suction to the containment sump.

Place 1B RH pump in PULL OUT

Close 1SI8812B

Place 1B CS pump in PULL OUT

Close 1CS001B

Open 1SI8811B

Start 1B RH pump

Open 1CS001B

Restart 1B CS pump (manually actuate CS/Phase B)

Check at least one CNMT sump recirc flowpath established

1B RH pump - RUNNING

1SI8811B - OPEN

Return to 1BwEP ES-1.3, step 3.d Note: At this point the scenario may be terminated (Final)

Comments:

Braidwood NRC 09-1 Page 18

Simulation Facility Braidwood Scenario Operating Test No.: 2009-1 No.:

NRC 09-2 Examiners: ______________________ Applicant: _____________________ SRO

______________________ _____________________ RO

______________________ _____________________ BOP Initial Conditions: IC-18 Turnover: Unit 1 is at 75% power, steady state, equilibrium xenon, MOL. Online risk is green. 1B Heater Drain Pump is OOS for motor replacement for the past 3 days. Expected back in service in 7 days. 1CV8149C was returned to service last shift following maintenance to replace its fuse block. Following completion of turnover, the shift manager requests the BOP swap 75 gpm letdown orifices from 1CV8149B to 1CV8149C per BwOP CV-9 for an upcoming clearance order on 1CV8149B to replace its fuse block while the RO monitors reactor power.

Event Malf. No. Event Event No. Type* Description IOR ZDI1HD01PB PTL 1B HD pump OOS IMF CV32B 1B CV pump auto start failure TRGSET 1 1A CV pump trip ZLO1SI01PA(3) = = 1 IMF CV01A (1 0)

TRGSET 2 1B SGTR when SG pressure drops to 600 PSIG ZAO1PI524A < 0.46 IMF TH03B (2 10) 600 60 1 None N-BOP, US Swap Letdown orifices 2 IMF PB2411 ON TS-US SG PORV 1MS018B inoperable IMF PB2412 ON IOR ZDI1MS018B CLS 3 IMF TH10B 100 15 C-RO, US 1RY455C spray valve fails open in auto (Potential)

TS-US 4 IMF RX10A 0 15 I-RO, US Turbine Impulse Pressure channel 1PT-505 failed low TS-US 5 IMF FW35A C-BOP, US 1A Heater Drain Pump trip requiring turbine runback R-RO, US 6 IMF MS03B 100 0 M-ALL 1B SG safety valves stuck open after turbine runback IMF MS03F 100 0 IMF MS03J 100 0 7 Preload C-RO 1A CV pump trips/1B CV pump fails to auto start 8 Preload M-ALL 1B SGTR (600 gpm) (faulted and ruptured)

(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 Heater Drain Pump is OOS for motor replacement for the past 3 days. Expected back in service in 7 days. 1CV8149C was returned to service last shift following maintenance to replace its fuse block. Following completion of turnover, the shift manager requests the BOP swap 75 gpm letdown orifices from 1CV8149B to 1CV8149C per BwOP CV-9 for an upcoming clearance order on 1CV8149B to replace its fuse block while the RO monitors reactor power.

After completing shift turnover and relief, the crew will swap letdown orifices. The BOP will manually lower letdown pressure, remove 1CV8149B from operation and place 1CV8149C on-line. The BOP will then restore letdown line pressure and restore letdown to automatic operation After completing the letdown orifice swap, Steam Generator 1B atmospheric relief valve 1MS018B, will develop a hydraulic leak. The Unit Supervisor will enter Tech Spec 3.7.4, Condition A and Tech Spec 3.6.3, Condition C. The crew will dispatch an operator to close 1MS019B to comply with TS 3.6.3, condition C.

1MS018B will remain unavailable for the remainder of the scenario.

After the 1MS018B failure has been addressed, 1PK-455C Pressurizer Spray Valve controller will fail to full demand position. 1RY455C will fail full open and pressurizer pressure will drop. The RO will take manual control of 1PK-455C and lower demand to close the pressurizer spray valve. TS 3.4.1 may be applicable if pressurizer pressure drops below 2209 psig.

After the 1PK-455C failure has been addressed, First Stage Turbine Impulse Pressure channel 1PT-505 will fail low. The RO 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 RO will return rod control to automatic after verifying Tave and Tref are within 1°F.

After the 1PT-505 failure has been 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 RO will borate the RCS as necessary to stabilize RCS temperature.

After the 1A HD pump trip has been addressed, the secondary pressure transient causes three safety valves on the 1B SG to stick open, causing a faulted SG. SG pressures will drop and a manual reactor trip will be required. The crew will implement 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION. When safety injection is actuated, the 1A CV pump will trip. The 1B CV pump must be manually started to establish high head ECCS flow. After determining 1B SG secondary pressure boundary is not intact the crew will transition to 1BwEP-2, FAULTED STEAM GENERATOR ISOLATION. When 1B SG pressure drops to 600 psig, a 600 gpm SGTR will occur on the 1B SG, causing a faulted/ruptured SG. The crew will complete isolation of 1B SG and transition to 1BwEP-3, STEAM GENERATOR TUBE RUPTURE, based on secondary radiation trends on the 1B SG. In addition, the crew will recognize 1B SG pressure does not drop to zero and lowering pressurizer level/pressure will indicate a SGTR (alternate indications). After determining ruptured SG pressure is less than 320 psig the crew will transition 1BwCA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.

Completion criteria is completion of step 6 of 1BwCA-3.1.

Braidwood NRC 09-2 Page 2

Critical Tasks

1. Manually start the 1B CV pump prior to completion step 6 of 1BwEP-0.

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

2. Isolate 1B Steam Generator prior to completing step 4 of 1BwEP-2.

(ERG Critical Task number - E-2--A) (K/A number - 000040AA1.10 importance - 4.1/4.1)

Braidwood NRC 09-2 Page 3

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).

Place 1B HD pump in PTL.

Run caep NRC 09-2 SETUP from disk and verify the following actuate:

IOR ZDI1HD01PB PTL

IMF CV32B

TRGSET 1 ZLO1SI01PA(3) = = 1

IMF CV01A (1 0)

TRGSET 2 ZAO1PI524A < 0.46

IMF TH03B (2 10) 600 60

Place info tag on 1B HD pump and INFO tag on 1HD075B.

Verify/Set I Target Curve slopes to +2% of I.

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

Braidwood NRC 09-2 Page 4

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Swap Letdown orifices As SM, acknowledge the completion of letdown orifice swap.

Event 2: SG PORV 1MS018B inoperable (Tech Spec)

Run caep NRC 09-2 EVENT 2 from disk and verify the following actuate:

IMF PB2411 ON

IMF PB2412 ON

IOR ZDI1MS018B CLS As SM acknowledge the failure, LCO 3.6.3, condition C and LCO 3.7.4, condition A, and requests for on line risk assessment, maintenance support, and IR initiation.

If dispatched as EO, report 1MS018B has a broken hydraulic line and a small puddle of hydraulic fluid is present beneath the valve.

As WEC supervisor, acknowledge request for EST for 1MS018B C/S, if EST is requested.

If dispatched as EO to close 1MS019B, perform the following:

IRF MS52 0 Event 3: 1PK-455C Pressurizer Spray Valve Controller failure.

Insert IMF TH10B 100 15 As SM, acknowledge the failure, LCO 3.4.1 condition A entry and exit (if applicable), and requests for, maintenance support, and IR initiation.

Braidwood NRC 09-2 Page 5

INSTRUCTOR/SIMULATOR RUN AID GUIDE 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 (GREEN), 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.

Event 5: 1A Heater Drain Pump trip ENSURE ROD CONTROL IS RETURNED TO AUTOMATIC PRIOR TO INSERTING THE NEXT MALFUNCTION.

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

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.

Braidwood NRC 09-2 Page 6

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 6: 1B SG Safety valves stuck open after runback WHEN THE LEAD EVALUATOR IS SATISFIED AFTER THE HD PUMP TRIP AND TURBINE RUNBACK:

Run caep NRC 09-2 EVENT 5 from disk and verify the following actuate:

IMF MS03B 100 0 IMF MS03F 100 0 IMF MS03J 100 0 After faulted SG is diagnosed by crew, report as security, steam flow from 1B/1C MSIV room safety valve tailpipes.

Acknowledge as SM procedure changes, E Plan evaluations, and STA request.

Event 7: 1A CV pump trips/1B CV pump fails to auto start (preload)

If dispatched as EO to investigate 1A CV pump, report ground overcurrent flag at breaker cubicle.

Event 8: Faulted ruptured 1B SG (preload)

Acknowledge as SM procedure changes, E Plan evaluations, and STA request.

After STA requested, as STA report CSF status.

Braidwood NRC 09-2 Page 7

Scenario NRC 09-2 Event 1 No: No.

Event Swap Letdown orifices

==

Description:==

Time Position Applicants Actions or Behavior CUE

Shift manager requests swapping letdown orifices from 1B to 1C (from turnover).

US

Directs RO to swap letdown orifices from 1B to 1C per BwOP CV-9 BOP

Refers to BwOP CV-9

Determine BwOP CV-9, step F.3 to be performed

Lower letdown pressure

Place 1PK-131, LTDWN Line Press Cont Vlv 1CV131, to MANUAL

Raise demand on 1PK-131, LTDWN Line Press Cont Vlv 1CV131, to lower letdown pressure to ~ 200 psig (1PI-131)

Remove 1B letdown orifice from operation

Close 1CV8149B

Align 1C letdown orifice

Open 1CV8149C

Restore letdown pressure to 370 psig

Lower demand on 1PK-131, LTDWN Line Press Cont Vlv 1CV131

Restore letdown pressure WITHOUT causing the following annunciators:

LTDWN HX OUTLT PRESSURE HIGH (1-8-B5)

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

Restore automatic letdown pressure control

Verify letdown pressure stable at ~370 psig (1PI-131)

Place 1PK-131, LTDWN Line Press Cont Vlv 1CV131, to AUTO

Verify letdown temperature 90°F - 115°F (1TI-130)

Verify PZR level is being maintained at the program value

Inform US letdown orifices swapped US

Acknowledge report

Notify SM letdown orifices swapped from 1B to 1C NOTE: After the actions for swapping letdown orifices are complete and with lead examiner concurrence, enter next event Comments:

Braidwood NRC 09-2 Page 8

Scenario NRC 09-2 Event 2 No: No.

Event SG PORV 1MS018B inoperable

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator S/G 1B PORV TROUBLE (1-15-B10).

SER 2411, 1B PORV HYDRAULIC FLUID RESERVOIR LOW.

SER 2412, S/G PORV 1B ACCUMULATOR PRESSURE LOW.

BOP

Identify/report trouble alarm on 1MS018B

Refer to BwAR 1-15-B10

Dispatch operator to 1MS018B o Place 1MS018B C/S in close to stop hydraulic pump o Request Equipment Status Tag for 1MS018B C/S & 1MS019B hand wheel.

RO o Assist US & BOP o Refer to BwAR o Dispatch operators o Refer to Tech Specs o Inform SM of 1MS018B failure US

Identify entry conditions for TS 3.7.4, condition A.

Identify entry conditions for TS 3.6.3, condition C o Direct operator to close 1MS019B.

US o Inform SM of 1MS018B status, TS Status, request IR, On Line Risk Assessment, maintenance support, and clearance order/EST for 1MS019B.

NOTE: After the actions for 1MS018B failure are complete and with lead examiner concurrence, enter next event Comments:

Braidwood NRC 09-2 Page 9

Scenario NRC 09-2 Event 3 No: No.

Event 1PK-455C failure

==

Description:==

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

1RY455C position lights indicating full open.

Pressurizer Pressure dropping.

Master Pressurizer Pressure Controller demand dropping.

RO

Identify condition/report alarm on 1PM05J

Place 1PK-455C in manual and lower demand to close 1RY455C BOP o Assist US & RO o Refer to BwAR o Refer to Tech Specs o Inform SM of 1PK-455C failure US o Identify entry conditions for TS 3.4.1, condition A.

o Identify exit conditions for TS 3.4.1, condition A o Direct operator to close 1RY455C.

US o Inform SM of 1PK-455C failure, TS Status, request IR, On Line Risk Assessment and maintenance support.

NOTE: After the actions for 1PK-455C failure are complete and with lead examiner concurrence, enter next event Comments:

Braidwood NRC 09-2 Page 10

Scenario NRC 09-2 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 RO/

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.

RO/

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%

RO/

Defeat 1PT-505 BOP

Place 1PS505Z, Turbine Impulse Pressure Defeat Switch, to DEFEAT P-505 Comments:

Braidwood NRC 09-2 Page 11

Scenario NRC 09-2 Event 4 No: No.

Event Turbine Impulse Pressure Channel 1PT-505 failed low

==

Description:==

Time Position Applicants Actions or Behavior US/RO

Check if rod control can be placed in auto o C5 NOT lit o Tave/Tref stable and within 1°F.

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 RO/

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:

Braidwood NRC 09-2 Page 12

Scenario NRC 09-2 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 Comments:

Braidwood NRC 09-2 Page 13

Scenario NRC 09-2 Event 5 No: No.

Event 1A Heater Drain Pump trip

==

Description:==

Time Position Applicants Actions or Behavior 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

Deactivate turbine runback.

US/RO

Check PDMS operable

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

1BwOS PDMS-1A not implemented

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

RO

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 Comments:

Braidwood NRC 09-2 Page 14

Scenario NRC 09-2 Event 5 No: No.

Event 1A Heater Drain Pump trip

==

Description:==

Time Position Applicants Actions or Behavior RO

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

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)

Comments:

Braidwood NRC 09-2 Page 15

Scenario NRC 09-2 Event 5 No: No.

Event 1A Heater Drain Pump trip

==

Description:==

Time Position Applicants Actions or Behavior 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 (SG 1B safety valves fail open) is 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:

Braidwood NRC 09-2 Page 16

Scenario NRC 09-2 Event 6&7 No: No.

Event 1B SG safety valves fail open, 1A CV pump trips/1B CV pump fails to auto start

==

Description:==

Time Position Applicants Actions or Behavior CUE o Annunciator S/G 1B FLOW MISMATCH FW FLOW LOW (1-15-B4) o NI power rising o PZR pressure lowering o Turbine MW output lowering CREW

Recognize indications of Faulted SG o Dispatch operators to look for steam leak o If report is receives that 1B SG safeties are open, recognize that SG pressure is below safeties lift setpoints and initiate reactor trip.

RO

Initiate a manual reactor trip and transition to 1BwEP-0

Initiate a manual SI 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 Comments:

Braidwood NRC 09-2 Page 17

Scenario NRC 09-2 Event 6&7 No: No.

Event 1B SG safety valves fail open, 1A CV pump trips/1B CV pump fails to auto start

==

Description:==

Time Position Applicants Actions or Behavior RO 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 governor valves - CLOSED BOP Perform immediate operator actions of 1BwEP-0:

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:

SG pressure cannot be maintained > 640 psig

Manually actuate SI from 1PM05J and 1PM06J CREW

Check SI Status o SI First OUT annunciator - LIT o SI ACTUATED Permissive Light - LIT o SI Equipment - AUTOMATICALLY ACTUATED o Either SI pumps - RUNNING o Either CV pump to cold leg isolation valve OPEN - 1SI8801A/B CREW o May choose to isolate 1B SG immediately due to safety considerations.

o Isolate FW to 1B SG.

o Actuate Main Steam Isolation.

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:

BOP

Verify FW isolated at 1PM04J:

FW pumps - TRIPPED.

Isolation monitor lights - LIT.

Comments:

Braidwood NRC 09-2 Page 18

Scenario NRC 09-2 Event 6&7 No: No.

Event 1B SG safety valves fail open, 1A CV pump trips/1B CV pump fails to auto start

==

Description:==

Time Position Applicants Actions or Behavior

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

0VA023Y - OPEN

0VA436Y - CLOSED

Plenum C:

0VA03CF RUNNING

0VA072Y - OPEN

0VA438Y - CLOSED Comments:

Braidwood NRC 09-2 Page 19

Scenario NRC 09-2 Event 6&7 No: No.

Event 1B SG safety valves fail open, 1A CV pump trips/1B CV pump fails to auto start

==

Description:==

Time Position Applicants Actions or Behavior

Verify FHB ventilation aligned at 0PM02J:

0VA04CB - RUNNING

0VA055Y - OPEN

0VA062Y - OPEN

0VA435Y - CLOSED

Notify US Attachment B complete RO/

Verify ECCS pumps running BOP

CV pumps - NONE RUNNING

[CT]

Manually start the 1B CV pump prior to completion step 6 of 1BwEP-0.

E-0--I

Both RH pumps - RUNNING

Both SI pumps - RUNNING RO/

Verify RCFCs running in Accident Mode BOP

Group 2 RCFC Accident Mode lights - LIT

Verify Phase A isolation

Group 3 Cnmt Isol monitor lights - LIT

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 - BOTH RUNNING

Verify SX pumps - BOTH RUNNING RO/

Check Main Steamline Isolation not required BOP

Check pressures o SG pressures > 640 psig - continue on in 1BwEP-0 o SG pressures < 640 psig - verify MSIVs and MSIV bypass valves closed

CNMT pressure < 8.2 psig RO/

Check CS not required BOP

CNMT pressure remained < 20 psig Comments:

Braidwood NRC 09-2 Page 20

Scenario NRC 09-2 Event 6&8 No: No.

Event 1B SGTR (600 gpm), Faulted ruptured 1B SG

==

Description:==

Time Position Applicants Actions or Behavior RO/

Verify Total AF flow:

BOP

AF flow > 500 gpm

SG levels maintained between 10% and 50%

Check status of S/G NR levels

S/G level not rising in an uncontrolled manner RO/

Verify ECCS valve alignment BOP

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

Verify ECCS flow

High Head SI flow >100 gpm (1FI-917) o RCS pressure < 1700 psig o SI pump discharge flow > 200 gpm o RCS pressure > 325 psig RO

Check PZR PORVs and SPRAYs:

PORV isolation valves - ENERGIZED

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

Normal PZR Spray valves - CLOSED RO

Maintain RCS temperature control

Check RCPs - RUNNING

Verify RCS average temperature stable at or trending to 557oF o Throttle AF flow o Isolate AF flow to 1B SG RO

Check status of RCPs

All RCPs - RUNNING

Check RCP trip criteria o RCS pressure > 1425 psig - continue on in 1BwEP-0 o RCS pressure < 1425 psig

Verify high head injection flow (1FI-917) > 100 gpm

Trip all RCPs BOP/ RO

Check if SG secondary pressure boundaries are intact:

Check pressure in all SGs:

1B SG pressure dropping in an uncontrolled manner Comments:

Braidwood NRC 09-2 Page 21

Scenario NRC 09-2 Event 6&8 No: No.

Event 1B SGTR (600 gpm), Faulted ruptured 1B SG

==

Description:==

Time Position Applicants Actions or Behavior CREW

Transition to 1BwEP-2, FAULTED STEAM GENERATOR ISOLATION 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 and direct operator actions of 1BwEP-2 to establish the following conditions BOP

Check MS isolation

All MSIVs and bypass valves - CLOSED BOP

Check if any SG secondary pressure boundary is intact

1A, 1C, & 1D SG pressures stable CREW

Identify faulted SG

1B SG pressure decreasing in an uncontrolled manner

1B SG indicates steam flow with MSIVs and MSIV bypass valve closed RO/ BOP

Isolate 1B Steam Generator prior to completing step 4 of 1BwEP-2.

[CT]

Verify/Close 1AF013B & F - may have already be closed at step 15 of 1BwEP-0 E-2--A

1B row of FW isolation monitor lights - lit

1MS018B closed

1SD002E & F closed

1SD005C closed BOP

Check Annunciator AF PUMP SX SUCTION VLVS ARMED (1-3-E7) - NOT LIT CREW

Check Secondary Radiation

Depress Phase A Reset Pushbuttons at 1PM06J

OPEN 1SD005A-D at 1PM11J

Request Chemistry sample SG for activity (US)

Check 1AR22/23B 1B Main Steam Line on HMI or RM-11 CREW Transition to 1BwEP-3, STEAM GENERATOR TUBE RUPTURE Comments:

Braidwood NRC 09-2 Page 22

Scenario NRC 09-2 Event 6&8 No: No.

Event Faulted ruptured 1B SG

==

Description:==

Time Position Applicants Actions or Behavior US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions o Request STA evaluation of status trees

Enter/Implement 1BwEP-3 and direct operator actions of 1BwEP-3 to establish the following conditions RO

Check Status of RCPs:

RCPs - NONE running - should have been tripped earlier when RCP trip criteria met BOP

Identify ruptured SG 1B 1B Main steam line rad monitor ABNORMAL for plant conditions

Isolate ruptured SG

1MS018B inoperable due to hydraulic leak o Confer with SM about continuing procedure with 1MS018B NOT in auto

Verify 1SD002E & F CLOSED

Verify MSIVs and MSIV bypass valves for 1B SG CLOSED

Check PORVs on intact (1A, 1C, & 1D) SGs available for RCS cool down

Check ruptured SG level - Narrow Range < 10%

Do not feed 1B SG per caution prior to step o Verify/close 1AF013B & F - should have already be closed in 1BwEP-0 OR 1BwEP-2 CREW

Determine ruptured SG pressure < 320 psig Transition to 1BwCA-3.1, SGTR WITH LOSS OF REACTOR COOLANT, - SUBCOOLED RECOVERY DESIRED US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions o Request STA evaluation of status trees

Enter/Implement 1BwCA-3.1 and direct operator actions of 1BwCA-3.1 to establish the following conditions Comments:

Braidwood NRC 09-2 Page 23

Scenario NRC 09-2 Event 6&8 No: No.

Event Faulted ruptured 1B SG

==

Description:==

Time Position Applicants Actions or Behavior RO/BOP

Reset SI

Depress both SI reset pushbuttons

Verify SI actuated permissive light - NOT LIT

Verify auto SI blocked permissive light - LIT

Reset CNMT isolation

Reset phase A isolation

Check SAC - one running

Open 1IA065 and 1IA066

Verify all AC buses energized by offsite power

All 4 KV ESF buses energized

All 4KV non-ESF buses energized

All 6.9 KV buses energized

De-energize PZR Heaters

Place all B/U heaters contactors to OFF

Place variable heaters in NAT o Consult with SM (TSC) for recommended minimum Prz level.

Check if CS should be stopped

CS pumps - NONE running

Check ruptured SG level

1B SG NR level < 10% - do not feed 1B SG per caution prior to step

Check if RH pumps should be stopped

1SI8812A & B open (aligned to RWST)

RCS pressure > 325 psig and stable

Stop both RH pumps and place in standby Note: At this point the scenario may be terminated Final Comments:

Braidwood NRC 09-2 Page 24

Simulation Facility Braidwood Scenario Operating Test No.:2009-1 No.:

NRC 09-3 Examiners: ______________________ Applicant: _____________________ SRO

______________________ _____________________ RO

______________________ _____________________ BOP Initial Conditions: IC-21 Turnover: The unit is operating at 100% power, steady state, equilibrium xenon, Boron concentration is 800 ppm. U-0 Boric Acid Transfer pump is OOS. Rods are in manual due to rod control summing amplifier malfunction last shift. 1B HD pump has been OOS for the last 3 days for breaker refurbishment. Expected back in 6 days. Online risk is yellow.

Event Malf. No. Event Event No. Type* Description Preload IMF RP14A SI auto actuation failure (Train A)

IMF RP14B SI auto actuation failure (Train B)

IMF MS01A 100 MSIV fail to close IMF MS01B 100 MSIV fail to close IMF MS01C 100 MSIV fail to close IMF MS01D 100 MSIV fail to close IMF CS01B 1B CS pp failure MRF RP37 OUT K643 CS Trn A actuation relay failure TRGSET 1 ZDISIA1 = = 1 TRG 1 DMF RP14A TRGSET 2 ZDISIA1 = = 1 TRG 2 DMF RP14B TRGSET 3 ZDISIA2 = = 1 TRG 3 DMF RP14A TRGSET 4 ZDISIA2 = = 1 TRG 4 DMF RP14B IOR ZDI1HD01PB PTL 1B HD pp OOS IMF RX17 3.5 Rod control failure 1 IMF RX01J 0 300 I-BOP, US 1D SG steam pressure channel fails low TS-US 2 IMF CV10 0 30 I-RO, US 1CV121 controller failure 3 IMF TH08 0.01 R-RO, US High RCS activity requiring plant shutdown TS-US 4 IMF CV03 C-RO, US Boric acid transfer pump trip 5 MS07C 4 0 M-ALL Uncontrolled depressurization of all SGs 6 Preload C-RO, US Failure of SI to automatically actuate 7 Preload C-BOP, Failure of both trains of CS to automatically US actuate 8 DMF MS01D C-ALL 1D MSIV closes (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient

SCENARIO OVERVIEW The unit is operating at 100% power, steady state, equilibrium xenon, Boron concentration is 800 ppm.

Online risk is yellow. 1B HD pump has been OOS for the last 3 days for seal replacement. Expected back in 6 days. Rods are in manual due to rod control summing amplifier malfunction last shift.

About 2 minutes into the scenario, 1D SG steam pressure channel, 1PT-544, fails low. The crew should take actions to stabilize the plant per 1BwOA INST-2. Technical Specifications 3.3.2 and 3.3.4 apply.

After the 1D SG steam pressure failure has been addressed, 1CV121 Charging pump flow control valve controller 1FK-121 will fail to 0% demand. The 1CV121 valve will full close and pressurizer level will drop.

The crew will take actions to stabilize the plant by taking manual control of the 1FK-121.

After the 1FK-121 failure has been addressed, a fuel element failure will be indicated by the VCT Cubicle and Gross Failed Fuel radiation monitors. The crew will implement 1BwOA PRI-4 and take actions accordingly. Technical Specification 3.4.16 applies. Technical Specification 3.4.15 applies if 1PR11J reaches the high alarm limit and isolates. A unit shutdown will be required. The crew should commence a power reduction.

During a boric acid addition, the Unit 1 Boric Acid pump motor bearing will seize while the pump is running. MCC 133X3, cubicle A4 will open, causing a trip of the Unit 1 Boric Acid Transfer Pump. The crew will stop the load reduction. The U-0 Boric Acid Transfer pump is OOS, and the crew will need to re-commence the ramp using rods only.

After a measurable change in power, a large fault will occur on the 1C MS line. While performing the actions of 1BwEP-0, the crew should note the failure of SI to automatically actuate. The crew should manually actuate SI. When containment pressure reaches 20 psig, Phase B actuates but the CS pumps do not start. The crew should manually realign 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. Entry into 1BwFR-H.1 will be required when the crew throttles AF flow to 45 gpm per SG, however, note in 1BwFR-H.1 directs the procedure not to be performed. The crew will continue in 1BwCA-2.1 until SI termination when the 1D MSIV will close and the crew will transition to 1BwEP-2. The crew will then isolate AF to the 1A, B & C SGs. Entry into 1BwFR-P.1 may be required as directed by the status trees.

Completion criteria is completion of 1BwEP-2.

Critical Tasks

1. Manually actuate Safety Injection prior to transition to 1BwEP-2 or past step 7.a of 1BwEP ES-0.1.

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

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 control AF flowrate to 45 gpm for each SG before orange path for integrity occurs.

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

Braidwood NRC 09-3 Page 2

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 Safety System Status Yellow placard on 1PM05J

Place 1B HD pump in PTL and place info tag on 1B HD pump C/S.

Place rod control to Manual

Run caep DEMO NRC 09-3 SETUP from disk and verify the following actuate:

IMF RP14A

IMF RP14B

IMF MS01A 100

IMF MS01B 100

IMF MS01C 100

IMF MS01D 100

IMF CS01B

MRF RP37 OUT

TRGSET 1 ZDISIA1 = = 1

TRG 1 DMF RP14A

TRGSET 2 ZDISIA1 = = 1

TRG 2 DMF RP14B

TRGSET 3 ZDISIA2 = = 1

TRG 3 DMF RP14A

TRGSET 4 ZDISIA2 = = 1

TRG 4 DMF RP14B

IOR ZDI1HD01PB PTL

IMF RX17 3.5

Verify/Set I Target Curve slopes to +2% of I.

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

Braidwood NRC 09-3 Page 3

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: 1D SG steam pressure channel fails low Insert IMF RX01J 0 300 As SM acknowledge 1PT-544 failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.

As SM, if requested support for tripping bistables, report that bistables are not to be tripped until work analyst and NSO support can be obtained (i.e. not at this time) and that the abnormal operating procedure should be continued. Bistable tripping will be conducted later.

Event 2: 1FK121 Controller failure Insert IMF CV10 0 30 If dispatched as EO to investigate, wait two minutes and report no visible damage to 1CV121 Valve. Valve appears to be failed closed 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.

Event 3: High RCS activity requiring plant shutdown Insert IMF TH08 0.01 As SM acknowledge high RCS activity, procedure entry, EAL review, TS entry, request for nuclear engineer, and shutdown required.

As Chemistry, acknowledge RCS sample request. 5 minutes after request to sample, give the following results: This may need to be revised per TS amendment to LCO 3.4.16 if it is in effect.

E(bar) = 1.7, DE I-131 = 50 µCi/gm, Gross Activity = 75 µCi/gm. Mixed bed decon factor is 65.

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

Acknowledge as Electric Ops initiation of ramp.

Braidwood NRC 09-3 Page 4

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 4: Boric acid transfer pump trip Note: Ensure a boration is in progress prior to inserting the next malfunction.

Insert IMF CV03 If dispatched as EO, report Unit 1 AB pump breaker at MCC 133X3 is tripped and does not appear to be damaged. If breaker re-closure is requested, report breaker is closed. DO NOT DELETE MALFUNCTION. If pump restart is attempted, report the breaker is open.

If dispatched as EO, report the Unit 1 AB pump bearing is hot and appears to be damaged.

If asked as SM about availability of U-0 boric acid transfer pump, report that the return to service will be expedited, however it may take several hours. Insist that the unit continue to ramp on rods only, until an AB transfer pump becomes available.

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

Event 5: Uncontrolled depressurization of all SGs/Auto SI, and CS failures Insert IMF MS07C 4 0 Acknowledge as SM procedure changes, E Plan evaluations, and STA request.

After STA requested, as STA report CSF status: Red on heat sink when AF throttled to 45 gpm per SG, orange on integrity if RCS temperature < 240°F.

If dispatched as EO to investigate 1B CS pump, report ground overcurrent flag at breaker cubicle.

PERFORM THE FOLLOWING IMMEDIATELY AFTER AF IS THROTTLED TO 45 GPM PER SG Event 8: 1D MSIV closes

DMF MS01D Acknowledge as SM procedure changes, E Plan evaluations, and STA request.

Braidwood NRC 09-3 Page 5

Scenario NRC 09-3 Event 1 No: No.

Event 1D SG steam pressure channel fails low

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator MS PRESS RATE STM LINE ISOL ALERT (1-15-E1)

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

Annunciator S/G 1D FLOW MISMATCH STM FLOW LOW (1-15-D3) o Annunciator S/G 1D LEVEL DEVIATION (1-15-D9)

S/G 1D feed flow and NR level lowering BOP

Determine SG 1D feed flow and/or NR level lowering

Identify 1PI-544 indicates low steam pressure o Reference BwARs 1-15-D1/1-15-D3 as time permits CREW

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

Implement 1BwOA INST-2 "OPERATION WITH A FAILED INSTRUMENT CHANNEL",

Attachment F "STEAM PRESSURE CHANNEL FAILURE" and direct operator action o Notify SM of SG pressure channel failure o Notify SM to evaluate for Emergency Plan.

BOP

Stabilize 1D SG level at 1PM04J:

Place 1FK-540, FW Reg Valve 1FW540 controller, in manual.

Raise demand on 1FK-540 sufficiently to raise feedwater flow to restore 1D SG level.

Operate 1FK-540 in manual to stabilize 1D SG level in the normal operating band.

Verify 1PI-509 indicates approximately 215 psid to ensure adequate feedwater P.

o Manually control FW pump speed to restore P, if necessary.

Select operable steam flow channel.

Place 1D SG steam flow channel select C/S to F-543.

Establish automatic level control by placing 1FK-540 in auto.

Comments:

Braidwood NRC 09-3 Page 6

Scenario NRC 09-3 Event 1 No: No.

Event 1D SG pressure channel failed low

==

Description:==

Time Position Applicants Actions or Behavior RO/BOP

Perform the following:

Monitor reactor power at 1PM05J.

Reduce turbine load by initiating 5 MW ramp at OWS 211 or 210.

Assist US by making notifications.

o Refer to BwARs as time permits.

Note: The reactor may exceed 100% power during the secondary transient. The crew may choose to enter 1BwOA PRI-16 to lower reactor power. Steps for 1BwOA PRI-16 are in italics below.

US

Determines TS 3.3.2 conditions A and D are applicable.

Determines TS 3.3.4 condition A is applicable. (May determine Tech Spec applicability by referring to 1BwOSR 3.3.4.1, UNIT ONE REMOTE SHUTDOWN INSTRUMENTATION MONTHLY CHANNEL CHECKS)

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

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

CREW

Identify entry conditions for 1BwOA PRI-16, RESPONSE TO OVERPOWER CONDITION US

Implement 1BwOA PRI-16, RESPONSE TO OVERPOWER CONDITION and direct operator action.

Notify SM of procedure entry.

RO/BOP

Check Reactor trip setpoints not exceeded

PR NIs < 109%

DT < OTDT and OPDT setpoints RO/BOP

Check Reactor Power <100%

PR NIs

10 min. Calorimetric computer point RO/BOP o Reduce turbine load by initiating ramp at OWS 211 or 210.

US

Contact SM to perform risk assessment, initiate IR, and contact appropriate personel.

Comments:

Braidwood NRC 09-3 Page 7

Scenario NRC 09-3 Event 2 No: No.

Event 1CV121 controller fails low in auto

==

Description:==

Time Position Applicants Actions or Behavior CUE

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

Annunciator 1-9-A1, REGEN HX LTDWN TEMP HIGH

1FK-121 controller output failed low.

1FI-121A Charging Flow Indication dropping.

Pzr level indicators 1LI459A/460A/461 indicate lowering level.

RO/

Perform the following at 1PM05J:

BOP

Determine loss of charging flow.

Identify 1FK-121 is failing low.

Report failure to US.

CREW o Reference BwARs o Isolate Letdown per BwAR direction. (the crew may elect to do this)

Recognize 1FK-121 output failed low.

o Dispatch operator to investigate cause of failure.

Note: The crew may elect to enter 1BwOA PRI-15, LOSS OF NORMAL CHARGING.

Actions for 1BwOA PRI-15 are in italics below.

US

Direct/Ensure RO takes manual control of 1FK-121 and returns charging flow to normal.

o Inform SM of FK-121 failure.

RO

Perform the following at 1PM05J:

Place 1FK-121, 1CV121 Controller, in manual.

Raise demand on 1FK-121.

Monitor charging flow and pressurizer level and return level to normal.

Maintain charging flow by operating 1FK-121 in manual.

US

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

US o IF PZR pressure drops below 2209 psig, enter Tech Spec 3.4.1 condition A.

Note: If crew elected to enter 1BwOA PRI-15, LOSS OF NORMAL CHARGING.

Actions for 1BwOA PRI-15 are in italics below.

Comments:

Braidwood NRC 09-3 Page 8

Scenario NRC 09-3 Event 2 No: No.

Event 1CV121 controller fails low in auto

==

Description:==

Time Position Applicants Actions or Behavior US

Notify Shift Manager of plant status and procedure entry.

o Request evaluation of Emergency Plan conditions.

Implement 1BwOA PRI-15, LOSS OF NORMAL CHARGING, and direct operator actions of 1BwOA PRI-15 to establish the following conditions:

RO

Perform the following at 1PM05J:

Check CV pump status:

Identify 1A CV pump is running.

Check indications of charging pumps NOT fluctuating.

Check CV valve alignment.

1CV8146 open

1CV8324A open

1CV8105 and 1CV8106 open

Check charging flow NOT established.

Throttle 1CV121 open by placing controller in manual and raising demand.

o Re-establish letdown per 1BwOA ESP-2 Note: If letdown was isolated, it must be restored before initiating the next event.

Initiate the next event when the lead examiner approves.

Comments:

Braidwood NRC 09-3 Page 9

Scenario NRC 09-3 Event 3&4 No: No.

Event High RCS activity requiring plant shutdown/ AB transfer pump trip.

==

Description:==

Time Position Applicants Actions or Behavior CUE

High alarm on gross failed fuel rad monitor 1PR06J o High alarm on VCT cubicle rad monitor 1AR013J o High alarm on containment atmosphere monitor 1PR11J CREW

Identify entry conditions for 1BwOA PRI-4, HIGH RCS ACTIVITY UNIT 1 US

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions

Enter/Implement 1BwOA PRI-4 and direct operator actions of 1BwOA PRI-4 to establish the following conditions:

US

Notify Chemistry to calculate DF for letdown mixed bed demineralizer

Notify Chemistry to sample for dose equivalent I-131 and noble gas activity

Notify Rad Protection to monitor aux building radiation RO/

Verify high alarm on gross failed fuel rad monitor 1PR06J BOP

Verify 120 gpm letdown flow US

Consult station nuclear engineer for operational guidance

Refer to TS 3.4.16

Determine conditions A & C applies - DE I-131 > 1 Ci/gm and gross radioactivity > 100/E-bar limit o Refer to TS 3.4.15 o Determine condition B applies if 1PR11J status changes to dark blue

Determine unit shutdown required o Check letdown demin DF acceptable per Chemistry Procedure Comments:

Braidwood NRC 09-3 Page 10

Scenario NRC 09-3 Event 3 No: No.

Event High RCS activity requiring plant shutdown

==

Description:==

Time Position Applicants Actions or Behavior US

Implement actions of 1BwGP 100-4

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

US

Direct plant shutdown o Initiate power reduction flow chart, 1BwGP 100-4T1 o Initiate rapid power reduction flow chart, 1BwGP 100-4T3 o Initiate load swing instruction sheet, 1BwGP 100-4T2 o If requested, nuclear engineer will obtain reference reactivity data CREW o Review applicable Precautions, Limitations and Actions of 1BwGP 100-4 Note: The boric acid transfer pump will trip during the boration.

RO

Verify rod position and boron concentration

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

Determine required boric acid volume approximate band: approx 234-345 gal) o Reactivity Maneuver (ReMa) Form

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 Comments:

Braidwood NRC 09-3 Page 11

Scenario NRC 09-3 Event 3&4 No: No.

Event High RCS activity requiring plant shutdown/ AB transfer pump trip.

==

Description:==

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

Open 1CV110B

Open 1CV110A

Start the BA Transfer pump

When desired amount of BA has been added (or AB pump trips), stop the BA Transfer Pump

Close 1CV110A

Close 1CV110B Note: When AB transfer pumps trips, RO must manually insert control rods for reactivity control prior to initiating next event.

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 below current value in REF window into REF DEMAND window.

Select ENTER.

Enter desired 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.

RO/

Monitor reactor power and load reduction BOP

Monitor NIs, Tave, I, Pzr press/level

Monitor MWe, Turb loading, EHC When lead examiner concurs, initiate the next event.

Comments:

Braidwood NRC 09-3 Page 12

Scenario NRC 09-3 Event 4 No: No.

Event Boric acid transfer pump trip

==

Description:==

Time Position Applicants Actions or Behavior CUE o (If boration was done in batch mode) o Annunciator BA XFER PUMP TRIP (1-9-A4) o Trip/yellow disagreement light on Boric Acid Transfer pump 1 + 0 C/S o (If boration was done in borate mode) o Boric acid flow stops o Annunciator BA FLOW DEVIATION (1-9-A6)

RO

Identify/report trip of Unit 1 Boric Acid Transfer pump

Refer to BwAR 1-9-A4

Dispatch operator to Unit 1 Boric Acid Transfer pump and breaker US

Notify SM of Unit 1 Boric Acid Transfer pump trip.

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 o Dispatch operators RO

Determine Unit 1 Boric Acid Transfer pump bearing is damaged

Report from EO o MAKE-UP MODE CONT SWITCH to STOP

Place Boric Acid Transfer pump 1 + 0 C/S in PULL OUT o Close 1CV110A o Close 1CV110B US o Contact SM to perform risk assessment, initiate IR, and contact maintenance to investigate/correct component.

o Recommence ramp using rods only.

BOP o Initiate turbine load reduction:

o When ready to begin load reduction, depress GO o Verify load reduction occurring Comments:

Braidwood NRC 09-3 Page 13

RO/

Monitor reactor power and load reduction BOP

Monitor NIs, Tave, I, Pzr press/level

Monitor MWe, Turb loading, EHC RO

Maintain Tave/Tref within desired band:

At 1PM05J - insert rods manually at desired intervals.

NOTE: After the actions for boric acid pump trip are complete and with lead examiners concurrence, enter next event Comments:

Braidwood NRC 09-3 Page 14

Scenario NRC 09-3 Event 5, 6 & 7 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 RO 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 RO Perform immediate operator actions of 1BwEP-0:

[CT]

Check SI status E-0--D

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:

Braidwood NRC 09-3 Page 15

Scenario NRC 09-3 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 open.

PMG output breaker open.

Trip all running HD 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.

Comments:

Braidwood NRC 09-3 Page 16

Scenario NRC 09-3 Event 5 No: No.

Event Steam leak inside containment/uncontrolled depressurization of all SGs

==

Description:==

Time Position Applicants Actions or Behavior

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 RO/

Verify ECCS pumps running BOP

Both CV pumps - RUNNING

Both RH pumps - RUNNING

Both SI pumps - RUNNING RO/

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

Verify Phase A isolation - Group 3 Cnmt Isol monitor lights - LIT

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 - BOTH RUNNING

Verify SX pumps- -BOTH RUNNING Comments:

Braidwood NRC 09-3 Page 17

Scenario NRC 09-3 Event 5 No: No.

Event Steam leak inside containment/uncontrolled depressurization of all SGs

==

Description:==

Time Position Applicants Actions or Behavior RO/

Check Main Steamlines Should Be Isolated BOP

CNMT pressure > 8.2 psig

Verify MS isolation

MSIVs open

Manually actuate MS isolation

MSIVs remain open BOP/

Check if CS is required RO

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 Note: RCPs may be stopped by crew any time after recognizing a Phase B isolation has occurred.

US

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

Braidwood NRC 09-3 Page 18

Scenario NRC 09-3 Event 8 No: No.

Event Failure of both trains of CS to automatically actuate

==

Description:==

Time Position Applicants Actions or Behavior RO/

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.

RO/

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 RO/

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 RO/

Verify ECCS valve alignment BOP

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

Braidwood NRC 09-3 Page 19

Scenario NRC 09-3 Event 5 No: No.

Event Steam leak inside containment/uncontrolled depressurization of all SGs

==

Description:==

Time Position Applicants Actions or Behavior 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 RO

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.

RO

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)

RO/

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 Comments:

Braidwood NRC 09-3 Page 20

Scenario NRC 09-3 Event 5 No: No.

Event Steam leak inside containment/uncontrolled depressurization of all SGs

==

Description:==

Time Position Applicants Actions or Behavior CREW Transitions to 1BwEP-2, FAULTED STEAM GENERATOR ISOLATION

Notifies SM of plant status and procedure entry

Requests evaluation of Emergency Plan conditions US

Request STA evaluation of status trees

Enter/Implement 1BwEP-2 and direct operator actions of 1BwEP-2 to establish the following conditions RO/

Check MS isolation BOP

MSIVs remain open CREW

Check if any secondary pressure boundary intact

No SG pressure stable or rising

All SG depressurizing in an uncontrolled manner

GO TO 1BwCA-2.1, 'UNCONTROLLED DEPRESSURIZATION OF ALL SGs Examiner note: Throttling AF flow to 45 gpm per SG will result in a red path on the heat sink status tree and require transition to 1BwFR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK. 1BwFR-H.1 will be entered and immediately exited due to operator action lowering AF flow to < 500 gpm.

Comments:

Braidwood NRC 09-3 Page 21

Scenario NRC 09-3 Event 5 No: No.

Event Steam leak inside containment/uncontrolled depressurization of all SGs

==

Description:==

Time Position Applicants Actions or Behavior CREW Transitions to 1BwCA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS US

Notifies SM of plant status and procedure entry

Requests evaluation of Emergency Plan conditions

Enter/Implement 1BwCA-2.1 and direct operator actions of 1BwCA-2.1 to establish the following conditions RO/

Check secondary pressure boundary BOP

MSIVs open - attempt to close w/control switch (may have been previously tried)

MSIV bypass valves - CLOSED

SG PORVs - CLOSED

Check FW isolation monitor lights - LIT

Check 1SD002A-H - CLOSED

Check 1SD005A-D - CLOSED RO/

Control feed flow to minimize RCS cooldown BOP

Throttle AF to 45 gpm per SG

[CT]

Check hot leg temperatures - Stable or Dropping ECA-2.1-

Check RCPs -NONE RUNNING

-A

Check Pzr PORVs and Isolation Valves

PORV Isolation Valves - BOTH Energized and Open

PORVs - BOTH Closed Note: When the crew recognizes 1D SG MSIV has closed and pressure is rising in the 1D SG. Transition is made back to 1BwEP-2 per the OAS.

RO/

Check Secondary Radiation BOP

Reset Phase A

Open 1SD005A-D

Check secondary radiation trends on RM-11 Or HMI - ALL Normal Comments:

Braidwood NRC 09-3 Page 22

Scenario NRC 09-3 Event 5 No: No.

Event Steam leak inside containment/uncontrolled depressurization of all SGs

==

Description:==

Time Position Applicants Actions or Behavior RO/

Check If RH Pumps Should Be Stopped BOP

RH Pumps - BOTH Running o RCS pressure >325 and stable or rising o Reset SI and Secure RH pps RCS pressure < 325 psig - Go to step 7 RO/

Check if CS Should be Isolated BOP

CS Pumps - BOTH Running o CS Add Tank LO-2 lights LIT and CNMT pressure <15 psig o Secure CS pumps and close 1CS007A/B and 1CS019A/B valves o CS Add Tank LO-2 lights NOT LIT or CNMT pressure >15 psig o Go to step 8

Check RWST Level > 46%

Check RCS pressure > 125 psig

Check if ECCS Flow Should be Reduced

Subcooling - ACCEPTABLE

RCS Pressure stable or Rising

Pzr Level > 28%

Note: By this point the crew should recognize 1D MSIV has closed and pressure is rising in the 1D SG.

If the crew has not recognized 1D MSIV has closed, the drill may be terminated at this point.

CREW Transitions to 1BwEP-2, FAULTED STEAM GENERATOR ISOLATION US

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

Enter/Implement 1BwEP-2 and direct operator actions of 1BwEP-2 to establish the following conditions RO/

Check MS isolation BOP

3 MSIVs remain open CREW

Check if any secondary pressure boundary intact Comments:

Braidwood NRC 09-3 Page 23

Scenario NRC 09-3 Event 5 No: No.

Event Steam leak inside containment/uncontrolled depressurization of all SGs

==

Description:==

Time Position Applicants Actions or Behavior

Recognize 1D SG pressure is stable or rising.

RO/

Identify Faulted SGs BOP

Recognize 1A, 1B & 1C SG pressure is lowering.

RO/

Isolate the faulted SGs BOP

CLOSE 1AF013A, B, C, E, F & G Note: At this point the scenario may be terminated.

Comments:

Braidwood NRC 09-3 Page 24

Simulation Facility Braidwood Scenario Operating Test No.:2009-1 No.:

NRC 09-4 Examiners: ______________________ Applicant: _____________________ SRO

______________________ _____________________ RO

______________________ _____________________ BOP Initial Conditions: IC-16 Turnover: Unit 1 is operating at 51% power, steady state, equilibrium xenon, Boron concentration is 742 ppm. Online risk is yellow. 1B RH pump has been OOS for breaker work for the past 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . LCO 3.5.2 has been entered. Expect 1B RH pump back in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . Following completion of turnover, the crew is to perform 1BwOS MS-Q1, UNIT 1 MAIN STEAM DUMP VALVE STROKE SURVEILLANCE. Power Team has requested Unit 1 be prepared to raise power to 880 MW at 0.6 MW/min due to grid demand following completion of 1BwOS MS-Q1.

1CV111B BORIC ACID BLNDR TO VCT VLV is OOS for solenoid replacement.

Event Malf. No. Event Event No. Type* Description Preload IOR ZDI1RH01PB PTL 1B RH pump OOS IMF RP01 Failure of Rx to auto trip IOR ZDIRT2 NORMAL Failure of Rx Trip switch on 1PM05J IMF RD05G13 15 stuck rod IMF RD05H12 15 stuck rod IMF RD05H14 8 stuck rod IMF RD05J13 25 stuck rod IMF EG08B 1B DG failure IOR ZDI1CV111B CLS 1CV111B OOS IOR ZDO1CV111B(1)

OFF IOR ZDO1CV111B(2)

OFF 1 None N-BOP, US Steam Dump Valve Stroke Surv.

2 None R-RO, US Raise power at 0.6 Mw/Min, Alt. Dilute only 3 IMF RX18H, 650 I-RO, US Loop 4 Thot RTD fails high IMF RX18L, 650 TS-US 4 None TS-US 1SA032, containment isol.valve fails stroke time test 5 IOR ZDI1HSTG010 C-RO, US Inadvertent turbine trip, failure of auto Rx trip TRIP Preload 6 Preload C-RO, US four stuck rods 7 IMF ED15C Loss of Offsite Power 8 IMF EG08A 90 M-ALL EDG1A fails 90 sec after start resulting in a loss of all AC power

(N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor Transient Braidwood NRC 09-4

SCENARIO OVERVIEW Unit 1 is operating at 51% power, steady state, equilibrium xenon, Boron concentration is 742 ppm. Online risk is yellow. 1B RH pump has been OOS for breaker work for the past 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months . LCO 3.5.2 has been entered. Expect 1B RH pump back in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . Following completion of turnover, the crew is to perform 1BwOS MS-Q1, UNIT 1 MAIN STEAM DUMP VALVE STROKE SURVEILLANCE using the step 2, full stroke test method. The Field Supervisor and Equipment Operators have been briefed and are standing by at the steam dump isolation valves. Power Team has requested Unit 1 be prepared to raise power to 880 MW at 0.6 MW/min due to grid demand following completion of 1BwOS MS-Q1.

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, the crew will raise power to 880 MW @ 0.6 MW/min due to grid demand.

After a measurable change in power, Loop 4 Thot fails high, resulting in demanded rod inward motion.

The crew should take actions to stabilize the plant per 1BwOA INST-2. Technical Specifications 3.3.1 applies.

After the RTD failure has been addressed, an extra NSO will inform the US that 1SA032 valve failed its stroke time test. Tech Spec 3.6.3 applies.

Once the above actions have been taken, a trip of the main turbine will occur. The reactor does not automatically trip and the manual trip switch at 1PM05J is disabled. The crew should trip the reactor from 1PM06J and complete immediate actions of 1BwEP-0. When the reactor trips, one control bank rod and three shutdown bank rods will not fully insert. The crew will transition to 1BwEP ES-0.1 and initiate emergency boration for the stuck rods. Once the crew has initiated emergency boration, a loss of all offsite power will occur. The 1B DG will not start. The 1A DG will start and energize ESF Bus 141. Approximately 90 seconds later, the 1A DG will trip resulting in a loss of all AC power to the unit. Transition will be made to 1BwCA-0.0. The crew must restore power to Unit 1 within 10 minutes. After power is restored to Bus 141, a transition will be made to either 1BwCA-0.1 or 1BwCA-0.2.

Completion criteria The scenario ends following restoration of charging flow.

Critical Tasks

1. Perform a manual reactor trip at 1PM06J before transition out of 1BwEP-0.

(ERG Critical Task number - E-0--A) (K/A number - 000029EA1.08 importance - 4.5/4.5)

2. Cross-tie an ESF bus to opposite unit within 10 minutes of Loss of All AC.

(10CFR50.63 section (c)(2)) (K/A number - 000055EA2.03 importance - 3.9/4.7)

3. Isolate RCP seal injection before a CV pump is started.

(ERG Critical Task number - ECA-0.0--H) (K/A number - 003000A4.01 importance - 3.3/3.2)

Braidwood NRC 09-4 2

SIMULATOR SETUP GUIDE:

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

Establish the conditions of IC-16, 51% 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).

Run caep NRC 09-4 SETUP from disk and verify the following actuate:

IOR ZDI1RH01PB PTL

IMF RP01

IOR ZDIRT2 NORMAL

IMF RD05G13 15

IMF RD05H12 15

IMF RD05H14 8

IMF RD05J13 25

IMF EG08B

IOR ZDI1CV111B CLS

IOR ZLO1CV111B1 OFF

IOR ZLO1CV111B2 OFF

Place 1B RH pump in PTL and place a info tag on the 1B RH pump control switch.

Place INFO card on 1CV111B C/S stating valve is de-energized for solenoid replacement.

Place PZR backup heaters in AUTO.

Update PARAGON to reflect 1B RH pump OOS and place YELLOW on line risk placard.

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

Braidwood NRC 09-4 3

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 CAEP NRC 09-4 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 Braidwood NRC 09-4 4

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: Raise power at 0.6 MW/min As Shift Manager, contact the MCR and request Unit 1 raise power to 880 MW at 0.6 MW/min due to grid demand.

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

Acknowledge as TSO initiation of ramp.

Braidwood NRC 09-4 5

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 3: Loop 4 Thot 2 RTD fails high Run caep NRC 09-4 EVENT 3 from disk and verify the following actuate:

IMF RX18H 650

IMF RX18L 650 Acknowledge as SM entry into TS 3.3.1, conditions A and E entry, request for NSOs, on line risk assessment(yellow), request for maintenance support, and IR requests.

As SM, if requested support for tripping bistables, report that bistables are not to be tripped until work analyst /NSO support can be obtained (i.e. not at this time) and that the abnormal operating procedure should be continued. Bistable tripping will be conducted later.

FOLLOWING COMPLETION OF THE SCENARIO, VERIFY/RESTORE THE FOLLOWING COMPUTER POINTS:

T0460

T0462 Event 4: 1SA032 fails its stroke time test As an extra NSO, deliver 1BwOSR 3.6.3.5.SA-1 surveillance to the US for review.

Acknowledge as SM entry into TS 3.6.3 Condition A, request for maintenance support, and IR requests.

If requested for support to isolate the failed containment penetration with a manual isolation valve, report 1SA155 manual isolation valve is already closed in its normal position.

Braidwood NRC 09-4 6

INSTRUCTOR/SIMULATOR RUN AID GUIDE Events 5 & 6: Inadvertent turbine trip/auto reactor trip failure with four stuck rods/loss of offsite power/loss of all AC power Insert: IOR ZDI1HSTG010 TRIP for inadvertent turbine trip.

Acknowledge as SM procedure changes, E Plan evaluations, request for SDM calculation, and STA request.

Events 7 & 8: Loss of offsite power/loss of all AC power Verify the crew has initiated emergency boration prior to initiating the next event Run caep NRC 09-4 EVENTS _7 _8 from disk and verify the following actuate:

IMF ED15C

IMF EG08A 90 Record time loss of all AC power occurred: ______:______:______

Record time AC power restored to Unit 1: ______:______:______

Calculate time to restore AC power: ______:______:______

Record time bus 142 restored ______:______:______

Acknowledge as SM procedure changes, E Plan evaluations, request for SDM calculation, and STA request.

After STA requested, as STA report CSF status - Yellow on inventory if pressurizer level < 17%.

When requested as EO to start the U1 D/Gs report that 1A D/G is seized and 1B D/G tripped on loss of field flash. 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, acknowledge request to perform 2BwCA-0.3, report both Unit 2 4KV ESF buses powered from Unit 2 SATs, and acknowledge request to monitor crosstie current as loads are started.

Wait 4 min 19 sec after loss of all AC power (if requested) to perform 2BwCA 0.3 then: Insert the following to perform crosstie:

MRF ED006 CLOSE (closes 2414 brk)

MRF ED007 CLOSE (closes 2424 brk)

Acknowledge as EO request to close 1CV8384A & B and insert the following to isolate the seal injection filters:

MRF CV41 0

MRF CV42 0 Braidwood NRC 09-4 7

Acknowledge as EO request to isolate CC surge tank auto makeup and insert the following to isolate CC surge tank makeup:

MRF CC51 0

MRF CC52 0 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

MRF CC16 100 FOLLOWING COMPLETION OF THE SCENARIO, VERIFY/RESTORE THE FOLLOWING COMPUTER POINTS:

T0460

T0462 Braidwood NRC 09-4 8

Scenario NRC 09-4 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.

US

Acknowledge report.

o Notify SM 1BwOS MS-Q1 is complete.

Comments:

Braidwood NRC 09-4 Page 9

Scenario NRC 09-4 Event 1 No: No.

Event Perform 1BwOS MS-Q1

==

Description:==

Time Position Applicants Actions or Behavior EVALUATOR NOTE: After 1BwOS MS-Q1 is complete and with lead examiner concurrence, enter next event.

Comments:

Braidwood NRC 09-4 Page 10

Scenario NRC 09-4 Event 2 No: No.

Event Raise power at 0.6 MW/min

==

Description:==

Time Position Applicants Actions or Behavior CUE o Call from Transmission System Operations to raise power to 880 MW at 0.6 Mw/min.

US

Acknowledge request to raise power to 880 MW at 0.6 Mw/min.

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

US

Direct raising load to 880 MW at 0.6 MW/min.

Initiate load swing instruction sheet, 1BwGP 100-4T2.

CREW

Review applicable Precautions, and Limitations and Actions RO

Verify rod position and boron concentration.

Initiate dilution, if required (BwOP CV-6)

Determine required PW volume: (approximate band: 2500 gal - 3000 gal)

Effects of previously performed dilutions Braidwood Boration Dilution Tables

Determine required PW flow rate.

Set 1FK-111 PW Flow Cont to desired PW flow rate.

Set 1FY-0111 PW/Total Predet Counter to desired PW volume.

Place MAKE-UP CONT SWITCH to STOP position.

Set MODE SELECT to DIL/ALT DIL position.

Place MAKE-UP CONT Switch to START Verify proper operation of valves and PW makeup pump, 1CV111A throttled, 1CV110B open (ALT DIL only), PW pump running, PW flow on recorder) o Turn on PZR backup heaters in accordance with BwOP RY-14, PRESSURIZER BACKUP HEATER OPERATION.

OR Batch addition of PW:

Open CV110B.

Open CV111A.

When desired amount of primary water added:

Close CV110B.

Close CV111A.

Comments:

Braidwood NRC 09-4 Page 11

Scenario NRC 09-4 Event 2 No: No.

Event Raise power at 0.6 MW/min

==

Description:==

Time Position Applicants Actions or Behavior BOP

Raise turbine load at 1PM02J or OWS drop 210 by performing the following::

Select SETPOINT.

Enter 880 MW into REF DEMAND window

Select ENTER.

Enter 0.6 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.

RO/

Monitor reactor power and load increase:

BOP

Monitor NIs, Tave, I, Pzr press/level

Monitor MWe, Turb loading, EHC

During dilution:

Monitor VCT level

Verify RCS boron concentration lowering

Monitor PW/Total flow predet counter

Verify dilution auto stops at preset value.

Return Reactor Makeup System to automatic at current boron concentration.

After measurable change in power and lead examiner approves, initiate the next event.

Comments:

Braidwood NRC 09-4 Page 12

Scenario NRC 09-4 Event 3 No: No.

Event Loop D Thot RTD fails high.

==

Description:==

Time Position Applicants Actions or Behavior CUE

Loop D Tave rise

Loop D T rise

Control rod inward motion o Annunciator CHG LINE FLOW HIGH/LOW (1-9-D3)

Annunciator PZR LVL CONT DEV LOW (1-12-B4)

Numerous annunciators on blocks 10 and 14 RO

Determines rod motion due to instrument failure

Place rod bank select switch in MANUAL RO

Identify/report failed Tave & T

Determine RTD failed on Loop D

Maintain Rod Bank Select switch in MANUAL US

Implement 1BwOA INST-2 "OPERATION WITH A FAILED INSTRUMENT CHANNEL", Attachment A "RCS NARROW RANGE RTD CHANNEL FAILURE" and direct operator action.

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

Manually defeat failed RTD channel

Select 1D position on Tave DEFEAT switch

Select 1D position on T DEFEAT switch

Check Reactor Power < 100%

Select operable channel for T recorder

Check if rod control can be placed in auto

C5 - NOT LIT

Check Tave-Tref stable and within 1°F o Restore to within 1°F o Place rod control in AUTO

Check PZR level normal & stable o Manually restore PZR level to program level - throttle 1CV121 to restore level Comments:

Braidwood NRC 09-4 Page 13

Scenario NRC 09-4 Event 3 No: No.

Event Loop D Thot 2 RTD fails high.

==

Description:==

Time Position Applicants Actions or Behavior RO

Check P12 interlock

LO-2 TAVE STM DUMP INTLK P12 (1-BP-4.5) not lit BOP

Place Computer points T0460 and T0462 in TEST US

Check Technical Specifications:

Determines TS 3.3.1 conditions A and E are applicable.

US

Inform SM/Maint of Loop 1D Thot RTD failure

Inform SM of unit status/potential EP event and TS 3.3.1 cond A and E entry.

o Enter dequip for P-12

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:

Braidwood NRC 09-4 Page 14

Scenario NRC 09-4 Event 4 No: No.

Event 1SA032 containment isolation valve fails stroke time test.

==

Description:==

Time Position Applicants Actions or Behavior CUE

Extra NSO delivers 1BwOSR 3.6.3.5.SA-1 surveillance to the US for review.

US

Recognize entry conditions for Tech Spec 3.6.3 Condition A o Inform SM of 1SA032 status, TS Status, request IR and maintenance support.

o Request verification that 1SA155 valve is closed.

EVALUATOR NOTE: After the actions for the 1SA032 failure are complete and with lead examiner concurrence, insert the next event.

Comments:

Braidwood NRC 09-4 Page 15

Scenario NRC 09-4 Event 5&6 No: No.

Event Inadvertent turbine trip/auto reactor trip failure with four stuck rods

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator TURB TRIP ABOVE P8 RX TRIP (1-11-A9)

Annunciator TURB STOP VLV CLOSED ALERT (1-18-A4)

US

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

RO Perform immediate operator actions of 1BwEP-0

Verify reactor trip

[CT]

Rod bottom lights - NOT ALL LIT E-0---A

Manually trip the reactor (1PM06J)

Reactor trip & Bypass breakers - OPEN

Neutron flux - DROPPING

PR channels < 5%

IR SUR is negative BOP Perform immediate operator actions of 1BwEP-0:

Verify Turbine Trip

All Turbine throttle valves - CLOSED

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

Verify power to 4KV busses

ESF Buses - BOTH ENERGIZED (141 & 142)

CREW Determine SI NOT actuated/required

Check SI status

SI First OUT annunciators NOT lit (1-11-B1, 1-11-C1, 1-11-D1, 1-11-E1)

SI ACTUATED permissive light NOT lit (1-BP-4.1)

SI Equipment NOT automatically actuated (no SI pump running, no1SI8801A/B open)

Check if SI is required

PZR pressure > 1829 psig

Steamline pressure > 640 psig

CNMT pressure <3.4 psig US

Review immediate operator actions and determine SI not required Comments:

Braidwood NRC 09-4 Page 16

Scenario NRC 09-4 Event 5&6 No: No.

Event Inadvertent turbine trip/auto reactor trip failure with four stuck rods

==

Description:==

Time Position Applicants Actions or Behavior

Notify SM of plant status (auto reactor trip failure) and procedure entry

Request evaluation of Emergency Plan conditions

Transition to 1BwEP ES-0.1 "REACTOR TRIP RESPONSE" o Request STA evaluation of status trees RO

Maintain RCS temperature control

Check RCPs - RUNNING

Verify RCS average temperature stable at or trending to 557o RO

Verify ALL control rods fully inserted

Rod at bottom lights - NOT ALL LIT

Initiate emergency boration of 5280 gallons (22000 gal. from RWST) per 1BwOA PRI-2, EMERGENCY BORATION

Calculate shutdown margin within one hour (request U-2 operators to perform SDM calculation)

RO

Initiate emergency boration per 1BwOA PRI-2 EMERGENCY BORATION

Check CV pump status

1A CV pump running

Emergency borate RCS

Establish boration flow from BAT o Open 1CV8104 o Open 1CV110A & 1CV110B

Start boric acid transfer pump

Check emergency boration flow > 30 gpm (1FT-0110 or 1FI-183A)

Verify CV pump discharge flow path aligned with proper flow

Equalize RCS and PZR boron

Verify PZR backup heaters energized

Continue boration until required gallons of boron added Once the crew has initiated emergency boration, initiate the next event.

RO o Check PZR level control

Level > 17% and trending to 26%

Charging and letdown - IN Service Comments:

Braidwood NRC 09-4 Page 17

Scenario NRC 09-4 Event 5&6 No: No.

Event Inadvertent turbine trip/auto reactor trip failure with four stuck rods

==

Description:==

Time Position Applicants Actions or Behavior RO o Check PZR pressure control

Pressure > 1829 psig and trending to 2235 psig BOP o Check FW isolation

Isolation monitor lights - LIT

Trip FW pumps o Check total feed flow to SGs - GREATER THAN 500 GPM o Start 1A FW Pump o Start AF pump(s)

BOP o Check SG levels

Levels maintained between 10% and 50%

BOP o Verify generator trip

Main transformer output breakers - OPEN

OCB 1-8

OCB 7-8

PMG output breaker - OPEN

Verify ALL AC busses energized Comments:

Braidwood NRC 09-4 Page 18

Scenario NRC 09-4 Event 7&8 No: No.

Event Loss of Offsite Power with 1B DG trip and failure of 1A DG 90 sec after start.

==

Description:==

Time Position Applicants Actions or Behavior CUE

A Loss of Offsite power is indicated

Annunciator LOSS OF OFFSITE POWER (1-20-A1)

CREW

Identify Loss of Offsite Power.

RO o Determine emergency boration stopped NOTE: US may enter 1BwOA ELEC-3 and ELEC-4 but must enter 1BwCA-0.0 when DG 1A is trips.

US

Implement 1BwCA-0.0 "LOSS OF ALL AC POWER"

Direct operator actions of 1BwCA-0.0

Notifies SM of plant status and procedure entry

Requests evaluation of Emergency Plan conditions NOTE: For evaluation of critical task, Record time loss of all AC power occurred.

RO Perform immediate operator actions of 1BwCA-0.0:

Verify reactor trip

Reactor trip & Bypass breakers - OPEN

Neutron flux - DROPPING BOP Perform immediate operator actions of 1BwCA-0.0:

Isolate Steamlines

Actuate main steamline isolation

Verify all MSIVs and MSIV Bypass valves - CLOSED BOP

Verify AF flow

>500 gpm (1B AF only)

Comments:

Braidwood NRC 09-4 Page 19

Scenario NRC 09-4 Event 7&8 No: No.

Event Loss of Offsite Power with 1B DG trip and failure of 1A DG 90 sec after start.

==

Description:==

Time Position Applicants Actions or Behavior

Verify RCS isolated

1RY455A and 1RY456 closed

1CV8149A, B & C closed

1CV459 and 1CV460 closed

1CV8153A & B closed BOP

Try to restore power to any/both Unit 1 4KV ESF buses

Identify/report neither DG running

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 US

Check status of Unit 2 ESF buses

Both Unit 2 4 KV ESF buses energized from SAT

Notify Unit 2 to implement 2BwCA-0.3.

BOP/

Crosstie bus 141 to Unit 2 US

Bus 241 energized from SAT

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)

Comments:

Braidwood NRC 09-4 Page 20

Scenario NRC 09-4 Event 7&8 No: No.

Event Loss of Offsite Power with 1B DG trip and failure of 1A DG 90 sec after start.

==

Description:==

Time Position Applicants Actions or Behavior

Crosstie bus 141 to Unit 2 (Contd)

Verify loads fed from Bus 141 available

Bus 131X

CENT CHG pump 1A

CC pump 1A or 0

SX pump 1A

MCR chiller 0A

Place ESF loads in PULL OUT

CENT CHG pumps

RH pumps

SI pumps

AF pump 1A

RCFCs (HI and LO)

CS pumps

CC pumps (1A, 1B, and 0)

SX pumps

MCR chillers

Check ACB 2414 closed (reserve feed light lit.)

[CT]

Synch and Close Bus 141/241 reserve feeder breaker

Close ACB 1414

Check Bus 141 energized

Check Bus 131X energized NOTE: For evaluation of critical task, record time AC power restored:

Time power restored - time power lost = ______:______:______ (<10 minutes)

BOP

Restore Unit 1 SX cooling

Check valves for available SX pump - OPEN

1SX001A

1SX016A

1SX027A

Start SX pump 1A

Check open SX crosstie valves - 1SX033 and 1SX034 Comments:

Braidwood NRC 09-4 Page 21

Scenario NRC 09-4 Event 7&8 No: No.

Event Loss of Offsite Power with 1B DG trip and failure of 1A DG 90 sec after start.

==

Description:==

Time Position Applicants Actions or Behavior RO

Verify Equipment loaded on energized 4KV ESF Bus(es)

/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)

BOP/

Align equipment for Unit 1 restoration RO

Verify 1B AF pump - RUNNING

Check both Unit 2 ESF buses - ENERGIZED FROM SAT

Check Bus 142 - NOT FAULTED

ACB 1423 (DG feed) in PULL OUT

ACB 1421 (Non-ESF bus tie) in PULL OUT

ACB 1422 (SAT feed) in PULL OUT

ACB 1424 (Reserve feed) in PULL OUT

Verify Bus 142 alarms NOT LIT

Annunciator BUS 142 FD BRKR ACB 1422 TRIP (1-22-A7)

Annunciator BRKR 1424 CROSS-TIE OVERCURRENT (1-22-B8)

Annunciator DG 1B OVERLOAD (1-22-B9)

Check ACB 2424 closed

Synch and Close Bus 142/242 reserve feeder breaker

Close ACB 1424

Dispatch EOs to start DGs per 1BwOA ELEC-3, LOSS OF 4KV ESF BUS

Dispatch EOs to Close 1CV8384A & B

Close CC from RCP Thermal Barrier isol valves - 1CC685 or 1CC9438

Close RCP seal water return isol valves - 1CV8100 or 1CV8112

Place S/G PORVs in Auto

Check VC fans - ONE TRAIN RUNNING

Start makeup fan Comments:

Braidwood NRC 09-4 Page 22

Scenario NRC 09-4 Event 7&8 No: No.

Event Loss of Offsite Power with 1B DG trip and failure of 1A DG 90 sec after start.

==

Description:==

Time Position Applicants Actions or Behavior CREW

Select proper recovery procedure

Check RCS subcooling acceptable per ICONIC DISPLAY or attachment A

Check PZR level > 14% (28% ADVERSE)

Verify SI Equipment NOT automatically actuated upon AC power restoration

Determine proper recovery procedure:

1BwCA-0.1 if all the following satisfied:

RCS subcooling acceptable Iconic Display OR Attachment A

Pzr level > 14% (28% ADVERSE)

NO SI equipment auto actuation on AC restoration:

No high head ECCS or SI pump flow indicated

1BwCA-0.2 if ANY of the above conditions NOT satisfied US o Transition to 1BwCA-0.1 "Loss of All AC Power Recovery without SI Required" (below) o Transition to 1BwCA-0.2 "Loss of All AC Power Recovery with SI Required" (page 28)

US Note: During performance of 1BwCA-0.1 the US may elect to transition to 1BwCA-0.2 based on OAS criteria for pressurizer level. If the US transitions to 1BwCA-0.2, go to page 28 Implement 1BwCA-0.1 "Loss of All AC Power Recovery without SI Required"

Direct operator actions of 1BwCA-0.1

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions RO

Check RCP Seal Isolation Status

[CT]

Check 1CV8384A & B CLOSED ECA-

Check 1CC685 and/or 1CC9438 CLOSED 0.0--H Comments:

Braidwood NRC 09-4 Page 23

Scenario CERT 09-4 Event 7&8 No: No.

Event Loss of Offsite Power with 1B DG trip and failure of 1A DG 90 sec after start.

==

Description:==

Time Position Applicants Actions or Behavior RO/

Reset CNMT Isol Phase A BOP RO/

Manually Load following equipment on 4KV bus BOP

Check if any SAC RUNNING

Unit 2 SAC running

Open IA CNMT Isol Valves - 1IA065 & 1IA066

Start one CC pump

Align CENT CHG pump suction to RWST (if 1CV112B & C are closed)

Open at least one RWST to CENT CHG pump suction valve - 1CV112D/E

Close at least one VCT outlet isol valve - 1CV112B/C

Reset SI recirc sump isol valves and CENT CHG pump miniflow isol valves

Verify available CENT CHG pump miniflow isol valves OPEN

Verify/close at least one charging line CNMT isol valve - 1CV8105/1CV8106

Verify/close CENT CHG pumps to cold legs injection isol valves - 1SI8801A/B

Start one CENT CHG pump NOTE: If actions of 1BwCA-0.1 are being performed, Scenario may be terminated at this point.

Comments:

Braidwood NRC 09-4 Page 24

Scenario NRC 09-4 Event 7&8 No: No.

Event Loss of Offsite Power with 1B DG trip and failure of 1A DG 90 sec after start.

==

Description:==

Time Position Applicants Actions or Behavior US Implement 1BwCA-0.2 " Loss of All AC Power Recovery with SI Required "

Direct operator actions of 1BwCA-0.2

Notify SM of plant status and procedure entry

Request evaluation of Emergency Plan conditions RO

Check SI reset

Check RWST level > 46%

CREW

Manually establish ECCS injection alignment on energized train(s)

Verify RH pump miniflow valves OPEN - 1RH610 and 1RH611

Verify RH Bypass flow control valves in MANUAL with ZERO demand - 1RH618 and 1RH619

Open CENT CHG pumps to cold leg isolation valves - 1SI8801A & B

Open RWST to CENT CHG pumps suction valves - 1CV112D & E

Close VCT outlet isol valves - 1CV112B & C

Close charging line CNMT isol valves - 1CV8106 & 1CV8105 RO

Check RCP Thermal Barrier CC Isolation Status

Check CC Pumps - 1A CC pump running

Check CC from RCP Thermal Barrier isol valves closed - 1CC685 and/or 1CC9438 (previously completed)

RO/

Load safeguards equipment as necessary on energized ESF buses BOP

CC pump(s)

1A RH Pump

SI Pumps

RCFCs (LO speed)

SX pumps

VC Train

0B Chilled water pump

0B MCR chiller Comments:

Braidwood NRC 09-4 Page 25

Scenario NRC 09-4 Event 7&8 No: No.

Event Loss of Offsite Power with 1B DG trip and failure of 1A DG 90 sec after start

==

Description:==

Time Position Applicants Actions or Behavior RO

Check if CENT CHG should be started:

Check CENT CHG pumps stopped

[CT] o Check 1CV8384A & B CLOSED ECA-

Start CENT CHG pump 0.0--H NOTE: Scenario may be terminated at this point Comments:

Braidwood NRC 09-4 Page 26

Simulation Braidwood Scenario No.: Operating Test No.: 2009-1 Facility NRC 09-5 Examiners: Applicant:

______________________ ____________________ SRO

______________________ ____________________ RO

______________________ ____________________ BOP Initial Conditions: IC-21 Turnover: Unit 1 is at 100% power, steady state, equilibrium xenon, BOL. RCS boron concentration in 798 ppm. On line risk is green. Following completion of turnover, the crew is to perform 1BwOS EH-M1, UNIT 1 EH PUMP OPERABILITY MONTHLY SURVEILLANCE using the preferred method of depressing and holding the MCB pushbutton. The Field Supervisor and Equipment Operators have been briefed and are standing by at the Unit 1 EH skid. Power Team has requested Unit 1 lower power 125 MW at 3 MW/min due to grid demand following completion of 1BwOS EH-M1.

Event No. Malf. No. Event Event Type Description Preload IMF RP15R 1B SX pump fail to automatically start MRF RP89 OPEN IMF PN1143 OFF Prevent inadvertent EH Sys. Trouble alarm IMF PN1144 OFF 1 None N-BOP, US Perform 1BwOS EH-M1 2 None R-RO, US Lower power at 3 MW/Min 3 IOR ZAI1TK130 I-RO, US 1TK-130 output fails high 100 5 4 IMF ED11C TS-US Loss of DC to inverter 113 5 IMF RX21A 1700 C-RO, US Pressurizer pressure channel 1PT-455 fails low 10 TS-US 6 IMF EG03 100 10 C-BOP, US Generator voltage regulator failure 7 IMF ED07A Loss of bus 141, Rx trip and SI 8 IMF TH03D 450 M-ALL 1D SGTR 9 Preload C-BOP, US 1B SX pump fail to automatically start

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

SCENARIO OVERVIEW Unit 1 is at 100% power, steady state, equilibrium xenon, BOL. RCS boron concentration in 798 ppm. On line risk is green. Following completion of turnover, the crew is to perform 1BwOS EH-M1, UNIT 1 EH PUMP OPERABILITY MONTHLY SURVEILLANCE using the preferred method of depressing and holding the MCB pushbutton. The Equipment Operator has been briefed and is standing by at the Unit 1 EH skid. Power Team has requested Unit 1 lower power 125 MW at 3 MW/min due to grid demand following completion of 1BwOS EH-M1.

After completing shift turnover and relief, the BOP will perform 1BwOS EH-M1, UNIT 1 EH PUMP OPERABILITY MONTHLY SURVEILLANCE.

After completing 1BwOS EH-M1, the crew will lower power 125 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, 1TK-130 output, Letdown Heat Exchanger Outlet Temperature Controller, will fail high. The BwAR should be referenced and the RO should take manual control to restore letdown temperature to normal. The crew may elect to isolate letdown due to high temperature. If isolated, letdown should be restored per BwOP CV-17.

After the 1TK130 Controller has been 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. On line risk becomes yellow.

Following completion of inverter 113 actions, the controlling pressurizer pressure channel will fail low. The RO 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 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, a ground fault will occur on bus 141. The loss of bus 141 will cause a loss of instrument bus 113. The loss of instrument bus 113 in conjunction with the previously tripped pressurizer bistables will generate a reactor trip and safety injection actuation. The 1B SX pump must be manually started due to a failure of its actuation relay. The SI initiation will cause a 1D SGTR. The crew will perform 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, and transition to 1BwEP-3, STEAM GENERATOR TUBE RUPTURE, at step 22 of 1BwEP-0.

The scenario is complete when the crew has terminated high head injection and established normal charging flow in 1BwEP-3.

Critical Tasks

1. Manually start the 1B SX pump before transition out of 1BwEP-0 (ERG Critical Task number - E-0--L) (K/A number 076000A4.01 2.9/2.9)

2. Identify the 1D SG as the ruptured SG and isolate prior to a transition to 1BwCA-3.1 is required.

(ERG Critical Task number - E-3--A) (K/A number EPE038EA1.32 importance 4.6/4.7)

3. Depressurize RCS to restore RCS inventory prior to 1D SG PORV or safety valve water release.

(ERG Critical Task number - E-3--C) (K/A number EPE038EA1.09 importance 3.2/3.3)

Braidwood NRC 09-5 Page 2 of 23

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, BOL, 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).

Monitor ruptured S/G status by using monitor file - SGTR

Run caep DEMO CERT 09-5 SETUP from disk and verify the following actuate:

IMF RP15R

MRF RP89 OPEN

IMF PN1143 OFF

IMF PN1144 OFF

Verify/Set I Target Curve slopes to +2% of I.

Provide examinees with 1BwOS EH-M1 with predefine cover sheet, turnover sheets, 1BwOS NR-1 and critical parameter sheet.

Braidwood NRC 09-5 Page 3 of 23

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Perform 1BwOS EH-M1.

When requested, as Equipment Operator report you are standing by at the Unit 1 EH skid. Report the following data as EH pumps are started and stopped:

EH system temperature is 110°F.

EH system pressure is 2025 psig with ONE EH pump running.

If requested, as Field Supervisor report you are providing direct supervision in the field for production risk.

Acknowledge as Shift Manager commencement and completion of procedure.

Event 2: Lower power 125 MW at 3 MW/min Acknowledge as chemistry/rad protection requests for RCS samples (if required).

Acknowledge as Power Team initiation of ramp.

Event 3: 1TK-130 fails high Insert: IOR ZAI1TK130 100 5 Open monitor file for 1CC130A/B valve position (CCV1CC130A/B)

Acknowledge as SM requests for maintenance support, on line risk assessment (yellow), and IR for 1TK-130 failure.

If dispatched as EO to 1CC130A/B, report valve position as indicated in monitor file.

As chemistry (if called), report that the in-service mixed bed demin will remain off until it can be sampled.

Event 4: 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.

Braidwood NRC 09-5 Page 4 of 23

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 5: Pressurizer pressure channel 1PT-455 fails low Insert IMF RX21A 1700 10 to fail 1PT-455 high low a 10 second period.

As SM, if requested support for tripping bistables, report that bistables are not to be tripped until work analyst/NSO support can be obtained (i.e. not at this time) and that the abnormal operating procedure should be continued. Bistable tripping will be conducted later.

As SM acknowledge the failure, LCOs 3.3.1, conditions A, E and K, 3.3.2, conditions A and D, and 3.3.4, condition A entries, on line risk assessment, request for maintenance support, and IR request.

Event 6: Main generator voltage regulator failure Insert IMF EG03 100 10 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.

Event 7 and 8: Loss of bus 141, Rx trip and SI, 1D SGTR

Run caep NRC 09-5 EVENT 7_8 from disk and verify the following actuate:

IMF ED07A

IMF TH03D 450 Acknowledge as SM procedure changes, E Plan evaluations, and STA request.

If requested as Equipment Operator to cross-tie 125 VDC bus 111 to 125 VDC bus 211 wait five minutes and insert the following:

MRF ED111 CLOSED If dispatched as Equipment Operator to depress 1A DG emergency stop push button insert the following:

MRF EG19 TRIP If dispatched as Equipment Operator to close containment isolation valves outside containment, wait 5 minutes and insert the following:

MRF CH13 0 (closes 1WO020A)

MRF CH11 0 (closes 1WO006A)

MRF CV17 0 (closes 1CV8100)

If dispatched as Equipment Operator to locally close 1AF005D insert the following:

IRF FW174 0 30 Braidwood NRC 09-5 Page 5 of 23

Scenario NRC 09-5 Event 1 No: No.

Event Perform 1BwOS EH-M1

==

Description:==

Time Position Applicants Actions or Behavior CUE o From turnover, perform 1BwOS EH-M1, UNIT 1 EH PUMP OPERABILITY MONTHLY SURVEILLANCE.

US

Direct BOP to perform 1BwOS EH-M1.

BOP

Refer to 1BwOS EH-M1.

Record initial data on Data Sheet D-2.

Notify Equipment Operator at EH skid of pending 1B EH pump start

At 1PM02J, depress EH PP LO PRESS AUTO START TEST (20/MPT) pushbutton.

o Equipment Operator locally verify 1B EH pump started.

Perform the following at 1PM02J:

Verify annunciator 1-18-B15, EH SYSTEM TROUBLE, remained clear.

Place 1B EH pump C/S in AFTER CLOSE.

Notify Equipment Operator at EH skid of pending 1A EH pump shutdown

At 1PM02J, place 1A EH pump C/S in AFTER TRIP.

Equipment Operator locally verify EH pressure 2000 +/- 50 psig.

Notify Equipment Operator at EH skid of pending 1A EH pump start

At 1PM02J, depress EH PP LO PRESS AUTO START TEST (20/MPT) pushbutton o Equipment Operator locally verify 1A EH pump started.

Perform the following at 1PM02J:

Verify annunciator 1-18-B15, EH SYSTEM TROUBLE, remained clear.

Place 1A EH pump C/S in AFTER TRIP.

Equipment Operator locally verify EH pressure 2000 +/- 50 psig.

Record initial data on Data Sheet D-2.

Inform US 1BwOS EH-M1 complete.

US

Acknowledge report.

o Notify SM 1BwOS EH-M1 is complete.

EVALUATOR NOTE: After 1BwOS EH-M1 is complete and with lead examiner concurrence, enter next event.

Comments:

NRC 09-5 Page 6 of 23

Scenario NRC 09-5 Event 2 No: No.

Event Lower power 125 MW at 3 MW/min

==

Description:==

Time Position Applicants Actions or Behavior CUE

Call from Power Team to lower power 125 MW at 3 Mw/min.

US

Acknowledge request to lower power 125 MW at 3 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.

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

RO

Verify rod position and boron concentration.

Initiate boration, if required. (BwOP CV-6) (approximate: 115-202 gal).

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:

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 Comments:

NRC 09-5 Page 7 of 23

Scenario NRC 09-5 Event 2 No: No.

Event Lower power 125 MW at 3 MW/min

==

Description:==

Time Positio Applicants Actions or Behavior n

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 Pressurizer backup heater group 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.

RO/

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 09-5 Page 8 of 23

Scenario NRC 09-4 Event 3 No: No.

Event 1TK-130 Failure

==

Description:==

Time Position Applicants Actions or Behavior Event CUE

Annunciator LETDWN TEMP HIGH (1-9-E2) 3

Annunciator LETDWN HX OUTLET TEMP HIGH (1-8-C5)

1TI-130 indicates letdown temperature high

1CV-129, demin high temp letdown divert valve, in VCT position RO

Recognize 1TK-130 output failed low.

CREW o Refer to BwARs as time permits US

Direct/Ensure RO takes manual control of 1TK-130 and returns letdown temperature to normal.

Inform SM and ask for IR and additional personnel for assistance.

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

Inform US of Letdown High temperature divert valve status US o Direct RO to place divert valve to DEMIN position o May contact chemistry to determine if demin should be returned to service. If chemistry contacted, direction will be provided to leave demin bypassed pending sampling Note: The crew may elect to isolate letdown based on elevated temperature. The steps for isolating and restoring letdown are in italics below.

RO o Establish normal letdown per BwOP CV-17

/BOP o Verify/close 1CV8149A/B/C o Verify CC aligned to letdown Hx (was previously aligned) o Place 1CV131 manual at 30% demand o Place 1CC130 in manual at 60% demand o Open 1CV8152/8160 o Open 1CV459/460 o Verify open 1CV8324B & 1CV8389B o Verify/open 1CV381B o Verify/close 1CV381A o Verify/open 1CV8401A o Verify/close 1CV8145 o Verify/open 1CV8146/8147 Comments:

NRC 09-5 Page 9 of 23

Scenario NRC 09-4 Event 3 No: No.

Event 1TK-130 Failure

==

Description:==

Time Position Applicants Actions or Behavior o Open 1SI8105/8106 o Adjust charging flow to approx. 100 gpm w/seal injection 8-10 gpm per RCP o Open 1CV8149A/B/C and control 1CV131 to maintain letdown pressure 360-380 psig o Control 1CC130 to maintain letdown temperature 90-115°F o Place controllers in auto o Verify 1PR06J in service 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 09-5 Page 10 of 23

Scenario NRC 09-5 Event 4 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)

RO/

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:

NRC 09-5 Page 11 of 23

Scenario NRC 09-5 Event 5 No: No.

Event Pressurizer pressure channel 1PT-455 fails low.

==

Description:==

Time Positio Applicants Actions or Behavior n

CUE

Annunciator PZR PRESS LOW RX TRIP STPT ALERT (1-12-A1)

Annunciator PZR PRESS LOW (1-12-B1)

Annunciator PZR PRESS CONT DEV LOW HTRS ON (1-12-C1)

Annunciator OTT HIGH ROD STOP C-3 (1-10-C5)

Annunciator OTT HIGH RX TRIP ALERT (1-14-B1)

PZR pressure indicators 456/457/458 rising

Master PZR pressure controller demand lowering RO

Identify/report failure of 1PT-455 o Take manual control to restore PZR pressure o Place 1PK-455A in manual and raise demand prior to PZR PORVs automatically opening CREW o Refer to BwARs as time permits.

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

US

Notify SM of plant status and procedure entry.

o 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/boration.

RO

Check PZR pressure at 1PM05J:

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

Manually restore PZR pressure using 1PK-455A.

o Select operable PZR pressure control channel o Place 1PK-455A in manual and restore PZR pressure to normal.

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

Comments:

NRC 09-5 Page 12 of 23

Scenario NRC 09-5 Event 5 No: No.

Event Pressurizer pressure channel 1PT-455 fails low.

==

Description:==

Time Positio Applicants Actions or Behavior n

RO

Check PZR PORVS, spray valves, and heaters at 1PM05J:

PZR PORVs closed.

PZR spray valves normal for plant conditions.

PZR heaters normal for plant conditions.

Check PZR pressure control in auto at 1PM05J:

Check the following components in AUTO:

PZR PORV 1RY455A

PZR PORV 1RY456

PZR spray valve 1RY455B

PZR spray valve 1RY455C

Master PZR pressure controller 1PK-455A.

Select operable recorders at 1PM05J:

Place PZR pressure select switch to CH-456, CH-457, or CH-458.

Place loop T recorder select switch to 1B, 1C, or 1D.

RO

Check P11 interlock at 1PM05J:

RCS pressure >1930 psig - P11 NOT LIT.

US

Determine TS 3.3.1, conditions A, E, and K, 3.3.2, conditions A and D, and 3.3.4, condition A are applicable.

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

o May reference 1BwOSR 3.3.4.1 as part of channel applicability determination.

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

Comments:

NRC 09-5 Page 13 of 23

Scenario NRC 09-5 Event 6 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 09-5 Page 14 of 23

Scenario NRC 09-5 Event 7&8 No: No.

Event Loss of bus 141/Rx trip/SI/1D SGTR

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator OT DT RX TRIP (1-11-B4) o Annunciator PZR PRESS LOW SI/RX TRIP (1-11-C1)

Annunciator BUS 141 FD BRKR1412 TRIP (1-21-A7)

Breaker 1412 open light lit at 1PM01J.

Bus 141 bus alive light NOT lit at 1PM01J.

Reactor trip indications at 1PM05J.

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

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 to establish the following conditions:

RO 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:

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 bus 141 - DEENERGIZED.

o Perform 1BwOA ELEC-3 (bus 141 faulted).

ESF bus 142 - ENERGIZED.

Comments:

NRC 09-5 Page 15 of 23

Scenario NRC 09-5 Event 7&8 No: No.

Event Loss of bus 141/Rx trip/SI/1D SGTR

==

Description:==

Time Position Applicants Actions or Behavior EVALUATOR NOTE: The US may direct the BOP to perform 1BwOA ELEC-3 while continuing in 1BwEP-0.

CREW

Check SI Status at 1PM05J:

SI First OUT annunciator - LIT.

SI ACTUATED Permissive Light - LIT.

SI Equipment - AUTOMATICALLY ACTUATED

Manually actuate SI at 1PM05J & 1PM06J.

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.

Trip all running HD 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 Comments:

NRC 09-5 Page 16 of 23

Scenario NRC 09-5 Event 7&8 No: No.

Event Loss of bus 141/Rx trip/SI/1D SGTR

==

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 NOTE: For the A train pumps and valves that have lost power the crew should acknowledge that they are not in the required position, but cannot correct.

RO/

Verify ECCS pumps running at 1PM05J/1PM06J:

BOP

CV pumps - 1B RUNNING.

RH pumps - 1B RUNNING.

SI pumps - 1B RUNNING.

RO/

Perform the following at 1PM06J:

BOP

RCFCs running in accident mode (1B train ONLY running)

RCFC accident mode status light lit

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

Dispatch EO to close de-energized valves outside containment Comments:

NRC 09-5 Page 17 of 23

Scenario NRC 09-5 Event 7, 8 & 9 No: No.

Event Loss of bus 141/Rx trip/SI/1D SGTR/1B SX pump fail to auto start

==

Description:==

Time Position Applicants Actions or Behavior RO/

Perform the following at 1PM06J:

BOP

Verify Cnmt Vent isolation:

Group 6 Cnmt Vent Isol monitor lights - LIT.

Verify AF system:

AF pumps - 1B AF pump RUNNING.

AF isolation valves - 1AF13A-H OPEN. (1AF013A-D are deenergized)

AF flow control valves - 1AF005A-D are OPEN (no flow), 1AF005E-H are THROTTLED.

Verify CC pumps running:

1B CC pump - RUNNING

Verify SX pumps running:

[CT]

NONE RUNNING.

E-0--L

Start 1B SX pump.

RO/

Check if Main Steamline Isolation required:

BOP o S/G pressures > 640 psig at 1PM04J (if turbine tripped prior to setpoint).

o CNMT pressure < 8.2 psig at 1PM06J.

RO/

Check CS not required:

BOP

CNMT pressure remained < 20 psig.

RO/

Verify Total AF flow:

BOP

AF flow > 500 gpm o If 1D SG levels > 10% and tube rupture is recognized then:

o Cannot CLOSE 1AF013D (no power available) o CLOSE 1AF005D and dispatch operator to gag valve closed.

o CLOSE 1AF013H RO/

Verify ECCS valves aligned BOP

Group 2 cold leg injection monitor lights lit (1B train valves LIT).

Verify ECCS FLOW

> 100 gpm on indicator 1FI-917 Comments:

NRC 09-5 Page 18 of 23

Scenario NRC 09-5 Event 7, 8 & 9 No: No.

Event Loss of bus 141/Rx trip/SI/1D SGTR/1B SX pump fail to auto start

==

Description:==

Time Positio Applicants Actions or Behavior n

RO

Check PZR PORVs and SPRAYs:

PORVs CLOSED.

PORV isolation valves - 1RY8000B ENERGIZED

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

Normal Spray valves CLOSED.

RO/

Check RCS Temperature BOP o RCPs running o Tave at or trending to 557°F o RCPs NOT running o Tcold at or trending to 557°F o Throttle AF to control cooldown.

RO/

Verify RCPs running.

BOP

Verify RCP trip criteria NOT met.

RO/

Check if SG secondary boundaries are intact.

BOP

Verify NO SG depressurizing uncontrollably or completely depressurized.

RO/

Check if SG tubes are intact.

BOP

Recognize 1PR27J and 1AR23J indicate high rads.

CREW Identify entry conditions for 1BwEP-3, STEAM GENERATOR TUBE RUPTURE.

US

Notify SM of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Request STA evaluation of status trees.

Comments:

NRC 09-5 Page 19 of 23

Scenario NRC 09-5 Event 8 No: No.

Event 1D SGTR

==

Description:==

Time Position Applicants Actions or Behavior US

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

RO/

Check Status of RCPs:

BOP

RCPs - running.

Identify ruptured SG 1D RO/ 1D Main steam line rad monitor ABNORMAL for plant conditions BOP 1D SG level rising uncontrollably.

Isolate ruptured SG

Verify 1MS018D CLOSED (controller de-energized)

Verify 1SD002C & D CLOSED

CLOSE MSIV and MSIV bypass valves for 1D SG

Check ruptured SG level - Narrow Range > 10%

[CT]

Verify/close 1AF013H - may have already been closed in 1BwEP-0.

E-3--A

Set controller for 1AF005D to 0%

Dispatch equipment operator to locally close 1AF005D RO/

Check ruptured SG pressure > 320 psig BOP US

Specify RCS temperature to which the RCS must be cooled down to allow depressurization of the RCS to ruptured SG pressure.

RO/

Dump steam at maximum rate via:

BOP o Steam dumps in steam pressure mode o Intact SG PORVs

Block MS Isolation after P-11 reached

Bypass Steam Dump P-12 interlock when setpoint is reached by holding steam dump off/reset switch in bypass.

RO/

Check intact SG levels BOP

Control Aux feed flow to maintain intact SG levels Between 30% and 50%

RO/

Check PZR PORVs and ISOL Valves:

BOP

PORVs CLOSED.

PORV isolation valves - 1RY8000B ENERGIZED

PORV isolation valves OPEN RO/

Reset SI BOP

Depress BOTH SI Reset Pushbuttons at 1PM06J Comments:

NRC 09-5 Page 20 of 23

Scenario NRC 09-5 Event 8 No: No.

Event 1D SGTR

==

Description:==

Time Position Applicants Actions or Behavior

Verify SI ACTUATED BP light NOT lit at 1PM05J

Verify AUTO SI BLOCKED BP light lit at 1PM05J Comments:

NRC 09-5 Page 21 of 23

Scenario NRC 09-5 Event 8 No: No.

Event 1D SGTR

==

Description:==

Time Position Applicants Actions or Behavior RO/

Reset Phase A BOP

Depress BOTH Phase A Reset Pushbuttons at 1PM06J RO/

Restore IA to Cnmt BOP

Verify a station air compressor is running at 0PM01J

OPEN 1IA065 and 1IA066 at 1PM11J RO/

Check if RH pumps should be stopped BOP

Check RCS pressure > 325 psig

Stop 1B RH pump RO/

Check if RCS cooldown should be stopped BOP

Check CETCs < required temperature

Reduce steam flow from steam dumps or intact SG PORVs

Maintain CETCs < required temperature

Check ruptured SG pressure stable or rising

Check RCS subcooling acceptable RO/

Depressurize RCS to refill Pzr BOP

OPEN PZR sprays/1 PZR PORV at 1PM05J until any of the following are met:

[CT] o RCS press < ruptured SG press and PZR level > 14%

E-3--C o PZR level > 68%

o RCS subcooling is unacceptable

CLOSE PZR sprays/1 PZR PORV at 1PM05J

Check RCS pressure rising RO/

Check if ECCS flow should be terminated BOP

Check subcooling acceptable

Check Aux feed flow >500 gpm OR NR level in 1 intact SG >10% level

Check RCS pressure rising

Check Pzr level >14%

Stop ECCS pumps

Stop 1B SI pump RO/

Terminate high-head ECCS & establish charging flow BOP

Depress BOTH SI recirc sump reset pushbuttons at 1PM06J

Depress BOTH CV pump recirc valve reset pushbuttons at 1PM05J

Check CV pump recirc valves OPEN at 1PM05J

1CV8110, 1CV8111, 1CV8114, 1CV8116 Comments:

NRC 09-5 Page 22 of 23

Scenario NRC 09-5 Event 8 No: No.

Event 1D SGTR

==

Description:==

Time Positio Applicants Actions or Behavior n

RO/

CLOSE 1SI8801B at 1PM05J (1SI8801A did not open, no power)

BOP

Place 1CV182 controller demand at 0% (controller is de-energized)

OPEN 1CV8105 at 1PM05J (1CV8106 did not close, no power)

Adjust 1CV121 and 1CV182 to maintain desired charging and seal injection flow.

NOTE: Scenario may be terminated at this point (Final)

Comments:

NRC 09-5 Page 23 of 23

Simulation Facility Braidwood Scenario Operating Test No.:2009-1 No.:

NRC 09-spare Examiners: ______________________ Applicant: ____________________ SRO

______________________ ____________________ RO

______________________ ____________________ BOP Initial Conditions: IC-21 Turnover:

Unit 1 is operating at 100% power, steady state, equilibrium xenon, Boron concentration is 800 ppm. Online risk is green. Following completion of turnover, the shift manager requests the BOP to start the 0B WS pump in accordance with BwOP WS-1, STARTUP AND OPERATION OF THE NON-ESSENTIAL SERVICE WATER SYSTEM, and secure the 0C WS pump in accordance with BwOP WS-3, SHUTDOWN OF A NON-ESSENTIAL SERVICE WATER PUMP, for an upcoming clearance order on the 0C WS pump. Align the 0C WS pump for standby after it is secured. Operators have been briefed and are standing by at the Lake Screen House to support WS pump swap.

Event Malf. No. Event Event No. Type* Description Preload IMF FW44 1B AF Pump fails to start IMF FW48A 1A AF Pump auto start failure IMF RP02A Reactor trip breaker A fails to open IMF RP02B Reactor trip breaker B fails to open 1 None N-BOP, US Swap WS pumps 2 None R-RO, US Emergency load drop of 100 MW 3 IMF RX03G 0 20 I-BOP, US Steam Flow channel 1FT542 fails low 4 IMF CV01A C-RO, US 1A CV pump trip TS, US 5 IMF RH05A 0 5 TS, US RWST level channel failure 6 IMF TH16C M-ALL 1C RCP Trip/ATWS 7 IOR ZDIRMIO NEUTRAL C-RO, US Control rods will not insert (must emergency IOR ZDIBKSEL MAN borate) 8 Preload C-BOP, US 1A AF pump auto start failure/1B AF fail to start

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

SCENARIO OVERVIEW Unit 1 is operating at 100% power, steady state, equilibrium xenon, Boron concentration is 800 ppm. Online risk is green. Following completion of turnover, the shift manager requests the BOP to start the 0B WS pump in accordance with BwOP WS-1, STARTUP AND OPERATION OF THE NON-ESSENTIAL SERVICE WATER SYSTEM, and secure the 0C WS pump in accordance with BwOP WS-3, SHUTDOWN OF A NON-ESSENTIAL SERVICE WATER PUMP, for an upcoming clearance order on the 0C WS pump. Align the 0C WS pump for standby after it is secured. Operators have been briefed and are standing by at the Lake Screen House to support WS pump swap.

After completing shift turnover and relief, the BOP will swap WS pumps in accordance with BwOP WS-1 and BwOP WS-3.

After swapping WS pumps, contact Unit 1 on the TSO phone as Bill Collins and direct Unit 1 to complete an emergency load reduction of 100 MW within 30 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.

After a measurable change in power, a failure of 1FT-542 will occur. The crew will enter 1BwOA INST-2 and perform appropriate actions. The crew should swap to an operable steam flow channel. No Technical Specification applies. On-line risk remains green. If reactor power exceeds 100% due to the secondary transient, the crew will implement 1BwOA PRI-16, RESPONSE TO REACTOR OVERPOWER CONDITION to restore reactor power below 100%.

Following completion of 1BwOA INST - 2 actions, 1A CV pump will trip. The crew will implement 1BwOA PRI-15, LOSS OF NORMAL CHARGING. The crew will start the 1B CV pump to restore normal charging.

Technical Specifications 3.5.2 condition A and TRM 3.1.d, condition A apply.

After the 1A CV pump is addressed, RWST level channel 1LT930 will fail low. The crew will enter 1BwOA INST-2 Attachment S. Technical Specifications 3.5.2 conditions A and K apply.

After the RWST level channel failure is addressed, 1C RCP will trip. The reactor will not automatically trip and when a manual reactor trip is attempted, the reactor will not trip, resulting in an ATWS. The crew will implement 1BwFR-S.1, RESPONSE TO NUCLEAR GENERATION/ATWS. The control rods will not insert in either automatic or manual. The RO will initiate emergency boration to add negative reactivity to the core. The 1B AF pump will not start and the 1A AF pump will have to be manually started. After completing actions of 1BwFR-S.1, the crew will transition to 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION.

The scenario is complete when the crew completes step 4 of 1BwEP-0.

Critical Tasks

1. Start 1A AF pump prior to completion of step 3 of 1BwFR-S.1 (ERG Critical Task number - FR-S.1--B) (K/A number -061000A2.04 importance - 3.4/3.8)

2. Insert negative reactivity into the core by establishing emergency boration flow to the RCS prior to completion of step 4 of 1BwFR-S.1.

(ERG Critical Task number - FR-S.1--C) (K/A number - 029000 2.2.44 importance - 4.2/4.4)

Braidwood NRC 09-spare Page 2 of 20

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.

Run caep NRC 09-spare SETUP from disk and verify the following actuate:

IMF FW44

IMF FW48A

IMF RP02A

IMF RP02B

Verify/Set I Target Curve slopes to +2% of I.

Verify SER and printer are clear of data.

Verify 5 MW load drop at 5 MW/minute is programmed into DEH.

Provide students with turnover sheets, 1BwOS NR-1, critical parameter sheet, and copies of BwOP WS-1 and BwOP WS-3.

Braidwood NRC 09-spare Page 3 of 20

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 1: Swap WS pumps.

If contacted as Equipment Operator for WS pump swap, report 0B WS pump is aligned for start and you are ready for the control room to start 0B WS pump in accordance with BwOP WS-1, step F.3.c.

If contacted as Equipment Operator for WS pump swap, report 0B WS pump has stable operating parameters once running, and no signs of reverse rotation from the 0C WS pump when the 0C WS pump is stopped.

Acknowledge as Shift Manager commencement and completion of procedure.

Event 2: Emergency load drop.

Contact Unit 1 on the TSO phone as Bill Collins and direct Unit 1 to complete an emergency load reduction of 100 MW within 30 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.

Acknowledge as Shift Manager initiation of load reduction.

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

Acknowledge as Power Team initiation of ramp.

Event 3: Steam Flow detector 1FT-542 failure NOTE: Ensure Rx Power is <99% prior to inserting next malfunction.

Insert IMF RX03G 0 20 As SM, acknowledge failure of 1FT-542, dequip entry, and requests for on line risk assessment, maintenance support, and IR initiation and evaluation for full power restoration.

As SM, acknowledge request for personnel notifications.

Braidwood NRC 09-spare Page 4 of 20

INSTRUCTOR/SIMULATOR RUN AID GUIDE Event 4: 1A CV pump trip Insert IMF CV01A for 1A CV pump.

If dispatched as Equipment Operator to 1A CV pump and/or pump breaker, wait three minutes and report 1A 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 5: RWST Level Channel Failure 1LT-930 Insert IMF RH05A 0 5 Acknowledge as Shift Manager the failure, LCOAR entry, on line risk assessment, EAL evaluation, request for maintenance support, and IR request.

As SM, if requested support for tripping bistables, report that bistables are not to be tripped until work analyst/NSO support can be obtained (i.e. not at this time) and that the abnormal operating procedure should be continued. Bistable tripping will be conducted later.

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

MRF RP20 OPEN (open protection cabinet #1 door)

MRF RH18 TRIP (trip RWST lo-2 level bistable 1LS-930C)

MRF RP20 CLOSE (close protection cabinet #1 door)

Events 6 & 7: 1C RCP Trip/ATWS/ Control rods will not insert Run caep NRC 09-spare EVENTS 5 & 6 from disk and verify the following actuate:

IMF TH16C

IOR ZDIRMIO NEUTRAL

IOR ZDIBKSEL MAN If dispatched as Equipment Operator to locally trip Unit 1 reactor, wait until 1BwFR-S.1 step 7 (VERIFY 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 Braidwood NRC 09-spare Page 5 of 20

If dispatched as Equipment Operator /Field Supervisor to verify dilution paths isolated, wait 15 minutes and report the following: 1CV8441, 1CV8435, & 1CV8453 are locked closed. 1AB8629A is closed.

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

After STA requested, as STA report CSF status: red on subcriticality until PR channels < 5%. Red on heat sink if 1A AF pump is not manually started and SG NR level <10%.

Event 8: 1A AF Pump auto start failure/1B AF Pump fails to start If dispatched as Equipment Operator to 1B AF pump, report low oil pressure annunciator is lit on 1AF01J and there is a puddle of oil beneath the 1B AF pump engine.

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

Braidwood NRC 09-spare Page 6 of 20

Scenario NRC 09-spare Event 1 No: No.

Event Swap WS Pumps

==

Description:==

Time Position Applicants Actions or Behavior CUE o From turnover, start the 0B WS pump in accordance with BwOP WS-1, STARTUP AND OPERATION OF THE NON-ESSENTIAL SERVICE WATER SYSTEM, and secure the 0C WS pump in accordance with BwOP WS-3, SHUTDOWN OF A NON-ESSENTIAL SERVICE WATER PUMP.

US

Direct BOP to perform BwOP WS-1 and BwOP WS-3.

BOP

Refer to BwOP WS-1.

Contact Equipment Operator at 0B WS pump to verify 0B WS pump is ready for start.

Start 0B WS pump at 0PM01J.

Check 0B WS pump amps and WS system pressure normal.

o Contact Equipment Operator at 0B WS pump to verify normal pump parameters.

Contact Equipment Operator at 0B WS pump to align chemical feed to 0B WS pump.

Refer to BwOP WS-3.

Contact Equipment Operator at 0C WS pump to isolate chemical feed to 0C WS pump.

Place 0C WS pump C/S to PULL OUT.

Contact Equipment Operator at 0C WS pump to determine if 0C WS pump shaft is not rotating backwards.

Verify WS header pressure is stable.

Place 0C WS pump C/S in AFTER TRIP.

Contact Equipment Operator at 0C WS pump to complete 0C WS pump shutdown.

Inform US WS pumps have been swapped.

US

Acknowledge report.

o Notify SM WS pump swap is complete.

NOTE: After WS pump swap is complete and with lead examiner concurrence, enter next event.

Comments:

NRC 09-spare Page 7 of 20

Scenario NRC 09-spare Event 2 No: No.

Event Emergency load drop of 100 MW

==

Description:==

Time Position Applicants Actions or Behavior CUE

Call from Power Team to perform emergency load drop of 100 MW.

US

Acknowledge request to lower power 100 MW.

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

Review applicable Precautions, and Limitations and Actions of 1BwGP 100-4.

EVALUATOR NOTE: The following step may be repeated as necessary to borate the RCS during the power descension.

RO

Verify rod position and boron concentration.

Initiate boration, if required. (BwOP CV-6) (approximate 134-202 gal).

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:

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 Comments:

NRC 09-spare Page 8 of 20

Scenario NRC 09-spare Event 2 No: No.

Event Emergency load drop of 100 MW

==

Description:==

Time Position Applicants Actions or Behavior RO

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 in accordance with BwOP RY-14, PRESSURIZER BACKUP HEATER OPERATION.

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 desired 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.

RO/

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.

EVALUATOR NOTE: After measurable change in power and with lead examiner approval, insert the next event.

Comments:

NRC 09-spare Page 9 of 20

Scenario NRC 09-spare Event 3 No: No.

Event Steam Flow channel 1FT542 fails low

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator SG 1D FLOW MISMATCH STM FLOW LOW (1-15-D3)

Annunciator SG 1D FLOW MISMATCH FW FLOW LOW (1-15-D4)

Annunciator SG 1D LEVEL DEVIATION HIGH LOW (1-15-D9)

1FI542A flow indicator fails low.

1D SG level indicators 1LI547/548/549/559 indicate lowering level RO/

Determine 1FT-542 failed Low.

BOP

Reference BwARs as time permits.

CREW

Identify entry conditions for 1BwOA INST-2, OPERATION WITH 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 FAILED INSTRUMENT CHANNEL - ATTACHMENT H and direct operator actions of 1BwOA INST-2 to establish the following conditions:

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

Stabilize 1D SG level If SG level abnormal

Control 1D FRV (1FW540) in manual

Place master feed pump speed control in manual

Verify adequate feedwater DP

Restore SG level(s)

Select operable steam flow channel

Establish/verify automatic SG level control

Verify steam pressure channels normal CREW

Check Rx Power <100%

US

Contact SM/maintenance to investigate/correct the failed steam flow channel

Determines TS is NOT applicable.

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

Contact SM or make appropriate personnel notifications.

EVALUATOR NOTE: After the actions for the failed steam flow channel are complete and with lead examiner concurrence, insert the next event.

Comments:

NRC 09-spare Page 10 of 20

Scenario NRC 09-spare Event 4 No: No.

Event 1A 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 LTDN TEMP HIGH

PZR level lowering.

Trip/yellow disagreement light on 1A CV pump C/S.

RO

Identify 1A 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.

Identify entry conditions for 1BwOA PRI-15, LOSS OF NORMAL CHARGING.

Dispatch operator to investigate cause of 1A CV pump trip.

US

Notify Shift Manager of plant status and procedure entry.

Request evaluation of Emergency Plan conditions.

Implement 1BwOA PRI-15, LOSS OF NORMAL CHARGING, and direct operator actions of 1BwOA PRI-15 to establish the following conditions:

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

o Enter Tech Spec 3.4.1 if PZR pressure < 2209 psig.

RO

Perform the following at 1PM05J:

Check CV pump status:

Identify NEITHER CV pump is running

Place 1A 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.

o Acknowledge RM-11 alarm caused by isolating flow to 1PR06J, Gross Failed Fuel Monitor.

Check VCT status:

Check 1CV112B & 1CV112C, VCT suction valves, OPEN.

Maintain VCT level greater than 20%.

Comments:

NRC 09-spare Page 11 of 20

Scenario NRC 09-spare Event 4 No: No.

Event 1A CV pump trip.

==

Description:==

Time Position Applicants Actions or Behavior

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.

RO/

Perform the following at 1PM05J:

BOP

Check for gas binding of previously running CV pump by verifying the following trends NOT fluctuating prior to pump trip (may use HMI trends):

RCP #1 seal leak off flow.

CV pump flow.

CV pump discharge pressure.

CV pump amps.

Restore normal charging flow:

Check 1CV8110 & 1CV8116, 1B CV pump miniflow isolation valves - OPEN.

Check RCS pressure approximately 2235 psig.

Place 1B CV pump C/S to start.

Check CV System Alignment:

Verify 1CV8147, charging to RC 1A 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:

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.

Comments:

NRC 09-spare Page 12 of 20

Scenario NRC 09-spare Event 4 No: No.

Event 1A CV pump trip.

==

Description:==

Time Position Applicants Actions or Behavior

Verify 1CV459 & 1CV460, letdown isolation valves - CLOSED.

Comments:

NRC 09-spare Page 13 of 20

Scenario NRC 09-spare Event 4 No: No.

Event 1A CV pump trip.

==

Description:==

Time Position Applicants Actions or Behavior 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 lower 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.

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

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.

Comments:

NRC 09-spare Page 14 of 20

Scenario NRC 09-spare Event 4 No: No.

Event 1A CV pump trip.

==

Description:==

Time Position Applicants Actions or Behavior EVALUATOR NOTE: After the actions for charging pump trip are complete and with lead examiner concurrence, enter next event.

Comments:

NRC 09-spare Page 15 of 20

Scenario NRC 09-spare Event 5 No: No.

Event RWST level channel failure 1LT-930

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator RWST LEVEL LO-3 (1-6-A7)

Annunciator RWST LEVEL LO-2 (1-6-B7)

Annunciator RWST LEVEL LOW (1-6-C7)

Level Indicator 1LI-930 Failed Low RO/

Determine 1LI-930 failed low.

BOP

Reference BwARs as time permits.

CREW

Identify entry conditions for 1BwOA INST-2, OPERATION WITH 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 FAILED INSTRUMENT CHANNEL, Attachment S, RWST LEVEL LOW LOW COINCIDENCE WITH SI.

Determines TS 3.3.2 condition A and K are applicable.

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

EVALUATOR NOTE: After the actions for the 1LT-930 failure are complete and with lead examiner concurrence, insert the next event.

Comments:

NRC 09-spare Page 16 of 20

Scenario NRC 09-spare Event 6&7 No: No.

Event 1C RCP trip/ATWS/ control rods will not insert

==

Description:==

Time Position Applicants Actions or Behavior CUE

Annunciator 1-11-C5, RCP LOW FLOW ABOVE P8 RX TRIP

Annunciator 1-13-C3, RCP 1C BRKR OPEN OR FLOW LOW ALERT

Annunciator 1-13-E3, RCP TRIP

Trip/yellow disagreement light on 1C RCP C/S.

CREW

Identify 1C RCP tripped.

Identify reactor did NOT automatically trip.

US

Notify SM of plant status.

Direct operator to manually trip reactor.

RO

Manually trip the reactor:

Place RX trip switch to TRIP at 1PM05J.

Place RX trip switch to TRIP at 1PM06J.

Determine reactor will NOT manually trip.

CREW

Identify entry conditions for 1BwFR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS.

Dispatch operator to locally trip reactor.

RO Perform immediate operator actions of 1BwFR-S.1:

Verify reactor trip:

Rod bottom lights - NONE LIT.

Reactor trip breakers - CLOSED.

Neutron flux - NOT DROPPING.

Manually trip the reactor (N/A if previously attempted):

Place RX trip switch to TRIP at 1PM05J.

Place RX trip switch to TRIP at 1PM06J.

Determine control rods NOT inserting automatically.

Attempt to manually insert control rods:

Place rod bank select switch to MANUAL.

Place rod control in-hold-out switch to IN.

Determine rods NOT inserting manually.

Comments:

NRC 09-spare Page 17 of 20

Scenario NRC 09-spare Event 6, 7, & 8 No: No.

Event ATWS/control rods will not insert/1A AF pump auto start failure/1B AF fail to start

==

Description:==

Time Position Applicants Actions or Behavior BOP Perform immediate operator actions of 1BwFR-S.1 at 1PM02J or OWS drop 210:

Verify Turbine Trip:

All Turbine throttle valves - CLOSED.

All Turbine governor valves - CLOSED.

BOP

Check AF pumps running:

AF pump run lights - NONE LIT.

[CT]

Manually start the 1A AF pump prior to completion of step 3 of 1BwFR-S.1.

FR-S.1-

Attempt to manually start 1B AF pump.

-B

Determine 1B AF pump will not start.

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.

RO/

Initiate emergency boration of the RCS at 1PM05J:

BOP

1B CV pump - RUNNING.

Place 1CV8104, EMERGENCY BORATION VALVE, C/S to OPEN.

[CT]

Start boric acid transfer pump.

FR-S.1-

Verify emergency boration flow > 30 gpm on 1FI-183A.

-C

Verify charging flow > 30 gpm on 1FI-121A.

Verify PZR pressure < 2335 psig on 1PI-455A/456/457/458.

o If PZR pressure rises > 2335 psig, verify PZR PORVs cycle as necessary to maintain PZR pressure 2135-2335 psig.

BOP

Verify CNMT vent isolation:

Group 6 CNMT vent isolation monitor lights - ALL LIT at 1PM06J.

RO

Check if the following trips have occurred:

Reactor trip at 1PM05J - NOT TRIPPED

Turbine trip at 1PM02J or OWS drop 210:

All Turbine throttle valves - CLOSED.

All Turbine governor valves - CLOSED.

Verify reactor subcritical at 1PM05J:

All PR channels < 5% (power may still be >5%).

All IR channels - NEGATIVE SUR.

Comments:

NRC 09-spare Page 18 of 20

Scenario NRC 09-spare Event 6, 7, & 8 No: No.

Event ATWS/control rods will not insert/1A AF pump auto start failure/1B AF fail to start

==

Description:==

Time Position Applicants Actions or Behavior RO/ o Check SG levels at 1PM04J:

BOP

At least one SG level > 10% (31%).

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

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

o Verify dilution paths isolated at 1PM05J:

1CV111A & B - CLOSED.

BTRS mode selector switch - OFF.

Dispatch operator to locally verify dilution paths isolated.

o Stop reactivity insertion from RCS cooldown:

RCS temperature not dropping in an uncontrolled manner.

All SG pressures not dropping in an uncontrolled manner.

Note: When the local reactor trip is recognized the crew will go to step 16 of 1BwFR-S.1 (per CAS) and then transition to 1BwEP-0 CREW

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

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.

RO

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.

Comments:

NRC 09-spare Page 19 of 20

Scenario NRC 09-spare Event 6, 7, & 8 No: No.

Event ATWS/control rods will not insert/1A AF pump auto start failure/1B AF fail to start

==

Description:==

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

Check SI actuated at 1PM05J and 1PM06J:

23B o SI ACTUATED Bypass Permissive - NOT LIT.

o SI first out annunciator - NOT LIT.

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

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

Transition to 1BwEP ES-0.1 EVALUATOR NOTE: At this point the scenario is terminated 28B Comments:

NRC 09-spare Page 20 of 20

ML100700255

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