ML022130365
| ML022130365 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 04/08/2002 |
| From: | Bielby M NRC/RGN-III/DRS/OLB |
| To: | |
| References | |
| ER-02-301 | |
| Download: ML022130365 (66) | |
Text
PROPOSED NRC-AUTHORIZED SCENARIOS FOR THE LASALLE INITIAL EXAMINATION - APRIL 2002
LaSalle County Station Operations Scenario #1 Exam Date: April 8, 2002 Developed By: Raymond Keith Walton Date 3 8/2002 Reviewed By: Date
Scenario #1 NARRATIVE
SUMMARY
Current plant operating status.
The unit is at 85% power de.-reasing to perform LOS-RP-Q3, MSTV Scram Functional Test. HPCS is inoperable. During MSJ\ iJnctional test, IA RBCCW pump trouble alarm comes in. 'C' Narrow range level instrument fails :m*scale. This is followed by a trip of the operating 'B' RWCU pump.
A TDRFP runs up to maxin-.:m flow. This is followed by a feedwater line break inside the steam tunnel. RCIC fails to start.
Scenario segments
"* Power decrease (from S,5% to < 82% power for testing)
"* LOS-RP-Q3, MSIV Scrc.rn Functional Test, Inboard MSIV Scram Solenoids will NOT deenergize
"* IA RBCCW pump Suc*::n Strainer high d/p
"* IC Narrow Range Level Instrument fails Upscale
"* 'B' RWCU pump trips
"* IA TDRFP M/A Statio- Fails High
"* FW Break in the Main S:eam Tunnel
"* Scram and LGA entry
"* RCIC fails to start PALasalle Exam\Scenario 1.doc 3
Scenario #1 SHIFT TURNOVER INFORMATION
= Day of week and shift
+ Today, Day Shift
=> Weather conditions
+ Warm
+ Windy
=> (Plant power levels)
- Unit I - 85% Power, 101% FCL Unit 2- 100 % Power, 108.5% FCL
- 2960 MWt 4 3489 MWt
- 945 MWe 1189 MWe
- 85 Mlbmlhr CORE FLOW 4 93 Mlbm/hr CORE FLOW
~ Thermal Limit Problems/Power Evolutions
- None None
= Existing LCOs, date of next surveillance
+ 3.5.1 condition B due to HPCS inop. None
= LOSs in progress or major maintenance
+ Complete LOS-RP-Q3 for I A inboard MSIV
- None
=> Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment
- HPCS 4 None
- lB TDRFP M/A in MANUAL 4
= Comments, evolutions, problems, etc.
+ Online Risk is Yellow
- Online Safety is Green
- 3 CW pumps operating
- 3 CW pumps operating P:\Lasalle Exam\Scenario 1.doc 4
Scenario #1 SIMULATOR SETUP A. CARDS/TAGS TO BE HUNG:
- 1E22-F004,-F015, and -C001 B. MISCELLANEOUS:
Timeclock Board
- 1. HPCS/R 3.5.1 condition E. Make TC Board and turnover sheets reflect 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> left on time clock to be in Mode 3.
C. TURNOVER INSTRUCTIONS:
- Gather the crew in an appropriate classroom setting and turnover sheet to provide a shift turnover. Stress the following items:
- 1. Unit is decreasing power to perform LOP-RP-Q3.
- 2. HPCS is inoperable and OOS
- 3. On the 101% FCL
- 4. Unit 2 at Full Power
- 5. 1B TDRFP is in manual due to control valve oscillations PALasallc Exam\Scenario 1.doc 5
Scenario #I Event 1-1 Initiation: Following Shift turover on the signal of lead examiner Time/Notes Expected Crew Response Power Decrease with Recirculation Flow Reactor Operator Response:
Takes actions to establish a pe; ..er ramp per LGP 1 and LOP-RR-07, to decrease load:
"* VERIFY Manual light on Recirc Loop Flow Controller M/A station A/B is ON.
"* Change Flow evenly in bo-r loops by pressing LOWER button and observing flow indication :-. Flow controller M/A Stations.
"* REDUCE core flow to app.-oximately 70 Mlbm/hour using Attachment C unless other-.1. ise directed by the QNE
"* At a rate up to 100 MNVe/hour
"* At a higher rate specifiel by a QNE BOP Operator Response:
"* REMOVE condensate polishers from service when no longer needed per LOP-CP-03
", MAINTAIN condensate flew through the polishers per LOP-CD-03 Unit Supervisor Response:
0 DIRECTS crew to reduce 7ower at <100 MWe/hour to <82% power using recirculation flow
- Notifies Electric Operations of power reduction
- DIRECTS crew to hold powver drop below 82% to complete LOS-RP-Q3 TERMINUS: Clearly observable plant response from change in power level.
PALasalle Exain\Sccnariol .doc 6
Scenario #I Event 1-2 Initiation: Following Shift turnover on signal from lead examiner.
Time/Notes Expected Crew Response Key Event; Perform LOS-RP-Q3 MSIV Scram Functional Test BOP Operator Response:
Takes actions to perform LOS-RP-Q3, MSIV Scram Functional Test for IA inboard MSIV and LA outboard MSIV:
"* VERIFIES Rx Power <82%, all MSIV switches in AUTO, Scrams RESET, and MSIV Relays energized.
"* One at a time, places lA inboard MSIV control Sw. in OPEN SLOW TEST
"* Depresses and Holds PB until 2 relays deenergize or for about 10 sec.
After receiving dual indication.
"* Then Releases PB.
"* VERIFIES 1A inboard MSIV reopens and 2 relays deenergize then reenergize.
"* Checks that lA/1B MSIV inbd/outbd Not Full Open alarm received.
"* Verify IA inboard MSIV open.
"* Verify all MSIV relays energized (1C71A-K3A through K3H).
"* Reset lA/lB MSIV Inbd/Otbd Not Full Open alarm.
"* Place 1B21-F022A, Inbd MSIV control switch in AUTO.
"* Waits 2 minutes to stabilize flows.
"* Repeats above steps with 1A outboard MSIV.
- 1. Except that 2 scram relays do NOT deenergize after holding PB for greater than 10 secs.
Reactor Operator Response:
"* VERIFIES Rx Power <82%, all MSIV switches in AUTO, Scrams RESET, and MSIV Relays energized.
"* Monitors plant parameters for alarms/unusual conditions Unit Supervisor Response:
- HOLDS power decrease to perform MSIV surveillance test
- MONITORs crew performing LOS-RP-Q3
- Refers to TS 3.0.5 TERMINUS: Completion of surveillance test P:\Lasalle Exan\Scenariol .doc 7
Scenario #1 Event 1-3 Initiation: After events 1-1 & 1-2 completed, on signal from lead examiner Time/Notes Expected Crew Response 1A RBCCW Pump Trouble 1PM1OJ-A102, RBCCW Pump Suction Strainer D/P High BOP Operator Response:
RESPONDS to Annunciator PM 10J-A 102:
"* ANNOUNCES annunciator alarm to crew.
"* SHIFT to standby RBCCW pump per LOP-WR-02.
Per LOP-WR-02, "Startup and Operation of RBCCW System:"
"* STARTS lB RBCCW Pump.
"* Observe 'B' RBCCW pump amperes increase to 145 - 172 amps
"* Observe 'B' RBCCW pump discharge header pressure increase to 52 80 psig
"* STOP the 'A' RBCCW pump after the system pressure stabilizes.
Reactor Operator Response:
- Holds reactor power steady at less than 82%.
Unit Supervisor Response:
0 Acknowledges alarm.
Terminus: Starts standby RBCCW pump.
P:ALasalle Exam\Scenariol .doc 8
Scenario #1 Event 1-4 Initiation: After Event 1-3 completed, after cue fr -r. lead examiner.
Time/Notes Expected Crew Response IC NR Level Instrument Fails Upscale Mismatch between IC and LA or lB NR Level IC Level 8 Trip Light Reactor Operator Response:
"* Recognize SPDS display turns RED
"* Recognize CX alarm for selected NR level
"* Recognize disparity between IC Narrow Range and the other two Narrow Range instruments
"* Informs the Unit Supervisor
"* REFERS to LOA-NB- 101, Reactor Vessel Ins,:-mentation Abnormal
"* CHECK redundant indications to identify a-:ual level/pressure
"* Identify suspect incorrect reading instrume-:
"* REFER to Attachment A to identify referer-. leg associated with suspect instrument
"* CHECK indications from other instrument_ -ed from same reference leg
"* Perform channel checks on suspect reactor level/press instruments.
" Check at least one instrument on shared ref.-ience leg outside limits of associated channel checks.
"* Verify proper operation of the RWLC system BOP Operator Response:
- Verifies proper operation of Feed and Condensate System Unit Supervisor Response:
For the failed 1C Narrow Range Level Instrument:
- Declare C Level 8 Switch INOP.
- Reviews Tech Spec 3.3.2.2 , Enters Action Sta-ement
- Contact IMD to investigate transmitter failure.
- Write a condition report Simulator Operator: As IMD, when sent to investigate the Narrow Range Level problem, wait several minutes then report that it appears the equalizing valve on the transmitter is leaking by. It will take about 2 shifts to get the package ready an ,!,P the valve.
TERMINUS: Unit Supervisor has investigated the appropriate Technical Specifications.
PALasalle Exam\Scenario 1.doc 9
Scenario # i Event 1-5 Initiation: After Event 1-4 completed, after cue from lead examiner.
Time/Notes Expected Crew Response 1B RWCU Pump Trips
_......... 1
RESPONDS to Annunciator P602-A 107, B RWCU RECIRC PMP AUTO TRIP:
- ANNOUNCES annunciator alarm to crew.
- VERIFIES 1B RWCU pump trips.
- REFERS to LOA-RT-101, B.2, Loss of RWCU pump:
"* OPEN G33-F354, RWCU Filter Demin Bypass Vlv.
"* Locally place A/B/C Vesse Control Sw to ISOLATE position.
"* Locally check Filter/Demin Vessel Inlet/Outlet Vlvs closed.
"* STARTS 1A RWCU Pump.
Reactor Operator Response:
- Holds reactor power steady at less than 82%.
- Reports any abnormal/unusual conditions/alarms Unit Supervisor Response:
- Acknowledges alarm.
TERMINUS: Starts standby RWCU pump.
P:ALasalle Exam\Scenario 1.doc 10
Scenario #1 Event 1-6 Initiation: After Event 1-5 completed, after cue from lead examiner.
Time/Notes Expected Crew Response 1A TDRFP MI/A Station Fails High IA TDRFP Flow Ramps High IH13-P603-A309 EW Control Rx Vessel Lvl Hi Reactor Operator Response:
Recognize failure of M/A station and takes actions per LOA-FW-101:
"* CHECK Manual Backup Station DIRECT DEMAND SUBSTITUTION or DIRECT VALVE POSITIONING LEDs ILLUMINATED.
"* CONTROL Reactor level by INCREASING/DECREASING turbine speed using SPEED/POSITION ADJUST switch.
- CHECK TDRFP M/A XFER station - OPERABLE
- Manually scram the reactor when level cannot be maintained within the level band given by the Unit Supervisor.
BOP Operator Response:
"* Assist Reactor Operator
"* Monitors status of Feed and Condensate System Unit Supervisor Response:
For the failed M/A Transfer Station:
CRITICAL '*. Give the NSO a level band to maintain SE Authorizes Reactor Operator to scram unit if can not maintain level S
STEP band.
- Prioritize and assign duties (who is in charge of level control, who is monitoring the reactor, etc.)
NOTE: Simulator Operator: Ensure RCIC failure to automatically start has been entered prior to initiating Events 1-7 and 1-8.
i TF"'NUNUS: If unable to r-,inlin RPV water level, scram plant.
If able to in* 2.. M xvater level, after cir' from lead examiner, start Event 1-7 P:\IA.id ic 1 A\ i\Sccnariol .doc I I
Scenario #1 Event 1-7 Initiation: Plant Scrams or after cue from lead examiner.
Time/Notes Expected Crew Response Key Event: FW Break in Steam Tunnel Lowering RPV Level 11H 13-P601-F404 - LD MSL Pipe Tunnel Amb Temp Hi 11H13-P601-1405 - LD MSL Pipe Tunnel Diff Temp Hi FW HDR flow Mis-atch Reactor Operator Response:
Per LGP-3-2, completes the actions of the Scram Hardcard and follows up with the procedure;
- CHECK all Control Rods in and Power Decreasing IINFORM Unit Supervisor Of Rod Status and Reactor Power
- Operate FW as necessary within the level bank 32 to 45 inches
- REPORT to the Unit Supervisor the status (and trend) of RPV Level and Pressure
- VERIFY Reactor Recirculation Pumps have downshifted
- STABILIZE Reactor Pressure <1020 psig
- GO TO Step E. 2 of LGP-3-2 BOP Operator Response:
"* Trip 1 TDRFP and close discharge valve.
"* Start MDRFP. If level can be maintained, trip remaining TDRFP and shut discharge valve.
- Verify Main Generator/Turbine Trip
- STABILIZE Reactor Pressure <1020 psig
- GO TO Step E. 2 of LGP-3-2 Unit Supervisor Response:
- \I ,asalk, ', ia\Scenariol .doc 12
Scenario #1 Key Event 1-8 Initiation: Initiated with key event I-7 Time/Notes Expected Crew Response Key Event 1-7 FW Break in Steam Tunnel (Continued)
RCIC Fails to Start Automatically Panel Operator Response:
Per LGA-00I RPV Level Control Leg
"* CONTROL Level I1 to 59.5 inches using ECCS Systems, (RT, Feedwater and Condensate should be isolated to stop the leak)
"* When level can't be held >-150 inches, then:
"* Maximize injection with all Preferred Injection
"* WAIT until level drops to -150 inches on WR then ENTER LGA-004 RPV Pressure Control Leg
"* Stabilize Pressure Below 1059 psig
"* Depressurize RPV using Turbine Bypass Valves at <l00°F/hour Panel Operator Response:
"* REPORTS that RCIC failed to start.
"* ATTEMPTs to start RCIC manually.
"* RCIC starts but trips less than 1 minute later.
CRITICAL * - Unit Supervisor Response:
C Directs actions per LGA-001 (See RO and BOP Operator Responses STEP above)
NOTE: If the crew is aggressive and uses the "anticipate a blowdown" override of LGA-001, a rapid depressurization with the Turbine Bypass Valves will allow LPCS injection and level recovery before RPV level drops to -150 inches.
P .\I ,, Scenario I (.loc I ý-),
Scenario #1 Time/Notes Expected Crew Response Key Event 1-7 FW Break in Steam Tunnel (continued)
Panel Operator Response:
Per LGA-002
- OPERATE Area Coolers and VR if possible
- If any area Temperature or Radiation is above Max Normal or if a sump is overflowing, then:
"* ISOLATE discharges into the area except for those needed to fight fires or needed by other LGAs (crew should isolate FW, CB/CD and RT)
"* MONITOR release rates for LGA-009 entry conditions
"* WAIT until 2 or more areas are greater than Max Safe and then:
"* SHUTDOWN the Reactor (LGP-3-2), and
"* ENTER LGA-004 (Blowdown)
Per LGA-004
- VERIFY Drywell Pressure is greater than 1.69 psig SCRITICAL
- VERIFY Suppression Pool Level is greater than -18 feet 0 INITIATE ADS (using BOTH pushbuttons)
STEPS
- VERIFY 7 ADS Valves are OPEN
- WAIT until Shutdown Cooling Interlocks clear (135 psig)
- COOLDOWN to Cold Shutdown using Shutdown Cooling (per LOP-RH-07)
Unit Supervisor Response:
- Directs actions per LGA-002, (See Operator Response above)
- Directs actions per LGA-004, (See Operator Response above)
Terminating a Restores and maintains RPV level 11 - 59.5" Conditions
- Commences cooldown at <1000 F/Hr if Emergency Depressurization was not required.
0 Cue from lead examiner P . lIc ,'xamn\Scena:-io I .doc 11ý
S ;,-iario #2 LaSalle County Station Operations Scenario #2 April 8, 2002 Developed By: Raymond Keith Walton Date March 8, 2002 Reviewed By:
. , Exam\swuiao2.Juc I
Scenario #2 NARRATIVE
SUMMARY
Current plant operating status.
A startup is in progress per LGP 1-1. Operators will place 'B' RHR in suppression pool cooling.
C APRM will fail high causing a half scram. Reactor Building Ventilation exhaust fan will trip.
An SRV will stick open but will be reseated after operators remove fuses. The FCV on one RR pump fails open. Subsequent high vibration and a Cooler leak on the RR pump req1sires the operators to manually trip the RR pump. Finally, a small LOCA requires LGA enti to stabilize the plant.
Scenario segments 0 Place 'B' RHR in Suppression Pool cooling
- Reactor Building Ventilation Exhaust fan will trip
- 1A RR Pump High Vibration w/ Winding leakage 0 SmallLOCA P:ALasalle Exam\Sccnaio2.d,2 2
Scenario #2 SHIFT TURNOVER INFORMATION SDay of week and shift
- Today, Day Shift
= Weather conditions
- Warm, mid-summer
- Windy (Plant power levels)
- Unit 1 - 100% Power, 109% FCL + Unit 2 - 100 % Power, 108.5% FCL
- 3489 MWt + 3489 MWt 11189 MWe + 1189 MWe
- 93 Mlbmlhr CORE FLOW + 93 Mlbm/hr CORE FLOW Limit Problems/Power Evolutions SThermal
+ None
- None
= Existing LCOs, date of next surveillance
+ None
- None
= LOSs in progress or major maintenance
- None
- None
=> Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment IlB VP Chiller is OOS
- None
- om ...... , evolutions, problems, etc.
+ Online Risk is Green + Online Risk is Green
+ 3 CW pumps operating
- 3 CW pumps operating i .'Lasafic Exam\Scenario2.doc 3
Scenario #2 SIMULATOR SETUP A. CARDS/TAGS TO BE HUNG:
Reactor Building Ventilation Lineup:
A & B Exhaust fans in operation A & B Supply fans in operation C. TURNOVER INSTRUCTIONS:
- Gather the crew in an appropriate classroom setting, use the SRO and NSO turnover sheets to provide a shift turnover. Stress the following items:
- 1. Unit 1 is at 100% power, 109% Flow Control Rod Line.
- 2. Place 'B' RHR in Suppression Pool Cooling.
- 3. No Time Clocks in effect.
- 5. Unit 2 is at rated power.
(
P:ILasalle Exam\Sccnario2.doc 4 t;
Scenario #2 Key Event 2-1 Initiation: After completion of shift turnover and after cue from lead examiner.
Time/Notes Expected Crew Response
....________ RHR Service Water
,_ .Start BOP Operator Response:
Starts RHR Service Water per LOP-RH-05
"* PLACE the appropriate Thermal Overload Bypass switch to BYPASS
"* LOG positioning of O/L Bypass switch in the Unit Log
"* If required, START an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> clock
"* MAKE PA Announcement and START the first RHR-WS Pump
"* OPEN the 1E12-F068A/B, Heat Exchanger Outlet Valve
"* When RHR-WS Flow is >3000 gpm, then START the second Pump
"* When 1E12-FO68A/B is full open, then CHECK Flow is >7400 gpm.
"* PLACE the appropriate Thermal Overload Bypass switch in NORMAL
"* LOG positioning of O/L Bypass switch in Unit Log
"* If started, STOP the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> clock
"* NOTIFY Chemistry to take required samples RHR-WS samples
"* Dispatch an NLO to locally place the strainer backwash in AUTO
"* Dispatch an NLO to locally VERIFY the CSCS Cubical Fan is running
"* VERIFY the RHR-WS Strainer high differential pressure alarm is clear
"* START the RHR Service Water PRM per LOP-PR-06 Reactor Operator Response:
0 Monitors Reactor Power and P603 panel Unit Supervisor Response:
- Directs starting Suppression Pool Cooling PALasallc ExanlSlccnai 2.dxdc 5
Scenario #2 Time/Notes Expected Crew Response Key Event 2-1 Start RHR 'B' in Suppression Pool Cooling (cont'd)
BOP Operator Response Start RHR in Suppression Pool Cooling Moie per LOP-RH-13
"* PLACE appropriate Thermal Overload B3pass switch in BYPASS
"* VERIFY CLOSED 1E12-F006B
"* VERIFY OPEN 1E12-F004B, -F047B. L-d -F048B
"* MAKE PA announcement and START -B RHR Pump
"* THROTTLE OPEN 1E12-F024B to mcntain 1500 to 7450 gpm
"* THROTTLE CLOSED 1E12-F048B
"* THROTTLE 1E12-FO03B
"* VERIFY flow between 1500 and 7450 z-,)m (but as high as possible)
"* Dispatch an NLO to VERIFY RHR Pu.') Room Fan STARTS
"* VERIFY Diesel Generator Cooling Wa:er Pump is STARTED
"* PLACE the O/L Bypass switch back to NORMAL
"* MONITOR Pool Temperature RO Response:
- Monitors Reactor Power and P603 panem Unit Supervisor Response:
0 Directs starting Suppression Pool Cool:-g Simulator Operator: When requested, make appropriate field reports that indicate startup of the RHR-WS and RHR Suppression Pool Cooling is normal.
i TERMINUS: RHRSW and 'B' RHR operating in Suppression Pooi Cooling Mode.
P:\Lasalle Exam\Scenario2.doc 6
Scenario #2 Key Event 2-2 Initiation: After completion of Event 2-1 and cue from lead examiner.
Time/Notes Expected Crew Response Reactor Building Exhaust Fan VR02CB Trips
_____________PMO6J-A207 RB I B Vent Exhaust Fan Auto Trip BOP Operator Response:
Per PM06J-A207:
"* VERIFY RB Vent Exhaust fan VR02CB Trips
" MIONITOR Temperatures as needed.
"* IF less than 2 exhaust fans are running, then perform following to Bypass Group 1 MSIV logic before starting fans:
0 At panel 1H13-P642, place MSL PIP TUNNEL DIF TEMP BYPASS DIV 2 SIG B/D to Bypass.
- Start appropriate Time Clock
"* Start standby RB Ventilation Exhaust Fan
"* PLACE MSL PIPE TUNNEL DIFF TEMP BYPASS DIV 2 SIG B/D keylock switches at Panel 1H13-P6423 to NORMAL.
"* Dispatch operator to investigate cause of alarm at SWGR 132X RO Response:
- Monitors Reactor Power and P603 panel for abnormal/unusual conditions.
Unit Supervisor Response:
"* REFERS to Tech Specs for operability
"* Acknowledges Starting/Stopping TS Time clock for Bypassing Gp 1
"* INITIATES appropriate corrective action (Condition Report)
TERMINUS: After SRO reviews appropriate Technical Specifications PALasallc Examn\Scenario2.doc 7
Scenario #2 Key Event 2-3 Initiation: After completion of Event 2-2 and after cue from lead examiner Time/Notes Expected Crew Response Stuck Open SRV (B21-FO13C)
H 13 -P60 I -E 102, ADS or SRV Leakage H13-P60NI-F201, ADS Valve Fully Open BOP Operator Response:
In response to H 13-P601 -F201 alarm:
"* CHECK Drywell Pressure, Reactor Vessel Level and low pressure ECCS system is running to verify and ADS is required to be open.
(Not required to be open)
"* Refers to LOA-SRV-101, (Stuck Open SRV):
I. IDENTIFY SRV has spuriously actuated or is stuck OPEN
- 2. DECLARE SRV B21-FOI3C Inop
- 3. Cycle B21-F013C control Switch from AUTO to OPEN and back to AUTO.
- 4. CHECK B21-FO13C open (SRV still open)
- 5. Monitor Suppression Pool water temperature
- 6. REFER to Table 1 of LOA-SRV-101 to identify fuses associated with stuck open B2 1-FO13C
- 7. Have Aux Operator remove fuses F3A, F4A, F5A, & F6A in Panel H13 P628 in Auxiliary Electric Equipment Room
- 8. Have Auxiliary Operator remove fuses F5B & F6B in Panel H13-P631 in Auxiliary Electric Equipment Room.
- 9. CHECK B21-FO13C OPEN (SRV indicates closed)
- 10. Wait 1 minute then replace fuses removed in steps 8 and 9.
- 11. CHECK Open B21-F013C (SRV indicates closed)
RO Response:
"* Monitors Reactor Power and P603 panel for abnormal/unusual conditions.
"* REDUCE Generator Load 100 Mwe to maintain Rx power < 100%.
(See Key Event 2-4)
Unit Supervisor Response:
"* DIRECTS completion of task
"* REFERS to Tech Specs 3.4.4, 3.5.1, 3.6.1.6 & 3.6.2.1 fr operability
"* Acceptable'lS Actions should include:
- 1. Declare ,RV in'op and enters 24 hr to trip / days to restore time clock ('IS 3.3.5.1)
- 2. Dccla, .,,. ,1Jb~c and enters 24 howi. ,-1e t*inc clock (1.
3.5.1.C) 0 REFRS to '-," T Section 3.3.d TER: r* After: SRO rev '*s ;oP iate Technical Spc. .. s.
P:La'isIlc I'- '"-'cc,' rio?.Aoc 8
Scenario #2 Event 2-4 Initiation: After event 2-3 completed and after cue from lead exanimner.
Time/Notes Expected Crew Response Power Decrease with Recirculation Flow Reactor Operator Response:
Takes actions to establish a power ramp per LGP-3-1 and LOP-RR-07, to decrease load 100 Mwe:
"* VERIFY Manual light on Recirc Loop Flow Controller M/A st,-z.ion A/B is ON.
"* Change Flow evenly in both loops by pressing LOWER button Lnd observing flow indication to Flow controller M/A Stations.
"* REDUCE core flow to approximately (?) Mlbm/hour using Attachment C unless otherwise directed by the QNE
"* At a rate up to 100 MWe/hour
"* At a higher rate specified by a QNE BOP Operator Response:
"* REMOVE condensate polishers from service when no longer needed per LOP-CP-03
"* MAINTAIN condensate flow through the polishers per LOP-CD-03 Unit Supervisor Response:
"* DIRECTS crew to reduce power at <100 MWe/hour using recirculation flow control.
"* Notifies Electric Operations of power reduction TERMINUS: Clearly observable plant response from change in power level.
J P:kLasallc t';xam\Scenario2.doc 9
Scenario #2 Key Event 2-5 Initiation: After Event 2-4 completes and cue from lead examiner.
Time/Notes Expected Crew Response 1A RR FCV Fails Open lH13-P602-Al~l IA RR Flow Control Vlv Trouble 11113-P603-A51 1 flux/Flow Controller Output Signal Abnml RR Motion Inhibit Light RR Motion Inhibit Light Reactor Operator Response:
Takes actions per LOA-RR-101 for RR FCV failing OPEN
"* CHECK FCV position is STABLE
"* PRESS HPU IA TRIP pushbutton
"* CHECK core flow and loop flows LESS THAN T/S MISMATCH (w/in 5.425 Mlbm/hour if core flow is >75.95 Mlbm/hour, and w/in 10.85 Mlbm/hour if core flow is <75.95 Mlbm/hour)
"* CHECK instrumentation for indications of FUEL DAMAGE
"* Evaluate core performance
"* If >TS MISMATCH:
- 1. Restore flow mismatch within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- 2. Initiate TADS.
- 3. Zero servor error on I A FCV M/A Station
- 4. Check HPU Subloop a%ailable
- 6. Check "Pump Motor Running" indicates False @ DS001 Operator Station in both subloops
- 7. Select Start/Stop pump motor, Press START
- 8. Check pump motor running & Pressure normal.
- 10. Push LOWER PB at lA FCV M/A station.
BOP Operator Response:
0 Monitors panels for changes in plant conditions Unit Supervisor Response:
"* Starts a 2-hour time clock per Tech Spec 3.4.1 condition F.
"* Contacts QNE to evaluate concerns for balancing loop flows Simulator Operator: As the QNE, when contacted, tell them you'll check thermal limits and get back to them. Wait 10mm. then repot that no thermal limits have been exceeded but they are
'L.ov, tn', -1ose in a couple areas -mil would like them to balance flows as soon as possible.
vo.
i i -
- !, ý1 ! 1INUS: Crew ha , :-tions for the failed RP in\..
ad SRO has reviewed apphcb . : 'alSpecificationS. ,,, :;. ocurrence u of the Chief Examimri *;'!.::::th iih vibrations 'IIi , 1 leakage.
'\R'-Ný\."... !'\NRC!4(_7I.iS]RS\R KW\Ii. II,.... --... "cc:,,iTio2.dc<: I ()
Scenario #2 Key Event 2-6 Initiation: After cue from lead examiner.
Time/Notes Expected Crew Response 1A RR Pump Hi Vibrations / Winding Leak lIH I3-P602-A304 11B RR Pmp Mtr Cig Wtr Flow Low/Cir Lkg, 1H13-P602-A305 lB3 RR Pmip Mtr Vibr Hi Reactor Operator Response:
Takes actions per LOR- 1H 13-P602-A304 for motor cooling abnormal:
"* CHECK motor bearing temperatures, motor amps, and loop flow
"* CHECKS SOR typer for R-points
"* TRIPS RR Pump when both R-points are received (R0591 and R0593)
"* REFER to LOA-RR-101, RR System Abnormal.
"* Continue to MONITOR abnormal trends or parameters.
BOP Operator Response:
Takes actions per LOR- 1H 13-P602-A305 for RR motor vibrations
"* PUSH Vibration RESET pushbutton
"* If alarm can't be reset IMMEDIATELY NOTIFY System Engineering to MONITOR and EVALUATE
"* CHECK Loose Parts Monitor
"* If abnormal conditions exist IMMEDIATELY trip the pump REFER to LOA-RR- 101.
Unit Supervisor Response:
"* Contacts System Engineering and IMD for assistance
"* REFER to Tech Spec 3.4.1 for Single Loop Operation.
PALasalle Exa=i'Scenario2.doc I1I
Scenario #2 Time/Notes Expected Crew Response Key Event 2-6 1A RR Pump Hi Vibrations/Winding Leak (Cont'd) Manual Trip of 1A RR Pump Reactor Operator Response:
Takes actions per LOA-RR-001 when directed to manually trip IA RR pump
- CHECK at least one RR pump running (yes)
- PERFORM Core Instability checks while continuing
"* CHECK FCL is below 95.2% (yes)
"* CHECK Reactor Power OUTSIDE of Region A (yes)
"* CHECK Reactor Power OUTSIDE of Region B (no)
"* INITIATE LOS-RR-SR1 within 15 minutes per T.S. 3.4.1 Action A.
"* INSERT Cram Arrays AND (RAISE core flow OR INSERT in-sequence rods) to IMMEDIATELY EXIT Region B.
"* START 2-hour timeclock per T/S 3.4.1 if required
"* CHECK APRM Noise <2 x Normal (yes)
"* CHECK core flow to RIGHT of Natural Circulation line (yes)
"* CHECK LPRM Noise <2 x Normal (yes)
"* CHECK APRM - OPERABLE APRMs within +/-2% of calculated core thermal power.
"* MONITOR and EVALUATE Core Performance
- CHECK recirculation flow in active loop Ž21,000 gpm
- CHECK Operating RR Pump in fast speed (yes)
- INITIATE actions of T/S 3.4.1 for single loop (REDUCE MCPR and APLHGR, ADJUST APRM and RBM setpoints)
- NOTIFY IMD to adjust APRM/RBM Flow Converters
- PLACE all breakers for tripped pump in PTL (when less than 350 rpm)
- INSERT Control Rods to <66.7% FCL
- REDUCE loop flow to <34,425 gpm
- MAINTAIN tripped pump's suction and discharge valves FULL OPEN
- COMMENCE LOP-RR- 13 Single Loop Baseline Date
"* Assists RO in establishing single loop operations:
"* ISOLATE CPs as needed
"* MAINTAIN Condensate Flow 5,000 to 8,000 gpm.
"* If both TDRFPs are running SHUTDOWN one as time permits.
"* INITIATE special log to monitor loop AT ITnit r,- -isor Response:
- Directs actions per LOA-RR-101
- R]l"1`I]RS to TS 3.4.1
- C~<ntwt Chemistry for> 20% powcr clango in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
- ?~ TNUS:
' After phint stabilized and SRO has revivcvJ ý,pp!icahle Technical Specificationls.
P:'. 11c :amn' ccnario2.doc 12
Scenario #2 Key Event 2-7 Initiation: After Event 2-6 completed and after cue from lead examiner.
Time/Notes Expected Crew Response Small Break LOCA Inside Primary Containment ..2, 1' 1PM.13J-A302 RB North/DW Flr Sump Trouble JPM'3J-A204 DW Cooler Cond Flow Rate Hi
______________11113-P603-13501 Pri Cnmt Pressure HiILo Reactor Operator Response:
Takes actions to manually scram per LGP-3-2, completes the actions of the Scram Hardcard and follows up with the procedure N\hen a LOCA is discovered;
"* ARM and DEPRESS Scram Pushbuttons
"* PLACE Reactor Mode Switch in SHUTDOWN
"* CHECK all Control Rods in and Power Decreasing
"* INFORM Unit Supervisor Of Rod Status and Reactor Power
"* Operate FW as necessary within the level bank 32 to 45 inches
" REPORT to the Unit Supervisor the status (and trend) of RPV Level and Pressure
"* VERIFY Reactor Recirculation Pumps have downshifted
"* STABILIZE Reactor Pressure <1020 psig
"* GO TO Step E.2 of LGP-3-2 BOP Operator Response:
"* VERIFY Main Turbine and Generator Trip
" STABILIZE Reactor Pressure <1020 psig
"* GO TO Step E.2 of LGP-3-2 Makes plant announcement for Reactor Scram and DW leak.
Takes actions per LGA-001 when level drops below 11 inches (see next page)
"* Verify Main Generator/Turbine Trip
"* GO TO Step E. 2 of LGP-3-2 Unit Supervisor Response:
- Directs actions to manually scram per LGP-3-2 PA:\Lisa~l Exam\Sccnario2.doc 13
Scenario #2 Timeline/Notes Expected Crew Response Key Event 2-7 SB LOCA Inside Primary Containment (Continued)'
Panel Operator Response:
Takes Actions p.-LGA-001, RPV Control RPV Lex cl Control Leg
"* CONTROL Level 11 to 59.5 inches using Preferred Injection Systems (primarily CD & FW)
"* If cannot re :,re level above 11 inches then hold level above -150 inches on WR (using Preferred Injection Systems)
RPV Pressure Control Lea 0 Stabilize Presure Below 1059 psig CRITICAL Depressuriz= RPV using Turbine Bypass Valves at <100°F/hour STEP Takes actions per LGA-003 when high drywell pressure is received Containrr-.ent Pressure Leg
"* Start Su-pression Chamber Sprays
"* When >1 psig;
- VERIFY within the Drywell Spray Initiation Limit (Figure D)
CRITICAL
- TRIP boe-- RR pumps
- START DW Sprays (per LGA-RH-103)
STEP
- E Drywell Temperature Leg
- VERIFY _l available Drywell Cooling is running (per LGA-VP-01)
Suppress-on Pool Temperature Leg
- START aI available Pool Cooling (LGA-RH-103) if temperature reaches r05°F/hour
- Monitor Suppression Pool Level Containr-..ent Hydrogen Leg
- START HydLogen and Oxygen Monitors (LGA-CM-01)
Unit Supervisor Response:
- Makes plant announcement for LGA entries CRITICAL Directs actions for LGA-00 1 (See Panel Operator Reponse above)
STEPS - Directs actions for LGA-003 (See Panel Operator Reponse above)
- Makes plant announcement for GSEP Alert Terminating
- Maintains RPV level I I",-5905" Conditions * , Powary Containment paraiaters under control
- Ctei from Lead Examiner L':\Lasallc Exam\Scenario2.doc 14
Scenario #3 LaSalle County Station Operations Scenario #3 Exam Date: April 8, 2002 Developed By Rfi\mond Keith Walto' FDntn: March 8, 2002 Reviewed By: Date:
\\R3NWFS I\NRC\USER S\ KW\I , xam\Scenario3.d(c I
Scenario #3 NARRATIVE
SUMMARY
Current plant operating status.
The plant is at approximately 100% power. Power will be reduced using recirculation flow. The Div II DG surveillance is in progress. The 1A DG cooling water pump will trip followed by a rod drift. HPCS will spuriously initiate followed by failure of both CRD pumps. Multiple scram accumulator alarms result, with a failure of rods to manually scram. The SBLC Squib valve will fail to open.
Scenario segments 0 1A DG Monthly Surveillance 0 1A DG Cooling Water Pump Trip a Rod Drift
- HPCS Initiation
- SBLC Squib valves fail to open
\\R3NWFS I\NRC'xl V'RS\RKW\Lasalle Exaln\Sccn:irio3. '2 2
Scenario #3 SHIFT TURNOVER INFORMATION of week and shift
- Today, Day Shift conditions
- Warm, mid-summer
- Windy (Plant power levels)
+ Unit 1 - 100 % Power, <109% FCL + L_-:2 - 100 % Power, 108.5% FCL
+ 3489 MWt + -',9 MWt
+ 1189MWe + ,9 MWe
+ 92.5 Mlbm/hr CORE FLOW + c \Ilbm/hr CORE FLOW
= Thermal Limit Problems/Power Evolutions
+ None + N: e
~ Existing LCOs, date of next surveillance
+ None + N-ie
= LOSs in progress or major maintenance
+ LOS-DG-M2 completed through step 1.24 of + N.'-e attachment I A-IDLE to be taken out of or returned to service tL:_ shift/maintenance on major plant equipment
+ lB Bus Duct Cooler Fan OOS + N ne
+ lB OG Pefi igcration Unit OOS +
- =:> Comments, evowlutions, problems, etc.
- Online Safety is Green (RAW = 1.0) C-iine Safety is Green ( N , - 1.0)
- 3 CW mpi operaling - ,Vpumps operating
\\R3NWFS1l\NRC ,US LRS\RK\V* '&asalle Exani\Sccnaii6,3.JuL 3
Scenario #3 SIMULATOR SETUP A. CARDS/TAGS TO BE HUNG:
- lB Bus Duct Cooler Fan
- Common SA Compressor B. MISCELLANEOUS:
- lB OG Refrigeration Machine
- Split 142X and 142Y Buses (for LOS-DG-M2, Attachment lA-IDLE Step 1.7)
- Verify 1A DG Voltmeter is not in OFF C. TURNOVER INSTRUCTIONS:
- Gather the crew in an appropriate classroom setting and use the turnover sheet to provide a shift turnover. Stress the following items:
- 1. The plant is starting up at 100% power.
- 2. LOS-DG-M2 is in progress and completed through Step 1.24 of attachment lA-IDLE
- 3. Tech Staff and Electrical Maintenance are standing by in the DG room.
- 4. Rod line is 109%
- 5. 1B Bus Duct Cooler Fan is OOS for motor replacement
\\R 3NWFSV . ( .- "*' \V\Lasallexaw\Scer , 3 Ar 4
Scenario #3 Key Event 3-1 Initiation: After completion of shift turnover and cue from lead examiner.
Time/Notes Expected Crew Response "PowerDecrease with Recirculation Flow Reactor Operator Response:
Takes actions to establish a power ramp per LGP-3-1 and LOP-RR-07, to decrease load:
"* VERIFY Manual light on Recirc Loop Flow Controller M/A station A/B is ON.
"* Change Flow evenly in both loops by pressing LOWER button and observing flow indication to Flow controller M/A Stations.
"* REDUCE core flow to approximately 70 Mlbm/hour using Attachment C unless otherwise directed by the QNE
- At a rate up to 100 MWe/hour At a higher rate specified by a QNE BOP Operator Response:
Takes actions to establish a power ramp per LGP-3-1 to decrease load:
"* REMOVE condensate polishers from service when no longer needed per LOP-CP-03.
"* MAINTAIN condensate flow through the polishers per LOP-CD-03.
Unit Supervisor Response:
"* DIRECTS crew to reduce power at <300 MWe/hour to 70 Mlbm/hr
"* Notifies Electric Operations of power reduction TERMINUS: _ Clearly observable plant response from change in power level.
\\R3NWFS ;i6,, -. d,.KW\Lasallc Exar\ .*iai i5 ,, 5
Scenario #3 Key Event 3-2 Initiation: After completion of shift turnover and cue from le: examiner.
Time/Notes Expected Crew Response
.1A DG Monthly Surveillance Test (LOS-DG-M2)
Reactor Operator Response:
0 Monitors panel P603 panel for changes in reactor parame':>.
BOP Operator Response:
Performs actions per LOS-DG-M2, Step E.2, and Attachmeni A-IDLE:
"* DIRECTS NLO to perform local steps 2.0 through 3.3.1
"* RECORDS time DG is Started
"* VERIFY IA DG Cooling Water Pump Switch is in NOR.M.L
"* VERIFIES IA DG Cooling Water Pump is running
"* VERIFIES lA DG Voltage and Frequency
"* PLACE Synchroscope to ON
"* ADJUST LA DG Speed and Voltage as required
"* SYNCHRONIZE the LA DG output breaker and CLOSE
"* PLACE Synchroscope to OFF
"* SLOWLY Load LA DG as follows:
"* MAINTAIN 1000/1300 kW and 350/750 kvar for 2 n autes
"* MAINTAIN 1750/2000 kW and 500/1300 kvar for 2 m-nutes
"* MAINTAIN 2400/2600 kW and 650/1750 kvar for 60 7inutes
"* RECORD Time and Date load is at or above 2400 kW Simulator operator: If asked, send an NLO to the IB DG, wait 2 minutes, then report that post start checks of the iB DG indicate satisfaztory operation of the Diesel.
Unit Supervisor Response:
"* VERIFY Surveillance is compatible with current plant co-- _tions
"* DETERMINE DG time clock (if applicable) and RECORD Note: The S1iulatoi Operator will not be able to ob'scrve actins at or near the 1A DG contr ols. His view from the control booth is obstrtzted.
Therefore, the Chiel-Examiner will have to keep t[ie Simulato: Operator informed of fip , the student opeiatcs 0 Panel.
7.i01J "TEMIN'V: 1A EDG is runwo.,- !icd.
\\R3NWi SI'N&.CSERS\RKW'vLasallc E . 6
Scenario #3 Key Event 3-3 Initiation: lA EDG is loaded and cue from lead examiner.
Time/Notes Expected Crew Response 1A DG Cooling Water Pump Trip IPMOIJ-B206 1A DG Trouble
_. _Local Alarm
........(R0993- DG- A Clg Wtr Pmp Bkr- A-Tn)*i Reactor Operator Response:
- Monitors panel P603 panel for changes in reactor parameters.
BOP Operator Response:
Takes actions per LOR- 1PMO 1J-B206:
"* DISPATCH NLO to IA DG Control Panel to DETERMINE cause
"* REFER to appropriate LOR procedures
"* REFER to SOE typer Takes actions to unload and shutdown 1A DG per LOP-DG-03:
"* PERFORM the following to unload the IA DG
"* CHECK bus is supplied by either SAT or UAT
"* REDUCE load and vars
"* When at or below 200 kW and 200 kvars then OPEN the lA DG output breaker
"* DISPATCH NLO to place Speed Droop to 0
"* VERIFY speed at 900 rpm
"* Let 1A DG run unloaded for 5 to 10 minutes
"* VERIFY 1A DG Engine Control Switch in AUTO
"* PLACE 1A DG Control Switch to STOP
"* CHECK DG shuts down
"* PLACE 1A DG Maintenance Switch to MAINT Unit Supervisor Response:
"* Refer to Technical Specifications 3.8.1.C, 3.7.2.A, 3.5.1.A, 3.6.2.3.A, 3.6.2.4.A, and 3.6.3.1.A. (Unit 2 is also affected by the loss of 1A DG, LCO 3.8.l.C)
"* Calls WCC SRO for assistance and repairs.
___ -, US: Operator pl',, r, in shutdown. US reviews J echnical Specifications.
\\ '": i* I '.,SERS\KW .asaI i:A , .J2doc 7
'- -nario #3 Key Event 3-4 Initiation: 1A EDG is loaded and after cue from lead examiner.
Time/Notes Expected Crew Response CRD Drift Annunciator iH13-P603-A504 CRD Drift Reactor Operator Response:
Performs actions per LOA-RD-101 for Individual Rod Drift or Scram
"* CHECK only one rod is drifting or scrammed (yes)
"* SELECT the drifting control rod
"* CHECK insert block light is off at rod select matrix
"* If not, then REMOVE the block by either BYPASSING the RWM or DISABLE blocks to 100%
"* INSERT the drifting rod to notch 00
"* CHECK the control rod remains at 00 (yes)
"* VERIFY cooling water is normal (<63 gpm, <30 psid)
"* OBTAIN OD-7 Option 2
"* RUN OD-20
"* NOTIFY QNE to MONITOR core parameters or RECOMMEND additional power level changes
"* CHECK all other rods are at correct positions
"* DECLARE the control rod inoperable
"* INVESTIGATE Cause of Rod Drift
"* CONTACT System Engineering to troubleshoot BOP Operator Response:
"* Monitors panels
"* Assists RO as necessary Unit Supervisor Response:
"* REFER to Technical Specification 3.1.3, enters Action Statement
"* Declares Rod Inoperable TERMINUS: Drifted control rdd inserted to 00. SRO rcvicwx applicable Techni6al Specificati,'s*un i,5N *ii : *i'C\USLRSaRKW\LaŽaNL iLi-xam'i'dci1 iou3.doc C)
Scenario #3 Key Event 3-5 Initiation: Event 3-4 complete, and after cue from lead examiner.
Time/Notes Expected Crew Response Inadvertent IIPCS Initiation 1H13-P601-A205 HPCS SYS'Actuated IH13-P601-A204 HPCS Pmp Bkr 2 Closed 1H13-P601-A406 HPCS Hdr Press Hi Reactor Operator Response:
- Monitors changes in core reactivity from cold water injection BOP Operator Response:
Recognizes HPCS inadvertent initiation DISPATCHES NLO to lB DG room SECURES lB DG By pressing STOP pushbutton PREVENTS re-start of 1B DG by placing Maintenance Switch in MAINT Takes actions per LOR- 1H I3-P60 1-A205 for HPCS Initiation
"* VERIFY automatic actions (HPCS aligns for injection)
"* CHECK initiation signal present
"* NOTIFY Shift Manager to classify GSEP (make notifications too)
"* If HPCS is not required then SHUTDOWN per LOP-HP-04 Takes actions per LOP-HP-04 to shutdown HPCS
"* VERIFY HPCS injection is NOT needed by multiple indications
"* VERIFY Initiation Signals Clear
"* RESET the HPCS logic by DEPRESSING both reset pushbuttons
"* CLOSE 1E22-F004 Injection Valve
"* VERIFY 1E22-F012 Minimum Flow Valve OPENS
"* STOP HPCS pump
"* VERIFY 1E22-F012 Minimum Flow Valve CLOSES
"* When HPCS room fan automatically stops, then SHUTDOWN the 1B DG Cooling Water Pump
"* When plant conditions permit, PLACE HPCS in standby per LOP-HP-03 Unit Supervisor Response:
- Refers to Tech Spec 3.5.1 and declarcs IIPCS INOP
- Contacts PMD and System Engineer;-,- f.1assistance in tIoO 1 , 2.-.-_" r
- Refers to Technical Specification 3.-.1 condition F. action I (both IA and I1 1) is arc inoperable)
[ * ::
,, US: Crew secuics 11PICS pump. SRO re*vi&c v.. *;.,, Technical Specificalolls.
. 7,'i 1' '1C\USERS\RKW\Lasall. ELa:..'2I> nairio3.doc (3
Scenario #3 Simulator Commands Instructor Role Play and Information Scenario Segment
Description:
This event simulates and inadvertent initiation of HPCS system logic. The crew will have to recognize that it is a spurious initiation and then take actions to secure the HPCS system and the 1B DG. The Unit Supervisor should call the HPCS system Inoperable.
Trigger 1 Simulator Operator: Wait until the crew has paralleled the 1A DG to the SAT and then with the concurrence of the Chief Examainer, initiate the spurious initiation of the Division 3 initiation logic by activating Event 3-5, HPCS initiation.
NOTE: When Event Trigger 1 is activated, it will initiate the Division 3 initiation logic causing the HPCS pump to start and the 1B DG. Event Trigger 1 also hides the Low Level annunciators. When the IB DG gets up to speed the Bus Alive light will come on activating Event Triggers 20, 21 and 22. Event Triggers 20, 21 and 22 delete the spurious initiation malfunction and the annunciator overrides that were installed by Event Trigger 1. This will allow the students to shutdown the HPCS system using LOP-HP-04.
Trigger 16 Role Play: If asked, have NLO place the IB DG in Maintenance Switch in the Maintenance position, wait 1 minute then activate Event Trigger 16 (ior iadgmanb maint).
\VI 31 \NRC\LJSERS\ KV'\L. Z...S.,cnai io3.doc
Scenario #3 Key Event 3-6 Initiation: Event 3-5 is completed and after cued by lead examiner.
Time/Notes Expected Crew Response CRD Suction Filter Clogged 1H13-P603-A303 CRD Feed Pmp Suet Filter DP Hii I1H1I3-P603-A203 CRD Feed Pmnp Suction Press Lo 1H1I3-P603-A 103 1lA CRD Feed Pmp Auto Trip Reactor Operator Response:
Per P603-A303, CRD Feed Pmp Suct Filter DP Hi:
"* Dispatches NLO to CRD Pump area
"* Directs an NLO to switch to the STBY suction filter per LOP-RD-14 Local operation of valves)
Per P603-A203 CRD Feed Pmp Suction Press Lo:
"* REDUCEs system flow by closing FCV to clear alarm and keep pump
- rom tripping on low suction pressure.
"* THROTTLEs down on drive water pressure to maintain about 280 psid.
"* Places standby CRD suction filter in service Per P603-A103 IA CRD Feed Pmp Auto Trip:
"* Has the NLO expedite switching filters.
"* STARTs STBY pump:
I. If CRD pressure is >500 psig then immediately starts pump, or Starts pump per LOP-RD-03.
Receives multiple accumulator alarms - Directed to scram reactor)
BOP Operator Response:
- Monitors panels for alarms/abnormal conditions Unit Supervisor Response:
"* Refers to Tech Spec 3.1.5 after first CRD Accumulator alarm
"* DIRECTS Actions to manually scram when multiple accumulator Jarms are received TERMINUS: Reactor Scram by crew.
\aR3NWFS1\NRC\USERSV.:. : '.a:mi\Sccnario3.doc 11
Scenario #3 Time/Notes Expected Crew Response Key Event CRD Suction Filter Clogged (Cont'd) 3-6 Manual Scram after Receiving Multiple Accumulator alarmis Reactor Operator Response:
- PLACE Reactor Mode Switch in SHUTDOWN
- CHECK all Control Rods in and Power Decreasing S REPORTS ATWS conditions to Unit Supervisor
- INFORM Unit Supervisor Of Rod Status and Reactor Power
- Operate FW as necessary within the level bank 32 to 45 inches
- REPORT to the Unit Supervisor the status (and trend) of RPV Level and Pressure
- VERIFY Reactor Recirculation Pumps have downshifted
- GO TO Step E.2 of LGP-3-2 BOP Operator Response:
"* VERIFY Main Turbine and Generator Trip
"* STABILIZE Reactor Pressure <1020 psig
"* GO TO Step E.2 of LGP-3-2 Unit Supervisor Response:
CRITICAL Take actions per LGA-00 1.
- When reactor power is greater than 3% and/or all rods are NOT in to at STEP least 02 and the reactor will not stay shutdown without Boron then EXITs LGA-001 and ENTERs LGA-010
,I.13NNWI7 S 1\NRC\USERS."',' LaI;-lc Exam\Sccnario3,dou 12
Scenario #3 Time/Notes Expected Crew Response Key Events ATWS 3-7 & 3-8 Failure of SBLC Squibb Valves to Open Panel Operator Response:
Per LGA-0 10:
"* Inhibit ADS
"* Prevent injection form HPCS, LPCS and LPCI LGA010 Power Leg
"* INITIATE ARI
"* RUNBACK Reactor Recirculation flow to minimum
"* If power is >3% then TRIP RR Pumps
"* ENTER LGA-NB-01, Alternate Rod Insertion
"* If power is >3% then START SBLC
- 1. Places 1A/B SBLC Pump keylock switch to Sys A/Sys B position
- 2. Checks C41-FO04A/B SBLC Inj Squib Vlv ON light extinguishes (ON light does NOT extinguish)
CRITICAL 3. SBLC Squib Vlv Continuity Loss alarm (A105) does NOT alarm
"* Identifies that SBLC does not initiate STEPý
"* Attempts to initiate Alternate Boron Injection using RWCU
- 1. Authorizes NLO to use submersible pump with FP hose attached and run hose from SBLC tank to RWCU precoat tank.
- 2. Defeat RWCU/SBLC isolations per Att. A. LGA-RT-103
- 3. Switch jumpers per Att B.
- 4. Remove RWCU Filter Demins from service per LOP-RT-04
- 5. Pump SBLC solution to RWCU precoat tank
- 7. Place RWCU filter demineralizer in service.
"* WAIT until Cold Shutdown Boron (<3100 gal in SBLC Tank) i Unit Supervisor Response:
- Acknowledges that SBLC docs not actuate CRITICAL
- Directs actions per LGA-NB-01, (See panel operator response above)
STEP
- Directs actions per LGA (-0) 'Ind LGA-010, (See panel onerator response above)
- Authorizes Alternate I, - iikection using RWCU pei GA-RT-103
'X"'R3NWFS 1\N RC\USERS\RKWLasalle Exarn\Sccnariý .d-U 1 13
Scenario #3 Time/Notes Expected Crew Response Key Events ATWS (Cont'd) 3-7 & 3-8 Failure of SBLC Squibb Valves to Open (Cont'd)
Panel Operator Response:
LGA-010 Pressure L.
"* If SRVs are cycling then OPEN SRVs to lower pressure to 935 psig
"* STABILIZE pressure < 1 43 psig using main turbine bypass valves
"* Okay to reduce pressure 'o CB pumps can be used to control RPV level before stabilizing pressure. Do NOT exceed cooldown rate of 100°F
/hr.
"* Use Alternate Pressure Control Systems if needed
"* EHC Pressure Set at 870 ?sig keeps SRVs closed when LLS is reset.
"* WAIT until Reactor is S`.utdown or Cold Shutdown Boron is injected
(<3100 gal in SBLC Tan*
LGA-010 Level Leg
"* VERIFY Automatic actions occur (Isolations and DGs Start)
"* If Steam Lines are open Then BYPASS MSIV isolations per LGA-MS-01 CRITICAL
- If reactor power >3% or unknown then Rapidly LOWER Level to at STEP least -60 inches and use only preferred systems to hold level between 150 and -60 inches.
Unit Supervisor Response:
"* Directs actions per LGA-010 (See panel operator response above)
"* EXITs LGA-010 and ENTERs LGA-001 when all rods are in, or Cold Shutdown Boron is injec:ed, or the reactor will stay shutdown without Boron.
\\R31NNFS l\NRC\USERS ,UQW\ allc Exain\Sccnario3. 14
Scenario #'
Time/Notes Expected Crew Response Key Event ATWS (Continued) 3-7 Failure of SBLC Squib Valves to Open (Cont'd) 3-8 Panel Operator Response:
The following actions will only be taken if level drops below -150 inches Take actions per LGA-006 when directed by LGA-010:
- VERIFY Suppression Pool Level is greater than -18 feet CRITICAL *
STEP
- VERIFY 7 ADS Valves are OPEN
- RETURN to LGA-010 at Step 10
- Commence re-injection when Reactor Pressure reaches 160 psig
- WAIT until Shutdown Cooling Interlocks clear (143 psig)
- WAIT until Reactor is shutdown or cold shutdown boron is injected
- COOLDOWN to Cold Shutdown using Shutdown Cooling (per LOP-RH-07)
Unit Supervisor Response:
CRITICA __ Directs actions per LGA-010 CRITICAL,! . Directs actions per LGA-006 STEP Simulator Operator: Insert Control Rods as RO either pulls fuses or drives rods in manually (one at a time).
Terminating 9 Maintain level 11 to 59.5" Conditions 0 All rods are in, or Cold Shutdown Boron is injected, or the reactor will stay shutdown without Boron.
- Cue from lead examiner
\\R3NWFS 1\-NRC\USERS\RKW\Lasallc ExarnSccnar o3.d c1 15
Scenario #4 LaSalle County Station Operations Scenario #4 April 8, 2002 0
Developed By: Raymond Keittihviun Date: March 24, 2002 Reviewved By: Date P:ALasallc I am\S ccn:io 4.toQ 1
- Scenario #4 NARRATIVE
SUMMARY
Current plant operating status.
The Unit is at 85% power. Crew will reduce reactor power using RR flow less than 82%
power. Perform a LOS-RP-Q3 for 'A' inboard and outboard MSIVs. The RO will identify the
'B' RR FCV slowly drifting closed. The RO may or may not compensate \;, :ih the 'A' RR FCV depending on the mismatch between loop flows. Containment Chill water -- imp 'B' trips. 'C' APRM fails upscale without RPS half-trip. The operating IA IN compress:.- will fail. A small break LOCA due to a recirc pump seal failure occurs followed by trip of bV. 142Y.
Scenario segments
"* Reduce reactor power to less than 82% power
"* 'A' inboard and outboard MSIV Surveillance Test
"* Containment chill water pump 'B' trips
"* APRM 'C' Fails High without an RPS half-trip occurring
"* Trip of IA IN compressor
"* SBLOCA in drywell
"* Bus 142Y trips P:\LaMIc L.\aIli\{ccnalio ;.doc 22
Scenario #4 Facility: LaSalle County Station Scenario No.: 4 Op-Test No.: 2002301 Examiners: Operators:
Initial Conditions: Reactor powe- 85%. 'B' IN compressor out of service Turnover: Perform MSIV Surve lHance Test for only 'A' Inboard and Outboard Isolation valves lAW LC)S-RP-Q3.
Event MaIf. Event Event No. No. Type* Description 1 R Reduce Reactor Power using RR flow to less than 82% pwr (RO) 2 N Performs LOS-RP-Q3 for 1A Inboard and Outboard MSIVs (BOP) 3 I RR FCV Controller output drifts causing 'B' RR FCV to drift (RO) c csed, operator may need to decrease RR flow on 'A' RR loop at M/A station 4 C Containment Chill Water Pump 'A' trips (BOP) 5 I 0 APRM Fails Upscale without RPS half-trip (mo) 6 C T--p of 'A' Instrument Nitrogen (IN) compressor.
___(BOP) 7 M SBLOCA in Drywell 8 C Bis 142Y trips t +
K(N)ormf, (R)F-activily, (I)nstrument, (C)omponent, (M)ajor LGA-4, ' - .,:ý,
- owdwl LGA-ouoý, "f-'v Blowdown 1:\as1- I'. nar; IclOC3 3
Scenario #4 SHIFT TURNOVER INFORMATION
~ Day of week and shift
- Today, Day Shift
= Weather conditions
+ Warm, mid-summer
+ Windy S (Plant power levels)
+ Unit I - 85 % Power, 100% FCL Unit 2 - 100 % Power, 108.5% FCL
+ 2965 MWt 3489 MWt
+ 945 MWe 1189 MWe
+ 85 Mlbm/hr CORE FLOW 93 Mlbm/hr CORE FLOW Limit Problems/Power Evolutions
+ None None
= Existing LCOs, date of next surveillance None
= LOSs in progress or major maintenance
- None
- None SEquipment to be taken out of or returned to service this shift/maintenance on major plant equipment IlB IN compressor OOS
- None
= Comments, evolutions, problems, etc.
+ Online Risk is Green
- Online Risk is Green
+ 3 CW pumps operating
- 3 CW pumps operating P:\Lazallc Exai\S&cnario4.doc I
Scenario #4 SIMULATOR SETUP A. CARDS/TAGS TO BE HUNG:
"* Place the >95.2% FCL placard on near the mode selector switch
- Place OOS tags on lB IN compressor B. MISCELLANEOUS:
- Time Clock Board None C. EQUIPMENT:
0 D. TURNOVER INSTRUCTIONS:
Gather the crew in an appropriate classroom setting; use the turnover sheets to provide a shift turnover. Stress the following items:
- 1. Unit 1 is at 85% power holding steady
- 2. Decrease power to perform LOS-RP-Q3 for 'A' MSIVs only
- 3. FCL>95.2%
- 4. Unit 2 is at rated power P:\La<al lc Exam\Scenario4.doc 5
Scenario #4 Event 4-1 Initiation: After completion o: shift turnover and cue fron lead examiner.
Time/Notes Expected Crew Response Power Decrease with Recirculation Flow Reactor Operator Response:
Takes actions to establish a power ramp per LGP-3-1 to decrease load:
"* Decrease core flow per LOP-RR-07
"* At a rate up to 300 MWe/hour
"* At a higher rate specified by a QNE LOP-RR-07:
"* Verify manual light on recirculation loop flow controller M/A station A/B is ON.
"* Change flow evenly in both loops by pressing LOWER button and observing flow indication to flow controller M/A station.
BOP Operator Response:
- MAINTAIN condensate flow through the polishers per LOP-CD-03 Unit Supervisor Response:
"* DIRECTS crew to decrease power at <300 MWe/hour to 100% power using recirculation flow
"* Notifies Electric Operations of power change
"* Enforces OPS expectations and standards
"* Ensures RO monitors critical parameters carefully
"* Ensures operations are conducted within bounds of TS TERMINUS: Clearly observable plant response from change in power level.
.:' -i!!c Exarn\Sccnario4.d(
Scenario #4 Event 4-2 Initiation: Followvin- Shift turnover on signal from lead examiner.
Time/Not , Expected Crew Response Key Event: Perform LOS-RP-Q3 MSJV Scram Functional Test BOP Operator Response:
Takes actions to perform LOS-RP-Q3, MSIV Scram Functional Test for IA inboard MSIV and IA outboard MSIV:
"* VERIFIES Rx Power <82%, all MSIV switches in AUTO, Scrams RESET, and MSIV Relays energized.
"* One at a time, places IA inboard MSIV control Sw. in OPEN SLOW TEST
"* Depresses and Holds PB until 2 relays deenergize or for about 10 sec.
After receiving dual indication.
"* Then Releases PB.
"* VERIFIES 1A inboard MSIV reopens and 2 relays deenergize then reenergize.
"* Checks that IA/lB MSIV inbd/outbd Not Full Open alarm received.
"* Verify IA inboard MSIV open.
"* Verify all MSIV relays energized (1C71A-K3A through K3H).
"* Reset 1A/IB MSIV Inbd/Otbd Not Full Open alarm.
"* Place 1B21-F022A, Inbd MSIV control switch in AUTO.
"* Waits 2 minutes to stabilize flows.
"* Repeats above steps with lA outboard MSIV.
- 1. Except that 2 scram relays (K3A and K3B) do NOT deenergize after holding PB for greater than 10 secs.
Reactor Operator Response:
"* VERIFIES Rx Power <82%, all MSIV switches in AUTO, Scrams RESET, and MSIV Relays energized.
"* Monitors plant parameters for alarms/unusual conditions Unit Supervisor Response:
"* HOLDS power decrease to perform MSIV surveillance test
"* MONITORs crew performing LOS-RP-Q3
"* Refers to TS 3.3.1.1 TERMINTUS: _ Completion of sdrveillance test 1:\Lasalle Exam SccnarioI .dn.7 7
Scenario #4 Key Event 4-3 Initiation: After SRO reviews TS for MSIVs and cue from lead examiner.
Time/Notes Expected Crew Response
'13 RR FCV Controller Output Drifts -, Closure of '13' FCV IH I13-P602-BlO01, 'B' RR Flow C'ontrol Vlv Trouble' Reactor Operator Response:
Immediate Response: Lockup 'B' RR FCV HPU Per P602-B 101, 'B' RR Flow Control Vlv Trouble:
"* CHECKS computer for alarm R0968, lB FCV Servo Amp Cont. Sig Abnormal and initiates corrective actions to reset alarm.
REFERS to LOA-RR- 101, Reactor Recirculation System Abnormal
"* CHECKS FCV position Stable (no)
"* If not done previously, Locks up 'B' FCV locked up by tripping RR FCV HPU.
"* CHECKS for core instabilities (none)
"* CHECK recirculation loop jet pump flows less than TS MISMATCH:
- 1. Within 5.425 Mlb/hr as read on B21-R611A/B or greater than or equal to 75.95 Mlbm/hr.
- 2. Within 10.85 Mlb/hr as read from B21-611A/B if core flow less than 75.95 Mlbm/hr.
NOTE: If candidates detect failure quickly and take immediate actions by locking up 1B RR FCV by tripping HPU, may not exceed TS Mismatch.
- If >TS MISMATCH:
- 1. Restore flow mismatch within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- 2. Initiate TADS.
- 3. Zero servor error on 1B FCV M/A Station
- 4. Check HPU Subloop available
- 6. Check "Pump Motor Running" indicates False @ DS001 Operator Station in both subloops
- 7. Select Start/Stop pump motor, Press START
- 8. Check pump motor running & Pressure normal.
- 9. Push 1B FCV Inhibit Reset PB & verify Motion Inhibit light clears.
- 10. Push LOWER PB at 1A FCV M/A station.
BOP Operator Response:
P MONITORS panels for abnormal conditions and alarms.
Unit Supervisor Response:
- Refers to Tech Spec 3.4.1, Condition F.
TERMINUS: PO baiances loop flows, if required. SRO reviews apphcab Tcc vical SSpecifications .
P:\Lasalle Exam\Scenario4.doc
Scenario #4 Key Event 4-4 Initiation: Event 4-3 complete, and cue from lead exami:-.er.
Time/Notes Expected Crew Response Cn e C Water Pump 'A" Trips ..
.PM6.J-A20 ,Primairy Ctmt Water Chiller Pump TO1PATnrip
___________P~d~-A*1, Pimay Ctmit Vent. Water 114ler YPO1ICA T~i~
BOP Operator Response:
Response to PM06J-A201:
"* VERIFY Automatic Isolations Occur:
- 1. TRIPS Primary Containment Water Chiller Pump 'VPO0PA, (Loss of Primary Containment Cooling).
- 2. TRIPS Primary Containment Water Chiller Unit IVPO1CA.
"* MONITORS Drywell temperature and pressure
"* DISPATCH operator to CHECK Protective Relays at compressor motor starter panel. 'A' chill water pump is fed from \ICC 133-1.
"* OPERATE available chillers per LOP-VP-02 to main:ain adequate Drywell Cooling.
"* MONITOR Drywell Temperature (Reference LOP-CNI-04).
"* MONITOR Drywell Pressure from recorders 1PR-CM027 and lPR CM028 on panel 1PM13J.
Response to PM06J-A501:
" Start 1B Primary containment chill water compressor and vent system per LOP-VP-02 Response to LOP-VP-02:
"* Coordinates with NLO and Starts the 1B VP Chill wa:er pump from CR.
"* After more local checks, Starts the 'B' Supply fan from PM06J.
"* After 30 seconds, ensures 'B' Supply Fan is still running.
"* Local operator starts chiller unit.
"* CLOSES lB VP Chiller Supply Bkrs to VPO1CB (action doesn't start the VP chiller).
"* Locally, NLO starts 1B VP chiller and checks for proper local operation.
PALasalle Exam\Sccnario4.dA( 9
Scenario #4 Time/Notes Expected Crew Response Key Event Containment Chill Water Pumpj 'A" Trips 4-4 PM06J-A20, Primiary Ctimt Water Chiller Pump VPIPA Trip (cont'd) PMO6J-A501, ~Primary Ctmnt ~Vent. Water Ch'ller VPOlCA Trouble Reactor Operator Response:
Monitors for alns/abnormal conditions on P603 panel.
BOP Operator Response:
(See previous page)
Unit Supervisor Response:
"* May REFER to LGA-003, Containment Control if receive high containment temperature alarms.
"* Refers to Tech Specs ?
TERMINUS: Orders NLO to locally reset RCIC trip throttle valve.
_____ Simulator Operator: DONOTreset RCIC trip Throttle Valve!
P:\Lasalle Exam\S .cnari 4.doc 10
Scenario #4 Key Event 4-5 Initiation: After Event 4-4 complete and cue from lead examiner.
Time/Notes ExDected Crew Resnonse APRM C Fails High, No Half-Tr p 1H13-P603-A405, Channel 'op 1H 13-P603-A308, Rod Out IH13-P603-AIOS, APRMI 1H!3-P?6O3-Bý07, 0PRM IIi Reactor Operator Response:
Announces 'C' APRM Upscale Trip without corresponding trip of 'A' RPS.
Per H 13-P603-A405:
"* VERIFIES Automatic Actions Occurred (no)
- 1. Trip of RPS Channel 'A' (no)
- 2. INSERTS trip of RPS Channel A.
"* Determine if one APRM has failed upscale or is inoperable.
"* BYPASS Inoperable/Upscale 'C' APRM
- 1. On H13-P603 panel, takes 'A' Channel APRM Joy stick to 'A' position
"* RESET RPS Channel A (May decide not to do - investigate cause of 'A' RPS not tripping)
Per H13-A308 & H13-A108:
"* Verifies Rod Block occurs (yes)
BOP Operator Response:
"* Monitors plant conditions
"* Assists Reactor Operator as needed to investigate cause of LPRM/APRM failure.
Unit Supervisor Response:
- Refers to Tech Spec 3.3o1.1 and 3.3.2.1
- Declares APRM C inoperable o Refers to TRM 3.3.C, conditions 1 & 2.
TERMIN-L: Crew bypasses 'C' APRI,>, and SRO reviews appli*ablc ichi. Specs.
P:\Lasallc Examn\Sccna.io4.doc 11
Scenario #4 Key Events Initiation: After completion of Event 4-5 and cue from lead examiner.
4-6 Time/Notes Expected Crew Response Reactor Operator Response:
Per PM03J-B503:
"° Decreases power to approximately 63% at a rate up to 300 MWe/hour by inserting CRAM rods and/or recirculation flow by:
- 1. VERIFY Manual light on Recirc Loop Flow Controller M/A station A/B is ON.
- 2. Change Flow evenly in both loops by pressing LOWER button and observing flow indication to Flow controller M/A Stations.
"* Must maintain:
- 1. Condensate Polisher D/P less than 60 psid
- 2. Feedwater pump suction pressure greater than 250 psig
- 3. Reactor water level greater than 31"
- 4. Core Flow greater than 49 Mlbm/hr Per B504, Htr Drain Pump Auto Trip:
"* Refer to LOA-HD-101, Heater Drain System Trouble:
- 1. Do NOT reduce core flow to the instability region (or below 49Mlb/hr).
- 2. Monitor Feedwater temperature.
- 3. REDUCE core flow at least 5Mlbs/hr for every 10F drop in FW temp.
- 4. If below FWHOOS line in Fig. 1, contact a QNE to adjust MCPR limits for FW htrs OOS and evaluate core performance.
Unit Supervisor Response:
"* DIRECTS crew to reduce power at <300 MWe/hour to <63% power
"* Notifies Electric Operations of power reduction P:\Lasallc Exn.m'Scen:oio.dt 12 1
Scenario #4 Time/Notes Expected CreN; Response Key Events Heater PrainTank Level Controller HK-HD-31!0 Fails Open 4-6 & 4-7 IM03J-B503, Ptr Dirain Tank L,-ei liYLo P
(Cont'd) P0 13JB504, Htr Drain Pump Auto Trip I Poe eraewt eiclto Flow BOP Operator Response:
Per PM03J-B504:
"* VERIFIES that HD pumps tripped --.d observes low level condition in heater drain tank.
"* VERIFIES Heater Drain Tank Level Controller operating properly (Determines that HK-HD-3 10, Hea-er Drain Tank to Condenser Level Controller NOT operating properl\.
"* Takes HK-HD-3 10 controller to M -,ual and decreases demand signal.
"* HD171A/B/C indicate closed.
"* Level starts to increase in Heater Dr:in Tank
"* Restarts heater drain pumps per LOP-HD-02:
- 1. Locally NLO latches LSV-HV2,9.240 & 241 (A, B & C HD pump forward control valve solenoid %-Aves)
- 2. ADJUST HK-HD066, setpoint 1.,7 feet
- 3. DEPRESS output increase (UP a--row) to open HD pump forward control vlvs until controller de\-Ition is at or near 0.
- 4. Transfer the HD pump Forward controller to AUTO by depressing the PB
- 5. SLOWLY adjust setpoint to 9 feet on HK-HD3 10. The low flow flushing valves HD171 A, B &C will go closed and Pump forward valves HD045A, B & C will cor.:rol heater drain tank level.
- 6. START/STOP HD pumps as necessary to maintain HD tank level.
"* REFERS to LOA-HD- 101, Heater Drain System Trouble
- 1. Check Main Turbine on line.
- 2. Monitor Feedwater temperature .)n computer points B744 - B747 or CRT Screen #46 or OD3 (Hea4 Balance Printout)
- 3. CHECK all 13 A/B/C FW heaters are on line.
TERMINUtS: Crew, eains lev*l in heater drain tank and reducesrector power to 63%o'
_ Or results in reactor schiaj on low fefdpumpsucki.
S(C)
P:\Lasallc Exam'n,- "nar:-. ý.doc 13
Scenario #4 Key Event 4-8 Initiation: Event 4-7 completes, or reactor scram results or cue from lead examiner. Events 4-8, 4-9 and 4- 10 can be initiated at the same time.
Time/Notes Expected Crew Response RR Line Break/ Small LOCA lI .1 3-.P603-B501 Pri Cnmt Pressure Hi/Lo IPM13-A30RB NorthIDW Fir Sum'p Troub]e
______________ & I1M13iJ-A204 PW Cooler Cond Plow Ra~teH Reactor Operator Response:
Takes actions per LGP-3-2, completes the actions of the Scram Hard card and follows up with the procedure;
- PLACE Reactor Mode Switch in SHUTDOWN
- CHECK all Control Rods in and Power Decreasing
- INFORM Unit Supervisor Of Rod Status and Reactor Power 0 Operate FW as necessary within the level bank 32 to 45 inches
- REPORT to the Unit Supervisor the status (and trend) of RPV Level and Pressure
- VERIFY Reactor Recirculation Pumps have downshifted
- STABILIZE Reactor Pressure <1020 psig
- GO TO Step E.2 of LGP-3-2 BOP Operator Response:
- VERIFY Main Turbine and Generator Trip
- GO TO Step E.2 of LGP-3-2 0 Takes actions per LGA-00 I when level drops below 11 inches
- 2. Checks all rods in to at least 02 position.
RPV Level Control Leg
- 1. CONTROL Level between 11 to 59.5 inches using Feedwater and Condensate RPV Pressure Control Leg I. Before RPV pressure reaches 440 psig, prevent LPCS and LPCI injection.
- 2. Stabilize Pressure Below 1059 psig using Turbine Bypass Valves
- 3. Depressurize RPV using Turbine Bypass Valves a <1000 F/hour Unit Supervisor Response:
"* Directs actions per LGP-3-2 (See RO and 13OP Response items above)
I:\LasaIle Exam\SccnarioJ.doc 14
Scenario #4 S..Time/Notes
... Ev n
,*Key Event I R IRR L 4-8 (Cont'd)'
". i¸ . ......-.
Panel Operator Response:
Per LGA-003:
Containment Pressure Leg
"* Start Suppression Chamber Sprays
"* When >12 psig;
"* VERIFY within the Drywell Spray Initiation Limit (Figure D)
"* TRIP both RR pumps CITICALTE '
"* START DW Sprays Drvwell Temperature Lea
"* VERIFY all available Drywell Cooling is running (per LGA-VP-01, 1' RITICAL can't be used when Drywell Temperature is above 212'F)
STEP "* If cannot restore and hold Drywell temperature below 340'F then:
Blowdown per LGA-004 Suppression Pool Temperature Leg
"* START all available Pool Cooling (LGA-RH-103) if temperature reaches 105°F/hour
"* Monitor Suppression Pool Level Containment Hydrogen Leg
"* START Hydrogen and Oxygen Monitors (LGA-CM-0 1)
CRITICAL Unit Supervisor Response:
STEP a Directs actions per LGA-003 (See actions above)
P:\Lr~aI~ac Ex:.:'-Sccnario4.doc Il1
enuo Key Events Initiation: lv'\cfl, 4 -9 11d 4- 10 nuy h initiated at the Naec . .hat 4-9 & 4-10 C\Cet 4-8 1, initiated.
Trinme/Notes Expected Crew Response Loss Of Bus 152 IPMOIJ-A206, 6.9KV Bus 151/152 Overcurrent IPMO IJ-A207, 6.9KV Bus 15 1/152 Undervoltage IPM03J-A103, IA/IB/1C FW Pmp Trip Loss of Feedwater IPM03J-A 110, CD/CB Pump Auto Trip IAIlB/1C FW Pump Trip
'A' Condensate/Booster Pump fails to Auto Start Panel Operator Response:
Per PM0IJ-A206 & A207:
Announces loss of Bus 152, loss of B & D condensate/booster -nips, and loss of both TDRFPs (low suction pressure).
A condensate/booster pump (in standby) fails to automatically Recognizes that Motor Driven RFP does not start (powered fror Bus 152)
Reports loss of feedwater system.
Reports loss of lB Recirculation pump (powered from Bus 152 Takes actions per LOA-AP-101 for loss of Bus 152.
Per LOA-AP- 101:
9 CHECKs I PMO 1J-A206 (over current) CLEAR (no)
- DISPATCHES equipment operator to check Bus 152 for tar Z:s and damage.
Per LOA-RR-01. for loss of 1B Recirculation Pump:
CHECK at least one RR pump running (yes, IA RR pump)
- t. Check RR Flow in the active loop >21,000 gpm
- 2. Check operating pump in fast speed (no)
- 3. Open FCV on running pump
- 4. Notify IMD
- 5. Decrease FCV of non-operating pump to minimum
- 6. When < 350 rpm, place breakers on non-running pump 1- PTL.
Unit Supervisor Response:
- Directs artia ,, pet LOA-RR-101, Rct, i,,ccirculation Sy-.-em
- I' Opcratorsi' EIev Event
Description:
The lo-- ,,, o.' KV AC Bus 152 will :,c'loss of Condesate
.'. IB ,onte DflIps. 1HDO45B and ,,,.1 this trips the 'F . orkw suction pressure.
I ' .cnai 01 (lOG
Scenario #4 Time/Notes Expected Crew Response Key Events Loss of Bus tS2/Loss of FW (Cont'd) 4-8 ~ RR Line Break/ Small LOCA (Corit'd) 4-9
.* 'A' Condensate/Booster Pump Fails to Auto Start (Cont'd) 4-101 ~
Panel Operator Response:
Takes actions per LGA-,))I when level drops below 12.5 inches:
RPV Pressure C. -itrol Leg Depressurize RPV using Turbine Bypass Valves at <100°F/hour RPV Level Cont:1l Leg 0 CONTROL Level +' I to +59.5 inches using Preferred Systems (FW Pumps unavailable., CRD pumps and 'C' condensate/booster pump available at <500 gpa7)
- If cannot restore leve. above 11 inches and hold it there then hold level above -150 inches.
- If cannot hold level d:'ove -150 inches, Enter LGA-004, Blowdown Per LGA-004 0 VERIFY Drywell Pressure is greater than 1.69 psig CRITICAL VERIFY Suppression Pool Level is greater than -18 feet STEP INITIATE ADS (usi,.g BOTH pushbuttons)
- VERIFY 7 ADS Valves are OPEN
- WAIT until Shutdov. n Cooling Interlocks clear (135 psig)
- COOLDOWN to Co&J Shutdown using Shutdown Cooling (per LOP-RH-07)
Unit Supervisor Response:
Directs actions per LGA-001 (See Panel Operator Response above)
SSTE7P Directs actions per LGA-004, Blowdown (See panel operator response above)
TERMINUS: ?
PA:\Lazv!! E:xa-n\Sccnario4.d -c 1-7
Scenaw- -,#4 Simulator Operator:
Event imf mrc 040 20 120 Event Event 5 imf mcp 005 rnf mni 098 125 Event imf mai 003 ; then take stby IN comp to STOP 7rom dwg IN I Event - imf mrdc 036 5 300 Event mnb 080 0
.. a. Exam\Sccnario4.doc
LaSalle County Station Operations Scenario #5 Exam Date: April 8, 2002 Developed By: Raymond Keith Walton Date: March 24, 2002
Scenario #5 NARRATIVE
SUMMARY
The unit is increasing power from 85%. The SRO will direct shutting down of RCIC after which a spurious Div I RCIC isolation signal will occur but 2 valves will not automatic":.y isolate. The RO will receive a call from the field indicating a high flow condition in the CRD s'.,em due to the CRD flow control valve failing open. A pre-inserted failure will simulate a broken containment monitoring instrument line result in a failure of division I drywell pressure indication and fail division 1 ECCS and EDG automatic initiation and prevent remote operation of Division 1 drywell spray. This will be followed by a major steam leak inside containment.
Scenario segments
"* Power ramp (from 85% to 100% power)
"* Shutdown RCIC
"* Spurious RCIC isolation with failure of two valves to automatically isolate.
"* Steam leak inside containment
"* Broken Containment monitoring instrument line PALasalle Exam\Scenario5rL .doc
Scenario #5 SHIFT TURNOVER INFORMATION z Day of week and shift
- Today, Day Shift z Weather conditions
- Warm, mid-summer
- Windy
= (Plant power levels)
- Unit 1- 88% Power, 109% FCL Unit 2 - 100 % Power, 108.5% FCL 4
+ 2960 MWt 3489 MWt
- 1017 MWe 4 1189 MWe
+ 77 Mlbm/hr CORE FLOW 93 Mlbm/hr CORE FLOW
= Thermal Limit Problems/Power Evolutions
+ Power Ascension for load follovx-x + None (300Mwe/hr)
=> Existing LCOs, date of next sur- :illance
- RCIC inop for testing + None SLOSs in progress or major maintenance
- I A RHR Pump in Suppression P :-1 Cooling Mode.
=> Equipment to be taken out of or returned to service this shift/maintenance on major plant equipment
- None
- None
-Ž Comnments, evolutio;iý, pio lcms.-tc.
, Online Risk is CG: * .,i: Safety is Green
- Unit I is in a Division 1 work v .-k 4 TLO Tempcraturc ntrU in .-. :.nual i':,Lillc Exam\Sccnario5rl .dLu'. 5
Scenario #5 SIMULATOR SETUP A. CARDS/TAGS TO BE HUNG:
- 1. None B. MISCELLANEOUS:
Timeclock Board 1.
C. TURNOVER INSTRUCTIONS:
- Gather the crew in an appropriate classroom setting and turnover sheet to provide a shift turnover. Stress the following items:
- 1. Unit is at 88% power increasing power using recirc FCV.
- 2. RCIC started for post maintenance testing after an oil change.
- 4. 1A RHR in suppression pool cooling mode.
- 5. Unit 2 at Full Power.
- 6. Complete all pre-evolutionary briefs before taking the watch.
P:\ ,asalle Exam\Scenario5r I .oc 6
Scenario #5 Event 5-1 Initiation: After completion of shift turnover and cue from lead examiner.
Time/Notes Expected Crew Response Power rIncrease with Recirculation Flow Reactor Operator Response:
Takes actions to establish a power ramp per LGP-3-1 to increase load:
"* INCREASE core flow per LOP-RR-07
"* At a rate up to 300 MWe/hour
"* At a higher rate specified by a QNE LOP-RR-107:
"* Verify manual light on recirculation loop flow controller M/A station AMB is ON.
"* Change flow evenly in both loops by pressing RAISE button and observing flow indication to flow controller MIA station.
BOP Operator Response:
- Places additional Condensate polishers in service as necessary per LOP-CP-02
- MAINTAIN condensate flow through the polishers per LOP-CD-03 Unit Supervisor Response:
"* DIRECTS crew to increase power at <300 MWe/hour to 100% power using recirculation flow
"* Notifies Electric Operations of power change
"* Enforces OPS expectations and standards
"* Ensures RO monitors critical parameters carefully
"* Ensures operations are conducted within bounds of TS TERMINUS: Clearly observable plant response from change in power level.
P :\Lasalle Exam\Scenario5r I .doc 7