ML070230512
| ML070230512 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/13/2006 |
| From: | NRC/RGN-III/DRS/OLB |
| To: | Exelon Generation Co |
| References | |
| 50-373/06-301, 50-374/06-301 | |
| Download: ML070230512 (30) | |
Text
Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Scenario No.: 1 Op-Test No.: 2006-301 Examiners: Operators:
Initial Conditions: 100% RTP; RCIC is OOS, day 3 of a scheduled 3 day outage.
Turnover: Maintain power at 100% RTP except as required ot perform TSV/EOC-RPT Functional Test. RCIC is OOS, day 3 of a scheduled 3 day outage and expected to be returned to service early next shift..
Event Malf. Event Event No. No. Type* Description I BOP Perform TSV Scram and EOC-RPT Functional Test.
1 (TS) SRO TSV-2 fails surveillance.
2 R RO/SRO Commence 200 Mwe Load Decrease.
C RO 3 A RR FCV controller failure.
(TS) SRO 4 C RO/SRO Loss of Hydrogen Seal Oil.
M ALL Degraded off-site power supplies leading to Loss of 5 C BOP Off-Site Power. Division 2 EDG fails to auto start.
(TS) SRO Degraded/Loss of cooling to Division 1 DG results in loss 6 C BOP/SRO of bus 141Y.
7 M ALL Station Blackout - recovery of Division 2 EDG.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Simulator Setup CAEP ILT / RI OOS, cse Event 1: imf rl258 off ior qr007 sg7 on Event 2: no actions Event 3: When directed from Expert - imf mrc039 0 120 Event 4: Override Recirc Pp On light ON Override Recirc Pp Off light OFF Override Amber light TRG 4 Override alarm RO855 TRG 4 ON Event 5: 241Y Not Live From SAT
Op-Test No.: 2006-301 Scenario No.: 1 Event No.: 1 Page 3 of 10 Event
Description:
Perform TSV Scram and EOC-RPT Functional Test. TSV-2 fails surveillance.
Time Position Applicants Actions or Behavior SRO Directs performance of LOS-RP-Q2 Performs the Turbine Stop Valve Scram and EOC-RPT Functional BOP Test, LOS-RP-Q2. While testing TSV-2, determine TSV-2 did not respond correctly.
Observes & reports correct indications for TSV-1 while testing COMM TSV-1, reports #2 TSV status light on 1B Trip System 1H13-P611 failed to de-energize.
Monitors plant, peer checks BOP. Reports that the reactor RO protection annunciator 603-B-210, 1 / 2 TSV NOT FULL OPEN, failed to energize.
BOP Reports failed surveillance to SRO, stops surveillance.
Refers to Tech Spec 3.3.1.1 and 3.3.4.1. May refer to 3.2.2 (not SRO applicable)
Op-Test No.: 2006-301 Scenario No.: 1 Event No.: 2 Page 4 of 10 Event
Description:
Commence 200 Mwe Load Decrease.
Time Position Applicants Actions or Behavior DIRECTS crew to reduce power at <300 MWe/hour for load SRO following to 70 Mlbm/hr. Notifies Electric Operations of power reduction Takes actions to establish a power ramp per LGP-3-1 to decrease RO load. Reduces core flow using Attachment C unless otherwise directed by the QNE at a rate up to 300 MWe/hour.
Monitors secondary plant, peer checks RO. Removes condensate BOP polishers from service when no longer needed per LOP-CP-03.
Maintains condensate flow through the polishers per LOP-CD-03.
NRC Remind SRO to have NSO perform reactivity manipulation.
As Shift Manager, direct power reduction using FCVs. Reduce COMM power by 200 MWe.
Op-Test No.: 2006-301 Scenario No.: 1 Event No.: 3 Page 5 of 10 Event
Description:
During load decrease A RR FCV controller fails such that valve continues to close until locked up by operator. Resultant flow mismatch will require TS evaluation.
Time Position Applicants Actions or Behavior Directs actions of LOA-RR-101 for RR FCV failing closed.
Determines core flow mismatch is >allowed.
Starts a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time clock per Tech Spec 3.4.1 condition F.
SRO Refers to T/S 3.4.2 A-1.
Contacts QNE to evaluate concerns for balancing loop flows Contacts System Engineering and IMD for assistance.
Takes actions per LOA-RR-101 for RR FCV failing closed.
Presses HPU TRIP pushbuttons.
Checks core flow and loop flows less than T/S mismatch (w/in RO 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).
Checks instrumentation for indications of fuel damage.
SRO Direct RO to balance flows using B FCV.
Monitors secondary plant, peer checks RO, receives direction from BOP SRO.
Op-Test No.: 2006-301 Scenario No.: 1 Event No.: 4 Page 6 of 10 Event
Description:
Loss of Hydrogen Seal Oil (Hydrogen pressure will slowly degrade, allowing the SRO time to begin a controlled plant shutdown.
Time Position Applicants Actions or Behavior Takes action per LOR-1PM02J-B102:
Verifies the Hydrogen Seal Oil Pump is tripped.
Verifies the Emergency Seal Oil Pump starts.
BOP Dispatches an NLO to Seal Oil Skid and panel 1PL19J and Breaker (136Y-3) to investigate.
Verifies H2 Purity is maintained >90%
Direct actions per LOR-1PM02J-B101, B102, B105.
SRO Direct plant shutdown.
When the ESOP trips:
Verify Hydrogen Seal Oil pressure is being maintained by Turbine Bearing Oil pressure.
If Main Generator Gas pressure drops to <30 psig then trips the BOP Main Generator and make PA announcement to:
STAND CLEAR of the Main Generator DO NOT WELD or BURN in Main Generator area DO NOT START or STOP electrical equipment in Main Generator area Verifies BOP information. Monitors reactor, begins preparations to RO shutdown the reactor plant.
SRO May direct a reactor scram and actions IAW LGP 3-2.
If SRO directs SCRAM:
Arms & depresses scram buttons in both RPS trip systems.
Places Reactor Mode Switch to SHUTDOWN.
Checks all Control Rods in and power decreasing.
Informs Supervisor of Control Rod Status and Reactor Power.
Op-Test No.: 2006-301 Scenario No.: 1 Event No.: 4 Page 7 of 10 Event
Description:
Loss of Hydrogen Seal Oil (Hydrogen pressure will slowly degrade, allowing the SRO time to begin a controlled plant shutdown.
Time Position Applicants Actions or Behavior Operates feedwater and/or ECCS as necessary within the level band of 32" to 45" or as specified by Unit Supervisor; After initial level shrink following Scram, as level begins to recover, trip one TDRFP and close its discharge valve.
Start MDRFP and verify proper operation (by control room indications).
Place FRV and LFFRV in AUTO.
If MDRFP can maintain level, trip running TDRFP and close its RO/BOP discharge valve.
Report to Unit Supervisor the status (and trend) of Reactor Water Level and Pressure.
Verify Reactor Recirc Pumps have downshifted.
Verify Main Turbine/Generator Trip.
Opens Bypass Valves to control reactor pressure <1020psig.
Opens Main Steam Line Drains.
Operates RWCU per LOP-RT-13.
Op-Test No.: 2006-301 Scenario No.: 1 Event No.: 5 Page 8 of 10 Event
Description:
Degraded off-site power supplies leading to Loss of Off-Site Power.
Division 2 EDG fails to auto start. (If SRO orders scram from previous event, Event 5 will not have Main Generator voltage oscillations.)
Time Position Applicants Actions or Behavior Identifies voltage regulator oscillations/off-site power fluctuations.
Places voltage regulator in manual.
BOP Refers to LOP-TG-02 fig. 2 for operating limits with the Main Gen.
Volt. Reg. In Manual.
Directs Panel Operator to place main generator voltage regulator in Manual.
Notifies Shift Manager.
Contacts System Engineering for Technical support.
Contacts Electrical Maint. For support.
SRO Performs crew brief or update on status of Main Generator Voltage Regulator on actions required during any transient due to Manual Voltage Regulation.
May direct scram.
Enters LGA-001.
Reports reactor scram RO Takes scram actions if not taken from Event 4.
Reports EDG 1 start and energize Bus 141Y. Reports failure to BOP start of EDG 0. Reports loss of bus 142Y.
Directs local start of EDG 0.
Enters T/S 3.8.7/3.3.8.1 SRO May direct pressure band of 450-650 psig.
Op-Test No.: 2006-301 Scenario No.: 1 Event No.: 6 Page 9 of 10 Event
Description:
Degraded/Loss of cooling to Division 1 DG results in loss of bus 141Y.
Time Position Applicants Actions or Behavior Loss of EDG:
Takes actions per LOR-1PM01J-B206:
Dispatches NLO to 1A DG control panel to determine BOP cause.
Refer to appropriate LOR procedures Refer to SOE typer Directs actions per LOA-RP-101 Directs actions per LOA-DG-101 SRO Declare 1A DG and one qualified Off-Site circuit INOPERABLE per Technical Specification 3.8.1 Condition A, C and E Loss of Bus 141Y:
Takes actions per the RPS Quick Swap hardcard.
BOP Take action per LOA-AP-101 for loss of 141Y Continues with scram actions. Maintains vessel level/pressure per RO/BOP SRO directives.
Op-Test No.: 2006-301 Scenario No.: 1 Event No.: 7 Page 10 of 10 Event
Description:
Station Blackout.
Time Position Applicants Actions or Behavior Directs entry into LOA AP-101, Attachment K, Station Blackout Contingencies SRO Determines EDG 0 may be restarted. Directs activities to start EDG 0 [Critical Task].
Determines Bus 142 can be re-energized when EDG-0 restarts.
Directs BOP to restore Bus 142Y loads when EDG-0 starts.
Executes LOA AP-101, Attachment K, Station Blackout RO Contingencies, per directive of SRO.
BOP Restores power to Bus 142Y when EDG 0 starts [Critical Task].
Directs recovery activities per LGA-001. When directed by LGA-001, transitions to LGP 2-1, Plant Shutdown.
SRO Restores pressure/level control Restarts necessary AC loads BOP/RO Executes directives to SRO to restore power/loads Upon reaching a stable configuration with one EDG/Bus 142Y energized, terminate scenario.
Facility: LaSalle Co. Station Scenario No.: 2 Op-Test No.: 2006-301 Examiners: Operators:
Initial Conditions: Approximate 20% RTP, both RR Pumps in slow speed with FCVs full open. IC-36 Turnover: Unit shutdown in progress (step E2..14.3 of LGP-2-1) to repair condenser tube leaks. Approximate 20% RTP, both RR Pumps in slow speed with FCVs full open. The MDRFP is in service. Shift will continue to insert control rods per LGP 2-1.
Event Malf. Event Event No. No. Type* Description 1 R RO/SRO Insert control rods until generator output is approx. 60 MWe I RO Two or more IRMs remain greater than 50% scale on range 2
(TS) SRO 10 after IRM detectors are inserted.
3 N BOP/SRO Transfer bus power supplies from in-house to off-site power.
(TS) SRO 5 C RO/SRO MDRFP develops oil leak.
6 M ALL Partial ATWS (several control rods fail to insert).
7 C BOP/SRO Main Turbine auto trip failure w/ TCV stuck open.
CRD pump trips following scram attempt and cannot be 8 C RO/SRO restarted until suction filter trips are bypassed or filters replaced.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Op-Test No.: 2006-301 Scenario No.: 2 Event No.: 1 Page 2 of 10 Event
Description:
Insert control rods until generator output is approximately 60 MWe.
Time Position Applicants Actions or Behavior IAW LGP 2-1, Normal Unit Shutdown, begin inserting control rods RO to reduce reactor power (Step E.2.4) per QNE provided REMA.
SRO Directs insertion of control rods per LGP 2-1.
Monitors secondary plant.
BOP Peer check for RO. (A 4th operator will be allowed in the simulator for reactivity peer checks.)
Op-Test No.: 2006-301 Scenario No.: 2 Event No.: 2 Page 3 of 10 Event
Description:
Two IRMs remain greater than 50% scale on range 10 after IRM detectors are inserted.
Time Position Applicants Actions or Behavior In accordance with step E.2.16 - 17, performs the following for the IRM detectors:
Exercises each IRM range switch from range 1 to 10 four or five times.
Inserts IRM detectors.
RO In accordance with step E.2.17, verifies IRM and APRM channel overlap by at least 1/2 decade. (Overlap is acceptable if all IRMs read less than 50 on range 10 prior to reaching APRM downscale alarms.)
Reports to SRO that two IRMs are reading >50%.
Observes IRM/APRM overlap, determines overlap is unsatisfactory. Refers to appropriate technical specification.
SRO (Tech Spec SR 3.3.1.1) (TRM 3.3.C)
Determines if reactor shutdown can continue.
BOP Continues to monitor secondary plant.
Op-Test No.: 2006-301 Scenario No.: 2 Event No.: 3 Page 4 of 10 Event
Description:
Transfer bus power supplies from in-house to off-site power IAW LGP 2-1.
Time Position Applicants Actions or Behavior Transfers the following to SAT 142 [LOP-AP-14]
Bus 151 through 1512.
Bus 152 through 1522.
Bus 141X through 1415.
BOP Bus 141Y through 1412.
Bus 142X through 1425.
Bus 142Y through 1422.
SRO Directs execution of step E.2.18 in LGP 2-1.
RO Monitors reactor plant, continues with reactor plant shutdown.
Op-Test No.: 2006-301 Scenario No.: 2 Event No.: 4 Page 5 of 10 Event
Description:
Spurious HPCS start.
Time Position Applicants Actions or Behavior Recognizes HPCS inadvertent initiation.
Secures 1B DG By pressing STOP pushbutton.
Prevents re-start of 1B DG by placing Maintenance Switch in MAINT.
Takes actions per LOR-1H13-P601-A205 for HPCS Initiation.
Verifies automatic actions (HPCS aligns for injection).
Checks initiation signal present.
Notifies Shift Manager to classify event & make notifications.
Shuts down HPCS per LOP-HP-04 BOP Verifies HPCS injection is NOT needed by multiple indications Verifies Initiation Signals Clear.
Resets the HPCS logic by depressing both reset pushbuttons Closes 1E22-F004 Injection Valve Verifies 1E22-F012 Minimum Flow Valve opens Stops HPCS pump.
Verifies 1E22-F012 Minimum Flow Valve closes.
When HPCS room fan automatically stops, then shuts down the 1B DG Cooling Water Pump.
When plant conditions permit, places HPCS in standby per LOP-HP-03.
SRO Directs activities of LOR-1H13-P601-A205 for HPCS Initiation.
Op-Test No.: 2006-301 Scenario No.: 2 Event No.: 5 Page 6 of 10 Event
Description:
MDRFP develops oil leak requiring restart of the TDRFP.
Time Position Applicants Actions or Behavior Initiates emergency startup of the Turbine Driven Reactor Feed BOP Pump IAW LOP-FW-04. Trips MDRFP upon completion of TDRFP startup. Takes post-scram actions if SRO directs scram.
May direct startup of the TDRFP, shutdown of the MDRFP.
SRO Directs scram before auto scram on low RPV level.
RO Initiates reactor scram when directed by SRO. Executes LGP 3-2.
Op-Test No.: 2006-301 Scenario No.: 2 Event No.: 6 Page 7 of 10 Event
Description:
When the RO scrams the reactor because of a loss of feedwater (Event 5) some control rods fail to insert. Operators must take action to insert all control rods.
Time Position Applicants Actions or Behavior Directs actions per LGA-001 until entry into LGA-010.
SRO Directs actions per LGA-010.
Takes action per LGP-3-2, completes the actions of the Scram Hard Card and follows up with the procedure when multiple alarms are received; Arms and depresses Scram Pushbuttons Places Reactor Mode Switch in SHUTDOWN Inserts IRMs and SRMs Checks all Control Rods IN and Power Decreasing (not all RO rods in)
Informs Unit Supervisor Of Rod Status and Reactor Power Operate CB as necessary within the level band 32 to 45 inches or as specified by the Unit Supervisor Reports to the Unit Supervisor the status (and trend) of RPV Level and Pressure Verifies Main Turbine and Generator Trip (no)
Stabilizes Reactor Pressure <1020 psig Operates RCIC as necessary within the level band of 32" to 45" or as specified by Unit Supervisor; may reduce reactor pressure to allow RPV level control using condensate booster pumps.
Report to Unit Supervisor the status (and trend) of Reactor Water Level and Pressure.
BOP Verify Reactor Recirc Pumps have downshifted.
Verify Main Turbine/Generator Trip.
Opens Bypass Valves to control reactor pressure <1020psig.
Opens Main Steam Line Drains.
Operates RWCU per LOP-RT-13.
Op-Test No.: 2006-301 Scenario No.: 2 Event No.: 6 Page 8 of 10 Event
Description:
When the RO scrams the reactor because of a loss of feedwater (Event 5) some control rods fail to insert. Operators must take action to insert all control rods.
Time Position Applicants Actions or Behavior Take actions per LGA-010 when directed from LGA-001:
Inhibits ADS.
Prevents injection from HPCS, LPCS and LPCI.
Per the POWER Leg:
Initiates ARI.
Enters LGA-NB-01.
Waits until Cold Shutdown Boron (<3100 gal in SBLC Tank) has been injected.
Per the Pressure Leg:
If SRVs are cycling then OPEN SRVs to lower pressure to 935 psig.
Stabilizes pressure <1059 using turbine bypass valves.
RO/BOP Okay to reduce pressure so 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 psig keeps SRVs closed when LLS is reset.
Per the Level Leg:
Verifies automatic actions occur (Isolations and DGs Start).
If Steam Lines are open then bypass MSIV isolations per LGA-MS-01.
When all rods are in, or Cold Shutdown Boron is injected, or the reactor will stay shutdown without Boron, then exits LGA-010 and enters LGA-001.
Op-Test No.: 2006-301 Scenario No.: 2 Event No.: 7 Page 9 of 10 Event
Description:
Main Turbine auto trip failure with stuck open TCV.
Time Position Applicants Actions or Behavior Determines that the main turbine trip is not complete and RO/BOP completes post-scram actions.
SRO Directs manual main turbine trip.
Trips Main Turbine from control room, reports status of the main RO/BOP turbine to the SRO.
Op-Test No.: 2006-301 Scenario No.: 2 Event No.: 8 Page 10 of 10 Event
Description:
CRD pump trips following scram attempt and cannot be restarted until suction filter trips are bypassed or filters replaced.
Time Position Applicants Actions or Behavior RO Detects trip of CRD pump. Dispatches NLO to CRD Pump area.
Directs an NLO to switch to the STBY suction filter per LOP-RD-14.
When suction pressure low alarm is received, reduces system flow by closing FCV to clear alarm and keep pump from tripping.
When CRD Pump trips, has the NLO expedite switching filters and then starts STBY pump:
If CRD pressure is > 500 psig then immediately starts pump, or Starts pump per LOP-RD-03
Appendix D Scenario Outline Form ES-D-1 Facility: LaSalle Co. Station Scenario No.: 3 Op-Test No.: 2006-301 Examiners: Operators:
Initial Conditions: Approximately 80% RTP; IC 129, down power to 70 Mlb/hr. Start one loop of suppression pool cooling. Insert 06-39.
Turnover: Approximately 80% RTP. LOS RP-WI- Manual 1/2 Scram Test was just completed. Control Rod 06-39 scrammed during the test. Cause was investigated, blown fuse was replaced. RCIC LOS RI-Q3 is critical this shift. Shift manager has determined that LOS RI-Q3 should be done first, Bulk Power needs power, but can wait until LOS RI-Q3 is complete and 06-39 is returned to its full-out position. Once control rod 06-39 is at notch 48, contact Bulk Power and tell them you are ready to return to rated power. Special Rema.
Event Malf. Event Event No. No. Type* Description N/C BOP RCIC fails pump surveillance.
1 (TS) SRO C RO Control rod drift (control rod continues to move out after 2
(TS) SRO single notch withdrawal).
SRO receives report from system engineer that fuel oil 3 (TS) SRO analysis for the common unit diesel generator indicates that fuel oil particulate concentration is out of specification.
TDRFP high vibration leading to removal of pump from 4 C BOP/SRO service.
5 C RO/SRO CRD flow control valve fails open.
A RR pumps seals sequentially fail resulting in a LOCA.
6 M ALL A loop cannot be isolated.
HPCS pump water hammer causes a pipe break down 7 C BOP stream of the pump (inside the HPCS pump room) that cannot be immediately isolated.
HPCS line break partially drains suppression pool to HPCS 8 M ALL room.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Op-Test No.: 2006-301 Scenario No.: 3 Event No.: 1 Page 2 of 10 Event
Description:
Conduct LOS RI-Q3 Surveillance.
Time Position Applicants Actions or Behavior Start RCIC system per LOS-RI-Q3. Begin at Step 5.0 Respond to annunciators for low lube pressure and high bearing temp (1H13-P601-103, RCIC TURB OIL PRESS BOP LO, 104, RCIC TURBINE TRIP, and 105, RCIC PMP DISCH FLOW LO.
Secures RCIC system Dispatches an NLO to RCIC room determine system status Directs operator to start RCIC IAW LOS-RI-Q3 at Step 5.0 Directs operator to shutdown RCIC IAW LOP RI-03, RCIC SRO Isolation & System Shutdown.
Refers to Tech Spec 3.5.3.A-1, A-2.
This event is a Technical Specification exercise for the Unit Supervisor. The event trigger simulates an oil leak on the RCIC SIM turbine leading to high bearing temp and low lube pressure. To simulate RCIC turbine oil leak, activate the Event Trigger number 1 (imf r0550 on, and imf r0552 on)
Op-Test No.: 2006-301 Scenario No.: 3 Event No.: 2 Page 3 of 10 Event
Description:
Control rod drift (control rod continues to move out after single notch withdrawal).
Time Position Applicants Actions or Behavior Responds to 1H13-P603-A-504, CRD DRIFT.
Enters and executes applicable steps of LOA-RD-101, Control Rod Drive Abnormal (Step B.1, Rod Drift/Scram)
Continually checks control rods status:
No more than 1 control rod moving at the same time.
No more than 3 control rods have scrammed or DRIFTED Full In.
RO Check control rods - no control rod currently moving.
Monitor full core display for rod drift lights.
Monitor RWM Screen.
MONITOR Four Rod Display.
SELECT drifting control rod.
VERIFY insert block light - OFF at rod select matrix.
Check control rod remains at position 04 or less.
If control rod will NOT remain at position 04 or less, depress and hold Insert push-button.
Enters and directs activities of LOA RD-101.
Refers to T.S. 3.1.3 C-1 and C-2., including T.S. Bases, to SRO determine Operability of affected control rod and applicable LCO Required Actions. Contacts QNE.
Op-Test No.: 2006-301 Scenario No.: 3 Event No.: 3 Page 4 of 10 Event
Description:
SRO receives report from system engineer that fuel oil analysis for the common unit diesel generator indicates that fuel oil particulate concentration is out of specification.
Time Position Applicants Actions or Behavior SRO is notified that the Diesel Fuel Oil Monthly Analysis Verification (STORED FUEL OIL), LOS-DO-M1, indicated that the COMM fuel oil for the common unit diesel generator has failed based on oil particulate concentration. Oil particulate concentration is 15 mg/L.
Enters Tech Spec 5.5.10.c & 3.8.3.B.1. Declares 0 Diesel SRO Generator INOPERABLE.
Op-Test No.: 2006-301 Scenario No.: 3 Event No.: 4 Page 5 of 10 Event
Description:
TDRFP high vibration leading to removal of pump from service.
Time Position Applicants Actions or Behavior Takes action per LOR-1PM02J-A403 for 1B TDRFP vibrations:
Checks 1B TDRFP vibration >3 mils Starts the MDRFP per LOP-FW-03 before 4 mils Shuts down 1B TDRFP per LOP-FW-05 before 5 mils IF vibration exceeds 5 mils, TRIP 1B TDRFP (SRO may order TDRFP trip before actually reaching 5 mils.
Takes action to start the MDRFP per LOP-FW-03 starting at Step 2.3 Dispatch NLO to perform pre-start checks (okay to start)
Verifies Min Flow Valve M/A station is in AUTO Verifies 1FW005 FRV M/A station is in MANUAL and at zero.
BOP Verifies 1FW146 LFCV M/A station is in MANUAL and at zero Verifies 1FW003 FRV Throttle valve is OPEN Verifies 1FW145 LFCV Upstream Isolation valve is OPEN Verifies 1PM03J-A102 NPSH alarm is CLEAR Verifies MDRFP Auxiliary Oil Pump is running Verifies RPV Level is lower than Level-8 Notifies NLO to perform local actions Starts MDRFP using control switch Verifies motor amps stabilize below 441 amps Verifies 1FW008 Min Flow valve indicates 60% OPEN Checks MDRFP discharge pressure >850 psig Shuts down MDRFP Auxiliary Oil pump SRO Directs start of MDRFP, shutdown of TDRFP.
Op-Test No.: 2006-301 Scenario No.: 3 Event No.: 4 Page 6 of 10 Event
Description:
TDRFP high vibration leading to removal of pump from service.
Time Position Applicants Actions or Behavior Takes actions per LOP-RL-01 to swap 1B TDRFP to MDRFP:
At 1DS001 selects transfer sequence B TDRFP to FRV and press START Verifies AUTO control of RPV level as MDRFP flow increases When FRV demand reaches common control output, BOP verifies 1B TDRFP M/A station transfers to MANUAL and FRV M/A station transfers to AUTO.
Checks 1B TDRFP starts to ramp off line after 3-minutes.
Verifies 1B TDRFP Min Flow valve starts to open at 4.9 Mlb/hr Transfers LFFRV M/A to AUTO Refers to LOP-FW-05 to shutdown the 1B TDRFP Directs activities of LOR-1PM02J-A403 for 1B TDRFP vibrations, SRO LOP-FW-03 and LOP-FW-05. May direct a reactor scram.
As an NLO sent to investigate the 1B TDRFP wait 2 minutes and then report that you cant really tell but it sounds louder than Comm:
normal. As to have the Field Supervisor meet you on the turbine deck outside the door to the 1B TDRFP room.
As the Field Supervisor wait 2 minutes after being sent to the 1B TDRFP room, then report that you think the 1B TDRFP is making Comm:
more noise than usual. Recommend shutting down the 1B TDRFP and calling MMD and System Engineering for assistance.
Op-Test No.: 2006-301 Scenario No.: 3 Event No.: 5 Page 7 of 10 Event
Description:
CRD flow control valve fails open causing degradation of RR pump seals due to thermal shock.
Time Position Applicants Actions or Behavior Enters and executes applicable steps of LOA-RD-101, Control Rod Drive Abnormal (Step B.3, CRD Flow Control Valve Failure)
Check DRIFT lights - OFF.
Check the following CRD parameters NORMAL:
CRD system flow approximately 63 gpm. (maximum flow)
Cooling Header P <30 psid.
Drive Water Header P < 600 psid.
Transfer Flow Controller, 1C11-R600, to MANUAL.
RO Adjust Flow Controller Output using OPEN/CLOSE pushbuttons to restore parameters to normal.
IF Flow Controller Output will not adjust, then locally verify instrument air is lined up to and is available to CRD Manual /Auto Station.
Throttle Drive Water PCV 1C11-F003 as required to restore parameters to normal.
Determine flow is extremely high, possible RR pump seal failure.
SRO Directs actions of LOA-RD-101.
RO May direct NLO to swap flow control valves.
Op-Test No.: 2006-301 Scenario No.: 3 Event No.: 6 Page 8 of 10 Event
Description:
1A RR pumps seals fail. A loop cannot be isolated. Small break LOCA occurs after CRD FCV failure to keep containment pressure/temperature rising to force LGA entry.
Time Position Applicants Actions or Behavior As drywell pressure rises, scram reactor.
RO Execute steps of LGP 3-2, Reactor Scram Maintains vessel level with FW until transferred to RCIC/HPCS.
Enters LGA-001, directs operators to scram reactor, execute steps SRO of LGP 3-2.
Enters LGA-003, Primary Containment Control.
Follows steps of LGP 3-2 Maintains RPV pressure using bypass valves/SRVs BOP Secures HPCS when directed Detects lowering Suppression Pool
Op-Test No.: 2006-301 Scenario No.: 3 Event No.: 7 Page 9 of 10 Event
Description:
When HPCS pump is started a water hammer causes a pipe break down stream of the pump (inside the HPCS pump room) that cannot be immediately isolated.
Time Position Applicants Actions or Behavior Recognizes when pump starts, it appears to be a normal start, then amps decrease, flow increases above normal. Diagnoses BOP discharge line break.
Reports to Unit Supervisor, requests permission to isolate HPCS.
Directs BOP to secure HPCS to preserve water inventory.
Op-Test No.: 2006-301 Scenario No.: 3 Event No.: 8 Page 10 of 10 Event
Description:
HPCS line break partially drains suppression pool to HPCS room.
Time Position Applicants Actions or Behavior Takes action per LOR-1PM13J-B304 for RB SE-SW Equip Drn Sump Trouble:
Dispatch NLO to sump to determine cause Verify second pump started if high-high level Refer to LOP-RE-01T to determine source of leakage Notify Unit Supervisor Notify Radiation Protection Takes actions per LOA-FLD-001 for flooding in Reactor Building Check for source of flooding (FP Leak)
Close valves to limit flooding input (if directed, leak can be isolated)
RO Shutdown pumps feeding flood (0A and 0B DFPs, Intermediate Jockey and Jockey Pumps)
ENTER LGA-002 Check water level stabilized or decreasing (no)
Evacuate building elevations below 710 feet (2-feet in SW corner room)
Shutdown running equipment in area (HPCS Water Leg Pump, CRD Pumps)
Close water tight doors Evaluate extent of flooding (SW corner room only)
Determine impact on technical specifications (T/S 3.5.1 for HPCS)
Declare affected safety equipment inoperable (HPCS)
Classify E-plan per EALs (HA5)
Takes actions per LGA-002 for flooding in SW Corner Room SRO Operate sump pumps to restore and hold below overflowing Isolate all discharges into affected area (except FP/LGA required)
Wait until 2 or more areas above max safe (only one area is flooding)