ML030840265
| ML030840265 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/09/2002 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Keenan J Carolina Power & Light Co |
| References | |
| 50-324/03-301, 50-325/03-301 | |
| Download: ML030840265 (58) | |
See also: IR 05000325/2003301
Text
Final Submittal
BRUNSWICK EXAM
50-2003-301
50-325 & 50-324
FEBRUARY 10 - 14 & 19, 2003
As Given Simulator Scenario Operator Actions ES
D-2
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
SIMULATOR SCENARIO
BNP-03-Cl
LESSON TITLE: Medium Break LOCA inside containment with Loss of Offsite Power
and failure of one EDG
REVISION NO: 00 APPROXIMATE TIME REQUIRED: Mins.
RECOMMENDED BY: *--* I*U I' "
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
1/2>
SHIFT TURNOVER
CURRENT PLANT STATUS
Unit Two is operating at approximately 28% power, following a down power to repair
a steam leak in the hot side. Applicable steps of GP-12 have been completed for
the down power. The steam leak has been repaired.
MSIV testing is in progress per PT-40.2.8, and has been completed except for B21
F028D. Feedwater control is in single element for this PT. The test is complete to
step 7.10.2.10.
The National Weather Service has issued severe thunderstorm warnings for
Brunswick and New Hanover Counties for the next two hours.
EQUIPMENT OUT OF SERVICE
APRM Channel 1 is failed downscale and is bypassed. I&C is currently
troubleshooting this failure.
No other equipment is out of service.
PLAN OF THE DAY
Complete MSIV testing per PT-40.2.8. I&C is available, and on station in the back
panels, to support completion of this PT.
When PT-40.2.8 is complete, commence power ascension per GP-12. The Reactor
Engineer has provided Control Rod Movement instructions per GP-12, Attachment
1. The Reactor Engineer recommends rod withdrawal per GP-12 instructions to
achieve the target rod pattern, then raising core flow to achieve rated power.
The Reactor Engineer has requested a temporary hold after withdrawa! of the Ist two
sets of Control Rods on the GP-12, Attachment 1. The Reactor Engineer reports
that the 1s' two sets of rods will place the unit at approximately 38% power and just
below the 80% rod line.
When the Reactor Engineer concurs, continue power ascension to rated power.
3C1 Page 2 of 24 Rev.00
Facility: Brunswick Scenario No.: 1 Op-Test No.:
Title: Medium Break LOCA inside containment with Loss of Offsite Power and failure of one
Examiners: Operators:
Initial Conditions: The crew assumes the shift with the plant at 27% power, BOL. Power
ascension is in progress per GP-12. HPCI is 0OS, the #1 APRM failed low and is bypassed.
Severe weather has been reported in the area. The previous shift completed partial
stroking of all MSIVs except D outboard
Turnover The plan of the day is to partial stroke the D outboard MSIV per PT-40.2.8 and
then to increase power to 40%. The Reactor Engineer recommends using control rods per
attached GP-12 instructions (continuous withdrawal acceptable).
Event Malf. No. Event Event
No. Type* Description
1 N/A N(RO) Partial stroke D Outboard MSIV
2 N/A R(RO) Increase power from 28% to 38%.
(SRO)
3 MRD018F C (RO) A CRD Pump suction filter plugged.
4 MNI037F I (RO) HPCI logic fuse blown.
5 MCN017F C (BOP) AOG Guard Bed Fire
(SRO)
6 MRC007F C (RO) A Recirc Pump Seal Leak.
MRC009F (SRO)
7 MEE032 M (ALL) Loss of Offsite Power
Rod 22-19 Fails to Insert
8 MDG002F C (BOP) One EDG fails to start
Note: This event is combined with Event 7 in one D-2
9 MNB0O9F M (ALL) 1000 GPM leak inside drywell
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
3C1 Page 3 of 24 Rev.00
EVENT 1 COMPLETE MSIV TESTING
Simulator Operator Activities
0VWhen the MSIV B21-F028D red light comes on, as I&C report C72-K3G contacts 1
2 & 3-4 are open; 5-6 & 7-8 are closed at P609 and C72-K3H contacts 1-2 & 3-4 are
open; 5-6 & 7-8 are closed on P611.
o When MSIV B21-F028D indicates open, report as I&C C72-K3G contacts 1-2 & 3-4
are closed; 5-6 & 7-8 are open at P609 and C72-K3H contacts 1-2 & 3-4 are closed;
5-6 & 7-8 are open on P611.
El When requested, report that MSIV DC & AC coil lights (P622/P623)
lights/indications are illuminated
Examiner Notes
Li No noticeable changes is steam flow or reactorpressure are expected during the
MSIV stroke
Operator Activities
SCO
ol Conduct shift turnover shift briefing.
ol Direct the BOP to perform the MSIV functional surveillance for the D Outboard MSIV
per procedure PT-40.2.8, and complete the PT.
El Notify IST Engineer when test is complete.
3C1 Page 4 of 24 Rev.O0
EVENT 1 COMPLETE MSIV TESTING (Con't)
01 Perform board walk-down.
o Obtain and review Precautions and Limitations of PT-40.2.8. Request RO to
monitor Rx Pressure and Main Steam Line Flow during valve stroking.
EO Confirm that annunciators A-05 1-7 and 1-8 are clear (Reactor Auto Scram Sys A &
B).
0 Depress and hold Outboard MSIV D Test, B21-F028D push button, and confirm
relay operation with I&C.
O1 Release Outboard MSIV D Test, B21-F028D push button, confirm B21-F028D
returns to full open, and confirm relay operation with I&C.
o1 Confirm that annunciators A-05 1-7 and 1-8 are clear (Reactor Auto Scram Sys A &
B).
o] Transfer Feedwater Control Mode Selector Switch to 3-Elem per OP-32, Section
8.2.
O1 Confirm annunciators A-05 4-6, A05 1-7, A05 1-8 and A07 4-2 are clear.
Ol Verify scram group lights lit on P603, P609 and P611.
Ol Confirm that MSIV DC & AC coil lights (P622/P623) lights/indications are
illuminated. (NOTE: not modeled in simulator)
o Record required information on cover page.
o Notify SCO test is complete.
O1 Perform board walk-down.
ol Monitor the plant during MSIV testing, especially Main Steam Flow and Reactor
Pressure.
3C1 Page 5 of 24 Rev.O0
EVENT 2 POWER ASCENSION
Simulator Operator Activities
U] Adjust MSR second stage as requested.
ExaminerNotes
El First two sets of rods on Rod Movement Instruction will raisepower to --38%.
ol First set of rods will likely bring in RBM upscale by notch 24. Second set of rods,
RBM is bypassed (peripheralrods)
Operator Activities
SCO
ol Inform load dispatcher of power increase
Eo Direct the RO to increase power in accordance with OGP-12. Specify using
withdrawal of Control Rods in per GP-12, Attachment 1
ol Direct the BOP to monitor BOP plant operation, perform Attachment 2 each 10%
change and start a 2 nd Condensate Booster Pump per OP-32.
o1 Withdraw control rods per Reactor Engineer instructions.
- Turn Rod Select power On and select desired rod
- Ensure ROD WITHDRAWAL PERMISSIVE is lit
- Hold EMERGENCY ROD IN NOTCH OVERRIDE to OVERRIDE and NOTCH
OUT as desired for continuous withdrawal (for continuous withdrawal from 16-22,
operator should release as soon as rod indicates 19)
- Release both switches and ensure rod settles to desired position
- 1s' set of rods are from 16-24, the operator is expected to stop continuous
withdrawal (if used) at notch 22, and single notch to 24
- 2nd set of rods are 24-48 and may be continuously withdrawn to 48 (no stop at 46
required). Coupling check must be completed at position 48.
- Place ROD SELECT POWER to OFF at end of rod movement
E0 If RBM upscale alarms, inform SCO, refer to APPs, de-select then re-select control
rod for continued motion if required.
3C1 Page 6 of 24 Rev.00
EVENT 2 POWER ASCENSION (Con't)
0 Monitor BOP plant during power ascension.
o Perform GP-12, Attachment 2 at approximately 30% power.
Obtain valid Heat Balance (Display 820) and record on Table 1
Obtain LPRM % Pwr (Display 861) and record on Table 1
Obtain total steam flow (from individual steam flow indicators or computer point
B041
Run MAN program (type in heat balance power and steam flow), or NE (screen 6)
to obtain steam flow alternate power and record in Table 1
Compare Heat Balance to other alternate indications, (Heat Balance > all alternate
indications, or within 5%
C Direct AO to adjust Low Load Valve Panel Loaders at 15 minute intervals per OP-36
o1 Ensure MVD-MOV-CA-4/3/1/2 are closed when turbine load reaches approximately
240 MWE
o1 Start a second Condensate Booster Pump, if directed by Unit SCO
0 Ifrequired, repeat GP-12, Attachment 2 at approximately 40% power (See above)
3C1 Page 7 of 24 Rev.00
EVENT 3 CRD PUMP SUCTION FILTER CLOGGED
Simulator Operator Activities
Lii When directed by lead examiner, insert MFRD018F
o Ifrequested to report suction filter dp, wait until pump trips and report 0 psid
o Ifrequested to shift suction filters, wait 5 minutes and delete MFRD018F
Examiner Notes
El From insertion of the malfunction, it takes approximately 7 minutes for the hi dp
alarm, and approximately 2 additionalminutes for the pump trip.
Operator Activities
SCO
o1 Direct actions of APP A-05 5-1
ol When CRD trips, direct entry into AOP-02.0
Eo Direct maintenance to clean CRD suction filter
E] Direct CRD restarted per OP-08, Section 8.17
o Observe alarm CRD Pump Inlet Filter DP High alarm and monitor CRD parameters
o Review APP A-05 6-1
ol Dispatch AO to check suction filter dp, and shift suction filters per OP-08
0 When CRD trips, enter and announce AOP-02.0
RO actions continued next page
3C1 Page 8 of 24 Rev.O0
EVENT 3 CRD PUMP SUCTION FILTER CLOGGED (Con't)
RO (Con't)
0 When AO reports suction filters shifted, start CRD following pump trip per OP-08,
Section 8.17as follows:
Check Recirc Pump seal temperature (back panel TR-R601) (Points 9 & 21)
Place CRD Flow Control to Man and reduce pot to minimum
Open PCV F003
Ensure RBCCW in operation
Start CRD Pump A or B
Raise CRD flow to 30-60 gpm using manual pot
NullICRD Flow Control using setpoint tape
Shift CRD Flow Control to Auto
Adjust setpoint tape to maintain cooling dp 10-26 psid
Ensure CRD flow is 30-60 gpm
Establish drive water dp 260-275 psid by throttling closed PCV F003
EO Monitor CRD operation per Section 6.0
0l Monitor the plant.
3C1 Page 9 of 24 Rev.00
EVENT 4 HPCI BLOWN LOGIC FUSE
Simulator Operator Activities
C3 When requested by lead examiner activate HPCI malfunctions
O1 If asked as AO to investigate, report all circuit breakers in DC Panel 4A are closed
Ol Ifasked as I&C to investigate, report fuse E41A-F1 in panel P620 is blown (blows
again if replaced)
Ol If requested open breakers for E41-F041 and F042 when valves are shut
Examiner Notes
-
Suppression pool suction valves auto open (will re-open again if closed)
O CST Suction valve remains open (can be closed)
Operator Activities
SCO
EO Direct actions of APP
O Contact maintenance to investigate
O Direct HPCI be isolated per OP-19
o Refer to Tech Spec 3.5.1, determine action D applies
ol Refer to 01-01.08 for reportability (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, loss of single train) (may be follow-up
question)
Ol Diagnose and report HPCI logic power loss
Ol Refer to APP A-01 5-5
Ol Direct AO to DC Panel 4A to check for tripped breakers
Ol Close HPCI CST Suction F004
O Isolate HPCI per OP-19 (Close E41-F002 and E41-F003)
El Close vacuum breaker isolation F075
Ol Close Suppression Pool Suction valves F041 & F042 (requires AO to be dispatched
to MCC to shut off breakers)
3C1 Page 10 of 24 Rev.00
El Monitor the plant
3C1I Page 11 of 24 Rev.00
EVENT 5 AOG GUARD BED FIRE
Simulator Operator Activities
7VWhen directed by the lead examiner, insert MFCN017F
Eo If asked, as AO initially report Guard Bed temperatures have significantly increased
but reheater temperatures are normal
ol When directed to locally isolate the Guard Bed, acknowledge the request (simulator
function not available)
o] When directed to initiate nitrogen purge, ensure AOG valve local switches match
actual valve position, then request control room place AOG master switch to Local.
ol Initiate nitrogen purge by opening NP-79, XCV-141, and XCV-143. When purge
initiated, delete MFCN017F, and report local temperature indication shows
temperatures are dropping
Examiner Notes
[] The initial alarm (Guard Bed D1 Hi Temp) directs local isolation of Guard Bed
O The GuardBed D1 Hi Temp alarm will be shortly followed by Adsorber D2-D6 Hi
Temp alarms in rapid succession. These alarms requiredbypass and isolation of
AOG from the control room
o Even when the fire malfunction is deleted, and purge initiated,is takes a long time
(=I hour) for temperatureindications to return on-scale on control room recorders
(<100 OF)
Operator Activities
SCO
ol Direct actions of APP for Guard Bed Hi Temp
ol Direct Guard Bed locally isolated and nitrogen purge per OP-33
ol When Adsorber Hi Temp alarms come in, direct AOG be bypassed and isolated
o1 Refer to ODCM 7.3.10 for AOG being bypassed
o Notify HP and Ops Management of problem
o1 Refer to PEP for fire (may be follow up question)
ol Monitor the plant
See Next Page
3C1 Page 12 of 24 Rev.00
EVENT 5 AOG GUARD BED FIRE (Con't)
ol Acknowledge receipt of 2-AOG-D1 Guard Bed Temperature High alarm and inform
ol Request AO to observe AOG parameters at local panel H2E
ol Ensure AOG HVAC equipment is normal
O3 Direct AO to bypass and Isolate guard bed (local valves)
Open 2-AOG-V013 and 2-AOG-V014 THEN, Close 2-AOG-VO09, 2-AOG-V010, 2
AOG-V01 1 and 2-AOG-V012
ol Monitor guard bed temperatures. - Ifguard bed continues to rise, direct AO to purge
with N2 per OP-33, Section 8.5
o1 When Adsorber Temp alarms received, bypass and isolate the AOG system:
Open 2-AOG-HVC-1 02, then
Close XVC-147, 148,141,143, and 142
0 When requested by AO, place AOG control to Local
3C1 Page 13 of 24 Rev.O0
EVENT 6 RECIRC PUMP A SEAL FAILURE
Simulator Operator Activities
0V When directed by lead examiner, insert MF_RC007F
O When directed by lead examiner, insert MF RC009F
ol If requested, as AO report seal injection flow at 4 gpm and seal staging flow at 1.8
gpm
ol If asked as Reactor Engineer, report plant operating below the 80% rod line
ExaminerNotes
LI Initial indications are of a #1 seal failure, followed by indicationsof failure of the #2
seal
E] AOP-14.0 directs shutdown of the Recirc Pump per OP-02. Due to potential
instabilityconcerns SRO may direct to Transfer to One Loop operation per OP-02
ratherthan tripping the Pump
ol Drywell pressure may approach 1.7 psig before the Recirc Pump can be secured
and isolated. The SRO should direct a manual scram priorto the automatic scram if
it becomes evident a scram is imminent
Operator Activities
SCO
0 Direct actions for APP for Seal Staging Flow Hi/Lo
ol Refer to OP-02 (Precaution & Limitation 3.11) for guidance on sudden seal pressure
increases
ol Direct preparations to shutdown Recirc Pump A
ol When indications of second seal failure, monitor drywell parameters and direct entry
into AOP-14.0
EO Direct Recirc Pump A be shutdown and isolated per guidance of APP or OP-02
ol Refer to 01-01.08 for Selected Out Of Service Contingencies (may be follow up if not
referenced)
ol Direct drywell venting via SBGT per OP-10
13 If drywell pressure approaches 1.7 psig, and a scram is imminent, direct a manual scram
C If the Recirc Pump is shutdown and isolated, refer to Tech Spec 3.4.1, and
determine LCO is not met, and that LCO must be met within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
K
3C1 Page 14 of 24 Rev.00
EVENT 6 RECIRC PUMP A SEAL FAILURE (Con't)
El Observe Pump A Seal Staging Flow High/Low alarm and notify SRO.
o Perform actions for APP
Verify seal injection valve V22 and staging valve V14 are open.
Dispatch AO to ensure seal injection flow is 3-5 gpm and report seal staging flow
locally
Monitor seal cavity pressures, report to SRO indications of seal #1 failure
Monitor seal temperatures on recorder B32-R601 (if directed by SRO)
Monitor drywell pressure
El When AO reports seal staging flow, determine indications of #1 seal failure and
report to SRO
o Observe Outer Seal Leakage Flow Detection Hi alarm and notify SRO.
ol Observe changing seal DPs and notify SRO that BOTH seals have failed.
Eo Report rising trend on drywell temperature and pressure, enter and announce AOP
14.0
ol If directed by SRO, trip and isolate Recirc Pump A
o3 If directed by SRO transfer to one loop operation per OP-02
0 Isolate A Recirc Pump (Critical Task, Sequence Is NOT Critical)
Close suction valve
Close discharge valve
Isolate seal purge (from CRD)
Close discharge bypass valve
E0 If directed by SCO, insert a manual scram
3Cl Page 15 of 24 Rev.00
EVENT 6 RECIRC PUMP A SEAL FAILURE (Con't)
0 If directed, monitor seal temperatures in back panel
0 Monitor containment parameters
0 When second seal fails report rising drywell pressure
0 Enter and announce AOP-14.0
0 Vent primary containment via SBGT per OP-10
Record reading on main stack rad monitor recorder, and determine venting must
be secured if reading rises by 1.7.
Close Reactor Building Suction Valves (VA-2D-BFV-RB, and VA-2H-BFV-RB)
Open DW Suction Valve VA-2F-BFV-RB
Open DW Purge Valves CAC-V9 and V23
Open DW Head Vents CAC-V49 and V50, if desired (NOT normally desired)
Monitor Main Stack Rad Monitor
3C1 Page 16 of 24 Rev.00
EVENT 6 RECIRC PUMP A SEAL FAILURE (Con't)
Examiner Notes
0 These actions are applicable only if the Reactor scrams as a result of the seal failure
ol Rod 22-19 fails to insert on scram
o1 If Loss Of Off-Site Power is initiatedprior to the crew isolating Recirc Pump A, the
Pump cannot be isolated due to power loss to the Suction Valve (unless E Buses
are cross-tied)
Operator Activities
SCO
o1 Enter and direct EOP-01-RSP
o] Enter and direct EOP-01-RVCP (Determine the Reactor will remain shutdown under
all conditions without boron with only one rod out)
o1 Enter and direct EOP-02-PCCP
ol Direct Recirc Pump A secured and isolated (PC/P leg of PCCP)
o1 Direct RPV level control +170-200" (RC/L leg of RVCP)
ol Direct RPV pressure control (800-1000 psig is preferred band) (RC/P leg of RVCP)
o1 Direct verification of auto actuations and isolation (LL1 and Hi DW Press) (RC/L leg
of RVCP)
o Perform scram immediate actions (EOP User's Guide)
When APRMs downscale, trip the main turbine
When steam flow <3 mlbm/hr, place Mode Switch to Shutdown
Ensure Level Set at +170"
(Note, Immediate action to trip a RFP is not applicable since only one RFP is in
operation)
0 Recognize and report failure of one rod to scram, all other rods full in
RO Actions continued next page
3C1 Page 17 of 24 Rev.O0
EVENT 6 RECIRC PUMP A SEAL FAILURE (Con't)
RO (Con't)
o1 Shutdown, then isolate Recirc Pump A (Critical Task, Sequence is NOT Critical)
Close suction valve
Close discharge valve
Isolate seal purge (from CRD)
Close discharge bypass valve
ol Control RPV level +170-200" (SULCV)
O] Control RPV pressure in band specified by SRO (EHC)
El Verify auto actuations and isolations (LL1 and Hi DW Press)
Ol Perform Scram Hard Card Actions
Insert Nuclear Instrumentation
Place Recirc Speed Control to 10%
Trip Heater Drain Pumps
Ensure Turbine Oil system operation
El Verify auto actuations and isolations (LL1 and Hi DW Press)
3C1 Page 18 of 24 Rev.00
EVENT 7 LOSS OF OFF-SITE POWER
Simulator Operator Activities
11 When directed by the lead examiner, insert MFEE032F.
o1 If asked, as Unit 1, report you can support cross-tie of service air
o3 As AO perform actions requested for LOOP (service air cross-tie, RCC cooling, AB
panel transfer)
Examiner Notes
E] One rod (22-19) fails to insert, all other rods are full in
o DG4 fails to auto start, can be started by depressing Auto Mode Start. Once
running, DG4 breaker will fail to auto close, can be manually closed
o DG3 will auto start and tie, DG3 will trip on differential overcurrent one minut Safter
the loss of power malfunction
Operator Activities
SCO
El Enter and direct EOP-01-RSP
o May enter and direct EOP-01-RVCP (Determine the Reactor will remain shutdown
under all conditions without boron with only one rod out)
ol Direct actions of AOP-36.1
ol Direct RPV level control +170-200" using RCIC/CRD (RSP or RC/L of RVCP)
ol Direct RPV pressure control using SRVs (800-1000 psig is preferred band) (RSP or
RC/P of RVCP)
O3 Direct verification of auto actuations and isolation (LL1 and Hi DW Press) (RSP or
RC/L of RVCP)
ol Enter and direct EOP-02-PCCP when torus temperature reaches 95°F
ol Direct RHR Loop B be placed in suppression pool cooling (SPIT of PCCP)
o1 Direct maintenance to investigate DG3 failure and trip
RO next page
3C1 Page 19 of 24 Rev.00
EVENT 7 LOSS OF OFF-SITE POWER (Con't)
o Perform scram immediate actions (EOP User's Guide)
Place Mode Switch to Shutdown (only applicable action)
(Note, No RFP is in operation, Turbine is tripped)
o) Recognize and report failure of one rod to scram, all other rods full in
0 Operate SRVs to control RPV pressure as directed by the SRO (use opening
sequence specified on Hard Card)
Eo Ifrequired start RCIC per the Hard Card for RPV level control (Flow may be raised
to 500 GPM) (See attached copy of Hard Card)
o Ifrequired, start CRD for level control per SEP-09 and/or the Hard Card
Ensure CRD Pump running
ol Place RHR Loop B in suppression pool cooling per the Hard Card (using NSW) (See
attached copy of Hard Card, examinee should align cooling from NSW)
ol Verify auto actuations and isolation (LL1 and Hi DW Press)
See Page 20 of 23
3C1 Page 20 of 24 Rev.00
EVENT 8 LOSS OF OFF-SITE POWER - ONE DG FAILS TO START
o1 Enter and announce AOP-36.1
ol Start DG4 by depressing Auto Mode Start push button (Critical Task)
ol When DG4 is running, close output breaker by turning on synch switch and closing
breaker (Critical Task)
ol Recognize DG3 trip on fault and report electric plant status to SRO (E4 only
energized bus)
o] Verify Auto Actions of AOP-36.1 (DC oil pumps and isolations)
o Place PCB Auto Reclosure Switches to OFF
o Ensure available SW Pumps running, start CSW Pump B (may align to NSW header
for SPC operation)
El Ensure battery chargers operating
o Start Control Room and battery Room HVAC
Ensure CB Inst Air Compr B operation (in Auto)
Start Ctl Room A/C Spare Supply Fan
Start Battery Room 2B Vent Fans
EO Restore Drywell Cooling. (Direct AO to close SW-V193 and open SW-V146)
O1 Direct AO to open Service Air Cross-tie, SA-V7
Ol Close SW-V3 to support suppression pool cooling
O1 Direct AO to transfer 2AB, 32AB and 2AB-RX to alternate power
ol Direct AO to restart RPS MG Set
El Restart CRD per OP-08 (or SEP-09 if directed), if not already complete by RO
Place CRD Flow Control to Man and reduce pot to minimum
Open PCV F003
Start CRD Pump B
3C1 Page 21 of 24 Rev.O0
EVENT 9 LINE BREAK IN THE DRYWELL
Simulator Operator Activities
U[ When directed by the lead examiner initiate MFNBO09F.
El Perform actions as requested (CRD Flow Max, SLC to Demin Water, E7-E8 cross
tie, securing DW coolers)
Examiner Notes
U The leak will start small, then develop into a leak in excess of the capacity of
available high pressure injection
o3 When RPV level drops to LL3 (+45') the ADS timers will start (83 seconds). The
SRO may direct inhibiting ADS, or may elect to allow ADS to automaticallyinitiate.
Operator Activities
SCO
ol Recognize rising drywell temperature/pressure and diagnose as line break in the
drywell
o1 Direct E Bus cross-tie operation (480 VAC E7-E8)
o Direct maximization of available high pressure injection systems to restore/maintain
RPV level +170-200" (RC/L of RVCP)
Direct RCIC flow at 500 GPM (if not already done)
Direct CRD Flow Max per SEP-09 (if not already done)
Direct Alternate Coolant Injection per LEP-01 (SLC using Demin Water)
ol Before suppression chamber pressure exceeds 11.5 psig, direct suppression
chamber spray per SEP-03 (PC/P of PCCP)
ol When suppression chamber pressure exceeds 11.5 psig, direct drywell spray per
SEP-02 (PC/P of PCCP)
0 When RPV level drops to LL3 (+45") direct verification of ECCS actuations (may
direct RHR removed from containment spray operation due to imminent emergency
depressurization, or may wait until depressurization begins) (RCIL of RVCP)
ol May direct inhibiting ADS (RC/L of RVCP)
o If ADS is inhibited, direct emergency depressurization when RPV level drops to TAF
(LL4 at the latest) (RC/L of RVCP) (Critical Task)
SCO Actions continued next page
3C1 Page 22 of 24 Rev.00
EVENT 9 LINE BREAK IN THE DRYWELL (Con't)
SCO (Con't)
o1 When ADS valves are open, direct RPV level restored and maintained +170-200"
(RC/L of RVCP)
o Direct RHR returned to containment cooling/spray when RPV level is maintained
normal. (SPIT and/or PC/P of PCCP)
ol Recognize rising drywell temperature/pressure and diagnose as line break in the
drywell
o1 Maximize RCIC flow (500 GPM, if not already done)
o1 Maximize CRD flow per SEP-09 and/or the Hard Card (if not already done)
o1 Enter Alternate Coolant Injection, request AO align SLC to Demin Water, and start
SLC when complete
o1 Monitor RPV level and provide frequent reports, with trends, to the SRO
o3 Place RHR in suppression chamber spray per SEP-03 as directed by the SRO
o) Place RHR in drywell spray per SEP-02 as directed by the SRO
ol At LL3 verify auto initiation of ECCS
o1 Inhibit ADS if directed by SRO
ol If directed by SRO, open 7 ADS valves for emergency depressurization (Critical
Task)
ol When RPV pressure drops to 400 psig, ensure LP ECCS (RHR A & B, and Core
Spray B injection valves open)
o Ensure RHR aligned for LPCI injection (spray valves are closed, if not already done)
Ol At 300 psig, ensure injection from Core Spray B, and that Recirc Pump discharge
and discharge bypass valves are closed
Eo At 200 psig, ensure injection from RHR A & B (Loop A flow instrument does not
have power unless E7-E8 cross-tie actions are complete)
RO Continued next page
3C1 Page 23 of 24 Rev.00
EVENT 9 LINE BREAK IN THE DRYWELL (Con't)
ol Operate RHR and Core Spray to restore/maintain RPV level +170-200" (should use
Core Spray as required to maintain level, leaving RHR available for containment
cooling/spray operation)
El Place RHR in containment cooling/spray operation as directed by SRO
ol Ifdirected by SRO, perform actions of AOP-36.1 to cross-tie E Buses
Determine 4KV Buses El-E3 cannot be cross-tied (differential overcurrent trip on
DG3) and proceed with 480V Bus E7-E8 cross-tie
Direct AO to rack in E7-E8 cross-tie breakers
Open Sub E7 480V Main Breaker (must be opened to satisfy cross-tie breaker
interlock)
Open Bus E3 to Sub E7 breaker
Close Bus E7 Tie To Bus E8 breaker
EC Assist RO in operating containment spray/cooling systems, and/or injection systems
as directed by the SRO
ol Assist RO in operating LP ECCS during emergency depressurization to
restore/maintain RPV level +170-200"
3C1 Page 24 of 24 Rev.00
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
SIMULATOR SCENARIO
LESSON TITLE: Steam leak outside containment with ATWS
REVISION NO: 00 APPROXIMATE TIME REQUIRED: Mins.
RECOMMENDED BY:
UM I
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
SHIFT BRIEFING
Plant Status
The plant is operating at 90% power, Middle Of Cycle. Power is currently at 90%
per the load dispatcher's request.
Equipment Out Of Service
RHR Pump 2C is under clearance to repair the motor breaker and is expected to be
returned to service in approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Condensate Booster Pump 2A is under clearance for motor bearing replacement will
remain under clearance this shift.
No other equipment is out of service.
Plan of the Day
When contacted by the load dispatcher, raise reactor power to 100%.
Routine maintenance is scheduled for CRD Pump 2A. When shift turnover is
complete, place CRD Pump 2B in service and secure CRD Pump 2A.
No other activities are scheduled for this shift.
3C2 Page 2 of 20 Rev.00
Facility: Brunswick Scenario No.: 2 Op-Test No.:
Title: Steam leak outside containment with ATWS
Examiners: Operators:
0
Initial Conditions: The crew assumes the shift with the plant at 90% power, Mid Life. The IA
Condensate Booster Pump is OOC.
Turnover: Night orders include direction to shift CRD pumps, and to place TBCCW Pump 2C
in service and secure TBCCW Pump 2A.
Event Malf. No. Event Event
No. Type* Description
I N/A N(RO) Shift CRD Pumps per OP-08
N/A R(RO) Raise reactor power to 100%
2 RD005M C(RO) Rod 18-19 Drift Out
3 MES010F C(BOP and Inadvertent HPCI initiation.
RO*)
- Assume
RO stays
at RX Pnl
4 N/A R (RO) Reduce power in preparation for removing 5A0 RFP
from service
5 MCF01OF C (BOP) IB0 Condensate Booster Pump Trip and rB0 RFP Trip
MCF036F (Low Suction Pressure).
6 MCF027F C(BOP) Manual shutdown/Trip of lAr RFP, Steam Leak from
C(RO*)trips RCIC
- RCIC
upon
initiation
7 MRP009F M(ALL) ATWS
(N)ormal, (R)eactivity, (I)nstrument, (C;)omponent, (ivi)ajor
3C2 Page 3 of 20 Rev.00
EVENT 1 NORMAL OPERATIONS
Simulator Operator
U Ifrequested, as AO report pre-start and local checks complete for CRD Pump 2B.
o1 If asked, as Unit 1, report your TBCCW Pump 2C control is in Idle
ol When CRD Pump 2B and TCC Pump 2C are in service, call control room as load
dispatcher and request power increase to 100%. Ifasked as Reactor Engineer,
report no restrictions on power rise.
ExaminerNotes
L] If RO asks for peer check for reactivity manipulation,the RO will be provided with a
peer check
Operator Activities
SCO
E0 Conduct shift turnover shift briefing.
11 Direct RO to shift CRD Pumps per OP-08
E0 When contacted by load dispatcher, direct RO to raise reactor power to 100% using
Recirc flow.
0 Perform board walk-down.
o Monitor the plant.
o Shift CRD Pumps per OP-08 as follows:
Ensure Suction, Discharge and Recirc Valves for Pump B are locked open (local)
Shift CRD Flow Control to Bal
Null CRD Flow Control using manual pot
Shift CRD Flow Control to Man
Set CRD flow to 35 gpm
Start CRD Pump B
Stop CRD Pump A
Continued next page
3C2 Page 4 of 20 Rev.00
EVENT 1 NORMAL OPERATIONS (Con't)
RO (Con't)
Null CRD Flow using setpoint tape
Shift CRD Flow Control to Auto
Ensure CRD flow rate is between 30 and 60 gpm
ol Monitor operation of CRD per OP-08, Section 6.0
o3 Request peer check for reactivity manipulations
o Increase Recirc flow, one pump at a time in increments of 2-4% to achieve rated
power. (Maintain pump speeds within 10% per LCO 3.4.1)
ol During power ascension, monitors nuclear instrumentation, Recirc System
parameters (i.e. pump speed, core flow)
o Periodically null DVM during power ascension and when power ascension is
complete (raise Gen Manual Volt Regulator on XU-1)
o1 Perform board walk-down.
ol Monitor the plant.
0 Perform alternate power verification per GP-12 at rated power
3C2 Page 5 of 20 Rev.O0
EVENT 2 ROD OUT DRIFT
Simulator Operator
77 When directed by the lead examiner, insert MFRD005M for rod 18-19.
o1 Delete MFRD05M for rod 18-19 when green full in light is lit
Examiner Notes
El Rod 18-19 slowly drifts out, can be momentarily arrestedby an insert signal, but will
continue to drift out when the insert signal is released
O Rod will successfully latch only when driven to full in (00)
Operator Activities
SCO
o1 Direct actions of APP A-05 3-2
o Direct rod 18-19 fully inserted
o Refer to AOP-03.0, Positive Reactivity Addition (may also refer to AOP-02.0, Control
Rod Malfunction/Misposition)
o] Inform Reactor Engineer of rod drift
o1 Declare control rod 18-19 Inoperable and enter LCO 3.1.3, Condition C (insert within
3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, disarm within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
o Direct maintenance to investigate rod problem
o Respond to rod drift per APP A-05 3-2 and report to SRO
o1 Determine from core display that the alarm is for rod 18-19
o1 Turn rod select power on and select rod 18-19
o1 Determine rod 18-19 is drifting out
o] Attempt to arrest drifting rod by giving rod an insert signal
o] Recognize failure to arrest rod and fully insert rod 18-19
o Recognize and report to SRO successful latching of rod 18-19 at 00
0 Reset rod drift
3C2 Page 6 of 20 Rev.00
BOP Next Page
3C2 Page 7 of 20 Rev.00
EVENT 2 ROD OUT DRIFT (Con't)
o1 Assist RO in rod drift actions
o Monitor main steam line and off-gas radiation monitors
o Enter and announce AOP-03.0 (Positive Reactivity Addition) and/or AOP-02.0
(Control Rod Malfunction/Misposition) if directed by the SRO
3C2 Page 8 of 20 Rev.00
EVENT 3 INADVERTENT HPCI INITIATION
Simulator Operator
[] When directed by the lead examiner, initiate MFES01OF
o1 When HPCI AOP is placed to P-T-L, insert MFES016F
Examiner Notes
Ul Whoever sees HPCI initiation 1st will respond at P601 to terminate HPCI (may be
o1 Once HPCI oil pump is locked out, HPCI will be unavailable for the remainderof the
scenario (oil pump trips on magnetic overload when started)
Operator Activities
SCO
0 Direct entry into AOP-03.0
El Direct termination of HPCI operation
El Direct reduction of reactor power as required to prevent a scram
o1 Direct I&C to investigate HPCI initiation
o1 Contact Reactor Engineer to monitor thermal limits
o Declare HPCI inoperable and enter required actions of LCO 3.5.1, Condition D, and
determine LCO 3.5.1 Condition E also applies since an RHR Pump is under
clearance
o1 Refer to 01-01.07 for reporting requirements (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> report due to loss of single
train) (may be follow up, if not addressed during scenario)
RO/BOP
ol Recognize and report inadvertent HPCI initiation
ol Verify by two independent indications misoperation of HPCI
o Perform AOP-03 immediate actions to terminate HPCI operation
Depress and hold HPCI turbine trip push button
When HPCI speed indicates 0 RPM, place Aux Oil Pump to Pull-To-Lock
Release HPCI turbine trip pushbutton and ensure HPCI stop valve remains closed
3C2 Page 9 of 20 Rev.00
0l Ifdirected, verify RCIC in standby alignment per RTGB dot convention
EVENT 3 INADVERTENT HPCI INITIATION (Con't)
BOP/RO
01 Enter and announce AOP-03.0
C Reduce reactor power as necessary to maintain *100% and/or prevent a reactor
3C2 Page 10 of 20 Rev.00
EVENT 4 OIL LEAK ON RFP A
Simulator Operator
Li When directed by lead examiner, insert alarm override for RFP A Oil Tank Hi/Lo.
0 When requested, as AO report unisolable oil leak on RFP A oil system, tank level 3"
below normal and slowly lowering
Examiner Notes
rI The alarm is an override of the alarm only, the actual oil leak malfunction is not
inserted until the next event
Operator Activities
SCO
M--Direct actions of APP UA-04 4-2.
ol Direct maintenance to attempt to repair oil leak
o1 Direct monitoring of RFP bearing oil drain temperature
ol Direct power reduction per ENP-24 to shutdown RFP A
o1 Request peer check for reactivity manipulation
o Reduce power per ENP-24 as directed by SRO
Reduce core flow to 43 mlbm/hr (Both Recirc controllers can be operated
simultaneously during rapidpower reduction, the rate of core flow reduction is
dependent on the crew's sense of urgency to reduce power)
When core flow is 43 mlbm/hr, insert rods per ENP-24 (1st rod on ENP-24 is rod
that earlierwas inserted due to drift, and will not be at position specified on the
immediate power reduction form)
o Report oil tank hi/Io level alarm and perform APP-UA-04 4-2
0 Dispatch AO to determine if tank level is high or low
o1 Monitor RFP A bearing oil drain temperature (PC display 450, or RFA-TR-757)
3C2 Page 11 of 20 Rev.00
EVENT 5 CONDENSATE BOOSTER PUMP B & RFP B TRIPS
Simulator Operator
U7When power has been reduced by Ž_10%, or as directed by the lead examiner,
initiate RFP A oil leak, Condensate Booster Pump B trip, and after 15 seconds RFP
B trip on low suction pressure.
Examiner Notes
[] Recirc will auto runback to speed limiter #2 when RPV level drops to + 182"
o The reactorwill enter the Scram Avoidance Region of the power/flow map, requiring
control rod insertion to exit the region (raisingcore flow would exceed capacity of a
single RFP and require the runbacks to be reset)
o Upon initiation of the oil leak malfunction, the low oil level alarm will be received
iný1.5 minutes RFPA will trip in --9.25 minutes
Operator Activities
SCO
El Direct entry into AOP-23.0 (Condensate/Feedwater System Failure)
ol Direct entry into AOP-04.0 (Low Core Flow)
o1 Direct control rod insertion to exit Scram Avoidance Region of power/flow map
o] May direct manual scram due to imminent loss of only operating RFP
0l (If time permits) reduce Recirc A & B speed demand to 45% (Operatoris expected
to stop manual flow reduction once auto runback occurs)
o1 Verify automatic runback to speed limiter #2 (=34% speed demand)
o1 Insert control rods to exit Scram Avoidance Region (1s' two sets of rods should be
sufficient)
o1 Ifdirected by SRO insert a manual reactor scram
BOP next page
3C2 Page 12 of 20 Rev.00
EVENT 5 CONDENSATE BOOSTER PUMP B & RFP B TRIPS (Con't)
o1 Recognize and report trip of Condensate Booster Pump B
El Recognize and report trip of RFP B
o1 Enter and announce AOP-23.0 (Condensate/Feedwater System Failure)
ol Determine operation is in Scram Avoidance Region and inform SCO
o Enter and announce AOP-04.0 (Low Core Flow)
3C2 Page 13 of 20 Rev.00
EVENT6 RFP A TRIPS
Simulator Operator
p]
Examiner Notes
0- Initialpower on the scram will be =12-15%
Operator Activities
SCO
01 Direct manual scram (if not already done)
0 Enter EOP-01-RSP and immediately transition to EOP-01-LPC
o1 Insert manual scram as directed by SRO (or insert manual scram if RPV level
approaching LL scram set point - +166)
o Recognize failure of control rods to insert and announce ATWS
C Report reactor power above APRM downscale set point (2%)
0 Report trip of RFP A
0] Recognize and report ATWS
3C2 Page 14 of 20 Rev.00
EVENT 7 ATWS/RCIC STEAM LEAK (INITIAL ACTIONS)
Simulator Operator
7rI Ifrequested to perform circuit alterations for Group 1 LL3 and LEP-02, perform
requested actions (wait until approved by lead examiner before installing LEP-02
jumpers)
Examiner Notes
El Power will drop below APRM downscale relatively quickly once SLC is initiated
ol The SRO is expected to initially direct actions of the power control leg of LPC
(RC/Q), then immediately transition to the level leg (RC/L)
o1 Actions performed by RO and BOP are interchangeabledepending on SRO
direction
o Actions assume MSIVs remain open
Operator Activities
SCO
ol Direct Mode Switch in Shutdown when steam flow <3 mlbm/hr (RC/Q of LPC)
o1 Direct initiation of ARI (RC/Q of LPC)
o7Direct Recirc Pump speed controllers to 10% (RC/Q of LPC)
o1 Direct Recirc Pumps tripped (RC/Q of LPC)
o1 Direct SLC Initiation (RC/Q of LPC)
o Direct ADS inhibited (RC/Q and RC/L of LPC)
11 Direct verification of RWCU isolation (RC/Q of LPC)
o1 Direct Alternate Control Rod Insertion per LEP-02 (RC/Q of LPC) (Critical Task)
ol Request Group I LL3 be bypassed (RCIL of LPC)
ol If power >APRM downscale and RPV level >90", direct injection to RPV be
terminated and prevented per RC/L-17 (CRD, SLC and RCIC excluded) (RC/L of
LPC)
RO/BOP next page
3C2, Page 15 of 20 Rev.00
EVIENT 7 ATWS/RCIC STEAM LEAK (INITIAL ACTIONS)
0]
Place Mode Switch in Shutdown when steam flow <3 mlbm/hr
0] Verify or manually initiate ARI (2 switch manipulation)
0]
Place Recirc Pump Speed controllers to 10%
0]
Trip Recirc Pumps
0]
Perform Alternate Control Rod Insertion LEP-02 (Critical Tasik, details on
following pages)
o Inhibit ADS
o1 Initiate SLC
o Verify RWCU isolation
0 Terminate and prevent injection from HPCI (already done since AOP is in P-T-L)
0 Terminate and prevent injection from feedwater by closing FW-V6 and FW-V8 on
XU-2 (RFPs already tripped)
3C2 Page 16 of 20 Rev.00
Simulator Operator
07When requested, perform field actions to reset RCIC overspeed trip
ExaminerNotes
El When RPV level drops to LL2, RCIC auto initiates, then trips on overspeed
o1 If HPCI AOP is taken from P-T-L, the AOP will trip
Operator Activities
SCO
5-When APRMs are downscale and RPV level is below +90 inches, direct RPV level
be maintained LL4 to +90 inches (+60-+90 preferred to avoid LOCA actuations)
fl-Insert control rods per LEP-02, Section 5
Start 2nd CRID Pump
Place CRD Flow Control to MAN and use pot to open FCV to raise drive water
pressure >260 psig
Bypass RWM
Turn rod select power On
Select control rods and insert using Emergency Rod In
ol Recognize RCIC trip
EO Start HPCI, determine Aux Oil Pump trip on magnetic overload
o1 Determine RCIC trip on overspeed (close RCIC TT&TV actuator and determine
TT&TV cannot be reopened)
ol Dispatch AO to reset RCIC mechanical trip
BOP Continued next page
3C2 Page 17 of 20 Rev.00
BOP (Con't)
0 Restart RCIC following Turbine trip with initiation signal present per the HARD
CARD
Place RCIC Control to Man and reduce output to 0
Slowly jog open TT&TV until governor controls speed
Fully open TT&TV
Raise RCIC Manual Control until flow >120 gpm
Place RCIC control to Auto
3C2 Page 18 of 20 Rev.O0
EVENT 7 RCIC STEAM LEAK
Simulator Operator
LU When RCIC is started, at direction form lead examiner, initiate malfunction RCIC
Steam in South RHR Room
o AS AO report steam from -17 south side and you have left the Reactor Building
ExaminerNotes
U PC/C fails to auto isolate on steam leak detection and/orsteam line break DP
detection. RCIC manual isolation will function and is critical.
o Attempts to manually isolate RCIC are unsuccessful
ol RHR Room CoolerA will operate, RHR Room Cooler B will fail
ol Subsequent manual scram per LEP-02 will insert all rods
o] An entry condition into EOP-03-SCCP,Secondary Containment Control, will not
exist until Steam Leak Detection alarm is received, Reactor Building radiationlevels
don't increase significantlysince the Reactor is shutdown
Operator Activities
SCO
o Direct entry into AOP-05.0
El If RHR reaches max normal temperature, enter and direct EOP-03-SCCP
o1 Direct RHR Room Coolers started and vital header aligned
o1 Determine leak from RCIC, direct RCIC isolation (Critical Task, must be directed
when auto isolation fails)
El When all rods in, determine conditions met to exit LPC
El Direct terminating SLC operation
ol Enter EOP-01-RVCP and direct RPV level restored and maintained +170-200"
(RC/L of RVCP) (Only available injection is CRD, SLC may be restartedper EOP
01-LEP-01)
RO/BOP next page
3C2 Page 19 of 20 Rev.00
EVENT 7 RCIC STEAM LEAK
o1 Continue inserting control rods per LEP-02, Section 5
o1 Insert control rods per LEP-02, Section 3
Reset ARI by placing Auto/Inop/Trip switch to Inop and place Reset Switch to
Reset
Request scram jumpers be installed
When RPS Jumpers installed, place SDV Test switch to Isolate and ensure SDV
Vent and Drain Valves are closed
Reset RPS
Place SDV Test Switch to Normal and ensure SDV Vent and Drain Valves open
After 2 minutes (or when SDV Hi-Hi RPS Trip clears, insert manual scram
Recognize and report rod motion
Report when all rods (or all rods but one) are full in
ol Terminate SLC operation when directed by SCO
o Enter and announce AOP-05
o Evacuate Reactor Building
ol Direct AO to close PIV-33
o3 Manually isolate RCIC when directed by SCO, or may isolate without SCO direction
if an isolation setpoint is exceeded (Critical Task)
ol Ensure RHR Room Coolers running and align vital header cooling by opening SW
V 11 or SW-Vi 17 (RHR Room Cooler B will fail, SW-VI 17 will auto open if RPV
level drops to LL3)
3C2 Page 20 of 20 Rev.O0
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
SIMULATOR SCENARIO
BNP-03-C3
LESSON TITLE: Unisolable RWCU Rupture Requiring Reactor Depressurization
REVISION NO: 00 APPROXIMATE TIME REQUIRED: Mins.
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
SHIFT BRIEFING
Plant Status
The plant is operating at 100% power, middle of cycle.
Equipment Out Of Service
SLC Pump 2B is under clearance after tripping during surveillance testing last shift.
A&C is currently investigating.
No other equipment is out of service.
Plan of the Day
Maintain 100% power.
No special activities are scheduled for this shift.
3.C.3 Page 2 of 13 Rev.00
Facility: Brunswick Scenario No.: 3 Op-Test No.:
Title: Steam leak outside containment with ATWS
Examiners: Operators:
Initial Conditions: The crew assumes the shift with the plant at 100% power, Mid Life. SLC
Pump 2B is under clearance.
Turnover: Maintain 100% Dower, no activities scheduled.
Event Malf. No. Event Event
No. Type* Description
I ES022F C(RO) RCIC Inadvertent Initiation with a loss of MCC 2XDB
______(S RO)
2 CN002F C(BOP) Condenser A-N Tube Leak, remove water box
(SRO)
R(RO) Reduce power for water box removal due to tube leak
(SRO)
3 N/A I(RO) Feedwater Master Control Failure requires manual
(SRO) control of reactor level.
4 RWO13F M (ALL) Unisolable RWCU line break requires scram, then
reactor depressurization due to Secondary
Containment Water levels > Max Safe
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
3.C.3 Page 3 of 13 Rev.00
EVENT I RCIC INITIATION/LOSS OF MCC 2XDB
Simulator Operator
U] When directed by lead examiner, initiate Ist event
ExaminerNotes
[] There are no alarms for loss of the DC MCC 2XDB
El RCIC will be running at 41000 RPM (less than RPM limitation)
Operator Activities
SCO
IThirect RCIC be tripped
0 Direct entry into AOP-39.0
O Direct I&C to investigate
o1 Refer to 01-50 for lost loads
o1 Refer to Tech Spec 3.5.3, determine action A applies
El Refer to Tech Spec 3.6.1.3, determine action A or B (B21-F019, E51-F008, E51
F013, B21-F019, E11-F008, G31-F004) and action C (E51-F019, E51-F031) apply
El Determine SLC is inoperable until RWCU is isolated (Tech Spec 3.3.6.1action H)
o3 Determine Tech Spec 3.3.3.2 action A applies for RSP instrumentation
ol Brief crew on affects of MCC loss
f-Diagnose RCIC initiation with loss of MCC 2XDB
o1 Recognize RCIC operation at low speed
11 Enter and announce AOP-39.0
El Dispatch AO to investigate
o1 Refer to 01-50 for affected loads
fl--Monitor the plant
3.C.3 Page 4 of 13 Rev.00
EVENT 2 CONDENSER TUBE LEAK
Simulator Operator
Li When directed by the lead examiner, initiate condenser tube leak.
o As AO perform requested actions for water box removal
ExaminerNotes
[] Condenser Hi Conductivity alarm, followed by other conductivity alarms
o1 OP-29 contains caution that water box removal above 60% may cause loss of
vacuum, but there is no proceduralrequirementto be <60% to begin water box
removal
Operator Activities
SCO
o1 Enter and direct activities of AOP-26.0
o] Direct 2A-N Water box isolated.
o] Direct power be reduced to 60% to support water box removal.
o1 Refer to AI-81 and the TRM for chemistry guidelines and limits
o Ifcondensate pump discharge conductivity exceeds 10 gmho (2-CO-CR-3075),
determine AI-81 action level 3 applies
o Perform power reduction per ENP-24 as directed by SCO for water box removal
Reduce core flow to 43 mlbm/hr, then
Insert control rods specified by ENP-24
BOP (Next Page)
3.C.3 Page 5 of 13 Re'v.00
EVENT 2 CONDENSER TUBE LEAK
o1 Enter and announce AOP-26.0.
ol Monitor reactor water, condensate, feedwater, and hotwell conductivity
ol Determine high conductivity is from A-N water box
C Direct hotwell reject be secured
C Isolate and Drain 2A-N condenser per OP-29 as follows:
Direct AO to secure cathodic protection
Place CW Mode Switch to position for 3 water boxes (month dependent)
Direct AO to place breaker off for CW-V1 5
Place 2A-N water box control switch to Man
Close CW-V1 1
Direct AO to open flush valve CW-V1 76, then turn breaker off
Close Hotwell isolation valves (CO-V1, CO-V1 11, and HD-V53 (all on one control
switch)
Close off-gas outlet valve OG-V3
Direct AO to remove air removal
3.C.3 Page 6 of 13 Rev.00
EVENT 3 FEEDWATER CONTROL SYSTEM FAILURE
Simulator Operator
Li When directed by lead examiner, override Feedwater Master Controller Off.
ExaminerNotes
o] MasterFW Controlleroutput begins to slowly ramp up causing level to rise
ol Operatorcan control level by placing Master Controller(or RFP controllers)in
Manual and adjusting the demand signal
El The longer the raise or lower pushbuttons are depressed, the faster the demand
signals change
Operator Activities
SCO
o1 Direct entry into AOP-23.0
o] Direct manual control of Feedwater to stabilize RPV level
o1 Direct I&C to investigate failure of control system
RO/BOP
El Diagnose and report failure of Feedwater to automatically control level
O] Take manual control of Feedwater Master (or RFP) controllers (AOP-23.0 immediate
action)
o Adjust demand signal to stabilize RPV level, then as required, bring level back into
the green band (+182" to +192") (Feed/Steam flow recorder indication is the best
way to determine required adjustments on manual demand signal)
o1 Continue adjustments as required to maintain RPV level in the normal band
o1 Enter and announce AOP-23.0
3.C.3 Page 7 of 13 Rev.00
EVENT 4 RWCU LINE BREAK
Simulator Operator
U] When directed by the lead examiner, initiate RWCU line break
ExaminerNotes
1Tindicationis Area Rad Hi in the ReactorBuilding, followed by Reactor Building
Sump alarms, and rising 50' temperatures
O] The RCWU rupture will require the
Operator Activities
SCO
o Direct entry into AOP-05.0
o1 Enter and direct EOP-03-SCCP
o1 Direct verification of auto actions (AOP-05.0)
o1 Direct evacuation of the reactor building (AOP-05.0)
0 Diagnose leak from RWCU and direct RWCU isolation (SCCP)
0 Direct RHR room coolers be started (SCCP)
o1 Direct service water aligned to the vital header (SCCP)
ol Contact engineering to perform EQ evaluation (SCCP)
o1 If reactor building loses negative pressure, enter and execute RRCP for
unmonitored release, and request field surveys
o1 Continue to operate Feedwater control in manual to maintain RPV level in the
normal band (will require slowly raising demand signal to maintain constant level as
RWCU break gets bigger, until scram is inserted)
BOP (Next Page)
3.C.3 Page 8 of 13 Rev.00
EVENT 4 RWCU LINE BREAK
o Enter and announce AOP-05.0
o Direct PIV-33 be closed
o Evacuate the reactor building (alarm, then announcement)
o Verify Secondary Containment and group 6 isolation and SBGT initiation if Rx Bldg
Vent exhaust hi-hi rad alarms
ol Diagnose as RWCU leak and attempt to manually isolate by closing G31-FOO1,
recognize and report RWCU inboard valve (F001) failure and inability to isolate
ol Start Both RHR room coolers
o Align service water to the vital header (SW-V1 11 or SW-V1 17)
o Monitor Reactor Building pressure, report when positive
3.C.3 Page 9 of 13 Rev.00
EVENT 4 RWCU LINE BREAK - REACTOR SCRAM
Simulator Operator
[] Do not perform any requested actions in the Reactor Building.
ExaminerNotes
Li Wide Range instruments (N026A/B) cannot be used to determine RPV level once
RB 50' temperatureexceeds 140 OF)
o If RPV level drops and remains below 150 on NOO4s, no direct indication of RPV
level until Recirc Pumps are tripped (then N036/N037 are available) (Indirect
indications of RPV level available through various level alarms and initiationstatus
lights)
ol Incorrect performance of scram immediate actions could result in a Group I
isolation (MSIV closure)
Operator Activities
SCO
o1 Before 50' reaches max safe temp (2000F), direct a manual reactor scram (Critical
Task)
o1 Enter and direct EOP-01-RSP
o Determine entry into EOP-01-RVCP is required, enter and direct
EO Direct verification of group isolations (RC/L of RVCP)
E] Direct maintaining RPV level 170-200" (RC/L of RVCP)
ol Direct pressure control using EHC (RC/P of RVCP)
ol Direct tripping Recirc Pumps for RPV level instrument indication (if level drops below
range of N004s)
RO (Next Page)
3.C.3 Page 10 of 13 Rev.00
EVENT4 RWCU LINE BREAK - REACTOR SCRAM
o3 Insert a manual scram as directed by SCO
o1 Perform scram immediate actions
When APRMs are downscale, trip the main turbine
When steam flow is <3 mlbm/hr, place Mode Switch to Shutdown
Ensure level set to +170"
When reactor level is +170" and rising, if 2 RFPs are in operation, then trip one
o1 Maintain RPV level 170-200" by placing the SULCV in service per the Hard Card
o1 Ensure EHC controls reactor pressure
0 Restart an RFP per the Hard Card if required (high level trip), or start HPCI per the
Hard Card
o Ifrequired, manually start HPCI to maintain RPV level
ol If level drops below range of N004s, recognize and report no direct RPV level
indication is available
ol Trip Recirc pumps if directed by SCO
El Perform scram Hard Card
Trip Heater Drain Pumps
Place Recirc Pump speed controllers to 10%
Ensure Turbine Lube Oil system operation
0 Verify Group isolations for LL1 (Groups 2, 6 and 8)
3.C.3 Page 11 of 13 Rev.00
EVENT 4 RWCU LINE BREAK - REACTOR DEPRESSURIZATION
Simulator Operator
EFNone
ExaminerNotes
Li The leak will result in a slow reduction in pressure without operatoraction
o The crew should initially ensure a cooldown <100 °F/Hr,then anticipateor perform
emergency depressurizationas conditions in Secondary Containmentdeteriorate
Operator Activities
SCO
o1 Direct a reactor cooldown not to exceed 100°F/Hr (SCCP)
o Recognize an area above Max Safe Water Level
o1 Consider anticipating ED per RVCP (SCCP)
C Recognize 2 n' area above max normal water level
ol Direct anticipating ED by rapidly depressurizing to the main condenser (SCCP and
RC/P of RVCP)
o1 Direct not exceeding 3 X 106 Ibm/hr (RC/P of RVCP)
o If2 areas exceed MSOWL, direct emergency depressurization (Critical Task, if ED
is anticipated, then that task should be considered Critical) (SCCP and RC/P of
RVCP)
o Direct control of injection systems during depressurization to maintain 170-200"
RO (Next Page)
3.C.3 Page 12 of 13 Rev.00
EVENT 4 RWCU LINE BREAK - REACTOR DEPRESSURIZATION
o Initiate a reactor cooldown not to exceed 100°F/Hr (may use steam line drains, or
BPVs, or simply allow the reactor to depressurize through the leak).
o] Continue to maintain reactor level +170-200" using Feedwater or HPCI
o Ifdirected, anticipate emergency depressurization
Open Bypass valves using BPV jack
Maintain steam flow <3 mlbm/Hr (red line on steam flow instruments, exceeding
this value results in MSIV closure with Mode Switch not in Run) (Critical Task)
o Ifdirected open 7 ADS valves for emergency depressurization (Critical Task)
ol Recognize/report Flood level Hi and Hi-Hi if alarms
o1 Assist RO as directed by the SCO (BOP may be directed to perform actions to
anticipate emergency depressurization)
3.C.3 Page 13 of 13 Rev.O0