ML072960427
| ML072960427 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/31/2007 |
| From: | - No Known Affiliation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-324/07-301, 50-325/07-301 50-324/07-301, 50-325/07-301 | |
| Download: ML072960427 (67) | |
See also: IR 05000325/2007301
Text
Draft Submittal (Pink Paper)SIMULATOR SCENARIOS BRUNSWICK JULY-AUG EXAM-325,324/2007-301
DRAFT SIMULATOR SCENARIOS (4)
PROGRESS ENERGY CAROLINAS BRUNSWICK TRAINING SECTION 2007 NRC EXA BRUNSWICK JULY-AUG EXAM-325,324/2007-301
DRAFT SIMULATOR SCENARIO 1 OF 4 2007 NRC Examination
Scenario#1
SCENARIO DESCRIPTION
Unit 2 is operating at maximum power, End Of Cycle with level transmitter
N026B and ERFIS out of service.A swap of RB Supply&Exhaust Fans will be required to support maintenance
activities.
Following the swap of RB fans, RBCCW Pump 2C will trip and 2B RBCCW Pump will fail to Auto-Start
on pressure, but will be able to be manuaUy started.2A will runback to cussions with I&C, the eturned to the pre-olers will trip and the RHR Loop"B" can ned causing drywell temperature
to rise cy depressurization (CRITICAL TASK).Following tor pressure and drywell reference leg temperature
will aturation limit ments (N004A, N004C, N036 and N027B)will begin to e leg flashing.With no valid indication
of RPV level, the looding Procedure.
.DG3 will auto start and II be unavailable.
E1 and E3 crew attempts to crosstie E7 7 results in loss of level for RPV level control.Ive will fail to auto open will be shifted to , 2-ABRX and 32AB will be transferred
ailable injection to maximum until at least 5 SRVs are open and Reactor pressur-is at least 50 psig above suppression
chamber pressure (Minimum Reactor Flooding Pressure)(CRITICAL TASK).Once these conditions
are established
the crew will throttle flow to maintain at least the required 50 psig differential
but as low as possible.The onl exhibit indi crew will ente Reactor Instrument
Penetration
line break occur instrument
N026B for Remote Shutdown Pan Specifications
must be addressed.
After restart of the 2B RBCCW Pump, Reactor Recirculation
Limiter#2.After addressing
the Technical Specifications
2A Recirculation
Pump Limiter#2 signal will be reset an.r-'event level.When RPV flooding conditions
havebeenestablished, the scenario may be term*inated.
2007 NRC Examination
Scenario#1 2
SIMULATOR SETUP Initial Conditions
IC 188 Scenario#1 ENP 24 for IC 14..Differential
Fault, Reactor Scram ,B21-N026B
fails downscale 1000/0 EOC Rx Pwr Core Age EVENTS Event Trigger Trigger Description
Number 1 NA NA Swap RBCCW 2 1 Manual 2C RBCCW Puml
3 2 Manual Runback of 2A 4 NA NA 5 3 Manual 6 4 Manual 7 NA NA 8 5 9 10 NA NB006F A MSL BREAK BEFORE FLOW RESTRICTOR
o 4.00 00:05:00 5 RC026F RECIRC PMP"A" RUNBACK TO LIMITER#2 False True 00:00:05 2 2007 NRC Examination
Scenario#1 3
Remotes Summary Remf ID Mult Description
ID Current Value Target Value Rmptime Actime Trig EP_IACS993P DW CLR A&D OVERRIDENORMAUSTOP
NORMAL STOP 00:05:00 6 7 9 7 9 7 6 8 10 8 00:04:00 NORMAL DW CLR A&D OVERRIDENORMAUSTOP
SW-V193 MAN ISOL NSW TO RBCCW RESTART RPS MG SET B PRS M-G SET B EPA BKRS CONY SW TO RBCCW HSX V146 PNL 32AB PWR (E7=;PNL 2AB PWR (E7=NORM/E8=AL
T)U 1-U2 WET HDR X-TIE VL V v5063
RP_IARPSB EP_IACS994P 2007 NRC Examination
Scenario#1 4
Override Summary NONE Window Descri tion Annunciator
Summary Tri Trig Trigger RBCCW PMP C AUTO RBCCW PMP C AUTO RBCCW PMP C AUTO RBCCW PMP A AUTO File Batch Files Special Instructions
2007 NRC Examination
Scenario#1 5
SHIFT BRIEFING Plant Status The plant is operating at maximum power, End of Cycle.Equipment Out of Service No equipment is out of service Plan of the Day Maintain current power.Following shift turnover, Place the 20 RB S secure 2C Fans.Maintenance
personne clearance is required.2007 NRC Examination
Scenario#1 6
SCENARIO INFORMATION
Examiner Notes Procedures
Used in Scenarios:
EVENT 1 OR L CONTROL PROCEDURE)
Y CONTAINMENT
CONTROL PROCEDURE)
- Annunciator
2-A-6, Window 3-2 (Recirc Pum,;,*EVENT 2*Annunciator
2-UA-3, Window 2-5 (RBCCW Pump Trip)*OAOP-16 (RBCCW Pump Trip)EVENT 3/4 EVENT 5 EVENT 10*2EOP-01-RV
ACTOR VESSEL CONTROL PROCEDURE)
- OEOP-01-RXFP (REACTOR FLOODING PROCEDURE)
Critical Tasks Perform emergency depressurization
when drywell average temperature
cannot be restored and maintained
below 300°F.Establish and maintain RPV pressure at least 50 psig above suppression
chamber pressure with at least 5 SRVs open.2007 NRC Examination
Scenario#1 7
EVENT 1 SHIFT TURNOVER, SWAPPING OF RB SUPPLY&EXHAUST FANS The crew swaps RB HVAC Fans per SCQ direction Malfunctions
required-None Objectives:
haust Fans to report thatted t the fans appear to be operating*When aske*normally.*sea-Directs BOP to shift from the 2C to the 2D RB Suppl support Maintenance
RB HVAC Supply&Exhaust Fans fans 2A, B, D Success Path: BOP-Starts 20 RB HVAC Fans in service&remove 37.1 Section 8.9 Simulator Operator Activities:
2007 NRC Examination
Scenario#1 8
EVENT 1 SHIFT TURNOVER/SWAPPING
OF RB SUPPLY&EXHAUST FANS Required Operator Actions SRO of RB Su*Directs BOP to shift from the 2C to the 2D RB Sup Maintenance
ACTIONS OR Normal 0 eration-Swa Normal 0 eration-Swa 2007 NRC Examination
Scenario#1 9
EVENT 2 RBCCW PUMP TRIP/PUMP in AUTO FAILS TO AUTO START The crew responds to a trip on one of the operating RBCCW Pumps Malfunctions
required: witch to ON)and RBCCW e 2C RBCCW Pump motor is hot to report that the power supply breaker for 2C RBCCW agnetics.report that the power supply breaker for 2C agnetics.*2B RBCCW Pump will fail to auto-start
on a low RBCC pressure Objectives:
sea-Directs BOP to enter and execute OAOP-1 BOP-Enters OAOP-16.0 to respond to the.start Success Path: 28 RBCCW Pump is manually start'is returned to normal operation (norm 2007 NRC Examination
Scenario#1 10
EVENT 2 RBCCW PUMP TRIP Required Operator Actions Transient Response-Entry into OAOP-16.0:
Failure of RBCCW System SRO*Directs BOP operator to enter and execute OA*Directs start of 2B RBCCW pump BOP*Refers to Annunciator
Respo*Enter OAOP-16*Manually starts 2B R 2007 NRC Examination
Scenario#1 11
EVENT 3 2A REACTOR RECIRCULATION
PUMP RUNBACK TO LIMITER#2 The crew responds to a spurious runback of the 2A Recirculation
Pump speed controller
to Speed Limiter#2.The scoop tube lockup circuit is defeated.(can not be locked up)Malfunction
required: nback signal to the rious, direct reset of the urn of power to the pre-nback signal per 20P-02, Section 8.3 eactor Recirculation
MG runback 2A Reactor Recirculation
Pump is identified, 2AOP-04.0 er level is stabilized, Technical Specification
requirements
circulation
Loop operation, and the Runback Signal is P-02.0 following resolution.
- 2A Reactor Recirlation
MG Set will experience
a spuri.Limiter#2 setpoint*Lockout circuit on scoop tube will be defeated (RO The runba is entered an are evaluated f successfully
reset Objectives:
SCQ Directs RO to enter and execute 2A Simulator Operator Activities:
WHEN directed by the lead examiner, activate TRIGGER 2.WHEN asked, as the Turbine Building Auxiliary Operator (TBAO), wait 3 minutes and report that there are no apparent problems at the 2A Reactor Recirculation
Motor Generator.
2007 NRC Examination
Scenario#1 12
Simulator Operator Activities (continued)
WHEN asked, as I&C, wait 5 minutes and report that the cause of the Runback to Limiter#2was due to an error in installation
of a jumper during the performance
of a surveillance
currently in progress.WHEN asked, as I&C, report that the lockout circuit has been r retested next shift.The runback may be reset.WHEN asked,asI&C, communicate
with the Reactor demand vs.actual speed control signal, in support of[Instructor
Aids-Panels-Recirc MG Set Bail...'WHEN asked, as NE, provide guidance on pattern does not need to be symmetrical.
2007 NRC Examination
Scenario#1 balance/verify
the e runback 13
EVENT 3 2A REACTOR RECIRCULATION
PUMP RUNBACK TO LIMITER#2 Required Operator Actions Transient response-Entry into 2AOP-04.0:
Low Core Flow SRO*Directs RO to enter and execute 2AOP-04.0:
or single of the loop with purious, direct reset of I to return of power to the nback signal per 20P-02, Section 8.3 eactor Recirculation
MG runback RO*Following determination
of the Runbac the 2A Reactor Recirculation
Pump Limit pre-event power level*Contacts Nuclear Eng.for gui*Evaluates Technical Specification (T.S.3.4 Recirculation
Loop operation (flow mism, the lower speed Recirculaton
Pump a*Contacts I&C for support 2007 NRC Examination
Scenario#1 14
EVENT 4 INCREASING
POWER FOLLOWING RUNBACK SIGNAL RESET The crew will take action to restore reactor power to the pre-runback
level.Malfunctions
required: None Objectives:
seo Directs RO to raise reactor power to 90%by rais*, Loop RO Raises reactor power per 20P-02.0 by r.Success Path: Simulator Operator Activities:
2007 NRC Examination
Scenario#1 be raised without ramp 15
EVENT 4 INCREASING
POWER FOLLOWING RUNBACK SIGNAL RESET Required Operator Actions Normal Operating Procedures
-20P-02 SRO*Contacts Load dispatcher
regarding power incr*Direct RO to raise reactor power to 900/0 RO o Whendirected,raises
reacto Recirculation
Flow per 20P-02..APPLICANT'S
ACTIONS OR BE 2007 NRC Examination
Scenario#1 Reactor 16
EVENT 5 INSTRUMENT
LINE PENETRATION
FAILS The crew will observe and report the parameter changes impacted by the instrument
failure.The SCO will diagnose the failure and evaluate the impact to plant operation, including Technical Specification
action statement(s).
Malfunctions
required:*Penetration
X49A Level instrument
B21-NO Objectives:
Success Path: SCO correctly evaluate correct Technical Sp 2007 NRC Examination
Scenario#1 17
EVENT 5 INSTRUMENT
LINE PENETRATION
FAILS Required Operator Actions: seQ*Evaluate the plant impact and Technical Specifica.instruments
affected.(3.3.3.2-Remote Shutdo Instrumentation-
30 days)APPLICANT'S
ACTIONS OR BEHAVIOR: 2007 NRC Examination
Scenario#1 quirements
for the nitoring 18
EVENT 6 REACTOR SCRAM, LOSS OF OFF-SITE POWER, DG#3 FAILURE The crew will respond to a loss of off-site power resulting in a reactor scram and a corresponding
failure of Emergency Diesel Generator#3 due to an electrical
fault on Bus E3.ulting in, a reactor nization of#3 op on Emergency availability
of the It parameters
re band of 800-1000 psig nd of 170" to 200" er to determine Distribution
Grid status*Off-site power will be lost due to a grid disturba scram.Immediately
following the starting an Emergency Diesel Generator, an electrical
Bus E3, resulting in a tripping of#3 Die Emergency Bus.AOP-36.1 in response to the loss of*Iure BOP Plant status ite power ded to Bus E4 o ripped due to overcurrent
trip on bus Places CB auto-reclosers
to OFF Directs AO to cross-tie air Ensures 2B Nuclear Service Water Pump is running, starts 28 and 2C Conventional
Pumps Starts Control Room and Battery Room HVAC Direct Transfer of RBCCW Cooling to Conventional
Service Water Start 2B CRD Pump Direct RPS to be restarted RO am and takes actions to control level and pressure ds using HPCI, RCle, and SRVs Objectives:
Malfunctions
required: 2007 NRC Examination
Scenario#1 19
Success Path: sea successfully
enters 2EOP-01, 2EOP-01-RSP, Reactor Scram Procedure and, subsequently, enters 2EOP-01-RVCP, Reactor Vessel Control Procedure and directs activities
relating to reactor vessel control (RPV pressure and level)and directs activities
relating to the loss of electrical
power.RO takes actions to control reactor level and pressure (HPCI, RCIC, SRV operation).
BOP enters OP-36.1 and takes actions 7 as directed to address the loss of electrical
power.2007 NRC Examination
Scenario#1 20
EVENT 6 REACTOR SCRAM, LOSS OF OFF-SITE POWER, DG#3 FAILURE Simulator Operator Activities
damage to the e for return to service.ait 2 minutes and inutes and report the EDG trip is due to WHEN it is requested to cross tie air, report t open.WHEN directed by lead examiner, activate TRIGGER 4 IF contacted as Load Dispatcher, report that there has be Transmission
Grid and that there is, currently, not a pro*IF asked as Unit 1 for permission
to cross-tie air, IF asked by I&C to*an electrical
lock IF asked to transfer RCC to CSW, wait 5 minute IF asked to restart RPS, wait 3 min IF requested to transfer 2AB, 2AB-R activate TRIGGER 7.2007 NRC Examination
Scenario#1 21
EVENT 6 REACTOR SCRAM, LOSS OF OFF-SITE POWER, DG#3 FAILURE Required Operator Actions SRO 2EOP-01-RSP, EOP-01-RVCP, o psig or Rx Level o Conventional
Service Water ram the reactor per 2EOP-01-RSP, Reactor Scram s to control Reactor Vessel Level and Pressure using HPCI, afety Relief Valves etermine Distribution
Grid status*Directs the RO to control reactor an*Executes the Emergency Operating Procedures:
Reactor Scram Procedure and, subsequently, e Reactor Vessel Control Procedure (if Rx Pre 100").*Enters and executes EOP-PCCP wh degrees.*Control pressure using*Directs BOP t*power and*RO BOP ReportsElectric
Plant status-Loss of off-site power-DG#4 loaded to Bus E4 2007 NRC Examination
Scenario#1 22
-DG#3 tripped due to overcurrent
trip on bus Places PCB auto-reclosers
to OFF Directs AO to cross-tie air the loss ofa-ite power nd Emergency Bus E3 Starts 2B CRD Pump Transfers of RBCCW Cooling to Conventio Execute applicable
steps of OAOP-36.and failure of the#3 Emergency Diesel G<Starts Control Room and Battery Room HVAC Ensures 2B Nuclear Service Water Pump is running, sta Conventional
Pumps APPLICANT'S
ACTIONS OR BE 2007 NRC Examination
Scenario#1 23
EVENT 7 HPCIINJECTION
VALVE FAILS TO OPEN The crew will respond to a failure of the HPCI injection valve to fail to automatically
open on a valid initiation
signal.Malfunctions
required: Success Path: atically open on a rator action to open the Opens the HPCI Injection Valve position and commences injection Identifies
that the HPCI Injection initiation
signal*The 2-E41-F006, HPCI Injection Valve, will fail to valid initiation
signal SCO/RO Objectives:
RO 2007 NRC Examination
Scenario#1 24
EVENT 7 HPCIINJECTION
VALVE FAILS TO OPEN Required Operator Actions: SRO/RO Identifies
the HPCllnjection
Valve, 2-E41-F006, has failed to open on a valid initiation
signal RO Opens the 2-E41-F006
by taking the control s*0 the"OPEN" position and establishing
injection flow to the reactor PCI.APPLICANT'S
ACTIONS OR BEHAVIOR: 2007 NRC Examination
Scenario#1 25
EVENT 8/9 STEAM LEAK IN DRYWELL REQUIRING EMERGENCY DEPRESSURIZATION
The crew will respond to a steam leak in the drywell in conjunction
with a failure of the ability to spray the containment, subsequently
leading to a requirement
to Emergency Depressurize
the reactor due to high drywell temperature.
Malfunctions
required:*A steam leak will occur in the drywell, resulti temperatures*A failure will be inserted, preventing
the Spray injection valve*Cross tie of E7 to E8 will not functi Objectives:
SCO Recognize condition temperatures
and pre Direct execution of app Containment
Control Pr at the Reactor Saturation
n during the depressurization
in control of Reactor Water Level and Pressure, as e trip:C when High level trip setpoint is reached (206"), of RH in Suppression
Pool Cooling when directed"8" Loop in Suppression
Chamber and Drywell Sprays when directed eport failure of"8" Loop Drywell Spray valve to open and s to attempt to open the valve When Irected, Emergency Depressurize
the reactor (high drywell temperature)
Control injection from Low Pressure systems to maintain reactor water level during depressurization.
Success Path: When 300°F is exceeded in the drywell, the reactor is Emergency Depressurized
and level is restored/maintained
in the normal band (170" to 200")2007 NRC Examination
Scenario#1 26
EVENT 8/9 STEAM LEAK IN DRYWELL REQUIRING EMERGENCY DEPRESSURIZATION
Simulator Operator Activities:
WHEN directed by the lead examiner, activate TRIGGER 5 IF asked, report that the breaker for the 2-E11-F016B
apR indication
and that the thermal overload appears to be.IF asked, report that the 2-E11-F016B
is mechani.WHEN to lock-out drywell coolers, activate T IF requested to support E7 to E8 cross-tie, ac 2007 NRC Examination
Scenario#1 27
EVENT 8/9 STEAM LEAK IN DRYWELL REQUIRING EMERGENCY DEPRESSURIZATION
Required Operator Action: SRO ted temperatures
001 Cooling when directed I trip setpoint is reached (206")in Suppression
Chamber and Drywell Sprays per SEP-ure of"8" Loop Drywell Spray valve to open and take pen the valve Low Pressure systems to maintain reactor water level zation.*Recognize conditions
of the steam leak in the drywell and pressures)
and provide direction to the RQ an*Must man*Control i during depr*Continue to main by the SCQ*When drywell temperature
cannot be Depressurization
of the reactor*Direct execution of applicable
steps of 2EQP-0 Control Procedure).
- RO/BOP*When directed, Emergency Depressurize
the Reactor by opening 7 ADS valves*Control Low Pressure Injection Systems to prevent Reactor Vessel overfeed on re-flood following Emergency Depressurization
2007 NRC Examination
Scenario#1 28
APPLICANT'S
ACTIONS OR BEHAVIOR: 2007 NRC Examination
Scenario#1 29
EVENT 10 LEVEL INSTRUMENT
FAILURE DUE TO REFERENCE LEG FLASHING-REACTOR FLOODING REQUIRED The crew will respond to indications
of Reactor Pressure Vessel Level reference leg flashing, resulting in a loss of all level instrumentation.
Objectives:
Success Path: reference leg n being available established
resulting in at ith at least 50 psid (but as ssion Chamber Reactor Pressure Ve least 5 safety relief val low as possible)betwee Pressure.Enter and execute EOP-01-RxFP,React
direction to the RO/BOP operators Implement directions
given by Flooding Conditions
to ensur As the eactor depressurizes, recognize indicati flashing and it impact, being no level instru RO/BOP SCO 2007 NRC Examination
Scenario#1 30
EVENT 10 LEVEL INSTRUMENT
FAILURE DUE TO REFERENCE LEG FLASHING-REACTOR FLOODING REQUIRED Required Operator Actions: EOP Action-Entry into and Execution of Reactor Flooding Procedure seQ*As the reactor depressurizes, correctly evaluate in.Instrument
Reference Leg Flashing is occurring*Enter and execute EQP-01-RxFP,Reactor
adequate core cooling RO/BOP*Observe and report indications
of Reacto flashing 2007 NRC Examination
Scenario#1 s to determine Level ing conditions
(5 or more ssion pool and reactor.)31
Simulator Operator Activities:
WHEN directed by the lead examiner, place the simulator in FREEZE.CAUTION DO NOT RESET THE SIMULATO OF CONCURRENCE
TO DO EXAM 2007 NRC Examination
Scenario#1 TO RECEIPT LEAD 32
8.9 Swapping Reactor Building Ventilation
Fans R Reference Use 8.9.1 Initial Conditions
1.Reactor Building Ventilation
System is in service in D accordance
with Section 5.1 or 8.1.8.9.2 Procedural
Steps 1.PERFORM the following to swap a Reactor Building Exhaust Fan: a.PLACE the selected fan control switch in START D AND HOLD.b.ENSUREtheselected
fan discharge damper D opens.c.RELEASEtheselected
fan control switch.D d.ENSURE the selected fan is running by observing D the control switch red fan light is on.e.PLACE the selected fan control switch in STOP.D 2.PERFORM the following to swap a Reactor Building Supply Fan: a.PLACE the selected fan control switch in STOP.D b.PLACE the selected fan control switch in START D AND HOLD.c.ENSUREtheselected
fan discharge damper D opens.d.RELEASE the selected fan control switch.D e.ENSURE the selected fan is running by observing D the control switch red fan light is on.120P-37.1 Rev.50 Page 33 of 551
8.9.2 Procedural
Steps\ZOP-37.1 3.4.ENSURE REACTOR BLDG NEG PRESSURE, D VA-PI-1297, at a minimum of 0.25 inches of water.ENSURE MSIV PIT EXHAUST AIR CHECK DAMPER, D VA-2A-CV-RB, did NOT close.Rev.50 Page 34 of 551
IOAOP-16.0
BRUNSWICK NUCLEAR PLANT PLANT OPERATING MANUAL VOLUME XXI ABNORMAL OPERATING PROCEDURE UNIT o OAOP-16.0 RBCCW SYSTEM FAILURE REVISION 18 Rev.18 Page 1 of 11 I
1aO SYMPTOMS 181 RBCCW PUMP DISCH HEADER PRESS LOW (UA-03 2-5)in alarm 1.2 RBCCW HEAD TANK LEVEL HI/LO (UA-03 1-5)in alarm 1.3 PUMP A SEAL CLOSED CLG WTR FLOW LO (A-06 1-4)in alarm 1.4 PUMP B SEAL CLOSED CLG WTR FLOW LOW (A-O?6-5)in alarm IRISI 1.5 RBCCW HX OUTLET HDR TEMP HI (UA-03 1-3)in alarm 1.6 UNIT 2 Only: DRYWELL CHILLER TRIP (UA-05 5-10)in alarm 1.?High temperature
alarms on equipment supplied by RBCCW.IRISI 1.8 High NSW or CSW header pressure approaching
pump shutoff head (approximately
90 psig).280 AUTOMATIC ACTIONS 2.1 IF system pressure decreases to 65 psig, THEN the standby D RBCCW pump will start.2.2 IF non-regenerative
heat exchanger outlet temperature
D increases to greater than 135°F, THEN RWCU will isolate.2.3 IF Drywell Equipment Drain Sump OR Reactor Building D Equipment Drain Tank temperature
increases to 180°F, THEN recirculation
of the affected system initiates.
3.0 OPERATOR ACTIONS 3.1 Immediate Actions None IOAOP-16.0
Rev.18 Page 2 of 11 I
3.0 OPERATOR ACTIONS 3.2 Supplementary
Actions NOTE: High drywell pressure and temperature
alarms should be anticipated.
3.2.1 PERFORM the foHowing as necessary to maintain RBCCW discharge header pressure greater than 60 psig: 1.ST ART available RBCCW pumps.D 2.ISOLATE any identified
leaks due to pipe rupture.D 3.2.2 IF 2D RBCCW Pump is in service to either drywell THEN PERFORM the following:
1.IF 2D RBCCW Pump is the source of the leakage, THEN PERFORM the following:
a.SECURE 20 RBCCW Pump.D b.ISOLATE the unit from the leak.D 2.IF a loss of heat sink (Unit 1 RB Chiller)has occurred, D THEN ENSURE 20 RBCCW Pump is tripped.NOTE: A complete loss of RBCCW is defined as discharge header pressure below 60 psig, high temperature
alarms on components
supplied by RBCCW, and all available RBCCW Pumps running.3.2.3 IF there is a complete loss of RBCCW, THEN PERFORM the following:
1.TRIP all RBCCW pumps (including
20 RBCCW Pump if operating on the affected unit).D 2.CLOSE the following valves: IOAOP-16.0
3.RBCCW TO OW ISOL VLVS, RCC-V28-RBCCW TO OW ISOL VLVS, RCC-V52 TRIP RWCU pump(s).Rev.18 D D D Page 3 of 11 I
3.0 OPERATOR ACTIONSISOLATE the RWCU
REDUCE the speed of both reactor recirculation
pumps to
MANUALLY SCRAM the reactor AND ENTER
TRIP both reactor recirculation
D D D D NOTE: CRD pumps may NOT be operated for greater than 20 minutes without cooling water except asdirectedby
the Unit sca under the following conditions:-A CRD pump is available AND alternate control rod insertion is required OR-CRD pump operation is required for reactor vessel level controlIF CRD pumps are NOT needed for control rod insertion OR reactor vessel level control, THEN TRIP both CRD
D 3.2.4 IF there is a partial loss of RBCCW pressure or service water, THEN PERFORM the following:
1.IF any of the following conditions
exist, THEN REFER to OAOP-18.0 or OAOP-19.0:
High temperatures
on equipment cooled by RBCCW D NSW or CSW header pressure approaching
pump D shutoff head (approximately
90 psig)RBCCW HX OUTLET HDR TEMP HI (UA-03 1-3)in D alarm IOAOP-16.0
Rev.18 Page 4 of 11 I
3.0 OPERATOR ACTIONS 2.MONITOR recirculation
pump seal temperature
on D RECIRC.PUMP TEMP recorder, 832-TR-R601.3.IF either of the following conditions
exist, THEN SHUT DOWN the affected reactor recirculation
pump(s): Seal heat exchanger inlet temperature
for Seal 1 or D Seal 2 exceeds 200°F RBCCW to the recirculation
pump seal heat D exchangers
is lost for more than 10 minutes.4.IF the Reactor Mode Switch is in RUN AND both reactor D recirculation
pumps have been shut down, THEN INSERT a manual reactor scram..5.REDUCE system heat load by removing the following systems from service: RWCU D Fuel Pool Cooling D Drywell Equipment Drain Cooler D Reactor Building Equipment Drain Cooler D Reactor Building, PASS, and Radwaste Sample D Stations 6.MONITOR drywell temperature
and pressure.D 7..IF abnormal primary containment
condition occurs, D THEN REFER to OAOP-14.0.
8.IF entry conditions
are reached, THEN ENTER D OEOP-02-PCCP.
9.IF RBCCW can NOT be restored, THEN COMMENCE a D plant shutdown in accordance
with OGP-05.10.IF necessary to maintain spent fuel pool water D temperature
below 125°F, THEN REFER to OAOP-38.0.
IOAOP-16.0
Rev.18 Page 5 of 11 I
3.0 OPERATOR ACTIONS 3.2.5 IFin-leakagefrom
components
cooled by RBCCW is suspected, THEN PERFORM the following:
NOTE: In-leakage
from a recirculation
pump seal cooler may cause high recirculation
pump motor temperature, low seal number 1 pressure, low recirculation
pump seal staging flow, as well as high activity in the RBCCW system.1.INITIATE actions to identify and isolate the source of the D in-leakage.
2.IF source of the in-leakage
can NOT be determined
from available indications, THEN NOTIFY E&RC to sample RBCCW from the following locations:
Reactor Recirc Pump A Cooler Outlet D Reactor Recirc Pump B Cooler Outlet D Cleanup NRHX A Shell Side Outlet D Cleanup NRHX B Shell Side Outlet D Fuel Pool HX A Shell Side Outlet D Fuel Pool HX B Shell Side Outlet D 3.2.6 IF RBCCW HEAD TANK LOW LEVEL (UA-03 1-5)is in alarm, AND low level is confirmed, THEN PERFORM the following:
1.MONITOR RBCCW Head Tank level.D 2.FILL the RBCCW Head Tank in accordance
with D 1 (2)OP-21 as necessary.
3.WALK DOWN accessible
system piping to locate D leakage.4.CHECK drywell floor drain sump leakage rate.D 5.ISOLATE any source of leakage.D IOAOP-16.0
Rev.18 Page 6 of 11 I
3.0 OPERATOR ACTIONS IR191 NOTE: NOTE: Loss of AC power to the unit could result in the inability to monitor drywell temperature
from the Control Room.During the time when the Control Room indication
is NOT available, CAC-TR-778, located at the RSDP, can be used to ensure peaklocaldrywell
temperature
history is accurately
known.Maximum drywell temperatures
allowed below the 75'elevation are as follows:-Control Room temperature
recorder CAC-TR-4426 greater than or equal to 260°F-RSDP temperature
recorder CAC-TR-778 greater than or equal to 258°F, Points 1, 3, and 4 3.2.7 IF all RBCCW pumps are off, THEN PERFORM the following:
1.IF drywell temperature
has previously
exceeded or is currently greater than the maximum temperature
allowed, THEN PERFORM the following:
a.b.PLACE all RBCCW pump control switches in OFF.RESTART RBCCW in accordance
with the infrequent
operation section of 1 (2)OP-21 for high drywell temperature.
D D 2.IF drywell temperature
has NOT exceeded the maximum temperature
AND the RBCCW pumps have lost electrical
power or will NOT start, THEN PERFORM the following:
IOAOP-16.0
a.b.c.IF the affected unit's 4KV E buses are D deenergized, THEN REFER to OAOP-36.1.
IF RBCCW pump breakers local thermal or D magnetic trips have activated, THEN RESET the tripped device.RESTART RBCCW in accordance
with 1 (2)OP-21 D when available.
Rev.18 Page 7 of 11 I
3.0 OPERATOR ACTIONS d.WHEN RBCCW is returned to service, THEN RESTORE plant systems to operation in accordance
with their respective
operating procedures.
D 3.2.8 WHEN directed by the EOPs, THEN OPEN the following valves to restore service water to RBCCW following a LOCA closure:-RBCCW HX SERVICE WATER INLET VALVE, D SW-V103-RBCCWHX SERVICE WATER OUTLET VALVE, D SW-V106.IOAOP-16.0
Rev.18 Page 8 of 11 I
480 GENERAL DISCUSSION
RBCCW failure interrupts
cooling water supply to the following components:
(1)Reactor Recirculation
Pumps (2)CRD Pumps (3)RWCU Recirculation
Pumps, Precoat Pump, and Nonregenerative
Hx (4)DrywelJ Coolers (5)Penetration
Coolers (6)Fuel Pool Heat Exchangers
(7)Drywell Equipment Drain Heat Exchanger (8)RBEDT Heat Exchanger (9)Reactor Building Sample Station (10)Radwaste Building Sample Station (11)Postaccident
Sample System Sample Coolers (12)Drywell Plate and Frame Heat Exchanger (when 2D RBCCW Pump in service)RBCCW system failure could be due to a pipe rupture, pump failure, or loss of service water.This procedure attempts to reduce the system heat load on a partial loss of pressure due to pump failure, or high temperature
due to service water failure.In the case where no RBCCW pumps are running and any drywell local temperature
below the 75'elevation has exceeded 260 degrees, restart of the RBCCW pumps will be controlled
using Infrequent
Operation sections in 1 (2)OP-21 in order to protect RBCCW piping integrity inside the drywell.If a loss of all pumps has occurred, and elevated drywell temperature
existed, system piping may contain voids, which could lead to waterhammer
upon an uncontrolled
restart.IOAOP-16.0
Rev.18 Page 9 of 11 I
5.0 REFERENCES1 OAOP-14.0, Abnormal Primary Containment
Conditions
5.2 OAOP-18.0, Nuclear Service Water System Failure 5.3 OAOP-19.0, Conventional
Service Water System Failure 5.4 OAOP-36.1, Loss of Any 4160V Buses Or 480V E-Buses 5.5 OAOP-38.0, Loss Of Fuel Pool Cooling 5.6 1 (2)APP-UA-03, Annunciator
Panel Procedure for Panel UA-03 5.7 1 (2)APP-A-06, Annunciator
Panel Procedure for Panel A-06 5.8 1 (2)APP-A-07, Annunciator
Panel Procedure for Panel A-07 5.9 2APP-UA-05, Annunciator
Panel Procedure for Panel UA-05 5.10 OEOP-02-PCCP, Primary Containment
Control Procedure 5.11 OENP-24.0, Reactor Engineering
Guidelines
5.12 1(2)EOP-01-RSP, Reactor Scram Procedure 5.13 OGP-05, Unit Shutdown 5.14 1(2)OP-21, Reactor Building Closed Cooling Water System Operating Procedure IRISI 5.15 IER#92-21-03(IFI);
FACTS#9389034 5.16 EWR#09588, Operation of CRD Pumps without RBCCW 5.17 GE SIL No.459, S2 5.18 Technical Memorandum
No.8/M-90-001
IR191 5.19 NRC Generic Letter 96-06, Assurance of Equipment Operability
and Containment
Integrity During Design Basis Conditions
5.20 ESR 01-00400, AST Implementation
for Fuel Handling 6.0 ATTACHMENTS
None IOAOP-16.0
Rev.18 Page10 of 11 I
REVISION SUMMARY Revision 18 is an editorial correction
to replace the Desdemona font used for check-off boxes and to enhance wording in
Revision 17 clarifies conditions
under which a CRD pump may be operated for greater than 20 minutes without cooling.Revision16
adds clarifying
information
in a NOTE above steps required to be performed for a complete loss of RBCCW.Revision15
-Added new Step 3.2.4.4 to instruct the Operator to scram the reactor upon loss of forced recirculation (Mode Switch in RUN)as required by 1 (2)AOP-04.0.
Revision 14-Format changes to meet the requirements
of OAP-005 and Microsoft Word XP.This revision makes non-intent
changes to steps for clarity.This change does NOT implement an intent change.Additional
administrative
changes classified
as"editorial":
are bolding action verbs, italicizing
components, change of cover page logo, removal of the"bar code" from the cover page, and adding place keeping aids.Revision 13 incorporates
EC 47025, Permanent RB/DW Chiller Installation.
New Supplementary
Action steps 2 and 3 have been added to address actions required if the 2D RBCCW Pump is in service to either drywelL Revision 12 incorporates
actions required in response to NRC Generic Letter 96-06.This action added a step to prevent RBCCW pump restart if all pumps were lost and any local drywell temperature
below the 75'elevation exceeded 260 degrees Fahrenheit.
Revision 11 switches the order of steps in the Supplementary
Actions section to clarify the actions to be taken for a complete loss of RBCCW and corrects procedure references.
IOAOP-16.0
Rev.18 Page 11 of 11 I
Unit 2 APP UA-03 2-5 Page 1 of 1 RBCCW PUMP DISCH HEADER PRESS LOW AUTO ACTIONS NONE CAUSE 1.RBCCW pump trip due to any of the following:
a.Overload device.b.Load shed sequence for applicable
emergency bus.c.Circuit malfunction.
2.Gross leakage or piping failure.3.Improper valve lineup.4.Increased heat load.S.Circuit malfunction.
OBSERVATIONS
1.RBCCW pump indicates tripped or associated
emergency 4160 volt bus has received an undervoltage
or loss of off-site power signal.2.RBCCW Pump Discharge And Header Pressure Indicator, RCC-PI-671-1, indicates less than 68 psig.3.If RBCCW header pressure reaches 65 psig as indicated on RCC-PI-671-1, then the standby RBCCW pump should start.ACTION 1.For RBCCW pump trip, start the standby pump if auto start has not occurred.2.If pressure cannot be restored, refer to AOP-16.0, Reactor Building Closed Cooling Water System Failure.3.If a circuit malfunction
is suspected, ensure that a Trouble Tag is prepared.DEVICE/SETPOINTS
Pressure switch RCC-PS-673
POSSIBLE PLANT EFFECTS 68 psig 1.Loss of RBCCW cooling capacity could result in a unit shutdown.REFERENCES
1.LL-9353-35 2.AOP-16.0, RBCCW System Failure 1 2 APP-UA-03 Rev.42 Page 21 of 631
\2AOP-04.0
BRUNSWICK NUCLEAR PLANT PLANT OPERATING MANUAL VOLUME XXI ABNORMAL OPERATING PROCEDURE UNIT 2 2AOP-04.0 LOW CORE FLOW REVISION 16 Rev.16 Page 1 of 131
1.0 SYMPTOMS 1&1 Reduction in core flow, reactor recirculation
pump motor amps, reactor power, generator output, etc.1.2 The following alarms may also appear in particular
instances:
-RECIRC FLOW A LIMIT (A-06 3-2)-RECIRC FLOW B LIMIT (A-07 2-4)-SPEED CONTROL A SIGNAL FAIL (A-06 5-1)-SPEED CONTROL B SIGNAL FAILURE (A-O?4-3)-RECIRC M-G A DRIVE MTR TRIP (A-06 2-3)-RECIRC M-G B DRIVE MTR TRIP (A-O?1-5)-OPRM PBAlCDA ALARM (A-OS 5-8)-OPRM UPSC TRIP (A-05 6-8)-APRM UPSCALE (A-06 2-8)2.0 AUTOMATIC ACTIONS 2.1 Reactor scram if OPRM detects instability
when it is enabled 3.0 OPERATOR ACTIONS 3.1 Immediate Actions 3.1.1 3.1.2!2AOP-04.0
IF the Reactor Mode Switch is in RUN AND both reactor D recirculation
pumps have tripped, THEN INSERT a manual reactor scram.IF reactor recirculation
pump speed is lowering AND a D recirculation
runback has NOT occurred, THEN PLACE the affected pump(s)SCOOP TUBE A (B)LOCK switch to TRIP.Rev.16 Page 2 of 131
380 OPERATOR ACTIONS 3.2 Supplementary
Actions NOTE: Reactor recirculation
pump speed mismatch and jet pump loop flows should be maintained
within the following limits:-20%speed and jet pump loop flows within 10%(maximum indicated difference
7.5 x1 0 6 Ibs/hr)with total core flow less than 58 x10 6 Ibs/hr-10%speed and jet pump loop flows within 5%(maximum indicated difference
3.5 x10 6 Ibs/hr)with total core flow greater than or equal to 58 x10 6 Ibs/hr NOTE: Process Computer Point U2CPWTCF, when validated, is the primary indication
of total core flow, and should be used for stability region compliance.
U2CPWTCF is invalid, U2NSSWDP or Attachment
1 may be used as an alternate indication
for total core flow.NOTE: As the stability region is a*pproached, Process Computer Point B018, Total Core Flow, and recorder 2B21-PDR/FR-R613, located on H12-P603, will read lower than Process Computer Point U2CPWTCF.NOTE: The following computer screens may be used for reference:
-802, Power/Flow
-OPRM Operable-TLO-803, Power/Flow
-OPRM Inoperable
-TLO-804, Power/Flow
-OPRM Operable-SLO-805, Power/Flow
-OPRM Inoperable
-SLO-806, Power/Flow
-OPRM Operable-FWTR-807, Power/Flow
-OPRM Inoperable
-FWTR.3.2.1 PERFORM the following to determine the current operating point ontheapplicable
Power-Flow
Map: 1.12AOP-04.0
IF reactor recirculation
pump speed AND jet pump loop D flow mismatch is within the allowable limits, THEN DETERMINE the current operating point using the applicable
Power-Flow
Map, as specified by OENP-24.0.
Rev.16 Page 3 of 131
3.0 OPERATOR ACTIONS 2.IF reactor recirculation
pump speed OR-jet pump loop flow mismatch is NOT within the allowable limits OR the plant is in single loop operation, THEN PERFORM the foHowing: NOTE: To compensate
for signal noise, an average of several core DP readings should be used.Process Computer Point 8017 or ERFIS point B21DA014 is the preferred method for obtaining this average.a.b.IF a valid total core flow from U2CPWTCF OR U2NSSWDP is NOT available, THEN DETERMINE total core flow using Attachment
1.DETERMINE the current operating point using the applicable
Power-Flow
Map, as specified by OENP-24.0.
D D 3.2.2 IF OPRM System is operable AND the current operating point is in the Scram Avoidance Region, THEN use one of the following methods to immediately
exit the region: NOTE: NOTE: When raising core flow with two reactor recirculation
pumps operating, pump speeds and jet pump loop flow mismatch should be maintained
within the allowable limit.Total core flow should NOT exceed 45 x 10 6 lbs/hr (58%)in single loop operation.
RAISE core flow D INSERT control rods in accordance
with D OENP-24.0, Form 2, Immediate Reactor Power Reduction Instructions.
12AOP-04.0
Rev.16 Page 4 of 131
3.0 OPERATOR ACTIONS fR1l3.2.3 3.2.4 1.IF the temperature
differential
between the coolant within the dome and the bottom head drain can NOT be maintained
less than 145°F during the performance
of this procedure, THEN INSERT a manual reactor scram.IF OPRM System is inoperable, THEN PERFORM the following:
IF either of the following conditions
are met, THEN INSERT a manual reactor scram: The current operating point is in Region A D D NOTE: Instability
may be indicatedbyany of the following:
-OPRM PBNCDA ALARM (A-05 5-8)is in alarm-OPRM UPSCALE TRIP (A-OS 6-8)is in alarm-A rise in baseline APRM noise level.SRM power level and period meters may also be oscillating
at the same frequency-LPRM and/or APRM upscale or downscale alarms being received-Sustained reactor power oscillations
with a peak to peak duration of less than 3 seconds.Indications
of thermal hydraulic instability
exist D AND the current operating point is in Region B, the 50/0 Buffer Region, or the OPRM Enabled Region.12AOP-04.0
Rev.16 Page 5 of 131
3.0 OPERATOR ACTIONS 2.IF the current operating point is in Region B, THEN use one of the following methods to exit the region: NOTE: NOTE: NOTE: Total core flow should NOT exceed 45 x 10 6 lbs/hr (580/0)in single loop operation.
Whenraisingcore
flow with two reactor recirculation
pumps operating, pump speeds and jet pump loop flow mismatch should be maintained
within the allowable limit.RAISE core flow D INSERT control rods in accordance
with D OENP-24.0, Form 2, Immediate Reactor Power Reduction Instructions.
Operating time in the 5%Buffer Region should be minimized.
3.IF the currentoperatingpoint
is in the 5%Buffer Region, D THEN INCREASE monitoring
nuclear instrumentation
for thermal hydraulic instability.
3.2.5 IF both reactor recirculation
pumps have tripped, THEN PERFORM the following:
1.REDUCE CRD flow to 30 gpm.D 2.IF the Reactor Mode Switch is NOT in RUN, THEN D PLACE the plant in Mode 3 with 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.3.2.6 IF the plant is in single loop operation, THEN PERFORM the following:
1.REDUCE CRD flow to 30 gpm.D 12AOP-04.0
Rev.16 Page 6 of 13\
3.0 OPERATOR ACTIONS NOTE: Total core flow should be maintained
greater than 30.8 x 10 6 Ibs/hr to prevent the idle loop from cooling down and possibly exceeding the 100°F per hour cooldown rate.@]2.IF total core flow is less than 30.8 x 10 6 Ibs/hr, THEN RECORD the following at 15 minute intervals:
Bottom head drain temperature
D Idle loop temperature
D 3.2.7 NOTIFY the duty Reactor Engineer.D 3.2.8 MONITOR individual
LPRM bar graphs from RBM ODAs D or PPC for reactor power oscillations.
[E]3.2.9 MONITOR the following for reactor power oscillations:
APRMs D SRMs D SRM period meters D 3.2.10 MONITOR core thermal parameters
AND ADJUST the following per the Reactor Engineer's
recommendations:
Rod position D Reactor recirculation
pumps speeds D 3.2.11 MONITOR plant parameters
including the following:
Off-gas activity D Stack gas activity 0 Reactor recirculation
pump variables D Recirculation
loop temperatures
D 12AOP-04.0
Rev.16 Page 7 of 131
390 OPERATOR ACTIONS 3.2.12 IF OPRM System is inoperable, AND entry into the 5%Buffer Region is required, THEN INCREASE monitoring
nuclear instrumentation
for thermal hydraulic instability.
D 3.2.13 1.2.3./2AOP-04.0
IF both reactor recirculation
pumps are operating, THEN PERFORM the following:
IF OPRM System is inoperable, THEN ENSURE Region D B is NOT entered.ADJUST reactor recirculation
pump speed as necessary D to maintain pump speed and jet pump loop flow mismatch within required limits.ENSURE thermal limits are NOT violated.D Rev.16 Page 8 of 131
3.0 OPERATOR ACTIONS 3.2.14 IF all of the following conditions
occur, THEN DETERMINE total core flow from U2NSSWDP OR Attachment
1 AND NOTIFY the Reactor Engineer for computer point substitution:
The plant is in single loop operation D Reactor power is greater than or equal to 23%D Computer point U2CPWTCF is NOT available D 3.2.15 CONFIRM all systems and components
are operating D within the Precautions
and Limitations
Section of 20P-02.3.2.16 IF 2AOP-04.0 entry was due to reactor recirculation
D pump trip OR runback, THEN NOTIFY NIT within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to back up OPRM data for evaluation.
3D2D17 NOTIFY Chemistry to sample for iodine within two to six D hours following a change of thermal power of more than 150/0 in one hour.3.2D18 IF entry condition for this procedure was a reactor recirculation
pump trip, THEN PERFORM the following:1D REVIEW OGP-14 for applicability.
D 2D PERFORM the following to facilitate
recovery from loss D of a recirculation
loop: NOTE: An idle reactor recirculation
pump should NOT be started with the discharge valve open./2AOP-04.0
a.bD c.CONTINUE plantoperationwith
the idle reactor D recirculation
pump discharge open.MAINTAIN total core flow between 30D8 x 10 6 D Ibs/hr (40%)and 45 x 10 6 fbs/hr (58%)to provide adequate backflow through the idle loop.IF desired to keep the loops differential
D temperature
less than or equal to 50°F, THEN RAISE the operating reactor recirculation
pump speed AND REDUCE the seal purge flow to a minimum of 3 gpm.Rev.16 Page 9 of 131
GENERAL DISCUSSION
Several varieties of recirculation
flow system malfunctions
can cause a decrease in core coolant flow.The Reactor Recirculation
System creates forced circulation
of reactor coolant through the core.It is a piping system designed primarily to provide driving flow for the reactor jet pumps which, in turn, provide the coolant flow through the reactor core.The system is comprised of two separate and parallel recirculation
loops.The tripping of one recirculation
pump will reduce core flow from 1000/0 to approximately
600/0.In this case, flow would reverse through the 10 idle jet pump diffusers, and the other 10 jet pumps would continue to function.If both recirculation
pumps trip, natural circulation
will provide approximately
300/0 of rated core flow and a gradual reduction in flow is the only result.However, due to core thermal hydraulic instability
uncertainties, the reactor must be manually scrammed in response to a dual recirculation
pump trip with the reactor mode switch in RUN.Recent problems identified
with core flow measurement
in single loop operation, and with recirculation
pump speeds outside the allowable mismatch, have created the need (under some circumstances)
to use core differential
pressure to determine entry into the region of thermal hydraulic instability.
Core differential
pressure was chosen as a means to estimate core flow due to its relationship
to core flow.Recirculation
pumps will automatically
trip on low water level+105" or high pressure 1137 psig.The OPRM system provides alarms and automatic trips as applicable.
If the OPRM System is inoperable, then Tech Specs require an alternate method to detect and suppress thermal hydraulic instability
oscillations
in accordance
with BWR Owners Group Guidelines
for Stability Interim Corrective
Action, June 6 1994.This requires three stability monitoring
regions (RegionA-manual scram, RegionB-immediate exit, and 5%Buffer).\2AOP-04.0
Rev.16 Page 10 of 131
5.0 REFERENCES
em 5.1 NEDO-32465-A, Licensing Topical Report, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology
for Reload Applicability
GE Nuclear Energy, August 1996.5.2 Technical Specifications 5.3 20P-02, Reactor Recirculation
System Operating Procedure[EJ 5.4 General Electric Service Information
Letter No.251/251, Supplement
1 5.5 General Electric Service Information
Letter No.517 5.6 Core Operating Limits Report (COLR)5.7 OENP-24, Reactor Engineering
Guidelines
5.8 Off-SiteDoseCalculation
Manual (ODCM)5.9 LER 1-99-002 (Insertion
of Manual Reactor Trip Due to Reactor Vessel Bottom Head Stratification)
5.10 OGP-14, Extended Single Recirculation
Loop Operation 6.0 ATTACHMENTS
1 Estimated Total Core Flow vs.Core Support Plate Delta-P!2AOP-04.0
Rev.16 Page 11 of 131
ATTACHMENT
1 Page 1 of 1 Estlmlated'TotaJ
COfe Flow'Core Support'PIO'te
Delta P'for'B2C18
Ii I/II/rl/fl/I//lltt/IIIJ))'//.Il/I/
)'1/'/f (I Iii 1/'111'/i 1111/11/'/11'flllllL/,111/1;'7/*
i: IJIJ/I,/*PerCellt j 27.0 26:0 25.0 24.0 23.0 i 22.0 21.0 20.0 19.0
0.0 i 20 25 30 35 40 45 50 55 60 85 70 75 80 85 Core Flow (Mlb/hr)12AOP-04.0
Rev.16 Page 12 of 131
REVISION SUMMARY Revision 16 incorporates
EC 62929 by updating the title of Attachment
1 to reflect B2C18.Revision 15 adds jet pump loop flow limit to recirc speed mismatch criteria.Revision 14 incorporates
EC 46653 (child 62488)by adding PPC point U2NSSWDP as an alternate for determining
total core flow.This revision also adds a caution that an idle recirc pump may not be restarted to exit the scram avoidance region.Revision 13 incorporates
EC 50100 by updating annunciator
A-05 5-8 noun name to'OPRM PDA/CDA ALARM'and EC 56472 by updating the core flow-core dIp figure for the current fuel cycle and update map numbers.Added a step to notify NIT for backing up OPRM data.Revision 12-Incorporated
EC 55156 which adds computer screens 811 and 812 to Note prior to Step 3.2.1 and corrected nomenclature
for screens 806, 807,808, and 809.Revision 11-Format changes to meet the requirements
of OAP-005 and Microsoft Word XP.Steps that are not time dependant have been re-ordered
to provide an easier transition.
Other steps that have common sub-steps have been grouped together.These changes do NOT implement an intent change or a change in procedure methodology.
Additional
administrative
changes classified
as"editorial":
are bolding action verbs, italicizing
components, change of cover page logo, removal of the"bar code" from the cover page, and adding place keeping aids.Revision 10 incorporates
EC 46730'Power Range Neutron Monitoring', EC 47907'EPU Implementation'
and EC 49331'B2C16 Reload Core Design (figure 1).Revision 9 incorporates
ESR 00-00260 by updating Figure 1 (Core Flow vs Core Plate Differential
Pressure)for cycle B2C15.This revision also deletes confusing wording in a caution and deletes a caution that was duplicated
on the same page.Revision 8 provides additional
instructions
for obtaining and documenting
FCBB to ensure Tech Spec Compliance.
\2AOP-04.0
Rev.16 Page 13 of 131
8.3 Recovery from Reactor Recirculation
Pump Runback 8.3.1 Initial Conditions
C Continuous
Use 1.Reactor Recirculation
Pump operation was previously
in accordance
with Section 5.2.D NOTE: Recirculation
Pump runback to approximately
49%speed occurs when reactor water level is less than or equal to 182 inches AND feedwater flow A or B is less than or equal to 16.40/0 of rated flow.A Recirculation
Pump speed runback to 34%will occur when the Recirculation
Pump discharge valve is NOT fully open or total feedwater flow is less than 16.40/0 of the rated flow.Both of these conditions
will require a manual reset of the runback.2.3.The conditions
that caused the runback have cleared.The system operation has stabilized.
D D 120P-02 Rev.126 Page 57 of 1531
8.3.2 Procedural
Steps 1.ADJUST the potentiometer
on RECIRC PUMP 2A(B)D CONTROL lowering the speed demand signal until the speed signal shows a slight decrease in pump speed using multiple indicators.
2.MONITOR Recirculation
Pump speed and be prepared D to manually lock out the scoop tube if speed increases rapidly.3.RESET the recirculation
runback for Reactor Recirculation
Pump A(B)as follows: a.DEPRESS the RECIRC RUNBACK RESET push D button for Reactor Recirculation
Pump A(B).b.ENSURE reactor power and flow are stabilized.
D 4.ADJUST flow as directed by the Unit SCQ.D 120P-02 Rev.126 Page 58 of 1531
5.3 Speed/Power
Increases Using the Recirculation
Pump A(B)Speed Control 5.3.1 Initial Conditions
R Reference Use 1.2.Reactor Recirculation
Pumps in operation in accordance
with Section 5.2.Feedwater flow is greater than 16.4%AND Recirculation
Pump flow limits are cleared.D D 5.3.2 Procedural
Steps NOTE: NOTE: NOTE: Recirculation
Pump speed changes are performed when directed by OGP-04 and OGP-12.Other operating procedures
are used simultaneously
with this procedure as directed by OGP-04, OGP-12, or the Unit seo.Speed changes are accomplished
by slowly turning the potentiometer
clockwise for increases and counterclockwise
for decreases.
Speed limiters number 1 and 2 must be manually reset prior to increasing
pump speed above the respective
speed limit setpoint.The following indications
should be observed to ensure proper response to increased speed demand from a Recirculation
Pump speed controller:
a.Recirculation
Pump speed increases.
b.Recirculation
loop flow increases.
c.Reactor power increases.
120P-02 Rev.126 Page 34 of 1531
5.3.2 Procedural
Steps 1.INCREASE Recirculation
Pump speed in increments
as directed by the Unit SeQ by slowly turning the RECIRC PUMP 2A(2B)SPEED CONTROL potentiometer
in the clockwise direction.
o 120P-02 Rev.126 Page 35 of 1531
Unit 2 APP UA-24 1-4 Page 1 of 1 PEN X 49B ELEV 86'-0" AZIMUTH 315 0 AUTO ACTIONS 1.The following excess flow check valve for the broken instrument
line will close: a.B21-IV-2455 (X49B-A)-excess flow check valve on Instrument
Line B21-7013 for B21-LT-N026A.
CAUSES 1.Pipe break in the above instrument
line.2.Circuit malfunction.
OBSERVATIONS
1.Amber line break indicating
light for penetration
X49B-A on RTGB Panel XU-2 (Control Switch Module RIP-CS-1200)
will be on for the broken instrument
line.2.Valve closed indicating
light for penetration
X49B-A on RTGB Panel XU-2 (Control Switch Module RIP-CS-1200)
will be on for the excess flow check valve on the broken instrument
line.ACTIONS 1.Investigate
the abnormal condition per 001-44.2.If the cause of the annunciator
is an instrument
line break or a circuit malfunction
is suspected, ensure that a WRlwo is prepared.DEVICE/sETPOINTS
Excess flow check valve B21-IV-2455
POSSIBLE
EFFECTS 1.5-3.0 gpm 1.Release of radioactivity
into the secondary containment.
2.Invalid initiation
signals and indications
from the instruments
supplied by the affected instrument
line.3.Excess flow check valve closure may result in a technical specification
LCO.REFERENCES
1.LL-9361-23 2.Technical Specification 3.6.1.3 3.001-44, Excess Flow Check Valve position Indication
Evaluation
Rev.33 Page 80f791
Remote Shutdown Monitoring
Instrumentation
3.3.3.2 3.3 INSTRUMENTATION
3.3.3.2 Remote Shutdown Monitoring
Instrumentation
LCO 3.3.3.2 The Remote Shutdown Monitoring
Instrumentation
Functions shall be OPERABLE.APPLICABILITY:
MODES 1 and 2.ACTIONS
Separate Condition entry is allowed for each Function.CONDITION REQUIRED ACTION COMPLETION
TIME A.One or more required A.1 Restore required Function 30 days Functions inoperable.
to OPERABLE status.8.Required Action and B.1 Be in MODE 3.12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />sassociatedCompletion
Time not met.SURVEILLANCE
REQUIREMENTS
SR 3.3.3.2.1 Brunswick Unit 2 SURVEILLANCE
Perform CHANNEL CHECK for each required instrumentation
channel that is normally energized.
3.3-30 FREQUENCY 31 days (continued)
Amendment No.260
Remote Shutdown Monitoring
Instrumentation
3.3.3.2 SURVEILLANCE
REQUIREMENTS (continued
SURVEILLANCE
FREQUENCY SR 3.3.3.2.2 Perform CHANNEL CALIBRATION
for each required 24 months instrumentation
channel.Brunswick Unit 2 3.3-31 Amendment No.233