ML021340610
| ML021340610 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/22/2002 |
| From: | Division of Reactor Safety II |
| To: | Florida Power & Light Co |
| References | |
| 50-335/02301, 50-389/02301 | |
| Download: ML021340610 (30) | |
See also: IR 05000389/2002301
Text
ST. LUCIE EXAM 2002-301
50-335 & 50-389/2002-301
APRIL 22, 2002
FINAL Submittal
Senior Reactor Operator Written Exam
References
REVISION NO.:
PROCEDURE TITLE:
PAGE:
13
CONTROL ROOM INACCESSIBILITY
43 of 89
PROCEDURE NO.'
2-ONP-100.02
ST. LUCIE UNIT 2
APPENDIX E
PLANT COOLDOWN & SHUTDOWN COOLING OPERATION
(Page 1 of 11)
INITIAL
1. ENSURE at least ONE of the following valves is positioned as
indicated to align charging pump suction from the BAMTs:
"* V2508, 2B BAMT Outlet to Gravity Feed MOV, is OPEN
"* V2509, 2A BAMT Outlet to Gravity Feed MOV, is OPEN
2.
MAINTAIN Pressurizer level 30 to 70% during plant cooldown.
NOTE
Supplemental portable lighting may be obtained for component manipulations
outside the Control Room.
"* Dedicated portable lanterns are available at the following locations:
"* Storage Locker 1: Walkway to Containment Personnel Hatch
"* Storage Locker 2: RAB Hallway West End (-0.5' elevation)
"* Storage Locker 3: RAB M.G. Set Room (19.5' elevation)
"* Storage Locker 4: RAB HVAC Room West (43.0' elevation)
"* Temporary portable lanterns are available at the following locations:
"* Field Operator Facility (FOF)
"* Steam Trestle (Inside Mezzanine level door)
"* Additional guidance may be found in OP 2-0030127, Reactor Plant
Cooldown - Hot Standby to Cold Shutdown or ONOP 2-0120039, Natural
Circulation Cooldown.
"* Performing an RCS cooldown with the charging pump suctions aligned to
the BAMTs for Pressurizer makeup due to shrinkage will ensure adequate
shutdown margin is maintained
"
Cooldown and Boration are performed simultaneously.
REVISION NO.:
PROCEDURE TITLE:
PAGE:
13
CONTROL ROOM INACCESSIBILITY
44 of 89
PROCEDURE NO.:
2-ONP-1 00.02
ST. LUCIE UNIT 2
APPENDIX E
PLANT COOLDOWN & SHUTDOWN COOLING OPERATION
(Page 2 of 11)
INITIAL
CAUTION
"* BOTH 2A and 2B BAMT level indications may NOT be reliable.
"* BAM tanks contain approximately 99 gallons per %.
"* BAM tank usage must be closely monitored to prevent gas binding of the
charging pump.
"* The charging pump low suction pressure trip is removed from the trip
circuit when the charging pump NORMAL / ISOLATE switch is in
ISOLATE.
NOTE
"* Cooldown and Boration are performed simultaneously.
"Continue with this appendix while borating and cooling down.
" Perform Step 3 when the required BAMT volume has been iniected.
3.
When an amount greater than the minimum required Technical
Specifications volume, in accordance with Figure 3.1-1, St. Lucie 2 Min
BAMT (attached), has been injected into the RCS from the BAM
tank(s), Then ALIGN the RWT for makeup as follows:
A. STOP ALL Charging Pumps.
B. POSITION the following components as indicated:
COMPONENT
COMPONENT NAME
POSITION
PERF
ID
INITIAL
V2504
RWT to Chg Pump Suction
OPEN
V2508
1B BAMT Outlet to Gravity Feed MOV
CLOSED
V2509
1A BAMT Outlet to Gravity Feed MOV
CLOSED
C. OPERATE the available Charging Pump(s) as required to maintain
Pressurizer level 30 to 70%.
REVISION NO.:
PROCEDURE TITLE:
PAGE:
13
CONTROL ROOM INACCESSIBILITY
86 of 89
PROCEDURE NO.:
2-ONP-100.02
ST. LUCIE UNIT 2
srT IlUCIF* 2 MIN RAMT
FIGURE 8
FIGURE 3.1-1
VOLUME VS STORED BAMT CONCENTRATION
(Page 1 of 1)
10
9
8
7
6
5
4
3
2.4
2.6
2.8
3
3.2
3.4
3.6
(4196 PPM)
(4546 PPM)
(4896 PPM)
(5245 PPM)
(5595 PPM)
(5944 PPM)
(6294 PPM)
STORED BAMT CONC (wt % boric acid)
0)
Lu
0
l'
z 2
m
0
-Z
REVISION NO.:
PROCEDURE TITLE:
PAGE:
33
PPENDIXES / FIGURES / TABLES / DATA SHEETS
123 of 158
PROCEDURE NO:
1-EOP-99
ST. LUCIE UNIT 1
FIGURE 1A
RCS PRESSURE TEMPERATURE
(Page 1 of 1)
(Containment Temperature Less Than or Equal to 200'F)
100
200
300
400
500
Indicated RCSTemperature (F)
600
700
800
CAUTION
The RCP NPSH curve assumes one pump is operating in each loop. RCP
instrumentation should be monitored for seal and pump performance in
accordance with 1-NOP-01.02, Reactor Coolant Pump Operation, as the
NPSH curve is approached.
2400
2200
2000
1800
1600
1400
1200
1000
800
600
400
200
0
REVISION NO.:
PROCEDURE TITLE:
PAGE:
33
PPENDIXES / FIGURES / TABLES / DATA SHEETS
124 of 158
PROCEDURE NO:
1-EOP-99
ST. LUCIE UNIT 1
FIGURE 1B
RCS PRESSURE TEMPERATURE
(Page 1 of 1)
(Containment Temperature Greater Than or Equal to 200'F)
0
100
200
300
400
500
Indicated RCS Temperature (F)
600
700
800
t)PM1/2 l&PY
CAUTION
The RCP NPSH curve assumes one pump is operating in each loop. RCP
instrumentation should be monitored for seal and pump performance in
accordance with 1-NOP-01.02, Reactor Coolant Pump Operation, as the
NPSH curve is approached.
2400
2200
2000
1800
1600
1400
1200
1000
800
600
400
200
0
§2
CAUTION
Section 1.A should not be used for a steam generator tube leak/rupture.
EVENT/CLASS
1.A. ABNORMAL
PRIMARY
LEAK RATE
(Page 1 of 2)
UNUSUAL EVENT
FROSt Leakage
1. RCS leakage
GREATER THAN
10 gpm as indicated
by:
A. Control Room
observation
B. Inventory balance
calculation
C. Field observation
D. Emergency
Coordinator
judgement
2. Indication of leaking
RCS safety or relief
valve which causes
RCS pressure to drop
below setpoints:
Unit 1 - 1600 psia
Unit 2- 1736 psia
ALERT
RCS Leakage GREATER
THAN 50 gpm
1. Unisolable RCS
leakage as indicated by
Charging/letdown
mismatch greater than
50 gpm but less than
available charging
pump capacity.
2. Unisolable measured
RCS leakage indicating
greater than 50 gpm
but less than available
charging pump
capacity.
SITE AREA EMERGENCY
LOCA GREATER THAN
capacity of charging pumps
1. RCS leakage greater
than available charging
pump capacity occurring
with RCS pressure
above HPSI shutoff
head.
2. RCS leakage greater
than available makeup
occurring with RCS
pressure below HPSI
shutoff head.
3. Loss of RCS subcooled
margin due to RCS
leakage (saturated
conditions).
4. Containment High Range
Radiation Monitors
indicate
7.3 X 10' R/hr (If
CHRRM inoperable,
Post-LOCA monitors
indicate between
100 and 1000 mR/hr).
GENERAL EMERGENCY
A release has occurred or is
in progress resulting in:
1. Containment High Range
Radiation monitor greater
than 1.46 X 10W RJhr (If
CHRRM inoperable. Post
LOCA monitors greater
than 1000 mR/hr).
2. Performance of EPIP-09
(Off-site Dose
Calculations) or
measured dose rates
from off-site surveys
indicate site boundary
(1 mile) exposure levels
have been exceeded as
indicated by either A, B,
C or D below:
A. 1000 mrem/hr
(total dose rate)
B. 1000 mrem
(total dose - TEDE)
C. 5000 mrem/hr
(thyroid dose rate)
D. 5000 mrem
(thyroid dose - CDE)
(continued on next page)
1.A. ABNORMAL
PRIMARY
LEAK RATE
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
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EVENTICLASS
I.A.
ABNORMAL
PRIMARY
LEAK RATE
(Page 2 of 2)
UNUSUAL EVENT
ALERT
SITE AREA EMERGENCY
GENERAL EMERGENCY
Loss of 2 of the 3 fission
product barriers with
imminent loss of the third
(any two of the following
exist and the third is
imminent).
1. Fuel element failure
(confirmed DEQ 1-131
activity greater than
275 pCi/mL).
AND
2. LOCA or Tube rupture on
unisolable steam
generator.
AND
3. Containment Integrity
Breached.
NOTE
Also refer to Potential
Core Melt Event/
Class 6.A.
1.A. ABNORMAL
PRIMARY
LEAK RATE
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
(
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EVENT/CLASS
1.B. ABNORMAL
PRIMARY TO
SECONDARY
LEAK RATE
(Page 1 of 2)
UNUSUAL EVENT
RCS PRI/SEC Leakage
1. Measured RCS to
secondary leakage
exceeds Tech. Spec.
limits.
AND
2. Secondary plant activity
is detected.
ALERT
Rapid gross failure of one
steam generator tube
(WITHIN charging pump
capacity) with loss of offsite
power
1. Measured RCS to
secondary leakage
greater than Tech. Spec.
Limits and within
charging pump capacity.
AND
2. Secondary plant activity
is detected.
AND
3. Loss of both Non-Vital
4.16 KV buses.
(continued on next page)
SITE AREA EMERGENCY
Rapid gross failure of steam
generator tubes (GREATER
THAN charging pump
capacity) with a loss of
offsite power
1. Measured RCS to
secondary leakage is
greater than charging
pump capacity.
AND
2. Secondary plant activity
is detected.
AND
3. Loss of both Non-Vital
4.16 KV buses.
(continued on next page)
GENERAL EMERGENCY
Loss of 2 of the 3 fission
product barriers with
imminent loss of the third
(any two of the following
exist and the third is
imminent).
1. Fuel element failure
(confirmed DEC 1-131
activity greater than
275 jCi/mL).
AND
2. LOCA or Tube rupture
on unisolable steam
generator.
AND
3. Containment integrity
breached.
I
NOTE
Also refer to Potential
0
Core Melt Eventf
Class 6.A.
1.8. ABNORMAL
PRIMARY TO
SECONDARY
LEAK RATE
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
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EVENTICLASS
l.B. ABNORMAL
PRIMARY TO
SECONDARY
LEAK RATE
(Page 2 of 2)
UNUSUAL EVENT
ALERT
Rapid failure of steam
generator tubes (GREATER
THAN charging pump
capacityl
1. Measured RCS to
secondary leakage
greater than charging
pump capacity.
AND
2. Secondary plant activity
is detected.
SITE AREA EMERGENCY
§, Rapid failure of steam
qenerator tube(s) (GREATER
THAN charging pump
capacity) with steam release
in progress
1. Measured RCS to
secondary leakage
greater than charging
pump capacity.
AND
2. Secondary plant activity
is detected.
AND
3. Secondary steam release
in progress from affected
generator (i.e., ADVs,
stuck steam safety(s) or
unisolable leak.)
GENERAL EMERGENCY
lB. ABNORMAL
PRIMARY TO
SECONDARY
LEAK RATE
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
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EVENT/CLASS
1.C. LOSS OF
SECONDARY
COOLANT
(Page 1 of 2)
UNUSUAL EVENT
Rapid depressurization of
secondary plant
1. Rapid drop in either
pressure to less than
600 psia.
ALERT
Major steam leak with
GREATER THAN 10 qpm
primary/secondary leakage
1. Rapid drop in either
pressure to less than
600 psia.
AND
2. Known pri/sec leak of
greater than 10 gpm.
AND
3. Secondary plant activity
is detected.
Total loss of feedwater
1. No main or auxiliary
feedwater flow available
for greater than
15 minutes when
required for heat
removal.
AND
2. Steam Generator levels
are less than 40% wide
range.
SITE AREA EMERGENCY
Maior steam leak with
GREATER THAN 50 qpm
primary/secondary leakage
and fuel damage indicated
1. Rapid drop in either
steam generator pressure
to less than 600 psia.
AND
2. Known pri/sec leak of
greater than 50 gpm.
AND
3. Secondary plant activity is
detected.
AND
4. Fuel element damage is
indicated (Refer to Fuel
Element Failure
Event/Class 4.A).
TLOF with once-through
cooling initiated
1. No main or auxiliary
feedwater flow available.
AND
2. PORV(s) have been
opened to facilitate core
heat removal.
GENERAL EMERGENCY
A release has occurred or is in
progress resulting in:
1. Containment High Range
Radiation monitor greater
than 1.46 X 10' R/hr (If
CHRRM inoperable, Post
LOCA monitors greater than
1000 mR/hr).
2. Performance of EPIP-09
(Off-site Dose Calculations)
or measured dose rates from
off-site surveys indicate site
boundary (1 mile) exposure
levels have been exceeded
as indicated by either A, B, C
or D below:
A. 1000 mrem/hr
(total dose rate)
B.
1000 mrem
(total dose - TEDE)
C. 5000 mrem/hr
(thyroid dose rate)
0. 5000 mrem
(thyroid dose-CDE)
(continued on next page)
1C. LOSS OF
SECONDARY
COOLANT
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
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EVENT/CLASS
UNUSUAL EVENT
ALERT
SITE AREA EMERGENCY
1.C. LOSS OF
SECONDARY
COOLANT
(Page 2 of 2)
GENERAL EMERGENCY
Loss of 2 of the 3 fission
product barriers with
imminent loss of the third
(any two of the following
exist and the third is
imminent).
1. Fuel element failure
(confirmed DEQ 1-131
activity greater than
275 pCi/mL).
AND
2. LOCA or Tube rupture
on unisolable steam
generator.
AND
3. Containment Integrity
Breached.
NOTE
Also refer to Potential Core
Melt Event/Class 6.A.
1.C. LOSS OF
SECONDARY
COOLANT
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
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EVENTICLASS
2.A. UNCONTROLLED
EFFLUENT
RELEASE
UNUSUAL EVENT
Radiological effluent
limits exceeded
1. Plant effluent
monitor(s)
exceed alarm
setpoint(s).
AND
2. Confirmed
analysis results
for gaseous or
liquid release
which exceeds
ODCM limits.
NOTE
If analysis is not
available within
one hour and it is
expected that
release is greater
than ODCM limit,
classify as
UNUSUAL EVENT.
ALERT
A release has occurred or §2
is in progress that is
10 times the effluent limit
1. Plant effluent
monitor(s) significantly
exceed alarm
setpoints.
AND
2. Confirmed analysis
results for gaseous or
liquid release which
exceeds 10 times
ODCM limits.
NOTE
If analysis is not
available within one
hour and it is expected
that release is equal to
or greater than 10 times
ODCM limit, classify as
ALERT.
SITE AREA EMERGENCY
A release has occurred or is in
progress resulting in:
I. Containment High Range
Radiation Monitor greater
than 7.3 X 10' R/hr
(Post-LOCA monitors
indicate between 100 and
1000 mR/hr, if CHRRM
2. Measured Dose Rates or
Offsite Dose Calculation
(EPIP-09) worksheet values
at one mile in excess of:
A.
50 mrem/hr (total dose
rate) or 250 mrem/hr
(thyroid dose rate) for
1/2 hour.
B.
500 mrem/hr (total dose
rate) or 2500 mrem/hr
(thyroid dose rate) for
two minutes at one
mile.
GENERAL EMERGENCY
A release has occurred or is in
progress resulting in:
1. Containment High Range
Radiation monitor greater than
1.46 X 10' R/hr (If CHRRM
inoperable, Post-LOCA monitors
greater than 1000 mR/hr).
2. Performance of EPIP-09 (Off-site
Dose Calculations) or measured
dose rates from off-site surveys
indicate site boundary (1 mile)
exposure levels have been
exceeded as indicated by either
A, B, C or D below:
A. 1000 mrem/hr
(total dose rate)
B. 1000 mrem
(total dose - TEDE)
C. 5000 mremlhr
(thyroid dose rate)
D. 5000 mrem
(thyroid dose-CDE)
ODCM - refeus to Chemoisty Procedure C-200 Oftscte Dose Calculation Manual (0DCM)
2.A.
UNCONTROLLED
EFFLUENT
RELEASE
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
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EVENTICLASS
UNUSUAL EVENT
2.8. HIGH RADIATION
LEVELS IN PLANT
ALERT
SITE AREA EMERGENCY
GENERAL EMERGENCY
High radiation levels or high
airborne contamination which
indicates a severe degradation
in the control of radioactive
materials
1. Any valid area monitor
alarm from indeterminable
source with meter near or
greater than full scale
deflection (10' mRlhr).
2. Unexpected plant iodine or
particulate airborne
concentration of 1000 DAC
as seen in routine surveying
or sampling.
3. Unexpected direct radiation
dose rate reading or
unexpected airborne
radioactivity concentration
from an indeterminable
source in excess of
1000 times normal levels.
2.B. HIGH RADIATION
LEVELS IN PLANT
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
0
m
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0.
UNUSUAL EVENT
§2 Uncontrolled fire within the
Power Block lasting more
than 10 minutes.
ALERT
Uncontrolled fire
1. Potentially affecting
safety systems.
AND
2. Requiring off-site
support in the opinion of
the NPSIEC.
SITE AREA EMERGENCY
§2 Fire compromising the
function of safety systems
(e.g., both trains rendered
GENERAL EMERGENCY
NOTE
Refer to Potential Core Melt
Event/Class 6.A.
§2
NOTE
Explosion is defined as a rapid chemical reaction resulting in noise, heat and rapid
expansion of gas.
Occurrence of an
explosion within the
Owner Controlled Area.
§2 Damage to
structures/components in
the Protected Area by
explosion which affects
plant operation.
§2 Severe damage to safe
shutdown equipment from
explosion (e.g., both trains
rendered inoperable.
3. FIRE
EXPLOSION
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
EVENT/CLASS
3. FIRE
EXPLOSION
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EVENT/CLASS
4.A. FUEL
ELEMENT
FAILURE
ALERT
Fuel element failure
1. Process monitors or
area radiation surveys
indicate increased
letdown activity and
confirmed RCS Samples
indicating DEC 1-131
activity greater than or
equal to 275 pCi/mL.
SITE AREA EMERGENCY
Fuel element failure with
inadequate core cooling
greater than or equal to
275 pCi/mL.
AND
2. Highest CET per core
quadrant indicates greater
than 1O0F superheat or
700-F,
UNUSUAL EVENT
Fuel element damage
1. Process monitors or
area radiation surveys
indicate increased
letdown activity
AND
2. Confirmed RCS sample
indicating:
A. Coolant activity
greater than the
Tech Spec limit for
iodine spike (Tech
Spec Figure 3.4-1.).
B. Coolant activity
greater than
100/t pCi/gram
specific activity.
NOTE
If analysis is not available
within one hour and it is
expected that activity is
greater than Tech Spec
limit, classify as
UNUSUAL EVENT.
GENERAL EMERGENCY
A release has occurred or is in
progress resulting in:
1. Containment High Range
Radiation monitor greater than
1.46 X 10' f/hr (If CHRRM
inoperable, Post-LOCA
monitors greater than
1000 mR/hr).
2. Performance of EPIP-09
(Off-site Dose Calculations) or
measured dose rates from
off-site surveys indicate site
boundary (1 mile) exposure
levels have been exceeded as
indicated by either A. B, C or
D below:
A. 1000 mrem/hr
(total dose rate)
B. 1000 mrem
(total dose - TEDE)
C. 5000 mrem/hr
(thyroid dose rate)
D. 5000 mrem
(thyroid dose - CDE)
4.A
FUEL
ELEMENT
FAILURE
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
NOTE
If analysis is not available
within one hour and it is
expected that RCS activity
for DEQ 1-131 is greater
than 275 pCi/mL, classify
as an ALERT.
T
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EVENTICLASS
UNUSUAL EVENT
4.B. FUEL HANDLING
ACCIDENT
ALERT
Fuel handling accident which
results in the release of
radioactivity to Containment or
Fuel Handling Building:
1. NPS/EC determines that an
irradiated fuel assembly may
have been damaged.
AND
2. Associated area or process
radiation monitors are in
alarm.
SITE AREA EMERGENCY
§2 Major damage to irradiated
fuel in Containment or Fuel
Handling Building
1. Affected area radiation
monitor greater than
1000 mrem/hr.
AND
2. Damage to more than
one irradiated fuel
assembly.
DR
Major damage resulting
from uncovering of one
or more irradiated fuel
assemblies in the Spent
Fuel Pool.
GENERAL EMERGENCY
43. FUEL HANDLING
ACCIDENT
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
m
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EVENT/CLASS
UNUSUAL EVENT
5.A.
§2 A confirmed earthquake
has occurred
1. A confirmed
earthquake has been
experienced within the
Owner Controlled
Area.
2. ¶, An earthquake is
detected by plant
seismic monitor
instruments or other
means.
5B. HURRICANE
Hurricane Waming
1. Confirmed hurricane
warning is in effect.
ALERT
§2 A confirmed earthquake has occurred.
§2
1. A confirmed earthquake has
occurred which registered
GREATER THAN 0.05g within the
Owner Controlled Area
2 A confirmed earthquake has
occurred that could or has caused
trip of the turbine generator or
reactor
Hurricane warnino with winds near
design basis
1. Confirmed hurricane warning is in
effect and winds are expected to
exceed 175 mph within the Owner
Controlled Area.
SITE AREA EMERGENCY
A confirmed earthquake has occurred.
1. A confirmed earthquake has
occurred which registered
GREATER THAN G.ig within the
Owner Controlled Area and the
plant not in Cold Shutdown.
2. A confirmed earthquake has
occurred that has caused loss of
any safety system function (e.g.,
both trains inoperable).
Hurricane warninq with winds
GREATER THAN desiqn basis
1. Plant not at cold shutdown.
AND
2. Confirmed hurricane warning is in
effect and winds are expected to
exceed 194 mph within the Owner
Controlled Area,
GENERAL EMERGENCY
NOTE
Refer to Potential Core
Melt Event/Class 6.A.
NOTE
Refer to Potential Core
W
Melt Event/Class 6 A
0
-tO
0
5A. EARTHQUAKE
5.B. HURRICANE
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
CA)
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NOTE
At FPL s request, NOAA will provide
an accurate projection of wind speeds
onsite 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the onset of
hurricane force winds. If that
projection is not available within
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering into the warning,
classify the event using current track
and wind speeds to project onsite
conditions. For example, projected
onsite wind speed would be less than
maximum hurricane wind speed if the
track is away from PSL.
NOTE
At FPLs request. NOAA will provide
an accurate projection of wind
speeds onsite 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the
onset of hurricane force winds. If
that projection is not available within
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering into the warning,
classify the event using current track
and wind speeds to project onsite
conditions. For example, projected
onsite wind speed would be less than
maximum hurricane wind speed if the
track is away from PSL.
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EVENT/CLASS
5.C. TORNADO
5.D. ABNORMAL
WATER LEVEL
UNUSUAL EVENT
Notification of a tornado
sighted in the Owner
Controlled Area
Abnormal water level
conditions are expected
or occurring
1. Low intake canal
level of -10.5 ft.
MLW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or
more.
2. Visual sightings by
station personnel
that water levels are
approaching storm
drain system
capacity.
ALERT
§2 Any tornado striking the Power
Block.
Flood, low water. hurricane suroe or
other abnormal water level
conditions
1. The storm drain capacity is
exceeded during hurricane surge
or known flood conditions.
2. Low intake canal level of -10.5 ft.
MLW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or more with
emergency barrier valves open.
SITE AREA EMERGENCY
GENERAL EMERGENCY
NOTE
Refer to Potential Core
Melt Event/Class 6.A.
Flood. low water, hurricane suroe or
other abnormal water level
conditions causing failure of vital
equipment
1. Flood/surge water level reaching
elevation +19.5 ft. (turbine
building/RAB ground floor).
2. Low intake canal level has
caused the loss of all ICW flow.
5.C. TORNADO
5.D. ABNORMAL
WATER LEVEL
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
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Activation of the Emergency Response Facilities does not require declaration of an emergency or entry into a specific emergency classification.
EVENTICLASS
5.A.
INCREASED
AWARENESS
POTENTIAL
CORE MELT
(Page 1 of 2)
UNUSUAL EVENT
Emergency Coordinator's
judgement that plant
conditions exist which
warrant increased
awareness on the part of
the operating staff andfor
local authorities.
1. The plant is shutdown
under abnormal
conditions (e.g..
exceeding cooldown
rates or primary
system pipe cracks are
found during
operation)
2. Any plant shutdown
required by Technical
Specifications in which
the required shutdown
is not reached within
action limits.
ALERT
§2 Emergency Coordinator's
judgement that plant
conditions exist which
have a potential to
degrade the level of safety
at the plant.
SITE AREA
EMERGENCY
§Ž Emergency Coordinator's
judgement that plant
conditions exist which are
significantly degrading in
an uncontrollable manner.
GENERAL EMERGENCY
Emeroencv Coordinator's iudoement that
plant conditions exist that make release or
laroe amounts of radioactivity in a short
period appear possible or likely. (Any core
melt situation)
1. LOCA with failure of ECCS leading to
severe core degradation or melt.
2. LOCA with initially successful ECCS and
subsequent failure of containment heat
removal systems for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
3. Total loss of feedwater followed by failure
of once-through-cooling (ECOS) to
adequately cool the core,
4. Failure of off-site and on-site power along
with total loss of feedwater makeup
capability for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
5. ATWS occurs which results in core
damage or causes failure of core cooling
and make-up systems.
6. Any major internal or external event (e p.,
fire, earthquake or tornado substantially
beyond design basis) which in the ECs
opinion has or could cause massive
damage to plant systems resulting in any
of the above.
(continued on next page)
SA.
INCREASED
AWARENESS
POTENTIAL
CORE MELT
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
03
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EVENTICLASS
UNUSUAL EVENT
ALERT
SITE AREA EMERGENCY
6.A. INCREASED
AWARENESS
OR POTENTIAL
CORE MELT
(Page 2 of 2)
GENERAL EMERGENCY
6.A.
INCREASED
AWARENESS
OR POTENTIAL
CORE MELT
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
m
0
m
0 m
z
0
NOTES
1. Most likely containment failure
mode is melt-through with
release of gases only. Quicker
releases are expected for failure
of containment isolation system.
2. General Emergency must be
declared for the above listed
events. The likelihood of
corrective action (repair of AFW
pump, etc.) should not be
considered.
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EVENTICLASS
7A. LOSS OF
POWER
UNUSUAL EVENT
Loss of off-site power or
loss of all on-site AC power
capability.
1. Loss of off-site AC
power.
2. Loss of capability to
power at least one vital
4.16 kv bus from any
available emergency
diesel generator.
ALERT
§2 Station Blackout (Total Loss
of AC)
1. Loss of off-site
AC power.
AND
2. Failure of both
emergency diesel
generators to start or
load.
Loss of all on-site DC
power
1. Drop in A and B DC bus
voltages to less than
70 VDC.
SITE AREA EMERGENCY
§2 Station Blackout (Total Loss
of AC) for GREATER THAN
15 minutes
I. Loss of offsite AC power.
AND
2. Sustained failure of both
emergency diesel
generators to start or
load.
AND
3. Failure to restore
AC power to at least one
vital 4.16 kv bus within
15 minutes.
Loss of all vital on-site DC
for greater than 15 minutes
1. Sustained drop in A and
B DC bus voltages to
70 VDC for greater than
15 minutes.
GENERAL EMERGENCY
NOTE
Refer to Potential Core
Melt Event/Class
.A.
7.A.
LOSS OF
POWER
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
m
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EVENTICLASS
UNUSUAL EVENT
&A. LOSS OF PLANT
CONTROL
FUNCTIONS
ALERT
Loss of Plant Control
Functions
1. Complete loss of any
function needed for plant
cold shutdown.
2 Failure of the Reactor
Protection System to
bring the reactor
subcritical when needed.
3. Control Room is
evacuated (for other than
drill purposes) with control
established locally at the
Hot Shutdown Control
Panel.
Loss of Shutdown Cooling
1 Complete loss of
functions needed to
maintain cold shutdown.
A. Failure of shutdown
cooling systems,
resulting in loss of
cold shutdown
conditions.
AND
B. RCS subcooling can
NOT be maintained
greater than 0°F.
SITE AREA EMERGENCY
Critical Loss of Plant Control
Functions
1. Loss of any function or
system which, in the
opinion of the Emergency
Coordinator, precludes
placing the plant in Hot
Shutdown.
2. Failure of the RPS to trip
the reactor when needed
and operator actions fail to
bring the reactor
subcritical,
3. Control Room is evacuated
(for other than drill
purposes) and control
cannot be established
locally at the Hot Shutdown
Control Panel within
15 minutes.
GENERAL EMERGENCY
8.A.
LOSS OF PLANT
CONTROL
FUNCTIONS
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
-o
"13
0
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EVENTICLASS
8B. LOSS OF ALARMS /
COMMUNICATION /
MONITORING
UNUSUAL EVENT
§2 Significant loss of effluent
monitoring capability,
communications, indication
and alarm panels. etc.. which
impairs ability to perform
accident or emergency
assessment.
1. Loss of effluent or
radiological monitoring
capability requiring plant
shutdown.
2. Loss of all primary and
backup communication
capability with offsite
locations.
3. Unplanned loss of most
(greater than 75%) or all
Safety System
annunciators for greater
than 15 minutes.
ALERT
§2
Loss of alarms
1. Unplanned loss of
most (greater than
75%) or all safety
system annunciators.
AND
2. Plant transient in
progress.
SITE AREA EMERGENCY
Loss of alarms/monitoring
1. Inability to monitor* a
significant transient in
progress.
GENERAL EMERGENCY
-1
Qo
o0
- Monitoring means loss of
the inability to determine
any one of the following:
reactivity control, core
cooling. RCS status or
containment integrity.
8.B.
LOSS OF ALARMS /
COMMUNICATION /
MONITORING
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
CA
(
0
0 m
m
-1
m
m
Iz
Cl)
-n
0
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C)
"-D
z
--
EVENT/CLASS
9.A. AIRCRAFT/
MISSILE
UNUSUAL EVENT
ALERT
Unusual aircraft activity
§2 Aircraft/missile impact
1. Aircraft crash in the
Owner Controlled Area
or unusual aircraft
activity over facility that
in the opinion of the
NPS/EC, could
threaten the safety of
the plant or personnel.
9.B. TURBINE
FAILURE
9.C. TOXIC OR
FLAMMABLE
GAS
Turbine rotating
component failure causing
rapid plant shutdown.
U n pla nnedluncontrolled
toxic or flammable gas
release in the Owner
Controlled Area that could
affect plant/personnel
safety.
1. Aircraft crash into the
Power Block.
2. Visual or audible
indication of missile
impact on the Power
Block.
Visual indication that the
turbine casing has been
penetrated by blading.
Entry of toxic or flammable
gas into areas potentially
affecting plant operation.
SITE AREA EMERGENCY
§2 Damage to vital systems
from aircraftlmissiles
1. Aircraft crash into the
Power Block damaging
vital plant systems.
2. Damage resulting in loss
of sale shutdown
equipment from any
missilpe.
GENERAL EMERGENCY
(D
0
-.o
0
§2 Toxic or flammable gas has
diffused into vital areas
compromising the function
of safety related equipment
(e.g., both trains rendered
9.A. AIRCRAFT /
MISSILE
9.B. TURBINE
FAILURE
9.C. TOXIC OR
FLAMMABLE
GAS
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
C
0
m
0
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2 0
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O5
UNUSUAL EVENT
A SECURITY ALERT has
been called by the Security
Force in response to one
or more of the items listed
below.
1. Bomb threat
2.
3.
4.
5.
6.
7.
8.
Attack threat
Civil disturbance
Protected area
intrusion
Sabotage attempt
Internal disturbance
Vital area intrusion
Security force strike
ALERT
A SECURITY
EMERGENCY has been
called by the Security
Force as defined in the
Safeguards Contingency
Plan.
SITE AREA EMERGENCY
A SECURITY EMERGENCY
involving imminent
occupancy of the control
room or other area(s) vital
to the operation of the
reactor as defined in the
Safeguards Contingency
Plan.
GENERAL EMERGENCY
A successful takeover of the
plant including the Control
Room or any other area(s)
vital to the operation of the
reactor (as per the Security
Plan).
10. SECURITY
THREAT
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
EVENT/CLASS
10. SECURITY
THREAT
m
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REVISION NO.:
PROCEDURE TITLE:
PAGE:
37C
SHUTDOWN COOLING OFF-NORMAL
PROCEDURE NO:
39 of 45
2-0440030
ST. LUCIE UNIT 2
FIGURE 1
TIME TO CORE BOILING
(Page 1 of 3)
PEFER TO FIGURE 1C FOP ADJUSTING TIME TO BOIL
REVISION NO.:
PROCEDURE TITLE:
PAGE:
37C
SHUTDOWN COOLING OFF-NORMAL
PROCEDURE NO.:
40 of 45
2-0440030
ST. LUCIE UNIT 2
FIGURE 1
TIME TO CORE BOILING
(Page 2 of 3)
Fiqute 113
TIME TO CORE BOILING, 0TO40 DAYS AFTER 50D, R1S AT MID.LOOP
t Int
0
2
4
6
B
19 12
14
16
18
20
22
24
28
2B
30
32
34
36
30
40U
Time afwtr 5ID (divs)
REFER TO FIGURE 1C FOP ADJUSTING TIME TO FOnl
L
H
REVISION NO.:
PROCEDURE TITLE:
PAGE:
37C
SHUTDOWN COOLING OFF-NORMAL
PROCEDURE NO:
41 of 45
2-0440030
ST. LUCIE UNIT 2
FIGURE 1
TIME TO CORE BOILING
(Page 3 of 3)
CORRECTION FORMULAS
1. If the Refueling Cavity level is greater than 36 feet, Then PERFORM the
following equations to correct time to boil.
A .
...........
.. ft - 36 =
Cavity level - 36 = adjusted level.
ft
B.
{1 + [0.23] x [ --------------
ft]} = ----------
{1 + [0.23] x [adjusted level]} = multiplier
C.
x
min= =
.
.
.
mi
multiplier x time to boil from curve = corrected time to boil
2.
If the core shuffle or reload has been completed, Then PERFORM the
following equation to correct time to boil.
Time to boil from curve or
corrected time to boil from 1.C
x 1.35 =
min
x 1.35 = corrected time to boil
11
REVISION NO.,
PROCEDURE TITLE:
PAGE:
37C
SHUTDOWN COOLING OFF-NORMAL
PROCEDURE NO.:
42 of 45
2-0440030
ST. LUCIE UNIT 2
FIGURE 2
FLOW TO MAKEUP FOR BOIL-OFF
(Page 1 of 1)
0CD
0
-J
U
0
U'
0
5
10
15
20
25
30
35
40
45
50
55
60
65
70
75
80
85
90
Time Since Shutdown (Days)
cIOPSsOPs-F2-4m
Assumptions:
Power History = 100%
Makeup Water Temp. = 100 0F
Boiling Point Temp. = 212°F