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)
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.
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.
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.
"Continuewith 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
FIGURE 8
FIGURE 3.1-1
srT IlUCIF* 2 MIN RAMT VOLUME VS STORED BAMT CONCENTRATION
(Page 1 of 1)
10
9
8
0)
7
Lu m
0 0
6
l' -Z
z
2
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)
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)
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
100 200 300 400 500 600 700 800
Indicated RCSTemperature (F)
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)
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
0 100 200 300 400 500 600 700 800
Indicated RCS Temperature (F) t)PM1/2 l&PY
C
p0 m
M
§2 CAUTION 0
-Cc z0
Section 1.A should not be used for a steam generator tube leak/rupture.
o z
0p
EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
1.A. ABNORMAL Reactor Coolant System RCS Leakage GREATER LOCA GREATER THAN A release has occurred or is w
THAN 50 gpm capacity of charging pumps in progress resulting in: *0
PRIMARY FROSt Leakage
LEAK RATE 0
(Page 1 of 2) 1. RCS leakage 1. Unisolable RCS 1. RCS leakage greater 1. Containment High Range m
GREATER THAN leakage as indicated by than available charging Radiation monitor greater 0
C:
X
10 gpm as indicated Charging/letdown pump capacity occurring than 1.46 X 10WRJhr (If m
by: mismatch greater than with RCS pressure CHRRM inoperable. Post C1
01
50 gpm but less than above HPSI shutoff LOCA monitors greater
A. Control Room
observation
available charging
pump capacity.
head.
than 1000 mR/hr).
z
OR OR 2. RCS leakage greater 2. Performance of EPIP-09
B. Inventory balance 2. Unisolable measured than available makeup (Off-site Dose C,)
calculation RCS leakage indicating occurring with RCS Calculations) or (C)
OR greater than 50 gpm pressure below HPSI measured dose rates (D i
C. Field observation but less than available shutoff head. from off-site surveys M
0
OR charging pump OR indicate site boundary
-C
D. Emergency
Coordinator
capacity. 3. Loss of RCS subcooled
margin due to RCS
(1 mile) exposure levels
have been exceeded as
0 -I
z r
judgement leakage (saturated indicated by either A, B,
OR conditions). C or D below: --4
2. Indication of leaking OR
RCS safety or relief 4. Containment High Range A. 1000 mrem/hr
zy
valve which causes Radiation Monitors (total dose rate)
RCS pressure to drop indicate
below setpoints: 7.3 X 10' R/hr (If B. 1000 mrem
Unit 1 - 1600 psia CHRRM inoperable, (total dose - TEDE)
Unit 2- 1736 psia Post-LOCA monitors
indicate between C. 5000 mrem/hr
100 and 1000 mR/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
( (
"-n m_0
EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
m m
o
"0 W z
I.A. ABNORMAL Loss of 2 of the 3 fission "-v
PRIMARY product barriers with 6 z 0
0
LEAK RATE imminent loss of the third
(Page 2 of 2) (any two of the following
exist and the third is 0
imminent).
0
1. Fuel element failure m
m on
(confirmed DEQ 1-131 -1
activity greater than
275 pCi/mL). rn
AND C)
2. LOCA or Tube rupture on
unisolable steam z
C) "n 1
generator.
AND -o 0 --n
3. Containment Integrity -H
Breached. C) A) I-
0 Ph
(D
Co
N) 0 0 C Zz C
NOTE 0 -n K U
Also refer to Potential NJ m (fln
Core Melt Event/ WD.
Class 6.A. zI m
-I z
--- K
Z C)
x
r
m
1.A. ABNORMAL -r
PRIMARY
LEAK RATE o
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR -&
(
EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m
1.B. ABNORMAL RCS PRI/SEC Leakage Rapid gross failure of one Rapid gross failure of steam Loss of 2 of the 3 fission
PRIMARY TO steam generator tube generator tubes (GREATER product barriers with
0
SECONDARY 1. Measured RCS to (WITHIN charging pump THAN charging pump imminent loss of the third
LEAK RATE secondary leakage capacity) with loss of offsite capacity) with a loss of (any two of the following
(Page 1 of 2) exceeds Tech. Spec. power offsite power exist and the third is
limits. imminent).
"-V
AND 1. Measured RCS to 1. Measured RCS to
2. Secondary plant activity secondary leakage secondary leakage is 1. Fuel element failure 0
is detected. greater than Tech. Spec. greater than charging (confirmed DEC 1-131 m m
to
Limits and within pump capacity. activity greater than m H
C
charging pump capacity. AND 275 jCi/mL). X
AND 2. Secondary plant activity AND
m
z m
2. Secondary plant activity is detected. 2. LOCA or Tube rupture rn
M
is detected. AND on unisolable steam
AND 3. Loss of both Non-Vital generator.
3. Loss of both Non-Vital
4.16 KV buses.
4.16 KV buses. AND
3. Containment integrity
I -n C10
7-f
breached.
(continued on next page) 0 r
(continued on next page)
C
M
NOTE
Also refer to Potential
-4 K
"rn
0
Core Melt Eventf
Class 6.A.
r'
cn z
z
1.8. ABNORMAL
PRIMARY TO
SECONDARY
LEAK RATE
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
( K
-v ;it
m
0
EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0
m m
z
0
l.B. ABNORMAL Rapid failure of steam §, Rapid failure of steam C
w z
PRIMARY TO generator tubes (GREATER qenerator tube(s) (GREATER m 0
SECONDARY THAN charging pump THAN charging pump 0 z
0
LEAK RATE capacityl capacity) with steam release
(Page 2 of 2) in progress
1. Measured RCS to
secondary leakage 1. Measured RCS to
greater than charging secondary leakage "0C)
pump capacity. greater than charging m
AND pump capacity. CoC
2. Secondary plant activity AND ;a Co*
Cnm
is detected. 2. Secondary plant activity G)
is detected.
AND z:)
3. Secondary steam release -n,-I
in progress from affected
C) -I
generator (i.e., ADVs, C,,
stuck steam safety(s) or C 0
(D
unisolable leak.)
0 z
0
C)
N) 0
znzi 0
-n
0
m
-- 0
-I
z
r 0
r'm
Co
lB. ABNORMAL
0
PRIMARY TO
SECONDARY 0
-
LEAK RATE Cr
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 0
C,)
(
-V
m
0
EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
m m
0z
1.C. LOSS OF Rapid depressurization of Major steam leak with Maior steam leak with A release has occurred or is in
SECONDARY secondary plant GREATER THAN 10 qpm GREATER THAN 50 qpm progress resulting in:
W z
o z 0
COOLANT primary/secondary leakage primary/secondary leakage
.0
(Page 1 of 2) 1. Rapid drop in either and fuel damage indicated 1. Containment High Range
steam generator 1. Rapid drop in either Radiation monitor greater
pressure to less than steam generator 1. Rapid drop in either than 1.46 X 10' R/hr (If -o
600 psia. pressure to less than steam generator pressure CHRRM inoperable, Post
600 psia. to less than 600 psia. LOCA monitors greater than 0
AND AND 1000 mR/hr). m
0
2. Known pri/sec leak of 2. Known pri/sec leak of OR Cm
greater than 10 gpm. greater than 50 gpm. 2. Performance of EPIP-09
AND AND (Off-site Dose Calculations) Co.
3. Secondary plant activity 3. Secondary plant activity is or measured dose rates from
is detected. detected. off-site surveys indicate site
AND boundary (1 mile) exposure
4. Fuel element damage is levels have been exceeded
Total loss of feedwater indicated (Refer to Fuel as indicated by either A, B, C
(D 4 -- i
Element Failure or D below: 0)
1. No main or auxiliary Event/Class 4.A). r-
feedwater flow available A. 1000 mrem/hr
(0 H
5
for greater than (total dose rate) K
C -n
15 minutes when TLOF with once-through 0 z 5- 0
required for heat cooling initiated B. 1000 mrem
removal. (total dose - TEDE) W
AND 1. No main or auxiliary m
2. Steam Generator levels feedwater flow available. C. 5000 mrem/hr
are less than 40% wide AND (thyroid dose rate)
range. 2. PORV(s) have been
opened to facilitate core 0. 5000 mrem z
heat removal. (thyroid dose-CDE) m
ci
(continued on next page)
1C. LOSS OF -U
SECONDARY 0
-
COOLANT
0)
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR C
-4,
(
-r
21 m
0
EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m 0
m 5
1.C. LOSS OF Loss of 2 of the 3 fission -v z
W z
SECONDARY product barriers with -0 0
COOLANT imminent loss of the third z
0
(Page 2 of 2) (any two of the following
exist and the third is
imminent).
1. Fuel element failure "0to
(confirmed DEQ 1-131 m C)
m
activity greater than K
275 pCi/mL).
AND Cn7
2. LOCA or Tube rupture m >o J
C
on unisolable steam z
generator.
AND
3. Containment Integrity
Breached. -
C) Co
(0 0 0
NOTE ClD C) z
Also refer to Potential6.A.
Melt Event/Class
Core 0) -n M U
n-I
m
5 -4
m
-4 0
m
z
w1 C)
(1)
1.C. LOSS OF -4
SECONDARY 0
COOLANT
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
'U m
xi
C
EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0
- xi
m
-u m 0
2.A. UNCONTROLLED Radiological effluent A release has occurred or §2 A release has occurred or is in A release has occurred or is in 2
m 5
EFFLUENT limits exceeded is in progress that is progress resulting in: progress resulting in:
,-U 0f
0
RELEASE 10 times the effluent limit 0 C F0
to
1. Plant effluent I. Containment High Range 1. Containment High Range W
monitor(s) 1. Plant effluent Radiation Monitor greater Radiation monitor greater than 2
exceed alarm monitor(s) significantly than 7.3 X 10' R/hr 1.46 X 10' R/hr (If CHRRM
setpoint(s). exceed alarm (Post-LOCA monitors inoperable, Post-LOCA monitors
AND setpoints. indicate between 100 and greater than 1000 mR/hr).
2. Confirmed AND 1000 mR/hr, if CHRRM OR m m
0
analysis results 2. Confirmed analysis inoperable). 2. Performance of EPIP-09 (Off-site
results for gaseous or OR Dose Calculations) or measured m C
for gaseous or on
liquid release liquid release which 2. Measured Dose Rates or dose rates from off-site surveys
which exceeds exceeds 10 times Offsite Dose Calculation indicate site boundary (1 mile)
ODCM limits. ODCM limits. (EPIP-09) worksheet values exposure levels have been to
z mm
at one mile in excess of: exceeded as indicated by either
NOTE A, B, C or D below:
NOTE A. 50 mrem/hr (total dose -I -n
If analysis is not Ifanalysis is not -I
available within rate) or 250 mrem/hr A. 1000 mrem/hr
available within one (thyroid dose rate) for (total dose rate) CD
one hour and it is Fn 0
hour and it is expected 1/2 hour. -4
expected that "-4
that release is equal to OR B. 1000 mrem z
release is greater 0 C)
than ODCM limit,
or greater than 10 times B. 500 mrem/hr (total dose (total dose - TEDE) -n r 0
ODCM limit, classify as rate) or 2500 mrem/hr N) -I I-4
za -n
classify as 0
ALERT.
UNUSUAL EVENT. (thyroid dose rate) for
two minutes at one
C. 5000 mremlhr
(thyroid dose rate) U) z7
mile.
D. 5000 mrem m
(thyroid dose-CDE) O
-Il
Co
79
ODCM - refeus to Chemoisty Procedure C-200 Oftscte Dose Calculation Manual (0DCM)
2.A. UNCONTROLLED 'V
0
EFFLUENT m*
RELEASE
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 0
-4,
(
0 m
EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m m
m 0
z
2.8. HIGH RADIATION High radiation levels or high W z
LEVELS IN PLANT airborne contamination which
o z 0
indicates a severe degradation .0
in the control of radioactive
materials
1. Any valid area monitor ~0
alarm from indeterminable 0
C)
source with meter near or I'ii m
m c
greater than full scale
deflection (10' mRlhr).
OR Q
2. Unexpected plant iodine or m
particulate airborne z
concentration of 1000 DAC
as seen in routine surveying
or sampling. -I Cf)
CD 6'1 r
OR (a
CO)
3. Unexpected direct radiation 00
CO
C 0
dose rate reading or
0 z
unexpected airborne 0
radioactivity concentration
-n m m .--i 0
z m
from an indeterminable 0
source in excess of
1000 times normal levels.
m
0 K
z m
i
z
rl
U')
2.B. HIGH RADIATION
LEVELS IN PLANT
Co
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 0.
(
0J
m
0
EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY k)
m m 0)
-a 0 z
3. FIRE §2 Uncontrolled fire within the Uncontrolled fire §2 Fire compromising the NOTE
C Wo 0z
Power Block lasting more function of safety systems ,0 m
m
Refer to Potential Core Melt
than 10 minutes. 1. Potentially affecting (e.g., both trains rendered
Event/Class 6.A. 0z
safety systems. inoperable).
AND
2. Requiring off-site
0
support in the opinion of
the NPSIEC. C)
m 0
m
§2 NOTE m
Explosion is defined as a rapid chemical reaction resulting in noise, heat and rapid C,
expansion of gas. G)
m
-I,
z 0
EXPLOSION Occurrence of an §2 Damage to §2 Severe damage to safe
C, C
explosion within the structures/components in shutdown equipment from 0) K
Owner Controlled Area. the Protected Area by explosion (e.g., both trains c
explosion which affects
plant operation.
rendered inoperable. (D
(0
C0 0 r mm
ccq -Il
-n m 0
- 5
m
z
z m
--4
m
co z
r
m C/)
3. FIRE G)
Fr
N)
0
EXPLOSION 0
-4'
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR c-c
-k
(
T
m
&0
EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Co
m or
C)
4.A. FUEL Fuel element damage Fuel element failure Fuel element failure with A release has occurred or is in m
7* z
"0 Cl
z Wi z
ELEMENT inadequate core cooling progress resulting in: 0 0
FAILURE 1. Process monitors or 1. Process monitors or
area radiation surveys area radiation surveys 1. RCS DEC 1-131 activity 1. Containment High Range
indicate increased indicate increased greater than or equal to Radiation monitor greater than
letdown activity letdown activity and 275 pCi/mL. 1.46 X 10' f/hr (If CHRRM
>
AND confirmed RCS Samples AND inoperable, Post-LOCA
2. Confirmed RCS sample indicating DEC 1-131 2. Highest CET per core monitors greater than 01
indicating: activity greater than or quadrant indicates greater 1000 mR/hr). rrl n
C
equal to 275 pCi/mL. than 1O0F superheat or OR
A. Coolant activity 700-F, 2. Performance of EPIP-09
greater than the (Off-site Dose Calculations) or cnn
measured dose rates from ;0 m
Tech Spec limit for
iodine spike (Tech off-site surveys indicate site z
Spec Figure 3.4-1.). boundary (1 mile) exposure "~11
OR NOTE
levels have been exceeded as
B. Coolant activity If analysis is not available
indicated by either A. B, C or ,n
U)
greater than D below: U) -H
within one hour and it is CD r
100/t pCi/gram expected that RCS activity C 0
specific activity. for DEQ 1-131 is greater
A. 1000 mrem/hr 0 _o z
than 275 pCi/mL, classify (total dose rate) 0 mT
0 0
as an ALERT. N) CA IM "r3 -n
B. 1000 mrem 0ý
(total dose - TEDE)
m
NOTE
If analysis is not available z m
within one hour and it is C. 5000 mrem/hr
Mi
expected that activity is (thyroid dose rate)
greater than Tech Spec
limit, classify as D. 5000 mrem z
(thyroid dose - CDE) 0
UNUSUAL EVENT.
M)
4.A FUEL
ELEMENT
FAILURE
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR N)
0
Ci)
(
- 0
nl m
EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0
m m
-0 z
4.B. FUEL HANDLING Fuel handling accident which §2 Major damage to irradiated C
w3 z
ACCIDENT results in the release of fuel in Containment or Fuel -0
radioactivity to Containment or Handling Building zC
Fuel Handling Building:
1. Affected area radiation
o
1. NPS/EC determines that an monitor greater than
irradiated fuel assembly may 1000 mrem/hr.
have been damaged. AND 0
AND 2. Damage to more than m m
2. Associated area or process one irradiated fuel M
radiation monitors are in assembly. m
DR
C) > -.
alarm. X
Major damage resulting
from uncovering of one "Cn
or more irradiated fuel
assemblies in the Spent
Fuel Pool. ED C/)
(0
C0 0
C: 0
(Al z
1 "(Al C0
m Z
0
N) z -I,
K
0 rn
z
-4i
z
'I 0
C0
43. FUEL HANDLING
ACCIDENT
N)
AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
-S
Cs)
-p
m _<
EVENT/CLASS UNUSUAL EVENT ALERT 0
SITE AREA EMERGENCY GENERAL EMERGENCY 0 (A
m
5.A. EARTHQUAKE §2 A confirmed earthquake §2 A confirmed earthquake has occurred. §2 A confirmed earthquake has occurred. -0
m 0z
has occurred NOTE -U Wa z
1. A confirmed earthquake has 1. A confirmed earthquake has Refer to Potential Core 0) z 0
1. A confirmed occurred which registered occurred which registered Melt Event/Class 6.A. 0
earthquake has been GREATER THAN 0.05g within the GREATER THAN G.ig within the
experienced within the Owner Controlled Area Owner Controlled Area and the
Owner Controlled OR plant not in Cold Shutdown. 0p
Area. 2 A confirmed earthquake has OR
OR occurred that could or has caused 2. A confirmed earthquake has 0
2. ¶, An earthquake is trip of the turbine generator or occurred that has caused loss of m
0
detected by plant
seismic monitor
reactor any safety system function (e.g., ;0
C
both trains inoperable).
instruments or other G)
m -j
means.
Z wm
0 -(n
5B. HURRICANE Hurricane Waming Hurricane warnino with winds near Hurricane warninq with winds
design basis GREATER THAN desiqn basis
NOTE 0 5
Refer to Potential Core W
Melt Event/Class 6 A H
"z 0
1. Confirmed hurricane 1. Confirmed hurricane warning is in 1. Plant not at cold shutdown. M C
warning is in effect. effect and winds are expected to AND -tO C-t
z
0 C F-)
exceed 175 mph within the Owner 2. Confirmed hurricane warning is in 0 "-n 0
Controlled Area. effect and winds are expected to 0 -0
exceed 194 mph within the Owner m
Controlled Area,
0 z m
NOTE NOTE
z H-
At FPL s request, NOAA will provide At FPLs request. NOAA will provide
an accurate projection of wind speeds an accurate projection of wind -4
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 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 z0
hurricane force winds. If that onset of hurricane force winds. If r C)
projection is not available within that projection is not available within m
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, 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, c,,
classify the event using current track classify the event using current track
and wind speeds to project onsite and wind speeds to project onsite
conditions. For example, projected conditions. For example, projected
onsite wind speed would be less than onsite wind speed would be less than
maximum hurricane wind speed if the maximum hurricane wind speed if the
track is away from PSL. track is away from PSL. "-V
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5A. EARTHQUAKE M3
5.B. HURRICANE Oa.
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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 GENERAL EMERGENCY 0
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5.C. TORNADO Notification of a tornado Any tornado striking the Power C z
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5.D. ABNORMAL Abnormal water level Flood, low water. hurricane suroe or Flood. low water, hurricane suroe or m
WATER LEVEL conditions are expected other abnormal water level other abnormal water level "cn
or occurring conditions conditions causing failure of vital
equipment "-u U)
1. Low intake canal 1. The storm drain capacity is (.C
level of -10.5 ft. exceeded during hurricane surge 1. Flood/surge water level reaching CD
MLW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or or known flood conditions. elevation +19.5 ft. (turbine M C:
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more. OR building/RAB ground floor). co C, 0 z
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2. Visual sightings by 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 2. Low intake canal level has IN) -n
station personnel emergency barrier valves open. caused the loss of all ICW flow. 0
that water levels are z m
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5.C. TORNADO
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5.D. ABNORMAL
WATER LEVEL I* m
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Activation of the Emergency Response Facilities does not require declaration of an emergency or entry into a specific emergency classification. z
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EMERGENCY GENERAL EMERGENCY z
EVENTICLASS UNUSUAL EVENT ALERT 0
5.A. INCREASED Emergency Coordinator's §2 Emergency Coordinator's §Ž Emergency Coordinator's Emeroencv Coordinator's iudoement that
AWARENESS judgement that plant judgement that plant judgement that plant plant conditions exist that make release or
OR conditions exist which conditions exist which conditions exist which are laroe amounts of radioactivity in a short
POTENTIAL warrant increased have a potential to significantly degrading in period appear possible or likely. (Any core -v
0
CORE MELT awareness on the part of degrade the level of safety an uncontrollable manner. melt situation) m
m
(Page 1 of 2) the operating staff andfor at the plant.
local authorities. 1. LOCA with failure of ECCS leading to C
severe core degradation or melt.
1. The plant is shutdown OR
under abnormal 2. LOCA with initially successful ECCS and ~,m
conditions (e.g.. subsequent failure of containment heat z ýn
exceeding cooldown 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 />. "11
rates or primary OR "'ll
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system pipe cracks are
found during
3. Total loss of feedwater followed by failure
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4. Failure of off-site and on-site power along CD
2. Any plant shutdown
required by Technical
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Specifications in which
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 />.
N)O M
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the required shutdown OR 5 m
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6. Any major internal or external event (e p., z
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opinion has or could cause massive
damage to plant systems resulting in any
of the above.
(continued on next page)
SA. INCREASED
AWARENESS
POTENTIAL
(;I
CORE MELT 0.9
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(
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EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m m Co
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6.A. INCREASED m W z
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AWARENESS 1. Most likely containment failure 0
z 0
OR POTENTIAL mode is melt-through with 0
CORE MELT release of gases only. Quicker
(Page 2 of 2) releases are expected for failure
of containment isolation system.
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2. General Emergency must be 0
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AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR --4
0oA
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EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m m 0
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7A. LOSS OF Loss of off-site power or §2 Station Blackout (Total Loss §2 Station Blackout (Total Loss NOTE C
W0 Z
POWER loss of all on-site AC power of AC) of AC) for GREATER THAN Refer to Potential Core -o m 0
capability. 15 minutes Melt Event/Class .A. z
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1. Loss of off-site
1. Loss of off-site AC AC power. I. Loss of offsite AC power.
power. AND AND
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2. Loss of capability to emergency diesel emergency diesel 0
power at least one vital generators to start or generators to start or m 0m
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4.16 kv bus from any load. load.
available emergency AND U)
diesel generator. 3. Failure to restore o.
Loss of all on-site DC AC power to at least one
power vital 4.16 kv bus within z
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7.A. LOSS OF
POWER -4
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AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
(
"13
m
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EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0
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&A. LOSS OF PLANT Loss of Plant Control Critical Loss of Plant Control M
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CONTROL Functions Functions
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FUNCTIONS
05 0
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1. Complete loss of any 1. Loss of any function or 0
function needed for plant system which, in the
cold shutdown. opinion of the Emergency
OR Coordinator, precludes
2 Failure of the Reactor placing the plant in Hot 0
Protection System to Shutdown. to
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bring the reactor OR C
subcritical when needed. 2. Failure of the RPS to trip
OR the reactor when needed ro
3. Control Room is and operator actions fail to
evacuated (for other than bring the reactor C )r
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established locally at the OR -n
Hot Shutdown Control 3. Control Room is evacuated U)
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Loss of Shutdown Cooling locally at the Hot Shutdown C
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1 Complete loss of
Control Panel within
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A. Failure of shutdown H-
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B. RCS subcooling can 0')
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greater than 0°F.
8.A. LOSS OF PLANT -U
CONTROL
0
FUNCTIONS
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AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR 0
C))
(
EVENTICLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
8B. LOSS OF ALARMS / §2 Significant loss of effluent §2 Loss of alarms Loss of alarms/monitoring
COMMUNICATION / monitoring capability,
MONITORING communications, indication 1. Unplanned loss of 1. Inability to monitor* a
and alarm panels. etc.. which most (greater than significant transient in
impairs ability to perform 75%) or all safety progress.
accident or emergency system annunciators.
assessment. AND
2. Plant transient in 0
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1. Loss of effluent or progress. m m
radiological monitoring m
capability requiring plant m
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2. Loss of all primary and Iz
backup communication
capability with offsite -1
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3. Unplanned loss of most o0 C
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annunciators for greater
than 15 minutes.
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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
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CA
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EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY 0"m3
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9.A. AIRCRAFT/ Unusual aircraft activity §2 Aircraft/missile impact §2 Damage to vital systems m
0
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MISSILE from aircraftlmissiles 0 C
1. Aircraft crash in the 1. Aircraft crash into the
Owner Controlled Area Power Block. 1. Aircraft crash into the
or unusual aircraft OR Power Block damaging
activity over facility that 2. Visual or audible vital plant systems.
in the opinion of the indication of missile OR 0
NPS/EC, could impact on the Power 2. Damage resulting in loss
threaten the safety of Block. of sale shutdown
a1, C
the plant or personnel. equipment from any 9,;
missilpe.
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9.B. TURBINE Turbine rotating Visual indication that the z
FAILURE component failure causing turbine casing has been
rapid plant shutdown. penetrated by blading. 04
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9.C. TOXIC OR Unpla nnedluncontrolled Entry of toxic or flammable
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FLAMMABLE toxic or flammable gas gas into areas potentially diffused into vital areas H>
GAS release in the Owner affecting plant operation. compromising the function
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Controlled Area that could of safety related equipment z
affect plant/personnel (e.g., both trains rendered
safety. inoperable).
C)
9.A. AIRCRAFT /
MISSILE
9.B. TURBINE
FAILURE
9.C. TOXIC OR m.
FLAMMABLE 0 0
GAS
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(
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EVENT/CLASS UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY m
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10. SECURITY A SECURITY ALERT has A SECURITY A SECURITY EMERGENCY A successful takeover of the z
THREAT been called by the Security EMERGENCY has been involving imminent plant including the Control ,5 W.) z
z0 0
Force in response to one called by the Security occupancy of the control Room or any other area(s)
or more of the items listed Force as defined in the room or other area(s) vital vital to the operation of the
below. Safeguards Contingency to the operation of the reactor (as per the Security
Plan. reactor as defined in the Plan).
1. Bomb threat Safeguards Contingency "0
2. Attack threat Plan. 0ro
3. Civil disturbance m
4. Protected area
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6. Internal disturbance
7. Vital area intrusion z r
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AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR
0
-4
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
L
H
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
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 = ft
Cavity level - 36 = adjusted level.
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.
x 1.35 = min
11 Time to boil from curve or x 1.35 = corrected time to boil
corrected time to boil from 1.C
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)
0
CD
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