ML021340592
| ML021340592 | |
| 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: ML021340592 (9) | |
See also: IR 05000389/2002301
Text
ST. LUCIE EXAM 2002-301
50-335 AND 50-389/2002-301
APRIL 22, 2002
FINAL Submittal
SRO Written Exam Outlines
Facility: St. Lucie (02-301)
Date of Exam: 4/22/02
Exam Level: SRO
K/A Category Points
Tier
Group
Point
K
K
KI K
K
K
A
A
A
A
G
Total
1
2
3
4
5
6
1
2
3j4
1
4
2
1
,
, , * ' 4
2 4
Emergency
& Abnormal
2
2
2
2
4______
2
16
Plant
v._
_
_
_ _
_ _
_
Evolutions
31
1
3
Tier
43
Tir 6
5
8
8
9
- ,
7
Totals
1
3
2
2
2
1
1
2
2
2
1
1
19
2.
Plant
2
2
3
2
2
1
1
1
2
2
1
17
Systems
3
1
1
1
1
4
Tier
6
2
5
5
3
3
3
4
4
3
2
40
Totals
3. Generic Knowledge and Abilities
Cat 1
Cat 2
Cat 3
Cat 4
17
4
4
4
5
Note:
1.
Ensure that at least two topics from every K/A category are sampled within each
tier (i.e., the "Tier Totals" in each K/A category shall not be less than two).
2.
The point total for each group and tier in the proposed outline must match that
specified in the table. The final point total for each group and tier may deviate +/-1
from that specified in the table based on NRC revisions. The final exam must total
100 points.
3.
Select topics from many systems; avoid selecting more than two or three K/A
topics from a given system unless they relate to plant-specific priorities.
4.
Systems/evolutions within each group are identified on the associated outline.
5.
The shaded areas are not applicable to the category/tier.
6.*
The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A
Catalog, but the topics must be relevant to the applicable evolution or system.
7.
On the following pages, enter the K/A numbers, a brief description of each topic,
the topics' importance ratings for the RO license level, and the point totals for
each system and category. K/As below 2.5 should be justified on the basis of
plant-specific priorities. Enter the tier totals for each category in the table above.
I
ES-401 St. Lucie (02-301) Date of Exam: 4/22/02
Form ES-401-3
Emergencv and Abnormal Plant Evolutions - Tier 1/Group 1
E/APE # / Name / Safety Function
K
K
K
A
A
G
K/A Topic(s)
Imp.
Exam
1
2
3
1
2
Akl.17 Knowledge ot operational implications eo M I u
SHU
000001 Continuous Rod Withdrawal/I
X
13.7
AK3.0 Knowledge o0 the reason for the Followng as they apply to the
-SRO
000003 Dropped Control Rod / I
Xdropped
CEA: Reset of demand position counter to zero.
3.0
000005 Inoperable/Stuck Control Rod /I
X
2.2.22 kn1
.K2.02 Knowledge of interrelations between pumps and large break
4.1
000011 Large Break LOCA/ III
X
LOCA's
2.7
AA2.10 Ability to determine when to secure RCP's on loss of cooling or
000015/17 RCP Malunctions/IV
X
seal injection.
3.7
AK2.2 Knowledge of interrelations between NC and heat removal
R
CE/Al 3 Natural Circ. / IV
X
systems and relations between the proper operation of these systems.
3.6
AKI.02 Knowledge ot operational implications ot emergency boration and
000024 Emergency Boration / I
X
relationship between boron addition and reactor power.
3.9
AK3.02 KnowledCoe ot the reasons Tor the automatic actions (aignment)
000026 Loss of Component Cooling Water / V111
X
X
within the CCWSNresulting from actuation of ESFAS.
3.9
G2.1.33 Tech Spec entrvlevel conditions
4.0
LK2.UO Knowledge Or interrelations between breakers relays and
R
000029 Anticipated Transient w/o Scram / I
X
disconnects following an ATWAS
3.1
EA0 .3 Ability to operate and/or monitor desired operating results dunng
000040 (CEJEO5) Steam Line Rupture- Excessive
X
X
abnormal and emergency situations.
4.0
Heat Transfer / IV
EA2.1 Ability to determine and interpret facility conditions and selection of
4.0
appropriate procedures dudng abnormal and emergency operations.
AK 1.2 Kno wledge of operational implications of normal, abnormal and
CE/All RCGS Overooting.- PTS / IV
X
EOP's associated with RCS overcooling.
3.3
AA2.02 Ability to determine and interpret conditions requiring
-
000051 Loss of Condenser Vacuum / IV
X
reactor/turbine trip on loss of condenser vacuum.
4.1
EK1.02 Knowledge ot operational implications of natural circulation
000055 Station Blackout! VI
X
X
coolin as they apply to station blackout.
4.4
EA1 .06 Ability to operate and monitor restoration of power with one EDG
4.5
000057 Loss of Vital AC Elec. Inst. Bus / VI
X
AA1.05 Ability to operate and/or monitor backup inst. Indications
3.4
000059 Accidental Liquid Release
G2.3.10 Ability to perform procedures to reduce levels of radiation and
3.3
guard against personnel exposure.
AK3.02 Knowledge of the reasons for automatic actions (alignments)
SR
000062 Loss of Nuclear Service Water/ IV
X
within the nuclear service water resulting from actuation ot the ESFAS
Q2.4.26 Knowled e of facilityprotection requirements including tire
3SRO
000067 Plant Fire On-site / IX
X
brigade and portable fire fighting equipment usage.
AK3.13 Knowledge of the reasons for periormmng a SDM calculation,
-SRO
000068 (BW/A06) Control Room Evac. / VIII
X
including boron needed and boration time.
000069 (W/E1 4) Loss of CTMT Integrity / V
X
AA2.01 Ability to determine and interpret loss of containment integnty.
4.3
-SR
EA1.05 Ability to operate and monitor PORV as applied to inadequate
1
S
000074 (W/E06&E07) Inad. Core Cooling / IV
X
core cooling.
AA2..02 Ability to determine and interpret correct actions required for high
3.4n
SR
000076 High Reactor Coolant Activity / IX
X
fission product activity in RCS
K/A Category Totals:
4
2 I5
4
5
4
Group Point Total:
24
2
ES-401 St. Lucie (02-301) Date of Exam: 4/22/02
Form ES-401-3
Emeroency and Abnormal Plant Evolutions - Tier 1/Group 2
E/APE # / Name / Safety Function
K1
K2
K
A
A
G
K/A Topic(s)
Imp.
Exam
3
1
2
LK1.2 Knowledge ot normal, abnormal and
-
Ln 'sUP
ýs
000007 CE/E02 Reactor Trip - Stabilization - Recovery /
x
associated with reactor trip recovery.
3.4
AK1.01 Knowledge ot operational implications ot
000008 Pressurizer Vapor Space Accident / Ill
X
thermodynamics and flow characteristics of open or
3.7
leaking valves
K3.10 KnOwled e Ot me reasons for PLH level as applied
3.6
000009 Small Break LOCA /III
X
to small break
A
3.6
AA1 .01 ADility to operatelmonitor Uvu letdown and
oZR7
000022 Loss of Reactor Coolant Makeup / II
X
charging as applied to loss of reactor coolant makeup
3.3
AK2.03 Knowledge ot interrelations between lOSS ot HHH
2T7
SRY
000025 Loss of RHR System / IV
X
X
and service water or closed cooling water pumps.
G2.2.3 Knowledge of design, procedural and operational
3.3
differences between units
AA2.1 0 Ability to determine and nterpret PLH heater
3W
000027 Pressurizer Pressure Control System Malfunction / III
X
energized/de-energized condition.
0e2.1.27 Knowledge of system purpose and or function
.W9
0 LVNot
chosen due to PSL does not have intermediate range
N/A
N/A
000033 Loss of Intermediate Range NI /VII
NI's.
AA2.1* b*1bii[to determine and interpret pressure at which
n::RTO
000037 Steam Generator Tube Leak / Ill
X
to maintain
dUS
durng Sb
cooldown.
4.3
LK2.02 Knowled e ot me interrelations between sensors
000038 Steam Generator Tube Rupture / III
X
and detectors ang a SGTR
2.5
AA1 .02 ADIlitV to operate ano/or monitor manual startup ot fRO
000054 (CE/E06) Loss of Main Feedwater/ IV
x
electric and steam driven AFW pumps as applied to loss
4.4
000054 (CEIE06) Loss of Main Feedwaller_____of
main feedwater.
SAl1.01 Ability to ooerate and/or monitor cross-bie of
3.
000058 Loss of DC Power / VI
X
affected dc bus with the alternate supply.
AA2.Ub Ability tO determine and interpret that automatic
47
000060 Accidental Gaseous Radwaste Rel. / IX
x
safety actions have occurred as a result of high ARM
AK3.02 Knowledee ot reason or guidance contained in
-3.9-
S
000061 ARM System Alarms / VII
X
alarm response Por ARM system
AA2.06 Ability to determine when to trip reactor it
4.2
S-O
000065 Loss of Instrument Air / VIii
X
instrument air pressure is decreasing.
EMA1.3 Ability o operate and/or monitor desired operating
3.TW
CE/E09 Functional Recovery
x
results during abnormal and emergency situations.
K/A Category Point Totals:
12
2
1 2
44 J 2
Group Point Total:
116
3
K-A Topic(s)
4
ES-401 St. Lucie (02-301) Date of Exam: 4/22/02
Form ES-401-3
Plant Systems - Tier 2/Group 1
System # / Name
K
K
K
K
K
K
A
A
A
A
G
K/A Topic(s)
Imp.
Exam
__
_
_
_
_
_
_
_
_
_
1
2
3
4
5
6
1
2
3
4
1
00 CntolRo Div
XK1
.05 Knoweg of phyia cnnections and/or
M
001 Control Rod Drive
X
cause effect relationship between CADS and NIS
4.4
and RPS.
003 Rector oolan PumpA2.01
Abiliy to predict the' imacts of problems with
1W
_
-Mr
003 Reactor Coolant Pump
X
RCP seals, especially rates of seal leak-off and use
procedures to correct, control or mitigate.
004 hemcal nd olum CotrolX
K.05 Knowledge Of bus power supplies to MO Vs.
2.9
0 04 CE mg
i cale and V olt F aum
e s Acn atrol
X-
K ilS K no wle
dge o f physical connectio n s and /o r
~ T
~U
013 Engineered Safety Features Actuation
X
cause effect relationship between ESFAS and MFW
system.
Al1O
Ablto predc and/rm
mnitor changes in
3.
014 Rod Position Indication
X
parameters (to prevent exceed in design
A1.03~~~~~
~~~
Abiit
limeic
n/o
o
ito
thags)n
38
associated with RPIS and PDIL, PPDIL
-
K4.07 Kniowledge of NIS design features andl/or
3.F
015 Nuclear Instrumentation
x
X
interlocks for ermissives
A4.03 Ability to manually operate and/or monitor in
3.9
the control room tip bypasses.
A2.02 Ability to predict the impact of core damage
017Incor TmpratreMonto
Xon
ITM, use procedures to Correct, control or,
4.1
mitigate the consequences of those malfunctions or
K22 Knowledge of t
eerations
hat a loss or
022 Containment Cooling
X
X
malfunction willmave on containment
instrumentation readings.
A3.01 Ability to monitor automatic operation of the
4.3
CCS including initiation of safeguards mode of ons.
K4.07 Knowledge of CSS design eatures and/or
4.1
fRl
028ConainentSpry
Xinterlock
wich provid adequale level in
I---containment
sump for suction (interlock)
056 Condensate -X
parameters associated with MFW suction pressure.
K6.12 Knowled e of the effect of a loss or
Valve will have on the MFW components.
_RZT~nw
ont r Upoller sploic s
for MFW
reg
2.
061 Auxiliary/Em nergency Feedwater
X
s ystem
's
06 uxlay/
mrenyFed
aerXX
K2.01 Knowledge of bus power supplies to A F-W
f.l:R
(32A.1T1 Knowledge of abnormal condition
3.6
----
---
procedures.
KI.02 Knowledge of the effect that a loss or
3.7
063 DC Electrical Distribution
X
malfunction of the DC elec. System will have on
X
-components
using DC control Dower.
Ki Ul Knowledge of physical connections between
2
068 Liquid Radwaste
X
K5.04 Knowledge of the operational implications of
2T'
S
071 Waste Gas Disposal
X
the relationships of hydrogen/oxygen
concentrations to flammability.
AM~ Ability to monitor automatic opration of the
~
l
072 Area Radiation Monitorng
X
ARM system to changes in ventilation alignment
K/A Category Point Totals:
3
1 2
2
j 2
i1
1
2J1[1
2
2_
2
__
1
1
1 19
5
ES-401 St. Lucie (02-301)
Date of Exam: 4/22/02
Form ES-401-3
--
Plant Systems - Tier 2/Group 2
System # / Name
K
K
K
K
K
K
A
A
A
A
G
K/A Topic(s)
Imp.
Exam
1
2
3
4
5
6
1
2
3
4
1
A4.03 Ability to manually operate and/or monitor
002 Reactor Coolant
in the control room indications and controls
4.4
necessary to recognize and correct saturation
conditions
K1.04 Knowledge ot the physical connect ons g_
u
006 Emergency Core Cooling
and/or cause/efect relationship between ECMS
2.8
and Aux. Spray svstem.
A3.02 Abilit to monitor automatic operation ot
35
5
010 Pressurizer Pressure Control
X
the PZR PC S including PZR pressure.
K6.03 Knowledge of the effect of a loss or
bRO
011 Pressurizer Level Control
X
malfunction between PZR level and PZR heater
3.3
control circuit.
012 Reactor Protection
A1.01 Ability to predict and/or monitor changes in
3.4
E;HU
parameters associated with operating the PS
includinq trip setpoint adiustment.
02.4.21 Knowledga
of the parameters and logic
4.3
ST_
027 Containment Iodine Removal
used to assess the status of safety functions
including containment systems.
K5.03 Knowledge of the operational implications
3.6
STO
028 Hydrogen Recombiner and Purge Control
+
X
of sources of hydrogen within containment.
K4.03 Knowledge ot design features and/or
35
029 Containment Purge
interlocks which provide automatic purge
isolation
K4.01 Knowledge ot desi n features and/or
3.2
033 Spent Fuel Pool Cooling
interlocks which provide or maintenance of spent
- fuel pool level.
A45 e Ability to manually operate and/or monitor
4.0
S
035 Steam Generator
in the control room levelco ntrol to enhance
natural circulation.
K3.05 Knowledge that a loss or malfunction ot
J.7 I
039 Main and Reheat Steam
the MRSS will have on the RCS.
055 Condenser Air Removal
K3.02 Knowledge of loss or malfunction of A.C.
4.4
062 AC Electrical Distribution
X
distribution will rave on EDG.
K1S03 Knowledge of the physical connections
4.0
S70_
064 Emergency Diesel Generator
and/or cause-eftect relationship between the
EDG and the EDG fuel oil suply system.
K5.01 Knowledge of the operational implications
3.0
073 Process Radiation Monitoring
X
as they apply to concepts to the PRM related to
radiation theory, including sources, types, units
andeffects.
075 Circulating Water
A2.01 Ability to predict the impacts o0 cross
079 Station Air
X
connection with lAS. Use procedures to correct,
control or miti ate.
A.U1 AbilTY to monitor automatic operation of
3
086 Fire Protection
X
the FPS including starting mechanisms of fire
water pumps.
K3.03 Knowledge of the effect that a loss or
4.1
103 ContainmentX
malfunction of containment system will have on
L :zcontainment
integrity under refueling conditions.
K/A Category Point Totals:
[2
i3
1 2 1-2-17-1_1 112
21
17
6
7
ES-401 St. Lucie (02-301)
Date of Exam: 4/22/02
Form ES-401-3
Plant Systems - Tier 2/Group 3
System#/Name
K
K
K
K
K
K
A
A
A
A
G
K/ATopic(s)
Imp.
Exam
___
__ ___
__
___
__
1
2
3
4
5
6
1
2
3
4
_
_
_
_
_
_
_
_
_
_
_
A2.02 Ability to predict the impacts of pressure
X
transient protection during cold shutdown and
3.7
based on predictions correci, control or mitigate.
007 Pressurizer Relief/Quench Tank
K4.02 Knowledge Ot CWUS des gn feature ancior
008 Component Cooling Water
x
interlocks whichg provide for operation of the surge
2.7
tank, associated valves and controls.
K(6.03 Knowledge of the effect ot a loss or
041 Steam Dump/Turbine Bypass Control
malfunction ot controllers positioners including ICS,
2.9
- - -- S/G,
CRDSwllhave on theSDS.
045 Main Turbine Generator
076 Service Water
K1.05 Knowledge of thephysical connections
078 Instrument Air
X
and/or cause effect relationship between IAS and
3.5
IIMSIV air.
K/A Category Point Totals:
JT11
1 [
1 J
1
I 1= =)Group Point Total:
Genedc Knowled a and Abilities Outline (Tier 3)
Form ES-401-5
Facility: St. Lucie
(02-301)
Date of Exam: 4a2/02
Exam Level: SRO
Category
K/A #
Topic
Imp.
Exam
Knowledge of one hour technical specification action
2.1.11
statements for systems.
3.8
2.1.32
Ability to explain and apply all systems limits and precautions
3.8
Conduct of
Operations
2.1.22
Ability to determine Mode of Operation
3.3
2.1.29
Knowledge of how to conduct and verify valve lineups
3.3
Total
4
Knowledge of the design, procedural and operational
3.3
2.2.3
differences between units.
2.2.22
Knowledge of limiting conditions for operations and safety limits
4.1
Control
2.2.12
Knowledge of surveillance procedures
3.4
2.2.27
Knowledge of the refuel ng process
3.5
4
Total
2.3.10
Ability to perform procedures to reduce excessive levels of
radiation and guard against personnel exposure
3.3
2.3.9
Knowledge of the process for performing a containment purge
Radiation
3,4
_____
Control
2.3.11
Ability to control radiation releases
3.2
2.3.6
Knowledge of the requirements for reviewing and approving
3.1
release permits.
4
Total
2.4.7
Knowledge of event based EOP mitigation strategies
3.8
2.4.49
Ability to perform without reference actions that require
4.0
Emergency
-
immediate operation of system components and con roIs
Procedures
and Plan
2.4.12
Knowledge of abnormal condition procedures.
3.6
2.4.41
Knowledge of EAL thresholds and classifications
4.1
2.4.40
Knowledge of SRO's responsibilities in E-Plan implementation
4.0
Total
5
Tier 3 Target Point Total SRO
17