ML021340557
| ML021340557 | |
| 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: ML021340557 (9) | |
See also: IR 05000389/2002301
Text
ST. LUCIE EXAM 2002-301
50-335 & 50-389/2002-301
APRIL 22, 2002
Draft Submittal
Senior Reactor Operator Written Exam
Sample Outlines
Facility: St. Lucie (02-301)
Date of Exam: 4/22/02
Exam Level: SRO
K/A Category Points
Tier
Group
Point
K
K
K
K
A
A
ii
Total
1
4
5
6
1
2
3
4
1._
I1 4
425
24
Emergency
FP1R
i,
Abnormal
2
2
2
2
164
4
2
Plant
Evolutions
31
1
31
Tier
6
5
8
8
9
7
Totals
.
..
% ,...
I
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
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.
1
ES-401 St. Lucie (02-301)
Date of Exam: 4/22/02
Form ES-401-3
Emergency and Abnormal Plant Evolutions - Tier I/Group 1
E/APE # / Name / Safety Function
K
K
K
A
A
G
KIA Topic(s)
Imp.
Exam
1
2
3
1
2
1
_
Ak1 .11* Knowledge o01 operational implications 01 M I L
000001 Continuous Rod Withdrawal / I
X
3.7
AK3.0b Knowledge or the reason tor the tollowing as they apply to the
S9
000003 Dropped Control Rod / I
X
dropped CEA: Reset of demand position counter to zero.
3.0
02.2.22 Knowledge of LCO's and safety limits
000005 Inoperable/Stuck Control Rod /I
X
4.1
EK2.02 Knowledge of interrelations between pumps and large brreak
000011 Large Break LOCA / III
X
LOCA's
2.7
AA2.10 Ability to determine when to secure HCP's on loss ol cooling or
000015/17 RCP Malfunctions / IV
X
seal injection.
3.7
AK2.2 Knowledge of interrelations between NC and heat removal
CE/A13 Natural Circ. / IV
X
systems and reations between the proper operation of these systems.
3.6
AK1.02 Knowledge of operational implications of emergency boration and
000024 Emergency Boration / I
X
relationship between boron addition and reactor power.
3.9
AK3.02 Knowledge o1 the reasons tor the automatic actions (alignment)
000026 Loss of Component Cooling Water /Vil
X
X
within the CCWresulting from actuation of ESFAS.
3.9
G2.1.33 Tech Spec entrlevel conditions
4.0
-EK2.Ob Knowledge oT interrelations between breakers relays and
000029 Anticipated Transient w/o Scram / I
X
disconnects followng an ATWAS
3.1
EA1.3 Ability to operate and/or monitor desired operating results dunng
000040 (CE/E05) 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 during abnormal and emergency operations.
AK1.2 Knowledge 01 operational implications o normal, abnormal and
CE/Al1 RCS Overcooling - PTS / IV
X
EOP's associated with RCS overcooling.
3.3
AA2.
bility to determine and interpret conditions requiring
4.1
000051 Loss of Condenser Vacuum / IV
X
reactor/turbine trip on loss of condenser vacuum.
4.1
EK1.02 Knowledge o operational implications 01 natural circulation
000055 Station Blackout / VI
X
X
cooling as they app
to station blackout.
4.4
EA1 .08 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
X
G2.3.10 Ability to perform procedures to reduce levels of radiation and
3.3
guard against personnel exposure.
AKS.02 Knowledge of the reasons for automatic actions (alignments)
3
000062 Loss of Nuclear Service Water / IV
X
within the nuclear service water resulting from actuation of the ESFAS
62.4.26 Knowledge of tacility protection requirements including lire
13
000067 Plant Fire On-site / IX
X
brigade and portable fire fighting equipment usage.
AK3.13 Knowledge of the reasons for performing a SDM calculation,
3.9
SR
000068 (BW/A06) Control Room Evac. / VIII
X
including boron needed and boration time.
AA2.01 Ability to determine and interpret loss of containment integnty.
4.y
000069 (W/E1 4) LOSS of CTMT Integrity / V
X
_______________________________
LA 1.05 Ability to operate and monitor PORV as applied to inadequate
4.1
-9T
000074 (W/E06&E07) Inad. Core Cooling / IV
X
core cooling.
I
X
AA2.02 Ability to determine and interpret correct actions required for high
3
000076 High Reactor Coolant Activity / IX
X
fission product activity in RCS
K/A CategoryTotals:
4
2
15
4
5
4
Group Point Total:
24
2
St. Lucie (02-301) Date of Exam: 4/22/02
Form ES-401-3
Emergency and Abnormal Plant Evolutions - Tier I/Group 2
E/APE # / Name / Safety Function
K1
K<2 K
A
A
G
K/A Topic(s)
Imp.
Exam
3
1
2
_
_
_
_
_
_
_
_
_
_
_
_
_
2K12. Knowledge of normal, abnormal and LOP's
000007 CEIE02 Reactor Thip - Stabilization - Recovery /
X
associated with reactor trip recovery.
3.4
AKi.01 Knowledge o0 operational implications Ot
000008 Pressurizer Vapor Space Accident / III
X
thermodynamics and flow characteristics of open or
3.7
leaking valves
EK3.1'0 Knowledge of tme reasons for FZt level as applied
3.6
000009 Small Break LOCA / III
x
to small break LOCA.
3.6
AA1 .01 AbIlty to operate/monitor CVGb letdown and
000022 Loss of Reactor Coolant Makeup / It
charging as applied to loss of reactor coolant makeup
3.3
AK2.03 Knowledge or interrelations between loss or KHRH
2.7- /
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
AA2.10 Ability to determine and interpret PZH heater
3.
000027 Pressurizer Pressure Control System Malfunction / III
energized/de-energized condition.
032.1.27 Knowledge of system purpose and or function
.
UR
Not chosen due to PSL does not have intermediate range
N/A
N/A
000033 Loss of Intermediate Range NI /ViI
Ni's.
AA2.16 Abill to determine and interpret pressure at which
000037 Steam Generator Tube Leak / III
X
to maintain ROS during S/G cooldown.
4.3
LK2.02 Knowledgeot
othe interrelations between sensors
000038 Steam Generator Tube Rupture / III
x
and detectors an* a SGTR
2.5
AA1 .02 Ability to operate and/or monitor manual startup ot
000054 (CE/E06) Loss of Main Feedwater / IV
x
electric and steam drven AFW pumps as applied to loss
4.4
of main feedwater.
AA1.01 Ability to operate andor monitor cross-tieof
-3.-
-SO
000058 Loss of DC Power/ VI
X
affected dc bus with the alternate supply.
AA2.05 Ability to determine and interpret that automatic
4.2
SKU
000060 Accidental Gaseous Radwaste Rel. / IX
X
safety actions have occurred as a result of high ARM
_________________________________________________________systemn signal.
AKS.u2 Knowledgpe 0 reason lor guidance contained in
- WW1 5HU
000061 ARM System Alarms / VII
X
alarm response tor ARM system
AA2.06 Ability to determine when to trip reactor it
4
STMF
000065 Loss of Instrument Air / VIII
X
instrument air pressure is decreasing.
E 1.3 Ability to operate and/or monitor desired operating
3.U
CE/EQ9 Functional Recovery
X
results during abnormal and emergency situations.
K/A Category Point Totals:
12
j2
2
4 14 1 2
Group PointTotal:
16
3
St. Lucie (02-301) Date of Exam: 4/22102
Form ES-401-3
Emergency and Abnormal Plant Evolutions -Tier 1/Group 3
E/APE # / Name / Safety Function
K
K
K
A
A
G
K/A Topic(s)
Imp.
Exam
1
2
3
1
2
1
AK2.02 Knowledge ot interrelations between maltunctions of sensors and
2.7
000028 Pressurizer Level Malfunction / II
X
detectors and pressurizer level control.
000036 (6W/AM8) Fuel Handlingq Accident I VtII
AK3.02 Knowledge of the reasons for actions contained in ELOP for loss of
4.7-
ISrUF
000056 Loss of Off-site Power / VI
X
offsite power.
G2.4.4 Ability to recognize abnormal indications for system operating
CE/A16 Excess RCS Leakagqe / II
X
parameters which are entry level conditions for ONP's and EOP's
4
K/A Category Point Totals:
_
Itlt
11
Group Point Total:
3
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
0
K/A Topic(s)
Imp.
Exam
__
_ _
_
_
_
_
_
_
_
1
2
3
4
5
6
1
2
3
4
_
_
_
_
_
_
_
_
_
_
_
_
Ki.05 Knowledge of physical connections and/or
001 Control Rod Drive
X
cause effect relationship between CRDS and NIS
4.4
and RPS.
A2.01 Ability to predict the impacts of problems with
.
003 Reactor Coolant Pump
X
RCP seals, especially rates of seal leak-off and use
rocedures to correct, control or mitigate.
- 2.05 Knowledge of bus power supplies to MOJVs.
2.
R
004 C he m ical a nd V o lum e C o ntro l
X
!__ K n w le deO_____ p w er_ up plis_ to____ s__L
96
1-1
K1.15 Knowledge of physical connections and/or
3.sR
013 Engineered Safety Features Actuation
X
cause effect relationship between ESFAS and MFW
system.
A1.03 Ability to predict and/or monitor changes in
3.8
014 Rod Position Indication
x
parameters (to prevent exceedingdesign limits)
associated with RPIS and PDIL, PPDIL
K4.07 Knowledge of NIb design features and/or
3
015 Nuclear Instrumentation
XX
interlocks forpermissives
A4.03 Ability to manually operate and/or monitor in
3.9
the control room triD byasses.
A2.02 Ability to predict the impact of core damage
017 In-core Temperature Monitor
X
on ITM, use procedures to correct, control or
4.1
mitigate the consequences of those malfunctions or
operations
K3.02 Knowledge of the effect that a loss or
3.3
-SR
022 Containment Cooling
X
X
malfunction willhave on containment
instrumentation readings.
A3.01 Ability to monitor automatic operation of the
4.3
CCS. includinq initiation of safeguards mode of ops.
K4.07 Knowledge of USS design features and/or
4.1
X
interlock which provide adequate level in
containment sump for suction (interlock)
A .08 Ability to predict and/or monitor changes in
2.6
056 Condensate
X
parameters associated with MFW suction pressure.
K6.12 Knowledge of the effect of a loss or
059 Main Feedwater
X
malfunction of /G controller logic for MFW reg.
2.5
Valve will have on the MFW components.
K2.01 Knowledge Of bus power supplies to AI-W
IS
061 Auxiliary/Emergency Feedwater
.1
Knowledge of abnormal condition
3.6
Brocedures.
K3.02 Knowledge o0 the effect that a loss or
.7"
063 DC Electrical Distribution
X
malfunction of tfe DC elec. Sytem will have on
components using DC contror power.
Kt.01 Knowledge of hysical connections between
2.
068 Liquid Radwaste
X
K5.04 Knowledge of the operational implications of
3RO
071 Waste Gas Disposal
X
the relationships of hydrogen/oxygen
concentrations to flammability.
A3.01 Ability to monitor automatic operation ot the
I
f1
SR
072 Area Radiation Monitoring
X
ARM system to changes in ventilation alignment
K/A Category Point Totals:
13
1.2
2 12
1t
1t 12 12 12
1t
1t 1
I1 9
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
A4.03 Ability to manually operate and/or monitor
-Z0
002 Reactor Coolant
X
in the control room indications and controls
4.4
necessary to recognize and correct saturation
conditions
K1.04 Knowledge of thetphysical connections
006 Emergency Core Cooling
X
and/or cause/effect relationship between ECCS
2.8
and Aux. Spray system.
A3.02 Ability to monitor automatic operation ot
3.5
010 Pressurizer Pressure Control
X
the PZR PCS including PZR pressure.
K6.03 Knowledge of the effect of a loss or
bHr
011 Pressurizer Level Control
X
malfunction between PZR level and PZR heater
3.3
control circuit.
A .01 Ability to predict and/or monitor changes in
3.4
-S0
012 Reactor Protection
X
parameters associated with operating the RPS
ncluding trip setpoint adiustment.
G2.4.21 Knowledge of the parameters and logic
4.3
027 Containment Iodine Removal
X
used to assess the status of safety functions
including containment systems.
K5.03 Knowledge of the operational implications
3.9
S7O
028 Hydrogen Recombiner and Purge Control
X
of sources of hydrogen within containment.
K4.03 Knowledge of design features and/or
3.5
bRu
029 Containment Purge
X
interlocks which provide automatic purge
isolation
K4.01 Knowledge of design features and/or
-T
-
033 Spent Fuel Pool Cooling
X
interlocks which provide For maintenance of spent
fuel pool level.
A4.05Abi lity to manually operate and/or monitor
4
035 Steam Generator
Xin
the control room lever control to enhance
natural circulation.
K3.05 Knowledge that a loss or malfunction of
3.7
039 Main and Reheat Steam
X
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 have on EDG.
K1.03 Knowledge of the physical connections
4.ZR
064 Emergency Diesel Generator
X
and/or cause-efect relationship between the
EDG and the EDG fuel oil supply system.
75.01 Knowledge of the operational implications
3.7
073 Process Radiation Monitoring
X
as they apply to concepts to the PRM related to
radiation theory, including sources, types, units
and effects.
075 Circulating Water
_______________________
A2.01 Ability to predict the impacts of cross
32
RL
079 Station Air
X
connection with lAS. Use procedures to correct,
control or mitigate.
A3.0I Ability to monitor automatic operation of
3.7
7RO
086 Fire Protection
X
the FPS including starting mechanisms of fire
water pumps.
K3.03 Knowledge of the effect that a loss or
4R
103 Containment
X
malfunction of containment system will have on
containment integrity under refueling" conditions.
K/A Category Point Totals:
I 2
1 3
[I1Z]ZI1 1ZI 11 Zt2
[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/A Topic(s)
Imp.
Exam
1
2
3
4
5
6
1
2
3
4
A2.02 Ability to predict the impacts otfp
re
X
transient protedion during cold shutdown and
3.7
based on predictions correct, control or mitigate.
007 Pressurizer Relief/Quench Tank
K4.02 Knowledge of CUWS design feature and/or
008 Component Cooling Water
x
interlocks which provide for operation of the surge
2.7
tank, associated valves and controls.
K6.03 Knowledge O1 the effect ot a loss or
041 Steam Dump/Turbine Bypass Control
malfunction of controllers positioners including ICS,
2.9
S/G. CRDS wll have on the SDS.
045 Main Turbine Generator
076 Service Water
K1.05 Knowled e of the physical connections
078 Instrument Air
x
and/or cause effect relationship between lAS and
3.5
MSIV air.
K/A Category Point Totals:
j
jJ
1
1j
1
1j{
J
Group Point Total:
-
4
Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-5
Facility: St. Lucie
(02-301)
Date of Exam: 4/22/02
Exam Level: SRO
Category
K/A If
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
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
Total4
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 refueling process
3.5
4
Total
2.3.10
Ability o perform poeurles to reduce excessive levels of
rad ation and guard against personnel exposure
3.3
Radiation
2.3.9
Knowledge of the process for performing a containment purge
Control
3.4
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 controls
and Plan
2.4.12
Knowledge of abnormal condition procedures.
3.6
Procedures
2..1 Knowledge of Et thesholds 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
S