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 24
Emergency
& Abnormal 2 2 2 2 4______ 2 16
Plant v._ _ _ _ _ _ _ _
Evolutions 31 1 3
Tier Tir 6 5 8 * 8 9 ;, 7 43
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 PWR SRO Examination Outline 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)
1 2 3 1 2 Imp. Exam
000001 Continuous Rod Withdrawal/I Akl.17 Knowledge ot operational implications eoMI u SHU
X 13.7
AK3.0 Knowledge o0the 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
.K2.02Knowledge of interrelations between pumps and large break 4.1
000011 Large Break LOCA/ III X LOCA's 2.7
000015/17 RCP Malunctions/IV AA2.10 Ability to determine when to secure RCP's on loss of cooling or
X seal injection. 3.7 SRO
CE/Al 3 Natural Circ. / IV AK2.2 Knowledge of interrelations between NC and heat removal R
X systems and relations between the proper operation of these systems. 3.6
000024 Emergency Boration / I AKI.02 Knowledge ot operational implications ot emergency boration and
X relationship between boron addition and reactor power. 3.9
000026 Loss of Component Cooling Water / V111 AK3.02 KnowledCoe ot the reasons Tor the automatic actions (aignment)
X X within the CCWSNresulting from actuation of ESFAS. 3.9 SRO
G2.1.33 Tech Spec entrvlevel conditions 4.0 SRO
relays and R
000029 Anticipated Transient w/o Scram / I X LK2.UO Knowledge
disconnects Or an
following ATWAS between breakers
interrelations 3.1
000040 (CEJEO5) Steam Line Rupture- Excessive EA0.3 Ability to operate and/or monitor desired operating results dunng
Heat Transfer / IV X X abnormal and emergency situations. 4.0 SRO
EA2.1 Ability to determine and interpret facility conditions and selection of 4.0 SRO
appropriate procedures dudng abnormal and emergency operations.
AK 1.2 Kno wledge of operational implications of normal, abnormal and SRO
CE/All RCGS Overooting.- PTS / IV X EOP's associated with RCS overcooling. 3.3
000051 Loss of Condenser Vacuum / IV AA2.02 Ability to determine and interpret conditions requiring - RO
X reactor/turbine trip on loss of condenser vacuum. 4.1
000055 Station Blackout! VI EK1.02 Knowledge ot operational implications of natural circulation
X X coolin as they apply to station blackout. 4.4 SRO
EA1 .06 Ability to operate and monitor restoration of power with one EDG 4.5 SRO
000057 Loss of Vital AC Elec. Inst. Bus / VI X AA1.05 Ability to operate and/or monitor backup inst. Indications 3.4 SRO
000059 Accidental Liquid Release G2.3.10 Ability to perform procedures to reduce levels of radiation and 3.3 SRO
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
000067 Plant Fire On-site / IX Q2.4.26 Knowled e of facilityprotection requirements including tire 3SRO
X brigade and portable fire fighting equipment usage.
000068 (BW/A06) Control Room Evac. / VIII AK3.13 Knowledge of the reasons for periormmng a SDM calculation, -SRO
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.
000076 High Reactor Coolant Activity / IX AA2..02 Ability to determine and interpret correct actions required for high 3.4n SR
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 PWR SRO Examination Outline
Emeroency and Abnormal Plant Evolutions - Tier Form ES-401-3
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
AK1.01 with reactor trip recovery.
Knowledge otoperational implications ot 3.4
000008 Pressurizer Vapor Space Accident / Ill X thermodynamics and flow characteristics of open or 3.7
leaking valves
000009 Small Break LOCA /III X small KnOwled
toK3.10 break Ot me reasons for PLH level as applied
eA 3.6
AA1 .01 ADility to operatelmonitor Uvu letdown and 3.6
000022 Loss of Reactor Coolant Makeup / II oZR7
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 SRO
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 SRO
0 LVNotchosen due to PSL does not have intermediate range N/A N/A
000033 Loss of Intermediate Range NI /VII NI's.
000037 Steam Generator Tube Leak / Ill AA2.1* b*1bii[to determine and interpret pressure at which n::RTO
X to maintain durng Sb cooldown.
dUS 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 otfRO
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.
CE/E09 Functional Recovery EMA1.3 Ability o operate and/or monitor desired operating 3.TW SRO
x results during abnormal and emergency situations.
K/A Category Point Totals: 12 2 12 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 PWR SRO Examination Outline
Plant Systems Form ES-401-3
- 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
001 Control Rod Drive 00 CntolRo Div XK1
X .05 Knoweg of phyia cnnections and/or M
cause effect relationship between CADS and NIS 4.4
and RPS.
003 Reactor Coolant Pump 003 Rector oolan PumpA2.01 X Abiliy to predict rates
RCP seals, the'imacts
of seal ofleak-off
problems with 1W _ -Mr
procedures especially
to correct, control or mitigate. and use
004 hemcal nd olum CotrolX K.05 Knowledge Of bus power supplies to MO Vs. 2.9
0 04 CEimg caleand VoltF aum e s Acnatrol X- K ilS K no wledge o f physical connection s and /o r ~ T ~U
013 Engineered Safety Features Actuation X cause effect relationship between ESFAS and MFW
system. ~~~ thags)n
ito limeic 38
014 Rod Position Indication Al1O
Ablto predc and/rm
A1.03~~~~~ Abiit
o
n/o mnitor changes in
X parameters with
associated (to prevent exceed in design 3.
RPIS and PDIL, PPDIL
015 Nuclear Instrumentation
- K4.07 Kniowledge of NIS design features andl/or 3.F
x X interlocks for to ermissives
A4.03 Ability manually operate and/or monitor in 3.9 SRO
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 SRO
mitigate the consequences of those malfunctions or
022 Containment Cooling K22 Knowledge of t eerations hat a loss or
X X malfunction willmave on containment
instrumentation readings.
A3.01 Ability to monitor automatic operation of the 4.3 SRO
CCS including initiation of safeguards mode of ons.
K4.07 Knowledge of CSS design eatures and/or fRl
4.1
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 SRO
Valve will have 'son the MFW components.
ystem
sK2.01 MOV
Knowledge
_RZT~nw of bus
ont power supplies
r Upoller for MFW
sploic s to AregF-W f.l:R
uxlay/
06aerXX mrenyFed
X 2.
061 Auxiliary/Em nergency Feedwater
(32A.1T1 Knowledge of abnormal condition 3.6 SRO
---- ---- --- 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
068 Liquid Radwaste X LRS and RCS and cVGS 2
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
072 Area Radiation Monitorng X ARM system to changes in ventilation alignment ~ l
K/A Category Point Totals: 3 12 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 PWR SRO Examination Outline 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)
1 Imp. Exam
2 3 4 5 6 1 2 3 4 1
002 Reactor Coolant A4.03 Ability to manually operate and/or monitor
in the control room indications and controls 4.4
necessary to recognize and correct saturation
conditions
006 Emergency Core Cooling K1.04 Knowledge ot the physical connect onsg_ u
and/or cause/efect relationship between ECMS 2.8
and Aux. Spray svstem.
010 Pressurizer Pressure Control A3.02 Abilit to monitor automatic operation ot 35 5
X the PZR PC S including PZR pressure.
011 Pressurizer Level Control K6.03 Knowledge of the effect of a loss or bRO
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.
028 Hydrogen Recombiner and Purge Control K5.03 Knowledge of the operational implications 3.6 STO
+ X of sources of hydrogen within containment.
K4.03 Knowledge ot design features and/orFSR 35
029 Containment Purge interlocks which provide automatic purge
isolation
033 Spent Fuel Pool Cooling K4.01 Knowledge ot desi n features and/or 3.2
interlocks which provide or maintenance of spent
- fuelpool level.
035 Steam Generator A45
in thee control
Ability toroom
manually operate
levelco ntrol toand/or monitor
enhance 4.0 S
natural circulation.
K3.05 Knowledge that a loss or malfunction ot J.7I SRO
039 Main and Reheat Steam the MRSS will have on the RCS.
055 Condenser Air Removal
062 AC Electrical Distribution K3.02 Knowledge of loss or malfunction of A.C. 4.4
X distribution willrave 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.
073 Process Radiation Monitoring K5.01 Knowledge of the operational implications 3.0
X as they apply to concepts to the PRM related to
radiation theory, including sources, types, units
andeffects.
075 Circulating Water
079 Station Air A2.01 Ability to predict the impacts o0 cross
X connection with lAS. Use procedures to correct,
control ormiti ate.
086 Fire Protection A.U1 AbilTY to monitor automatic operation of 3
X the FPS including starting mechanisms of fire
waterpumps.
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 12 1-2-17-1_1
i3 112 21 17
6
ES-401 St. Lucie (02-301) Date of Exam: 4/22/02 PWR SRO Examination Outline 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
005 Residual Heat Removal X transient protection during cold shutdown and 3.7 SRO
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 SRO
tank, associated valves and controls.
K(6.03 Knowledge of the effect ot a loss or
041 Steam Dump/Turbine Bypass Control malfunction
S/G, ot controllers
- - --CRDSwllhave positioners including ICS,
on theSDS. 2.9 SRO
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 SRO
IIMSIV air.
K/A Category Point Totals: JT11 1 [ 1 J 1 I 1= =)Group Point Total:
7
ES-401 Genedc Knowled a and Abilities Outline (Tier 3) Form ES-401-5
Facility: St. Lucie (02-301) Date of Exam: 4 a2/02 Exam Level: SRO
Category K/A # Topic Imp. Exam
Knowledge of one hour technical specification action
2.1.11 statements for systems. 3.8 SRO
2.1.32 Ability to explain and apply all systems limits and precautions 3.8 SRO
Conduct of
Operations 2.1.22 Ability to determine Mode of Operation 3.3 SRO
2.1.29 Knowledge of how to conduct and verify valve lineups 3.3 SRO
Total 4
Knowledge of the design, procedural and operational 3.3
2.2.3 differences between units. SRO
2.2.22 Knowledge of limiting conditions for operations and safety limits 4.1 SRO
Control 2.2.12 Knowledge of surveillance procedures 3.4 SRO
2.2.27 Knowledge of the refuel ng process 3.5 SRO
4
Total
2.3.10 Ability to perform procedures to reduce excessive levels of SRO
radiation and guard against personnel exposure 3.3
2.3.9 Knowledge of the process for performing a containment purge 3,4 SRO
Radiation _____
Control
2.3.11 Ability to control radiation releases 3.2 SRO
2.3.6 Knowledge of the requirements for reviewing and approving 3.1 SRO
release permits.
4
Total
2.4.7 Knowledge of event based EOP mitigation strategies 3.8 SRO
2.4.49 Ability to perform without reference actions that require 4.0 SRO
Emergency - immediate operation of system components and con roIs
Procedures
and Plan 2.4.12 Knowledge of abnormal condition procedures. 3.6 SRO
2.4.41 Knowledge of EAL thresholds and classifications 4.1 SRO
2.4.40 Knowledge of SRO's responsibilities in E-Plan implementation 4.0 SRO
Total 5
Tier 3 Target Point Total SRO 17