ML032940448
| ML032940448 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/29/2003 |
| From: | NRC/RGN-II |
| To: | Progress Energy Florida |
| References | |
| 50-302/03-301 50-302/03-301 | |
| Download: ML032940448 (27) | |
See also: IR 05000302/2003301
Text
Draft Submittal
(Pink Paper)
I. Written Exam Sample out~ines
CRYSTAL RIVER AUGUST
EXAM 50-302/2003-301
-
AUGUST 25 29,2003
ES-401 PWR EXAMINATION OUTLINE (RO) FORM ES-401-2
1 Facility: CRYSTAL RIVER UNIT 3
I I
Date of Exam: AUGUST 25,2003
I
1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline
(i.e., the "Tier Totals" in each K/A category shall not be less than two). Refer to Section D.1.c for
additional guidance regarding SRO sampling.
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 by r l from that specified in the table based on
NRC revisions. The final RO exam must total 75 points and the SRC-only exam must total 25 points.
3. Select topics from many systems and evolutions: avoid selecting more than two KIA topics from a
given system or evolution unless they relate to plant-specific priorities.
4. Systemslevolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the categorykier.
6.* The generic (G) 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. The SRO K/As must also be linked to
10 CFR 55.43 or an SRC-level learning objective.
7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance
ratings (IR) for the applicable license level, and the point totals for each system and category. Enter
the group and tier totals for each category in the table above; summarize all the SRO-only knowledge
and non-A2 ability categories in the columns labeled "K" and "A," Use duplicate pages for RO and
SRO-only exams.
8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.
The random sampling guidance provided in ES-401, Attachment 1, was used to
generate this outline.
Page 1 of 15 NUREG-1021, DRAFT REV. 9
F\2003 NRC Exam\OUTLINES\Written\RONRC ZK3 Written Exam 0utline.doc
Emergency and Abnormal Plant Evolutions - Tier 11Group 1 (Ro)
-
EIAPE # I Name I Safety WA Topic(s) IR
T
-
-
007EA2.02 - Abilitv to determine or interoret the
000007 or EOZEIO Reactor Trip - fol oiing as they apply IO a reactor ir p 'Proper
Stabilization- Recovery / 1 actions to be laden f tne aLtoma18c safety 4.3 1
fdnctions nave no1 laken pace
- -
OOBAKI .01 - Knowledge of the operational
000008 Pressurizer Vapor Space X implications of the following concepts as they
Accident / 3 apply to a Pressurizer Vapor Space Accident: 1
3.2
Thermodynamics and flow characteristics of
open or leaking valves
- -
009EK2.03 - Knowledge of the interrelations
000009 Small Break LOCA I 3 I between the small break LOCA and the S/GS. 3.0
-
1
-
000011 Large Break LOCA I 3
I 01162.4.20 - Knwledge of operational
implications of EOP warnings, cautions, and 3.3 1
I-
notes
- _.
015AK2.07 - Know edge of tne intene alions
000015/17 RCP Malfunctions I 4 between Reactor Coolant PJmp Ma fLnCl ons 2.9 1
fLossof RC Flow) and tne RCP seals.
- -
022AA2.04-Abilitv to determine and interpret
---t
000022 Loss of Rx Coolant Makeup / 2 the following as thky apply to the Loss of 2.9 1
Reactor Coolant Pump Makeup: How long PZR
level can be maintained within limits
- -
025AX2 05 - Know edge of the nterrelallons
000025 Loss of RHR System / 4 DeNveen the -oss of Decay Heat Removal 2.6 1
System and the l o owing Reactor DL. alng
SUmD
~
- -
026AA1.04 - Abilitv to operate and / o r monitor
000026 Loss of Component Cooling the followina as thev aodv to the Loss of 2.7 1
Water / 8 NLclear Sekices / Deday'Heal C osed Cycle
Cool ng CRDM n gh-temperalde alarm syslem
- -
027AA1 05 - A~ililyto operate and I or mon lor
~
000027 Pressurizer Pressure Control m e following as they apply IO Ihe Pressurizer 3.3 1
System Malfunction / 3 Pressdre Control Malhnct ons Transfer of
heaters to backup Dower supply
- -
029EK3.11- Knowledge of the reasons for the 4.2 1
000029 ATWS / 1 followina resoonses as the apDIv to the ATWS:
lnitiatini emergency boration .
- -
038EA2.08 - Abilitv to determine or interpret the
000038 Steam Gen. Tube Rupture / 3 follow,ng as they a'pp~y to a SGTR. v ade 3.8 1
a ternatnves for plac ng plan1 in safe condil on
wnen condenser s not avai able
- -
I EO5EA1.2- Ab lily 10 Operate and I or monitor
000040 or E05 Steam Line Rupture - me followinq as tney. apply. . . to the (Excess ve 3.6 1
Excessive Heat Transfer / 4 Heat Transfer): Operating behavior
charactenstics ofthe facility.
- -
__ ~.~~
~~~
n54AA1~02-
. Abilihl
. ., to
-- ooerate and /or monitor
~ ~ ~
tne follow ng as they apply 10 tne Loss of Main
000054 Loss of Main Feedwater I 4 Feeawater (MFW): Manual slart~pof elec1r.c 4.4 1
and steamdriven EFW pumps
~
- - -
Page 2 of 15 NUREG-1021,DRAFT REV. 9
F\2003 NRC Exam\OUTLINES\Written\RO NRC 2K3 Written Exam 0utline.doc
ES-401 PWR EXAMINATION OUTLINE (RO) FORM ES-401-2
1
c Function
Emergency and Abnormal Plant Evolutions - Tier 11Group 1 (Ro)
EIAPE # I Name I Safety
000055 Station Blackout / 6
000056 Loss of Off-site Power / 6
000057 Loss of Vital AC Inst. Bus / 6
000058 LOSS of DC Power / 6
000062 Loss of Nuclear Svc Water / 4
I
oDeration.
KIA Topic(s)
055EK3.02 - Knowledge of the reasons for the
following responses as the apply to the Station
Blackout: Actions contained in EOP for loss of
offsite and onsite Dower
056G2.1.2 - Knowledge of operator
responsibilitiesduring all modes of plant
058AA2.02 - Aoility to aeterm ne ana interpret
me follow ng as they apply lo the -0% of DC
Power: 125V dc bJs vodage, low alarm
062AK3.02 - Knowledge of the reasons for the
following responses as they apply to the Loss of
Raw Water: The automatic actions
(a ignments) w in n the RWS result*ngfrom lne
act~aton of [ne ESFAS
000065 Loss of Instrument Air / 8
-lI I EMEKI.3- Knowledae of the ooerational
iiipliations of the foiowing cokepts as tney
apply to the (InadeqLate Heal Transfer)
E04 Inadequate Heat Transfer- Loss of Annunc ators and conditions ind cat ng Signals,
Secondary Heat Sink / 4 and remedial actions associated with the
(Inadequate Heat Transfer).
KIA Category Totals: 2 Group Point Total:
Page 3 of 15 NUREG-1021. DRAFT REV. 9
F\2003 NRC Exam\OUTLINES\Written\RO NRC 2K3 Written Exam 0utline.doc
ES-401 PWR EXAMINATION OUTLINE (RO) FORM ES-401-2
Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (Ro)
E/APE # / Name / Safety K1 KZ K/A Topic(s) IR #
Function ~~~~~~
003AK3.07 - Knowledge of the reaions for
000003 Dropped Control Rod / 1 the foilowing responses as they apply to the
Dropped Control Rod: TechSpec limits for T- 3.8 1
ave
000005 InoperablelStuck Control Rod / 1
000024 Emergency Boration / 1
028AK2.02 - Knowledge of the interrelations
000028 Pressurizer Level Malfunc~on /2 X between the Pressurizer Level Control
Malfunctions and the following: Sensors and 2.6 1
detectors
000032 Loss of Source Range NI / 7
033AA2.04-Ability to determine and interpret
000033 Loss of intermediate Range NI / 7 the following as they apply to the Loss of
intermediate Range Nuclear Instrumentation: 3.2 1
Satisfactoly overlap between sourcerange,
intermediate-range and power-range
instrumentation
000036 (BW/AO8) Fuel Handling Accident /
0
037AK3.05 - Knowledae of the reasons for
~~
000037 Steam Generator Tube Leak / 3 the following responses as they apply to the
Steam Generator Tube Leak: Actions
contained in prccedures for radiation 3.7 1
monitoring. RCS water inventory balance, S/G
tube failure, and plant shutdown I I
t
~
000051 Loss of Condenser Vacuum / 4
000059 Accidental Liquid RadWaste Rel. /
000060 Accidental Gaseous Fadwaste Rel.
19
000061 ARM System Alarms / 7
000067 Plant Fire On-site / 8
000068 (BW/AO6) Control Room Evac. / 8
069G2.1.33 -Ability to recognize indications
000069 (W/E14) Loss of CTMT Integrity / 5 for system operating parameters which are
entry-level conditions for technical 3.4 1
specifications.
000074 (W/E06&E07) had. Core Cwling /
Page 4 of 15 NUREG-1021. DRAFT REV. 9
F\2003 NRC Exam\OUTLINES\Written\RO NRC 2K3 Written Exam 0udine.doc
ES-401 PWR EXAMINATION OUTLINE (RO) FORM ES-401-2
Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (Ro)
K/A Topic@)
AOlAA2 2 . Ability to determine and nterpret
me follow ng as they app y to the (Plant
Runback) Adnerence to appropriate
procedures and operation within the
limitations in the facilitys license and
amendments
AWAAl. 1 -Ab lhly to operate and I or monitor
the fol ow ng as they apply to the (Tub ne
Trip). Components, and fLnctions of COntrO
and safety systems, including instrumentation,
signals, interlocks, failure modes, and
automatic and manual features.
A07AK1.2 - Knowledge of the operational
implications of the following concepts as they
apply to the (Flooding): Normal, abnormal
and emergency operating procedures
associatedwith (Flooding).
E13EQ 1 - Know eage of the interre ations
berween the (EOP RJles) ana the folowlng
Components, and fmctions of control and
safety systems. ncLding instrunentation.
s gna s. nterlocks, failLre moaes, and
automate and manua features
Group Point Total: I 9/E
Page 5 of 15 NUREG-1021. DRAFT REV. 9
F\2003 NRC Exam\OUTLlNES\Written\RO NRC 2K3 Written Exam Outline.doc
ES-401 PWR EXAMINATION OUTLINE (RO) FORM ES-401-2
Plant Systems - Tier 21Group 1 (Ro)
System # I Name 1 K*
KIA Topic@)
--r
003 Reactor Coolant
Pump
003K3.05 - 6nowleage of tne
effect that a oss or ma fJnct on
of the RCPs w II have on the
lo ow,ng' ICs
003K6.04 - Knowledge of the
effect of a loss or malfunction of
Reactor Building isolation valves
on RCP operation
004A1.12-Abilityto predict
and/or monitor changes in the
rate of boron concentration
reduction in RCS as a function of
004 Chemical and letdown flow while deborating
Volume Control demineralizer is in service (to
prevent exceeding design limits)
associated with operating the
MUPS controls
00564 08. Knowleage of Decay
Heat System design featJre(s)
analor nter ock(s) wn ch prov ae
005 Residual Heat for tne following L neup for
Removal pggy-backmodewln hgh-
pressure In.ection (MakeJp
System)
006K4 05 - 6nowledge of ECCS
des gn featJre(s) analor
nterlock(s)which prowde for
aLtostati of dP /.PI
006G2.1.28 - Knowledged the
purpose and function of major
system components and
controls.
007A4.10-Ability to manually
operate andlor monitor in the
007 Pressurizer control room: Recognition of
RelieflCluenchTank leaking PORVIcode safety
008A4.07-Ability to manually
operate and/or monitor in the
008 Component control room: Control of
Cooling Water minimum level in the SWS I DCS
surge tank
Page 6 of 15 NUREG-1021,DRAFT REV. 9
F\2003 NRC Exam\OUTLINES\Written\RO NRC 2K3 Written Exam 0utline.doc
ES-401 PWR EXAMINATION OUTLINE (RO) FORM ES-401-2
Plant Systems - Tier 2/Group 1 (Ro)
WA Topic(s)
)10K5.01 - Knowledge of the
Iperational implications of the
ollowing concepts as the apply
010 Pressurizer o the PZR PCS: Determination
Pressure Control )f condition of fluid in PZR, using
- team tables
)12K1.03 - Knowledge ofthe
)hysical wnnections andlor
012 Reactor :ause-effect relationships
Protection letween the RPS and the CRDS.
)13K6.01 - Knowledge of the
?ffectof a loss or malfunction of
- SFAS related sensors and
jetectors.
013 Engineered
Safety Features )13K1.13- Knowledgeofthe
Actuation )hysical connections andlor
- awe effect relationshios
)eween the ESFAS and the
7VAC systems.
122A2.04- Ability to (a) predict
he impacts of the following
nalfunctions or operations on the
- CS; and (b) based on those
022 Containment )redictions. use procedures to
Cooling :orrect, wntrol. or mitigate the
-
- onsequences of those
nalfunctions or operations: Loss
)f cooling water
326A3.01 - Abilityto monitor
automatic operation of the BSS,
026 Containment ncluding: Pump starts and
Spray :orrect MOV positioning
Page 7 of 15 NUREG-1021,DRAFT REV.9
F\2003 NRC Exam\OUTLINES\Written\RO NRC 2K3 Written Exam 0utline.doc
ES-401 PWR EXAMINATION OUTLINE (RO) FORM ES-401-2
Plant Systems - Tier 2/Group 1 (R4)
-
K/A Topic(s)
IR
-
039K3.04 - Knowledge of the
effect that a loss or malfunction
of the MRSS will have on the 2.5
following: MFW pumps
039A2.05- Ability to (a) predict
the impacts of the following
039 Main and Reheat malfunctions or operations on the
Steam MRSS: and (b) based on
predictions, use procedures to
correct, controi, or mitigate the 3.3
consequences of those
malfunctions or operations:
lncreasino steam demand. its
relationstp to increases in
reactor power
-
056K1.03 - Knowledge of the
physical connections andlor
cause-effect relationships 2.6
056 Condensate between the Condensate System
and the following systems: MFW
-
059A4.10-Ability to manually 3.9
operate and monitor in the
control room: ICs
059 Main Feedwater
059G2.1.22 -Ability to determine 2.8
Mode of Operation.
-
061 061K2.01 - Knowleoge of OLS
Auxiliary/Emergency power supplies lo the following: 3.2
-
062K3.01 - Knowledge of the
effect that a loss or malfunction
of the AC distribution system will 3.5
have on the following: Major
system loads
062 AC Electrical -
Distribution 06202.1.33 - A b ty to recognize
indica1ons for system operating
parameters wnich are entry-leve 3.1
condit ons for tecnntcal
spec ficat ons.
-
063A3.01- Aoil ty to monitor
aLtomatic operation of the dc
063 DC Electrical eieclr cal system, ncluding:
Distribution 2.7
Meters. annLnc alors. ala 5 .
recorders, and in0:cating lights
-
Page 8 of 15 NUREG-1021, DRAFT REV. 9
F\2003 NRC Exam\OUTLINES\Written\RONRC 2K3 Written Exam 0utline.doc
~
ES-401 PWR EXAMINATION OUTLINE (RO) FORM ES-401-2
Plant Systems - Tier 2/Group 1 (Ro)
WA Topic(s)
System # / Name
064A2.08- Ability to (a) predict
the impacts of the following
malfunctions or operations on the
ED/G system; and (b) based on
064 Emergency those predictions, use
Diesel Generator procedures to correct, control, or
mitigate the consequences of
those malfunctions or operations:
Consequences of
openinglclosing breaker between
buses (VARS, out-d-phase.
voltage)
073K5.02 - 6nowleage of the
operat onal mpl callonS as lney
app y IO concepts as they apply
073 Process to the PRM svslem: Raoation
Radiation Monitoring intensity chaAges with source
distance
076A2.02Ability to (a) predict
the impacts of the following
malfunctions or operations on the
RWS; and (b) based on those
predictions, use procedures to
076 Service Water correct, control, or mitigate the
consequences of those
malfunctions or operations: RW
header pressure
078K2.01 - Knowledge of bus
power supplies to the following:
078 Instrument Air Instrument air compressor
103A3.01 -Ability to monitor
automatic operation of the
reactor building system,
103 Containment including: Reactor Building
isolation
WA Category Point Group Point Total:
Totals:
Page 9 of 15 NUREG-1021, DRAFT REV. 9
F\2003 NRC Exam\OUTLINES\Written\RO NRC 2K3 Written Exam 0utline.doc
ES-401 PWR EXAMINATION OUTLINE (RO) FORM ES-401-2
System # I Name
001 Control Rod
Drive
,, Plant Systems - Tier 2/Group 2 (Ro)
KIA Topic@)
OOlK5.28 - Knowledge of
boron reactivity worth vs.
boron concentration. (i.e.;
amount of boron needed
(ppm) to change core
reactivity to desired amount).
002K1.09 - Knowledge of the
physical connectons and/or
cause-effect relationships
002 Reactor Coolant X between the RCS and the
Pressurizer (PZR).
011 Pressurizer Leve
Control
014K4.05 - Knowledge of
RPlS design feature(s) and/or
014 Rod Position interlock(s) which provide rod
IndicaBon hold interlocks.
015A1.04-Abiiityto predict
andlor monitor changes in
parameters (to prevent
015 Nuclear exceeding design limits)
Instrumentation associated with operating the
NIS controls inciuding:
Quadrant power tilt ratio
016A301 -Ao~llytomonlor
aLtomat c operat on of me
016 Non-nuclea! h N S. NncLdlng AJtOmatiC
Instrumentation select on of hNlS nputs to
contro systems
017 In-core
Temperature Monitor
027 Containment
iodine Removal
028 Hydrogen
Recornbiner and
Purge Control
Page 10 of 15 NUREG-1021. DRAFT REV. 9
F\2003 NRC Exam\OUTLINES\Written\RO NRC 2K3 Written Exam 0utline.doc
ES-401 PWR EXAMINATION OUTLINE (RO) FORM ES-401-2
Plant Systems - Tier 2/Group 2
3
System # / Name WA Topic(s)
029 Containment
Purge
033 Spent Fuel Pool
Cooling
034 Fuel Handling
Equipment
035K4 01 - Know edge of
SIGS design featJre(s) andlor
035 Steam Generator inierlock(s)wnich prov de for 3.6
SIG level wntro.
041A2.02-Ability to (a)
predict the impacts of the
following malfunctions or
operations on the Turbine
041 Steam Bypass Valves; and (b) based
DumpITurbine on those predictions or 3.6
Bypass Control mitigate the consequences of
those malfunctions or
operations: Steam valve
stuck open
045 Main Turbine
Generator
04543.01 - Xnowleage of the
effect that a oss or
rnalfJnct on of me MTIG
system will have on the
I 2.9
055 Condenser Air
Removal
068 Liquid Radwaste
071K3.04 - Knowledge of the
effect that a loss or
malfunction of the Waste Gas 2.7
071 Waste Gas Disposal System will have on
Disposal the following: Ventilation
system
072 Area Radiation
Monitoring
Page 11 of 15 NUREG-1021, DRAFT REV. 9
F:\2003 NRC Exam\OUTLINES\Written\RO NRC 2K3 Written Exam 0utline.doc
ES-401 PWR EXAMINATION OUTLINE (RO) FORM ES-401-2
Plant Systems - Tier 2/Group 2 (Ro)
086 Fire Protection
IIlIEt
KIA Categoly Point
Totals
Page 12 of 15 NUREG-1021.DRAFT REV.9
F\2003 NRC Exarn\OUTLINES\Written\RONRC 2K3 Written Exam 0udine.doc
~ ~~~
ES-401 Generic Knowledge and Abilities Outline (RO) Form ES-401-3
z
Facility: Crystal River Unit #3 Date of Exam: August 25,2003
I I
Category KIA # Topic SRO-Only
~
2.1.4 Knowledge of shift staffing requirements. I I
Ability to evaluate plant performance and make
1. operational judgments based on operating
Conduct of 2.1.7 characteristics, reactor behavior, and instrument 3.7 1
Operations interpretation.
Ability to apply technical specifications for a
2.1.12 system.
2.1.20 Ability to execute procedure steps. 4.3 1
2.
Equipment
Control
3.
Radiation
Control
3.1 I 1
Page 13 of 15 NUREG-1021. DRAFT REV. 9
F\2003 NRC Exam\OUTLINES\Written\RO NRC 2K3 Written Exam 0utline.doc
ES-401 Generic Knowledge and Abilities Outline (RO) Form ES-401-3
Facility: Crystal River Unit #3 Date of Exam: August 25,2003
Category KIA# I Topic I RO I SRO-Only
IR # IR #
Knowledge of EOP entry conditions and
2'4'1 immediate action steps.
4.3 1
Knowledge of symptom based EOP mitigation
2.4.' 4.0 1
strategies.
2.4.1 1 Knowledge of abnormal condition procedures. 3.4 1
4.
Emergency Knowledge of RO tasks performed outside the
Procedures main control room during emergency operations
2'4'35 3,3 1
I Plan including system geography and system
implications.
Knowledge of the emergency action level
Tier 3 Point T
Page 14 of 15 NUREG-1021. DRAFT REV. 9
F\Z003 NRC Exam\OUTLINES\Written\RO NRC ZK3 Written Exam 0utline.doc
ES-401 Record of Rejected K/As FORM ES-401-4
Group I Randomly
Selected WA I Reason for Rejection
1I1 015AK2.05 WA= 1.9
112 003K3.06 WA =2.2
1I2 I 028AK2.07 I WA=1.8
211 I 006K4.02 I Not applicable at CR #3
211 007A4.02 WA= 2.2
211 007A4.05 WA = 2.4
211 008A4.11 Not applicable at CR #3
211 I 013K6.03 I WA = 2.4
211 I 039A2.02 I WA = 2.4
211 056 Only 2 RO WAS2 2.5 in whole system -flipped coin.
211 059A4.02 WA = 2.3
211 064K6.02 WA = 2.4
211 1 064K6.06 1 WA=2.3
212 I 002K1.15 I WA=2.2
212 I 035K4.04 I Not applicable at CR #3
212 I 035K4.08 I Not applicable at CR #3 and WA = 1.9
212 071K3.01 KIA = 2.0
Generic 2.3.5 I RO WA = 2.3
I
Page 15 of 15 NUREG-1021. DRAFT REV. 9
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~~ ~~
ES-401 PWR EXAMINATION OUTLINE (SRO) FORM ES-401-2
Facility: ( ?YSTAL RIVER UNIT 3 Date of Exam: AUGUST 25,2003
I I
Tier
1.
Emergency
!,Abnormal
Plant
Evolutions
2.
Plant
Systems
3. Generic Knowledge and 1 2 3 4 1 2 3 4
Abilities Categories 10 7
3 2 2 3 2 2 1 2
Yote:
1. Ensure that at least two topics from every KIA category are sampled within each tier of the RO outline
(Le.. the Tier Totals in each K/A category shall not be less than two). Refer to Section D.1.c for
additional guidance regarding SRO sampling.
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 by +I from that specified in the table based on
NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a
given system or evolution unless they relate to plant-specific priorities.
1. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the categoryltier.
5.* The generic (G) 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. The SRO K/As must also be linked to
10 CFR 55.43 or an SRC-level learning objective.
7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance
ratings (IR) for the applicable license level, and the point totals for each system and category. Enter
the group and tier totals for each category in the table above; summarize all the SRO-only knowledge
and non-A2 ability categories in the columns labeled K and A, Use duplicate pages for RO and
SRO-only exams.
5. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.
The random sampling guidance provided in ES-401, Attachment 1, was used to
generate this outline, with the exception of the 18 Tier 1 and Tier 2 SRO only
WAS. A smartrandom sampling method was approved for use by the Chief
Examiner.
Page 1 of 11 NUREG-1021. DRAFT REV. 9
F\2003 NRC Exam\OUTLINES\Written\SRO NRC 2K3 Written Exam 0utline.doc
ES-401 PWR EXAMINATION OUTLINE (SRO) FORM ES-401-2
Emergency and Abnormal Plant Evolutions - Tier 11Group 1 (SRO)
EIAPE # I Name I Safety WA Topic@) IR
Function
300007 or E02E10 Reactor Trip -
Stabilization- Recovery / 1
300008 Pressurizer Vapor Space
4ccident / 3
009EK3.06 - Knowledge of the reasons for the
300009 Small Break LOCA / 3 following responses, as they apply to the small 4.0
break LOCA: RCS inventoq balance
300011 Large Break LOCA / 3
300015/17 RCP Malfunctions / 4
000022 Loss of Rx Coolant Makeup / 2
025AK1.01- Knowledge of the operational
implications of the following concepts as they
apply to Loss of Decay Heat Removal System: 4.3
000025 Loss of RHR System / 4 Loss of DH System during all modes of
operation
026G2.4.47 -Ability to diagnose and recognize
000026 Loss of Component Cooling trends in an accurate and timely manner utilizing 3.7
Water I 8 the appropriate control room reference material.
000027 Pressurizer Pressure Control
System Malfunction/ 3
029EA2.09 - Ability to determine or interpret the
000029 ATWS / 1 following as they apply to a ATWS Occurrence 4.5
of a main turbineheactor trip
038EA2.13 -Ability to determine or interpret the
000038 Steam Gen. Tube Rupture / 3 following as they apply to a SGTR Magnitude
of rupture
040AK3.2 - Knowledge of the reasons for the
000040 or E05 Steam Line Rupture. following responses as they apply to the
Excessive Heat Transfer / 4 (Excessive Heat Transfer): Normal, abnormal
and emergency operating procedures
associated with (Excessive Heat Transfer).
000054 Loss of Main Feedwater / 4
05502.4.7 - Knowledge of event based EOP
000055 Station Blackout / 6
000056 Loss of Offsite Power / 6
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ES-401 PWR X AMINATIN \i OUTLINE (SRO) RM ES-401-2
Emergency and Abnormal Plant Evolutions - Tier l/Group 1 (SRO)
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ES-401 PWR EXAMINATION OUTLINE (SRO) FORM ES-401-2
000005 InoperablelStuck Control Rod / 1
00036 (SW/AOS) Fuel Handling Accident /
000060 Accidental Gaseous Radwaste Rel.
01 Plant Runback / 1
I I i i i i
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ES-401 PWR EXAMINATION OUTLINE (SRO) FORM ES-401-2
Emergency and Abnormal Plant Evolutions - Tier 11Group 2 (SRO)
EIAPE # I Name I Safety 42 G KIA Topic(s) IR #
Function
AOZAA1.1 -Ability to operate and/or monitor
the following as they apply to the (Loss of
NNkX): Components, and functions of control
BW/A02&A03 Loss of NNI-XPI/ 7 and safety systems, including instrumentation, 3,8
signals, interlocks, failure modes, and
automatic and manual features.
BWIAO4 Turbine Trip / 4
A05G2.2.20- Knowledge of the process for
BW/A05 Emergency Diesel Actuation I 6 X managing troubleshooting activities. 3.3 1
BW/A07 Flooding / 8
BW/E03 Inadequate Subcooling Margin / 4
BW/EO8; W/E03 LOCA Cooldown -
Depress. / 4
BW/EO9; CEIA13: W/E09&E10 Natura
Circ. / 4
BW/E13&E14 EOP Rules and Enclosures
KIA Categoly Point Totals: 1*I Group Point Total: 9/5
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ES-401 PWR EXAMINATION OUTLINE (SRO) FORM ES-401-2
Plant Systems - Tier 2/Group 1 (SRO)
q I I
K/A Topic(s)
003 Reactor Coolant
Pump I I
004A2.09-Ability to (a) predict
the impacts of a high primaly
andlor secondaly activty on the
MUPS; and (b) based on those 3.9 1
004 Chemical and predictions, use procedures to
Volume Control correct, control, or mitigate the
consequences of these
malfunctions.
005 Residual Heat
Removal
006 Emergency Core
Cooling
t
007 Pressurizer
RelieflQuench Tank
008 Component
Cooling Water
010 Pressurizer
Pressure Control
01262.2.24 -Ability to analyze
012 Reactor the affect of maintenance 3.8 1
Protection activities on LCO status.
013 Enoineered
Safety Features
Actuation I I
Cooling
026 Containment
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ES-401 PWR EXAMINATION OUTLINE (SRO) FORM ES-401-2
Plant Systems - Tier 2/Group 1 (SRO)
I System # / Name
WA Topic@)
t 039 Main and Reheat
Steam
056 Condensate
059 Main Feedwater
AuxilialyIEmergency
I
061A2.05- Ability to (a) predict
the impacts of the following
malfunctions or operations on the
ENV: and (b) based on those
predictions, use procedures to
correct, control, or mitigate the
3.4
consequences of those
malfunctions or operations:
Automatic control malfunction.
063 DC Electrical
Distribution 1
064A1.03-Ability to predict
andlor monitor changes in
parameters (to prevent
OW Emergency exceeding design limits) 3.3
Diesel Generator associated with operating the
ED/G system controis including:
Operating voltages. currents. and
temperatures
073 Process
076 Service Water
078 instrument Air
103 Containment
I
1 KIA Categoly Point
Totals: Group Point Total:
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ES-401 PWR EXAMINATION OUTLINE (SRO) FORM ES-401-2
Plant Systems - Tier 2/Group 2 (SRO)
Page 8 of 11 NUREG-1021, DRAFT REV. 9
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ES-401 PWR EXAMINATION OUTLINE (SRO) FORM ES-401-2
Plant Systems - Tier 2/Group 2 (SRO)
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ES-401 Generic Knowledge and Abilities Outline (SRO) Form ES-401-3
Facility: Crystal River Unit #3 Date of Exam: August 25,2003
Category KIA # Topic RO SRO-Only
~~~
JT--JT
2.1.4 =edge of shift staffing requirements.
-
Ability to evaluate plant performance and make
1. operational judgments based on operating
Conduct of 2.1.7 characteristics, reactor behavior, and instrument
Operations interpretation.
Ability to apply technical specifications for a
I
2.1.20 I Ability to execute procedure steps
Ability to obtain and interpret station electrical
2'1 '24 and mechanical drawings.
Subtotal
2.2.2 '
Ability to manipulate the console controls as
required to operate the facility between shutdown
and designated power levels.
4.0 I 1
i
2.
Equipment 2.2.12 Knowledge of surveillance procedures.
Control
Knowledge of limiting conditions for operations
2'2'22 and safety limits.
2.2.27 Knowledge of the refueling process.
Subtotal
!
Knowledge of 10CFR20 and related facility
2'3'1 radiation control requirements.
2.3.4 Knowledge of radiation exposure limits and
3. contamination control, including permissible
Radiation levels in excess of those authorized.
Control
2.3.6 Knowledge of the requirements for reviewing and
approving release permits.
Subtotal
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ES-401 Generic Knowledge and Abilities Outline (SRO) Form ES-401-3
Facility: Crystal River Unit #3 Date of Exam: August 25,2003
Topic RO SRO-Only
4.
Emergency
c 2.4.1
2.4.6
2.4.1 1
Knowledge of EOP entry conditions and
immediate action steps.
Knowledge of symptom based EOP mitigation
strategies.
IR
4.3
1
IR
4.0
1
I Plan
Knowledge of the emergency action level 4.1 1
2.4.41 thresholds and classifications.
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