ML031560723
| ML031560723 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 05/15/2003 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 50-390/03-301 | |
| Download: ML031560723 (16) | |
See also: IR 05000390/2003301
Text
Draft Submittal
(Pink Paper)
1 .
Written Exam Sample outlines
WATTS BAR EXAM 2003-301
50-390/2003-301
MAY 15, 2003
PWIR SRO Examination Outline
Printed: 03/13/2003
Facilitv:
Watts Bar Nuclear Plant
Form ES-401-3
Exam Date: 05/12/2003
Exam Level: SRO
Note: 1. Ensure thatat leasttwo topics from every K/A category are sampled within each teir (i.e., the "Tier Totals" in each
K/A category shall not be less than two).
2. Actual point totals must match those specified in the table.
3. Select topics from many systems; avoid selecting more than two or three K/Atopics from agiven 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 I and2 shall be selected from Section 2 of the K/A Catalog, butthetopics must be
relevantto 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 priorites. Enter the tier totals for each category in the table above.
Facility:
Watts Bar Nuclear Plant
mnination Outline
Printed:
03/1310
PC - JA0
Rmeraenev and Abnormal Plant Evolutions - Tier 1 / Group 1
Form ES-401-3
E/APE #
E/APE Name / Safety Function
Ki
K2 K3 Al
A2 G KA Top ie
imp.
Points
003
Dropped Control Rod / I
X
AK3.08 - Criteria for inoperable control rods
4.2
1
015
Reactor Coolant Pump (RCP) Malfunctions /4
_ _ _ _
X _
AA2.09 - When to secure RCPs on high stator3.5
temperatures
015
Reactor Coolant Pump (RCP) Malfunctions /4
X
-
_
_
_
_ AKI.05 -Effects of unbalanced RCS flow on in-core
3.3
1
average temperature, core imbalance, and quadrant
alfuntion
4
xpower
tilt
017
Reactor Coolant Pump (RCP) Malfunctions (Loss of
X 2.4.8 - Knowledge of how the event-based
3.7
1
RC Flow) / 4
emergency/abnormal operating procedures are used in
RC Foconjunction
with the symptom-based EOPs.
017
Reactor Coolant Pump (RCP) Malfunctions (Loss of
-
_
X
_
AK3.07 - Ensuring that S/G levels are controlled
4.2
RC Flow) /4
properly for natural circulation enhancement
026
Loss of Component Cooling Water (CCW) / 8
X 2.4.11 - Knowledge of abnormal condition procedures.
3.6
1
029
Anticipated Transient Without Scram (ATWS) I
X
-
_
_
_ EK2.06 - Breakers, relays, and disconnects
3.1*
1
040
Steam Line Rupture /4
_
_
_
X
AAI.24 - Main steam header pressure gauges
3.8
1
051
_
_
_
X _ AA2.02 - Conditions requiring reactor and/or turbine
4.1
trip
051
X
AA1.04 -Rod position
2.5*
1
I
Facility:
Watts Blar Nuclear Plant
nination Outline
Printed:
03/131<
Cmnrnanr,,
ond
An hnrrmn Plant Evolutions - Tier 1 / Group I
Form ES-401-3
....
.
A
.
ES - 4011
"rJ
mg-
-.-
_
Bu-
E/APE#
E/APE Name / Safety Function
K1 K2 K3 Al A2 G
KA Topic
Imp.
Points
057
Loss of Vital AC Electrical Instrument Bus / 6
x
AA2.12 - PZR level controller, instrumentation, and
3.7
1
heater indications
062
Loss of Nuclear Service Water / 4
_
_
-
_
x _ AA2.03 - The valve lineups necessary to restart the
2.9
SWS while bypassing the portion of the system causing
the abnormal condition
067
Plant Fire on Site / 9
X 2.2.30 - Knowledge of RO duties in the control room
3.3
during fuel handling such as alarms from fuel handling
area, communidation with fuel storage facility, systems
operated from the control room in support of fueling
operations, and supporting instrumentation.
067
Plant Fire on Site / 9
_
_
X
-
AK3.02 - Steps called out in the site fire protection plan,
3.3
FPS manual, and fire zone manual
068
Control Room Evacuation/ 8
X
-
_
-
AK2.03 - Controllers and positioners
3.1
069
Loss of Containment Integrity / 5
X
-
_
_
_
_ AKL .0 - Effect of pressure on leak rate
3.1
074
Inadequate Core Cooling/4
X
_
_
_
EK1.08 - Definition of subcooled liquid
3.1
076
High Reactor Coolant Activity / 9
_
-
X
AA1.04 - Failed fuel-monitoring equipment
3.4
Facility:
Watts Bar Nuclear Plant
PWRSRO(
nination Outline
Printed:
0311312(
I-
..
- .ani Abnnrmal Plmnt Evolutions - Tier 1/ Group 1
Form ES-401-3
ES - 4(1
"mergency
mu
-
E/APE #
E/APE Name / Safety Function
Ki K2 K3 Al A2 G KA Topic
Imp.
Points
E0i
Rediagnosis / 3
_
X
EK2.2 - Facility's heat removal systems, including
3.8
primary coolant, emergency coolant, the decay heat
removal systems, and relations between the proper
operation of these systems to the operation of the facility
EOi
Rediagnosis /3
_
_
-
X
EAI .3 - Desired operating results during abnormal and
3.8
emergency situations
E02
SI Termination /3
-
-
X
_
EK3.3 - Manipulation of controls required to obtain
3.9
desired operatirg results during abnormal; and
emergency situations
E6
Degraded Core Cooling /4
-
_
_
_
_
X 2.4.10 - Knowledge of annunciator response procedures.
3.1
E08
Pressurized Thermal Shock /4
X
_
_
_
_
EKI.3 - Annunciators and conditions indicating signals,
4.0
and remedial actions associated with the Pressurized
Thermal Shock
ElO
Natural Circulation with Steam Void in Vessel
X
-_ _ _
EK2.2 - Facility's heat removal systems, including
3.9
with/without RVLIS / 4
primary coolant, emergency coolant, the decay heat
operation of these systems to the operation of the facility
K/A Category Totals:
4
4
4 4
4
4
Group Point Total:
24
3
(
nination Outline
Printed:
03/13/K
Facility:
Watts Bar Nuclear Plant
CEeraanpr .nd Abnnrmal Plant Evolutions - Tier 1 / Group 2
Form ES-401-3
we Ann
r - 'WI
E/APE
E/APE Name / Safety Function
Ki
l
KA TGK0-Why
PZR
level may come back on
scale
if
4.4
1
008
Pressurizer (PZR) Vapor Space Accident (Relieft
AK3.01-WhPZlelmacoebkonslei4.
Valve Stuck Open) / 3
RCS is saturated
022
Loss of Reactor Coolant Makeup / 2
_
X
3.3
1
025
Loss of Residual Heat Removal System (RIRS) /4
_
_
_
_
X
_ AA2.07 - Pump cavitation
3.7
1
025
Loss of Residual Heat Removal System (RHRS) / 4
-
X
_
_
_
_ AK2.01 - RHR heat exchangers
2.9
1
027
Pressurizer Pressure Control (PZR PCS) Malfunction
X
-
_
_
_
_ AKI.03 - Latent heat of vaporization/condensation
2.9
1
/ 3
027
Pressurizer Pressure Control (PZR PCS) Malfunction
-
X
-
_
_ AK2.03 - Controllers and positioners
2.8
1
/ 3
032
Loss of Source Range Nuclear Instrumentation /7
_ _ _
-
X
_ AA2.09 - Effect of improper HV setting
2.9
1
038
Steam Generator Tube Rupture (SGTR) /3
-
_
-
X
EAI .08 - Core cooling monitor
3.8*
1
038
Steam Generator Tube Rupture (SGTR) / 3
X 2.4.2 - Knowledge of system set points, interlocks and
4.1
1
automatic actions associated with EOP entry conditions.
Note: The issue of setpoints and automatic safety
features is not specifically covered in the systems
sections.
054
Loss of Main Feedwater (MFW)/ 4
X
AA2.08 - Steam flow-feed trend recorder
3.3
1
I
Facility:
Wats Bar Nuclear Plant
nination Outline
Printed:
03/13/2
CC - AMl
Rmerrenev and Abnormal Plant Evolutions - Tier I / Group 2
Form ES-401-3
E/APE
E/APE Name I Safety Function
K_ K2 K3 Al A2 G KA Topic
Imp.
Points
060
Accidental Gaseous Radwaste Release /9
X
-
_
_
AKI.02 - Biological effects on humans of the various
3.1*
1
types of radiation, exposure levels that are acceptable
for personnel in a nuclear reactor power plant; the units
used for radiation intensity measurements and for
radiation exposure levels
060
Accidental Gaseous Radwaste Release /9
_
-
X
-
AK3.02 - Isolation of the auxiliary building ventilation
3.5*
1
061
Area Radiation Monitoring (ARM) System Alarms / 7
X 2.3.8 - Knowlege of the process for performing a
3.2
1
planned gaseous radioactive release.
061
Area Radiation Monitoring (ARM) System Alarms / 7
_
X
-
_
_
_ AK2.01 - Detectors at each ARM system location
2.6*
1
E03
LOCA Cooldown and Depressurization /4
X
_
_
_
_
_ EK1.I - Components, capacity, and function of
4.0
1
emergency systems
E05
Loss of Secondary Heat Sink / 4
X 2.4.41 - Knowledge of the emergency action level
4.1
thresholds and classifications.
K/A Category Totals:
3
3
2
2
3
3
Group Point Total:
16
2
Wau. jar Nuclear Plant
ruination Outline
Printed:
03/13/at
Facility:
FR - 4(01
Emerienev and Abnormal Plant Evolutions - Tier 1 / Group 3
Form ES-401-3
EIAPE #
E/APE Name / Safety Function
K1
K2 K3 Al A2 G KA Topic
Imp.
Points
028
Pressurizer (PZR) Level Control Malfunction /2
X
AA2.11 - Leak in PZR
3.6
056
_
_
_
_
-
X 2.4.21 - Knowledge of the parameters and logic used to
4.3
assess the status of safety functions including: 1.
Reactivity control; 2. Core cooling and heat removal;
3. Reactor coolant system integrity; 4. Containment
conditions; 5. Radioactivity release control.
E13
Steam Generator Overpressure /4
-
X
_ _ _
EK2.1 - Comptnents, and functions of control and
3.1
safety systems, including instrumentation, signals,
interlocs, taiure modes, ano automatic ano manual
features
K/A Category Totals:
0
1
f
0f
1
l
Group Point Total:
3
I
U$.
- Bar Nuclear Plant
ination Outline
Printed:
03/13t
'3
Facility:
we
401
PDInt Cvstnmt - Tier 2/
lrnun I
Form ES-401-3
- i- qUl
_ _ __
_
__
rl
Y A~ll
- .'--- -
rl
-
--
SysIEv #
System / Evolution Name
K1
K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic
Imp.
Points
001
Control Rod Drive System / I
X
A2.16 - Possible causes of mismatched control
3.8
1
rods
003
Reactor Coolant Pump System
X
K6.02 - RCP seals and seal water supply
3.1
1
(RCPS) /4
004
Chemical and Volume Control System
K4.08 - Hydrogen control in RCS
3.2
1
(CVCS)/ I
004
Chemical and Volume Control System
X
A 1.A4 - PZR pressure and level
4.1
(CVCS)/ I
013
Engineered Safety Features Actuation
K2.01 - ESFAS/safeguards equipment control
3.8
1
System (ESFAS) / 2
014
Rod Position indication System
K5.01 - Reasons for differences between RPIS
3.0
1
(RPIS) / I
and step counter
025
Ice Condenser System / 5
X 2.1.14 - Knowledge of system status criteria
3.3
1
which require the notification of plant
personnel.
_
_
_
_
_
_
025
Ice Condenser System / 5
X
K3.01 - Containment
3.8*
I
056
Condensate System /4
X
A2.04 - Loss of condensate pumps
2.8*
1
059
Main Feedwater (MFW) System /4
X 2.2.9 - Knowledge of the process for
3.3
1
determining if the proposed change, test or
experiment increases the probability of
occurrence or consequences of an accident
during the change, test or experiment.
I
Facility:
B3ar Nuclear PlantK
ination Outline
Printed:
03/10
'3
- 401
Plnnt Svstems - Tier 2 Groun I
Form ES-401-3
Sys/Ev #
System / Evolution Name
K1 K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic
Imp.
Points
059
Main Feedwater (MFW) System /4
X
A3.04 - Turbine driven feed pump
2.6*
1
061
Auxiliary / Emergency Feedwater
X
3.3
1
(AFW) System / 4
063
D.C. Electrical Distribution System /6
X
A4.02 - Battery voltage indicator
2.9
068
Liquid Radwaste System (LRS) /9
X
K1.07 - Sources of liquid wastes for LRS
2.9
1
068
Liquid Radwaste System (LRS) /9
X
K5.03 - Units of radiation, dose, and dose rate
2.6
1
071
Waste Gas Disposal System (WODS)
X
K3.04 - Ventilation system
2.9
1
/ 9
071
Waste Gas Disposal System (WGDS)
X
K4.06 - Sampling and monitoring of waste gas
3.5*
/9
release tanks
072
Area Radiation Monitoring (ARM)
X
KI 02 - Containment isolation
3.9
I
System / 7
072
Area Radiation Monitoring (ARM)
Al .0l - Radiation levels
3.6
1
__ _
_
_ System !/ 7
__
_
_
_
_
_
_
_
__
_
_
_
_
_
_
_I__
_
_
_
_
_
_
K/A Category Totals:
2
2
2
2
2
1
2
2
1
1
2
Group Point Total:
19
2
(
ination Outline
Printed:
03/O (
Facility:
Watts Bar Nuclear Plant
ES - 4AM
Plant Systems - Tier 2/ Group 2
Form ES-401-3
Sys/Ev #
System / Evolution Name
K1
K2 K3 K4 K5 K6 Al A2 A3
A4 G KA Topic
Imp.
Points
002
Reactor Coolant System (RCS) / 2
x
A4.04 - The filling/draining of LPI pumps
2.6
1
during refueling
011
Pressurizer Level Control System
_
K4.07 - Cold-calibrated channel
3.2
(PZR LCS) /2
012
X
K4.05 - Spurious trip protection
2.9
1
016
Non-Nuclear Instrumentation System
X
K5.01 - Separation of control an protection
2.8*
1
(NNIS) /7
circuits
028
Hydrogen Recombiner and Purge
X
K2.01 - Hydrogen recombiners
2.8*
1
Control System (HRPS) / 5
029
Containment Purge System (CPS) / 8
X
-
A3.01 - CPS isolation
4.0
1
034
Fuel Handling Equipment System
X 2.2.6 - Knowledge of the process for making
3.3
1
(FHES) /8
changes in procedures as described in the safety
analysis report.
035
Steam Generator System (S/GS) / 4
X 2.4.22 - Knowledge of the bases for prioritizing
4.0
safety functions during abnormal/emergency
operations.
055
Condenser Air Removal System
X-
KI.06 - PRM system
2.6
1
(CARS) / 4
062
A.C. Electrical Distribution System /6
A2.07 - Consequences of opening a disconnect
3.4*
_
I I I I
under load
Facility:
Wat., Bar Nuclear Plant
'nation Outline
Printed:
03/13
Plant Cvstnms - Tielr 7/ Cronn
Form ES-401-3
are And
EN - '.ui
Sys/Ev # System / Evolution Name
KI K2 K3 K4 K5 K6 Al
A2 A3 A4 G KA Topic
Imp.
Points
073
Process Radiation Monitoring (PRM)
X
A.01 - Radiation levels
3.5
1
System / 7
073
Process Radiation Monitoring (PRM)X
-
_
A2.02 - Detector failure
3.2
1
System / 7
075
X
K2.03 - Emergency/essential SWS pumps
2.7*
1
075
XK3.
7 -ESFAS
3.5*
086
Fire Protection System (FPS) /8
_
K6.04 - Fire, smoke, and heat detectors
2.9
1
086
Fire Protection System (FPS) / 8
X
A3.01 - Starting mechanisms of fire water
3.3
pumps
103
Containment System / 5
X
_K3.03
- Loss of containment integrity under
4.1
1
_
_
_
_
_
_
_
_
_
_
_
refueling operations
K/A Category Totals:
1
2
2
2
1
1
1
2
2
1
2
Group Point Total:
17
2
Wats Bar Nuclear Plant
nation Outline
Printed:
03/13(
Facility:
Plont qvctemQ - Tier 2 I Croun 3
Form ES-401-3
Z3 - qui
Sys/Ev # System / Evolution Name
K1
K2
1K3
(4 K5 K6 JAl lA2 JA3 lA4 lG KATopic
Imp.
Points
008
Component Cooling Water System
X 2.1.12 - Ability to apply technical specifications 4.0
1
(CCWS) /8
for a system.
041
Steam Dump System (SDS) and
K6.03 -Controller and positioners, including
2.9
1
Turbine Bypass Control / 4
ICS, S/G, CRDS
076
Service Water System (SWS) / 4
_
K2.04 - Reactor building closed cooling water
2.6*
I
078
Instrument Air System (lAS) / 8
X
A3.01 -Air pressure
3.2
1
K/A Category Totals:
0
1
0
0
0
1
0
0
1
0
1
Group Point Total:
4
I
(
Generic Knowledge and Abilities outline (I ier 5)
Printed: 03/13/2003(
Form ES-401-5
Facility:
Watts Bar Nuclear Plant
Generic Category
KYA
KA Topic
Imp.
Points
Conduct of Operations
2.1.3
Knowledge of shift turnover practices.
3.4
2.1.7
Ability to evaluate plant performance and make operational judgments based on operating
4.4
1
characteristics, reactor behavior, and instrument interpretation.
2.1.25
Ability to obtain and interpret station reference materials such as graphs, monographs, and
3.1
1
tables which contain performance data.
2.1.34
Ability to maintain primary and secondary plant chemistry within allowable limits.
2.9
I
Category Total:
4
Equipment Control
2.2.20
Knowledge of the process for managing troubleshooting activities.
3.3
1
2.2.28
Knowledge of new and spent fuel movement procedures.
3.5
1
2.2.31
Knowledge of procedures and limitations involved in initial core loading.
2.9*
1
2.2.33
Knowledge of control rod programming.
2.9
1
Category Total:
4
Radiation Control
2.3.2
Knowledge of facility ALARA program.
2.9
1
2.3.3
Knowledge of SRO responsibilities for auxiliary systems that are outside the control room
2.9
(e.g., waste disposal and handling systems).
2.3.9
Knowledge of the process for performing a containment purge.
3.4
1
2.3.10
Ability to perform procedures to reduce excessive levels of radiation and guard against
3.3
1
_
personnel exposure.
_
Category Total:
4
7
Generic Knowledge ann ADfilues uulmne t(iler i)
(V
tion Outline
Printed: 03/13/2003(
Form ES-401-5
Facility:
Watts Bar Nuclear Plant
Generic Category
KA Topic
Imp.
Points
Emergency Procedures/Plan
2.4,2e Knowledge of operaaondl iplliualOmI
EOPa
ug-
autions,-and-notes.,
4.0
2.4.21
Knowledge of the parameters and logic used to assess the status of safety functions
4.3
including: 1. Reactivity control; 2. Core cooling and heat removal; 3. Reactor coolant
system integrity; 4. Containment conditions; 5. Radioactivity release control.
2.4.27
Knowledge of fire in the plant procedure.
3.5
2.4.29
Knowledge of the emergency plan.
4.0
2.4.50
Ability to verify system alarm setpoints and operate controls identified in the alarm
3.3
response manual.
Category Total:
5
Generic Total:
17
2
Written Examination Statistics:
Description
No. Questions
SRO Only
31
Knowledge/Fundamental
33
Comprehensive/Analysis
67
Bank Questions
56
Modified Questions
10
New Questions
34
..