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
ES-401 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.
PWR SRO( mnination Outline Printed: 03/1310
Facility: Watts Bar Nuclear Plant
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
alfuntion xpower 4 averagetilttemperature, core imbalance, and quadrant
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 Loss of Condenser Vacuum /4 _ _ _ X _ AA2.02 - Conditions requiring reactor and/or turbine 4.1
trip
051 Loss of Condenser Vacuum /4 X AA1.04 -Rod position 2.5* 1
I
PWR SRO( nination Outline Printed: 03/131<
Facility: Watts Blar Nuclear Plant
. A . Cmnrnanr,, ond An hnrrmn Plant Evolutions - Tier 1 / Group I Form ES-401-3
ES - 4011 mg-"rJ _ Bu-
....
-.-
K1 K2 K3 Al A2 G KA Topic Imp. Points
E/APE# E/APE Name / Safety Function 3.7 1
057 Loss of Vital AC Electrical Instrument Bus / 6 x AA2.12 - PZR level controller, instrumentation, and
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
X 2.2.30 - Knowledge of RO duties in the control room 3.3
067 Plant Fire on Site / 9
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.
_ _ X AK3.02 - Steps called out in the site fire protection plan, 3.3
067 Plant Fire on Site / 9 -
FPS manual, and fire zone manual
X _ AK2.03 - Controllers and positioners 3.1
068 Control Room Evacuation/ 8 - -
X _ _ _ _ AKL .0 - Effect of pressure on leak rate 3.1
069 Loss of Containment Integrity / 5 -
X _ _ _ EK1.08 - Definition of subcooled liquid 3.1
074 Inadequate Core Cooling/4
_ X AA1.04 - Failed fuel-monitoring equipment 3.4
076 High Reactor Coolant Activity / 9 -
PWRSRO( nination Outline Printed: 0311312(
Facility: Watts Bar Nuclear Plant
I- .. - .ani Abnnrmal Plmnt Evolutions - Tier 1/ Group 1 Form ES-401-3
ES - 4(1 mu
"mergency -
E/APE Name / Safety Function Ki K2 K3 Al A2 G KA Topic Imp. Points
E/APE #
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
X _ EK3.3 - Manipulation of controls required to obtain 3.9
E02 SI Termination /3 - -
desired operatirg results during abnormal; and
emergency situations
Degraded Core Cooling /4 _ _ _ _ X 2.4.10 - Knowledge of annunciator response procedures. 3.1
E6 -
Pressurized Thermal Shock /4 X _ _ _ _ EKI.3 - Annunciators and conditions indicating signals, 4.0
E08
and remedial actions associated with the Pressurized
Thermal Shock
X _ EK2.2 - Facility's heat removal systems, including 3.9
ElO Natural Circulation with Steam Void in Vessel -
with/without RVLIS / 4 primary coolant, emergency coolant, the decay heat
operation of these systems to the operation of the facility
4 4 4 4 4 4 Group Point Total: 24
K/A Category Totals:
3
( PWR SRO( nination Outline Printed: 03/13/K
Facility: Watts Bar Nuclear Plant
Ann CEeraanpr .nd Abnnrmal Plant Evolutions - Tier 1 / Group 2 Form ES-401-3
we
r - 'WI
E/APE E/APE Name / Safety Function Ki l KA TGK0-Why on
level may come back PZR if 4.4
scale 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 AA .08 - VCT level 3.3 1
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
025 -
X _ _ _ _ AKI.03 - Latent heat of vaporization/condensation 2.9 1
027 Pressurizer Pressure Control (PZR PCS) Malfunction -
/3
X _ _ AK2.03 - Controllers and positioners 2.8 1
027 Pressurizer Pressure Control (PZR PCS) Malfunction - -
/3
X _ AA2.09 - Effect of improper HV setting 2.9 1
032 Loss of Source Range Nuclear Instrumentation /7 _ -
038 Steam Generator Tube Rupture (SGTR) /3 - _ - X EAI .08 - Core cooling monitor 3.8* 1
X 2.4.2 - Knowledge of system set points, interlocks and 4.1 1
038 Steam Generator Tube Rupture (SGTR) / 3
automatic actions associated with EOP entry conditions.
Note: The issue of setpoints and automatic safety
features is not specifically covered in the systems
sections.
X AA2.08 - Steam flow-feed trend recorder 3.3 1
054 Loss of Main Feedwater (MFW)/ 4
I
PWR SRO( nination Outline Printed: 03/13/2
Facility: Wats Bar Nuclear Plant
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
PWR SRO( ruination Outline Printed: 03/13/at
Facility: Wau. jar Nuclear Plant
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 Loss of Offsite Power /6 _ _ _ _ - 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
PWR SRO E ination Outline Printed: 03/13t '3
Facility: U$. - Bar Nuclear Plant
we
- i-
401
qUl _ _ __ _ __ rl
PDInt Cvstnmt - Tier 2/
.'--- -
Y ; A~ll
lrnun I
- rl --
Form ES-401-3
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 A1.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
PWR SRO F( ination Outline Printed: 03/10 '3
Facility: B3ar Nuclear PlantK
VP - 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 K2.01 - AFW system MOVs 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
( PWR SRO E( 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 Reactor Protection System / 7 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
PWR SRO E 'nation Outline Printed: 03/13
Facility: Wat., Bar Nuclear Plant
are - And Plant Cvstnms - Tielr 7/ Cronn Form ES-401-3
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 Circulating Water System / 8 X K2.03 - Emergency/essential SWS pumps 2.7* 1
075 Circulating Water System / 8 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
nation Outline Printed: 03/13(
Facility: Wats Bar Nuclear Plant
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)
Printed: 03/13/2003(
(V
Form ES-401-5
Facility: Watts Bar Nuclear Plant
Generic Category KA 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
..