ML030840259
| ML030840259 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/09/2002 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Keenan J Carolina Power & Light Co |
| References | |
| 50-324/03-301, 50-325/03-301 | |
| Download: ML030840259 (26) | |
See also: IR 05000325/2003301
Text
Final Submittal
BRUNSWICK EXAM
50-2003-301
50-325 & 50-324
FEBRUARY 10 - 14 & 19, 2003
FINAL SAMPLE PLANS I OUTLINES
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, S1)
Facility: Brunswick Date of Exam: 2/19/03 Exam Level: SRO
K/A Category Points
Tier Group Point
K K K K K A A A A IG Total
1 2 3 4 5 6 1 2 131 4
1. 1 4 3 44 26
Emergency & - 1
Abnormal 2 2 3 3
Plant
Evolutions Tier 6 6 61 43
Totals
2. 1 2 2 1 2 2 2 2 2 2 3 23
Plant 2 2 1 1 2 1 0 1 2 1 1 1 13
Systems 3 1 1 1 1 4
Tier 4 4 2 5 3 2 4 5 3 4 4 40
Totals I I
3. Generic Knowledge and Abilities
_ _ _ I_
I Cat 1 Cat 2
12 Cat 3 Cat 4 1
1_
14 4 1 2 7
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 by +/-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 SRO 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.
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier l/Group 1
E/APE # / Name I Safety Function K1 K2 KQ Al A2 G K/A Topic(s) Imp. Points
295003 Partial or Complete Loss of AC Pwr /6 02 2.1.10 AK1.02 Knowledge of the operational implications fo the following 3.1/3.4 1
concepts as they apply to PARTIAL OR COMPLETE LOSS OF
A.C. POWER: Load shedding.
2.1.10 Knowledge of conditions and limitations in the facility 2.7/3.9 1
license.
295006 SCRAM / 1 05 2.2.20 AA2.05 Ability to determine and/or interpret the following as 4.6/4.6 1
they apply to SCRAM : Whether a reactor SCRAM has occurred
2.2.20 Knowledge of the process for managing troubleshooting 2.2/3.3 1
activities.
295007 High Reactor Pressure / 3 06 AK3.06 Knowledge of the reasons for the following responses as 3.7/3.8 1
they apply to HIGH REACTOR PRESSURE : Reactor/turbine
pressure regulating system operation.
295009 Low Reactor Water Level /2 05 2.4.1 AK1.05 Knowledge of the operational implications of the following 3.3/3.4 1
concepts as they apply to LOW REACTOR WATER LEVEL:
Natural circulation.
2.4.1 Knowledge of EOP entry conditions and immediate action 4.3/4.6 1
steps. (SRO ONLY)
295010 High Drywell Pressure / 5 01 06 AA1.01 Ability to operate and/or monitor the following as they 3.4/3.5 1
apply to HIGH DRYWELL PRESSURE : Safety/relief valve
operation. 3.6/3.6 1
AA2.06 Ability to determine and/or interpret the following as they
a I to HIGH DRYWELL PRESSURE: Drywell temperature.
(SOONLY)
295013 High Suppression Pool Temp. / 5 03 02 AK1.03 Knowledge of the operational implications of the following 3.0/3.3 1
concepts as they apply to HIGH SUPPRESSION POOL
TEMPERATURE: Localized heating.
AA2.02 Ability to determine and/or inter pret the following as they 3.2/3.5 1
apply to HIGH SUPPRESSION POOL TEMPERATURE: Localized
heating/stratification. (SRO ONLY)
295014 Inadvertent Reactivity Addition / 1 03 03 AA2.03 Ability to determine and/or inter pret the following as they 4.0/4.3 1
apply to INADVERTENT REACTIVITY ADDITION: Cause of
reactivity addition.
AK2.03 Knowledge of the interrelations between INADVERTENT 3.3/3.4 1
REACTIVITY ADDITION and the following: Fuel temperature.
295015 Incomplete SCRAM / 1 02 AK1.02 Knowledge of the operational implications of the following 3.9/4.1 1
concepts as they apply to INCOMPLETE SCRAM: Cooldown
effects on reactor power.
295016 Control Room Abandonment / 7 01 AK3.01 Knowledge of the reasons for the following responses as 4.1/4.2 1
theyapply to CONTROL ROOM ABANDONMENT: Reactor
SCRM
295017 High Off-site Release Rate / 9 2.1.2 G2.1.2 Knowledge of operator responsibilities during all modes of 3.0/4.0 1
plant operation.
Accidents Cooling Mode / 88
Refueling Acci
295023 Refuelin 02 AA2.02 Ability to determine and/or interpret the following as they 3.4/3.7 1
apply to REFUELING ACCIDENTS : Fuel pool level.
295024 High Drywell Pressure /5 01 EK3.01 Knowledge of the reasons for the following responses as 3.6/4.0 1
they apply to HIGH DRYWELL PRESSURE : Drywell spray
operation.
295025 High Reactor Pressure / 3 02 2.4.4 EAI.02 Ability to operate and/or monitor the following as they 3.8/3.8 1
apply to HIGH REACTOR PRESSURE: Reactor/turbine pressure
rer u atinn vsstem.
G .4.4 A iiI to recognize abnormal indications for system 4.0/4.3 1
operating parameters which are entry-level conditions for
emergency and abnormal operating procedures. (SRO ONLY)
295026 Suppression Pool High Water Temp. 1 5 04 EK2.04 Knowledge of the interrelations between SUPPRESSION 2.5/2.8 1
POOL HIGH WATER TEMPERATURE and the following:
SPDS/ERIS/CRIDS/GDS.
295027 High Containment Temperature / 5 Does not apply to Brunswick. Mark Ill containment only.
i
295030 Low Suppression Pool Water Level / 5 05 EAI.05 Ability to operate and/or monitor the following as they 3.5/3.5 1
apply toLOW SUPPRESSIONPOOL WATER LEVEL:_HPCI.
295031 Reactor Low Water Level / 2 2.1.1 G2.1.1 Knowledge of conduct of operations requirements. 3.7/3.8 1
295037 SCRAM Condition Present and Power 05 EK2.05 Knowled e of the interrelations between SCRAM 4.0/4.1 1
Above APRM Downscale or Unknown / 1 CONDITION PRESENT AND REACTOR POWER ABOVE APRM
DOWNSCALE OR UNKNOWN and the following: CRD hydraulic
system.
295038 High Off-site Release Rate / 9 . 03 EA2.03 Ability to determine and/or interpret the following as they 3.5/4.3 1
ap1
A6R to HIGH OFF-SITE RELEASE RATE: Radiation levels.
ONLY)
500000 High Containment Hydrogen Conc./ 5 01 EA2.01 Ability to determine and / or inter pret the following as they 3.1/3.5 1
apply to HIGH PRIMARY CONTAINMENT HYDROGEN
CONCENTRATIONS: Hydrogen monitoring system availability.
K/A Category Totals: 14 13 13 13 1 I Group PointTotal: 1 26
ES-401 BWR SRO Examination Outline Form ES-401-1 (R.8 S1)
Emergency and Abnormal Plant Evolutions - Tier I/Group 2
E/APE # I Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points
295001 Partial or Complete Loss of Forced Core 02 AK2.02 Knowledge of the interrelations between PARTIAL OR 3.2/3.2 1
Flow Circulation / 1 &4 COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION
and the following: Nuclear boiler instrumentation.
295002 Loss of Main Condenser Vacuum / 3 08 02 AK2.08 Knowledge of the interrelations between LOSS OF MAIN 3.1/3.2 2
CONDENSER VACUUM and the following: Condenser circulating
water system.
AK3.02 Knowledge of the reasons for the following responses as 3.4/3.4
they apply to LOSS OF MAIN CONDENSER VACUUM : Turbine
trp.
295004 Partial or Total Loss of DC Pwr / 6 02 AA2.02 Abilityto determine and/or interpret the following as they 3.5/3.9 1
apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER:
Extent of partial or complete loss of D. C. power.
295005 Main Turbine Generator Trip / 3 05 AA1.05 Ability to operate and/or monitor the following as they 3.6/3.6 1
apply to MAIN TURBINE GENERATOR TRIP: Reactor/turbine
pressure regulating system.
295008 High Reactor Water Level / 2 04 AK3.04
t Knowledge of the reasons for the following responses as 3.3/3.5 1
hey aply to HIGH REACTOR WATER LEVEL: Reactor feed
pump rap: Plant-Specific.
295011 High Containment Temperature / 5 Does not apply to Hatch. For Mark Ill containment only.
295012 High Drywell Temperature / 5 02 AAI.02 Ability to operate and/or monitor the following as they 3.8/3.8 1
apply to HIGH DRYWELL TEMPERATURE: Drywell cooling
system.
295018 Partial or Total Loss of CCW / 8
295019 Partial or Total Loss of Inst. Air / 8 01 AA1.01 Ability to operate and/or monitor the following as they 3.5/3.3 1
apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:
Backup air supply.
295020 Inadvertent Cont. Isolation / 5 & 7 06 AA2.06 Ability to determine and/or interpret the following as they 3.4/3.8 1
apply to INADVERTENT CONTAINMENT ISOLATION: Cause of
isolation.
295021 Loss of Shutdown Cooling / 4 01 01 AK2.01 Knowledge of the interrelations between LOSS OF 3.6/3.7 2
SHUTDOWN COOLING and the following: Reactor water
temperature.
AA2.01 Ability to determine and/or interpret the following as 3.5/3.6
they apply to LOSS OF SHUTDOWN COOLING: Reactor water
heatupfcooldown rate.
295022 Loss of CRD Pumps / 1 2.1.30 2.1.30 Ability to locate and operate components / including local 3.9/3.4 1
controls.
295028 High Drywell Temperature / 5 01 EK1.01 Knowledge of the operational implications of the following 3.513.7 -1
concepts as they apply to HIGH DRYWELL TEMPERATURE:
Reactor water level measurement.
295029 High Suppression Pool Water Level / 5 Not selected.
295032 High Secondary Containment Area 01 EK3.O1 Knowledge of the reasons for the following responses as 3.5/3.8 1
Temperature / 5 they apply to HIGH SECONDARY CONTAINMENT AREA
TEMPERATURE: Emergency/normal depressurization.
295033 High Secondary Containment Area 2.3.10 2.3.10 Ability to perform procedures to reduce excessive levels of 2.9/3.3 1
Radiation Levels/ 9 radiation and guard against personnel exposure. (SRO ONLY)
295034 Secondary Containment Ventilation High 02 EKI.02 Knowledge of the operational implications of the following 4.1/4.4 1
Radiation / 9 concepts as they apply to SECONDARY CONTAINMENT
VENTILATION HIGH DIATION: Radiation release.
295035 Secondary Containment High Differential
Pressure / 5
295036 Secondary Containment High Sump/Area Not selected.
Water Level / 5
600000 Plant Fire On Site / 8 06 AA2.06 Ability to determine and interpret the following as they 2.5/2.8 1
apply to PLANT FIRE ON SITE: Need for pressurizing control
room (recirculation mode). (SRO ONLY)
K/A Category Point Totals: j21 3 13 13 j 3 I Group Point Total: 1 1
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, S)
Plant Systems - Tier 2/Group 1
System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points
201005 RCIS Applies to BWR 6 - N/A
202002 Recirculation Flow Control 06 K4.06 Knowledge of 3.1/3.1 1
REClRCULATION FLOW
CONTROL SYSTEM design
feature(s) and/or interlocks which
provide for thefollowin
ecirculation pump NPSH. i
203000 RHR/LPCI: Injection Mode 04 A1.04 Ability to predict and/or 3.6/3.6 1
monitor change in parameters
associated with operating the
RHRPLPCI: INJECTION MODE
controls including: System pressure.
206000 HPCI 08 K5.08 Knowledge of the operational 3.0/3.2 1
implications of tIe following
concepts as they apply to HIGH
PRESSURE COOLNT INJECTION
SYSTEM: Vacuum breaker
operation.
207000 Isolation (Emergency) Condenser Not applicable to Brunswick.
209001 LPCS 03 K,2.03 Knowledge of the electrical 2.9/3.1 1
power supplies to the following:
Initiation logic.
209002 HPCS -Not applicable to Brunswick.
211000 SLC 08 A3.08 Ability to monitor automatic 4.2/4.2 1
operations of the STANDBY LIQUID
CONTROL SYSTEM including:
System initiation: Plant-Specific.
212000 RPS 04 K6.04 Knowledge of the effect that a 2.8/3.1 1
loss or malfunction of the following
will have on the REACTOR
PROTECTION SYSTEM: D.C.
electrical distribution.
215004 Source Range Monitor 2.2.1 G2.2.1 Ability to perform pre-startup 3.7/3.6 1
procedures for the facility / including
operating those controls associated
with plant equipment that could
affect reactivity.
215005 APRM / LPRM 06 A4.06 Ability to manually operate 3.6/3.8 1
and/or monitor in the control room:
Verification of proper functioning /
operability.
216000 Nuclear Boiler Instrumentation 01 K2.01 Knowledge of electrical power 2.8/2.8 1
supsplies to the following: Analog trip
I I I __I _system.
217000 RCIC 01 2.1.28 K1.01 Knowledge of the physical 3.5/3.5 1
connections and/or cause-effect
relationships between REACTOR
CORE ISOLATION COOLING
SYSTEM (RCIC) and the following:
Condensate storage and transfer
- '2stem.
.1.28 Knowledge of the purpose 3.213.3 1
-and function of major system
components and controls.
218000 ADS 02 A4.02 Ability to manually operate 4.214.2 1
and/or monitor in the control room:
ADS logic initiation.
223001 Primary CTMT and Auxiliaries 01 2.1.7 A2.01 Ability to (a) predict the 4.3/4.4 2
impacts of the following on the
SYSTEM AND AUXILIARIES; and
(b) based on those predictions, use
procedures to correct, control, or
mitigate the consequences of those
abnormal conditions or operations:
2.1.7 Ability to evaluate plant 3.7/4.4
performance and make operational
judgments based on operating
characteristics / reactor behavior/
and instrument interpretation.
223002 PCIS/Nuclear Steam Supply Shutoff 07 02 K1.07 Knowledge of the physical 3.4/3.6 1
connections and/or cause-effect
relationships between PRIMARY
CONTAINMENT ISOLATION
SYSTEM/NUCLEAR STEAM
SUPPLY SHUT-OFF and the
following: Reactor core isolation
cooling. 3.5/3.5
A3.02 Ability to monitor automatic I
operation o the PRIMARY
CONTAINMENT ISOLATION
SYSTEM/NUCLEAR STEAM
SUPPLY SHUT-OFF including:
valve closure.
226001 RHR/LPCI: CTMT Spray Mode
239002 SRVs 01 A1.01 Ability to predict and/or 3.3/3.4
monitor changes in parameters
associated with operating the
RELIEF/SAFETY VALVES controls
including: Tail pipe temperature.
241000 Reactor/Turbine Pressure Regulator 05 K6.05 Knowledge of the effect that a 3.4/3.4
loss or malfunction of the following
will have on the
REACTOR/TURBINE PRESSURE
REGULATING SYSTEM: Condenser
vacuum.
204000 Reactor Water Cleanup System 06 K1.06 Knowledge of the physical 2.8/2.8
connections and/or cause-effect
relationships between REACTOR
WATER CLEANUP SYSTEM and
the following: Main condenser
261000 SGTS 04 K3.04 Knowledge of the effect that 3.1/3.1 1
a loss or malfunction of the
STANDBY GAS TREATMENT
SYSTEM will have on following:
High pressure coolant injection
system: Plant-Specific
262001 AC Electrical Distribution 03 05 A2.03 Ability to (a) predict the 3.9/4.3
impacts of the following on the A.C.
ELECTRICAL DISTRIBUTION; and
(b) bases on those predictions, use
procedures to correct, control, or
mitigate the consequences of those
abnormal conditions or operations:
Loss of off-site power.
A4.05 Ability to manually operate
and/or monitor in the control room: 3.4/3.4 1
Voltage, current, power, frequency
and A.C. buses.
264000 EDGs 05 06 K4.05 Knowledge of EMERGENCY 3.2/3.5 2
GENERATORS (DIESEL/JET)
design feature(s) and/or interlocks
which provide for the following:
Load shedding and sequencing
K5.06 Knowledge of the operational 3.4/3.5
implications of the following
oncepts as the appl to
EMERGENCY ENETORS
I (DIESEL/JET): Load sequencing.
290001 Secondary CTMT Not selected.
K/A Category Point Totals: 1212 1 1 13 12 12 1212 12 1 13
2 Group Point Total: 23
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, Si)
Plant Systems - Tier 2/Group 2
System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KIA Topic(s) Imp. Points
201001 CRD Hydraulic Not selected.
201002 RMCS 02 03 K4.02 Knowledge of REACTOR 3.5/3.5 2
MANUAL CONTROL SYSTEM
designfeature(s) and/or interlocks which
provide for the following: Control rod
blocks
A3.03 Ability to monitor automatic 3.2/3.2
operations of the REACTOR MANUAL
CONTROL SYSTEM including: rod drift
alarm.
201004 RSCS Does not apply to Browns Ferry.
201006 RWM Not selected.
202001 Recirculation 07 Al.07 Ability to predict and/or monitor 2.7/2.8
changes in parameters associated with
operating the RECIRCULATION
SYSTEM controls including:
Recirculation pump speed.
204000 RWCU 06 04 K1.06 Knowledge of the physical 2.8/2.8 2
connections and/or cause- effect
relationships between REACTOR
WATER CLEANUP SYSTEM and the
following: Main condenser.
K5.04 Knowledge of the operational 2.7/2.7
implications of the following concepts as
the applyto REACTOR WATER
CLEANUP SYSTEM: Heat exchanger
operation.
214000 RPIS 01 K4.01 Knowledge of ROD POSITION 3.0/3.1
INFORMATION SYSTEM design
feature(s) and/or interlocks which
provide for the following: Reed switch
0 _a ions.
215002 RBM Not selected.
215003 IRM Not selected.
219000 RHR/LPCI: Torus/Pool Cooling Mode 03 A2.03 Ability to (a) predict the impacts 3.1/3.2'
of the following on the RHRJLPCI:
TORUS/SUPPRESSION POOL
COOLING MODE; and (b) based on
those predictions, use procedures to
correct, control, or mitigate the
consequences of those abnormal
conditions or operations: Valve
closures.
230000 RHR/LPCI: Torus/Pool Spray Mode Changed to 272000K2.05 due to KA
selected was the same as
226001 K2.02.
234000 Fuel Handling Equipment
239003 MSIV Leakage Control Does not apply to Hatch.
245000 Main Turbine Gen. and Auxiliaries 10 A4.1O Ability to manually operate and/or 2.6/2.6
monitor in the control room: Hydrogen
gas pressure.
259001 Reactor Feedwater 07 A2.07 Ability to(a) predict the impacts of 3.7/3.8
the following on the REACTOR
FEEDWATER SYSTEM; and (b) based
on those predictions, use procedures to
correct, control, or mitigate the
consequences of those abnormal
conditions or operations: Reactor water
level control malfunctions.
262002 UPS (AC/DC) Not selected.
263000 DC Electrical Distribution 01 K2.01 Knowledge of electrical poser 3.1/3.4
supplies to the following: Major D.C.
loads.
271000 Offgas Not selected.
272000 Radiation Monitoring 02 K1.02 Knowledge of the physical 3.2/3.5
connections and/or cause-effect
relationships between RADIATION
MONITORING SYSTEM and the
following: Offgas system.
286000 Fire Protection Not selected.
290003 Control Room HVAC Not selected.
300000 Instrument Air 02 K3.02 Knowledge of the effect that a 3.3/3.4
loss or malfuntion of the INSTRUMENT
AIR SYSTEM will have on the following:
Systems having pneumatic valves and
controls.
400000 Component Cooling Water 2.2.18 G2.2.18 Knowledge of the process of 2.3/3.6
managing maintenance activities during
shutdown operations. (SRO ONLY)
K/A Category Point Totals: 1 1111 1-211101112111112 I Group Point Total: 113
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, Si)
Plant Systems - Tier 2/Group 3
System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points
201003 Control Rod and Drive Mechanism Not selected.
215001 Traversing In-core Probe Not selected.
233000 Fuel Pool Cooling and Cleanup Not selected.
239001 Main and Reheat Steam 16 K33.16 Knowledge of the effect that a 3.6/3.6 1
loss or malfunction of the MAIN AND
REHEAT STEAM SYSTEM will have on
the following: Relief/safety valves.
256000 Reactor Condensate 01 K2.01
to Knowledge
the system of the power supplies
pumps 2.7/2.8
___
1
____
268000 Radwaste 01 A1.01 Ability to predict and/or monitor 2.7/3.1 1
changes in parameters associated with
operating the RADWASTE controls
including: Radiation level.
288000 Plant Ventilation 02 A2.02 Ability to (a) prediect the impacts 3.4/3.6 1
of the following on the PLANT
VENTILATION SYSTEMS; and (b)
based on those predictions, use
procedures to correct, control, or
mitigate the consequences of those
abnormal conditions or operations: LOW
REACTOR
(SRO ONLY)WATER LEVEL. _______
290002 Reactor Vessel Internals Not selected.
K/A Category Point Totals: 1 1 1 1 Group Point Total: 4
Plant-Specific Priorities
System / Topic Recommended Replacement for... Reason Points
Plant-Specific Priority Total (limit 10):
NUREG-1021, Revision 8, Supplement 1 18 of 46
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5
Facility: Brunswick Date of Exam: Exam Level: SRO
Category K/A # Topic Imp. Pts.
2.1.1 Knowledge of conduct of operations requirements. 3.7/3.8 1
2.1.10 Knowledge of conditions and limitations in the facility 2.7/3.9 1
license
Conduct of
Operations 2.1.28 Knowledge of the purpose and function of major 3.2/3.3 1
system components and controls.
2.1.12 Ability to apply technical specifications for a system. 2.9/4.0 1
Total
2.2.3 Knowledge of the design / procedural / and operational 3.1/3.3
differences between units.
2.2.14 Knowledge of the process for making configuration 2.1/3.0 1
Equipment - changes. (SRO ONLY)
Control 2.2.17 Knowledge of the process for managing maintenance 2.3/3.5 1
activities during power operations. (SRO ONLY)
2.2.27 Knowledge of the refueling process. (SRO ONLY) 2.6/3.5 1
Total
2.3.1 Knowledge of the process for performing a 2.8/3.0 1
containment purge.
2.3.4 Knowledge of radiation exposure limits and 2.5/3.1 1
contamination control / including permissible levels in
Radiation excess of those authorized.
Control
Total
2.4.1 Knowledge of EOP entry conditions and immediate 4.3/4.6 1
action steps.
2.4.2 Knowledge of system set points / interlocks and 3.9/4.1 1
Emergency automatic actions associated with EOP entry conditions.
Procedures/
Plan 2.4.3 Ability to identify post-accident instrumentation. 3.5/3.8 1
2.4.11 Knowledge of abnormal condition procedures. 3.4/3.6 1
2.4.18 Knowledge of the specific basis for EOPs. 2.7/3.6 1
2.4.27 Knowledge of fire in the plant procedure. (SRO ONLY) 3.0/3.5 1
2.4.48 Ability to interpret control room indication. (SRO ONLY) 3.5/3.8 1
Total
Tier 3 Point Total (SRO) 17
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, S1)
ES-401W 1 I
Facility: Brunswick Date of Exam: 2/19/03 Exam Level: RO
K/A Category Points
Tier Group Point
KTK K K K K A A A A G Total
1 212 3 4 5 6 1 2 3 4 *
1. 1 2 2 2 3 2 2 13
Emergency &
2 4 3 3 3 3 3 19
Abnormal
Plant 3 1 1 1 1 4
Evolutions Tier 7 6 6 6 6 5 36
Totals
1 3 2 2 15 2 3= 2 1 3 13 3 29
2.
Plan 2 2 2 3 1 1 1 1 3 2 2 1 19
Plant ___
Systems 3 1 1 1 3
Tier 5 5 5 6 3 4 4 5 5 5 4 51
Totals III
3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4
3 3 2 35
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 by +/-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 SRO 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.
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 1
E/APE #/ Name / Safety Function K K K A A G K/A Topic(s) Imp. Poin
1 2 3 1 2 Its
295005 Main Turbine Generator Trip /3 05 AA1.05 Ability to operate and/or monitor the following as they 3.6/3.6 1
apply to MAIN TURBINE GENERATOR TRIP: Reactor/turbine
pressure regulating system.
295006 SCRAM / 1 06 AA2.06 Ability to determine and/or interpret the following as they 3.5/3.8 1
apply to SCRAM: Cause of reactor SCRAM. (RO ONLY)
295007 High Reactor Pressure / 3 06 AK3.06 Knowledge of the reasons for the following responses as 3.7/3.8 1
they apply to HI9H REACTOR PRESSURE : Reactor/turbine
pressure regulating system operation.
295009 Low Reactor Water Level / 2 05 AKt.05 Knowledge of the operational implications of the following 3.3/3.4 1
concepts as they apply to LOW REACTOR WATER LEVEL:
Natural circulation.
295010 High Drywell Pressure/ 5 01 AA1.01 Ability to operate and/or monitor the following as they 3.4/3.5 1
apply to HIGH DRYWELL PRESSURE: Safety/relief valve
operation.
295014 Inadvertent Reactivity Addition/ 1 03 AK2.03 Knowledge of the interrelations between INADVERTENT 3.3/3.4 1
REACTIVITY ADDITION and the following: Fuel temperature.
295015 Incomplete SCRAM/ 1 02 AKI.02 Knowledge of the operational implications of the following 3.9/4.1 1
concepts as they apply to INCOMPLETE SCRAM: Cooldown
effects on reactor power.
295024 High Drywell Pressure /5 01 EK3.01 Knowledge of the reasons for the following responses as 3.6/4.0 1
they apply to HIGH DRYWELL PRESSURE: Drywell spray
operation.
295025 High Reactor Pressure / 3 02 2.1.20 EA1.02 Ability to operate and/or monitor the following as they 3.8/3.8 1
appily to HIGH REACTOR PRESSURE: Reactor/turbine pressure
neulatingsystem.
G2.1.20 biity, to execute procedure steps. (RO ONLY) 4.3/4.2 1
295031 Reactor Low Water Level / 2 2.1.1 G2.1.1 Knowledge of conduct of operations requirements. 3.7/3.8 1
295037 SCRAM Condition Present and Power 05 EK2.05 Knowledge of the interrelations between SCRAM 4.0/4.1 1
Above APRM Downscale or Unknown / 1 CONDITION PRESENT AND REACTOR POWER ABOVE APRM
DOWNSCALE OR UNKNOWN and the following: CRD hydraulic
system.
500000 High Containment Hydrogen Conc. / 5 01 EA2.O1 Ability to determine and / or intermret the following as they 3.1/3.5 1
apply to HIGH PRIMARY CONTAINMENT HYDROGEN
CONCENTRATIONS: Hydrogen monitoring system availability.
SACategory motes: 121212 31 1 12 J Group PointTotal: 13
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 2
E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Point
s
295001 Partial or Complete Loss of Forced Core 02 AIK2.2 Knowledge of the interrelations between PARTIAL OR 3.2/3.3 1
Flow Circulation / I & 4 COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and
the following: Nuclear boiler instrumentation
295002 Loss of Main Condenser Vacuum / 3 08 02 K2.08 Knowledqe of the interrelations between LOSS OF 3.1/3.2 2
MAINCONDENSER VACUUM and the following: Condenser
circulating water system 3.4/3.4
AK3.02 KIowledge of the reasons for the followin res nses as
they apply to LOSS OF MAIN CONDENSER VACUUM TTurbine
trip.
295003 Partial or Complete Loss of AC Pwr / 6 02 AKI.02Knowledge of the operational implications fo the following 3.1/3.4 1
concepts as they apply to PARTIAL OR COMPLETE LOSS OF
A.C. POWER: Load shedding.
295004 Partial or Complete Loss of DC Pwr / 6 02 AA2.02 Ability to determine and/or inter pret the following as they 3.5/3.9 1
apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Extent
o partial or complete loss of D. C. power.
295008 High Reactor Water Level / 2 04 AK3.04 Knowledge of the reasons for the following responses as 3.3/3.5 1
they apply to HIGH REACTOR WATER LEVEL: Reactor feed
pump tnp: Plant-Specific
295011 High CTMT Temperature// 5 (Mark Ill Containment Only) - N/A
295012 High Drywell Temperature / 5 02 AAI.02 Ability to operate and/or monitor the following as they apply 3.8/3.8 1
to HIGH DRYWELL TEMPERATURE: Drywell cooling system.
295013 High Suppression Pool Temp. /5 03 AKI.O3 Knowledge of the operational implications of the following 3.0/3:3 1
concepts as they apply to HIGH SUPPRESSION POOL
TEMPERATURE: Localized heating.
295016 Control Room Abandonment / 7 01 AK3.01 Knowledge of the reasons for the following responses as 4.1/4.2 1
theyply to CONTROL ROOM ABANDONMENT: Reactor
295017 High Off-site Release Rate / 9 2.1.2 G2.1.2 Knowledge of operator responsibilities during all modes of 3.0/4.0 1
plant operation.
295018 Partial or Complete Loss of CCW / 8
295019 Part. or Comp. Loss of Inst. Air/ 8 01 AAI.01 Ability to operate and/or monitor the following as they apply 3.5/3.3 -1
to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:
Backup air supply.
295020 Inadvertent Cont. Isolation / 5 & 7 06 AA2.06 Ability to determine and/or intemret the following as they 3.413.8 1
apply to INADVERTENT CONTAINMENT ISOLATION: Cause of
isolation.
295022 Loss of CRD Pumps / 1 2.1.30 2.1.30 Ability to locate and operate components / including local 3.9/3.4 1
controls.
295026 High Suppression Pool Water Temp. / 5 04 EK2.04 Knowledge of the interrelations between SUPPRESSION 2.5/2.8 1
POOL HIGH WATER TEMPERATURE and the following:
SPDS/ERIS/CRIDS/GDS.
295027 High Containment Temperature / 5 (Mark III Containment Only) - N/A
295028 High Drywell Temperature / 5 01 EKI.01 Knowledge of the operational implications of the following 3.5/3.7 1
concepts as they apply to HIGH DRYWELL TEMPERATURE:
Reactor water level measurement.
295029 High Suppression Pool Water Level / 5 Not selected.
295030 Low Suppression Pool Water Level / 5 05 EA1.05 Ability to operate and/or monitor the following as they apply 3.5/3.5 1
to LOW SUPPRESSION POOL WATER LEVEL: HPCI.
295033 High Sec. Cont. Area Red. Levels / 9 2.3.2 G2.3.2 Knowledge of facility ALARA program. (RO ONLY) 2.5/2.9 1
295034 Sec. Cont. Ventilation High Red. / 9 02 EK1.02 Knowledge of the operational implications of the following 4.1/4.4 1
concepts as they apply to SECONDARY CONTAINMENT
VENT LATION HIGH RADIATION: Radiation releases
295038 High Off-site Release Rate / 9 Not selected.
600000 Plant Fire On Site / 8 02 AA2.02 Ability to determine and interpret the following as they 2.8/2.9 1
apply to PLANT FIRE ON SITE: Damper position. (RO ONLY)
K/A Category Point Totals: 4 3 3 3 3 3 Group Point Total:
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 3
E/APE # / Name I Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Point
S
295021 Loss of Shutdown Cooling / 4 01 AK2.01 Knowledge of the interrelations-between LOSS OF SHUTDOWN 3.6/3.7 1
COOLING and the following: Reactor water temperature.
295023 Refueling Accidents / 8 02 AA2.02 Ability to determine and/or interpret the following as they apply 3.4/3.7 1
to REFUELING ACCIDENTS: Fuel pool level.
295032 High Secondary Containment Area 01 EK3.01 Knowledge of the reasons for the following responses as they 3.5/3.8 1
Temperature / 5 apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE:
Emergency/normal depressurization
295035 Secondary Containment High Differential 01 EK1.01 Knowledge of the operational implications of the following 3.9/4.2 1
Pressure / 5 concepts as they apply to SECONDARY CONTAINMENT HIGH
DIFFERENTIAL PRESSURE: Secondary containment integrity.
(RO ONLY)
295036 Secondary Containment High Sump/Area Not selected.
Water Level I 5
K/A Category Point Totals: 1111111 IiJ j Group Point Total: -J 4
ES-401 BWR RO Examination Outline Form ES-401-2 (R, S)
Plant Systems - Tier 2/Group 1
System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Point
s
201001 CRD Hydraulic 01 K1.01 Knowledge of the physical 3.1/3.1 1
connections and/or cause- effect
relationships between CONTROL ROD
DRIVE HYDURALIC SYSTEM and the
followinai: Condensate system.
(RO ON Y)
201002 RMCS 01 02 03 K3.01 Knowled e of the effect that a 3.4/3.4. 1
loss or malfuncion of the REACTOR
MANUAL CONTROL SYSTEM will
have on following: Ability to move
control rods 3.5/3.5 1
0 ONLY)
.020 Knowlede of REACTOR
MANUAL CONT OL SYSTEM design
feature(s) and/or interlocks which
grovide for the following: Control rod
locks 3.2/3.2 1
A3.03 Ability to monitor automatic
Coperations of the REACTOR MANUAL
CONTROL SYSTEM including: Rod
drift alarm.
201005 RCIS Applies to BWR 6 - N/A
202002 Recirculation Flow Control 06 K4.06 Knowledge of RECIRCULATION 3.1/3.1 1
FLOW CONTROL SYSTEM design
feature(s) and/or interlocks which
provide for the following: Recirculation
pump NPSH.
203000 RHR/LPCI: Injection Mode 04 Al.04 Ability to predict and/or monitor 3.6/3.6 1
change
peratingin tearameters
RHl/LPCI:associated with
INJECTION
MODE controls including: System
pressure.
206000 HPCI 08 KS.08 Knowledge of the operational 3.0/3.2 1
implications of the followin concepts
as they applyto HIGH PRESSURE
COOLANT INJECTION SYSTEM:
Vacuum breaker operation.
207000 Isolation (Emerg.) Condenser Not applicable to Brunswick.
209001 LPCS 03 K2.03 Knowledge of the electrical 2.9/3.1 1
initiation
p_ower
_
togic.1 to the following:
supplies
209002 HPCS Not applicable to Brunswick.
211000 SLC 08 A3.08 Ability to monitor automatic 4.2./4.2 1
operations of the STANDBY LIQUID
CONTROL SYSTEM including:
System initiation: Plant-Specific
212000 RPS 04 2.1.27 K6.04 Knowled[e of the effect that a 2.8/3.1
loss or malfunction of the followingwill
have on the REACTOR PROTECTION
SYSTEM: D.C. electrical distribution
G2.1.27 Knowled of system purpose 2.8/2.9
and or function. (RO ONLY)
215003 IRM 07 A4.07 Ability to manually operate 13.613.6
and/or monitor in the control room:
t of (FROONLY)
Verification
operability. roper functioningo
215004 SRM 2.2.1 G2.2.1 Ability
procedures fortothe
perform
facility pre-startup
/ including 3.7/3.6
operating those controls associated
with plan equipment that could affect
reactivity.
215005 APRM / LPRM 06 A4.06 Ability to manually operate 3.613.8
and/or monitor in the control room:
Vedfication of proper functioning /
operability.
216000 Nuclear Boiler Instrumentation 01 K2.01 Knowledge of electrical power 2.8/2.81
supplies
system.
to the following: Analog trip
217000 RCIC 01 2.1.28 K1.01 Knowledge of the physical 3.5/3.5
connections and/or cause-effect
relationships between REACTOR
CORE ISOLATION COOLING
SYSTEM (RCIC) and the following:
Condensate storage and transfer
s stem. 3.23.3
G2.1.28 Knowledge of the purpose and
function of major system components
and controls.
218000 ADS 02 A4.02 Ability to manually operate 4.2/4.2
and/or monitor in the control room:
ADS logic initiation.
223001 Primary CTMT and Auxiliaries 03 K4.03 Knowledge of PRIMARY 3.7/3.8
CONTAINMENT SYSTEM AND
AUXILIARIES design feature(s) and/or
interlocks which provide for the
following: Containment/drywell
isolation. (RO Only)
223002 PCIS/Nuclear Steam Supply 07 02 K1.07 Knowledge of the physical 3.4/3.6
Shutoff connections and/or cause-effect
relationships between PRIMARY
CONTAINMENT ISOLATION
SYSTEM/NUCLEAR STEAM SUPPLY
SHUT-OFF and the following: Reactor
core isolation cooling.
A3.02 Ability to monitor automatic 3.5/3.5
operation of the PRIMARY
CONTAINMENT ISOLATION
SYSTEM/NUCLEAR STEAM SUPPLY
SHUT-OFF including: valve closure.
239002 SRVs 05 01 K6.05 Knowledge of the effect that a 3.0/3.2 2
loss or malfunction of the following will
have on the RELIEF/SAFETY
VALVES: Discharge line vacuum
breaker
AI.01 Ability to mointor automatic 3.3/3.4
actions of the RELIEF/SAFETY
VALVES including: Tail pipe
temperature
241000 Reactor/Turbine Pressure 05 K6.05 Knowledge of the effect that a 3.4/3.4
Regulator loss or malfunction of the following will
have on the REACTOR/TURBINE
PRESSURE REGULATING SYSTEM:
Condenser vacuum.
259001 Reactor Feedwater 07 A2.07 Ability to(a) predict the impacts 3.7/3.8
of the following on the REACTOR
FEEDWATER SYSTEM; and (bi based
on those predictions, use procedures
to correct, control, or mitigate the
consequences of those abnormal
conditions or operations: Reactor
water level control malfunctions.
261000 SGTS 04 01 K3.04 Knowledge of the effect that a 3.1/3.1 1
loss or malfuncion of the STANDBY
GAS TREATMENT SYSTEM will have
on the following: High pressure
coolannt injection system.
K4.01 Knowled e of STANDBY GAS
TREATMENT ScYSTEM design 3.7/3.8 1
feature(s) and/or interlocks w]hich
provide for the following: Automatic
system initiation. (RO Only)
264000 EDGs 05 06 K4.05 Knowledge of EMERGENCY 3.2/3.5 2
GENERATORS -(DIESELIJET) design
feature(s) and/or interlocks which
provide for the following: Laod
shedding and sequencing
K5.06 Knowledge of the op Load 3.4/3.5
shedding and sequencing erational
implications of the following concepts
as they ap to EMERGENCY
GENERATORS (DIESEL/JET): Load
sequencing.
KfA Category Point Totals: 13 12 I11Z 12 12 1 2 12 13 3 13 IGroup Point Total: 28
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, SI)
Plant Systems - Tier 2/Group 2
System # / Name K1 K2 K3 t(4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points
201003 Control Rod and Drive Mechanism 01 09 K3.01 Knowledge of the effect that a 3.2/3.4 2
loss or malfunction of the CONTROL
ROD AND DRIVE MECHANISM will
have on following: Reactor power. (RO
ONLY) 3.2/3.4
A2.09 Ability to (a) predict the impacts
of the followin on the CONTROL ROD
AND DRIVE MECHANISM; and (b)
based on those predictions, use
procedures to correct, control, or
mitigate the consequences of those
abnormal conditions or operations: Low
reactor pressure
201004 RSCS Does not apply to Browns Ferry.
201006 RWM 2.2.12 G2.2.12 Knowledge of surveillance 3.0/3.4 1
procedures. (RO ONLY)
202001 Recirculation 07 A1.07 Ability to predict and/or monitor 2.7/2.8 1
changes in parameters associated with
operating the RECIRCULATION
SYSTEM controls including:
Recirculation pump speed.
204000 RWCU 06 04 K1.06 Knowledge of the physical 2.8/2.8 2
connections and/or cause- effect
relationships between REACTOR
WATER CLEANUP SYSTEM and the
following: Main condenser
K5.04 Knowledge of the operational 2.7/2.7
implications of the following concepts as
they applyto REACTOR WATER
CLEANUP SYSTEM: Heat exchanger
operation.
205000 Shutdown Cooling 01 A3.01 Ability to monitor automatic 3.2/3.1 1
operations of the SHUTDOWN
COOLING SYSTEM (RHR SHUTDOWN
COOLING MODE)including: Valve
I operation. (RO ONLY)
214000 RPIS 01 K4.01 Knowledge of ROD POSITION 3.0/3.1 1
INFORMATION SYSTEM design
feature(s) and/or interlocks which
provide for the following: Reed switch
locations.
215002 RBM 04 K6.04 Knowledge of the effect that a 2.8/3.0 1
loss or malfunction of the following will
have on the ROD BLOCK MONITOR
SYSTEM: APRM reference channel.
1__ ____ 1__1_1(RO ONLY) I I
219000 RHRJLPCI: Torus/Pool Cooling Mode 03 A2.03 Ability to (a) predict the impacts 3.113.2
of the following on the RHR/LPCI:
TORUS/SUPPRESSION POOL
COOLING MODE; and (b) based on
those predictions, use procedures to
correct, control, or mitigate the
consequences of those abnormal
conditions or operations: Valve closures
226001 RHR/LPCI: CTMT Spray Mode
230000 RHRPLPCI: Torus/Pool Spray Mode 15 A2.15 Ability to (a) predict the impacts 4.0/4.1
of the following on the RHR/LPCI:
TORUS/SUPPRESSION POOL SPRAY
MODE; and (b) based on those
predictions, use procedures to correct,
control, or mitigate the consequiences of
those abnormal conditions or
o*erations: Loss of coolant accident.
1 0 ONLY)
239001 Main and Reheat Steam 16 K3.16 Knowledge of the effect that a 3.6/3.6
loss or malfunction of the MAIN AND
REHEAT STEAM SYSTEM will have on
the following: Relief/safety valves.
245000 Main Turbine Gen. and Auxiliaries 10 A4.10 Ability to manually operate and/or 2.6/2.6
monitor in the control room: Hydrogen
gas pressure.
256000 Reactor Condensate 01 K2.01 Knowledge of electrical power 2.7/2.8
supplies to the following: System
pumps.
262001 AC Electrical Distribution 05 A4.05
monitorAbility
in thetocontrol
manually operate and/or 3.3/3.3
room: Voltage,
current, power, frequency and A.C.
buses.
262002 UPS (AC/DC) Not selected.
263000 DC Electrical Distribution 01 K2.01 Knowledge of electrical poser 3.1/3.4
supplies to the following: Major D.C.
loads.
271000 Offgas 02 A3.02 Ability to monitor automatic 2.9/2.8
operations of the OFFGAS SYSTEM
including: System flows. (RO ONLY)
272000 Radiation Monitoring 02 K1.02 Knowledge of the physical 3.2/3.5
connections and/or cause-effect
relationships between the RADIATION
MONITORING SYSTEM and the
following: Offgas system (augmented
offgas).
286000 Fire Protection Not selected.
290001 Secondary CTMT
290003 Control Room HVAC Not selected.
300000 Instrument Air 02 K3.02 Knowledge of the effect that a 3.3/3.4
loss or malfuntion of the INSTRUMENT
AIR SYSTEM will have on the following:
Systems having pneumatic valves and
controls.
400000 Component Cooling Water Not selected.
KIA Category Point Totals: 1
I2 3 I2 1 I I 13 I2 122 IGroup Point Total: I19
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, Si)
Plant Systems - Tier 2/Group 3 I
System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/A Topic(s) Imp. PTS
215001 Traversing In-core Probe 01 A2.01 Ability to (a) predict the impacts of 2.7/2.9 1
the following on the TRAVERSING IN
CORE PROBE; and (b) based on those
predictions, use proceures to correct,
control, or mitigate the consequences of
those abnorna9 conditions or operations:
Low reactor water level. (RO ONLY)
233000 Fuel Pool Cooling and Cleanup 02 K2.02 Knowledge of electrical power 2.8/2.9 1
supplies to the following: RHR pumps.
(RO ONLY)
239003 MSIV Leakage Control Does not apply to Brunswick.
268000 Radwaste 01 A1.01 Ability to predict and/or monitor 2.7/3.1 1
changes in parameters associated with
operating the RADWASTE controls
including: Radiation level.
288000 Plant Ventilation
290002 Reactor Vessel Internals
K/A Category Point Totals: [ 1 1]j1 1 1 1 1 11 1 1J Group Point Total: 4
Plant-Specific Priorities
System / Topic Recommended Replacement for... Reason Point
a
Plant-Specific Priority Total: (limit 10)
=QAA4 ni ITt rr
I IMP:: Form F S-401-5-
~f l IIP
- ctAAI~~~~r- f~rip WnnwdnrinP zndt Ahiliting Outline (Tier 3) ~ Fr S4t
Facility: Brunswick Date of Exam: Exam Level: RO
Category K/A # Topic Imp. Pts.
2.1.1 Knowledge of conduct of operations requirements. 3.7/3.8 1
2.1.10 Knowledge of conditions and limitations in the 2.7/3.9 1
Conduct of facility license
Operations 2.1.28 Knowledge of the purpose and function of major 3.2/3.3 1
system components and controls.
Total
2.2.3 Knowledge of the design / procedural / and 3.1/3.3
operational differences between units.
2.2.12 Knowledge of surveillance procedures. RO ONLY 3.0/3.4
Control 2.2.13 Knowledge of tagging and clearance procedures. 3.6/3.8
RO ONLY
Total
2.3.1 Knowledge fo 10 CFR: 20 and related facility 2.6/3.0 1
radiation control requirements.
2.3.11 Ability to control radiation releases (RO ONLY) 2.7/3.2
Radiation
Control Total
2.4.1 Knowledge of EOP entry conditions and 4.3/4.6 1
immediate action steps.
Emergency 2.4.2 Knowledge of system set points / interlocks and 3.9/4.1 1
Procedures/ automatic actions associated with EOP entry
Plan conditions.
2.4.3 Ability to identify post-accident instrumentation. 3.5/3.8 1
2.4.11 Knowledge of abnormal condition procedures. 3.0/3.1 1
2.4.18 Knowledge of the specific basis for EOPs. 2.7/3.6 1
Total 13
Tier 3 Point Total (RO) 13