ML081370266
| ML081370266 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/08/2008 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-259/08-301 50-259/08-301 | |
| Download: ML081370266 (15) | |
See also: IR 05000259/2008301
Text
Draft Submittal
(Pink Paper)
ti; DRAFT Written Exam Quality Checklist (ES-401-6)
vi & Written Exam Sample Plan
ES-401 Written Examination Quality Checklist Form ES-401-6
Facility: Browns Ferry Date of Exam: 2/25/2008 Exam Level: RO ~ SRO 0
Initial
Item Description a b*
1. Questions and answers are technically accurate and applicable to the facility.
2. a. NRC KlAs are referenced for all questions.
b. Facility learning objectives are referenced as available.
3. SRO questions are appropriate in accordance with Section D.2.d of ES-401
4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions
were repeated from the last 2 NRC licensing exam, consult the NRR OL program office).
5. Question duplication from the license screening/audit exam was controlled
as indicated below (check the item that applies) and appears appropriate:
~ the audit exam was systematically and randomly developed; or
_ the audit exam was completed before the license exam was started; or
~ the examinations were developed independently; or
~ the licensee certifies that there is no duplication; or
_other (explain)
6. Bank use meets limits (no more than 75 percent Bank Modified New
from the bank, at least 10 percent new, and the rest
new or modified); enter the actual RO / SRO-only 49 8 18
question distribution(s) at right.
7. Between 50 and 60 percent of the questions on the RO Memo CIA
exam are written at the comprehension /analysis level;
the SRO exam may exceed 60 percent if the randomly 28 47
selected KAs support the higher cognitive levels; enter 37.40/0 62.6%
the actual RO / SRO question distribution(s) at right.
8. References/handouts provided do not give away answers
or aid in the elimination of distractors.
9. Question content conforms with specific KIA statements in the previously approved
examination outline and is apprcoriate for the Tier to which they are assigned;
deviations are justified
10. Question psychometric quality and format meet the guidelines in ES Appendix B.
11. The exam contains the required number of one-point, multiple choice items;
the total is correct and agrees with value on cover sheet
Date
a. Author 1/8/2008
b. Facility Reviewer (*) 1/8/2008
c. NRC Chief Examiner (#)
d. NRC Regional Supervisor
Note: * The facility reviewer's initials/signature are not applicable for NRGdeveloped examinations.
- Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
ES-401, Page 29 of 33
ES-401 Written Examination Quality Checklist Form ES-401-6
Facility: Browns Ferry Date of Exam: 2/25/2008 Exam Level: RO D SRO C8J
Initial
Item Description a b*
1. Questions and answers are technically accurate and applicable to the facility.
2. a. NRC KlAs are referenced for all questions.
b. Facility learning objectives are referenced as available.
3. SRO questions are appropriate in accordance with Section D.2.d of ES-401
4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions
were repeated from the last 2 NRC licensing exam, consult the NRR OL program office).
5. Question duplication from the license screening/audit exam was controlled
as indicated below (check the item that applies) and appears appropriate:
~ the audit exam was systematically and randomly developed; or
_ the audit exam was completed before the license exam was started; or
~ the examinations were developed independently; or
~ the licensee certifies that there is no duplication; or
_other (explain)
6. Bank use meets limits (no more than 75 percent Bank Modified New
from the bank, at least 10 percent new, and the rest
new or modified); enter the actual RO / SRO-only 12 2 11
question distribution(s) at right.
7. Between 50 and 60 percent of the questions on the RO Memo CIA
exam are written at the comprehension /analysis level;
the SRO exam may exceed 60 percent if the randomly 3 22
selected KAs support the higher cognitive levels; enter 120/0 88°~
the actual RO / SRO question distribution(s) at right.
8. References/handouts provided do not give away answers
or aid in the elimination of distractors.
9. Question content conforms with specific KIA statements in the previously approved
examination outline and is appropriae for the Tier to which they are assigned;
deviations are justified
10. Question psychometric quality and format meet the guidelines in ES Appendix B.
11. The exam contains the required number of one-point, multiple choice items;
the total is correct and agrees with value on cover sheet
Date
a. Author 1/8/2008
b. Facility Reviewer (*) E. Robert Scillian 1/8/2008
c. NRC Chief Examiner (#)
d. NRC Regional Supervisor
Note: * The facility reviewer's initials/signature are not applicable for NRGdeveloped examinations.
- Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
ES-401, Page 29 of 33
ES-401 Written Examination Outline Form ES-401-1
Facility: 0610 NRC Exam Outline Date of Exam: 02/25/2008
RO KIA Category Points SRO-Only Points
Tier Group K K K K K K A A A A G
Total A2 G* Total
1 2 3 4 5 6 1 2 3 4 *
1. 1 3 3 3 3 4 4 20 4 3 7
Emergency
& 2 1 1 1 1 2 1 7 1 2 3
Plant
Tier
Evolutions 4 4 4 4 6 5 27 5 5 10
Totals
1 2 3 2 2 2 2 2 3 3 3 2 26 3 2 5
2.
Plant 2 1 1 1 1 1 2 1 1 1 1 1 12 0 2 1 3
Systems
Tier
3 4 3 3 3 4 3 4 4 4 3 38 5 3 8
Totals
3. Generic Knowledge & Abilities
1 2 3 4 1 2 3 4
10 7
Categories
3 2 2 3 1 2 2 2
Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and
SRO-only outlines (i.e., except for one category in Tier 3 ofthe SRO-only outline, the "Tier Totals" in each KIA
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 +/-l 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. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not
apply at the facility should be deleted and justified; operationally important, site-specific systems that are not
included on the outline should be added . Refer to section D.l.b ofES-401, for guidance regarding elimination of
inappropriate KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group
before selecting a second topic for any system or evolution.
5. Absent a plant specific priority, only those KAs having an importance rating (IR) of2.5 or higher shall be
L
selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers I and 2 from the shaded systems and KIA categories.
7.* The generic (G) KI As in Tiers I and 2 shall be selected from Section 2 ofthe KIA Catalog, but the topics must be
relevant to the applicable evolution or system. Refer to Section D.I .b of ES-40 1 for the applicable KIA's
8. On the following pages, enter the KIA 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. Iffuel handling equipment is sampled in other than Category A2 or
G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply).
Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 ofthe KIA Catalog, and enter the KIA numbers, descriptions, IRs, and
point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to IOCFR55.43
.(
0610 NRC Exam Outline
Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 1
I EAPE # I Name Safety Function K1 K2 K3 I A1 I A2 I G KJA Topic(s) Imp. I Q# I
AA2.01 - Ability to determineand/or interpret
295006 SCRAM 11 X the followingas they apply to SCRAM: 4.6 76
Reactor power
AA2.07 - Ability to determineand/or interpret
the followingas they applyto LOSS OF
295021 Loss of ShutdownCooling I 4 X 3.1 77
SHUTDOWN COOLING: Reactor
recirculation flow
2.1.28 - Conductof OperationsKnowledge of
295024 High Drywell Pressure I 5 X the purpose and functionof major system 3.3 78
components and controls.
EA2.01 - Abilityto determineand/or interpret
295026 SuppressionPool High Water the followingas they apply to SUPPRESSION
X 4.2 79
Temp. 15 POOL HIGH WATERTEMPERATURE:
Suppression pool water temperature
EA2.05 - Ability to determineand/or interpret
295037 SCRAM Condition Present the followingas they apply to SCRAM
and Power Above APRM Downscale X CONDITION PRESENTAND REACTOR 4.3 80
or Unknown11 POWER ABOVEAPRM DOWNSCALE OR
UNKNOWN: Control rod position
2.2.22 - EquipmentControlKnowledge of
295038High Off-site Release Rate 19 X limiting conditionsfor operationsand safety 4.1 81
limits.
2.2.24 - EquipmentControlAbility to analyze
600000Plant Fire On-site I 8 X the affect of maintenance activitieson LCO 3.8 82
status.
c 295001Partial or CompleteLoss of
Forced Core Flow Circulation II & 4 X
2.1.14 - Conduct of OperationsKnowledgeof
system status criteria whichrequirethe
notificationof plant personnel.
AK3.01 - Knowledgeof the reasons for the
followingresponsesas they applyto PARTIAL
2.5 39
29500I Partial or CompleteLoss of
Forced Core Flow Circulation II & 4
X OR COMPLETELOSS OF FORCEDCORE 3.4 40
FLOW CIRCULATION : Reactorwater level
response
AA2.01 - Ability to determineand/or interpret
295003Partial or Complete Loss of the followingas they apply to PARTIALOR
AC/6
X 3.4 41
COMPLETELOSS OF AC. POWER : Cause
of partial or completeloss of AC. power
AKI.03 - Knowledgeof the operational
295004Partial or Total Loss of DC implicationsof the followingconceptsas they
X applyto PARTIALOR COMPLETE LOSS OF 2.9 42
Pwr/6
D.C. POWER: Electricalbus divisional
separation
AA1.04 - Abilityto operate and/or monitor
295005Main Turbine GeneratorTrip I the following as they apply to MAIN
3
X 2.7 43
TURBINE GENERATOR TRIP : Main
generator controls
AK3.05 - Knowledge of the reasons for the
following responses as they apply to
295006SCRAM I 1 X 3.8 44
SCRAM : Direct turbine generator trip:
Plant-5pecific
AA2.04 - Abilityto determine and/or
295016 Control Room AbandonmentI interpret the following as they apply to
7
X 3.9 45
CONTROL ROOM ABANDONMENT :
Suppression pool temoerature
AK2.01 - Knowledge of the interrelations
295018Partial or Total Loss ofCCW I between PARTIALOR COMPLETE LOSS
X 3.3 46
8 OF COMPONENT COOLING WATER and
the following: System loads
( 295019Partial or Total Loss ofInst.
X
AA2.02 - Ability to determine and/or
3.6 47
Air I 8 interpret the following as they apply to
0610 NRC Exam Outline
Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 1
I EAPE # I Name Safety Function I K1 I K2 I K3 I A1 I A2 I G I KIA Topic(s) Imp. I Q# I
PARTIAL OR COMPLETE LOSS OF
INSTRUMENT AIR: Status of safety-
related instrument air system loads (see
AK2.1 - AK2.19)
"" 2.4.50 - Emergency Procedures I Plan
Ability to verify system alarm setpoints and
295021Loss of ShutdownCooling I 4 X operate controls identified in the alarm 3.3 48
I'" response manual.
AK1.02 - Knowledge of the operational
295023Refueling Ace Cooling Mode I implications of the following concepts as
X they apply to REFUELING ACCIDENTS :
3.2 49
8
2.1.33 - Conduct of Operations Ability to
recognize indications for system operating
295024High DrywelI Pressure I 5 X parameters which are entry-level 3.4 50
conditions for technical specifications.
'" EK2.08 - Knowledge of the interrelations
between HIGH REACTOR PRESSURE
295025High ReactorPressure 13 X 3.7 51
and the following: Reactor/turbine pressure
regulating system: Plant-Specific
EA2.01 - Ability to determine and/or
interpret the following as they apply to
295026Suppression Pool High Water
X SUPPRESSION POOL HIGH WATER 4.1 52
Temp. 15
TEMPERATURE: Suppression pool water
temperature
~
EK3.04 - Knowledge of the reasons for the
following responses as they apply to HIGH
295028High DrywelI Temperature I 5 X 3.6 53
DRYWELL TEMPERATURE: Increased
drywell cooling
EA1.06 - Ability to operate and/or monitor
the following as they apply to LOW
295030Low Suppression Pool Water "
Levell 5
X SUPPRESSION POOL WATER LEVEL : 3.4 54
Condensate storage and transfer (make-up
'" to the suppression pool): Plant-Specific
~
2.4.6 - Emergency Procedures I Plan
295031 ReactorLow Water Level/2 X Knowledge symptom based EOP 3.1 55
'" mitigation strateg ies.
EK2 .11 - Knowledge of the interrelations
295037SCRAM Condition Present between SCRAM CONDITION PRESENT
andPower Above APRM Downscale X WI AND REACTOR POWER ABOVE APRM 3.8 56
or Unknown 11 DOWNSCALE OR UNKNOWN and the
~
following : RMCS: Plant-Specific
EK1.01 - Knowledge of the operational
implications of the following concepts as
~,
295038High Off-site Release Rate 19 X they apply to HIGH OFF-SITE RELEASE 2.5 57
RATE : Biological effects of radioisotope
inaestion
" AA 1.08 - Ability to operate and I or monitor
the follOWing as they apply to PLANT FIRE
600000Plant Fire On-site I 8 X 2.6 58
ON SITE : Fire fighting equipment used on
each class of fire
KIA CategoryTotals: 3 3 3 3 8 7 Group Point Total:
I 20/7
(
0610 NRC Exam Outline
Written Examination Outline
Emergency and Abnormal Plant Evolutions - Tier 1 Group 2
I EAPE # / Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. I Q# I
2.4.6 - Emergency Procedures I Plan
295002 Loss of Main Condenser Vac 13 X Knowledge symptom based EOP mitigation 4.0 83
strategies.
2.4.31 - Emergency Procedures I Plan
295009 Low Reactor Water Level 12 X Knowledge of annunciators alarms and 3.4 84
indications, and use of the response instructions.
EA2.02 - Ability to determine and I or interpret
the following as they apply to HIGH
500000 High CTMT Hydrogen Cone, I
X PRIMARY CONTAINMENT HYDROGEN 3.5 85
5
CONCENTRATIONS: Oxygen monitoring
system availabilitv
AK2.01 - Knowledge ofthe interrelations
295009 Low Reactor Water Level 12 X between LOW REACTOR WATER LEVEL 3.9 59
and the following : Reactor water level indication
2.2.22 - Equipment Control Knowledge of
295012 High Drywell Temperature 15 X limiting conditions for operations and safety 3.4 60
limits .
AK1.02 - Knowledge of the operational
implications of the following concepts as they
295015 Incomplete SCRAM /1 X 3.9 61
apply to INCOMPLETE SCRAM: (CPR 41.8 to
41.10) Cooldown effects on reactor DOwer
AKJ.08 - Knowledge of the reasons for the
following responses as they apply to
295020 Inadvertent Cont. Isolation I 5 &
X INADVERTENT CONTAINMENT 3.3 62
7
ISOLATION: Suppression chamber pressure
response
EA1.01 - Ability to operate and/or monitor the
295032 High Secondary Containment following as they apply to HIGH SECONDARY
X 3.6 63
Area Temperature 15 CONTAINMENT AREA TEMPERATURE :
Area temperature monitorinz svstem
EA2 .01 - Ability to determine and/or interpret
295033 High Secondary Containment the following as they apply to HIGH
X 3.8 64
Area Radiation Levels 19 SECONDARY CONTAINMENT AREA
RADIATION LEVELS: Area radiation levels
EA2.02 - Ability to determine and/or interpret
295035 Secondary Containment High the following as they apply to SECONDARY
X CONTAINMENT HIGH DIFFERENTIAL 2.8 65
Differential Pressure I 5
PRESSURE: Off-site release rate: Plant-
Specific
KIA Category Totals : 1 1 1 1 3 3 Group Point Total:
I 7/3
(
0610 NRC Exam Outline
Written Examination Outline
( Plant Systems - Tier 2 Group 1
K K K K K K A A A A Q#
System # / Name G Imp.
1 2 3 4 5 6 1 2 3 4
A2.16 - Abilityto (a) predictthe impacts
of the following on the RHRILPCI:
INJECTION MODE(pLANTSPECIFIC) ;
203000RHRILPCI: Injection and (b) basedon thosepredictions, use
X 4.5 86
Mode procedures to correct, control, or mitigate
the consequences of those abnormal
conditions or operations: Loss of coolant
accident
2.1.14- Conductof Operations Knowledge
215003lRM X of systemstatus criteriawhichrequire the 3.3 87
notification of plantpersonnel.
2.l.23 - Conductof Operations Abilityto
259002ReactorWaterLevel performspecificsystemand integrated
X 4.0 88
Control plantprocedures duringall modesof plant
operation.
A2.06 - Abilityto (a) predictthe impacts
of the following on the SHUTDOWN
COOLING SYSTEM(RHR SHUTDOWN
259002ReactorWaterLevel COOLING MODE); and (b) basedon
X 3.5 89
Control those predictions, use procedures to correct,
control, or mitigatethe consequences of
those abnormal conditions SOCIRHR
pumptrips
A2.12 - Abilityto (a) predictthe impacts
( of the following on the REACTOR
PROTECTION SYSTEM; and (b) based
259002ReactorWaterLevel on thosepredictions, use procedures to
Control
X 4.1 90
correct, control, or mitigatethe
consequences of those abnormal conditions
or operations: Mainturbinestop control
valveclosure
Al.OI - Abilityto predictand/ormonitor
203000RHRILPCI: Injection changes in parameters associated with
X operating the RHRILPCI: INJECTION 4.2 I
Mode
MODE(pLANTSPECIFIC) controls
including: Reactorwater level
K4.02 - KnOWledge of SHUTDOWN
COOLING SYSTEM (RHR
205000Shutdown Cooling SHUTDOWNCOOLINGMODE)
X 3.7 2
design feature(s) and/or interlocks
which provide for the following: High
pressure isolation: Plant-Specific
K6.09 - Knowledge of the effect that a
loss or malfunction of the follOWing will
206000HPCI have on the HIGHPRESSURE
X 3.5 3
COOLANTINJECTIONSYSTEM :
Condensate storage and transfer
system: BWR-2,3,4
K5.04 - Knowledge of the operational
implications of the following concepts
209001 LPCS X as they apply to LOWPRESSURE 2.8 4
CORE SPRAY SYSTEM : Heat
removal (transfer) mechanisms
211000SLC K2.01 - Knowledge of electrical power
X 2.9 5
supplies to the following: SBLC pumps
(
0610 NRC Exam Outline
Written Examination Outline
( Plant Systems - Tier 2 Group 1
K K K K K K A A A A Q#
System # / Name G Imp.
1 2 3 4 5 6 1 2 3 4
K6.03 - Knowledge of the effect that a
loss or malfunction of the following will
212000RPS X have on the REACTOR PROTECTION 3.5 6
SYSTEM: Nuclear boiler
instrumentation
A4 .04 - Ability to manually operate
and/or monitor in the control room: IRM
215003 IRM X 3.1 7
back panel switches , meters , and
indicating lights
A3 .03 - Ability to monitor automatic
operations of the SOURCE RANGE
215004 Source Range Monitor X 3.6 8
MONITOR (SRM) SYSTEM including :
RPS status
A2 .03 - Ability to (a) predict the impacts
of the following on the AVERAGE
POWER RANGE MONITOR/LOCAL
POWER RANGE MONITOR SYSTEM ;
215005 APRM / LPRM X and (b) based on those predictions, use 3.6 9
procedures to correct, control, or
mitigate the consequences of those
abnormal conditions Inoperative trip (all
causes)
K2.03 - Knowledge of electrical power
217000 RCIC X supplies to the following: RCIC flow 2.7 10
controller
K1.05 - Knowledge of the physical
connections and/or cause- effect
relationships between AUTOMATIC
218000 ADS X 3.9 11
DEPRESSURIZATION SYSTEM and
the following: Remote shutdown
system : Plant-5pecific
2.1.24 - Conduct of Operations Ability
218000 ADS X to obtain and interpret station electrical 2.8 12
and mechanical drawings.
A2 .06 - Ability to (a) predict the impacts
of the following on the PRIMARY
CONTAINMENT ISOLATION
SYSTEM/NUCLEAR STEAM SUPPLY
223002 PCISlNuclear Steam
X SHUT-oFF; and (b) based on those 3.0 13
Supply Shutoff
predictions, use procedures to correct,
control , or mitigate the consequences
of those abn cond or ops. Containment
instrumentation failures
A3 .01 - Ability to monitor automatic
operations of the PRIMARY
223002 PCISlNuciear Steam CONTAINMENT ISOLATION
Supply Shutoff
X 3.4 14
SYSTEM/NUCLEAR STEAM SUPPLY
SHUT-OFF including : System
indicatinQ IiQhtsand alarms
A3 .03 - Ability to monitor automatic
operat ions of the RELIEF/SAFETY
239002SRVs X VALVES including : Tail pipe
3.6 15
temoeratures
A4.08 - Ability to manually operate
and/or monitor in the control room:
239002SRVs X Plant air system pressure: Plant-
3.2 16
Specific
(
0610 NRC Exam Outline
Written Examination Outline
( Plant Systems - Tier 2 Group 1
K K K K K K A A A A
System # / Name G Imp. Q#
1 2 3 4 5 6 1 2 3 4
A4.03 - Ability to manually operate
and/or monitor in the control room: All
259002 Reactor Water Level
X individual component controllers when 3.8 17
Control
transferring from manual to automatic
modes
K3.06 - Knowledge of the effect that a
loss or malfunction ofthe STANDBY
261000 SGTS X GAS TREATMENT SYSTEM will have 3.0 18
on following : Primary containment
oxygen content: Mark-I&II
K4.04 - Knowledge of A.C.
ELECTRICAL DISTRIBUTION design
262001 AC Electrical
X feature(s) and/or interlocks which 2.8 19
Distribution
provide for the following: Protective
relavina
A1.02 - Ability to predict and/or monitor
changes in parameters associated with
262002 UPS (ACIDC) X operating the UNINTERRUPTABLE 2.5 20
POWER SUPPLY (A.C.ID.C .) controls
including: Motor generator outputs
K1.02 - Knowledge of the physical
connections and/or cause- effect
263000 DC Electrical
X relationships between D.C. 3.2 21
Distribution
ELECTRICAL DISTRIBUTION and the
following: Battery charger and battery
K5.06 - Knowledge of the operational
implications of the following concepts
264oooEOOs X as they apply to EMERGENCY 3.4 22
GENERATORS (DIESEUJET): Load
secuencina
K2.02 - Knowledge of electrical power
300000 Instrument Air X supplies to the following: Emergency 3.0 23
air compressor
K3.01 - Knowledge of the effect that a
loss or malfunction of the
300000 Instrument Air X (INSTRUMENT AIR SYSTEM) will 2.7 24
have on the following: Containment air
svstem
2.4.31 - Emergency Procedures / Plan
400000 Component Cooling Knowledge of annunciators alarms and
X 3.3 25
Water indications, and use of the response
instructions.
A2 .02 - Ability to (a) predict the impacts
of the following on the CCWS and (b)
based on those predictions, use
400000 Component Cooling
X procedures to correct, control , or 2.8 26
Water
mitigate the consequences of those
abnormal operation: High/low surge
tank level
KJA Category Totals : 2 3 2 2 2 2 2 6 3 3 4 Group Point Total:
I 26/5
(
0610 NRC Exam Outline
Written Examination Outline
( Plant Systems - Tier 2 Group 2
K K K K K K A A A A Imp. Q#
System # I Name G
1 2 3 4 5 6 1 2 3 4
A2.01 - Abilityto (a) predictthe impacts
of the following on the RADWASTE ; and
(b) basedon thosepredictions, use
268000Radwaste X 3.5 91
procedures to correct, control, or mitigate
the consequences of thoseabnormal
conditions or operations: System rupture
2.4.36- Emergency Procedures I Plan
271000Off-gas X Knowledge of chemistry I healthphysics 2.8 92
tasksduringemergency operations.
A2.03 - Abilityto (a) predictthe impacts
of the following on the PLANT
VENTILATION SYSTEMS; and (b)
basedon thosepredictions, use procedures
288000PlantVentilation X to correct, control, or mitigate the 3.7 93
consequences of thoseabnormal conditions
or operations: Lossof coolantaccident:
Plant-Specific
10.03 - Knowledge of the effectthat a
201003 Control Rod and Drive lossor malfunction of the CONTROL
X 3.2 27
Mechanism RODANDDRIVEMECHANISM will
haveon following: Shutdown margin
K4.09- Knowledge of RODWORTH
MINIMIZER SYSTEM (RWM) (pLANT
20loo6RWM X SPECIFIC) designfeature(s) and/or 3.2 28
( interlocks whichprovide for the following:
System initialization: P-Soec(Not-BWR6)
K6.09 - Knowledge of the effectthat a
lossor malfunction of the following will
20200I Recirculation X 3.4 29
haveon the RECIRCULATION SYSTEM
- Reactorwater level
A1.01 - Ability to predict and/or monitor
changes in parameters associated with
215001 Traversing In-coreProbe X operating the TRAVERSING IN-CORE 2.8 30
PROBE controls including: Radiation
levels: (Not-BWR1)
K1.10 - Knowledge of the physical
connections and/or cause- effect
216000NuclearBoilerInst. relationships between NUCLEAR
X 3.2 31
BOILERINSTRUMENTATION and the
following: Recirculation flowcontrol
svstem
219000RHRILPCI: TorusIPool K2.02 - Knowledge of electrical power
CoolingMode X 3.1 32
supplies to the followina: Pumps
226001 RHRILPCI: CTMTSpray A4.12 - Ability to manually operate
X and/or monitor in the control room: 3.8 33
Mode
Containmentldrywell pressure
2.4.50 - Emergency Procedures I Plan
234000FuelHandling Equipment Ability to verify system alarm setpoints
X 3.3 34
and operate controls identified in the
alarm response manual.
K6.04 - Knowledge of the effect that a
loss or malfunction of the following will
245000MainTurbineGen. I Aux. X have on the MAIN TURBINE 2.6 35
GENERATORANDAUXILIARY
SYSTEMS : Hydrogen cooling
(
0610 NRC Exam Outline
Written Examination Outline
Plant Systems - Tier 2 Group 2
(
K K K K K K A A A A Q#
System # I Name G Imp.
1 2 3 4 5 6 1 2 3 4
A2 .01 - Ability to (a) predict the
impacts of the following on the
RADWASTE ; and (b) based on those
268000 Radwaste X predictions, use procedures to correct, 2.9 36
control , or mitigate the consequences
of those abnormal conditions or
ooerations: SYStemruoture
K5.01 - Knowledge of the operational
implications of the following concepts
as they apply to RADIATION
272000 RadiationMonitoring X 3.2 37
MONITORING SYSTEM : Hydrogen
injection operation's effect on process
radiation indications: Plant-5oecific
A3.01 - Ability to monitor automatic
operations of the CONTROL ROOM
290003 Control Room HVAC X 3.3 38
HVAC inclUding:
Initiationlreconfiguration
KIA CategoryTotals: 1 1 1 1 1 2 1 3 1 1 2 Group Point Total:
I 1213
(
(
ES-401 Generic Knowledge and Abilities Outline (Tier3) Form ES-401-3
( Facility: 0610 NRC Exam Outline Date:
RO SRO-Only
Category K/A# Topic
IR Q# IR Q#
2.1.12 Ability to apply technical specifications for a system . 4.0 94
Ability to recognize indications for system operating
1. 2.1.33 parameters which are entry-level conditions for 3.4 66
Conduct technical specifications.
of Operations Ability to operate plant phone, paging system, and
2.1.16
two-way radio.
2.9 67
Ability to make accurate, clear and concise logs,
2.1.18
records , status boards, and reports.
2.9 68
~
Subtotal 3 1
Knowledge of limiting conditions for operations and
2.2.22
safety limits.
4.1 95
Ability to analyze the affect of maintenance activities
2.2.24
on LCO status.
3.8 96
2.
Equipment
Control 2.2.13 Knowledge oftagging and clearance procedures. 3.6 69
2.2.33 Knowledge of control rod programming. 2.5 70
Subtotal 2 2
Knowledge of SRO responsibilities for auxiliary
2.3.3 systems that are outside the control room (e.g., waste 2.9 97
disposal and handling systems).
Knowledge ofthe process for performing a
2.3.9 3.4 98
containment purge.
3.
Radiation Ability to perform procedures to reduce excessive
Control 2.3.10 levels of radiation and guard against personnel 2.9 71
exposure.
Knowledge of the process for performing a
2.3.9 2.5 72
containment purge.
Subtotal 2 2
Knowledge of the parameters and logic used to
4.
assess the status of safety functions including: I
Emergency
2.4.21 Reactivity control 2. Core cooling and heat removal 3. 4.3 99
Procedures/
Reactor coolant system integrity 4. Containment
Plan
( conditions 5. Radioactivity release control.
ES-401 Generic Knowledge andAbilities Outline (Tier3) Form ES-401-3
Knowledge of which events related to system
( 2.4.30 operations/status should be reported to outside
agencies.
3.6 100
Ability to diagnose and recognize trends in an
2.4.47 accurate and timely manner utilizing the appropriate 3.4 73
control room reference material.
Knowledge of communications procedures
2.4.15 3.0 74
associated with EOP implementation
Knowledge of how the event-based
2.4.8 emergency/abnormal operating procedures are used in 3.0 75
conjunction with the symptom-based EOPs .
Subtotal 3 2
Tier 3 Point Total 10 7
(
ES-401 Record of Rejected KIA's Form ES-401-4
( Tier! Group
Randomly Selected
Reason for Rejection
KIA
1/1 295016/ AA2.07 Replaced by NRC Chief Examiner
2/1 218000/2.1.14 Replaced by NRC Chief Examiner
2/1 600000 /2.2.25 Replaced by NRC Chief Examiner
2/1 212000/ A2.17 Replaced by NRC Chief Examiner
2/1 205000 / A2.04 Replaced by NRC Chief Examiner
2/1 400000 / 2.4.30 Replaced by NRC Chief Examiner
Admin Replaced due to conflict with independently developed Audit
AJPM501
JPM examination.
('-. ..