ML080860129
| ML080860129 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/17/2009 |
| From: | Haag R NRC/RGN-II/DRS/OLB |
| To: | Tennessee Valley Authority |
| References | |
| 50-259/07-301, 50-260/07-301, 50-296/07-301 | |
| Download: ML080860129 (22) | |
Text
Draft Submittal (Pink Paper)
¢jfUJWIIJS FEL~y c2#-o:{ -~I DRAFT Written Exam Quality Checklist (ES-401-6)
&Written Exam Sample' Plan
ES-401 BWR Examination Outline Form ES-401-1 I Facility:
BFN Date of Exam: 09/04/07 DI?vAf:r RO KIA Category Points SRO-Only Points Tier Group K
K K
G Total A2 G
Total 1
2 3
1.
1 4
3 3
3 20 4
3 7
Emergency 2
1 2
1 1
7 2
1 3
&Abnormal Tier 5
5 4
4 27 6
4 10 Plant Evolutions Totals 2.
1 2
3 2
2 2
3 2
2 3
3 2
26 3
2 5
Plant 2
1 1
1 1
1 1
1 1
1 1
2 12 2
1 3
Systems Tier 3
4 3
3 3
4 3
3 4
4 4
38 5
3 8
Totals
- 3. Generic Knowledge and 1
2 3
4 1
2 3
4 Abilities Categories 10 7
3 2
2 3
2 2
2 1
Note: 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines i.e., except for one category in Tier 3 of the 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 +/-1 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; syst~ms 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 ES-401, Attachment 2, for guidance regarding the 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 KlAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.*
The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system.
8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) 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. Use duplicate pages for RO and SRO-only exams.
9.
For Tier 3, select topics from Section 2 of the 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 10 CFR 55.43.
17
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ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)
E/APE # / Name / Safety Function K
K K
A A
G KIA Topic(s)
IR I
2 3
I 2
295001 Partial or Complete Loss of Forced x
AK2.07 Knowledge ofthe interrelations between 3.4 Core Flow Circulation / 1 & 4 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and the following: Core flow indication 295001 Partial or Complete Loss of x
G2.2.3 Knowledge of the design / procedural/ and 3.3 Forced Core Flow Circulation /1 & 4 operational differences between units.
295003 Partial or Complete Loss of AC / 6 x
AA2.04 Ability to detennine and/or interpret the 3.5 following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: System lineups 295004 Partial or Total Loss of DC Pwr /6 x
AA2.02 Ability to determine and/or interpret the 3.5 following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Extent ofpartial or complete loss of D.C. power 295005 Main Turbine Generator Trip /3 x
AAI.05 Ability to operate and/or monitor the following 3.6 as they apply to MAIN TURBINE GENERATOR TRIP: Reactor/turbine pressure regulating system 295005 Main Turbine Generator Trip /3 x
AA2.07 Ability to determine and/or interpret the 3.6 following as they apply to MAIN TURBINE GENERATOR TRIP: Reactor water level 295006 SCRAM / 1 x
2.4.46 Ability to verify that the alarms are consistent 3.5 with the plant conditions.
295016 Control Room Abandonment /7 x
AAI.07 Ability to operate and/or monitor the following 4.2 as they apply to CONTROL ROOM ABANDONMENT: Control roomllocal control transfer mechanisms 295018 Partial or Total Loss of CCW /8 x
AKI.Ol Knowledge ofthe operational implications of 3.5 the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Effects on component/system operations 295019 Partial or Total Loss of Inst. Air /8 x
AK3.0I Knowledge ofthe reasons for the following 3.3 responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Backup air system supply 295019 Partial or Total Loss of Inst. Air I x
AA2.01 Ability to determine and/or interpret the 3.6 8
following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:
Instrument air system pressure 295021 Loss of Shutdown Cooling /4 x
AK1.04 Knowledge ofthe operational implications of 3.6 the following concepts as they apply to LOSS OF SHUTDOWN COOLING: Natural circulation 295023 Refueling Acc Cooling Mode / 8 x
AKl.03 Knowledge ofthe operational implications of 3.7 the following concepts as they apply to REFUELING ACCIDENTS : Inadvertant Criticality 295024 High Drywell Pressure / 5 x
EK3.06 Knowledge ofthe reasons for the following 4.0 responses as they apply to HIGH DRYWELL PRESSURE: Reactor Scram 295024 High Drywell Pressure I 5 x
EA2.06 Ability to determine and/or interpret the 4.1 following as they apply to HIGH DRYWELL PRESSURE: Suppression pool temperature 295025 High Reactor Pressure / 3 x
EK2.09 Knowledge ofthe interrelations between HIGH 3.9 REACTOR PRESSURE and the following: Reactor power
(
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO I SRO)
EIAPE # I Name I Safety Function K
K K
A A
G KIA Topic(s)
IR I
2 3
I 2
295025 High Reactor Pressure I 3 x
G2.4.4 Ability to recognize abnonnal indications for 4.0 system operating parameters which are entry-level conditions for emergency and abnonnal operating procedures.
295026 Suppression Pool High Water x
EKI.02 Knowledge ofthe operational implications of 3.5 Temp./5 the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Steam condensation 295027 High Containment Temperature 15 295028 High Drywell Temperature 15 x
EK3.05 Knowledge ofthe reasons for the following 3.6 responses as they apply to HIGH DRYWELL TEMPERATURE: Reactor SCRAM 295030 Low Suppression Pool Wtr Lvl/5 x
EAI.02 Ability to operate and/or monitor the following 3.4 as they apply to LOW SUPPRESSION POOL WATER LEVEL: RCIC 295031 Reactor Low Water Level 12 x
EK2.09 Knowledge ofthe interrelations between 3.3 REACTOR LOW WATER LEVEL and the following:
Recirculation system 295031 Reactor Low Water Level 12 x
G2.3.10 Ability to perform procedures to reduce 3.3 excessive levels of radiation and guard against personnel exposure.
295037 SCRAM Condition Present and x
EA2.0I Ability to determine and/or interpret the 4.2 Power Above APRM Downscale or following as they apply to SCRAM CONDITION Unknown 11 PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Reactor power 295038 High Off-site Release Rate 19 x
G2.3.2 Knowledge offacility ALARA program.
2.5 295038 High Off-site Release Rate 19 x
G2.2.25 Knowledge of bases in technical 3.7 specifications for limiting conditions for operations and safety limits.
600000 Plant Fire On Site I 8 x
AAl.OI Ability to operate and / or monitor the 3.0 following as they apply to PLANT FIRE ON SITE:
Respirator air pack 600000 Plant Fire On Site 18 x
AA2.04 Ability to determine and interpret the 3.1 following as they apply to PLANT FIRE ON SITE:
The fire's extent of potential operational damage to plant equipment KIA Category Totals:
4 3
3 4
3 3
Group Point Total:
20/7 4
3
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I ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I SRO)
EIAPE # I Name I Safety Function K
K K
A A
G KIA Topic(s)
IR 1
2 3
1 2
295002 Loss of Main Condenser Vac I 3 x
G2.1.18 Ability to make accurate I clear and concise 2.9 logs / records / status boards / and reports.
295007 High Reactor Pressure I 3 295008 High Reactor Water Levell 2 x
AK2.06 Knowledge ofthe interrelations between HIGH 3.4 REACTOR WATER LEVEL and the following:
RCIC 295009 Low Reactor Water Levell 2 x
AAI.02 Ability to operate and/or monitor the following as 4.0 they apply to LOW REACTOR WATER LEVEL:
Reactor water level control 295010 High Drywell Pressure 15 x
AK2.04 Knowledge ofthe interrelations between HIGH 2.6 DRYWELL PRESSURE and the following: Nitrogen makeup system 295011 High Containment Temp 15 295012 High Drywell Temperature I 5 x
G2.1.23 Ability to perform specific system and 4.0 integrated plant procedures during different modes of plant operation.
295013 High Suppression Pool Temp. 15 295014 Inadvertent Reactivity Addition 11 295015 Incomplete SCRAM 11 x
AK.3.01 Knowledge ofthe reasons for the following 3.4 responses as they apply to INCOMPLETE SCRAM :
Bypassing rod insertion blocks 295017 High Off-site Release Rate I 9 x
AA2.04 Ability to determine and/or interpret the-3.8 following as they apply to HIGH OFF-SITE RELEASE RATE: Source of off-site release 295020 Inadvertent Cont. Isolation I 5 & 7 295022 Loss of CRD Pumps 11 295029 High Suppression Pool Wtr LviI 5 295032 High Secondary Containment Area Temperature 15 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation x
EKI.OI Knowledge ofthe operational implications ofthe 3.8 High Radiation I 9 following concepts as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION:
Personnel protection 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High x
EA2.01 Ability to determine and/or interpret the 3.2 SumplArea Water Level/5 following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Operability of components within the affected area.
500000 High CTMT Hydrogen Cone. I 5 x
EA2.03 Ability to determine and / or interpret the 3.3 following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS:
Combustible limits for drywell KIA Category Point Totals:
I 2
1 I
I I
Group Point Total:
7/3 2
1
ES-401 BWR Examination Outline Fonn ES-401-1 Plant Systems - Tier 21Group 1 (RO I SRO)
System # I Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
4 203000 RHRlLPCI: Injection x
A3.08 Ability to monitor automatic operations of 4.1 Mode the RHRILPCI: INJECTION MODE (PLANT SPECIFIC) including: System initiation sequence 205000 Shutdown Cooling x
K2.0 I Knowledge ofelectrical power supplies to 3.1 the following: Pump motors 206000 HPCI x
K6.06 Knowledge ofthe effect that a loss or 3.1 malfunction ofthe following will have on the HIGH PRESSURE COOLANT INJECTION SYSTEM: SBGTS 206000 HPCI x
A4.14 Ability to manually operate and/or 4.2 monitor in the control room: System auto start control 209001 LPCS x
A2.03 Ability to (a) predict the impacts ofthe 3.4 following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences ofthose abnormal conditions or operations: A.C. failures 209001 LPCS x
G2.3.4 Knowledge of radiation exposure limits 3.1 and contamination control I including permissible levels in excess of those authorized.
211000 SLC x
KS.04 Knowledge ofthe operational implications 3.1 ofthe following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM:
Explosive Valve operation 211000 SLC x
G2.2.25 Knowledge ofbases in technical 2.5 specifications for limiting conditions for operations and safety limits.
212000 RPS x
K2.02 Knowledge of electrical power supplies to 2.7 the following: Analog trip system logic cabinets 2150031RM x
AI.02 Ability to predict and/or monitor changes 3.7 in parameters associated with operating the INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM controls including: Reactor power indication response to rod position changes 2150031RM x
A4.06 Ability to manually operate and/or 3.0 monitor in the control room: Detector drives 215004 Source Range Monitor x
KI.02 Knowledge ofthe physical connections 3.4 and/or causeeffect relationships between SOURCE RANGE MONITOR (SRM) SYSTEM and the following: Reactor Manual Control 215005 APRM I LPRM x
K5.05 Knowledge ofthe operational implications 3.6 ofthe following concepts as they apply to AVERAGE POWER RANGE MONITORILOCAL POWER RANGE MONITOR SYSTEM: Core flow effects on APRM trip setpoints
(
01 BWR Examination Outline Fonn ES-401-1 Plant Systems - Tier 21Group 1 (RO / SRO)
System # / Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1
2 3
4 5
'6 1
2 3
A2.07 Ability to (a) predict the impacts of the 3.4 following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Recirculation flow channels flow mismatch 217000 RCIC x
K2.0 I Knowledge of electrical power supplies to 2.8 the following: Motor operated valves 217000 RCIC x
G2.4.7 Knowledge of event based EOP 3.8 mitigation strategies.
218000 ADS x
AI.04 Ability to predict and/or monitor changes 4.1 in parameters associated with operating the AUTOMATIC DEPRESSURIZATION SYSTEM controls including: Reactor pressure 218000 ADS x
A2.05 Ability to (a) predict the impacts of the 3.6 following on the AUTOMATIC DEPRESSURIZATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences ofthose abnormal conditions or operations:
Loss of A.C. or D.C. power to ADS valves 223002 PCIS/Nuclear Steam x
KI.20 Knowledge ofthe physical connections 2.8 Supply Shutoff and/or causeeffect relationships between PRIMARY CONTAINMENT ISOLATION SYSTEMINUCLEAR STEAM SUPPLY SHUT-OFF and the following: AC Distribution 239002 SRVs x
A3.02 Ability to monitor automatic operations of 4.3 the RELIEF/SAFETY VALVES including: SRV operation on high reactor pressure 259002 Reactor Water Level x
A2.06 Ability to (a) predict the impacts ofthe 3.3 Control following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences ofthose abnormal conditions or operations: Loss ofcontroller signal output 259002 Reactor Water Level x
G2.3.1 Knowledge of 10 CFR: 20 and related 2.6 Control facility radiation control requirements.
261000 SGTS x
K3.03 Knowledge ofthe effect that a loss or 3.2 malfunction ofthe STANDBY GAS TREATMENT SYSTEM will have on following:
Primary containment pressure 261000 SGTS x
A4.02 Ability to manually operate and/or 3.1 monitor in the control room: Suction valves 262001 AC Electrical x
K3.03 Knowledge ofthe effect that a loss or 2.9 Distribution malfunction ofthe A.C. ELECTRICAL DISTRffiUTION will have on following: D.C.
electrical distribution
(
(
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO 1SRO)
System # 1Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
4 262001 AC Electrical x
A2.03 Ability to (a) predict the impacts of the 4.3 Distribution following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of off-site power 262002 UPS (AC/DC) x K6.02 Knowledge ofthe effect that a loss or 2.8 malfunction ofthe following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C.lD.C.): D.C. electrical power 263000 DC Electrical x
K4.02 Knowledge of D.C. ELECTRICAL 3.1 Distribution DISTRIBUTION design feature(s) and/or interlocks which provide for the following:
Breaker interlocks, permissives, bypasses and crossties 264000 EDGs x
K4.07 Knowledge of EMERGENCY 3.3 GENERATORS (DIESEUJET) design feature(s) and/or interlocks which provide for the following: Local operation and control 300000 Instrument Air x
A3.02 Ability to monitor automatic operations of 2.9 the INSTRUMENT AIR SYSTEM including:
Air temperature 400000 Component Cooling x
K6.01 Knowledge ofthe effect that a loss or 2.7 Water malfunction ofthe following will have on the CCWS: Valves nt Totals:
2 3
2 2
2 3
2 2
3 3
2 Group Point Total:
26/5 3
2
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 2 (RO / SRO)
System # / Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
4 201001 CRD Hydraulic x
K6.03 Knowledge ofthe effecfthat a loss 3.0 or malfunction ofthe following will have on the CONTROL ROD DRIVE HYDRAULIC System: Plant Air System 201002 RMCS 201003 Control Rod and Drive x
K5.03 Knowledge ofthe operational 3.3 Mechanism implications ofthe following concepts as they apply to CONTROL ROD AND DRIVE MECHANISM: Reactor power control 201004 RSCS 201005 RCIS 201006 RWM x
A2.06 Ability to (a) predict the impacts 3.3 of the following on the ROD WORTH MINIMIZER SYSTEM (RWH) (PLANT SPECIFIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Loss of reactor water level control input:
202001 Recirculation 202002 Recirculation Flow Control x
A4.07 Ability to manually operate and/or 3.3 monitor in the control room: Recirculation pump speed 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe x
G2.2.13 Knowledge of tagging and 3.8 clearance procedures.
215002 RBM 216000 Nuclear Boiler Inst.
X K2.0 I Knowledge of electrical power 2.8 supplies to the following: Analog trip system 219000 RHRlLPCI: Torus/Pool x
KI.08 Knowledge ofthe physical-2.6 Cooling Mode connections and/or causeeffect relationships between RHR/LPCI:
TORUS/SUPPRESSION POOL COOLING MODE and the following:
D.C. electrical power 223001 Primary CTMT and Aux.
226001 RHRlLPCI: CTMT Spray x
Knowledge ofthe effect that a loss or 3.6 Mode malfunction ofthe RHRlLPCI:
CONTAINMENT SPRAY SYSTEM MODE will have on following:
Containment/dryweIVsuppression chamber pressure 230000 RHRlLPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO I SRO)
. System # I Name K K K
K K
K A
A A
A G
KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
4 239001 Main and Reheat Steam x
K4.02 Knowledge of MAIN AND 3.1 REHEAT STEAM SYSTEM design feature(s) and/or interlocks which provide for the following: Automatic isolation and opening ofdrain valves:
241000 ReactorlTurbine Pressure Regulator 245000 Main Turbine Gen. I Aux.
x A3.04 Ability to monitor automatic 2.7 operations ofthe MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS including: Turbine Speed 256000 Reactor Condensate x
G2.4.21 Knowledge ofthe parameters and 3.7 logic used to assess the status of safety functions including:
I. Reactivity control
- 2. Core cooling and heat removal
- 3. Reactor coolant system integrity
- 4. Containment conditions
- 5. Radioactivity release control.
259001 Reactor Feedwater x
AI.04 Ability to predict and/or monitor 2.8 changes in parameters associated with operating the REACTOR FEEDWATER SYSTEM controls including: RFP turbine speed 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring x
A2.02 Ability to (a) predict the impacts of 3.3 the following on the RADIATION MONITORING SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences ofthose abnormal conditions or operations: Reactor protection system power failure 286000 Fire Protection x
A2.11 Ability to (a) predict the impacts 3.2 of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Pump trips 290002 Reactor Vessel Internals x
2.1.23 Ability to perform specific system 3.9 and integrated plant procedures during different modes ofplant operation.
KIA Category Point Totals:
I 1
1 1
1 I
1 1
I I
2 Group Point Total:
12/3 2
1 NUREG-1021, Revision 9
(
ES-401 Generic Knowledge and Abilities Outline Form ES-401-3 Facility:
BFN Date of Exam:
09/04/07 Category KIA #
Topic RO SRO-Onh IR IR Knowledge of less than one hour technical specification action 3.0 2.1.11 statements for sYStems.
Ability to explain and apply system limits and precautions.
3.4 1.
2.1.32 Conduct of Ability to execute procedure steps.
4.3 2.1.20 Operations Ability to apply technical specifications for a system.
4.0 2.1.12 Ability to recognize indications for system operating parameters 4.0 2.1.33 which are entry-level conditions for technical specifications.
2.1.
Subtotal
~
Knowledge ofthe design / procedural/and operational differences 3.1 2.2.3 between units.
Knowledge ofbases in technical specifications for limiting 2.5 2.2.25 conditions for ooerations and safety limits.
2.
Knowledge of tagging and clearance procedures.
3.8 2.2.13 Equipment Ability to analyze the affect of maintenance activities on LCO 3.8 Control 2.2.24 status.
2.2.
Subtotal
~
Knowledge offacility AURA program.
2.5 2.3.2 Knowledge ofradiation exposure limits and contamination control /
2.5 2.3.4 including permissible levels in excess ofthose authorized.
3.
2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control 3.0 reauirements.
Radiation 2.3.6 Ability to control radiation releases.
3.2 Control
~
Subtotal Knowledge ofsystem set points / interlocks and automatic actions 3.9 2.4.2 associated with EOP entry conditions.
Knowledge of general operating crew responsibilities during 3.4 4.
2.4.12 emergencv operations.
Emergency Knowledge ofannunciators alarms and indications / and use ofthe 3.3 2.4.31 response instructions.
Procedures /
Ability to prioritize and interpret the significance of each 3.6 Plan 2.4.45 annunciator or alarm.
2.4.
2.4.
Subtotal 9I Tier 3 Point Total M
10 7
ES-401 BWR Examination Outline Form ES-401-1 Facility:
BFN RO KIA Category Points SRO-Only Points Tier Group K
K K
G Total A2 G
.Total 1
2 3
1.
1 4
3 3
3 20 4
3 7
Emergency 2
1 2
1 1
7 2
1 3
&Abnormal Tier 5
5 4
4 27 6
4 10 Plant Evolutions Totals 2.
1 2
3 2
2 2
3 2
2 3
3 2
26 3
2 5
Plant 2
1 1
1 1
1 1
1 1
1 1
2 12 2
1 3
Systems Tier 3
4 3
3 3
4 3
3 4
4 4
38 5
3 8
Totals
- 3. Generic Knowledge and 1
2 3
4 1
2 3
4 Abilities Categories 10 7
3 2
2 3
2 2
2 1
Note: 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines i.e., except for one category in Tier 3 of the 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 +/-1 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 ES-401, Attachment 2, for guidance regarding the 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 KlAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.*
The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be~elevant to the applicable evolution or system.
. 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) 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. Use duplicate pages for RO and SRO-only exams.
9.
For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
17
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO 1SRO)
E/APE # 1Name 1Safety Function K
K K
A A
G KIA Topic(s)
IR I
2 3
1 2
295001 Partial or Complete Loss of Forced x
AK2.07 Knowledge ofthe interrelations between 3.4 Core Flow Circulation 11 &4 PARTIAL OR COMPLETE LOSS OF FORCED 171.007-026 CORE FLOW CIRCULATION and the following: Core flow indication 295001 Partial or Complete Loss of x
G2~2.3 Knowledge of the design / procedural/and 3.3 Forced Core Flow Circulation /1 & 4 operational differences between units.
171.007-021 295003 Partial or Complete Loss of AC 16 x
AA2.04 Ability to detennine and/or interpret the 3.5 171.047-032 following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: System lineups 295004 Partial or Total Loss of DC Pwr 16 x
AA2.02 Ability to determine and/or interpret the 3.5 171.037-061 following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Extent ofpartial or complete loss of D.C. power 295005 Main Turbine Generator Trip 13 x
AAI.05 Ability to operate and/or monitor the following 3.6 171.228-012 as they apply to MAIN TURBINE GENERATOR TRIP: Reactor/turbine pressure regulating system 295005 Main Turbine Generator Trip / 3 x
AA2.07 Ability to determine and/or interpret the 3.6 171.010-019 following as they apply to MAIN TURBINE GENERATOR TRIP: Reactor water level 295006*SCRAM 11 x
2.4.46 Ability to verify that the alarms are consistent 3.5 171.028-177 with the plant conditions.
295016 Control Room Abandonment 17 x
AAl.07 Ability to operate and/or monitor the following 4.2 171.208-009 as they apply to CONTROL ROOM ABANDONMENT: Control room/local control transfer mechanisms 295018 Partial or Total Loss of CCW 18 x
AKl.O1 Knowledge ofthe operational implications of 3.5 171.047-049 the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Effects on component/system operations 295019 Partial or Total Loss of lnst. Air 18 x
AK3.01 Knowledge ofthe reasons for the following 3.3 171.054-052 responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Backup air system supply 295019 Partial or Total Loss of Inst. Air /
x AA2.01 Ability to determine and/or interpret the 3.6 8
following as they apply to PARTIAL OR 171.054-054 COMPLETE LOSS OF INSTRUMENT AIR:
Instrument air system pressure 295021 Loss of Shutdown Cooling 14 x
AKl.04 Knowledge ofthe operational implications of 3~6 171.044-093 the following concepts as they apply to LOSS OF SHUTDOWN COOLING: Natural circulation 295023 Refueling Acc Cooling Mode 18 x
AK1.03 Knowledge ofthe operational itnplications of 3.7 171.098-007 the following concepts as they apply to REFUELING ACCIDENTS: Inadvertant Criticality 295024 High Drywell Pressure 15 x
EK3.06 Knowledge ofthe reasons for the following 4.0 171.028-178 responses as they apply to HIGH DRYWELL PRESSURE: Reactor Scram 295024 High Drywell Pressure / 5 x
EA2.06 Ability to determine and/or interpret the 4.1 171.203-135 following as they apply to HIGH DRYWELL PRESSURE: Suppression pool temperature 295025 High Reactor Pressure 13 x
EK2.09 Knowledge ofthe interrelations between HIGH 3.9 171.009-057 REACTOR PRESSURE and the following: Reactor power
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO 1SRO)
E/APE # 1Name 1Safety Function K
K K
A A
G K/A Topic(s)
IR I
2 3
I 2
295025 High Reactor Pressure 13 x
G2.4.4 Ability to recognize abnonnal indications for 4.0 171.202-062 system operating parameters which are entry-level conditions for etnergency and abnonnal operating procedures.
295026 Suppression Pool High Water x
EKI.02 Knowledge ofthe operational implications of 3.5 Temp. 15 the following concepts as they apply to SUPPRESSION 171.203-017 POOL HIGH WATER TEMPERATURE: Steam condensation 295027 High Containment Temperature 15 295028 High Drywell Temperature 15 x
EK3.0S Knowledge ofthe reasons for the following 3.6 171.203-084 responses as they apply to HIGH DRYWELL TEMPERATURE: Reactor SCRAM 295030 Low Suppression Pool Wtr Lvi 15 x
EAI.02 Ability to operate and/or monitor the following 3.4 171.042-215 as they apply to LOW SUPPRESSION POOL WATER LEVEL: RCIC 295031 Reactor Low Water Level /2 x
EK2.09 Knowledge ofthe interrelations between 3.3 171.007-018 REACTOR LOW WATER LEVEL and the following:
Recirculation system 295031 Reactor Low Water Levell 2 x
G2.3.10 Ability to perform procedures to reduce 3.3 171.098-017 excessive levels of radiation and guard against personnel exposure.
295037 SCRAM Condition Present and x
EA2.0 I Ability to detennine and/or interpret the 4.2 Power Above APRM Downscale or following as they apply to SCRAM CONDITION Unknown 11 PRESENT AND REACTOR POWER ABOVE APRM 171.202-027 DOWNSCALE OR UNKNOWN: Reactor power 295038 High Off-site Release Rate 19 x
G2.3.2 Knowledge offacility ALARA program.
2.5 171.000-001 295038 High Off-site Release Rate /9 x
G2.2.25 Knowledge of bases in technical 3.7 171.087-064 specifications for limiting conditions for operations and safety limits.
600000 Plant Fire On Site 18 x
AAI.O I Ability to operate and / or monitor the 3.0 171.000-002 following as they apply to PLANT FIRE ON SITE:
Respirator air pack 600000 Plant Fire On Site / 8 x
AA2.04 Ability to determine and interpret the 3.1 171.031-084 following as they apply to PLANT FIRE ON SITE:
The fire's extent of potential operational damage to plant equipment KIA Category Totals:
4 3
3 4
3 3
Group Point Total:
2017 4
3
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I SRO)
E/APE # I Name I Safety Function K
K K
A A
G KIA Topic(s)
IR 1
2 3
1 2
295002 Loss of Main Condenser Vac I 3 x
G2.1.18 Ability to make accurate / clear and concise 2.9 171.030-113 logs / records / status boards / and reports.
295007 High Reactor Pressure I 3 295008 High Reactor Water Level 12 x
AK2.06 Knowledge ofthe interrelations between HIGH 3.4 171.040-048 REACTOR WATER LEVEL and the following:
RCIC 295009 Low Reactor Water Level I 2 x
AAI.02 Ability to operate and/or monitor the following as 4.0 171.012-044 they apply to LOW REACTOR WATER LEVEL:
Reactor water level control 295010 High Drywell Pressure I 5 x
AK2.04 Knowledge ofthe interrelations betweenHIGH 2.6 171.017-106 DRYWELL PRESSURE and the following: Nitrogen makeup system 295011 High Containment Temp I 5 295012 High Drywell Temperature / 5 x
G2.1.23 Ability to perform specific system and 4.0 171.203-136 integrated plant procedures during different modes of plant operation.
295013 High Suppression Pool Temp. I 5 295014 Inadvertent Reactivity Addition I 1 295015 Incomplete SCRAM I 1 x
AK3.01 Knowledge ofthe reasons for the following 3.4 171.205-122 responses as they apply to INCOMPLETE SCRAM :
Bypassing rod insertion blocks 295017 High Off-site Release Rate / 9 x
AA2.04 Ability to determine and/or interpret the 3.8 171.204-053 following as they apply to HIGH OFF-SITE RELEASE RATE: Source of off-site release 295020 Inadvertent Cont. Isolation /5 &7 295022 Loss of CRD Pumps I 1 295029 High Suppression Pool Wtr Lvi I 5 295032 High Secondary Containment Area Temperature I 5 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation x
EKI.O I Knowledge ofthe operational implications ofthe 3.8 High Radiation I 9 following concepts as they apply to SECONDARY 171.067-043 CONTAINMENT VENTILATION HIGH RADIATION:
Personnel protection 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High x
EA2.01 Ability to determine and/or interpret the 3.2 Sump/Area Water Levell 5 following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Operability of components within the affected area.
500000 High CTMT Hydrogen Cone. I 5 x
EA2.03 Ability to detennine and / or interpret the 3.3 171.203-034 following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS:
Combustible limits for drywell KIA Category Point Totals:
I 2
I I
1 1
Group Point Total:
7/3 2
1
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)
System # / Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
4 203000 RHR/LPCI: Injection x
A3.08 Ability to Inonitor automatic operations of 4.1 Mode the RHR/LPCI: INJECTION MODE (PLANT 171.044-005 SPECIFIC) including: System initiation sequence 205000 Shutdown Cooling x
K2.0 1 Knowledge of electrical power supplies to 3.1 171.044-126 the following: Pump motors 206000 HPCI x
K6.06 Knowledge ofthe effect that a loss or 3.1 171.042-216 malfunction ofthe following will have on the HIGH PRESSURE COOLANT INJECTION SYSTEM: SBGTS 206000 HPCI x
A4.14 Ability to Inanually operate and/or 4.2 171.042-007 monitor in the control rOOln: System auto start control 209001 LPCS x
A2.03 Ability to (a) predict the impacts ofthe 3.4 171.045-018 following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate.the consequences of those abnormal.
conditions or operations: A.C. failures 209001 LPCS x
G2.3.4 Knowledge of radiation exposure limits 3.1 171.000-005 and contamination control/including permissible levels in excess of those authorized.
211000 SLC x
K5.04 Knowledge ofthe operational implications 3.1 171.039-017 ofthe following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM:
Explosive Valve operation 211000 SLC x
G2.2.25 Knowledge ofbases in technical 2.5 171.039-055 specifications for limiting conditions for operations and safety limits.
212000 RPS x
K2.02 Knowledge of electrical power supplies to 2.7 171.028-036 the following: Analog trip systeln logic cabinets 2150031RM x
Al.02 Ability to predictand/or Inonitor changes 3.7 171.020-012 in parameters associated with operating the INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM controls including: Reactor power indication response to rod position changes 2150031RM x
A4.06 Ability to Inanually operate and/or 3.0 171.020-018 Inonitor in the control room: Detector drives 215004 Source Range Monitor x
. Kl:02 Knowledge ofthe physical connections 3.4 171.019-012 and/or causeeffect relationships between SOURCE RANGE MONITOR (SRM) SYSTEM and the following: Reactor Manual Control 215005 APRM / LPRM x
K5.05 Knowledge ofthe operational itnplications 3.6 171.148-215 ofthe following concepts as they apply to AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM: Core flow effects on APRM trip setpoints
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO / SRO)
System # / Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
A2.07 Ability to (a) predict the impacts of the 3.4 171.148-009 following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Recirculation flow channels flow mismatch 217000 RCIC x
1<2.01 Knowledge ofelectrical power supplies to 2.8 171.040-034 the following: Motor operated valves 217000 RCIC x
G2.4.7 Knowledge of event based EOP 3.8 171.205-123 mitigation strategies.
218000 ADS x
Al.04 Ability to predict and/or monitor changes 4.1 171.043-001 in parameters associated with operating the AUTOMATIC DEPRESSURIZATION SYSTEM controls including: Reactor pressure 218000 ADS x
A2.05 Ability to (a) predict the impacts of the 3.6 171.205-124 following on the AUTOMATIC DEPRESSURIZATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Loss of A.C. or D.C. power to ADS valves 223002 PCIS/Nuclear Steam x
Kl.20 Knowledge ofthe physical connections 2.8 Supply Shutoff and/or causeeffect relationships between 171.017-120 PRIMARY CONTAINMENT ISOLATION SYSTEMINUCLEAR STEAM SUPPLY SHUT-OFF and the following: AC Distribution 239002 SRVs x
A3.02 Ability to monitor automatic operations of 4.3 171.009-052 the RELIEF/SAFETY VALVES including: SRV operation on high reactor pressure 259002 Reactor Water Level x
A2.06 Ability to (a) predict the impacts ofthe 3.3 Control following on the REACTOR WATER LEVEL 171.012-023 CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or tnitigate the consequences ofthose abnormal conditions or operations: Loss ofcontroller signal output 259002 Reactor Water Level x
G2.4.4 Ability to recognize abnonnal indications 4.0 Control for systetn operating parameters which are entry-171.012-086 level conditions for emergency and abnormal operating procedures.
261000 SGTS x
K3.03 Knowledge ofthe effect that a loss or 3.2 171.018-042 malfunction ofthe STANDBY GAS TREATMENT SYSTEM will have on following:
Primary containment pressure 261000 SGTS x
A4.02 Ability to manually operate and/or 3.1 171.018-006 tnonitor in the control room: Suction valves 262001 AC Electrical x
K3.03 Knowledge ofthe effect that a loss or 2.9 Distribution malfunction ofthe A.C. ELECTRICAL 171.072-024 DISTRIBUTION will have on following: D.C.
electrical distribution
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO I SRO)
System # I Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
4 262001 AC Electrical x
A2.03 Ability to (a) predict the impacts of the 4.3 Distribution following on the A.C. ELECTRICAL 171.036-015 DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of off"':site power 262002 UPS (AC/DC) x K6.02 Knowledge ofthe effect that a loss or 2;8 171.102-055 malfunction ofthe following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.): D.C. electrical power 263000 DC Electrical x
K4.02 Knowledge of D.C. ELECTRICAL 3.1 Distribution DISTRIBUTION design feature(s) and/or 171.037-010 interlocks which provide for the following:
Breaker interlocks, permissives, bypasses and crossties 264000 EDGs x
K4.07 Knowledge of EMERGENCY 3.3 171.038-264 GENERATORS (DIESEUJET) design feature(s) and/or interlocks which provide for the following: Local operation and control 300000 Instrument Air x
A3.02 Ability to monitor automatic operations of 2.9 171.054-053 the INSTRUMENT AIR SYSTEM including:
Air temperature 400000 Component Cooling x
K6.01 Knowledge ofthe effect that a loss or 2.7 Water malfunction ofthe following*will have on the 171.047-039 CCWS: Valves KIA Category Point Totals:
2 3
2 2
2 3
2 2
3 3
2 Group Point Total:
26/5 3
2
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO / SRO)
System # / Name K
K K
K K
K A
A A
A G
KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
4 201001 CRD Hydraulic x
K6.03 Knowledge ofthe effect that a loss 3.0 171.005-046 or Inalfunction ofthe following will have on the CONTROL ROD DRIVE HYDRAULIC System: Plant Air System 201002 RMCS 201003 Control Rod and Drive x
K5.03 Knowledge ofthe operational 3.3 Mechanism implications ofthe following concepts as 171.006-043 they apply to CONTROL ROD AND DRIVE MECHANISM: Reactor power control 201004 RSCS 201005 RCIS 201006 RWM x
A2.06 Ability to (a) predict the impacts 3.3 171.024-088 of the following on the ROD WORTH MINIMIZER SYSTEM (RWH) (PLANT SPECIFIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Loss of reactor water level control input:
202001 Recirculation 202002 Recirculation Flow Control x
A4.07 Ability to manually operate and/or 3.3 171.007-020 monitor in the control room: Recirculation puinp speed 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe x
G2.2.13 Knowledge of tagging and 3.8 171.016-097 clearance procedures.
215002 RBM 216000 Nuclear Boiler Inst.
X K2.0 1 Knowledge of electrical power 2.8 171.003-041 supplies to the following: Analog trip systeln 219000 RHR/LPCI: Torus/Pool x
K1.08 Knowledge ofthe physical 2.6 Cooling Mode connections and/or causeeffect 171.044-114 relationships between RHR/LPCI:
TORUS/SUPPRESSION POOL COOLING MODE and the following:
D.C. electrical power 223001 Primary CTMT and Aux.
226001 RHR/LPCI: CTMT Spray x
K3.01 Knowledge ofthe effect that a loss 3.6 Mode or malfunction ofthe RHRILPCI:
171.203-134 CONTAINMENT SPRAY SYSTEM MODE will have on following:
Contairunent/drywell/suppression chamber pressure 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment
ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO I SRO)
System # I Name K
K K
K K
K, A
A A
A G
KIA Topic(s)
IR 1
2 3
4 5
6 1
2 3
4 239001 Main and Reheat Steam x
K4.02 Knowledge of MAIN AND 3.1 171.009-056 REHEAT STEAM SYSTEM design feature(s) and/or interlocks which provide for the following: Automatic isolation and opening of drain valves:
241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. I Aux.
x A3.04 Ability to monitor automatic 2.7 171.228-020 operations ofthe MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS including: Turbine Speed 256000 Reactor Condensate x
G2.4.21 Knowledge ofthe parameters and 3.7 171.201-062 logic used to 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.
259001 Reactor Feedwater x
Al.04 Ability to predict and/or monitor 2.8 171.012-085 changes in parameters associated with operating the REACTOR FEEDWATER SYSTEM controls including: RFP turbine speed 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring x
A2.02 Ability to (a) predict the impacts of 3.3 171.033-060 the following on the RADIATION MONITORING SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences ofthose abnormal conditions or operations: Reactor protection systeln power failure 286000 Fire Protection x
A2.11 Ability to (a) predict the impacts 3.2 171.049-025 of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Pump trips 290002 Reactor Vessel Internals x
2.1.23 Ability to perfonn specific system 3.9 171.044-052 and integrated plant procedures during different modes ofplant operation.
KIA Category Point Totals:
1 1
1 1
1 1
1 1
1 1
2 Group Point Total:
12/3 2
1 NUREG-1 021, Revision 9
ES-401 Generic Knowledge and Abilities Outline Form ES-401-3 Facility:
BFN Date of Exam:
09/04/07 Category KIA #
Topic RO SRO-Only IR IR Knowledge of less than one hour technical specification action 3.0 2.1.11 statelnents for systems. 171.028-179 Ability to explain and apply system limits and precautions.
3.4 1.
2.1.32 171.007-192 Conduct of Ability to execute procedure steps.
4.3 2.1.20 171.042-217 Operations Ability to apply technical specifications for a system.
4.0 2.1.12 171.018-122 Ability to recognize indications for system operating parameters 4.0 2.1.33 which are entry-level conditions for technical specifications.
171.016-105 2.1.
Subtotal
~
Knowledge ofthe design / procedural/and operational differences 3.1 2.2.3 between units. 171.026-053 Knowledge ofbases in technical specifications for lilniting 2.5 2.2.25 conditions for operations and safety limits. 171.087-063 2.
Knowledge of tagging and clearance procedures.
3.8 2.2.13 171.086-004 Equipment Ability to analyze the affect of maintenance activities on LCO 3.8 Control 2.2.24 status. 171.046-032 2.2.
Subtotal
~
Knowledge of facility ALARA program.
2.5 2.3.2 171.000-003 Knowledge ofradiation exposure limits and contalnination control/
2.5 2.3.4 including permissible levels in excess ofthose authorized.
3.
171.000-004 Knowledge of 10 CFR: 20 and related facility radiation control 3.0 Radiation 2.3.1 requirements. 171.000-006,
Control 2.3.11 Ability to control radiation releases.
3.2 171.033-014 Subtotal
~
Knowledge of systeln set points / interlocks and automatic actions 3.9 2.4.2 associated with EOP entry conditions. 171.044-264 Knowledge of general operating crew responsibilities during 3.4 4.
2.4.12 emergency operations. 171.075-001 Emergency Knowledge of annunciators alanns and indications / and use ofthe 3.3 2.4.31 response instructions. 171.018-043 Procedures 1 Ability to prioritize and interpret the significance of each 3.6 Plan 2.4.45 annunciator or alarm. 171.033-019 2.4.
2.4.
Subtotal Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Tier /
Randomly Reason for Rejection Group Selected KIA T2Gl 259002G2.3.1 Unable to write a question to tie Feedwater level control to 10CFR20 Rad requirements. Replaced with 259002G2.4.4 per Ron Aiello 6/20/2007 28