ML14318A458
| ML14318A458 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/15/2014 |
| From: | Operations Branch I |
| To: | FitzPatrick |
| Shared Package | |
| ML14101A125 | List: |
| References | |
| TAC U01887 | |
| Download: ML14318A458 (26) | |
Text
ES-401 Written Examination Outline Form ES-401-1 Facility:
James A. Fitzpatrick Date of Exam:
September 2014 RO KIA Category Points SRO-Only Points Tier Group K
K K
K K
K A
A A
A G
A2 G*
Total 1
2 3
4 5
6 1
2 3
4 Total
- 1.
1 3
4 3
3 3
4 20 3
4 7
Emergency 2
1 2
1 1
1 1
7 1
2 3
Plant Tier Evolutions Totals 4
6 4
4 4
5 27 4
6 10 1
3 2
3 3
2 3
2 1
2 3
2 26 2
3 5
- 2.
2 Plant 2
0 1
1 1
1 1
2 1
1 1
12 0
2 1
3 Systems Tier Totals 5
2 4
4 3
4 3
3 3
4 3
38 4
4 8
- 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 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 section D.1.b of ES-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) 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) KIAs 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. Refer to Section D.1.b of ES-401 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. If fuel 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 of the KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 1 OCFR55.43
ES-401 2
JAF 14-2 NRC Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 EAPE # I Name Safety Function KIA Topic(s)
EA2.03-Ability to determine and/or 295030 Low Suppression Pool X
interpret the following as they apply to 3.9 76 Water Level I 5 LOW SUPPRESSION POOL WATER LEVEL: Reactor pressure AA2.02-Ability to determine and/or interpret the following as they apply to 295019 Partial or Complete X
PARTIAL OR COMPLETE LOSS OF 3.7 77 Loss of Instrument Air I 8 INSTRUMENT AIR: Status of safety-related instrument air system loads (see AK2.1 - AK2.19)
EA2.05 -Ability to determine and/or 295028 High Drywell interpret the following as they apply to X
HIGH DRYWELL TEMPERATURE:
3.8 78 Temperature I 5 Torus/suppression chamber pressure:
Plant-Specific 2.4.4 - Emergency Procedures I Plan:
295038 High Off-site Release Ability to recognize abnormal indications Rate I 9 X
for system operating parameters that 4.7 79 are entry-level conditions for emergency and abnormal operating procedures.
700000 Generator Voltage and 2.2.37 -Ability to determine operability X
and/or availability of safety related 4.6 80 Electric Grid Disturbances equipment.
295016 Control Room 2.4.11 - Emergency Procedures I Plan:
Abandonment I 7 X
Knowledge of abnormal condition 4.2 81 procedures.
2.4.41 -Emergency Procedures I Plan:
295023 Refueling Accidents I 8 X
Knowledge of the emergency action 4.6 82 level thresholds and classifications.
AK1.01 -Knowledge of the operational 295001 Partial or Complete implications of the following concepts as Loss of Forced Core Flow X
they apply to PARTIAL OR COMPLETE 3.5 39 Circulation I 1 & 4 LOSS OF FORCED CORE FLOW CIRCULATION: Natural circulation AK1.03-Knowledge of the operational 295023 Refueling Accidents I 8 X
implications of the following concepts as 3.7 40 they apply to REFUELING ACCIDENTS: Inadvertent criticality AK1.02 - Knowledge of the operation 600000 Plant Fire On-site I 8 X
applications of the following concepts 2.9 41 as they apply to Plant Fire On Site: Fire Fighting AK2.07-Knowledge of the interrelations 295006 SCRAM I 1 X
between SCRAM and the following:
4.0 42 Reactor pressure control EK2.07-Knowledge of the interrelations 295030 Low Suppression Pool between LOW SUPPRESSION POOL Water Level I 5 X
WATER LEVEL and the following:
3.5 43 Downcomer/horizontal vent submergence AK2.01 -Knowledge of the interrelations 295004 Partial or Complete X
between PARTIAL OR COMPLETE 3.1 44 Loss of DC Power I 6 LOSS OF D.C. POWER and the following: Battery charger AK3.03-Knowledge of the reasons for 295016 Control Room
.X the following responses as they apply to 3.5 45 Abandonment I 7 CONTROL ROOM ABANDONMENT:
Disabling control room controls 295025 High Reactor Pressure I X
EK3.03-Knowledge of the reasons for 3.8 46 3
the following responses as they apply to
ES-401 2
JAF 14-2 NRC Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE #I Name Safety Function KJA Topic(s)
HIGH REACTOR PRESSURE: HPCI operation: Plant-Specific EK3.05-Knowledge of the reasons for 295031 Reactor Low Water X
the following responses as they apply to 4.2 47 Level/2 REACTOR LOW WATER LEVEL:
Emergency depressurization AA 1.02 -Ability to operate and/or 295003 Partial or Complete X
monitor the following as they apply to 4.2 48 Loss of AC Power I 6 PARTIAL OR COMPLETE LOSS OF A. C. POWER: Emergency generators AA 1.02-Ability to operate and/or 295019 Partial or Complete monitor the following as they apply to X
PARTIAL OR COMPLETE LOSS OF 3.3 49 Loss of Instrument Air I 8 INSTRUMENT AIR: Instrument air system valves: Plant-Specific EA 1.07-Ability to operate and/or 295038 High Off-site Release X
monitor the following as they apply to 3.6 50 Rate /9 HIGH OFF-SITE RELEASE RATE:
Control room ventilation: Plant-Specific EA2.02-Ability to determine and/or 295024 High Drywell Pressure I X
interpret the following as they apply to 3.9 51 5
HIGH DRYWELL PRESSURE: Drywell temperature AA2.04-Ability to determine and/or 295018 Partial or Complete interpret the following as they apply to Loss of CCW I 8 X
PARTIAL OR COMPLETE LOSS OF 2.9 52 COMPONENT COOLING WATER:
System flow AA2.07-Ability to determine and/or 295021 Loss of Shutdown X
interpret the following as they apply to 2.9 53 Cooling /4 LOSS OF SHUTDOWN COOLING:
Reactor recirculation flow 2.4.30 - Emergency Procedures I Plan:
Knowledge of events related to system 700000 Generator Voltage and X
operation I status that must be reported 2.7 54 Electric Grid Disturbances to internal organizations or external agencies, such as the state, the NRC, or the transmission system operator.
295005 Main Turbine Generator 2.1.20 - Conduct of Operations: Ability Trip /3 X
to interpret and execute procedure 4.6 55 steps.
295026 Suppression Pool High 2.4.18 - Emergency Procedures I Plan:
Water Temperature I 5 X
Knowledge of the specific bases for 3.3 56 EOPs.
EK2.03-Knowledge of the interrelations 295028 High Drywell X
between HIGH DRYWELL 3.6 57 Temperature I 5 TEMPERATURE and the following:
Reactor water level indication 295037 SCRAM Conditions 2.4.4 - Emergency Procedures I Plan:
Present and Reactor Power Ability to recognize abnormal indications Above APRM Downscale or X
for system operating parameters that 4.5 58 Unknown /1 are entry-level conditions for emergency and abnormal operating procedures.
KJA Category Totals:
3 4
3 3
3/3 4/4 Group Point Total:
I 2017
ES-401 3
JAF 14-2 NRC Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 EAPE #I Name Safety Function KIA Topic(s)
AA2.02 -Ability to determine and/or 295015 Incomplete SCRAM /1 X
interpret the following as they apply to 4.2 83 INCOMPLETE SCRAM: Control rod position 2.4.47-Emergency Procedures I Plan:
295036 Secondary Ability to diagnose and recognize trends Containment High Sump/Area X
in an accurate and timely manner 4.2 84 Water Level/ 5 utilizing the appropriate control room reference material.
295009 Low Reactor Water 2.4.31 -Emergency Procedures I Plan:
Level/2 X
Knowledge of annunciator alarms, 4.1 85 indications, or response procedures.
EK1.01 - Knowledge of the operational 295029 High Suppression Pool implications of the following concepts as Water Level/ 5 X
they apply to HIGH SUPPRESSION 3.4 59 POOL WATER LEVEL: Containment integrity AK2.05-Knowledge of the interrelations 295002 Loss of Main X
between LOSS OF MAIN CONDENSER 2.7 60 Condenser Vacuum I 3 VACUUM and the following: Feedwater system AK3.01 - Knowledge of the reasons for 295009 Low Reactor Water the following responses as they apply to Level/2 X
LOW REACTOR WATER LEVEL:
3.2 61 Recirculation pump run back: Plant-Specific AA 1.01 -Ability to operate and/or 29501 0 High Drywell Pressure I X
monitor the following as they apply to 3.4 62 5
HIGH DRYWELL PRESSURE: Drywell ventilation/cooling AA2.03-Ability to determine and/or 295020 Inadvertent X
interpret the following as they apply to 3.7 63 Containment Isolation I 5 & 7 INADVERTENT CONTAINMENT ISOLATION: Reactor power 2.1.31 -Conduct of Operations: Ability to 500000 High Containment locate control room switches, controls, Hydrogen Concentration I 5 X
and indications, and to determine that 4.6 64 they correctly reflect the desired plant lineup.
AK2.09-Knowledge of the interrelations 295008 High Reactor Water between HIGH REACTOR WATER Level/2 X
LEVEL and the following: Reactor water 3.1 65 cleanup system (ability to drain): Plant-Specific KIA Category Totals:
1 2
1 1
1/1 1/2 Group Point Total:
7/3
ES-401 System # I Name K
K K
1 2
3 259002 Reactor Water Level Control System 223002 PCIS/Nuclear Steam Supply Shutoff 262001 AC Electrical Distribution 2150031RM 215005 APRM I LPRM 203000 RHRILPCI: Injection X
Mode 400000 Component Cooling Water X
209001 LPCS X
212000 RPS X
4 Form ES-401-1 JAF 14-2 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
A2.01 -Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b)
X based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of any number of main steam flow in outs A2.11 -Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM X
SUPPLY SHUT-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Standby liquid initiation 2.2.38 - Equipment Control:
X Knowledge of conditions and limitations in the facilitv license.
2.1.25 - Conduct of Operations:
X Ability to interpret reference materials, such as graphs, curves, tables, etc.
2.1. 7 - Conduct of Operations:
Ability to evaluate plant performance and make X
operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
K1.01 - Knowledge of the physical connections and/or cause-effect relationships between RHRILPCI:
INJECTION MODE (PLANT SPECIFIC) and the following:
Condensate storage and transfer system: Plant-Soecific K1.04-Knowledge of the physical connections and I or cause-effect relationships between CCWS and the following: Reactor coolant system, in order to determine source (s)
K2.02 -Knowledge of electrical power supplies to the following:
Valve oower K2.01 -Knowledge of electrical power supplies to the following:
RPS motor-aenerator sets Imp.
Q#
3.4 86 3.9 87 4.5 88 4.2 89 4.7 90 2.8 1
2.9 2
2.5 3
3.2 4
ES-401 System # I Name K
K K
1 2
3 262002 UPS (AC/DC)
X 205000 Shutdown Cooling X
223002 PC IS/Nuclear Steam Supply Shutoff 215004 Source Range Monitor 259002 Reactor Water Level Control 218000 ADS 261000 SGTS 217000 RCIC 264000 EDGs 4
Form ES-401-1 JAF 14-2 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
K3.11 - Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER SUPPLY (A. C./D.C.) will have on following: MSIVs: Plant-Specific K3.02 - Knowledge of the effect that a loss or malfunction of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) will have on following: Reactor water level:
Plant-Specific K4.06-Knowledge of PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF design X
feature(s) and/or interlocks which provide for the following:
Once initiated, system reset requires deliberate operator action K4.04 - Knowledge of SOURCE RANGE MONITOR (SRM)
X SYSTEM design feature(s) and/or interlocks which provide for the following: Changing detector position K5.03 - Knowledge of the operational implications of the X
following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM: Water level measurement K5.01 - Knowledge of the operational implications of the X
following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM: ADS loaic operation K6.05-Knowledge of the effect that a loss or malfunction of the X
following will have on the STANDBY GAS TREATMENT SYSTEM: Reactor protection system: Plant-Specific K6.03-Knowledge of the effect that a loss or malfunction of the X
following will have on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC):
Suppression pool water supply A 1.01 -Ability to predict and/or monitor changes in parameters X
associated with operating the EMERGENCY GENERA TORS (DIESEUJET) controls including:
Lube oil temperature Imp.
Q#
2.8 5
3.2 6
3.4 7
2.8 8
3.1 9
3.8 10 3.1 11 3.5 12 3.0 13
ES-401 System # I Name K
K K
1 2
3 215003 IRM 263000 DC Electrical X
Distribution 215005 APRM I LPRM 206000 HPCI 239002 SRVs 211000 SLC 300000 Instrument Air 262001 AC Electrical Distribution 217000 RCIC 4
Form ES-401-1 JAF 14-2 NRC Exam Written Examination Outline Plant Systems -Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
A 1.06-Ability to predict and/or monitor changes in parameters associated with operating the X
INTERMEDIATE RANGE MONITOR (IRM) SYSTEM controls including: Lights and alarms K3.03-Knowledge of the effect that a loss or malfunction of the D.C. ELECTRICAL DISTRIBUTION will have on following: Systems with D.C.
components (i.e. valves, motors, solenoids, etc.)
A2.07-Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; X
and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions:
Recirculation flow channels flow mismatch A3.02 -Ability to monitor automatic operations of the X
HIGH PRESSURE COOLANT INJECTION SYSTEM including:
System Flow: BWR-2,3,4 A3.04-Ability to monitor automatic operations of the X
RELIEF/SAFETY VALVES including: Acoustical monitor noise: Plant-Specific A4.07-Ability to manually X
operate and/or monitor in the control room: Lights and alarms A4.01 -Ability to manually X
operate and/or monitor in the control room: Pressure gauges 2.4.21 - Emergency Procedures I Plan: Knowledge of the parameters and logic used to assess the status of safety X
functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
2.4.2 - Emergency Procedures I Plan: Knowledge of system set X
points, interlocks and automatic actions associated with EOP entry conditions.
Imp.
Q#
3.3 14 3.4 15 3.2 16 3.8 17 3.6 18 3.6 19 2.6 20 4.0 21 4.5 22
ES-401 System #I Name K
K K
1 2
3 263000 DC Electrical Distribution X
211000 SLC 206000 HPCI 259002 Reactor Water Level Control KIA Category Totals:
3 2
3 4
Form ES-401-1 JAF 14-2 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
A A2 A
A G
4 5
6 1
3 4
K1.01 - Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECTRICAL DISTRIBUTION and the following: A.C. electrical distribution K4.08-Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s)
X and/or interlocks which provide for the following: System initiation upon operation of SBLC control switch A4.09-Ability to manually X
operate and/or monitor in the control room: Suppression pool level: BWR-2,3,4 K6.01 -Knowledge of the effect that a loss or malfunction of the X
following will have on the REACTOR WATER LEVEL CONTROL SYSTEM: Plant air systems 3
2 3
2 1/2 2
3 2/3 Group Point Total:
Imp.
Q#
3.3 23 4.2 24 3.8 25 3.2 26 I
26/5
ES-401 System #I Name K
K K
1 2
3 202002 Recirculation Flow Control 245000 Main Turbine Generator and Auxiliary Systems 288000 Plant Ventilation Systems 233000 Fuel Pool Cooling/Cleanup X
259001 Reactor Feedwater X
239001 Main and Reheat X
Steam 202002 Recirculation Flow Control 241000 Reactor/Turbine Pressure Regulating System 5
Form ES-401-1 JAF 14-2 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K
K K A A2 A
A G
4 5
6 1
3 4
A2.09-Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM; and (b)
X based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation flow mismatch: Plant-Specific 2.4.50- Emergency Procedures I Plan: Ability to verify system X
alarm setpoints and operate controls identified in the alarm response manual.
A2.01 -Ability to (a) predict the impacts of the following on the PLANT VENTILATION SYSTEMS; and (b) based on X
those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High drywell pressure: Plant-Specific K 1.14 - Knowledge of the physical connections and/or cause-effect relationships between FUEL POOL COOLING AND CLEAN-UP and the following: Reactor building ventilation K1.20- Knowledge of the physical connections and/or cause-effect relationships between REACTOR FEEDWATER SYSTEM and the following: Main steam system:
TDRFPs-Only K3.02 -Knowledge of the effect that a loss or malfunction of the MAIN AND REHEAT STEAM SYSTEM will have on following:
Condenser K4.03-Knowledge of RECIRCULATION FLOW CONTROL SYSTEM design X
feature(s) and/or interlocks which provide for the following:
Signal failure detection: Plant-Specific K5.03-Knowledge of the operational Implications of the following concepts as they apply X
to REACTOR/TURBINE PRESSURE REGULATING SYSTEM: Reactor power vs.
reactor pressure Imp.
Q#
3.3 91 4.0 92 3.4 93 2.5 27 3.1 28 3.1 29 3.0 30 3.5 31
ES-401 System #I Name K
K K
1 2
3 286000 Fire Protection 272000 Radiation Monitoring 234000 Fuel Handling Equipment 288000 Plant Ventilation Systems 271000 Offgas 290003 Control Room HVAC 215001 Traversing In-core Probe KIA Category Totals:
2 0
1 5
Form ES-401-1 JAF 14-2 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K
K K
A A2 A
A G
4 5
6 1
3 4
K6.01 - Knowledge of the effect that a loss or malfunction of the X
following will have on the FIRE PROTECTION SYSTEM: A.C.
electrical distribution: Plant-Specific A 1.01 -Ability to predict and/or monitor changes in parameters associated with operating the X
RADIATION MONITORING SYSTEM controls including:
Lights, alarms, and indications associated with normal operations A2.01 -Ability to (a) predict the impacts of the following on the FUEL HANDLING EQUIPMENT; and (b) based on X
those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or OQ_erations: Interlock failure A3.01 -Ability to monitor automatic operations of the X
PLANT VENTILATION SYSTEMS including:
Isolation/initiation signals A4.09-Ability to manually X
operate and/or monitor in the control room: Offgas system controls/components 2.4.47 - Emergency Procedures I Plan: Ability to diagnose and X
recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
A2.01 -Ability to (a) predict the impacts of the following on the TRAVERSING IN-CORE PROBE; and (b) based on those X
predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low reactor water level: Mark-I&I!{_Not-BWR1_l 1
1 1
1 212 1
1 1/1 Group Point Total:
Imp.
Q#
3.1 32 3.2 33 3.3 34 3.8 35 3.3 36 4.2 37 2.7 38 I
12/3
Facility:
James A. Fitzpatrick Date:
September 2014 RO SRO-Only Category KIA#
Topic Q#
Q#
IR IR 2.1.34 Knowledge of primary and secondary plant 3.5 94 chemistry limits.
2.1.32 Ability to explain and apply all system limits 3.8 66
- 1.
and precautions.
Conduct Knowledge of industrial safety procedures of Operations 2.1.26 (such as rotating equipment, electrical, high 3.4 67 temperature, high pressure, caustic, chlorine, oxygen and hydrogen).
2.1.30 Ability to locate and operate components, 4.4 75 including local controls.
Subtotal 3
1 Knowledge of the process for managing 2.2.18 maintenance activities during shutdown 3.9 95 operations, such as risk assessments, work prioritizaion, etc.
2.2.40 Ability to apply technical specifications for a 4.7 99 system.
- 2.
Equipment Ability to perform pre-startup procedures for Control 2.2.1 the facility, including operating those controls 4.5 68 associated with plant equipment that could affect reactivity.
2.2.43 Knowledge of the process used to track 3.0 69 inoperable alarms.
Subtotal 2
2 Knowledge of radiation or containment 2.3.14 hazards that may arise during normal, 3.8 96 abnormal, or emergency conditions or activities.
Ability to use radiation monitoring systems,
- 3.
2.3.5 such as fixed radiation monitors and alarms, 2.9 100 portable survey instruments, personnel Radiation monitoring equipment, etc.
Control Knowledge of radiation monitoring systems, 2.3.15 such as fixed radiation monitors and alarms, 2.9 70 portable survey instruments, personnel monitoring equipment, etc.
Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such 2.3.12 as containment entry requirements, fuel 3.2 71 handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Subtotal 2
2 Knowledge of local auxiliary operator tasks 2.4.35 during an emergency and the resultant 4.0 97 operational effects.
Knowledge of events related to system operation I status that must be reported to 2.4.30 internal organizations or external agencies, 4.1 98 such as the state, the NRC, or the transmission system operator.
- 4.
Emergency Knowledge of the parameters and logic used Procedures I to assess the status of safety functions, such Plan as reactivity control, core cooling and heat 2.4.21 removal, reactor coolant system integrity, 4.0 72 containment conditions, radioactivity release control, etc.
2.4.27 Knowledge of "fire in the plant" procedures.
3.4 73 2.4.28 Knowledge of procedures relating to a 3.2 74 security event (non-safeguards information).
Subtotal 3
2 Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 Tier I Randomly Selected KIA Reason for Rejection Group The following topics I K/As were excluded from the systematic and random sampling process:
295027 High Containment This topic applies to plants with Mark Ill 1 /1 Temperature containments only. The facility has a Mark I containment.
295011 High Containment This topic applies to plants with Mark Ill 1 /2 Temperature containments only. The facility has a Mark I containment.
207000 Isolation (Emergency)
This system is not installed at the facility.
2/1 Condenser 209002 HPCS This system is not installed at the facility.
2/1 201004 RSCS This system is no longer installed at the facility.
2/2 201005 RCIS This system is not installed at the facility.
2/2 2.2.3 Knowledge of the design, This KIA applies to multi-unit facilities only.
G procedural, and operational differences between units.
2.2.4 Ability to explain the This KIA applies to multi-unit facilities only.
variations in control board/control room layouts, G
systems, instrumentation, and procedural actions between units at a facility.
The following KJAs were rejected following the svstematic and random samolina ""~:
Question 91 The facility is a BWR-4 and does not have 202002 Recirculation Flow Recirculation flow control valves (FCVs).
Control Randomly re-selected KIA 202002 Recirculation Flow Control A2.01 -Ability to (a)
A2.08 -Ability to (a) predict the predict the impacts of the following on the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM; RECIRCULATION FLOW and (b) based on those predictions, use 2/2 CONTROL SYSTEM; and (b) procedures to correct, control, or mitigate the based on those predictions, use consequences of those abnormal conditions or procedures to correct, control, operations: Recirculation pump trip or mitigate the consequences of those abnormal conditions or operations: FCV lockup: BWR-5,6 Question 28 The facility has steam-driven Feedwater 259001 Reactor Feedwater pumps, not motor-driven Feedwater pumps.
Randomly re-selected KIA 259001 Reactor K2.01 -Knowledge of electrical Feedwater K1.20- Knowledge of the physical 2/2 power supplies to the following:
connections and/or cause-effect relationships Reactor feedwater pump(s):
between REACTOR FEEDWATER SYSTEM Motor-Driven-Only and the following: Main steam system:
TDRFPs-Only Question 31 The facility does not have a unitized actuator as 241000 Reactor/Turbine part of the Reactor/Turbine Pressure Regulating System.
Pressure Regulating System Randomly re-selected KIA 241000 K5.07-Knowledge of the Reactor/Turbine Pressure Regulating System 2/2 operational Implications of the K5.03-Knowledge of the operational following concepts as they Implications of the following concepts as they apply to REACTOR/TURBINE apply to REACTOR/TURBINE PRESSURE PRESSURE REGULATING REGULATING SYSTEM: Reactor power vs.
SYSTEM: Unitized actuator reactor pressure operation: Fermi-Only
Question 17 Unable to be develop a question for the randomly selected KIA without overlapping with 206000 HPCI Question 12.
A3.08 -Ability to monitor Randomly reselected KIA 206000 HPCI A3.02-automatic operations of the Ability to monitor automatic operations of the 2/1 HIGH PRESSURE COOLANT HIGH PRESSURE COOLANT INJECTION INJECTION SYSTEM including: SYSTEM including: System Flow: BWR-2,3,4 Condensate storage tank level:
BWR-2,3,4 Question 21 Unable to develop a question at the correct license level for the randomly selected generic 262001 AC Electrical KIA related to the given system.
Distribution Randomly reselected KIA 262001 AC Electrical 2.4.41 - Emergency Procedures Distribution 2.4.21 -Emergency Procedures I I Plan: Knowledge of the Plan: Knowledge of the parameters and logic 2/1 emergency action level used to assess the status of safety functions, thresholds and classifications.
such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
Question 23 Unable to develop a question without overlap 263000 DC Electrical with question on last NRC exam. Resampling to limit overlap.
Distribution Randomly reselected KIA 263000 DC Electrical K5.01 -Knowledge of the Distribution K1.01 -Knowledge of the physical 2/1 operational implications of the connections and/or cause-effect relationships following concepts as they between D.C. ELECTRICAL DISTRIBUTION apply to D.C. ELECTRICAL and the following: A. C. electrical distribution DISTRIBUTION: Hydrogen generation during battery charging
Question 30
!he facility does not have a design feature or 202002 Recirculation Flow Interlock specifically related to break of a scoop Control tube.
K4.01 - Knowledge of Randomly re-selected KIA 202002 2/2 RECIRCULATION FLOW Recirculation Flow Control K4.03-Knowledge CONTROL SYSTEM design of RECIRCULATION FLOW CONTROL feature(s) and/or interlocks SYSTEM design feature(s) and/or interlocks which provide for the following:
which provide for the following: Signal failure Scoop tube break: Plant-detection: Plant-Specific Specific Question 58 The randomly selected generic KIA is 295037 SCRAM Conditions oversampled on this exam (Questions 37 58 Present and Reactor Power 84, 89).
Above APRM Downscale or Randomly re-selected KIA 295037 SCRAM Unknown Conditions Present and Reactor Power Above 1 /1 2.4.47-Emergency Procedures APRM.Downscale or Unknown 2.4.4 - Ability to I Plan: Ability to diagnose and recogmze abnormal indications for system recognize trends in an accurate operating parameters that are entry-level and timely manner utilizing the conditions for emergency and abnormal appropriate control room operating procedures.
reference material.
Question 61 The facility does not have a specific Feedwater 295009 Low Reactor Water pump run-out flow control feature.
Level Randomly re-selected KIA 295009 Low Reactor AK3.02-Knowledge of the Water Level AK3.01 - Knowledge of the 1 /2 reasons for the following reasons for the following responses as they responses as they apply to apply to LOW REACTOR WATER LEVEL*
LOW REACTOR WATER Recirculation pump run back: Plant-Specific.
LEVEL: Reactor feedpump runout flow control: Plant-Specific
Question 81 The randomly selected generic KIA does not support developing an operationally relevant 295016 Control Room question for the randomly selected abnormal Abandonment plant evolution.
2.2.42 - Equipment Control:
Randomly re-selected KIA 295016 Control 1 I 1 Ability to recognize system Room Abandonment 2.4.11 - Emergency parameters that are entry-level Procedures I Plan: Knowledge of abnormal conditions for Technical condition procedures.
Specifications.
Question 89 The randomly selected generic KIA is 215003 IRM oversampled on this exam.
Randomly re-selected KIA 215003 IRM 2.1.25-2.4.47 - Emergency Procedures Emergency Procedures I Plan: Ability to I Plan: Ability to diagnose and interpret reference materials, such as graphs, 2 I 1 recognize trends in an accurate curves, tables, etc.
and timely manner utilizing the appropriate control room reference material.
Question 94 The randomly selected generic KIA does not support developing a written question at the 2.1.45 -Ability to identify and appropriate license level and is tested interpret diverse indications to extensively during the operating portion of the 3
validate the response of another examination.
indicator.
Randomly re-selected KIA 2.1.34-K~owl~d~e of primary and secondary plant chem1stry llm1ts.
Question 91 Unable to develop an appropriate SRO-Ievel 202002 Recirculation Flow question for the randomly selected KIA.
Control Randomly re-selected KIA 202002 Recirculation Flow Control A2.09-Ability to (a)
A2.01 -Ability to (a) predict the predict the impacts of the following on the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM; 212 RECIRCULATION FLOW and (b) based on those predictions, use CONTROL SYSTEM; and (b) procedures to correct, control, or mitigate the based on those predictions, use consequences of those abnormal conditions or procedures to correct, control, operations: Recirculation flow mismatch: Plant-or mitigate the consequences of Specific.
those abnormal conditions or operations: Recirculation pump trip
Question 80 The randomly selected generic KIA does not support developing an operationally relevant 700000 Generator Voltage and question without testing minutia for the Electric Grid Disturbances randomly selected abnormal plant evolution.
1 /1 2.4.45 -Ability to prioritize and Randomly re-selected KIA 700000 Generator interpret the significance of Voltage and Electric Grid Disturbances 2.2.37 -
each annunciator or alarm.
Ability to determine operability and/or availability of safety related equipment.
Question 15 Unable to write an operationally discriminating 263000 DC Electrical question for the randomly selected KIA Distribution Randomly re-selected KIA 263000 DC Electrical Distribution K3.03-Knowledge of the A2.01 -Ability to (a) predict the effect that a loss or malfunction of the D.C.
impacts of the following on the ELECTRICAL DISTRIBUTION will have on D.C. ELECTRICAL following: Systems with D.C. components (i.e.
2/1 DISTRIBUTION; and (b) based valves, motors, solenoids, etc.).
on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Grounds
ES-301 Administrative Topics Outline Form ES-301-1 Facility: James A. Fitz!;1atrick Date of Examination: Se12tember 2014 Examination Level: RO Operating Test Number: 14-2 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Conduct of Operations P, D, S Perform RHR Lineup Verification 14-1 NRC KIA2.1.29 (4.1), ST-2AN Re-activation of RO License Conduct of Operations M, R KIA 2.1.4 (3.3), ODS0-30 Equipment Control M, R Perform ST-23C, Jet Pump Operability-Two Loop KIA 2.2.12 (3.7), ST-23C Radiation Control D,R Determine Worker Exposure for Emergent Work KIA 2.3.4 (3.2), EN-RP-201 Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (s 3 for ROs; s 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (~ 1)
(P)revious 2 exams (S 1; randomly selected)
ES-301 Administrative Topics Outline Form ES-301-1 Facility: James A Fitz[2atrick Date of Examination: Se12tember 2014 Examination Level: SRO Operating Test Number: 14-2 Administrative Topic Type Describe activity to be performed (see Note)
Code*
Conduct of Operations P, D, R Verify Fuel Movement Sheets 12-1 NRC KIA 2.1.35 (3.9), OSP-66.001 Re-activation of SRO License Conduct of Operations D, R KIA 2.1.4 (3.8), ODS0-30 Equipment Control M, R Review ST-23C, Jet Pump Operability-Two Loop KIA2.2.12 (4.1), ST-23C Radiation Control D, R Determine Visitor RCA Access Requirements KIA 2.3.4 (3. 7), EN-RP-201, EN-RP-202 Classify General Emergency, Determine PARs, and Emergency Procedures/Plan M, R Perform Event Notification KIA 2.4.44 (4.4), IAP-1, IAP-2 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria:
(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (s 3 for ROs; s 4 for SROs & RO retakes)
(N)ew or (M)odified from bank (~ 1)
(P)revious 2 exams (S 1; randomly selected)
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: James A. Fitzpatrick Date of Examination: September 2014 Exam Level: RO/SRO Operating Test No.: 14-2 Control Room Systems (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title Type Code*
Safety Function
KIA 201001 A2.07 (3.2/3.1 ), EP-3, OP-25 2014-1 NRC
KIA 400000 A4.01 (3.1/3.0), OP-21, OP-40 2012-2 NRC
- d. Start EDGs A and C Due to Hurricane Warning N,EN,S 6
KIA 264000 A4.04 (3.7/3.7), OP-22
- e. Restore Shutdown Cooling After Isolation, RHR Pump Trips M,A, L, S 4
KIA 205000 A4.01 (3.7/3.7), AOP-30
- f. Manually Isolate Reactor Building Ventilation, Low Reactor Building D/P M,A, EN, S 9
KIA 261000 A4.06 (3.3/3.6), OP-51A, OP-20
- g. Reset Group 2 Isolation, Restore RWCU M, EN, S 5
KIA 223002 A4.03 (3.6/3.5), AOP-15, OP-28
- h. (RO Only) Perform Rod Worth Minimizer On-Line Diagnostic Test N, S 7
KIA 201006 A4.02 (2.9/2.9), ST-20A In-Plant Systems (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)
- i. Vent Torus to Lower Primary Containment Pressure D,A, E 5
KIA 295010 AA1.05 (3.1/3.4), EP-6
- j. Lineup SLC Test Tank for Injection D,R,E 2
KIA 295031 EA1.08 (3.8/3.9), EP-8
KIA 201003 A2.02 (3.7/3.8), OP-25
All RO and SR0-1 control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO I SR0-11 SRO-U (A}Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank
- 591:581:54 (E)mergency or abnormal in-plant
- 11;
- :11;::1 (EN)gineered safety feature
- I -
I ;::1 (control room system)
(L)ow-Power I Shutdown
- 11;
- :11;::1 (N)ew or (M)odified from bank including 1 (A)
- 21;
- :21;::1 (P)revious 2 exams
- 5 3 I :5 31 :5 2 (randomly selected)
(R)CA
- 11;
- :11;::1 (S)imulator
Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-1 Op-Test No.: 14-2 Examiners:
Operators:
Initial Conditions: The plant is operating at approximately 90% power. RCIC is out of service for maintenance. Torus cooling is in service on RHR loop A.
Turnover: Secure Torus cooling per OP-13B sections F.1 and F.?.
Event Malf.
Event Event No.
No.
Type*
Description N-Shutdown Torus Cooling 1
N/A
SW04:A C-SRO RHRSW Pump A Trip ARP 09-3-1 -25, Technical Specifications 3
NM14:B 1-ATC, APRM B Fails Upscale SRO OP-16, ARP 09-5-1 -4 I-BOP, HPCI Inadvertent Initiation 4
HP05 SRO AOP-77, AOP-32, Technical Specifications FW05:A C-BOP Feedwater Pump A High Vibration and Pump Trip 5
R-ATC, FW01 :A SRO ARP 09-6-4-11, AOP-41 RR15:A Loss of Coolant Accident 6
M-All MS02:A EOP-2, EOP-4 FW01 :B Feedwater Pump B Trip, HPCI Trip 7
C-All HP02 EOP-2 ED43:A Loss of Offsite Power 8
C-All ED43:B AOP-72 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-2 Op-Test No.: 14-2 Examiners:
Operators:
Initial Conditions: The plant is operating at approximately 99% power. Air Compressor B is out of service for maintenance. Core Spray pump A is ready for full flow testing. Main Generator reactive load is at minimum per Power Control request.
Turnover: Perform Core Spray full flow testing per ST-3PA, starting at step 8.7.6.
Event Malf.
Event Event No.
No.
Type*
Description N-Perform Core Spray Full Flow Test 1
N/A
Override
- BOP, SRO ARP 09-3-1-31, Technical Specifications RD06 C-Control Rod Drive Pump Trip, One Control Rod Drive Accumulator 3
- ATC, Low Pressure RD09 SRO AOP-69, ARP-09-5-1-43, Technical Specifications TU04 R-ATC Main Turbine Bearing High Vibration; Loss of Main Condenser 4
C-ATC, Vacuum MC01 SRO AOP-66, AOP-31, AOP-1 RP01AB Failure of RPS and ARI to Actuate 5
RP01BB M-All RP09 EOP-2, EOP-3 SL02 C-First SLC Squib Valve Fails to Fire, Second SLC Pump Trips, 6
SL01
- ATC, Recirculatibn Pumps Fail to Automatically Trip RR13 SRO EOP-3 EG01 C-Main Generator Trip, Two Turbine Bypass Valves Fail Closed 7
Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-3 Op-Test No.: 14-2 Examiners:
Operators:
Initial Conditions: The plant is operating at approximately 100% power. Air Compressor B is out of service for maintenance.
Turnover: Swap RBCLC pumps per OP-40 section G.1. Then lower Reactor power to 95% using Recirculation flow.
Event Malt.
Event Event No.
No.
Type*
Description N-Swap RBCLC Pumps 1
N/A
N/A
RR23:B I-AII OP-16, Technical Specifications C-Electrical Fault on Bus L-15 4
ED21:A
AD06:C
M-All MS16:G AOP-36, AOP-1, EOP-2, EOP-4 7
TC11 1-ATC, Main Turbine Fails to Trip SRO AOP-1 RH01 C-RHR Pump Trip, RHR Pump Suction Valve Fails Closed, RHRSW 8
Remotes
- BOP, Crossties Fail Closed Overrides SRO EOP-4, EOP-2 (N)ormal, (R)eactivity, (l)nstrument (C)omponent, (M)ajor
Appendix D Scenario Outline Form ES-D-1 Facility: James A. Fitzpatrick Scenario No.: NRC-4 Op-Test No.: 14-2 Examiners:
Operators:
Initial Conditions: The plant is operating at approximately 65% power. Circulating Water pump Cis ready to be returned to service following maintenance.
Turnover: Start Circulating Water pump C per OP-4 section 0.17. Then, raise Reactor power using Recirculation flow per the provided reactivity instruction.
Event Malf.
Event Event No.
No.
Type*
Description N-Start Circulating Water Pump C 1
N/A
N/A
Override 1-ATC, Recirculation Pump B Runs High SRO OP-27, Technical Specifications C-Loss of Steam Packing Exhauster A 4
Override
- BOP, SRO ARP 09-7-3-43, OP-240 C-Loss of RBCLC Flow to Recirculation Pump B 5
SW01 :B
MS05 M-All Main Steam Leak into Turbine Building AOP-40, AOP-1, EOP-2 7
RP12 1-ATC, All MSIVs Fail to Automatically Close SRO AOP-40 FW03/04 Loss of High Pressure Injection 8
RD06 M-All Override EOP-2 Override I-BOP, HPCI Flow Controller Failure in Automatic, HPCI Trips 9
HP02 SRO OP-15, EOP-2 RC02 RCIC Fails to Automatically Initiate, RCIC Trips, ADS Fails to 10 RC03 I-AII Automatically Initiate AD01 OP-19, EOP-2 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor