ML082830222
| ML082830222 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/26/2008 |
| From: | Garchow S Operations Branch IV |
| To: | Southern California Edison Co |
| References | |
| Download: ML082830222 (15) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 NUREG-1021, Revision 9.1 Page 1 of 15 SONGS Sept 2008 NRC Rev 1 Facility:
SONGS 2 & 3 NRC Date of Exam:
09/22/08 Tier Group RO K/A Category Points SRO-Only Points K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
Total A2 G*
Total
- 1. Emergency
& Abnormal Plant Evolutions 1
3 3
6 2
3 1
18 3
3 6
2 0
2 2
1 2
2 9
2 2
4 Tier Totals 3
5 8
3 5
3 27 5
5 10
- 2. Plant Systems 1
3 2
3 4
1 1
2 3
3 3
3 28 3
2 5
2 1
0 1
0 1
1 2
1 0
1 2
10 0
2 1
3 Tier Totals 4
2 4
4 2
2 4
4 3
4 5
38 5
3 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
2 2
3 3
2 2
1 2
Note:
- 1.
Ensure that at least two topics from every applicable K/A 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 K/A category shall not be less than two).
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final 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 / evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A 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 K/As 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 K/A categories.
7.*
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8.
On the following pages, enter the K/A 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; 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 K/A catalog, and enter the K/A 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.
ES-401 SONGS 2 & 3 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Form ES-401-2 NUREG-1021, Revision 9.1 Page 2 of 15 SONGS Sept 2008 NRC Rev 1 E/APE # / Name Safety Function K1 K2 K3 A1 A2 G
Number K/A Topic(s)
Imp.
Q#
009 / Small Break LOCA / 3 X
EA2.39 Ability to determine or interpret the following as they apply to a Small Break LOCA: Adequate core cooling 4.7 76 011 / Large Break LOCA / 3 X
EA2.03 Ability to determine or interpret the following as they apply to a Large Break LOCA:
Consequences of managing LOCA with loss of CCW 4.2 77 057 / Loss of Vital AC Instrument Bus / 6 X
2.1.20 Conduct of Operations: Ability to interpret and execute procedure steps 4.6 78 027 / Pressurizer Pressure Control System Malfunction / 3 X
AA2.16 Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: Actions to be taken if pressurizer pressure instrument fails low 3.9 79 029 / ATWS / 1 X
2.4.11 Emergency Procedures / Plan: Knowledge of abnormal condition procedures 4.2 80 007 / Reactor Trip / Stabilization / Recovery / 1 X
2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm 4.3 81 008 / Pressurizer Vapor Space Accident / 3 X
AA1.08 Ability to operate and/or monitor the following as they apply to the Pressurizer Vapor Space Accident: PRT level, pressure, and temperature 3.8 39 009 / Small Break LOCA / 3 X
EK2.03 Knowledge of the interrelations between the small break LOCA and the following: SGs 3.0 40 011 / Large Break LOCA / 3 X
EK3.03 Knowledge of the reasons for the following responses as they apply to the large break LOCA: Starting auxiliary feed pumps and flow, EDG, and service water pumps 4.1 41 015 / 17 / RCP Malfunctions / 4 X
2.1.20 Conduct of Operations: Ability to interpret and execute procedure steps 4.6 42 022 / Loss of Reactor Coolant Makeup / 2 X
AK1.02 Knowledge of the operational implications of the following concepts as they apply to the Loss of Reactor Coolant Makeup: Relationship of charging flow to pressure differential between charging and RCS 2.7 43 025 / Loss of RHR System / 4 X
AK2.02 Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following: LPI or Decay Heat Removal / RHR pumps 3.2 44
ES-401 SONGS 2 & 3 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Form ES-401-2 NUREG-1021, Revision 9.1 Page 3 of 15 SONGS Sept 2008 NRC Rev 1 E/APE # / Name Safety Function K1 K2 K3 A1 A2 G
Number K/A Topic(s)
Imp.
Q#
026 / Loss of Component Cooling Water / 8 X
AK3.03 Knowledge of the reasons for the following responses as they apply to the Loss of Component Cooling Water: Guidance actions contained in EOP for loss of CCW 4.0 45 027 / Pressurizer Pressure Control System Malfunction / 3 X
AA1.01 Ability to operate and/or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: Pressurizer heaters, sprays, and PORVs 4.0 46 029 / ATWS / 1 X
EK2.06 Knowledge of the interrelations between the following and an ATWS: Breakers, relays, and disconnects 2.9 47 038 / Steam Generator Tube Rupture / 3 X
EA2.13 Ability to determine or interpret the following as they apply to a SGTR: Magnitude of rupture 3.1 48 055 / Station Blackout / 6 X
EK1.01 Knowledge of the operational implications of the following concepts as they apply to the Station Blackout: Effect of battery discharge rates on capacity 3.3 49 056 / Loss of Offsite Power / 6 X
AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Offsite Power: Actions contained in EOP for loss of offsite power 4.4 50 057 / Loss of Vital AC Instrument Bus / 6 X
AK3.01 Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus 4.1 51 058 / Loss of DC Power / 6 X
AK1.01 Knowledge of the operational implications of the following concepts as they apply to Loss of DC Power: Battery charger equipment and instrumentation 2.8 52 065 / Loss of Instrument Air / 8 X
AK3.04 Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air: Cross-over to backup air supplies 3.0 53 077 / Generator Voltage and Electric Grid Disturbances / 6 X
AA2.02 Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: Voltage outside the generator capability curve 3.5 54
ES-401 SONGS 2 & 3 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Form ES-401-2 NUREG-1021, Revision 9.1 Page 4 of 15 SONGS Sept 2008 NRC Rev 1 E/APE # / Name Safety Function K1 K2 K3 A1 A2 G
Number K/A Topic(s)
Imp.
Q#
CE / E05 / Steam Line Rupture - Excessive Heat Transfer / 4 X
EA2.2 Ability to determine and interpret the following as they apply to the Excess Steam Demand:
Adherence to appropriate procedures and operation within the limitations in the facilities license and amendments 3.4 55 CE / E06 / Loss of Main Feedwater / 4 X
EK3.3 Knowledge of the reasons for the following responses as they apply to the Loss of Feedwater: Manipulation of controls required to obtain desired operating results during abnormal and emergency situations 3.7 56 K/A Category Point Totals:
3 3
6 2
3 / 4 1 / 2 Group Point Total:
18 / 6
ES-401 SONGS 2 & 3 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 Form ES-401-2 NUREG-1021, Revision 9.1 Page 5 of 15 SONGS Sept 2008 NRC Rev 1 E/APE # / Name Safety Function K1 K2 K3 A1 A2 G
Number K/A Topic(s)
Imp.
Q#
024 / Emergency Boration / 1 X
2.4.4 Emergency Procedures / Plan: Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures 4.7 82 032 / Loss of Source Range Nuclear Instrumentation / 7 X
AA2.07 Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation: Maximum allowable channel disagreement 3.4 83 037 / Steam Generator Tube Leak / 3 X
2.4.45 Emergency Procedures / Plan: Ability to prioritize and interpret the significance of each annunciator or alarm 4.3 84 005 / Inoperable / Stuck Control Rod / 1 X
AA2.01 Ability to determine or interpret the following as they apply to the Inoperable / Stuck Control Rod:
Stuck or inoperable Rod from in-core and ex-core NIS, in-core or loop temperature measurements 4.1 85 001 / Continuous Rod Withdrawal / 1 X
AK3.01 Knowledge of the reasons for the following responses as they apply to the Continuous Rod Withdrawal: Manually driving rods into position that existed before start of casualty 3.2 57 003 / Dropped Control Rod / 1 X
AK2.03 Knowledge of the interrelations between the Dropped Control Rod and the following:
Metroscope 3.1 58 028 / Pressurizer Level Control Malfunction / 2 X
AK3.02 Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions: Relationships between PZR pressure increase and reactor makeup /
letdown imbalance 2.9 59 032 / Loss of Source Range Nuclear Instrumentation / 7 X
AA2.02 Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation: Expected change in source range count rate when rods are moved 3.6 60 059 / Accidental Liquid Radwaste Release / 9 X
AK2.01 Knowledge of the interrelations between the Accidental Liquid Radwaste Release and the following: Radioactive liquid monitors 2.7 61 069 / Loss of Containment Integrity / 5 X
2.2.40 Equipment Control: Ability to apply Technical Specifications for a system 3.4 62
ES-401 SONGS 2 & 3 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 Form ES-401-2 NUREG-1021, Revision 9.1 Page 6 of 15 SONGS Sept 2008 NRC Rev 1 E/APE # / Name Safety Function K1 K2 K3 A1 A2 G
Number K/A Topic(s)
Imp.
Q#
074 / Inadequate Core Cooling / 4 X
EA1.15 Ability to operate and monitor the following as they apply to an Inadequate Core Cooling:
Hot-leg and cold-leg temperature recorders 3.9 63 076 / High Reactor Coolant Activity / 9 X
AA2.02 Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity:
Corrective actions required for high fission product activity in the RCS 2.8 64 CE / A13 / Natural Circulation / 4 X
2.4.31 Emergency Procedures / Plan: Knowledge of annunciator alarms, indications, or response procedures 4.2 65 K/A Category Point Totals:
0 2
2 1
2 / 2 2 / 2 Group Point Total:
9 / 4
ES-401 SONGS 2 & 3 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 Form ES-401-2 NUREG-1021, Revision 9.1 Page 7 of 15 SONGS Sept 2008 NRC Rev 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
Number K/A Topics Imp.
Q#
026 / Containment Spray X
2.4.46 Emergency Procedures / Plan: Ability to verify that alarms are consistent with the plant conditions 4.2 86 061 / Auxiliary / Emergency Feedwater X
A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of DC power 3.4 87 073 / Process Radiation Monitoring X
2.1.32 Conduct of Operations: Ability to explain and apply system limits and precautions 4.0 88 004 / Chemical and Volume Control X
A2.20 Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Shifting demineralizer while divert valve is lined up to VCT 2.7 89 103 / Containment X
A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the containment system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Containment evacuation (including recognition of the alarm) 3.6 90 003 / Reactor Coolant Pump X
A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPs; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Problems with RCP seals, especially rates of seal leak off 3.5 1
003 / Reactor Coolant Pump X
K5.03 Knowledge of the operational implications of the following concepts as the apply to the RCPs: Effects of RCP shutdown on Tave, including the reason for the unreliability of Tave in the shutdown loop 3.1 2
ES-401 SONGS 2 & 3 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 Form ES-401-2 NUREG-1021, Revision 9.1 Page 8 of 15 SONGS Sept 2008 NRC Rev 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
Number K/A Topics Imp.
Q#
004 / Chemical and Volume Control X
K3.07 Knowledge of the effect that a loss or malfunction of the CVCS will have on the following: PZR level and pressure 3.8 3
005 / Residual Heat Removal X
A4.02 Ability to manually operate and/or monitor in the control room: Heat exchanger bypass flow control 3.4 4
006 / Emergency Core Cooling X
K4.09 Knowledge of the ECCS design features and/or interlocks which provide for the following: Valve positioning on safety injection signal 3.9 5
006 / Emergency Core Cooling X
2.1.27 Conduct of Operations: Knowledge of system purpose and/or function 3.9 6
007 / Pressurizer Relief /
Quench Tank X
K1.03 Knowledge of the physical connections and/or cause-effect relationships between the PRTS and the following systems: RCS 3.0 7
008 / Component Cooling Water X
K2.02 Knowledge of bus power supplies to the following: CCW pump, including emergency backup 3.0 8
010 / Pressurizer Pressure Control X
A1.04 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR PCS controls including: Effect of temperature change during solid operation 3.6 9
010 / Pressurizer Pressure Control X
A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Spray valve failures 3.9 10 012 / Reactor Protection X
K6.09 Knowledge of the effect of a loss or malfunction of the following will have on the RPS: CEAC 3.6 11 013 / Engineered Safety Features Actuation X
K4.12 Knowledge of the ESFAS design features and/or interlocks which provide for the following: Safety injection block 3.7 12
ES-401 SONGS 2 & 3 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 Form ES-401-2 NUREG-1021, Revision 9.1 Page 9 of 15 SONGS Sept 2008 NRC Rev 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
Number K/A Topics Imp.
Q#
022 / Containment Cooling X
2.4.45 Emergency Procedures / Plan: Ability to prioritize and interpret the significance of each annunciator or alarm 4.1 13 022 / Containment Cooling X
A3.01 Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation 4.1 14 026 / Containment Spray X
K3.01 Knowledge of the effect that a loss or malfunction of the CSS will have on the following: CCS 3.9 15 039 / Main and Reheat Steam X
K4.08 Knowledge of MRSS design features and/or interlocks which provide for the following:
Interlocks on MSIV and bypass valves 3.3 16 039 / Main and Reheat Steam X
A4.07 Ability to manually operate and/or monitor in the control room: Steam dump valves 2.8 17 059 / Main Feedwater X
A4.12 Ability to manually operate and/or monitor in the control room: Initiation of automatic feedwater isolation 3.4 18 059 / Main Feedwater X
2.4.31 Emergency Procedures / Plan: Knowledge of annunciator alarms, indications, or response procedures 4.2 19 061 / Auxiliary/Emergency Feedwater X
A3.02 Ability to monitor automatic operation of the AFW, including: RCS cooldown during AFW operations 4.0 20 062 / AC Electrical Distribution X
K3.02 Knowledge of the effect that a loss or malfunction of the AC distribution system will have on the following: EDG 4.1 21 063 / DC Electrical Distribution X
A3.01 Ability to monitor automatic operation of the DC electrical system, including: Meters, annunciators, dials, recorders, and indicating lights 2.7 22 064 / Emergency Diesel Generator X
K1.05 Knowledge of the physical connections and/or cause-effect relationships between the EDG system and the following systems: Starting air system 3.4 23
ES-401 SONGS 2 & 3 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 Form ES-401-2 NUREG-1021, Revision 9.1 Page 10 of 15 SONGS Sept 2008 NRC Rev 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
Number K/A Topics Imp.
Q#
073 / Process Radiation Monitoring X
A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRM system controls including: Radiation levels 3.2 24 076 / Service Water X
K2.08 Knowledge of bus power supplies to the following: ESF-actuated MOVs 3.1 25 076 / Service Water X
K4.06 Knowledge of SWS design features and/or interlocks which provide for the following:
Service water train separation 2.8 26 078 / Instrument Air X
K1.03 Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems: Containment air 3.3 27 103 / Containment X
A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the containment system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Emergency containment entry 2.9 28 K/A Category Point Totals:
3 2
3 4
1 1
2 3 / 3 3
3 3 / 2 Group Point Total:
28 / 5
ES-401 SONGS 2 & 3 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 Form ES-401-2 NUREG-1021, Revision 9.1 Page 11 of 15 SONGS Sept 2008 NRC Rev 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
Number K/A Topics Imp.
Q#
011 / Pressurizer Level Control X
2.4.6 Emergency Procedures / Plan: Knowledge of EOP mitigation strategies 4.7 91 034 / Fuel Handling Equipment X
A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the Fuel Handling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Dropped cask 3.9 92 015 / Nuclear Instrumentation X
A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Xenon oscillations 3.5 93 001 / Control Rod Drive X
A4.08 Ability to manually operate and/or monitor in the control room: Mode select for CRDS; operation of rod control M/G sets and control panel 3.7 29 002 / Reactor Coolant X
A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of heat sinks 4.3 30 014 / Rod Position Indication X
K1.02 Knowledge of the physical connections and/or cause-effect relationships between the RPIS and the following systems: NIS 3.0 31 027 / Containment Iodine Removal X
2.1.23 Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation 4.3 32 041 / Steam Dump/Turbine Bypass Control X
K6.03 Knowledge of the effect of a loss or malfunction of the following will have on the SDS: Controller and positioners, including ICS, SG, CRDS 2.7 33
ES-401 SONGS 2 & 3 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 Form ES-401-2 NUREG-1021, Revision 9.1 Page 12 of 15 SONGS Sept 2008 NRC Rev 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
Number K/A Topics Imp.
Q#
029 / Containment Purge X
A1.03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating Containment Purge System controls including: Containment pressure, temperature, and humidity 3.0 34 033 / Spent Fuel Cooling X
2.4.49 Emergency Procedures / Plan: Ability to perform without reference to procedures those actions that require immediate operation of system components and controls 4.6 35 045 / Main Turbine Generator X
A1.06 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating MTG System controls including: Expected response of secondary plant parameters following TG trip 3.3 36 055 / Condenser Air Removal X
K3.01 Knowledge of the effect that a loss or malfunction of the CARS will have on the following: Main condenser 2.5 37 071 / Waste Gas Disposal X
K5.04 Knowledge of the operational implication of the following concepts as they apply to the Waste Gas Disposal System: Relationship of hydrogen/oxygen concentrations to flammability 2.5 38 K/A Category Point Totals:
1 0
1 0
1 1
2 1 / 2 0
1 2 / 1 Group Point Total:
10 / 3
ES-401 Generic Knowledge and Abilities Outline - Tier 3 Form ES-401-3 NUREG-1021, Revision 9.1 Page 13 of 15 SONGS Sept 2008 NRC Rev 1 Facility: SONGS 2& 3 Date of Exam: 09/22/2008 Category K/A #
Topic RO SRO-Only IR IR
- 1.
Conduct of Operations 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
4.2 94 2.1.40 Knowledge of refueling administrative requirements 3.9 95 2.1.14 Knowledge of criteria or conditions for plant wide announcements, such as pump starts, reactor trips, mode changes, etc.
3.1 66 2.1.9 Ability to direct personnel activities inside the control room 2.9 67 Subtotal 2
2
- 2.
Equipment Control 2.2.5 Knowledge of the process for making design or operating changes to the facility 3.2 96 2.2.37 Ability to determine operability and/or availability of safety related equipment 4.6 97 2.2.14 Knowledge of the process for controlling equipment configuration or status 3.9 68 2.2.38 Knowledge of conditions and limitations in the facility license 3.6 69 Subtotal 2
2
- 3.
Radiation Control 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
3.1 98 2.3.7 Ability to comply with the radiation work permit requirements during normal or abnormal conditions 3.5 70 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities 3.4 71 2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
2.9 72 Subtotal 3
1
- 4.
Emergency Procedures /
Plan 2.4.11 Knowledge of abnormal condition procedures 4.2 99 2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations 4.4 100 2.4.13 Knowledge of crew roles and responsibilities during EOP usage 4.0 73 2.4.39 Knowledge of RO responsibilities in emergency plan implementation 3.9 74 2.4.17 Knowledge of EOP terms and definitions 3.9 75 Subtotal 3
2 Tier 3 Point Total 10 7
ES-401 Record of Rejected K/As Form ES-401-4 NUREG-1021, Revision 9.1 Page 14 of 15 SONGS Sept 2008 NRC Rev 1 Tier /
Group Randomly Selected K/A Reason for Rejection 1 / 1 022 AK1.04 Q #43 - This specific K/A does not apply because SONGS does not have a charging flow valve controller. Randomly reselected 022 AK1.02.
1 / 2 076 AA2.01 Q #64 - This specific K/A does not apply at SONGS. Radiation monitoring of the CVCS system has been abandoned for many years. While the system was in service it did not isolate letdown on high radiation. There are no other radiation monitors that have any input to any CVCS isolation valves or the system as a whole. Randomly reselected 076 AA2.02.
2 / 1 076 K1.20 Q #25 - This specific K/A does not apply because there is no relationship between the service water system and auxiliary feedwater at SONGS.
Randomly reselected 076 K2.08 to meet skyscraper requirements (per Outline selection of Rev. a).
2 / 2 028 G2.2.39 Q #33 - Hydrogen recombiners have been removed from Tech Specs and are abandoned in place. Parts of the system are slated for removal from containment on the upcoming set of outages. Randomly reselected 041 K6.03 to meet skyscraper requirements (per Outline selection of Rev. a).
2 / 1 012 K4.09 Q #11 - Randomly reselected 012 K6.09 to meet skyscraper requirements (per Outline selection of Rev. a).
2 / 2 071 G2.1.28 Q #38 - Randomly reselected 071 K5.04 to meet skyscraper requirements (per Outline selection of Rev. a).
1 / 2 032 AA2.09 Q #83 - This specific K/A does not apply at SONGS because the source range fission chambers operate in the Ion Chamber region of the General Detector Curve (Region 2). Randomly reselected 032 AA2.07.
2 / 2 011 G2.4.2 Q #91 - This K/A does not meet the requirements of 10 CFR 55.43 for SRO-only questions. Randomly reselected 011 G2.4.6 2 / 1 005 A4.04 Q #04 - This specific K/A does not apply because SONGS does not have a closed cooling water system. Randomly reselected 005 A4.02.
2 / 2 001 A4.01 Q #29 - Randomly reselected 001 A4.08 because original topic is addressed by Control Room JPM C-3.
1 / 2 074 EA2.02 Q #85 - Randomly reselected 003 AA2.01 because original topic is already addressed by Q #76.
2 / 1 076 A2.02 Q #89 - Randomly reselected 004 A2.20 because this topic is already adequately addressed on the exam and unable to create SRO level question from randomly selected K/A.
1 / 1 062 AK3.03 Q #53 - Randomly reselected 065 AK3.04 because SONGS Nuclear Service Water is a nuclear-grade makeup water system used for flushing and filling of various components in Radwaste.
1 / 1 062 AA2.03 Q #81 - Randomly reselected 007 G 2.4.45 because SONGS Nuclear Service Water is a nuclear-grade makeup water system used for flushing and filling of various components in Radwaste
ES-401 Record of Rejected K/As Form ES-401-4 NUREG-1021, Revision 9.1 Page 15 of 15 SONGS Sept 2008 NRC Rev 1 Tier /
Group Randomly Selected K/A Reason for Rejection 1 / 1 015 / 17 G 2.4.31 Q #78 - Selected 057 G 2.1.20. Unable to develop an appropriate SRO level question on RCP Malfunctions.
3 / 4 G 2.4.35 Q #99 - Selected G 2.4.11. Unable to develop an appropriate SRO level question on local operator actions.