ML082830367

SO-2008-09-Final Written Exam Outlines

ML082830367
Person / Time
Site:	San Onofre
Issue date:	09/26/2008
From:	Garchow S Operations Branch IV
To:	Southern California Edison Co
References
50-361/08-301, 50-362/08-301, ES-401, ES-401-2, NUREG-1021 R9.1 50-361/08-301, 50-362/08-301
Download: ML082830367 (15)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: SONGS 2 & 3 NRC Date of Exam: 09/22/08 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

1. Emergency 1 3 3 6 2 3 1 18 3 3 6

& Abnormal 2 1 2 1 1 2 2 9 2 2 4 Plant Evolutions Tier Totals 4 5 7 3 5 3 27 5 5 10 1 3 2 3 4 1 1 2 3 3 3 3 28 3 2 5

2. Plant Systems 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 1 2 3 4 1 2 3 4 Categories 10 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.

NUREG-1021, Revision 9.1 Page 1 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 SONGS 2 & 3 Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function K1 K2 K3 A1 A2 G Number K/A Topic(s) Imp. Q#

Ability to determine or interpret the following as 009 / Small Break LOCA / 3 X EA2.39 they apply to a Small Break LOCA: Adequate 4.7 76 core cooling Ability to determine or interpret the following as they apply to a Large Break LOCA:

011 / Large Break LOCA / 3 X EA2.03 4.2 77 Consequences of managing LOCA with loss of CCW Conduct of Operations: Ability to interpret and 057 / Loss of Vital AC Instrument Bus / 6 X 2.1.20 4.6 78 execute procedure steps Ability to determine and interpret the following as 027 / Pressurizer Pressure Control System they apply to the Pressurizer Pressure Control X AA2.16 3.9 79 Malfunction / 3 Malfunctions: Actions to be taken if pressurizer pressure instrument fails low Emergency Procedures / Plan: Knowledge of 029 / ATWS / 1 X 2.4.11 4.2 80 abnormal condition procedures Ability to prioritize and interpret the significance 007 / Reactor Trip / Stabilization / Recovery / 1 X 2.4.45 4.3 81 of each annunciator or alarm Ability to operate and/or monitor the following as 008 / Pressurizer Vapor Space Accident / 3 X AA1.08 they apply to the Pressurizer Vapor Space 3.8 39 Accident: PRT level, pressure, and temperature Knowledge of the interrelations between the 009 / Small Break LOCA / 3 X EK2.03 3.0 40 small break LOCA and the following: SGs Knowledge of the reasons for the following responses as they apply to the large break 011 / Large Break LOCA / 3 X EK3.03 4.1 41 LOCA: Starting auxiliary feed pumps and flow, EDG, and service water pumps Conduct of Operations: Ability to interpret and 015 / 17 / RCP Malfunctions / 4 X 2.1.20 4.6 42 execute procedure steps Knowledge of the operational implications of the following concepts as they apply to the Loss of 022 / Loss of Reactor Coolant Makeup / 2 X AK1.02 Reactor Coolant Makeup: Relationship of 2.7 43 charging flow to pressure differential between charging and RCS Knowledge of the interrelations between the Loss of Residual Heat Removal System and the 025 / Loss of RHR System / 4 X AK2.02 3.2 44 following: LPI or Decay Heat Removal / RHR pumps NUREG-1021, Revision 9.1 Page 2 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 SONGS 2 & 3 Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function K1 K2 K3 A1 A2 G Number K/A Topic(s) Imp. Q#

Knowledge of the reasons for the following responses as they apply to the Loss of 026 / Loss of Component Cooling Water / 8 X AK3.03 4.0 45 Component Cooling Water: Guidance actions contained in EOP for loss of CCW Ability to operate and/or monitor the following as 027 / Pressurizer Pressure Control System they apply to the Pressurizer Pressure Control X AA1.01 4.0 46 Malfunction / 3 Malfunctions: Pressurizer heaters, sprays, and PORVs Knowledge of the interrelations between the 029 / ATWS / 1 X EK2.06 following and an ATWS: Breakers, relays, and 2.9 47 disconnects Ability to determine or interpret the following as 038 / Steam Generator Tube Rupture / 3 X EA2.01 they apply to a SGTR: When to isolate one or 4.1 48 more S/Gs Knowledge of the operational implications of the following concepts as they apply to the Station 055 / Station Blackout / 6 X EK1.01 3.3 49 Blackout: Effect of battery discharge rates on capacity Knowledge of the reasons for the following responses as they apply to the Loss of Offsite 056 / Loss of Offsite Power / 6 X AK3.02 4.4 50 Power: Actions contained in EOP for loss of offsite power Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC 057 / Loss of Vital AC Instrument Bus / 6 X AK3.01 4.1 51 Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus Knowledge of the operational implications of the following concepts as they apply to Loss of DC 058 / Loss of DC Power / 6 X AK1.01 2.8 52 Power: Battery charger equipment and instrumentation Knowledge of the reasons for the following responses as they apply to the Loss of 065 / Loss of Instrument Air / 8 X AK3.04 3.0 53 Instrument Air: Cross-over to backup air supplies Ability to determine and interpret the following as 077 / Generator Voltage and Electric Grid they apply to Generator Voltage and Electric X AA2.02 3.5 54 Disturbances / 6 Grid Disturbances: Voltage outside the generator capability curve NUREG-1021, Revision 9.1 Page 3 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 SONGS 2 & 3 Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function K1 K2 K3 A1 A2 G Number K/A Topic(s) Imp. Q#

Ability to determine and interpret the following as they apply to the Excess Steam Demand:

CE / E05 / Steam Line Rupture - Excessive Heat X EA2.2 Adherence to appropriate procedures and 3.4 55 Transfer / 4 operation within the limitations in the facilities license and amendments Knowledge of the reasons for the following responses as they apply to the Loss of CE / E06 / Loss of Main Feedwater / 4 X EK3.3 Feedwater: Manipulation of controls required to 3.7 56 obtain desired operating results during abnormal and emergency situations K/A Category Point Totals: 3 3 6 2 3/4 1/2 Group Point Total: 18 / 6 NUREG-1021, Revision 9.1 Page 4 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 SONGS 2 & 3 Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # / Name Safety Function K1 K2 K3 A1 A2 G Number K/A Topic(s) Imp. Q#

Emergency Procedures / Plan: Ability to recognize abnormal indications for system 024 / Emergency Boration / 1 X 2.4.4 operating parameters that are entry-level 4.7 82 conditions for emergency and abnormal operating procedures Ability to determine and interpret the following as 032 / Loss of Source Range Nuclear they apply to the Loss of Source Range Nuclear X AA2.07 3.4 83 Instrumentation / 7 Instrumentation: Maximum allowable channel disagreement Emergency Procedures / Plan: Ability to 037 / Steam Generator Tube Leak / 3 X 2.4.45 prioritize and interpret the significance of each 4.3 84 annunciator or alarm Ability to determine or interpret the following as they apply to the Inoperable / Stuck Control Rod:

005 / Inoperable / Stuck Control Rod / 1 X AA2.01 Stuck or inoperable Rod from in-core and 4.1 85 ex-core NIS, in-core or loop temperature measurements Knowledge of the operational implications of the 001 / Continuous Rod Withdrawal / 1 X AK1.17 following concepts as they apply to the 3.4 57 Continuous Rod Withdrawal: MTC Knowledge of the interrelations between the 003 / Dropped Control Rod / 1 X AK2.03 Dropped Control Rod and the following: 3.1 58 Metroscope Knowledge of the reasons for the following responses as they apply to the Pressurizer Level 028 / Pressurizer Level Control Malfunction / 2 X AK3.02 Control Malfunctions: Relationships between 2.9 59 PZR pressure increase and reactor makeup /

letdown imbalance Ability to determine and interpret the following as 032 / Loss of Source Range Nuclear they apply to the Loss of Source Range Nuclear X AA2.02 3.6 60 Instrumentation / 7 Instrumentation: Expected change in source range count rate when rods are moved Knowledge of the interrelations between the 059 / Accidental Liquid Radwaste Release / 9 X AK2.01 Accidental Liquid Radwaste Release and the 2.7 61 following: Radioactive liquid monitors Equipment Control: Ability to apply Technical 069 / Loss of Containment Integrity / 5 X 2.2.40 3.4 62 Specifications for a system NUREG-1021, Revision 9.1 Page 5 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 SONGS 2 & 3 Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # / Name Safety Function K1 K2 K3 A1 A2 G Number K/A Topic(s) Imp. Q#

Ability to operate and monitor the following as 074 / Inadequate Core Cooling / 4 X EA1.15 they apply to an Inadequate Core Cooling: 3.9 63 Hot-leg and cold-leg temperature recorders Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity:

076 / High Reactor Coolant Activity / 9 X AA2.02 2.8 64 Corrective actions required for high fission product activity in the RCS Emergency Procedures / Plan: Knowledge of CE / A13 / Natural Circulation / 4 X 2.4.31 annunciator alarms, indications, or response 4.2 65 procedures K/A Category Point Totals: 1 2 1 1 2/2 2/2 Group Point Total: 9/4 NUREG-1021, Revision 9.1 Page 6 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 SONGS 2 & 3 Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Number K/A Topics Imp. Q#

Emergency Procedures / Plan: Ability to verify 026 / Containment Spray X 2.4.46 that alarms are consistent with the plant 4.2 86 conditions Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and 061 / Auxiliary / Emergency (b) based on those predictions, use procedures X A2.03 3.4 87 Feedwater to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of DC power 073 / Process Radiation Conduct of Operations: Ability to explain and X 2.1.32 4.0 88 Monitoring apply system limits and precautions Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures 004 / Chemical and Volume X A2.20 to correct, control, or mitigate the 2.7 89 Control consequences of those malfunctions or operations: Shifting demineralizer while divert valve is lined up to VCT Ability to (a) predict the impacts of the following malfunctions or operations on the containment system; and (b) based on those predictions, 103 / Containment X A2.04 use procedures to correct, control, or mitigate 3.6 90 the consequences of those malfunctions or operations: Containment evacuation (including recognition of the alarm)

Ability to (a) predict the impacts of the following malfunctions or operations on the RCPs; and (b) based on those predictions, use procedures 003 / Reactor Coolant Pump X A2.01 to correct, control, or mitigate the 3.5 1 consequences of those malfunctions or operations: Problems with RCP seals, especially rates of seal leak off Knowledge of the operational implications of the following concepts as the apply to the 003 / Reactor Coolant Pump X K5.03 RCPs: Effects of RCP shutdown on Tave, 3.1 2 including the reason for the unreliability of Tave in the shutdown loop NUREG-1021, Revision 9.1 Page 7 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 SONGS 2 & 3 Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Number K/A Topics Imp. Q#

Knowledge of the effect that a loss or 004 / Chemical and Volume X K3.07 malfunction of the CVCS will have on the 3.8 3 Control following: PZR level and pressure Ability to manually operate and/or monitor in 005 / Residual Heat Removal X A4.02 the control room: Heat exchanger bypass flow 3.4 4 control Knowledge of the ECCS design features 006 / Emergency Core and/or interlocks which provide for the X K4.09 3.9 5 Cooling following: Valve positioning on safety injection signal 006 / Emergency Core Conduct of Operations: Knowledge of system X 2.1.27 3.9 6 Cooling purpose and/or function Knowledge of the physical connections and/or 007 / Pressurizer Relief /

X K1.03 cause-effect relationships between the PRTS 3.0 7 Quench Tank and the following systems: RCS Knowledge of bus power supplies to the 008 / Component Cooling X K2.02 following: CCW pump, including emergency 3.0 8 Water backup Ability to predict and/or monitor changes in parameters (to prevent exceeding design 010 / Pressurizer Pressure X A1.04 limits) associated with operating the PZR PCS 3.6 9 Control controls including: Effect of temperature change during solid operation Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; 010 / Pressurizer Pressure and (b) based on those predictions, use X A2.02 3.9 10 Control procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Spray valve failures Knowledge of the effect of a loss or 012 / Reactor Protection X K6.09 malfunction of the following will have on the 3.6 11 RPS: CEAC Knowledge of the ESFAS design features 013 / Engineered Safety X K4.12 and/or interlocks which provide for the 3.7 12 Features Actuation following: Safety injection block NUREG-1021, Revision 9.1 Page 8 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 SONGS 2 & 3 Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Number K/A Topics Imp. Q#

Emergency Procedures / Plan: Ability to 022 / Containment Cooling X 2.4.45 prioritize and interpret the significance of each 4.1 13 annunciator or alarm Ability to monitor automatic operation of the 022 / Containment Cooling X A3.01 CCS, including: Initiation of safeguards mode 4.1 14 of operation Knowledge of the effect that a loss or 026 / Containment Spray X K3.01 malfunction of the CSS will have on the 3.9 15 following: CCS Knowledge of MRSS design features and/or 039 / Main and Reheat Steam X K4.08 interlocks which provide for the following: 3.3 16 Interlocks on MSIV and bypass valves Ability to manually operate and/or monitor in 039 / Main and Reheat Steam X A4.07 2.8 17 the control room: Steam dump valves Ability to manually operate and/or monitor in 059 / Main Feedwater X A4.12 the control room: Initiation of automatic 3.4 18 feedwater isolation Emergency Procedures / Plan: Knowledge of 059 / Main Feedwater X 2.4.31 annunciator alarms, indications, or response 4.2 19 procedures Ability to monitor automatic operation of the 061 / Auxiliary/Emergency X A3.02 AFW, including: RCS cooldown during AFW 4.0 20 Feedwater operations Knowledge of the effect that a loss or 062 / AC Electrical X K3.02 malfunction of the AC distribution system will 4.1 21 Distribution have on the following: EDG Ability to monitor automatic operation of the 063 / DC Electrical DC electrical system, including: Meters, X A3.01 2.7 22 Distribution annunciators, dials, recorders, and indicating lights Knowledge of the physical connections and/or 064 / Emergency Diesel cause-effect relationships between the EDG X K1.05 3.4 23 Generator system and the following systems: Starting air system NUREG-1021, Revision 9.1 Page 9 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 SONGS 2 & 3 Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Number K/A Topics Imp. Q#

Ability to predict and/or monitor changes in 073 / Process Radiation parameters (to prevent exceeding design X A1.01 3.2 24 Monitoring limits) associated with operating the PRM system controls including: Radiation levels Knowledge of bus power supplies to the 076 / Service Water X K2.08 3.1 25 following: ESF-actuated MOVs Knowledge of SWS design features and/or 076 / Service Water X K4.06 interlocks which provide for the following: 2.8 26 Service water train separation Knowledge of the physical connections and/or 078 / Instrument Air X K1.03 cause-effect relationships between the IAS and 3.3 27 the following systems: Containment air Ability to (a) predict the impacts of the following malfunctions or operations on the containment system; and (b) based on those predictions, 103 / Containment X A2.05 2.9 28 use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Emergency containment entry K/A Category Point Totals: 3 2 3 4 1 1 2 3/3 3 3 3/2 Group Point Total: 28 / 5 NUREG-1021, Revision 9.1 Page 10 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 SONGS 2 & 3 Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Number K/A Topics Imp. Q#

011 / Pressurizer Level Emergency Procedures / Plan: Knowledge X 2.4.6 4.7 91 Control of EOP mitigation strategies Ability to (a) predict the impacts of the following malfunctions or operations on the Fuel Handling System; and (b) based on 034 / Fuel Handling X A2.02 those predictions, use procedures to correct, 3.9 92 Equipment control, or mitigate the consequences of those malfunctions or operations: Dropped cask Ability to (a) predict the impacts of the following malfunctions or operations on the NIS; and (b) based on those predictions, use 015 / Nuclear Instrumentation X A2.03 3.5 93 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Xenon oscillations Ability to manually operate and/or monitor in the control room: Mode select for CRDS; 001 / Control Rod Drive X A4.08 3.7 29 operation of rod control M/G sets and control panel Ability to (a) predict the impacts of the following malfunctions or operations on the RCS; and (b) based on those predictions, 002 / Reactor Coolant X A2.04 use procedures to correct, control, or 4.3 30 mitigate the consequences of those malfunctions or operations: Loss of heat sinks Knowledge of the physical connections 014 / Rod Position Indication X K1.01 and/or cause-effect relationships between 3.2 31 the RPIS and the following systems: CRDS Conduct of Operations: Ability to perform 027 / Containment Iodine specific system and integrated plant X 2.1.23 4.3 32 Removal procedures during all modes of plant operation Knowledge of the effect of a loss or 041 / Steam Dump/Turbine malfunction of the following will have on the X K6.03 2.7 33 Bypass Control SDS: Controller and positioners, including ICS, SG, CRDS NUREG-1021, Revision 9.1 Page 11 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 SONGS 2 & 3 Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Number K/A Topics Imp. Q#

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating 029 / Containment Purge X A1.03 3.0 34 Containment Purge System controls including: Containment pressure, temperature, and humidity Emergency Procedures / Plan: Ability to perform without reference to procedures 033 / Spent Fuel Cooling X 2.4.49 those actions that require immediate 4.6 35 operation of system components and controls Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating MTG 045 / Main Turbine Generator X A1.06 3.3 36 System controls including: Expected response of secondary plant parameters following TG trip Knowledge of the effect that a loss or 055 / Condenser Air Removal X K3.01 malfunction of the CARS will have on the 2.5 37 following: Main condenser Knowledge of the operational implication of the following concepts as they apply to the 071 / Waste Gas Disposal X K5.04 Waste Gas Disposal System: Relationship of 2.5 38 hydrogen/oxygen concentrations to flammability K/A Category Point Totals: 1 0 1 0 1 1 2 1/2 0 1 2 / 1 Group Point Total: 10 / 3 NUREG-1021, Revision 9.1 Page 12 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 Generic Knowledge and Abilities Outline - Tier 3 Form ES-401-3 Facility: SONGS 2& 3 Date of Exam: 09/22/2008 Category K/A # Topic RO SRO-Only IR # IR #

2.1.25 Ability to interpret reference materials, such as graphs, 4.2 94 curves, tables, etc.

1. 2.1.40 Knowledge of refueling administrative requirements 3.9 95 Conduct of Operations 2.1.14 Knowledge of criteria or conditions for plant wide 3.1 66 announcements, such as pump starts, reactor trips, mode changes, etc.

2.1.9 Ability to direct personnel activities inside the control 2.9 67 room Subtotal 2 2 2.2.5 Knowledge of the process for making design or operating 3.2 96 changes to the facility 2.2.37 Ability to determine operability and/or availability of safety 4.6 97

2. related equipment Equipment Control 2.2.14 Knowledge of the process for controlling equipment 3.9 68 configuration or status 2.2.38 Knowledge of conditions and limitations in the facility 3.6 69 license Subtotal 2 2 2.3.15 Knowledge of radiation monitoring systems, such as fixed 3.1 98 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

3. Ability to comply with the radiation work permit 3.5 70 2.3.7 Radiation requirements during normal or abnormal conditions Control 2.3.14 Knowledge of radiation or contamination hazards that 3.4 71 may arise during normal, abnormal, or emergency conditions or activities 2.3.5 Ability to use radiation monitoring systems, such as fixed 2.9 72 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Subtotal 3 1 2.4.11 Knowledge of abnormal condition procedures 4.2 99 2.4.23 Knowledge of the bases for prioritizing emergency 4.4 100

4. procedure implementation during emergency operations Emergency Procedures / 2.4.13 Knowledge of crew roles and responsibilities during EOP 4.0 73 Plan usage 2.4.39 Knowledge of RO responsibilities in emergency plan 3.9 74 implementation 2.4.17 Knowledge of EOP terms and definitions 3.9 75 Subtotal 3 2 Tier 3 Point Total 10 7 NUREG-1021, Revision 9.1 Page 13 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A Q #43 - This specific K/A does not apply because SONGS does not have a 1/1 022 AK1.04 charging flow valve controller. Randomly reselected 022 AK1.02.

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 1/2 076 AA2.01 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.

Q #25 - This specific K/A does not apply because there is no relationship between the service water system and auxiliary feedwater at SONGS.

2/1 076 K1.20 Randomly reselected 076 K2.08 to meet skyscraper requirements (per Outline selection of Rev. a).

Q #33 - Hydrogen recombiners have been removed from Tech Specs and are abandoned in place. Parts of the system are slated for removal from 2/2 028 G2.2.39 containment on the upcoming set of outages. Randomly reselected 041 K6.03 to meet skyscraper requirements (per Outline selection of Rev. a).

Q #11 - Randomly reselected 012 K6.09 to meet skyscraper requirements 2/1 012 K4.09 (per Outline selection of Rev. a).

Q #38 - Randomly reselected 071 K5.04 to meet skyscraper requirements 2/2 071 G2.1.28 (per Outline selection of Rev. a).

Q #83 - This specific K/A does not apply at SONGS because the source range 1/2 032 AA2.09 fission chambers operate in the Ion Chamber region of the General Detector Curve (Region 2). Randomly reselected 032 AA2.07.

Q #91 - This K/A does not meet the requirements of 10 CFR 55.43 for 2/2 011 G2.4.2 SRO-only questions. Randomly reselected 011 G2.4.6 Q #04 - This specific K/A does not apply because SONGS does not have a 2/1 005 A4.04 closed cooling water system. Randomly reselected 005 A4.02.

Q #29 - Randomly reselected 001 A4.08 because original topic is addressed 2/2 001 A4.01 by Control Room JPM C-3.

Q #85 - Randomly reselected 003 AA2.01 because original topic is already 1/2 074 EA2.02 addressed by Q #76.

Q #89 - Randomly reselected 004 A2.20 because this topic is already 2/1 076 A2.02 adequately addressed on the exam and unable to create SRO level question from randomly selected K/A.

Q #53 - Randomly reselected 065 AK3.04 because SONGS Nuclear Service 1/1 062 AK3.03 Water is a nuclear-grade makeup water system used for flushing and filling of various components in Radwaste.

Q #81 - Randomly reselected 007 G 2.4.45 because SONGS Nuclear Service 1/1 062 AA2.03 Water is a nuclear-grade makeup water system used for flushing and filling of various components in Radwaste NUREG-1021, Revision 9.1 Page 14 of 15 SONGS Sept 2008 NRC Rev Final

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 015 / 17 Q #78 - Selected 057 G 2.1.20. Unable to develop an appropriate SRO level 1/1 G 2.4.31 question on RCP Malfunctions.

Q #99 - Selected G 2.4.11. Unable to develop an appropriate SRO level 3/4 G 2.4.35 question on local operator actions.

Q #48 - Selected 038 EA2.01. Unable to develop an appropriate RO level 1/1 038 EA2.13 question on the relationship between SGTR and magnitude of rupture.

Q #57 - Selected 001 AK1.17. Unable to develop an appropriate procedural 1/2 001 AK3.01 reference on the relationship between a continuous rod withdrawal and the driving of rods to their original position that existed at the start of the casualty.

Q #31 - Selected 014.K1.01. Unable to develop an appropriate RO level 2/2 014 K1.02 question on the relationship between RPIS and NIS.

NUREG-1021, Revision 9.1 Page 15 of 15 SONGS Sept 2008 NRC Rev Final