ML120470684

SO-2011-11 Draft Outlines

ML120470684
Person / Time
Site:	South Texas
Issue date:	10/28/2011
From:	Division of Reactor Safety IV
To:
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Download: ML120470684 (37)

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ES-401 PWR Examination Outline Form ES-401-2 Page 1 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc Facility: SONGS 2 & 3 NRC Date of Exam:

10/31/1 1 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 2 2 3 3 4 4 18 3 3 6 2 2 2 0 1 3 1 9 2 2 4 Tier Totals 4 4 3 4 7 5 27 5 5 10 2. Plant Systems 1 3 3 2 4 1 3 1 3 3 3 2 28 2 3 5 2 1 0 1 2 1 1 1 1 1 0 1 10 2 0 1 3 Tier Totals 4 3 3 6 2 4 2 4 4 3 3 38 3 5 8 3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 2 3 2 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 Page 2 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc E/APE # / Name Safety Function K1 K2 K3 A1 A2 G Number K/A Topic(s)

Imp. Q# 009 / Small Break LOCA / 3 X EA2.14 Ability to determine and interpret the following as they apply to the small break LOCA: Actions to be taken if PTS limits are violated 4.4 76 011 / Large Break LOCA / 3 X 2.2.37 Equipment Control: Ability to determine operability and/or availability of safety related equipment 4.6 77 015/017 / RCP Malfunctions / 4 X AA2.0 1 Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Cause of RCP failure 3.5 78 027 / Pressurizer Pressure Control Malfunction

/ 3 X 2.4.50 Emergency Procedures/Plan: Ability to verify system alarms setpoints and operate controls identified in the alarm response manual 4.0 79 029 / ATWS / 1 X EA2.01 Ability to determine and interpret the following as they apply to the ATWS: Reactor nuclear instrumentation 4.7 80 058 / Loss of D C Power / 6 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 81 007 / Reactor Trip

- Stabilization

- Recovery / 1 X 2.1.7 Conduct of Operations: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretati on 4.4 39 009 / Small Break LOCA / 3 X EK2.03 Knowledge of the interrelations between small break LOCA and the following: SGs 3.0 40 015 / 17 / RCP Malfunctions / 4 X AA1.0 3 Ability to operate and/or monitor the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow)

Reactor trip alarms, switches, and indicators 3.7 41 022 / Loss of Reactor Coolant Makeup / 2 X AK3.06 Knowledge of the reasons for the following responses as they apply to the Loss of Reactor Coolant Makeup: RCP thermal barrier cooling 3.2 42 ES-401 SONGS 2 & 3 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions

- Tier 1 Group 1 Form ES-401-2 Page 3 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc E/APE # / Name Safety Function K1 K2 K3 A1 A2 G Number K/A Topic(s)

Imp. Q# 025 / Loss of RHR System / 4 X AA2.02 Ability to determine and interpret the following as they apply to the Loss of Residual Heat Removal System

Leakage of reactor coolant from RHR into closed cooling water system or into reactor building atmosphere 3.4 43 026 / Loss of Component Cooling Water / 8 X AA2.06 Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The length of time after the loss of CCW flow to a component before that component may be damaged 2.8 44 027 / Pressurizer Pressure Control System Malfunction / 3 X AA1.03 Ability to operate and/or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions

Pressure control when on a steam bubble 3.6 45 029 / ATWS / 1 X EK2.06 Knowledge of the interrelations between ATWS and the following: Breakers, relays, and disconnects 2.9 46 038 / Steam Generator Tube Rupture / 3 X EA2.01 Ability to determine or interpret the following as they apply to a SGTR: When to isolate one or more SGs 4.1 47 040 / Steam Line Rupture

- Excessive Heat Transfer / 4 X AK1.0 1 Knowledge of the operational implications of the following concepts as they apply to the Steam Line Rupture: Consequences of PTS 4.1 48 011 / Large Break LOCA

/ 3 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 49 055 / Station Blackout / 6 X EK1.02 Knowledge of the operational implications of the following concepts as they apply to the Station Blackout: Natural circulation cooling 4.1 50 056 / 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 51 057 / Loss of Vital AC Instrument Bus / 6 X AA2.1 2 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus: PZR level controller, instrumentation, and heater indications 3.5 52 ES-401 SONGS 2 & 3 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions

- Tier 1 Group 1 Form ES-401-2 Page 4 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc E/APE # / Name Safety Function K1 K2 K3 A1 A2 G Number K/A Topic(s)

Imp. Q# 058 / Loss of DC Power / 6 X AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Actions contained in EOP for loss of DC power 4.0 53 062 / Loss of Nuclear Service Water / 4 X 2.4.35 Emergency Procedures/Plan: Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects 3.8 54 065 / Loss of Instrument Air / 8 X AA1.04 Ability to operate and/or monitor the following as they apply to the Loss of Instrument Air

Emergency air compressor 3.5 55 077 / Generator Voltage and Electric Grid Disturbances / 6 X 2.1.23 Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation 4.3 56 K/A Category Point Totals:

2 2 3 3 4 / 3 4 / 3 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 Page 5 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc E/APE # / Name Safety Function K1 K2 K3 A1 A2 G Number K/A Topic(s)

Imp. Q# 032 / Loss of Source Range NI / 7 X AA2.09 Ability to determine and interpret the following a s they apply to the Loss of Source Range Nuclear Instrumentation

Effect of improper HV setting 2.9 82 051 / Loss of Condenser Vacuum / 4 X 2.4.18 Emergency Procedures/Plan:

Knowledge of specific bases for EOPs 4.0 83 061 / Area Radiation Monitoring System Alarms /

7 X AA2.06 Ability to determine and interpret the following as they apply to the Area Radiation Monitoring System Alarms

Required actions if the alarm channel is out of service 4.1 84 CE / A16 / Excess RCS Leakage / 2 X 2.4.21 Emergency Procedures/Plan:

Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. 4.6 85 001 / Continuous Rod Withdrawal / 1 X AA1.02 Ability to operate and/or monitor the following as they apply to the Continuous Rod Withdrawal

Rod in-hold-out switch 3.6 57 003 / Dropped Control Rod / 1 X AA2.0 1 Ability to determine and interpret the following as they apply to the Dropped Control Rod

Rod position indication to actual rod position 3.7 58 024 / Emergency Boration / 1 X AK1.02 Knowledge of the operational implications of the following concepts as they apply to Emergency Boration: Relationship between boron addition and reactor power 3.6 59 060 / Accidental Gaseous Radwaste Release

/ 9 X AA2.0 6 Ability to determine and interpret the following as they apply to the Accidental Gaseous Release

Valve lineup for release of radioactive gases 3.6 60 061 / Area Radiation Monitoring System Alarms /

7 X 2.4.6 Emergency Procedures/Plan:

Knowledge of EOP mitigation strategies 3.7 61 067 / Plant Fire on Site / 8 X AK1.02 Knowledge of the operational implications of the following concepts as they apply to Plant Fire on Site: Fire fighting 3.1 62 069 / Loss of Containment Integrity / 5 X AK2.03 Knowledge of the interrelations between t he Loss of Containment Integrity and the following

Personnel access hatch and emergency access hatch 2.8 63 ES-401 SONGS 2 & 3 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions

- Tier 1 Group 2 Form ES-401-2 Page 6 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc E/APE # / Name Safety Function K1 K2 K3 A1 A2 G Number K/A Topic(s)

Imp. Q# 076 / High Reactor Coolant Activity / 9 X AA2.01 Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity

Location or process point that is causing an alarm 2.7 64 CE / A11 / RCS Overcooling

- PTS / 4 X AK2.2 Knowledge of the interrelations between RCS Overcooling and the following: Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility 3.2 65 K/A Category Point Totals:

2 2 0 1 3 / 2 1 / 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 Page 7 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Number K/A Topics Imp. Q# 006 / Emergency Core Cooling X 2.2.37 Equipment Control:

Ability to determine operability and / or availability of safety-related equipment 4.6 86 062 / AC Electrical Distribution X 2.4.21 Emergency Procedures/Plan

knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

4.6 87 013 / Engineered Safety Features Actuation X A2.0 6 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Inadvertent ESFAS actuation 4.0 88 061 / Auxiliary/Emergency Feedwater X A2.07 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:

Air or MOV failure 3.5 89 012 / Reactor Protection X 2.2.22 Emergency Procedures/Plan:

Knowledge of limiting conditions for operations and safety limits 4.7 90 003 / Reactor Coolant Pump X A2 .03 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 associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems 2.7 1 003 / Reactor Coolant Pump X K2.02 Knowledge of bus power supplies to the following: CCW pumps 2.5 2 004 / Chemical and Volume Control X K2.06 Knowledge of bus power supplies to the following: Control instrumentation 2.6 3 ES-401 SONGS 2 & 3 NRC Written Examination Outline Plant Systems

- Tier 2 Group 1 Form ES-401-2 Page 8 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc 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 K4.12 Knowledge of the CVCS design feature(s) and/or interlock(s) which provide for the following: Minimum level of VCT 3.1 4 005 / Residual Heat Removal X A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the RHR system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown 3.5 5 005 / Residual Heat Removal X K1.08 Knowledge of the physical connections and/or cause-effect relationships between the RHRS and the following systems: SWS 2.7 6 006 / Emergency Core Cooling X K6.01 Knowledge of the effect that a loss or malfunction of the following will have on the ECCS: BIT / borated water sources 3.4 7 007 / Pressurizer Relief

/ Quench Tank X 2.4.11 Emergency Procedures/Plan:

Knowledge of abnormal condition procedures 4.0 8 008 / Component Cooling Water X K4.07 Knowledge of the CCW S design feature(s) and/or interlock(s) that provide for the following:

Operation of the CCW swing

-bus power supply and its associated breaker s and controls 2.6 9 010 / Pressurizer Pressure Contro l X K6.01 Knowledge of the effect that a loss or malfunction of the following will have on the PZR PCS: Pressure detection systems 2.7 10 012 / Reactor Protection X K6.09 Knowledge of the effect that a loss or malfunction of the following will have on the RPS: CEAC 3.6 11 012 / Reactor Protection X K3.01 Knowledge of the effect that a loss or malfunction of the RPS will have on the following: CRDS 3.9 12 013 / Engineered Safety Features Actuation X 2.1.28 Conduct of Operations: Knowledge of the purpose and function of major system components and controls 4.1 13 013 / Engineered Safety Features Actuation X A4.0 2 Ability to manually operate and/or monitor in the control room: Reset of ESFAS channels 4.3 14 ES-401 SONGS 2 & 3 NRC Written Examination Outline Plant Systems

- Tier 2 Group 1 Form ES-401-2 Page 9 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Number K/A Topics Imp. Q# 022 / Containment Cooling X A3.01 Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation 4.1 15 026 / Containment Spray X K1.02 Knowledge of the physical connections and/or cause-effect relationships between the CSS and the following systems: Cooling water 4.1 16 026 / Containment Spray X A4.01 Ability to manually operate and/or monitor in the control room: CSS controls 4.5 17 039 / Main and Reheat Steam X A3.02 Ability to monitor automatic operation of the MRSS, including: Isolation of the MRSS 3.1 18 059 / Main Feedwater X K1.03 Knowledge of the physical connections and/or cause-effect relationships between the MFW and the following systems: SGs 3.1 19 061 / Auxiliary/Emergency Feedwater X K5.03 Knowledge of the operational implications of the following concepts as they apply to the AFW: Pump head effects when control valve is shut 2.6 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 A1.08 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the EDG system controls including: Maintaining minimum load on EDG (to prevent reverse power) 3.1 23 064 / Emergency Diesel Generator X K2.01 Knowledge of bus power supplies to the following: Air compressor 2.7 24 073 / Process Radiation Monitoring X K4.01 Knowledge of the PRM system design feature(s) and/or interlock(s) that provide for the following: Release termination when radiation exceeds setpoint 4.0 25 ES-401 SONGS 2 & 3 NRC Written Examination Outline Plant Systems

- Tier 2 Group 1 Form ES-401-2 Page 10 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Number K/A Topics Imp. Q# 076 / Service Water X A4.04 Ability to manually operate and/or monitor in the control room: Emergency heat loads 3.5 26 078 / Instrument Air X K4.03 Knowledge of the IAS system design feature(s) and/or interlock(s) that provide for the following: Securing of SAS upon loss of cooling water 3.1 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 3 2 4 1 3 1 3 / 2 3 3 2 / 3 Group Point Total:

28 / 5 ES-401 SONGS 2 & 3 NRC Written Examination Outline Plant Systems

- Tier 2 Group 2 Form ES-401-2 Page 11 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Number K/A Topics Imp. Q# 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 91 045 / Main Turbine Generator X A2.0 8 Ability to (a) predict the impacts of the following malfunctions or operations on the MTG System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Steam dumps are not cycling properly at low load, or stick open at higher load (isolate and use atmospheric reliefs when necessary) 3.1 92 035 / Steam Generator X 2.4.47 Emergency Procedures/Plan:

Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material 4.2 93 002 / Reactor Coolant X A3.03 Ability to monitor automatic operation of the RCS, including: Pressure, temperature, and flows 4.4 29 011 / Pressurizer Level Control X K3.01 Knowledge of the effect that a loss or malfunction of the PZR LCS will have on the following: CVCS 3.2 30 015 / Nuclear Instrumentation X K5.17 Knowledge of the operational implications of the following concepts as they apply to the NIS: DNB and DNBR definition and effects 3.5 31 016 / Non-Nuclear Instrumentation X K1.12 Knowledge of the physical connections and/or cause

-effect relationships between the NNIS and the following systems: S/G 3.5 32 033 / Spent Fuel Pool Cooling X A1.0 1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Spent Fuel Pool Cooling System controls including: Spent fuel pool water level 2.7 33 ES-401 SONGS 2 & 3 NRC Written Examination Outline Plant Systems

- Tier 2 Group 2 Form ES-401-2 Page 12 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc System #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Number K/A Topics Imp. Q# 034 / Fuel Handling Equipment X K4.0 2 Knowledge of design feature(s) and/or interlock(s) that provide for the following:

Fuel movement 2.6 34 056 / Condensate X A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate system; and (b) based on thos e predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps 2.6 35 068 / Liquid Radwaste X K6.10 Knowledge of the effect that a loss or malfunction of the following will have on the Liquid Radwaste System: Radiation monitors 2.5 36 071 / Waste Gas Disposal X 2.1.27 Conduct of Operations: Knowledge of system purpose and/or function 3.9 37 072 / Area Radiation Monitoring X K4.02 Knowledge of the ARM system design feature(s) and/or interlock(s) that provide for the following: Fuel building isolation 3.2 38 K/A Category Point Totals:

1 0 1 2 1 1 1 1 / 2 1 0 1 / 1 Group Point Total:

10 / 3 ES-401 Generic Knowledge and Abilities Outline

- Tier 3 Form ES-401-3 Page 13 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc Facility: SONGS 2 & 3 NRC Date of Exam: 10/31/11 Category K/A # Topic RO SRO-Only IR # IR # 1. Conduct of Operations 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, over time limitations, etc.

3.9 94 2.1.34 Knowledge of primary and secondary plant chemistry limits 3.5 95 2.1.19 Ability to use plant computers to evaluate system or component status 3.9 66 2.1.32 Ability to explain and apply system limits and precautions 3.8 67 Subtotal 2 2

2. Equipment Control 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator 3.8 9 6 2.2.40 Ability to apply Technical Specifications for a system 4.7 9 7 2.2.12 Knowledge of surveillance procedures 3.7 68 2.2.14 Knowledge of the process for controlling equipment configuration or status 3.9 69 2.2.35 Ability to determine Technical Specification Mode of Operation 3.6 70 Subtotal 3 2 3. Radiation Control 2.3.6 Ability to approve release permits 3.8 98 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions 3.5 71 2.3.11 Ability to control radiation releases 3.8 7 2 Subtotal 2 1

4. Emergency Procedures / Plan 2.4.27 Knowledge of "fire in the plant" procedures 3.9 99 2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm 4.3 100 2.4.2 Knowledge of systems setpoints, interlocks and automatic actions associated with EOP entry conditions 4.5 73 2.4.26 Knowledge of facility protection requirements, including fire brigade and portable firefighting equipment usage 3.1 74 2.4.32 Knowledge of operator response to loss of all annunciators 3.6 75 Subtotal 3 2 Tier 3 Point Total 10 7 ES-401 Record of Rejected K/As Form ES-401-4 Page 14 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc Tier / Group Randomly Selected K/A Reason for Rejection 1 / 1 015/017 AA2.11 Q #78 - Jogging of RCPs is not performed at SONGS during Inadequate Core Cooling. Randomly reselected 015/017 AA2.01

. 2 / 2 016 K1.07 Q #32 - There is no interface between the Non

-Nuclear Instrumentation and Emergency Core Cooling Systems at SONGS. Randomly reselected 016 K1.12. 2 / 2 033 A1.02 Q #33 - There is no interface between the Spent Fuel Pool Cooling System and Radiation Monitoring System at SONGS. Randomly reselected 033 A1.01.

2 / 2 034 A4.01 Q #34 - There is no interface between the Fuel Handling Equipment System and Radiation Monitoring System (radiation levels) at SONGS. Reselected 034 K4.02. 2 / 2 071 G 2.4.4 Q #37 - There are no Abnormal or Emergency Operating Procedures associated with the Waste Gas Disposal System. Reselected 071 G 2.1.27. The rejected K/As listed above were identified by SONGS during development of the DRAFT written exam outline

. The K/As listed below were identified during written exam development (prior to draft outline submittal)

. 1 / 2 024 G 2.2.22 Q #59 - Unable to develop a psychometrically sound question that discriminates at the RO license level. Reselected 024 AK1.02.

2 / 1 063 A1.01 Q #22 - This K/A was determined operationally invalid during exam validation. Question was left on Worksheet for CE review. Reselected 063 A3.01. 1 / 2 060 AK3.03 Q #60 - Unable to develop a psychometrically sound question that discriminates at the RO license level. Reselected 060 AA2.06

. 2 / 1 006 K5.11 Q #07 - This K/A identified as generic fundamentals. Reselected 006 K6.01.

2 / 1 013 A4.01 Q #14 - This K/A adequately covered during Scenario events. Randomly reselected 013 A4.02. 1 / 1 057 AA2.11 Q #52 - Unable to develop a psychometrically sound question that discriminates at the RO license level. Randomly r eselected 057 AA2.12

. 1 / 1 038 EA1.08 Q #47 - Unable to develop a psychometrically sound question that discriminates at the RO license level. Reselected 038 EA2.01

. 1 / 1 061 G 2.1.25 Q #54 - This K/A is addressed by Admin JPM RA1. R eselected 061 G 2.4.35. 1 / 2 003 AK1.04 Q #58 - This K/A identified as generic fundamentals. Reselected 003 AA2.01.

1 / 1 040 AK1.04 Q #48 - Unable to develop a psychometrically sound question that discriminates at the RO license level. Randomly reselected 040 AK1.01

. 1 / 1 007 G 2.2.25 Q #39 - Unable to develop a psychometrically sound question that discriminates at the RO license level. Randomly reselected 007 G 2.1.7

. 1 / 1 054 G 2.2.36 Q #49 - Replaced K/A to test concept not addressed during Simulator Scenario development (Safety Injection Throttle / Stop). R eselected 011 G 2.4.49. 1 / 1 027 G 2.4.3 Q #79 - Unable to develop a psychometrically sound question that discriminates at the SRO license level. 027 G 2.4.50.

ES-401 Record of Rejected K/As Form ES-401-4 Page 15 of 15 SONGS NRC 2011 ES

-401-2 3 4 Written Outline Rev c.doc Tier / Group Randomly Selected K/A Reason for Rejection 1 / 1 057 AA2.05 Q #81 - Unable to develop a psychometrically sound question that discriminates at the SRO license level. Reselected Abnormal Operating Instruction not addressed during Simulator Scenario development (Loss of DC Power) 058 G 2.4.4. 2 / 1 010 G 2.2.37 Q #86 - Pressurizer Pressure Control System adequately addressed by Simulator Scenarios. Reselected 006 G 2.2.37

. 2 / 1 062 G 2.1.30 Q #87 - Unable to develop a psychometrically sound question that discriminates at the SRO license level. Reselected 062 G 2.4.21

. 2 / 1 013 A2.04 Q #88 - Unable to develop a psychometrically sound question that discriminates at the SRO license level. Reselected 013 A2.06

. 2 / 1 063 G 2.4.8 Q #90 - Unable to develop a psychometrically sound question that discriminates at the SRO license level. Reselected 012 G 2.2.22

. 2 / 2 068 G 2.4.49 Q #91 - Unable to develop a psychometrically sound question that discriminates at the SRO license level. Reselected 015 A2.03

. 2 / 2 072 A2.02 Q #92 - Unable to develop a psychometrically sound question that discriminates at the SRO license level. Reselected 045 A2.08

. 1 / 1 015/17 AK3.07 Q #41 - K/A replaced as it provided information required for Q#51.

Unable to develop a psychometrically sound question that discriminates at the RO license level fro K/A AK3.07. Reselected 015/17 AA1.03

.