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 Facility: SONGS 2 & 3 NRC Date of Exam: 10/31/11 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 2 2 3 3 4 4 18 3 3 6

& Abnormal 2 2 2 0 1 3 1 9 2 2 4 Plant Evolutions Tier Totals 4 4 3 4 7 5 27 5 5 10 1 3 3 2 4 1 3 1 3 3 3 2 28 2 3 5

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

Page 1 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

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 009 / Small Break LOCA / 3 X EA2.14 they apply to the small break LOCA: Actions to 4.4 76 be taken if PTS limits are violated Equipment Control: Ability to determine 011 / Large Break LOCA / 3 X 2.2.37 operability and/or availability of safety related 4.6 77 equipment Ability to determine and interpret the following as they apply to the Reactor Coolant Pump 015/017 / RCP Malfunctions / 4 X AA2.01 3.5 78 Malfunctions (Loss of RC Flow): Cause of RCP failure Emergency Procedures/Plan: Ability to verify 027 / Pressurizer Pressure Control Malfunction / 3 X 2.4.50 system alarms setpoints and operate controls 4.0 79 identified in the alarm response manual Ability to determine and interpret the following as 029 / ATWS / 1 X EA2.01 they apply to the ATWS: Reactor nuclear 4.7 80 instrumentation Emergency Procedures/Plan: Ability to recognize abnormal indications for system 058 / Loss of DC Power / 6 X 2.4.4 operating parameters that are entry-level 4.7 81 conditions for emergency and abnormal operating procedures Conduct of Operations: Ability to evaluate plant performance and make operational judgments 007 / Reactor Trip - Stabilization - Recovery / 1 X 2.1.7 4.4 39 based on operating characteristics, reactor behavior, and instrument interpretation Knowledge of the interrelations between small 009 / Small Break LOCA / 3 X EK2.03 3.0 40 break LOCA and the following: SGs Ability to operate and/or monitor the following as they apply to the Reactor Coolant Pump 015 / 17 / RCP Malfunctions / 4 X AA1.03 3.7 41 Malfunctions (Loss of RC Flow): Reactor trip alarms, switches, and indicators Knowledge of the reasons for the following 022 / Loss of Reactor Coolant Makeup / 2 X AK3.06 responses as they apply to the Loss of Reactor 3.2 42 Coolant Makeup: RCP thermal barrier cooling Page 2 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

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 Loss of Residual Heat 025 / Loss of RHR System / 4 X AA2.02 Removal System: Leakage of reactor coolant 3.4 43 from RHR into closed cooling water system or into reactor building atmosphere Ability to determine and interpret the following as they apply to the Loss of Component Cooling 026 / Loss of Component Cooling Water / 8 X AA2.06 Water: The length of time after the loss of CCW 2.8 44 flow to a component before that component may be damaged Ability to operate and/or monitor the following as 027 / Pressurizer Pressure Control System they apply to the Pressurizer Pressure Control X AA1.03 3.6 45 Malfunction / 3 Malfunctions: Pressure control when on a steam bubble Knowledge of the interrelations between ATWS 029 / ATWS / 1 X EK2.06 and the following: Breakers, relays, and 2.9 46 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 47 more SGs Knowledge of the operational implications of the 040 / Steam Line Rupture - Excessive Heat X AK1.01 following concepts as they apply to the Steam 4.1 48 Transfer / 4 Line Rupture: Consequences of PTS Emergency Procedures/Plan: Ability to perform without reference to procedures those actions 011 / Large Break LOCA / 3 X 2.4.49 4.6 49 that require immediate operation of system components and controls Knowledge of the operational implications of the 055 / Station Blackout / 6 X EK1.02 following concepts as they apply to the Station 4.1 50 Blackout: Natural circulation cooling 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 51 Power: Actions contained in EOP for loss of offsite power Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument 057 / Loss of Vital AC Instrument Bus / 6 X AA2.12 3.5 52 Bus: PZR level controller, instrumentation, and heater indications Page 3 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

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 DC 058 / Loss of DC Power / 6 X AK3.02 4.0 53 Power: Actions contained in EOP for loss of DC power Emergency Procedures/Plan: Knowledge of 062 / Loss of Nuclear Service Water / 4 X 2.4.35 local auxiliary operator tasks during an 3.8 54 emergency and the resultant operational effects Ability to operate and/or monitor the following as 065 / Loss of Instrument Air / 8 X AA1.04 they apply to the Loss of Instrument Air: 3.5 55 Emergency air compressor Conduct of Operations: Ability to perform 077 / Generator Voltage and Electric Grid X 2.1.23 specific system and integrated plant procedures 4.3 56 Disturbances / 6 during all modes of plant operation K/A Category Point Totals: 2 2 3 3 4/3 4/3 Group Point Total: 18 / 6 Page 4 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

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 determine and interpret the following as 032 / Loss of Source Range NI / 7 X AA2.09 they apply to the Loss of Source Range Nuclear 2.9 82 Instrumentation: Effect of improper HV setting Emergency Procedures/Plan: Knowledge of 051 / Loss of Condenser Vacuum / 4 X 2.4.18 4.0 83 specific bases for EOPs Ability to determine and interpret the following as 061 / Area Radiation Monitoring System Alarms / they apply to the Area Radiation Monitoring X AA2.06 4.1 84 7 System Alarms: Required actions if the alarm channel is out of service Emergency Procedures/Plan: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, CE / A16 / Excess RCS Leakage / 2 X 2.4.21 4.6 85 core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Ability to operate and/or monitor the following as 001 / Continuous Rod Withdrawal / 1 X AA1.02 they apply to the Continuous Rod Withdrawal: 3.6 57 Rod in-hold-out switch Ability to determine and interpret the following as 003 / Dropped Control Rod / 1 X AA2.01 they apply to the Dropped Control Rod: Rod 3.7 58 position indication to actual rod position Knowledge of the operational implications of the following concepts as they apply to Emergency 024 / Emergency Boration / 1 X AK1.02 3.6 59 Boration: Relationship between boron addition and reactor power Ability to determine and interpret the following as 060 / Accidental Gaseous Radwaste Release / 9 X AA2.06 they apply to the Accidental Gaseous Release: 3.6 60 Valve lineup for release of radioactive gases 061 / Area Radiation Monitoring System Alarms / Emergency Procedures/Plan: Knowledge of X 2.4.6 3.7 61 7 EOP mitigation strategies Knowledge of the operational implications of the 067 / Plant Fire on Site / 8 X AK1.02 following concepts as they apply to Plant Fire on 3.1 62 Site: Fire fighting Knowledge of the interrelations between the Loss of Containment Integrity and the following:

069 / Loss of Containment Integrity / 5 X AK2.03 2.8 63 Personnel access hatch and emergency access hatch Page 5 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

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 determine and interpret the following as they apply to the High Reactor Coolant Activity:

076 / High Reactor Coolant Activity / 9 X AA2.01 2.7 64 Location or process point that is causing an alarm Knowledge of the interrelations between RCS Overcooling and the following: Facilitys heat removal systems, including primary coolant, CE / A11 / RCS Overcooling - PTS / 4 X AK2.2 emergency coolant, the decay heat removal 3.2 65 systems, and relations between the proper operation of these systems to the operation of the facility K/A Category Point Totals: 2 2 0 1 3/2 1/2 Group Point Total: 9/4 Page 6 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

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#

Equipment Control: Ability to determine 006 / Emergency Core X 2.2.37 operability and / or availability of safety-related 4.6 86 Cooling equipment Emergency Procedures/Plan: knowledge of the parameters and logic used to assess the status 062 / AC Electrical of safety functions, such as reactivity control, X 2.4.21 4.6 87 Distribution core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and 013 / Engineered Safety (b) based on those predictions, use procedures X A2.06 4.0 88 Features Actuation to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent ESFAS actuation 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 A2.07 3.5 89 Feedwater to correct, control, or mitigate the consequences of those malfunctions or operations: Air or MOV failure Emergency Procedures/Plan: Knowledge of 012 / Reactor Protection X 2.2.22 limiting conditions for operations and safety 4.7 90 limits 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 003 / Reactor Coolant Pump X A2 .03 consequences of those malfunctions or 2.7 1 operations: Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems Knowledge of bus power supplies to the 003 / Reactor Coolant Pump X K2.02 2.5 2 following: CCW pumps 004 / Chemical and Volume Knowledge of bus power supplies to the X K2.06 2.6 3 Control following: Control instrumentation Page 7 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

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 CVCS design feature(s) 004 / Chemical and Volume X K4.12 and/or interlock(s) which provide for the 3.1 4 Control following: Minimum level of VCT Ability to (a) predict the impacts of the following malfunctions or operations on the RHR system; and (b) based on those predictions, 005 / Residual Heat Removal X A2.02 use procedures to correct, control, or mitigate 3.5 5 the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown Knowledge of the physical connections and/or 005 / Residual Heat Removal X K1.08 cause-effect relationships between the RHRS 2.7 6 and the following systems: SWS Knowledge of the effect that a loss or 006 / Emergency Core X K6.01 malfunction of the following will have on the 3.4 7 Cooling ECCS: BIT / borated water sources 007 / Pressurizer Relief / Emergency Procedures/Plan: Knowledge of X 2.4.11 4.0 8 Quench Tank abnormal condition procedures Knowledge of the CCWS design feature(s) and/or interlock(s) that provide for the 008 / Component Cooling X K4.07 following: Operation of the CCW swing-bus 2.6 9 Water power supply and its associated breakers and controls Knowledge of the effect that a loss or 010 / Pressurizer Pressure X K6.01 malfunction of the following will have on the 2.7 10 Control PZR PCS: Pressure detection systems Knowledge of the effect that 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 effect that a loss or 012 / Reactor Protection X K3.01 malfunction of the RPS will have on the 3.9 12 following: CRDS Conduct of Operations: Knowledge of the 013 / Engineered Safety X 2.1.28 purpose and function of major system 4.1 13 Features Actuation components and controls 013 / Engineered Safety Ability to manually operate and/or monitor in X A4.02 4.3 14 Features Actuation the control room: Reset of ESFAS channels Page 8 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

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 monitor automatic operation of the 022 / Containment Cooling X A3.01 CCS, including: Initiation of safeguards mode 4.1 15 of operation Knowledge of the physical connections and/or 026 / Containment Spray X K1.02 cause-effect relationships between the CSS 4.1 16 and the following systems: Cooling water Ability to manually operate and/or monitor in 026 / Containment Spray X A4.01 4.5 17 the control room: CSS controls Ability to monitor automatic operation of the 039 / Main and Reheat Steam X A3.02 3.1 18 MRSS, including: Isolation of the MRSS Knowledge of the physical connections and/or 059 / Main Feedwater X K1.03 cause-effect relationships between the MFW 3.1 19 and the following systems: SGs Knowledge of the operational implications of 061 / Auxiliary/Emergency the following concepts as they apply to the X K5.03 2.6 20 Feedwater AFW: Pump head effects when control valve is shut 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 Ability to predict and/or monitor changes in parameters (to prevent exceeding design 064 / Emergency Diesel limits) associated with operating the EDG X A1.08 3.1 23 Generator system controls including: Maintaining minimum load on EDG (to prevent reverse power) 064 / Emergency Diesel Knowledge of bus power supplies to the X K2.01 2.7 24 Generator following: Air compressor Knowledge of the PRM system design 073 / Process Radiation feature(s) and/or interlock(s) that provide for X K4.01 4.0 25 Monitoring the following: Release termination when radiation exceeds setpoint Page 9 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

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 manually operate and/or monitor in 076 / Service Water X A4.04 3.5 26 the control room: Emergency heat loads Knowledge of the IAS system design feature(s) and/or interlock(s) that provide for the 078 / Instrument Air X K4.03 3.1 27 following: Securing of SAS upon loss of cooling water 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 3 2 4 1 3 1 3/2 3 3 2/3 Group Point Total: 28 / 5 Page 10 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

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 (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 91 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Xenon oscillations 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, 045 / Main Turbine Generator X A2.08 control, or mitigate the consequences of 3.1 92 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)

Emergency Procedures/Plan: Ability to diagnose and recognize trends in an 035 / Steam Generator X 2.4.47 4.2 93 accurate and timely manner utilizing the appropriate control room reference material Ability to monitor automatic operation of the 002 / Reactor Coolant X A3.03 RCS, including: Pressure, temperature, and 4.4 29 flows Knowledge of the effect that a loss or 011 / Pressurizer Level X K3.01 malfunction of the PZR LCS will have on the 3.2 30 Control following: CVCS Knowledge of the operational implications of 015 / Nuclear Instrumentation X K5.17 the following concepts as they apply to the 3.5 31 NIS: DNB and DNBR definition and effects Knowledge of the physical connections 016 / Non-Nuclear X K1.12 and/or cause-effect relationships between 3.5 32 Instrumentation the NNIS and the following systems: S/G Ability to predict and/or monitor changes in parameters (to prevent exceeding design 033 / Spent Fuel Pool Cooling X A1.01 limits) associated with operating the Spent 2.7 33 Fuel Pool Cooling System controls including:

Spent fuel pool water level Page 11 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

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#

Knowledge of design feature(s) and/or 034 / Fuel Handling X K4.02 interlock(s) that provide for the following: 2.6 34 Equipment Fuel movement Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate system; and (b) based on those 056 / Condensate X A2.04 predictions, use procedures to correct, 2.6 35 control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps Knowledge of the effect that a loss or malfunction of the following will have on the 068 / Liquid Radwaste X K6.10 2.5 36 Liquid Radwaste System: Radiation monitors Conduct of Operations: Knowledge of 071 / Waste Gas Disposal X 2.1.27 3.9 37 system purpose and/or function Knowledge of the ARM system design 072 / Area Radiation X K4.02 feature(s) and/or interlock(s) that provide for 3.2 38 Monitoring the following: Fuel building isolation K/A Category Point Totals: 1 0 1 2 1 1 1 1/2 1 0 1 / 1 Group Point Total: 10 / 3 Page 12 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

ES-401 Generic Knowledge and Abilities Outline - Tier 3 Form ES-401-3 Facility: SONGS 2 & 3 NRC Date of Exam: 10/31/11 Category K/A # Topic RO SRO-Only IR # IR #

2.1.5 Ability to use procedures related to shift staffing, such as 3.9 94

1. minimum crew complement, over time limitations, etc.

Conduct 2.1.34 Knowledge of primary and secondary plant chemistry 3.5 95 of Operations limits 2.1.19 Ability to use plant computers to evaluate system or 3.9 66 component status 2.1.32 Ability to explain and apply system limits and precautions 3.8 67 Subtotal 2 2 2.2.17 Knowledge of the process for managing maintenance 3.8 96

2. activities during power operations, such as risk Equipment assessments, work prioritization, and coordination with Control the transmission system operator 2.2.40 Ability to apply Technical Specifications for a system 4.7 97 2.2.12 Knowledge of surveillance procedures 3.7 68 2.2.14 Knowledge of the process for controlling equipment 3.9 69 configuration or status 2.2.35 Ability to determine Technical Specification Mode of 3.6 70 Operation Subtotal 3 2 2.3.6 Ability to approve release permits 3.8 98

3. 2.3.7 Ability to comply with radiation work permit requirements 3.5 71 Radiation during normal or abnormal conditions Control 2.3.11 Ability to control radiation releases 3.8 72 Subtotal 2 1 2.4.27 Knowledge of fire in the plant procedures 3.9 99

4. 2.4.45 Ability to prioritize and interpret the significance of each 4.3 100 Emergency annunciator or alarm Procedures /

Plan 2.4.2 Knowledge of systems setpoints, interlocks and automatic 4.5 73 actions associated with EOP entry conditions 2.4.26 Knowledge of facility protection requirements, including 3.1 74 fire brigade and portable firefighting equipment usage 2.4.32 Knowledge of operator response to loss of all 3.6 75 annunciators Subtotal 3 2 Tier 3 Point Total 10 7 Page 13 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 015/017 Q #78 - Jogging of RCPs is not performed at SONGS during Inadequate Core 1/1 AA2.11 Cooling. Randomly reselected 015/017 AA2.01.

Q #32 - There is no interface between the Non-Nuclear Instrumentation and 2/2 016 K1.07 Emergency Core Cooling Systems at SONGS. Randomly reselected 016 K1.12.

Q #33 - There is no interface between the Spent Fuel Pool Cooling System 2/2 033 A1.02 and Radiation Monitoring System at SONGS. Randomly reselected 033 A1.01.

Q #34 - There is no interface between the Fuel Handling Equipment System 2/2 034 A4.01 and Radiation Monitoring System (radiation levels) at SONGS. Reselected 034 K4.02.

Q #37 - There are no Abnormal or Emergency Operating Procedures 2/2 071 G 2.4.4 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).

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

Q #22 - This K/A was determined operationally invalid during exam validation.

2/1 063 A1.01 Question was left on Worksheet for CE review. Reselected 063 A3.01.

Q #60 - Unable to develop a psychometrically sound question that 1/2 060 AK3.03 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.

Q #14 - This K/A adequately covered during Scenario events. Randomly 2/1 013 A4.01 reselected 013 A4.02.

Q #52 - Unable to develop a psychometrically sound question that 1/1 057 AA2.11 discriminates at the RO license level. Randomly reselected 057 AA2.12.

Q #47 - Unable to develop a psychometrically sound question that 1/1 038 EA1.08 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. Reselected 061 G 2.4.35.

1/2 003 AK1.04 Q #58 - This K/A identified as generic fundamentals. Reselected 003 AA2.01.

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

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

Q #49 - Replaced K/A to test concept not addressed during Simulator Scenario 1/1 054 G 2.2.36 development (Safety Injection Throttle / Stop). Reselected 011 G 2.4.49.

Q #79 - Unable to develop a psychometrically sound question that 1/1 027 G 2.4.3 discriminates at the SRO license level. 027 G 2.4.50.

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ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A Q #81 - Unable to develop a psychometrically sound question that discriminates at the SRO license level. Reselected Abnormal Operating 1/1 057 AA2.05 Instruction not addressed during Simulator Scenario development (Loss of DC Power) 058 G 2.4.4.

Q #86 - Pressurizer Pressure Control System adequately addressed by 2/1 010 G 2.2.37 Simulator Scenarios. Reselected 006 G 2.2.37.

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

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

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

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

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

Q #41 - K/A replaced as it provided information required for Q#51. Unable to 015/17 1/1 develop a psychometrically sound question that discriminates at the RO AK3.07 license level fro K/A AK3.07. Reselected 015/17 AA1.03.

Page 15 of 15 SONGS NRC 2011 ES-401-2 3 4 Written Outline Rev c.doc