ML103210278

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SONGS-2010-10-Final Outlines
ML103210278
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 10/15/2010
From: Clyde Osterholtz
Operations Branch IV
To:
Southern California Edison Co
References
Download: ML103210278 (18)
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ES-401 PWR Examination Outline Form ES-401-2 Facility: SONGS 2 & 3 NRC Date of Exam: 10/18/10 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 3 3 3 3 4 18 3 3 6

& Abnormal 2 2 1 3 0 2 1 9 4 0 4 Plant Evolutions Tier Totals 4 4 6 3 5 5 27 7 3 10 1 3 2 2 4 2 2 3 2 2 3 3 28 2 3 5

2. Plant Systems 2 1 1 1 1 1 1 0 1 1 1 1 10 2 0 1 3 Tier Totals 4 3 3 5 3 3 3 3 3 4 4 38 4 4 8
3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 Categories 10 7 2 3 3 2 1 2 2 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 2010 ES-401-2 & 3 & 4 Written Outline Rev h.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#

Equipment Control: Ability to interpret control room indications to verify the status and 015/017 / RCP Malfunctions / 4 X 2.2.44 operation of a system, and understand how 4.4 76 operator actions and directives affect plant and system conditions Ability to determine or interpret the following as they apply to a reactor trip: If reactor should 007 / Reactor Trip - Stabilization - Recovery / 1 X EA2.04 have tripped but has not done so, manually trip 4.6 77 the reactor and carry out actions in the ATWS EOP Emergency Procedures/Plan: Knowledge of 029 / ATWS / 1 X 2.4.6 4.7 78 EOP mitigation strategies Ability to determine and interpret the following as they apply to the Loss of Feedwater: Facility CE / E06 / Loss of Main Feedwater / 4 X EA2.1 conditions and selection of appropriate 3.9 79 procedures during abnormal and emergency operations Emergency Procedures/Plan: Knowledge of 009 / Small Break LOCA / 3 X 2.4.41 emergency action level thresholds and 4.6 80 classifications 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 81 Consequences of managing LOCA with loss of CCW Conduct of Operations: Ability to locate control CE / E02 / Reactor Trip - Stabilization - Recovery room switches, controls, and indications, and to X 2.1.31 4.6 39

/1 determine that they correctly reflect the desired plant lineup 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 40 Accident: PRT level, pressure, and temperature Knowledge of the reasons for the following 009 / Small Break LOCA / 3 X EK3.22 responses as they apply to the Small Break 4.4 41 LOCA: Maintenance of heat sink Ability to determine and interpret the following as 011 / Large Break LOCA / 3 X EA2.11 they apply to a Large Break LOCA: Conditions 3.9 42 for throttling or stopping HPI Page 2 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.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 operational implications of the following concepts as they apply to RCP 015 / 17 / RCP Malfunctions / 4 X AK1.02 3.7 43 Malfunctions (Loss of RC Flow): Consequences of an RCP failure Knowledge of the reasons for the following responses as they apply to the Loss of Residual 025 / Loss of RHR System / 4 X AK3.01 3.1 44 Heat Removal System: Shift to alternate flowpath Conduct of Operations: Ability to use plant 022 / Loss of Reactor Coolant Makeup / 2 X 2.1.19 computers to evaluate system or component 3.9 45 status Knowledge of the interrelations between the 027 / Pressurizer Pressure Control System X AK2.03 Pressurizer Pressure Control Malfunctions and 2.6 46 Malfunction / 3 the following: Controllers and positioners Ability to determine and interpret the following as they apply to the Excess Steam Demand:

CE / E05 / Excess Steam Demand / 4 X EA2.1 Facility conditions and selection of appropriate 2.7 47 procedures during abnormal and emergency operations Knowledge of the operational implications of the following concepts as they apply to the Steam 038 / Steam Generator Tube Rupture / 3 X EK1.02 3.2 48 Generator Tube Rupture: Leak rate versus pressure drop Knowledge of the interrelations between the Loss of Feedwater and the following:

Components, and functions of control and safety CE / E06 / Loss of Feedwater / 4 X EK2.1 3.3 49 systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 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 Ability to operate and/or monitor the following as 057 / Loss of Vital AC Instrument Bus / 6 X AA1.05 they apply to the Loss of Vital AC Instrument 3.2 51 Bus: Backup instrument indications Page 3 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.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 operate and/or monitor the following as 058 / Loss of DC Power / 6 X AA1.03 they apply to the Loss of DC power: Vital and 3.1 52 battery bus components Emergency Procedures/Plan: Ability to recognize abnormal indications for system operating 062 / Loss of Nuclear Service Water / 4 X 2.4.4 4.5 53 parameters that are entry-level conditions for emergency and abnormal operating procedures Ability to determine and interpret the following as they apply to the Station Blackout: RCS core 055 / Station Blackout / 6 X EA2.02 4.4 54 cooling through natural circulation cooling to SG cooling Knowledge of the interrelations between 077 / Generator Voltage and Electric Grid X AK2.02 Generator Voltage and Electric Grid 3.1 55 Disturbances / 6 Disturbances and the following: Breakers, relays Conduct of Operations: Ability to evaluate plant performance and make operational judgments 029 / ATWS / 1 X 2.1.7 4.4 56 based on operating characteristics, reactor behavior, and instrument interpretation.

K/A Category Point Totals: 2 3 3 3 3/3 4/3 Group Point Total: 18 / 6 Page 4 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.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 036 / Fuel Handling Accident / 8 X AA2.02 they apply to the Fuel Handling Incidents: 4.1 82 Occurrence of a fuel handling incident Ability to determine and interpret the following as they apply to the RCS Overcooling: Adherence A11 / RCS Overcooling-PTS / 4 X AA2.2 to appropriate procedures and operation within 3.4 83 the limitations in the facilitys license and amendments.

Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear 032 / Loss of Source Range NI / 7 X AA2.01 2.9 84 Instrumentation: Normal/abnormal power supply operation Ability to determine and interpret the following as 069 / Loss of Containment Integrity / 5 X AA2.01 they apply to the Loss of Containment Integrity: 4.3 85 Loss of containment integrity Ability to determine and interpret the following as they apply to an Inadequate Core Cooling: The 074 / Inadequate Core Cooling / 4 X EA2.07 4.1 57 difference between a LOCA and inadequate core cooling, from trends and indicators Knowledge of the reasons for the following responses as they apply to the Pressurizer Level 028 / Pressurizer Level Malfunction / 2 X AK3.05 3.7 58 Control Malfunction: Actions contained in EOP for PZR level malfunction Knowledge of the interrelations between the 005 / Inoperable/Stuck Control Rod / 1 X AK2.03 Inoperable/Stuck Control Rod and the following: 3.1 59 Metroscope Ability to operate and/or monitor the following as 036 / Fuel Handling Accident / 8 X AA1.02 they apply to the Fuel Handling Incidents: ARM 3.1 60 system Knowledge of the reasons for the following responses as they apply to the Accidental 060 / Accidental Gaseous Radwaste Release / 9 X AK3.02 3.3 61 Gaseous Radwaste Release: Isolation of the auxiliary building ventilation.

Knowledge of the operational implications of the following concepts as they apply to the Dropped 003 / Dropped Control Rod / 1 X AK1.04 3.1 62 Control Rod: Effects of power level and control position on flux Page 5 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.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#

Knowledge of the reasons for the following responses as they apply to the Loss of 051 / Loss of Condenser Vacuum / 4 X AK3.01 2.8 63 Condenser Vacuum: Loss of steam dump capability upon loss of condenser vacuum Conduct of Operations: Ability to evaluate plant performance and make operational judgments 037 / Steam Generator Tube Leak / 3 X 2.1.7 4.4 64 based on operating characteristics, reactor behavior, and instrument interpretations Knowledge of the operational implications of the 067 / Plant Fire on Site / 8 X AK1.02 following concepts as they apply to the Plant 3.1 65 Fire on Site: Fire fighting K/A Category Point Totals: 1 1 3 1 2/4 1/0 Group Point Total: 9/4 Page 6 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.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#

Emergency Procedures/Plan: Knowledge of 022 / Containment Cooling X 2.4.1 EOP entry conditions and immediate action 4.8 86 steps Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of 026 / Containment Spray X A2.07 3.9 87 containment spray pump suction when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding, or sump level below cutoff (interlock) limit Conduct of Operations: Ability to evaluate plant 061 / Auxiliary/Emergency performance and make operational judgments X 2.1.7 4.7 88 Feedwater based on operating characteristics, reactor behavior, and instrument interpretation Equipment Control: Knowledge of limiting 005 / Residual Heat Removal X 2.2.22 4.7 89 conditions for operations and safety limits Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and 006 / Emergency Core (b) based on those predictions, use procedures X A2.10 3.9 90 Cooling to correct, control, or mitigate the consequences of those malfunctions or operations: Low boron concentration in SIS Knowledge of the physical connections and/or 003 / Reactor Coolant Pump X K1.03 cause-effect relationships between the RCPS 3.3 1 and the following systems: RCP seal system Knowledge of the CVCS design feature(s) and/or interlock(s) which provide for the 004 / Chemical and Volume X K4.03 following: Protection of the ion exchangers 2.8 2 Control (high letdown temperature will isolate ion exchangers)

Knowledge of the operational implications of 004 / Chemical and Volume the following concepts as they apply to the X K5.04 2.8 3 Control CVCS: Reason for hydrogen cover gas in VCT (oxygen scavenge)

Page 7 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.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 005 / Residual Heat Removal X A4.02 the control room: Heat exchanger bypass flow 3.4 4 control 006 / Emergency Core Ability to manually operate and/or monitor in X A4.02 4.0 5 Cooling the control room: Valves Knowledge of the effect of a loss or 006 / Emergency Core X K6.03 malfunction on the following will have on the 3.6 6 Cooling ECCS: Safety Injection Pumps Knowledge of the effect that a loss or 007 / Pressurizer Relief /

X K3.01 malfunction of the PRTS will have on the 3.3 7 Quench Tank following: Containment Knowledge of CCWS design feature(s) and/or 008 / Component Cooling interlock(s) which provide for the following:

X K4.07 2.6 8 Water Operation of the CCW swing bus power supply and its associated breakers and controls Ability to predict and/or monitor changes in 010 / Pressurizer Pressure parameters (to prevent exceeding design X A1.07 3.7 9 Control limits) associated with operating the PZR PCS controls including: RCS pressure Knowledge of the effect of a loss or 012 / Reactor Protection X K6.06 malfunction of the following will have on the 2.7 10 RPS: Sensors and detectors Ability to monitor automatic operation of the 012 / Reactor Protection X A3.03 3.4 11 RPS, including: Power supply 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 A2.03 4.4 12 Features Actuation to correct, control, or mitigate the consequences of those malfunctions or operations: Rapid depressurization Ability to monitor automatic operation of the 022 / Containment Cooling X A3.01 CCS, including: Initiation of safeguards mode 4.1 13 of operation Conduct of Operations: Ability to evaluate plant performance and make operational judgments 022 / Containment Cooling X 2.1.7 4.4 14 based on operating characteristics, reactor behavior, and instrument interpretation Page 8 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.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 (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to 026 / Containment Spray X A2.02 4.2 15 correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic recirculation transfer Knowledge of the CSS design feature(s) and/or interlock(s) which provide for the 026 / Containment Spray X K4.07 3.8 16 following: Adequate level in the containment sump for suction (interlock)

Ability to manually operate and/or monitor in 039 / Main and Reheat Steam X A4.03 2.8 17 the control room: MFW pump turbines Ability to predict and/or monitor changes in parameters (to prevent exceeding design 059 / Main Feedwater X A1.07 limits) associated with operating the MFW 2.5 18 controls, including: Feed Pump speed, including normal control speed for ICS 061 / Auxiliary/Emergency Knowledge of the bus power supplies to the X K2.01 3.2 19 Feedwater following: AFW system MOVs Conduct of Operations: Knowledge of the 062 / AC Electrical X 2.1.28 purpose and function of major system 4.1 20 Distribution components and controls Knowledge of the physical connections and/or 062 / AC Electrical cause-effect relationships between the AC X K1.04 3.7 21 Distribution Electrical Distribution System and the following systems: Offsite power sources Knowledge of the physical connections and/or 063 / DC Electrical cause-effect relationships between the DC X K1.02 2.7 22 Distribution Electrical Distribution System and the following systems: AC electrical system 064 / Emergency Diesel Knowledge of the bus power supplies to the X K2.01 2.7 23 Generator following: Air compressor Knowledge of the effect that a loss or 064 / Emergency Diesel X K3.03 malfunction of the EDG system will have on 3.6 24 Generator the following: EDG (manual loads)

Page 9 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.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 operational implications of 073 / Process Radiation the following concepts as they apply to the X K5.03 2.9 25 Monitoring PRM system: Relationship between radiation intensity and exposure limits Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following:

076 / Service Water X K4.03 2.9 26 Automatic opening features associated with SWS isolation valves to CCW heat exchangers Equipment Control: Ability to determine 078 / Instrument Air X 2.2.37 operability and/or availability of safety related 3.6 27 equipment Ability to predict and/or monitor changes in parameters (to prevent exceeding design 103 / Containment X A1.01 limits) associated with operating the 3.7 28 containment controls including: Containment pressure, temperature, and humidity K/A Category Point Totals: 3 2 2 4 2 2 3 2/2 2 3 3/3 Group Point Total: 28 / 5 Page 10 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.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 Liquid Radwaste System; and (b) based on 068 / Liquid Radwaste X A2.02 those predictions, use procedures to correct, 2.8 91 control, or mitigate the consequences of those malfunctions or operations: Lack of tank recirculation prior to release 072 / Area Radiation Equipment Control: Ability to apply Technical X 2.2.40 4.7 92 Monitoring Specifications for a system Ability to (a) predict the impacts of the following malfunctions or operations on the 035 / Steam Generator X A2.05 SG; and (b) based on those predictions, use 3.4 93 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Unbalanced flow to the SGs 027 / Containment Iodine Knowledge of bus power supplies to the X K2.01 3.1 29 Removal following: Fans Ability to monitor automatic operation of the 055 / Condenser Air Removal X A3.03 CARS, including: Automatic diversion of 2.5 30 CARS exhaust Knowledge of the operational implication of the following concepts as they apply to the 086 / Fire Protection X K5.04 Fire Protection System: Hazards to 2.9 31 personnel as a result of fire type and methods of protection Ability to manually operate and/or monitor in 041 / Steam Dump/Turbine X A4.06 the control room: Atmospheric relief valve 2.9 32 Bypass Control controllers Knowledge of RPIS design feature(s) and/or 014 / Rod Position Indication X K4.03 interlock(s) which provide for the following: 3.2 33 Rod bottom lights 072 / Area Radiation Conduct of Operations: Knowledge of X 2.1.27 3.9 34 Monitoring system purpose and/or function Knowledge of the effect of a loss or 035 / Steam Generator X K6.01 malfunction of the following will have on the 3.2 35 SGS: MSIVs Page 11 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.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 ITM System; and (b) based on those 017 / Incore Temperature X A2.01 predictions, use procedures to correct, 3.1 36 Monitoring control, or mitigate the consequences of those malfunctions or operations:

Thermocouple open and short-circuits Knowledge of the physical connections and/or cause-effect relationships between 015 / Nuclear Instrumentation X K 1.08 2.6 37 the NIS and the following systems: RCS (pump start)

Knowledge of the effect that a loss or 045 / Main Turbine Generator X K3.01 malfunction of the MTG system will have on 2.9 38 the following: Remainder of the plant K/A Category Point Totals: 1 1 1 1 1 1 0 1/2 1 1 1 / 1 Group Point Total: 10 / 3 Page 12 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.doc

ES-401 Generic Knowledge and Abilities Outline - Tier 3 Form ES-401-3 Facility: SONGS 2 & 3 NRC Date of Exam: 10/18/2009 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, overtime limitations, etc.

Conduct 2.1.19 Ability to use plant computers to evaluate system or 3.9 66 of Operations component status 2.1.30 Ability to locate and operate components, including local 4.4 67 controls Subtotal 2 1 2.2.23 Ability to track Technical Specification limiting conditions 4.6 95 for operations

2. 2.2.7 Knowledge of the process for conducting special or 3.6 96 Equipment infrequent tests Control 2.2.22 Knowledge of limiting conditions for operations and safety 4.0 68 limits 2.2.13 Knowledge of tagging and clearance procedures 4.1 69 2.2.2 Ability to manipulate the console controls as required to 4.6 70 operate the facility between shutdown and designated power levels Subtotal 3 2 2.3.4 Knowledge of radiation exposure limits under normal or 3.7 97
3. emergency conditions Radiation 2.3.6 Ability to approve release permits 3.8 98 Control 2.3.7 Ability to comply with radiation work permit requirements 3.5 71 during normal or abnormal conditions 2.3.15 Knowledge of radiation monitoring systems, such as fixed 2.9 72 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

2.3.12 Knowledge of radiological safety principles pertaining to 3.2 73 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Subtotal 3 2 2.4.40 Knowledge of SRO responsibilities in emergency plan 4.5 99

4. implementation Emergency 2.4.44 Knowledge of emergency plan protective action 4.4 100 Procedures / recommendations Plan 2.4.3 Ability to identify post accident instrumentation 3.7 74 2.4.11 Knowledge of abnormal condition procedures 4.0 75 Subtotal 2 2 Tier 3 Point Total 10 7 Page 13 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.doc

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A Q #31 - Unable to develop a psychometrically sound question that 2/2 016 K5.01 discriminates at the RO license level. Randomly reselected 086 K5.04.

Q #42 - This specific K/A adequately covered by Question #54. Randomly 1/1 011 EA2.09 reselected 011 EA2.11.

Q #57 - Unable to develop a psychometrically sound question that 1/2 074 EA2.05 discriminates at the RO license level. Reselected 074 EA2.07.

Q #76 - Unable to develop a psychometrically sound question that 015/017 1/1 discriminates at the SRO license level. Randomly reselected 015/017 AA2.07 G 2.2.44.

Q #81 - Unable to develop an appropriate SRO level question that 1/1 011 G 2.4.3 discriminates at the SRO license level. Reselected 011 EA2.03.

Q #83 - Unable to develop a psychometrically sound question that 1/2 001 G 2.4.1 discriminates at the SRO license level. Automatic Rod Control has been disabled at SONGS. Randomly reselected A11 AA2.2.

Q #55 - Unable to develop a psychometrically sound question that is 1/1 077 AK2.03 considered important to safety. Randomly reselected 077 AK2.02.

Q #84 - Unable to develop a psychometrically sound question that 1/2 032 AA2.02 discriminates at the SRO license level. Reselected 032 AA2.01.

Q #85 - Unable to develop a psychometrically sound question that 1/2 068 AA2.07 discriminates at the SRO license level. Reselected 069 AA2.01.

Q #88 - Unable to develop a psychometrically sound question that 2/1 061 A2.07 discriminates at the SRO license level. Reselected 061 G 2.1.7.

Q #61 - Emergency Plan implementation is considered SRO level knowledge.

1/2 060 AK3.01 Randomly reselected 060 AK3.02.

Q #82 - Coverage of radioactive releases deemed adequate per Questions 1/2 059 AA2.04 #61, #91, and #98. Reselected 036 AA2.02 to address exam content of 10CFR 55.43(7).

Q #18 - Unable to develop a psychometrically sound question that 2/1 059 A2.12 discriminates at the RO license level. Reselected 059 A1.07 for skyscraper balance.

Q #03 - Unable to develop a psychometrically sound question that 2/1 004 K5.29 discriminates at the RO license level. Reselected 004 K5.04.

Q #24 - Unable to develop a psychometrically sound question that 2/1 064 K3.01 discriminates at the RO license level. No automatic loader information available to the operator. Reselected 064 K3.03.

Q #34 - This specific K/A already covered by Q #60. Reselected 072 G 2.1.27 2/2 072 K3.02 for skyscraper balance.

Q #70 - Assigned K/A G 2.2.2 as it is a better fit for the question and avoids 3/2 G 2.2.25 issues with Technical Specification Bases for Reactor Operators.

Q #39 - Substituted K/A G 2.1.31 as the Unit 3 Steam Generator replacement 1/1 EO2 G 2.2.3 will be underway and negate identified differences between Units.

Page 14 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.doc

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 EO6 EA1.2 Q #49 - Reselected E06 EK2.1 for skyscraper balance.

Q #01 - This specific K/A already covered by scenario malfunctions.

2/1 003 K1.12 Reselected 003 K1.03.

Q #06 - Multiple interpretations as to meaning of selected K/A. Assigned a 2/1 006 K6.05 more appropriate K/A to this new question. Selected 006 K6.03.

Q #15 - Unable to develop a psychometrically sound question that 2/1 026 A2.05 discriminates at the RO license level since there are no Chemical Injection Tanks associated with the Containment Spray System. Reselected 026 A2.02.

Q #40 - Unable to develop a psychometrically sound question that 1/1 008 AA1.05 discriminates at the RO license level. Reselected 008 AA1.08.

Q #52 - Unable to develop a psychometrically sound question that 1/1 058 AA1.01 discriminates at the RO license level. Reselected 058 AA1.03.

Q #65 - Unable to develop a psychometrically sound question that discriminates at the RO license level. Fire Computer is frequently OOS in the 1/2 067 AA1.09 Control Room because this function is performed by the Site Fire Brigade.

Reselected 067 AK1.02.

Q #62 - Unable to develop a psychometrically sound question that 1/2 003 AK1.07 discriminates at the RO license level. Reselected 003 AK1.04.

2/1 005 A4.01 Q #04 - This specific K/A already covered by JPM S-4. Reselected 005 A4.02.

Q #15 - Unable to develop a psychometrically sound question that 2/1 010 G2.4.9 discriminates at the RO license. Reselected 012 K6.06 for skyscraper balance.

3/4 G2.4.18 Q #75 - Assigned a more appropriate K/A to this question. Selected G2.4.11.

Q #14 - Assigned a more appropriate K/A to this new question. Selected 2/1 022 K3.02 G2.1.7.

Q #45 - Assigned a more appropriate K/A to this Cycle 16 Plant Modification.

1/1 022 G2.4.2 Selected G2.1.19.

Q #77 - Replaced question per Chief Examiner request. Reselected 007 1/1 065 AA2.03 EA2.04.

Q #92 - Assigned a more appropriate K/A to this new question per Chief 2/2 072 G2.2.12 Examiner request. Selected G2.2.40.

Q #93 - Replaced question per Chief Examiner request. Reselected 035 2/2 086 G2.4.31 A2.05.

Page 15 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev h.doc

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 and 3 Scenario No.: 2 Op Test No.: October 2010 NRC Examiners: Operators:

Initial Conditions:

  • Train A Component Cooling Water Pump (P-025) in service.
  • Charging Pump (P-192) running with (P-191) aligned to 480 Volt Bus 2B04.
  • Channel X Pressurizer Pressure and Level in service.

Turnover: Maintain steady-state conditions following return of Main Feedwater Pump to service.

Critical Tasks:

  • Restore Component Cooling Water Flow due to Loss of CCW Pump.

Event No. Malf. No. Event Type* Event Description 1 RC17B I (RO, BOP, CRS) Pressurizer Pressure Wide Range Transmitter (PT-0102-2) Fails

+15 min TS (CRS) Low.

2 CV22C C (RO, CRS) Charging Pump (P-192) Overcurrent Trip.

+25 min TS (CRS) 3 CC06B C (BOP, CRS) Train A Component Cooling Water Pump (P-025) Trip.

+30 min 4 OBE with C (RO, CRS) Seismic Event with Reactor Coolant Pump (P-001) Seized Shaft

+32 min RC07A (60 second time delay).

5 RP15 I (RO) Reactor Fails to Automatically Trip.

+32 min 6 MS05A M (RO, BOP, CRS) Steam Generator (E-088) Main Steam Leak Upstream of Main

+35 min Steam Isolation Valve.

7 TU07 I (BOP) Turbine Trip Failure on Reactor Trip.

+35 min 8 RC03 M (RO, BOP, CRS) Reactor Coolant System Leakage at 500 GPM.

+35 min RC19 Failed Fuel due to RCP Seized Shaft Exceeding DNBR & LPD.

9 RP01M C (RO) Containment Spray Pump (P-012) Auto Start Failure.

+40 min

  • (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (TS)Technical Specifications

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 and 3 Scenario No.: 3 Op Test No.: October 2010 NRC Examiners: Operators:

Initial Conditions:

  • Train A Component Cooling Water Pump (P-025) in service.
  • Channel Y Pressurizer Pressure and Level in service.

Turnover: Secure Auxiliary Feedwater System and Raise Power to 18%.

Critical Tasks:

  • Initiate Emergency Boration for Two (2) Stuck Control Element Assemblies.

Event No. Malf. No. Event Type* Event Description 1 N (BOP) Place Auxiliary Feedwater System in Standby.

+15 min 2 R (RO) Power increase to 18% power.

+30 min N (BOP, CRS) 3 CH03A TS (CRS), I (CRS, Containment Pressure Transmitter (PT-0351-1) Fails High.

+40 min RO) 4 ED07B C (RO, BOP, CRS) Loss of Vital AC Instrument Bus (Y-02).

+70 min TS (CRS) 5 RP23B C, M (RO, BOP, Train A & B Inadvertent Containment Isolation Actuation Signal

+72 min CRS) (CIAS) Actuation.

6 RD0102 C, M (RO) Two (2) Stuck CEAs (#1 & #2) upon Reactor Trip. Emergency

+72 min RD0202 Boration Required.

7 RP01O C (BOP) Auxiliary Feedwater Pumps (P-141 & P-504) Fail to Start on

+78 min RP01P Emergency Feedwater Actuation Signal.

8 FW25 C (BOP) Turbine Driven Auxiliary Feedwater Pumps (P-140) Overspeed

+78 min Trip on Emergency Feedwater Actuation Signal.

  • (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (TS)Technical Specifications D1 Scenario 3.docx

Appendix D Scenario Outline Form ES-D-1 Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 and 3 Scenario No.: 4 Op Test No.: October 2010 NRC Examiners: Operators:

Initial Conditions:

  • Train A Component Cooling Water Pump (P-025) in service.
  • Charging Pump (P-191) aligned to 480 Volt Bus 2B04.
  • Channel X Pressurizer Pressure and Level in service.

Turnover: Transfer Reactor Coolant Pump (RCP) 6900 V Bus 2A01 from UAT to RAT.

Critical Tasks:

Event No. Malf. No. Event Type* Event Description 1 N (BOP) Transfer Reactor Coolant Pump 6900 Volt Bus 2A01 from Unit

+10 min Auxiliary Transformer to Reserve Auxiliary Transformer.

2 RC16A I (RO, CRS) Pressurizer Level Control Channel X (LT-0110-1) Fails High.

+20 min TS (CRS) 3 CS05B TS (CRS) Refueling Water Storage Tank Level Transmitter (LT-0305-2) Fails

+30 min Low.

4 SG01A C (RO, CRS) Steam Generator (E-088) Tube Leak Greater Than 150 GPD.

+35 min 5 R (RO) Rapid Power Reduction for Steam Generator (E-088) Tube Leak.

+50 min N (BOP, CRS) 6 SG01A M (RO, BOP, CRS) Steam Generator (E-088) Tube Rupture at 300 GPM (5 minute

+55 min ramp).

7 RP02A I (RO) All Reactor Trip Pushbuttons Disabled / Anticipated Transient

+55 min RP02B without Scram.

8 2A03 LP C (BOP) Non-1E 4160 Volt Bus 2A03 Fails to Auto Transfer on Reactor Trip.

+60 min

  • (N)ormal (R)eactivity (I)nstrument (C)omponent (M)ajor (TS)Technical Specifications D1 Scenario 4.docx
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