ML103200716

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SONGS-2010-10-DRAFT Outlines
ML103200716
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: ML103200716 (28)
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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 1 0 2 3 Tier Totals 4 3 3 5 3 3 3 3 3 4 4 38 3 5 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 g.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 and interpret the following as 065 / Loss of Instrument Air / 8 X AA2.03 they apply to the Loss of Instrument Air: 2.9 77 Location and isolation of leaks 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 g.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 g.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 g.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 g.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 g.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 g.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 g.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 g.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 g.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: Knowledge of X 2.2.12 4.1 92 Monitoring surveillance procedures Emergency Procedures/Plan: Knowledge of 086 / Fire Protection X 2.4.31 annunciator alarms, indications, or response 4.1 93 procedures 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 g.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 1/1 1 1 1 / 2 Group Point Total: 10 / 3 Page 12 of 15 SONGS NRC 2010 ES-401-2 & 3 & 4 Written Outline Rev g.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 g.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 g.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.

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SONGS 2 & 3 Date of Examination: 10/18/10 Examination Level: Reactor Operator Operating Test Number: NRC Administrative Topic Type Code* Describe Activity to be Performed (see Note) 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9).

Conduct of Operations M, R JPM: Determine Boration required to Cooldown to MODE 5. (J169A) 2.1.19 Ability to use plant computers to evaluate system or component status (3.9).

Conduct of Operations N, S JPM: Remove a Nuisance Radiation Monitor From Scan on DAS. (New) 2.2.12 Knowledge of surveillance procedures (3.7).

Equipment Control N, S JPM: Perform QSPDS Administrative Channel Checks. (New) 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions (3.5).

Radiation Control M, R JPM: Determine Stay Times / Respond to changing radiological conditions. (J216A)

Emergency Plan -

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; for 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected) 1 of 2 SONGS NRC 2010 ES-301-1 RO Admin JPM Outline Rev e.doc

Administrative Topics Outline Task Summary RA1 The applicant will determine the target Boron Concentration required to cool the plant down to MODE 5 per SO23-5-1.5, Plant Shutdown from Hot Standby to Cold Shutdown. The critical steps include determination of the proper value of boron concentration and the required amount to borate using Operations Boration / Dilution Charts. This is a modified bank JPM.

RA2 The applicant will remove a Radiation Monitor causing nuisance alarms from Scan on the Data Acquisition System per SO23-3-2.36, Radiation Monitor Data Acquisition System, Section 6.4, Bypassing and Restoring RTP Chassis Monitor Alarms. The critical steps include proper monitor selection and removing the Radiation Monitor alarm from Scan. This is a new JPM.

RA3 The applicant will perform the administrative CHANNEL CHECKS for the Qualified Safety Parameter Display System per SO23-3-2.35, Qualified Safety Parameter Display System, Attachment 3, QSPDS Administrative Channel Checks. The critical steps include collecting data and determining whether each parameter is within tolerance per the Acceptance Criteria. This is a new JPM.

RA4 The applicant will review a Radiation Entry Permit, select a Survey Map, and determine stay times while hanging a Clearance per SO123-VII-20.9, Radiological Surveys. The critical steps include selecting the appropriate Survey Map and calculating stay time based on the allowable External Dose Equivalent.

This is a modified bank JPM.

2 of 2 SONGS NRC 2010 ES-301-1 RO Admin JPM Outline Rev e.doc

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SONGS 2 & 3 Date of Examination: 10/18/10 Examination Level: Senior Reactor Operator Operating Test Number: NRC Administrative Topic Type Code* Describe Activity to be Performed (see Note) 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation (4.4).

Conduct of Operations M, R JPM: Perform DNBR Margin Limit Verification.

(J271A) 2.1.25 Ability to interpret reference materials such as graphs, curves, tables, etc. (4.2).

Conduct of Operations M, R JPM: Perform Monthly Surveillance to Update Power Maneuvering Guidelines. (J255A) 2.2.37 Ability to determine operability and/or availability of safety related equipment (4.6).

Equipment Control N, S JPM: Evaluate Reactor Trip Breaker Operability.

(New) 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors andl alarms, portable survey instruments, personnel Radiation Control N, R monitoring equipment, etc. (3.1)

JPM: Determine Change in Steam Generator Tube Leakage. (New) 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required Emergency Plan M, S (4.4).

JPM: Perform Actions for an Aircraft Attack Security Event. (J281A)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Page 1 of 2 SONGS NRC 2010 ES-301-1 SRO Admin JPM Outline Rev e.doc

Administrative Topics Outline Task Summary

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; for 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

SA1 The applicant will perform a Departure from Nucleate Boiling Ratio Margin Limit verification per SO23-3-3.06, COLSS Out of Service Surveillance. The critical steps include properly identifying the margins and determining if the margin Acceptance Criteria is met. This is a modified bank JPM.

SA2 The applicant will perform the monthly surveillance to update the Power Maneuvering Guidelines per SO23-5-1.7, Power Operations. The critical steps include correctly determining each boration requirement within specified tolerances and correctly updating the Operating Thumbrules. This is a modified bank JPM.

SA3 The applicant will evaluate the operability of a Reactor Trip Breaker and perform actions required based on the evaluation per SO23-3-3.5, CEA / Reactor Trip Circuit Breaker OPERABILITY Testing, Attachment 3, Reactor Trip Circuit Breaker Monthly Test - MODES 1 and 2. The critical steps include properly identifying OPERABILITY and determining affected Technical Specifications when the surveillance fails to meet Acceptance Criteria. This is a new JPM.

SA4 The applicant will determine the change in leakrate during a Steam Generator Tube Leak based on the change in ci/sec as read on RE-7870, Condenser Air Ejector Wide Range Gas Monitor. The critical steps include calculating the change in leakrate based on RE-7870, per SO23-13-14, Reactor Coolant Leak, Attachment 1, RE-7870 Steam Generator Radiation and Leakage Readings, and determining the required action per SO23-13-14, Step 4s. This is a new JPM.

SA5 The applicant will perform an NRC notification and other actions for an aircraft attack per SO23-13-25, Operator Actions During Security Events, Attachment 5, Aircraft Attack Threat. The critical steps include notifying the NRC and initiating a train of Toxic Gas Isolation Signal (TGIS). This is a modified bank JPM.

Page 2 of 2 SONGS NRC 2010 ES-301-1 SRO Admin JPM Outline Rev e.doc

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 Facility: SONGS Units 2 and 3 Date of Examination: 10/18/10 Exam Level: RO SRO(I) SRO (U) Operating Test No.: NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-1 001 - Control Rod Drive System (J080FS) A, M, S 1 Perform an Individual Control Rod Exercise S-2 013 - Engineered Safety Feature Actuation System (J069S) D, EN, S 2 Reset a SIAS and CCAS S-3 010 - Pressurizer Pressure Control System (J254FS) A, D, S 3 Respond to an Open Pressurizer Spray Valve S-4 005 - Residual Heat Removal System (J152FS) A, D, L, S 4P Perform Actions for Loss of Shutdown Cooling S-5 059 - Main Feedwater System (J034S) (RO Only) M, S 4S Transfer from Main Feedwater to Auxiliary Feedwater S-6 064 - Emergency Diesel Generators (J286S) D, S 6 Parallel Isochronous EDG with Reserve Auxiliary Transformer S-7 016 - Non-Nuclear Instrumentation System (New) A, N, S 7 Respond to Loss of Turbine DCS Control Panels S-8 029 - Containment Purge System (New) A, EN, N, S 8 Respond to a Refueling Accident in Containment In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P-1 033 - Spent Fuel Pool Cooling System (New) E, N, R 8 Align Spent Fuel Pool Makeup from the RWST P-2 039 - Main and Reheat Steam Systems (J022) D 4S Restore Atmospheric Dump Valve to Remote Operation P-3 004 - Chemical and Volume Control System (J064) D, E 2 Locally Close a Charging Pump Breaker 1 of 3 SONGS NRC 2010 ES-301-2 RO & SRO JPM Outline Rev e.doc

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator NRC JPM Examination Summary Description S-1 The applicant will exercise an individual Control Element Assembly (CEA) after I&C Maintenance per SO23-3-2.19, Control Element Drive Mechanism Control System. The alternate path occurs when two (2) CEAs drop into the Core requiring the actions of SO23-13-13, Misaligned or Immovable Control Element Assembly. This is a time critical, modified bank JPM under the Control Rod Drive System - Reactivity Control Safety Function. This is a PRA significant action.

S-2 The applicant will perform a reset of the Safety Injection Actuation Signal (SIAS) and Containment Cooling Actuation Signal (CCAS) per SO23-3-2.22, Engineered Safety Features Actuation System Operation, Attachment 5, SIAS / CCAS and CIAS Reset. This is a bank JPM under the Engineered Safety Features Actuation System - Reactor Coolant System Inventory Control Safety Function.

S-3 The applicant will respond to an open Pressurizer Spray Valve per SO23-13-27, Pressurizer Pressure and Level Malfunction. The alternate path includes tripping the Reactor and associated Reactor Coolant Pumps for the affected Pressurizer Spray Valve, when it is determined that the Spray Valve will not close. This is a bank JPM under the Pressurizer Pressure and Level Control System - Reactor Pressure Control Safety Function. This is a PRA significant action.

S-4 The applicant will perform the actions for a Loss of Shutdown Cooling (SDC) per SO23-13-15, Loss of Shutdown Cooling, during a Loss of Offsite Power while in a Reduced Inventory Condition. The alternate path occurs when the SDC Pump starts to cavitate and actions must be taken to refill the Reactor Coolant System using High Pressure Safety Injection. This is a bank JPM under the Residual Heat Removal System -

Heat Removal from Reactor Core Safety Function. This is a PRA significant action.

2 of 3 SONGS NRC 2010 ES-301-2 RO & SRO JPM Outline Rev e.doc

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 S-5 The applicant will shift from the Main Feedwater System to the Auxiliary Feedwater System during a plant shutdown per SO23-9-6, Feedwater Control System Operation, Attachment 6, Feedwater Control System Operation - Unit Shutdown. This is a modified bank JPM under the Main Feedwater System - Secondary System Heat Removal from the Reactor Core Safety Function.

S-6 The applicant will synchronize the Emergency Diesel Generator operating in the Isochronous Mode with the Reserve Auxiliary Transformer per SO23-02-13, Diesel Generator Operation, Attachment 2, Section 2.6, Paralleling a Diesel Supplied Isochronous Bus to the RAT, and Section 2.8, Unloading the Diesel Generator. This is a bank JPM under the Emergency Diesel Generator System - Electrical Safety Function.

S-7 The applicant will be directed to reduce Turbine load per SO23-5-1.7, Power Operations, Section 6.3, Turbine Load Change Using Setpoint Adjustment. The alternate path occurs when power to both Turbine DCS Control Panels and the Ovation Keyboard is lost requiring action to place an alternate control screen in service and stop the Turbine load change. This is a new JPM under the Non-Nuclear Instrumentation System -

Instrumentation Safety Function.

S-8 The applicant will respond to a Fuel Handling Accident in Containment during MODE 6 operations per SO23-13-20, Fuel Handling Accidents. The alternate path occurs when the Containment Purge System fails to isolate and must be manually isolated per SO23-3-2.22, Engineered Safety Features Actuation System Operation, Attachment 20, CPIS Actuation Verification. This is a new JPM under the Containment Purge System -

Plant Service System Safety Function.

P-1 The applicant will respond to a loss of Spent Fuel Pool inventory per SO23-13-23, Loss of Spent Fuel Pool Cooling, by locally aligning makeup from the Refueling Water Storage Tank per SO23-3-2.11.1, Spent Fuel Pool Level Change and Purification Crosstie Operations, Attachment 3, SFP Makeup Using the RWST and SFP Pump P-009. This is a new JPM under the Spent Fuel Pool Cooling System - Plant Service System Safety Function.

P-2 The applicant will restore remote operation of a Unit 2 Atmospheric Dump Valve per SO23-3-2.18.1, Atmospheric Dump Valve Operation, Attachment 4, Local Manual Operation of HV-8419 Atmospheric Dump Valve, Section 2.2, Restoration from HV-8419 Local Manual Operation or Attachment 5, Local Manual Operation of HV-8421 Atmospheric Dump Valve, Section 2.2, Restoration from HV-8421 Local Manual Operation. This is a bank JPM under the Main and Reheat Steam System - Secondary System Heat Removal from Reactor Core Safety Function.

P-3 The applicant will locally close a Charging Pump Breaker per SO23-13-2, Shutdown From Outside the Control Room, Attachment 21, Circuit Breaker Abnormal Operation.

This is a bank JPM under the Chemical and Volume Control System - Reactor Coolant Inventory Control Safety Function. This is a PRA significant action.

3 of 3 SONGS NRC 2010 ES-301-2 RO & SRO JPM Outline Rev e.doc

ES-301 Transient and Event Checklist Form ES-301-5 Facility: SONGS 2 and 3 Date of Exam: 10/18/10 Operating Test Number: 1 E

SCENARIOS A V P E SONGS #1 SONGS #2 SONGS #4 P N L T MINIMUM(*)

T I CREW CREW CREW CREW O C T POSITION POSITION POSITION POSITION T A Y A S A B S A B S A B S A B N P R T O R T O R T O R T O L R I U T E O C P O C P O C P O C P RX - - - - - - - - - 0 1 1 0 NOR 4 - - - - - - - - 1 1 1 1 SROU-1 I/C 1,2,3, - - 1,2,3, - - - - -

9 4 4 2 5 4,5 MAJ 6 - - 6,8 - - - - - 3 2 2 1 TS 1,5 - - 1,2 - - - - - 4 0 2 2 RX - - - - - - - - - 0 1 1 0 NOR 4 - - - - - - - 1,5 3 1 1 1 SROI-1 I/C 1,2,3, - - - 1,2,4, - - - 8 10 4 4 2 5 5,9 MAJ 6 - - - 6,8 - - - 6 4 2 2 1 TS 1,5 - - - - - - - - 2 0 2 2 RX - 4 - - - - - - - 1 1 1 0 NOR - - - - - - 5 - - 1 1 1 1 SROI-2 I/C - 2,5 - 1,2,3, - - 2,3,4 - -

10 4 4 2 4,5 MAJ - 6 - 6,8 - - 6 - - 4 2 2 1 TS - - - 1,2 - - 2,3 - - 4 0 2 2 RX - - - - - - - - - 0 1 1 0 NOR 4 - - - - - - - 1,5 3 1 1 1 SROI-3 I/C 1,2,3, - - - 1,2,4, - - - 8 10 4 4 2 5 5,9 MAJ 6 - - - 6,8 - - - 6 4 2 2 1 TS 1,5 - - - - - - - - 2 0 2 2 RX - 4 - - - - - - - 1 1 1 0 NOR - - - - - - 5 - - 1 1 1 1 SROI-4 I/C - 2,5 - 1,2,3, - - 2,3,4 - -

10 4 4 2 4,5 MAJ - 6 - 6,8 - - 6 - - 4 2 2 1 TS - - - 1,2 - - 2,3 - - 4 0 2 2 RX - 4 - - - - - - - 1 1 1 0 NOR - - - - - - - - - 0 1 1 1 RO-1 I/C - 2,5 - - - 1,3,7 - - - 5 4 4 2 MAJ - 6 - - - 6,8 - - - 3 2 2 1 TS - - - - - - - - - 0 0 2 2 RX - - - - - - - 5 - 1 1 1 0 NOR - - 4 - - - - - - 1 1 1 1 RO-2 I/C - - 1,8,9 - - 1,3,7 - 2,4,7 - 9 4 4 2 MAJ - - 6 - - 6,8 - 6 - 4 2 2 1 TS - - - - - - - - - 0 0 2 2 Page 1 of 2 SONGS NRC 2010 ES-301-5 Transient and Event Checklist Rev e.doc

ES-301 Transient and Event Checklist Form ES-301-5 E

SCENARIOS A V P E SONGS #1 SONGS #2 SONGS #4 P N L T MINIMUM(*)

T I CREW CREW CREW CREW O C T POSITION POSITION POSITION POSITION T A Y A S A B S A B S A B S A B N P R T O R T O R T O R T O L R I U T E O C P O C P O C P O C P RX - - - - - - - 5 - 1 1 1 0 NOR - - 4 - - - - - - 1 1 1 1 RO-3 I/C - - 1,8,9 - - 1,3,7 - 2,4,7 - 9 4 4 2 MAJ - - 6 - - 6,8 - 6 - 4 2 2 1 TS - - - - - - - - - 0 0 2 2 RX - 4 - - - - - - - 1 1 1 0 NOR - - - - - - - - - 0 1 1 1 RO-4 I/C - 2,5 - - - 1,3,7 - - - 5 4 4 2 MAJ - 6 - - - 6,8 - - - 3 2 2 1 TS - - - - - - - - - 0 0 2 2 RX - - - - - - - - - 0 1 1 0 NOR - - 4 - - - - - - 1 1 1 1 RO-5 I/C - - 1,8,9 - 1,2,4, - - - -

8 4 4 2 5,9 MAJ - - 6 - 6,8 - - - - 3 2 2 1 TS - - - - - - - - - 0 0 2 2 RX - - - - - - - - - 0 1 1 0 NOR - - 4 - - - - - - 1 1 1 1 RO-6 I/C - - 1,8,9 - 1,2,4, - - - -

8 4 4 2 5,9 MAJ - - 6 - 6,8 - - - - 3 2 2 1 TS - - - - - - - - - 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.
2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

Page 2 of 2 SONGS NRC 2010 ES-301-5 Transient and Event Checklist Rev e.doc

Appendix D Operator Action Form ES-D-1 Operating Test : NRC Scenario # 1 Event # 6, 7, 8, & 9 Page 1 of 1 Event

Description:

Steam Line Break Inside Containment / Loss of Offsite Power / Loss of SDG&E Switchyard / Train B EDG Breaker Failure / Main Steam Isolation Signal Actuation Failure Time Position Applicants Actions or Behavior Facility: SONGS 2 and 3 Scenario No.: 1 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: Maintain steady-state power level.

Critical Tasks:

  • Stabilize Temperature Following Loss of Heat Removal from Faulted Steam Generator.

Event No. Malf. No. Event Type* Event Description 1 SG03G I (BOP, CRS) Steam Generator (E-089) Pressure Transmitter (PT-1013-3) Fails

+10 min TS (CRS) Low.

2 RC15A I (RO, CRS) Pressurizer Pressure Control Channel X (PT-0100X) Fails High.

+20 min 3 CW05A Circulating Water Pump (P-115) Overcurrent Trip.

+25 min 4 R (RO) Rapid Power Reduction to 85% due to Loss of Circulating Water

+50 min N (BOP, CRS) Pump (P-115) per Direction of Shift Manager.

5 CV17B C (RO, CRS) Boric Acid Makeup Pump (P-175) Trips During Boration.

+55 min TS (CRS) 6 MS03B M (RO, BOP, CRS) Steam Generator (E-089) Main Steam Line Break Inside

+60 min Containment.

7 PG24 Loss of Offsite Power (30 second time delay) Post Trip.

+60 min PG57 Loss of SDG&E Switchyard Post Trip (60 second time delay).

8 EG16B C (BOP) Train B Emergency Diesel Generator (2G003) Breaker Fails to

+60 min Automatically Close.

9 MSIS LP I (BOP) Main Steam Isolation Signal Fails to Automatically Actuate.

+65 min

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

Appendix D Operator Action Form ES-D-1 Operating Test : NRC Scenario # 2 Event # 6, 7, 8, & 9 Page 1 of 1 Event

Description:

Steam Line Break Outside Containment / Reactor Coolant System Leak / Fuel Failure / Turbine Trip Failure / Containment Spray Pump Start Failure Time Position Applicants Actions or Behavior 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 Operator Action Form ES-D-1 Operating Test : NRC Scenario # 3 Event # 6&7 Page 1 of 1 Event

Description:

Two Stuck Control Element Assemblies / Auxiliary Feedwater Pump EFAS Start Failures Time Position Applicants Actions or Behavior 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) Containment Pressure Transmitter (PT-0351-1) Fails High.

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

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

+72 min (CIAS) Actuation.

6 RD0102 C (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.

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

Appendix D Operator Action Form ES-D-1 Operating Test : NRC Scenario # 4 Event # 6, 7, & 8 Page 1 of 1 Event

Description:

Steam Generator Tube Rupture / Anticipated Transient without Scram / Non-1E Bus Failure Time Position Applicants Actions or Behavior 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
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