ML13123A307

SO-2010-10-DRAFT Outlines

ML13123A307
Person / Time
Site:	San Onofre
Issue date:	11/01/2012
From:	Apger G Operations Branch IV
To:	Southern California Edison Co
laura hurley
References
50-361/10-010, 50-362/10-010
Download: ML13123A307 (42)

Text

Administrative Topics Outline Facility: SONGS Units 2 and 3 Date of Examination: 10/12/12 Examination Level RO 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 Conduct of Operations graphs, curves, tables, etc. (3.9)

M, R (A1)

JPM: Determine Time to Boil (J213A).

2.1.19 Ability to use plant computers to evaluate Conduct of Operations system or component status (3.9).

M, R (A2)

JPM: Calculate Azimuthal Power Tilt (J250A).

2.2.12 Knowledge of surveillance procedures. (3.7)

Equipment Control N, R (A3) JPM: Perform a Manual Water Inventory Balance (New).

Radiation Control - -

2.4.39 Knowledge of RO responsibilities in Emergency Plan emergency plan implementation. (3.9)

(A4) M, S JPM: Perform PA/Siren Coordination (J157A).

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)

SONGS NRC 2012 ES-301-1 RO Admin JPM Outline Rev a

Administrative Topics Outline Task Summary A1 The applicant will use data provided to perform a Time to Boil calculation using SO23-5-1.8.1, Shutdown Nuclear Safety. This is a modified bank JPM.

A2 The applicant will use provided data from the Core Protection Calculator System to calculate Azimuthal Power Tilt in the core per SO23-3-3.6, COLSS Out of Service Surveillance. This is a modified bank JPM.

A3 The applicant will use provided data to manually calculate a water inventory balance per SO23-3-3.37, Reactor Coolant System Water Inventory Balance. This is a new JPM.

A4 The applicant will perform a PA/Siren coordination per SO23-VIII-30, Units 2/3 Operations Leader Duties. This JPM will be conducted in the simulator. This is a modified bank JPM.

SONGS NRC 2012 ES-301-1 RO Admin JPM Outline Rev a

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SONGS Units 2 and 3 Date of Examination: 10/12/12 Examination Level SRO 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. (4.2)

Conduct of Operations M, R (A5)

JPM: Determine Time to Boil and Containment Closure Requirements (J213A).

2.1.19 Ability to use plant computers to evaluate system or component status (3.8).

Conduct of Operations M, R (A6)

JPM: Calculate Azimuthal Power Tilt and Evaluate Technical Specifications (J250A).

2.2.40 Ability to apply Technical Specification for a system (4.7).

Equipment Control N, R (A7)

JPM: Determine Technical Specification Applicability (New).

2.3.11 Ability to control radiation releases (4.3).

Radiation Control N, R (A8) JPM: Perform Process Flow Estimation for Waste Gas Decay Tank Release (New).

2.4.41 Knowledge of the emergency action level Emergency Plan thresholds and classifications (4.6).

M, R (A9)

JPM: Classify an Emergency Plan Event (J274A).

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)

Page 1 of 2 SONGS NRC 2012 ES-301-1 SRO Admin JPM Outline Rev aa

Administrative Topics Outline Task Summary A5 The applicant will use data provided to perform a Time to Boil calculation using SO23-5-1.8.1, Shutdown Nuclear Safety, and determine containment closure requirements based on the time to boil calculation. This is a modified bank JPM.

A6 The applicant will use provided data from the Core Protection Calculator System to calculate Azimuthal Power Tilt in the core per SO23-3-3.6, COLSS Out of Service Surveillance, and evaluate potential Technical Specification Actions based on the Azimuthal Power Tilt calculation. This is a modified bank JPM.

A7 The applicant will determine applicable Technical Specification Conditions and Actions based on a provided timeline of events. This is a new JPM.

A8 The applicant will calculate an estimated Waste Gas Decay Tank flowrate with an inoperable flow detector per SO23-8-15, Radwaste Gas Discharge. This is a new JPM.

A9 The applicant will classify an emergency plan event per SO23-VIII-1, Recognition and Classification of Emergencies, and make protective action recommendations per SO23-VIII-10.3, Protective Action Recommendations. This is a modified bank JPM.

Page 2 of 2 SONGS NRC 2012 ES-301-1 SRO Admin JPM Outline Rev aa

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 Facility: SONGS Units 2 and 3 Date of Examination: 10/12/12 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-1 004 - Chemical and Volume Control System (J275S) D, S 1 Perform 50 gallon dilution to the RCS S-2 011 - Pressurizer Level Control System (New) N, S 2 Transfer in-service letdown flow controllers S-3 006 - Emergency Core Cooling System (New) A, EN, L, N, S 3 Transfer Charging Pump Suction Post-SIAS S-4 045 - Main Turbine Generator System (New) A, N, S 4S Synch the Main Turbine to the grid and apply block load S-5 022 - Containment Cooling System (New) A, EN, N, S 5 Perform Containment Cooling Actuation System Relay Testing S-6 062 - AC Electrical Distribution System (J007) A, M, S 6 Transfer 6.9kV bus 2A01 from UAT to RAT S-7 073 - Process Radiation Monitoring System (J290) D, S 7 Change Radiation Monitor setpoints during small S/G tube leak S-8 071 - Align and Discharge a Waste Gas Decay Tank A, D, S 9 (J231FS) (RO only)

In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P-1 039 - Main and Reheat Steam System (J038) D, E 4S Manually open an Atmospheric Dump Valve P-2 064 - Emergency Diesel Generators (J016) D, E 6 Locally start Emergency Diesel Generator P-3 001 - Control Rod Drive System (J017) D, R 1 Remove MG Set # 1 from service 1 of 3 SONGS NRC 2012 ES-301-2 RO & SRO JPM Outline Rev aa

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 perform a 50 gallon dilution to the RCS per SO23-3-2.2, Makeup Operations. This is a bank JPM under the Chemical Volume and Control System -

Reactivity Control Safety Function.

S-2 The applicant will place the standby Letdown Flow Control Valve controller in service and remove the in-service Letdown Flow Control Valve from service per SO23-3-2.1, CVCS Operations. This is a new JPM under the Chemical Volume and Control System -

Reactor Coolant System Inventory Control Safety Function.

S-3 The applicant will perform FS-24, Transfer Charging Pump Suction, per SO23-12-11, EOI Supporting Attachments. The alternate path occurs when a valve is found to be out of its required position. This is a new JPM under the Emergency Core Cooling System -

Reactor Pressure Control Safety Function.

S-4 The applicant will raise Main Generator load per SO23-5-1.7, Power Operations. The alternate path occurs when high Turbine vibrations require the Reactor to be immediately tripped. This is a new JPM under the Main Turbine Generator System - Secondary System Heat Removal From Reactor Core Safety Function.

S-5 The applicant will perform Containment Cooling Actuation Signal K-Relay testing per SO23-3-3.43.38, ESF Subgroup Relays K-306A and K-306B Semiannual Test. The alternate path occurs when the expected test response is not obtained. This is a new JPM under the Containment Cooling System - Containment Integrity Safety Function.

S-6 The applicant will transfer 6.9kV bus 2A01 from the Unit Auxiliary Transformer to the Reserve Auxiliary Transformer per SO23-6-1, Transferring 6.9kv Buses, in preparation for 2 of 3 SONGS NRC 2012 ES-301-2 RO & SRO JPM Outline Rev aa

ES-301 Control Room / In-Plant Systems Outline Form ES-301-2 breaker maintenance. The alternate path occurs following the transfer when the supply breaker to bus 2A01 trips on overcurrent. The Reactor will fail to automatically trip on RCS Low Flow and the applicant will have to manually trip the Reactor. This is a modified JPM under the AC Electrical Distribution System - Electrical Safety Function.

S-7 The applicant will reset RE-7870, Condenser Air Ejector Wide Range Gas Monitor, Hi and HI-HI setpoints during a small SGTR per SO23-3-2.36, Radiation Monitoring Data Acquisition System. This is a bank JPM under the Process Radiation Monitoring System

- Instrumentation Safety Function.

S-8 The applicant will line up and discharge a Waste Gas Decay Tank per SO23-8-15, Radwaste Gas Discharge. The alternate path occurs when radiation monitors respond abnormally after the discharge is commenced. This is a bank JPM under the Waste Gas Disposal System - Radioactivity Release Safety Function.

P-1 The applicant will locally open an Atmospheric Dump Valve to establish RCS Heat Removal per SO23-13-2, Shutdown From Outside the Control Room. This is a bank JPM under the Main and Reheat Steam System - Secondary System Heat Removal From Reactor Core Safety Function.

P-2 The applicant will locally start an Emergency Diesel Generator per SO23-13-2, Shutdown from Outside the Control Room. This is a bank JPM under the Emergency Diesel Generators System - Electrical Safety Function.

P-3 The applicant will remove Control Rod Drive System Motor Generator # 1 from service per SO23-3-2.19, Control Element Drive Mechanism Control System Operation. This is a bank JPM under the Control Rod Drive System - Reactivity Control Safety Function.

3 of 3 SONGS NRC 2012 ES-301-2 RO & SRO JPM Outline Rev aa

ES-401 PWR Examination Outline Form ES-401-2 Facility: San Onofre Nuclear Generating Station Date of Exam: October 25, 2012 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G A2 G* Total

• Total

1. 1 2 2 4 4 3 3 18 4 2 6 Emergency &

Abnormal Plant 2 2 2 2 N/A 1 1 N/A 1 9 2 2 4 Evolutions Tier Totals 4 4 6 5 4 4 27 6 4 10 1 4 1 2 3 2 1 3 3 3 3 3 28 3 2 5 2.

2 1 1 1 1 1 1 1 1 1 1 0 10 1 2 3 Plant Systems Tier Totals 5 2 3 4 3 2 4 4 4 4 3 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 10 Categories 3 3 2 2 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 16

ES-401 2a Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) IR #

000007 (BW/E02&E10; CE/E02) Reactor CE/E02 EA1.1 Ability to interpret and/or monitor the Trip - Stabilization - Recovery / 1 following as they apply to Reactor Trip Recovery:

Components, and functions of control and safety X 3.7 39 systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

000008 Pressurizer Vapor Space Accident / 008AK2.02 Knowledge of the interrelation between 3 X the Pressurizer Vapor Space Accident and the 2.7 40 following: Sensors and detectors.

000009 Small Break LOCA / 3 009EK3.21 Knowledge of the reasons for the following responses as the apply to the small break X 4.2 41 LOCA: Actions contained in EOP for small break LOCA/leak 000011 Large Break LOCA / 3 011EA2.04 Ability to determine or interpret the X following as they apply to a Large Break LOCA: 3.7 42 Significance of PZR readings 000015/17 RCP Malfunctions / 4 015/017AK1.04 Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC X 2.9 43 Flow): Basic steady state thermodynamic relationship between RCS loops and S/Gs resulting from unbalanced RCS flow.

000025 Loss of RHR System / 4 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and X 4.2 44 understand how operator actions and directives affect plant and system conditions.

000026 Loss of Component Cooling Water / 026AK3.04 Knowledge of the reasons for the 8 following responses as they apply to the Loss of X 3.5 45 Component Cooling Water: Effect on the CCW flow header of a loss of CCW.

000027 Pressurizer Pressure Control 2.1.31 Ability to locate control room switches, System Malfunction / 3 X controls, and indications, and to determine that they 4.6 46 correctly reflect the desired plant lineup.

000038 Steam Gen. Tube Rupture / 3 038EK1.03 Knowledge of the operational X implications of the following concepts as 3.9 47 they apply to the SGTR: Natural circulation 000040 (BW/E05; CE/E05; W/E12) Steam CE/E05 EA2.2 Ability to determine and interpret the Line Rupture - Excessive Heat Transfer / following as they apply to the (Excess Steam 4 X Demand): Adherence to appropriate procedures 3.4 48 and operation within the limitations in the facilitys license and amendments.

000054 (CE/E06) Loss of Main Feedwater / 054AK3.04 Knowledge of the reasons for the 4 following responses as they apply to the Loss of X 4.4 49 Main Feedwater (MFW): Actions contained in EOPs for loss of MFW.

000055 Station Blackout / 6 055EA1.05 Ability to operate and monitor the X following as they apply to a Station Blackout: 3.3 50 Battery, when approaching fully discharged 000056 Loss of Off-site Power / 6 056AA1.06 Ability to operate and / or monitor the X following as they apply to the Loss of Offsite Power: 3.6 51 Safety Injection Pump.

000057 Loss of Vital AC Inst. Bus / 6 057AA1.01 Ability to operate and / or monitor the X following as they apply to the Loss of Vital AC 3.7 52 Instrument Bus: Manual Inverter Swapping Page 2 of 16

000058 Loss of DC Power / 6 2.4.8 Knowledge of how abnormal operating X 3.8 53 procedures are used in conjunction with EOPs.

000062 Loss of Nuclear Svc Water / 4 062AK3.01 Knowledge of the reasons for the following responses as they apply to the Loss of Nuclear Service Water: The conditions that will X 3.2 54 initiate the automatic opening and closing of the SWS isolation valves to the nuclear service water coolers.

000065 Loss of Instrument Air / 8 AA2.06 Ability to determine and interpret the following as they apply to the Loss of Instrument X 3.6 55 Air: When to trip reactor if instrument air pressure is de-creasing 000077 Generator Voltage and Electric Grid 077AK2.07 Knowledge of the interrelations between Disturbances / 6 X Generator Voltage and Electric Grid Disturbances 3.6 56 and the following: Turbine / generator control K/A Category Totals: 2 2 4 4 3 3 Group Point Total: 18/6 Page 3 of 16

ES-401 3a Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) IR #

000001 Continuous Rod Withdrawal / 1 001AK1.06 Knowledge of the operational implications of the following concepts as they X apply to Continuous Rod Withdrawal: 4.0 57 Relationship of reactivity and reactor power to rod movement 000005 Inoperable/Stuck Control Rod / 1 005AK3.05 Knowledge of the reasons for the following responses as they apply to X 3.4 58 the Inoperable / Stuck Control Rod: Power limits on rod misalignment 000051 Loss of Condenser Vacuum / 4 051AA1.04 Ability to operate and / or monitor X the following as they apply to the Loss of 2.5 59 Condenser Vacuum: Rod position 000059 Accidental Liquid RadWaste Rel. / 9 059AA2.03 Ability to determine and interpret the following as they apply to the Accidental X Liquid Radwaste Release: Failure modes, their 3.1 60 symptoms, and the causes of misleading indications on a radioactive-liquid monitor.

000068 (BW/A06) Control Room Evac. / 8 068AK2.01 Knowledge of the interrelations X between the Control Room Evacuation and the 3.9 61 following: Auxiliary shutdown panel layout 000074 (W/E06&E07) Inad. Core Cooling / 4 074 G2.4.6 Knowledge of EOP mitigation X 3.7 62 strategies.

000076 High Reactor Coolant Activity / 9 AK2.01 Knowledge of the interrelations X between the High Reactor Coolant Activity and 2.6 63 the following: Process radiation monitors CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A11 AK3.3 Knowledge of the reasons for the following responses as they apply to the (RCS Overcooling): Manipulation of X 3.1 64 controls required to obtain desired operating results during abnormal and emergency situations.

CE/E09 Functional Recovery CE/E09 EK1.3 Knowledge of the operational implications of the following concepts as they apply to the (Functional Recovery):

X 3.2 65 Annunciators and conditions indicating signals, and remedial actions associated with the (Functional Recovery).

K/A Category Point Totals: 2 2 2 1 1 1 Group Point Total: 9/4 Page 4 of 16

ES-401 4a Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) IR #

003 Reactor Coolant Pump 2.2.35 Ability to determine Technical X 3.6 1 Specification Mode of Operation 004 Chemical and Volume Control 004A3.03 Ability to monitor automatic X operation of the CVCS, including: Ion 2.9 2 exchange bypass 005 Residual Heat Removal 005K2.01 Knowledge of bus power X 3.0 3 supplies to the following: RHR Pumps 006 Emergency Core Cooling 006A1.06 Ability to predict and/or monitor changes in parameters (to prevent X exceeding design limits) associated with 3.6 4 operating the ECCS controls including:

Subcooling Margin 007 Pressurizer Relief/Quench Tank 007K4.01 Knowledge of PRTS design 2.6 feature(s) and/or interlock(s) which 5 provide for the following: Quench tank cooling.

X X 007A3.01 Ability to monitor automatic 2.7 operation of the PRTS, including: 6 Components which discharge to the PRT 008 Component Cooling Water 008A2.05 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to X correct, control, or mitigate the 3.3 7 consequences of those malfunctions or operations: Effect of loss of instrument and control air on the position of the CCW valves that are air operated 010 Pressurizer Pressure Control 010K5.02 Knowledge of the operational implications of the following concepts as X 2.6 8 the apply to the PZR PCS: Constant enthalpy expansion through a valve 012 Reactor Protection 012A1.01 Ability to predict and/or monitor 2.9 Changes in parameters (to prevent 9 exceeding design limits) associated with operating the RPS controls including: Trip X X setpoint adjustment.

012A4.06 Ability to manually operate 4.3 and/or monitor in the control room: 10 Reactor trip breakers 013 Engineered Safety Features 013K1.16 Knowledge of the physical Actuation connections and/or cause effect X 2.9 11 relationships between the ESFAS and the following systems: MRSS 022 Containment Cooling 022K3.02 Knowledge of the effect that a loss or malfunction of the CCS will have X 3.0 12 on the following: Containment instrumentation readings 026 Containment Spray 026K1.02 Knowledge of the physical connections and/or cause / effect X 4.1 13 relationships between the CSS and the following systems: Cooling water Page 5 of 16

039 Main and Reheat Steam 039K5.08 Knowledge of the operational implications of the following concepts as X 3.6 14 the apply to the MRSS: Effect of steam removal on reactivity 059 Main Feedwater 059K1.04 Knowledge of the physical connections and/or cause-effect relationships between the MFW and the 3.4 15 following systems: S/GS water level control system 059A2.12 Ability to (a) predict the impacts X X of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the 3.1 16 consequences of those malfunctions or operations: Failure of feedwater regulating valves 061 Auxiliary/Emergency Feedwater 061K6.01 Knowledge of the effect of a loss or malfunction of the following will X 2.5 17 have on the AFW components:

Controllers and positioners.

062 AC Electrical Distribution 062A4.03 Ability to manually operate and/or monitor in the control room:

X Synchroscope, including an 2.8 18 understanding of running and incoming voltages 063 DC Electrical Distribution 063K3.01 Knowledge of the effect that a 3.7 loss or malfunction of the DC electrical 19 system will have on the following: ED/G X X 063K4.01 Knowledge of DC electrical 2.7 system design feature(s) and / or interlock(s) which provide for the 20 following: Manual/automatic transfers of control 064 Emergency Diesel Generator 064A1.03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with 3.2 21 operating the ED/G system controls including: Operating voltages, currents, and temperatures 073 Process Radiation Monitoring 2.4.4 Ability to recognize abnormal indications for system operating X parameters that are entry-level conditions 4.5 22 for emergency and abnormal operating procedures.

076 Service Water 076A4.02 Ability to manually operate 2.6 and/or monitor in the control room: SWS 23 valves X X 2.1.27 Knowledge of system purpose 3.9 24 and/or function.

078 Instrument Air 078K1.03 Knowledge of the physical 3.3 connections and/or cause-effect 25 relationships between the IAS and the following systems: Containment air.

X X 078A3.01 Ability to monitor automatic 3.1 26 operation of the IAS, including: Air pressure.

Page 6 of 16

103 Containment 103K4.06 Knowledge of containment 3.1 system design feature(s) and/or interlock(s) which provide for the 27 following: Containment isolation system 103A2.04 Ability to (a) predict the impacts 3.5 X X of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions 28 or operations: Containment evacuation (including recognition of the alarm)

K/A Category Point Totals: 4 1 2 3 2 1 3 3 3 3 3 Group Point Total: 28/5 Page 7 of 16

ES-401 5a Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) IR #

001 Control Rod Drive 001K1.05 Knowledge of the physical connections and/or cause effect X 4.5 29 relationships between the CRDS and the following systems: NIS and RPS 002 Reactor Coolant 002A3. 03 Ability to monitor automatic X operation of the RCS, including: Pressure, 4.4 30 temperatures, and flows 014 Rod Position Indication 014K4.06 Knowledge of RPIS design feature(s) and/or interlock(s) which provide X 3.4 31 for the following: Individual and group misalignment 015 Nuclear Instrumentation 015K5.06 Knowledge of the operational implications of the following concepts as X 3.4 32 they apply to the NIS: Subcritical multiplications and NIS indications 017 In-core Temperature Monitor 017A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the ITM system; and (b) based on those X predictions, use procedures to correct, 3.6 33 control or mitigate the consequences of those malfunctions or operations: Core damage.

033 Spent Fuel Pool Cooling 033K3.02 Knowledge of the effect that a loss or malfunction of the X Spent Fuel Pool Cooling System will have 2.8 34 on the following: Area and ventilation radiation monitoring systems 041 Steam Dump/Turbine Bypass 041K6.03 Knowledge of the effect of a loss Control or malfunction on the following will have on X 2.7 35 the SDS: Controller and positioners, including ICS, S/G, CRDS 045 Main Turbine Generator 045A1.05 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with X operating the MT/G system controls 3.8 36 including: Expected response of primary plant parameters (temperature and pressure) following T/G trip 068 Liquid Radwaste 068 A4.04 Ability to manually operate X and/or monitor in the control room: 3.8 37 Automatic isolation 075 Circulating Water 075K2.03 Knowledge of bus power X supplies to the following: 2.6 38 Emergency/essential SWS pumps K/A Category Point Totals: 1 1 1 1 1 1 1 1 1 1 0 Group Point Total: 10/3 Page 8 of 16

ES-401 2b Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) IR #

000007 (BW/E02&E10; CE/E02) Reactor 007EA2.02 Ability to determine or interpret the Trip - Stabilization - Recovery / 1 following as they apply to a reactor trip: Proper X 4.6 76 actions to be taken if the automatic safety functions have not taken place.

000008 Pressurizer Vapor Space Accident / 2.4.21 Knowledge of the parameters and logic 3 used to assess the status of safety functions, such as reactivity control, core cooling and heat X 4.6 77 removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

000056 Loss of Off-site Power / 6 2.4.13 Knowledge of crew roles and X 4.6 78 responsibilities during EOP usage.

000058 Loss of DC Power / 6 058AA2.03 Ability to determine and interpret the following as they apply to the Loss of DC Power:

X 3.9 79 DC loads lost; impact on ability to operate and monitor plant systems 000062 Loss of Nuclear Svc Water / 4 062AA2.02 Ability to determine and interpret the X following as they apply to the Loss of Nuclear 3.6 80 Service Water: The cause of possible SWS loss 000077 Generator Voltage and Electric Grid 077AA2.10 Ability to determine and interpret the Disturbances / 6 following as they apply to Generator Voltage and X 3.8 81 Electric Grid Disturbances: Generator overheating and the required actions K/A Category Totals: 4 2 Group Point Total: 18/6 Page 9 of 16

ES-401 3b Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) IR #

000003 Dropped Control Rod / 1 2.4.4 Ability to recognize abnormal indications for system operating parameters X 4.7 82 that are entry-level conditions for emergency and abnormal operating procedures.

000060 Accidental Gaseous Radwaste Rel. / 9 AA2.02 Ability to determine and interpret the following as they apply to the Accidental Gaseous Radwaste Release: The possible X 4.0 83 location of a radioactive-gas leak, with the assistance of PEO, health physics and chemistry personnel 000061 ARM System Alarms / 7 2.4.6 Knowledge of EOP mitigation X 4.7 84 strategies.

CE/A16 Excess RCS Leakage / 2 CE/A16 AA2.1 Ability to determine and interpret the following as they apply to the X (Excess RCS Leakage): Facility conditions 3.5 85 and selection of appropriate procedures during abnormal and emergency operations.

K/A Category Point Totals: 2 2 Group Point Total: 9/4 Page 10 of 16

ES-401 4b Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) IR #

005 Residual Heat Removal 005A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based X on those predictions, use procedures to 2.9 86 correct, control, or mitigate the consequences of those malfunctions or operations: RHR valve malfunction 013 Engineered Safety Features 013A2.06 Ability to (a) predict the Actuation impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use X 4.0 87 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent ESFAS actuation 062 AC Electrical Distribution 2.2.25 Knowledge of the bases in Technical Specifications for limiting X 4.2 88 conditions for operations and safety limits.

063 DC Electrical Distribution 063A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; X and (b) based on those predictions, use 3.2 89 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Grounds 078 Instrument Air 2.1.7 Ability to evaluate plant performance and make operational X judgments based on operating 4.7 90 characteristics, reactor behavior, and instrument interpretation.

K/A Category Point Totals: 3 2 Group Point Total: 28/5 Page 11 of 16

ES-401 5b Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) IR #

011 Pressurizer Level Control 011A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) based on those X predictions, use procedures to correct, 3.9 91 control, or mitigate the consequences of those malfunctions or operations:

Inadvertent PZR spray actuation.

035 Steam Generator 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner X 4.2 92 utilizing the appropriate control room reference material.

071 Waste Gas Disposal 2.1.23 Ability to perform specific system X and integrated plant procedures during all 4.4 93 modes of plant operation.

K/A Category Point Totals: 1 2 Group Point Total: 10/3 Page 12 of 16

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: SONGS Date of Exam: 10/25/2012 Category K/A # Topic RO SRO-Only IR # IR #

2.1.3 Knowledge of shift or short-term relief turnover practices. 3.7 66 2.1.19 Ability to use plant computers to evaluate system or component

1. 3.9 67 status.

Conduct of Operations 2.1.44 Knowledge of RO duties in the control room during fuel handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from 3.9 68 the control room in support of fueling operations, and supporting instrumentation.

2.1.

2.1.15 Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, 3.4 94 Operations memos, etc.

2.1.42 Knowledge of new and spent fuel movement procedures. 3.4 95 Subtotal 3 2 2.2.4 (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and 3.6 69 procedural actions between units at a facility.

2. 2.2.14 Knowledge of the process for controlling equipment configuration 3.9 70 Equipment or status.

Control 2.2.41 Ability to obtain and interpret station electrical and mechanical 3.5 71 drawings.

2.2.

2.2.5 Knowledge of the process for making design or operating changes 3.2 96 to the facility.

2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work 3.9 97 prioritization, etc.

Subtotal 3 2 2.3.11 Ability to control radiation releases. 3.8 72 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms,

3. 3.4 73 containment entry requirements, fuel handling responsibilities, Radiation Control access to locked high-radiation areas, aligning filters, etc.

2.3.

2.3.

2.3.

2.3.6 Ability to approve release permits. 3.8 98 Subtotal 2 1 2.4.3 Ability to identify post-accident instrumentation. 3.7 74 2.4.49 Ability to perform without reference to procedures those actions

4. that require immediate operation of system components and 4.4 75 Emergency controls.

Procedures / Plan 2.4.

2.4.

Page 13 of 16

2.4.18 Knowledge of the specific bases for EOPs. 4.0 99 2.4.44 Knowledge of emergency plan protective action recommendations. 4.4 100 Subtotal 2 2 Tier 3 Point Total 10 7 Page 14 of 16

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 2/1 003 G2.2.39 No less than or equal to one hour TS exists for the Reactor Coolant Pump System. Reselected 003 G2.2.35.

2/1 004 A3.07 The CVCS System does not tie into S/G level and pressure.

Reselected 004 A3.03.

2/1 039 K5.05 TS Bases is SRO knowledge. Reselected 039 K5.08.

2/1 059 K3.03 Oversampling (Q 14 and Q 15). Reselected 059 K1.04 Page 15 of 16

Page 16 of 16 Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 & 3 Scenario No.: 1 Op Test No.: October 2012 NRC Examiners: Operators:

Initial Conditions: 100% power MOC.

Turnover: Maintain steady state conditions.

Critical Tasks:

• Restore power to 1E 4kV bus 2A04 following a Station Blackout per SO23-12-9, Functional Recovery.

• Manually start HPSI Pump P-018 (or P-017) following the restoration of power to 1E 4kV bus 2A04 to establish minimum required HPSI flow per SO23-12-9, Functional Recovery.

Event No. Malf. Event Type* Event Description No.

1 (10 min) RM06 I (RO, SRO) Containment High Range Radiation Monitor 7820-1 Fails High TS (SRO) 2 (15 min) NSW C (BOP, SRO) Nuclear Service Water Pump P-139 O/C Trip, P-138 Fails to Auto LP Start 3 (25 min) RC03 C (RO, SRO) Reactor Coolant System Leak (10 GPM)

TS (SRO) 4 (45 min) R (RO, BOP, SRO) Rapid Power Reduction due to RCS Leak 5 (50 min) ED04A C (BOP, SRO) 480V Bus 2A03 O/C 6 (50 min) RC03 M (RO, BOP, SRO) RCS Leak Increases to 500 GPM on Reactor Trip 7 (50 min) PG24 C (RO, BOP, SRO) Loss of Offsite Power upon Reactor Trip (10 second time delay) 8 (50 min) EG08A C (BOP, SRO) Train A EDG Fails to Start (cannot be started from CR) 9 (50 min) EG16B C (BOP, SRO) Train B EDG Output Breaker Fails to Auto Close 10 (55 min) ED03B M (RO, BOP, SRO) Train B EDG Output Breaker O/C Trip (60 second time delay from manual breaker closure) 11 (75 min) RP01BA C (RO/BOP, SRO) Train A HPSI P-018 Fails to Auto Start upon restoration of power to 1E 4kV bus 2A04

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 10 Total malfunctions (5-8) 5 Malfunctions after EOP entry (1-2) 4 Abnormal events (2-4) 2 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)

SONGS 2012 NRC Sim Scenario # 1 Rev A

Appendix D Scenario Outline Form ES-D-1 SONGS 2012 NRC Sim Scenario # 1 Rev A

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 & 3 Scenario No.: 2 Op Test No.: October 2012 NRC Examiners: Operators:

Initial Conditions: 100% Power MOC Turnover: Maintain steady state conditions.

Critical Tasks:

• Emergency Borate the RCS following Reactor Trip following the failure of two full-length CEAs to insert on Reactor trip per SO23-12-1, Standard Post Trip Actions.

• Trip all 4 RCPs within 10 minutes of the CIAS due to the loss of Component Cooling Water to the RCPs.

Event No. Malf. Event Type* Event Description No.

1 (10 min) SG03G I (BOP, SRO) S/G E-089 Pressure Transmitter PT-1013-3 fails low TS (SRO) 2 (25 min) MFW N (RO, BOP, SRO) MFW Pump K-006 Trip (Rapid Power Reduction to 65% Power)

LP 3 (25 min) FW02A TS (SRO) AFW Pump P-141 O/C Trip 4 (35 min) RC11 I (RO, SRO) Thot Instrument TT-0121X2 Fails High 5 (50 min) ED08B C (RO, BOP, SRO) Loss of Non-1E Instrument Bus 2Q0612 6 (52 min) RP23B M (RO, BOP, SRO) Inadvertent CIAS - Loss of Forced Circulation 7 (55 min) ED03A C (BOP) 1E 4kV Bus 2A04 O/C Trip on Reactor Trip 8 (55 min) RD1002 R (RO, SRO) Two Full Length CEAs Fail to Fully Insert - Gravity Feed Emergency Boration Required RD4002 9 (55 min) ELEC I (BOP) Non-1E 4kV Bus 2A08 Fails to Auto Transfer on Reactor Trip LP

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 9 Total malfunctions (5-8) 3 Malfunctions after EOP entry (1-2) 5 Abnormal events (2-4) 1 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 2 Critical tasks (2-3)

SONGS 2012 NRC Sim Scenario # 2 Rev A

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 & 3 Scenario No.: 3 Op Test No.: October 2012 NRC Examiners: Operators:

Initial Conditions: 100 Power MOC Turnover: Perform post-maintenance testing of CEA 55. Maintain steady state conditions.

Critical Tasks:

• Emergency Borate the RCS following a failure of two full-length CEAs to insert on the Reactor trip per SO23-12-1, Standard Post Trip Actions.

• Isolate S/G E-088 prior to exiting SO23-12-5, Excess Steam Demand Event.

• Perform HPSI Throttle/Stop prior to the Pressurizer going solid per SO23-12-11, EOI Supporting Attachments.

Event No. Malf. Event Type* Event Description No.

1 (10 min) SG05A I (BOP, SRO) S/G E-088 Level Transmitter LT-1123-1 fails high TS (SRO) 2 (15 min) N (RO) Exercise CEA 55 for post-maintenance testing 3 (30 min) RD5503 I (RO, SRO) CEA 55 Drop ~ 50 TS (SRO) 4 (45 min) N (RO, BOP, SRO) Rapid Power Reduction to 85%

5 (50 min) TP02B C (BOP) TPCW Pump O/C, Standby Pump Fails to Auto Start TP08A 6 (55 min) FW04B M (RO, BOP, SRO) MFW Rupture (S/G E-089) Inside Containment (50% severity, 15 minute ramp) 7 (60 min) RD5502 R (RO, SRO) Two Full Length CEAs Fail to Fully Insert on Reactor Trip RD5802 8 (65 min) RP01E C (RO) LPSI P-016 Fails to Auto Start on SIAS

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 6 Total malfunctions (5-8) 2 Malfunctions after EOP entry (1-2) 3 Abnormal events (2-4) 1 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 3 Critical tasks (2-3)

SONGS 2012 NRC Sim Scenario # 3 Rev A

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 & 3 Scenario No.: 4 Op Test No.: October 2012 NRC Examiners: Operators:

Initial Conditions: 100% Power MOC Turnover: Maintain steady state conditions.

Critical Tasks:

• Transfer the CCW Non-Critical Loop prior to exceeding an RCP operating temperature limits following a loss of Train A SWC Pump P-112.

• Manually start a HPSI pump following an O/C on HPSI Pump P-018 and failure of HPSI Pump P-019 to auto start on SIAS.

• Manually initiate CIAS following a failure of CIAS to automatically actuate on high containment pressure prior to exiting SO23-12-1, Standard Post Trip Actions.

Event No. Malf. Event Type* Event Description No.

1 (10 min) SC01A C (BOP, SRO) Train A Saltwater Cooling Pump P-112 Shaft Seizure TS (SRO) 2 (20 min) RX04B I (RO, SRO) Pressurizer Pressure Control Channel Transmitter PT-0100Y Fails High 3 (40 min) ED07B C (RO, BOP, SRO) Loss of Vital Bus Y02 TS (SRO) 4 (45 min) SWC LP C (BOP, SRO) Stator Water Cooling Pump P-291 OC Trip, P-290 Fails to Auto Start 5 (50 min) RD1501 M (RO, BOP, SRO) Ejected CEA (LBLOCA) 6 (50 min) RP01P C (BOP) Motor Driven Auxiliary Feedwater Pump P-141 Fails to Auto Start on EFAS 7 (50 min) EC08DA I (RO/BOP) HPSI P-018 O/C Trip on SIAS, HPSI P-019 Fails to Auto Start on RP01C SIAS 8 (55 min) PPS LP I (RO/BOP) CIAS Fails to Auto Actuate

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 8 Total malfunctions (5-8) 3 Malfunctions after EOP entry (1-2) 3 Abnormal events (2-4) 1 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 3 Critical tasks (2-3)

SONGS 2012 NRC Sim Scenario # 4 Rev A

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 & 3 Scenario No.: 5 Op Test No.: October 2012 NRC Examiners: Operators:

Initial Conditions: 100% Power MOC Turnover: Maintain steady state conditions.

Critical Tasks:

• Restore CCW flow to the RCPs prior to exceeding RCP operating temperature limits per SO23-13-7, Loss of Component Cooling Water / Saltwater Cooling.

• Manually initiate Containment Spray prior to exceeding Containment temperature and pressure limits following a failure of Containment Spray to automatically actuate.

• Stabilize RCS temperature following an ESDE from S/G E-088.

• Isolate S/G E-088 within 30 minutes of entering SO23-12-9, Functional Recovery.

Event No. Malf. Event Type* Event Description No.

1 (10 min) RC16B I (RO, SRO) Pressurizer Level Control Channel Transmitter LT-0110-2 fails low TS (SRO) 2 (20 min) CC06B C (BOP, SRO) CCW Pump P-025 O/C, P-024 fails to start CCW TS (SRO)

LP 3 (30 min) CV03C C (RO, SRO) RCP P-003 Upper and Middle Seal Failures CV04C 4 (50 min) N (RO, BOP, SRO) Rapid Power Reduction 5 (55 min) OBE LP M (RO, BOP, SRO) Earthquake (OBE w/o MFW Pump Trip)

SG01A 400 GPM SGTR on S/G E-088 6 (55 min) MS03A M (RO, BOP, SRO) ESDE inside containment from S/G E-088 on Reactor Trip 7 (55 min) TU07 I (BOP) Main Turbine Fails to Trip on Reactor Trip 8 (60 min) PPS LP I (RO) CSAS Fails to Auto Actuate

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 8 Total malfunctions (5-8) 3 Malfunctions after EOP entry (1-2) 4 Abnormal events (2-4) 2 Major transients (1-2) 3 EOPs entered/requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions (0-2) 4 Critical tasks (2-3)

SONGS 2012 NRC Sim Scenario # 5 Rev A

Appendix D Scenario Outline Form ES-D-1 Facility: SONGS 2 & 3 Scenario No.: 6 Op Test No.: October 2012 NRC Examiners: Operators:

Initial Conditions: 4% Reactor Power MOC Turnover: Raise power to 18% and stabilize for > 20% power surveillances.

Critical Tasks:

• Manually trip the Reactor within one minute of the failure of the Reactor Trip Pushbutton failure to trip the Reactor.

• Restore power to 1E 4kV bus 2A04 prior to exiting SO23-12-1, Standard Post Trip Actions.

• Manually start HPSI Pump P-018 (or P-017) following the restoration of power to 1E 4kV bus 2A04 to establish minimum HPSI flow.

Event No. Malf. Event Type* Event Description No.

1 (20 min) R (RO, BOP, SRO) Raise Reactor Power to 18%

2 (30 min) CS05C I (RO, SRO) RWST Level Transmitter LT-0305-3 Fails Low TS (SRO) 3 (40 min) RX08 C (BOP, SRO) SBCS Valves Fail Open 4 (50 min) ED11 I (RO, BOP, SRO) Loss of Control Room Annunciators 5 (55 min) RC03 M (RO, BOP, SRO) 400 GPM Steam Generator Tube Rupture (600 second ramp)

TS (SRO) 6 (55 min) RP02A C (RO, SRO) Failure of All Reactor Trip Pushbuttons to Trip the Reactor RP02B 7 (55 min) PG24 M (RO, BOP, SRO) Loss of Offsite Power on Reactor Trip 8 (55 min) ED03B C (BOP) 1E 4kV Bus 2A06 O/C Trip on Reactor Trip 9 (60 min) ELEC C (BOP) Reserve Aux Transformer breaker fails to open on Rx Trip (2G002 LP O/P breaker will not close until RAT breaker is opened manually).

10 (65 min) RP01BA C (RO) HPSI Pump P-018 Fails to Start on SIAS

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Technical Specifications Actual Target Quantitative Attributes 9 Total malfunctions (5-8) 4 Malfunctions after EOP entry (1-2) 4 Abnormal events (2-4) 2 Major transients (1-2) 2 EOPs entered/requiring substantive actions (1-2) 0 EOP contingencies requiring substantive actions (0-2) 3 Critical tasks (2-3)

SONGS 2012 NRC Sim Scenario # 6 Rev A

Appendix D Scenario Outline Form ES-D-1 SONGS 2012 NRC Sim Scenario # 6 Rev A

ES-301 Competencies Checklist Form ES-301-6 Facility: SONGS 2 & 3 Date of Examination: 10/12/12 Operating Test Number: NRC 1, 2, 3, 4, & 5 Applicants SROU-1 SROU-2 SROU-3 Competencies SCENARIO SCENARIO SCENARIO 1 2 1 4 1 4 Interpret/Diag- 1,2,3,5, 1,2,3,5, 1,2,3,5, 1,2,3,4, nose Events 7,8,9,1 5,6,8, 7,8,9,10 ALL 7,8,9,10 ALL 0,11 ,11 ,11 and Conditions Comply With and Use ALL ALL ALL ALL ALL ALL Procedures (1)

Operate Control Boards N/A N/A N/A N/A N/A N/A (2)

Communicate and ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory ALL ALL ALL ALL ALL ALL Ability (3)

Comply With and Use Tech. 1,3 1,3 1,3 1,3 1,3 1,3 Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

SONGS NRC 2012 ES-301-6 Competencies Checklist Rev a

ES-301 Competencies Checklist Form ES-301-6 Facility: SONGS 2 & 3 Date of Examination: 10/12/12 Operating Test Number: NRC 1, 2, 3, 4, & 5 Applicants SROU-4 SROI-1 SROI-2 Competencies SCENARIO SCENARIO SCENARIO 1 4 1 2 5 1 5 5 Interpret/Diag- 1,2,3,5, 1,2,3,5, 1,2,3, 1,2,3,5, nose Events 7,8,9,1 ALL 1,3,8 7,9 5,6,8 1,3,8 6,8 0,11 and Conditions Comply With 1,2,5,7, and Use ALL ALL 1,3,4,8 9

ALL 1,3,4,8 ALL Procedures (1)

Operate 1,3,4,5, 1,2,5,7, 1,3,4,5, Control Boards N/A N/A 8 9 N/A 8

N/A (2)

Communicate and ALL ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory ALL ALL N/A N/A ALL N/A ALL Ability (3)

Comply With and Use Tech. 1,3 1,3 N/A N/A 1,2 N/A 1,2 Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

SONGS NRC 2012 ES-301-6 Competencies Checklist Rev a

ES-301 Competencies Checklist Form ES-301-6 Facility: SONGS 2 & 3 Date of Examination: 10/12/12 Operating Test Number: NRC 1, 2, 3, 4, & 5 Applicants SROI-3 SROI-4 SROI-5 Competencies SCENARIO SCENARIO SCENARIO 1 5 1 5 3 5 Interpret/Diag-1,2,3,5, 1,2,3,5, 1,3,5,6, 1,3,5,6, nose Events 1,3,8 6,8 1,3,8 6,8 7 8 and Conditions Comply With 1,3,4,5, and Use 1,3,4,8 ALL 1,3,4,8 ALL ALL 8

Procedures (1)

Operate 1,3,4,5, 1,3,4,5, 1,3,4,5, Control Boards 8 N/A 8

N/A N/A 8

(2)

Communicate and ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory N/A ALL N/A ALL ALL N/A Ability (3)

Comply With and Use Tech. N/A 1,2 N/A 1,2 1,3 N/A Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

SONGS NRC 2012 ES-301-6 Competencies Checklist Rev a

ES-301 Competencies Checklist Form ES-301-6 Facility: SONGS 2 & 3 Date of Examination: 10/12/12 Operating Test Number: NRC 1, 2, 3, 4, & 5 Applicants SROI-6 SROI-7 SROI-8 Competencies SCENARIO SCENARIO SCENARIO 3 5 3 5 3 5 Interpret/Diag-1,3,5,6, 1,3,5,6, 1,3,5,6, 1,3,5,6, 1,3,5,6, 1,3,5,6, nose Events 7 8 7 8 7 8 and Conditions Comply With 1,3,4,5, 1,3,4,5, 1,3,4,5, and Use ALL 8

ALL 8

ALL 8

Procedures (1)

Operate 1,3,4,5, 1,3,4,5, 1,3,4,5, Control Boards N/A 8

N/A 8

N/A 8

(2)

Communicate and ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory ALL N/A ALL N/A ALL N/A Ability (3)

Comply With and Use Tech. 1,3 N/A 1,3 N/A 1,3 N/A Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

SONGS NRC 2012 ES-301-6 Competencies Checklist Rev a

ES-301 Competencies Checklist Form ES-301-6 Facility: SONGS 2 & 3 Date of Examination: 10/12/12 Operating Test Number: NRC 1, 2, 3, 4, & 5 Applicants SROI-9 RO-1 RO-2 Competencies SCENARIO SCENARIO SCENARIO 2 4 1 3 4 1 3 4 Interpret/Diag- 1,3,4, 1,3,4, 2,5,7,9, 3,6,7, 2,5,7,9, 3,6,7, nose Events 4,5,6,8 ALL 10,11 8 5,6,7, 10,11 8 5,6,7, 8 8 and Conditions Comply With 2,9,10, 1,3,4, 2,9,10, 1,3,4, and Use 2,4,5,8 ALL 11 2,3,4,7 6,8 11 2,3,4,7 6,8 Procedures (1)

Operate 2,4,5,6, 2,4,9,10 2,3,4,6, 1,3,4, 2,4,9,10 2,3,4,6, 1,3,4, Control Boards 8 N/A

,11 7,8 6,8 ,11 7,8 6,8 (2)

Communicate and ALL ALL ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory N/A ALL N/A N/A N/A N/A N/A N/A Ability (3)

Comply With and Use Tech. N/A 1,3 N/A N/A N/A N/A N/A N/A Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

SONGS NRC 2012 ES-301-6 Competencies Checklist Rev a

ES-301 Competencies Checklist Form ES-301-6 Facility: SONGS 2 & 3 Date of Examination: 10/12/12 Operating Test Number: NRC 1, 2, 3, 4, & 5 Applicants RO-3 RO-4 RO-5 Competencies SCENARIO SCENARIO SCENARIO 1 3 4 1 3 4 3 4 5 Interpret/Diag- 1,3,4 1,3,4, 2,5,7,9, 3,6,7 2,5,7,9, 3,6,7, 2,3,5, 2,5,6, nose Events 10,11 ,8

,5,6, 10,11 8 5,6,7, 1,5,6 9 7 7,8 8 and Conditions Comply With 2,9,10, 1,3,4 2,9,10, 1,3,4, 2,4,6, and Use 11 2,3,4,7

,6,8 11 2,3,4,7 6,8 1,4,5 2,3,9 7

Procedures (1)

Operate 2,4,9,1 2,3,4,6, 1,3,4 2,4,9,10 2,3,4,6, 1,3,4, 2,3,5, 2,4,6, Control Boards 0,11 7,8 ,6,8 ,11 7,8 6,8 1,4,5 9 7 (2)

Communicate and ALL ALL ALL ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory N/A N/A N/A N/A N/A N/A N/A N/A N/A Ability (3)

Comply With and Use Tech. N/A N/A N/A N/A N/A N/A N/A N/A N/A Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

SONGS NRC 2012 ES-301-6 Competencies Checklist Rev a

ES-301 Competencies Checklist Form ES-301-6 Facility: SONGS 2 & 3 Date of Examination: 10/12/12 Operating Test Number: NRC 1, 2, 3, 4, & 5 Applicants RO-6 RO-7 RO-8 Competencies SCENARIO SCENARIO SCENARIO 3 4 5 3 4 5 3 4 5 Interpret/Diag-2,3,5 2,5,6 2,3,5, 2,5,6, 2,3,5, 2,5,6, nose Events 1,5,6

,9 ,7 1,5,6 9 7 1,5,6 9 7 and Conditions Comply With 2,4,6 2,4,6, 2,4,6, and Use 1,4,5 2,3,9

,7 1,4,5 2,3,9 7

1,4,5 2,3,9 7

Procedures (1)

Operate 2,3,5 2,4,6 2,3,5, 2,4,6, 2,3,5, 2,4,6, Control Boards 1,4,5

,9 ,7 1,4,5 9 7 1,4,5 9 7 (2)

Communicate and ALL ALL ALL ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory N/A N/A N/A N/A N/A N/A N/A N/A N/A Ability (3)

Comply With and Use Tech. N/A N/A N/A N/A N/A N/A N/A N/A N/A Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

SONGS NRC 2012 ES-301-6 Competencies Checklist Rev a

ES-301 Transient and Event Checklist Form ES-301-5 Facility: SONGS 2 and 3 Date of Exam: 10/12/12 Operating Test Number: 1 E SCENARIOS A V P E SONGS #1 SONGS #2 SONGS #3 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 4 8 2 0 NOR - 2 1 1 SROU-1 I/C 1,2,3,7, 8,9,10 1,4,5 10 2 MAJ 6,11 6 3 1 TS 1,3 1,3 4 2 RX 4 - 1 0 NOR - - 0 1 SROU-2 I/C 1,2, 1,2,3,7, 8,9,10 3,4, 13 2 5,7 MAJ 6,11 8 3 1 TS 1,3 1,3 4 2 RX 4 - 1 0 NOR - - 0 1 SROU-3 I/C 1,2, 1,2,3,7, 8,9,10 3,4, 13 2 5,7 MAJ 6,11 8 3 1 TS 1,3 1,3 4 2 RX 4 - 1 0 NOR - - 0 1 SROU-4 I/C 1,2, 1,2,3,7, 8,9,10 3,4, 13 2 5,7 MAJ 6,11 8 3 1 TS 1,3 1,3 4 2 RX 4 - *- 1 1 NOR - 2 *5 2 1 SROI-1 I/C 1,3,5 1,5, *1,2

,7,8 12 4 7,9 ,3 MAJ 6,11 6 *5,6 5 2 TS - - *1,2 2 2 RX 4 *- 1 1 NOR - *5 1 1 SROI-2 I/C 1,3,5 *1,2

,7,8 8 4

,3 MAJ 6,11 *5,6 4 2 TS - *1,2 2 2

• Scenario #5 Page 1 of 4 SONGS NRC 2012 ES-301-5 Transient and Event Checklist Rev a

ES-301 Transient and Event Checklist Form ES-301-5 Facility: SONGS 2 and 3 Date of Exam: 10/12/12 Operating Test Number: 1 E SCENARIOS A V P E SONGS #1 SONGS #2 SONGS #3 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 4 *- 1 1 NOR - *5 1 1 SROI-3 I/C 1,3,5 *1,2

,7,8 8 4

,3 MAJ 6,11 *5,6 4 2 TS - *1,2 2 2 RX 4 *- 1 1 NOR - *5 1 1 SROI-4 I/C 1,3,5 *1,2

,7,8 8 4

,3 MAJ 6,11 *5,6 4 2 TS - *1,2 2 2 RX 4 *- 1 1 NOR - *5 1 1 SROI-5 I/C *1,3, 1,3 5 4 8

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

MAJ 6 *5,6 3 2 TS 1,3 *- 2 2 RX 4 *- 1 1 NOR - *5 1 1 SROI-7 I/C *1,3, 1,3 5 4 8

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

,8 MAJ 6 *5,6 3 2 TS 1,3 *- 2 2

• Scenario #5 Page 2 of 4 SONGS NRC 2012 ES-301-5 Transient and Event Checklist Rev a

ES-301 Transient and Event Checklist Form ES-301-5 Facility: SONGS 2 and 3 Date of Exam: 10/12/12 Operating Test Number: 1 E SCENARIOS A V P E SONGS #1 SONGS #2 SONGS #3 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 8 - 1 1 NOR 2 - 1 1 SROI-9 I/C 1,2, 4,5 3,4, 8 4 5,7 MAJ 6 8 2 2 TS - 1,3 2 2 RX 4 4,7 - 3 1 NOR - 2 - 1 1 RO-1 I/C 1,3, 2,7, 3,7 4,5, 12 4 9,10 6,7 MAJ 6,11 6 8 4 2 TS - - - 0 0 RX 4 4,7 - 3 1 NOR - 2 - 1 1 RO-2 I/C 1,3, 2,7, 3,7 4,5, 12 4 9,10 6,7 MAJ 6,11 6 8 4 2 TS - - - 0 0 RX 4 4,7 - 3 1 NOR - 2 - 1 1 RO-3 I/C 1,3, 2,7, 3,7 4,5, 12 4 9,10 6,7 MAJ 6,11 6 8 4 2 TS - - - 0 0 RX 4 4,7 - 3 1 NOR - 2 - 1 1 RO-4 I/C 1,3, 2,7, 3,7 4,5, 12 4 9,10 6,7 MAJ 6,11 6 8 4 2 TS - - - 0 0 RX *- 4 - 1 1 NOR *5 - - 1 1 RO-5 I/C 2,3,

• 2,7 1,5 8 4 5,9 MAJ *5,6 6 8 4 2 TS *- - - 0 0

• Scenario #5 Page 3 of 4 SONGS NRC 2012 ES-301-5 Transient and Event Checklist Rev a

ES-301 Transient and Event Checklist Form ES-301-5 Facility: SONGS 2 and 3 Date of Exam: 10/12/12 Operating Test Number: 1 E SCENARIOS A V P E SONGS #1 SONGS #2 SONGS #3 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 *- 4 - 1 1 NOR *5 - - 1 1 RO-6 I/C 2,3,

• 2,7 1,5 8 4 5,9 MAJ *5,6 6 8 4 2 TS *- - - 0 0 RX *- 4 - 1 1 NOR *5 - - 1 1 RO-7 I/C 2,3,

• 2,7 1,5 8 4 5,9 MAJ *5,6 6 8 4 2 TS *- - - 0 0 RX *- 4 - 1 1 NOR *5 - - 1 1 RO-8 I/C 2,3,

• 2,7 1,5 8 4 5,9 MAJ *5,6 6 8 4 2 TS *- - - 0 0

• Scenario #5 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 4 of 4 SONGS NRC 2012 ES-301-5 Transient and Event Checklist Rev a