ML14279A082

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08 Final Outlines
ML14279A082
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 08/08/2014
From: Vincent Gaddy
Operations Branch IV
To:
Pacific Gas & Electric Co
laura hurley
References
50-275/14-08, 50-323/14-08 50-275/OL-14, 50-323/OL-14
Download: ML14279A082 (30)
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Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: DCPP Printed: 04/02/2014 Date Of Exam: 08/08/2014 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 3 3 18 0 0 0 Emergency 2 2 2 1 N/A 1 1 2 9 0 0 0

& N/A Abnormal Tier Plant Totals 5 5 4 4 4 5 27 0 0 0 Evolutions 1 3 2 3 3 2 2 3 1 3 3 3 28 0 0 0 2.

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

3. Generic Knowledge And 10 0 Abilities Categories 4 2 2 2 0 0 0 0 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.

04/02/2014 11:19:00 am 1

PWR RO Examination Outline Printed: 04/02/2014 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000008 Pressurizer Vapor Space Accident / X 2.1.7 - Ability to evaluate plant 4.4 1 3 performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

000009 Small Break LOCA / 3 X EK2.03 - S/Gs 3.0 1 000011 Large Break LOCA / 3 X EK1.01 - Natural circulation and 4.1 1 cooling, including reflux boiling 000015/000017 RCP Malfunctions / 4 X AA1.06 - CCWS 3.1 1 000022 Loss of Rx Coolant Makeup / 2 X 2.1.23 - Ability to perform specific 4.3 1 system and integrated plant procedures during all modes of plant operation.

000025 Loss of RHR System / 4 X AK1.01 - Loss of RHRS during all 3.9 1 modes of operation 000027 Pressurizer Pressure Control System X 2.4.21 - Knowledge of the parameters 4.0 1 Malfunction / 3 and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

000029 ATWS / 1 X EK2.06 - Breakers, relays, and 2.9* 1 disconnects 000038 Steam Gen. Tube Rupture / 3 X EA2.01 - When to isolate one or more 4.1 1 S/Gs 000040 Steam Line Rupture - Excessive X AK3.04 - Actions contained in EOPs for 4.5 1 Heat Transfer / 4 steam line rupture 000054 Loss of Main Feedwater / 4 X AA2.05 - Status of MFW pumps, 3.5 1 regulating and stop valves 000055 Station Blackout / 6 X EK1.02 - Natural circulation cooling 4.1 1 000056 Loss of Off-site Power / 6 X AA2.04 - Operational status of service 3.5 1 water pump 000057 Loss of Vital AC Inst. Bus / 6 X AA1.06 - Manual control of 3.5 1 components for which automatic control is lost 000058 Loss of DC Power / 6 X AA1.01 - Cross-tie of the affected dc 3.4* 1 bus with the alternate supply W/E04 LOCA Outside Containment / 3 X EK3.3 - Manipulation of controls 3.8 1 required to obtain desired operating results during abnormal, and emergency situations 04/02/2014 11:18:29 am 1

PWR RO Examination Outline Printed: 04/02/2014 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points W/E05 Inadequate Heat Transfer - Loss of X EK3.2 - Normal, abnormal and 3.7 1 Secondary Heat Sink / 4 emergency operating procedures associated with Loss of Secondary Heat Sink W/E11 Loss of Emergency Coolant Recirc. / X EK2.1 - Components, and functions of 3.6 1 4 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 04/02/2014 11:18:29 am 2

PWR RO Examination Outline Printed: 04/02/2014 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000003 Dropped Control Rod / 1 X AK3.04 - Actions contained in EOP for 3.8* 1 dropped control rod 000024 Emergency Boration / 1 X AA2.05 - Amount of boron to add to 3.3 1 achieve required SDM 000033 Loss of Intermediate Range NI / 7 X AK1.01 - Effects of voltage changes on 2.7 1 performance 000067 Plant Fire On-site / 9 X AK1.02 - Fire fighting 3.1 1 000069 Loss of CTMT Integrity / 5 X 2.4.20 - Knowledge of operational 3.8 1 implications of EOP warnings, cautions, and notes.

000074 Inad. Core Cooling / 4 X EK2.01 - RCP 3.6 1 W/E02 SI Termination / 3 X 2.2.44 - Ability to interpret control 4.2 1 room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

W/E08 RCS Overcooling - PTS / 4 X EK2.2 - Facility's heat removal systems, 3.6 1 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility W/E13 Steam Generator Over-pressure / 4 X EA1.1 - Components, and functions of 3.1 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features K/A Category Totals: 2 2 1 1 1 2 Group Point Total: 9 04/02/2014 11:18:35 am 1

PWR RO Examination Outline Printed: 04/02/2014 Facility: DCPP ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X A1.07 - RCS temperature 3.4* 1 and pressure 004 Chemical and Volume Control X A4.01 - Boron and control 3.8 1 rod reactivity effects 005 Residual Heat Removal X K2.01 - RHR pumps 3.0 1 006 Emergency Core Cooling X 2.1.20 - Ability to interpret 4.6 1 and execute procedure steps.

007 Pressurizer Relief /Quench X K1.03 - RCS 3.0 1 Tank 008 Component Cooling Water X K1.05 - Sources of makeup 3.0 1 water 010 Pressurizer Pressure Control X K5.01 - Determination of 3.5 1 condition of fluid in PZR, using steam tables 012 Reactor Protection X K4.01 - Trip logic when one 3.7 1 channel OOC or in test 012 Reactor Protection X K2.01 - RPS channels, 3.3 1 components, and interconnections 013 Engineered Safety Features X K3.03 - Containment 4.3 1 Actuation 013 Engineered Safety Features X K6.01 - Sensors and 2.7* 1 Actuation detectors 022 Containment Cooling X 2.4.46 - Ability to verify that 4.2 1 the alarms are consistent with the plant conditions.

022 Containment Cooling X A1.02 - Containment 3.6 1 pressure 026 Containment Spray X K4.01 - Source of water for 4.2 1 CSS, including recirculation phase after LOCA 039 Main and Reheat Steam X A2.04 - Malfunctioning 3.4 1 steam dump 059 Main Feedwater X 2.1.31 - Ability to locate 4.6 1 control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

061 Auxiliary/Emergency X A3.04 - Automatic AFW 4.1 1 Feedwater isolation 061 Auxiliary/Emergency X K5.02 - Decay heat sources 3.2 1 Feedwater and magnitude 062 AC Electrical Distribution X A4.07 - Synchronizing and 3.1* 1 paralleling of different ac supplies 063 DC Electrical Distribution X K1.03 - Battery charger and 2.9 1 battery 04/02/2014 11:18:42 am 1

PWR RO Examination Outline Printed: 04/02/2014 Facility: DCPP ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 063 DC Electrical Distribution X A4.03 - Battery discharge 3.0* 1 rate 064 Emergency Diesel Generator X K6.08 - Fuel oil storage 3.2 1 tanks 064 Emergency Diesel Generator X K4.10 - Automatic load 3.5 1 sequencer: blackout 073 Process Radiation Monitoring X K3.01 - Radioactive effluent 3.6 1 releases 076 Service Water X A3.02 - Emergency heat 3.7 1 loads 076 Service Water X K3.01 - Closed cooling 3.4* 1 water 078 Instrument Air X A3.01 - Air pressure 3.1 1 103 Containment X A1.01 - Containment 3.7 1 pressure, temperature, and humidity K/A Category Totals: 3 2 3 3 2 2 3 1 3 3 3 Group Point Total: 28 04/02/2014 11:18:42 am 2

PWR RO Examination Outline Printed: 04/02/2014 Facility: DCPP ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 011 Pressurizer Level Control X K3.01 - CVCS 3.2* 1 014 Rod Position Indication X K5.01 - Reasons for 2.7 1 differences between RPIS and step counter 015 Nuclear Instrumentation X K1.02 - Vital ac systems 3.4 1 016 Non-nuclear Instrumentation X A2.03 - Interruption of 3.0 1 transmitted signal 017 In-core Temperature Monitor X K6.01 - Sensors and 2.7 1 detectors 028 Hydrogen Recombiner and X A1.01 - Hydrogen 3.4 1 Purge Control concentration 029 Containment Purge X K4.03 - Automatic purge 3.2* 1 isolation 072 Area Radiation Monitoring X A1.01 - Radiation levels 3.4 1 075 Circulating Water X K2.03 - Emergency/essential 2.6* 1 SWS pumps 086 Fire Protection X A4.05 - Deluge valves 3.0 1 K/A Category Totals: 1 1 1 1 1 1 2 1 0 1 0 Group Point Total: 10 04/02/2014 11:18:48 am 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 04/02/2014 Facility: DCPP Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.1 Knowledge of conduct of operations 3.8 1 requirements.

2.1.15 Knowledge of administrative requirements for 2.7 1 temporary management directives, such as standing orders, night orders, Operations memos, etc.

2.1.19 Ability to use plant computers to evaluate system 3.9 1 or component status.

2.1.32 Ability to explain and apply system limits and 3.8 1 precautions.

Category Total: 4 Equipment Control 2.2.2 Ability to manipulate the console controls as 4.6 1 required to operate the facility between shutdown and designated power levels.

2.2.13 Knowledge of tagging and clearance procedures. 4.1 1 Category Total: 2 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.2 1 normal or emergency conditions.

2.3.11 Ability to control radiation releases. 3.8 1 Category Total: 2 Emergency Procedures/Plan 2.4.6 Knowledge of EOP mitigation strategies. 3.7 1 2.4.12 Knowledge of general operating crew 4.0 1 responsibilities during emergency operations.

Category Total: 2 Generic Total: 10 04/02/2014 11:18:55 am 1

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection 000065 AA1.04 T1/G1 DCPP does not have emergency air compressors.

Randomly replaced with: APE 027 G2.4.21 T1/G1 EPE 055 G2.2.22 Unable to write to RO level question. Would require Tech Spec bases knowledge.

Randomly replaced with: EPE 055 EK1.02 Very close to 000008 Pressurizer Vapor Space G2.1.7 .

T1/G2 APE 028 AA2.11 Randomly replaced with E08 EK2.2 T1/G2 WE016 EK3.3 Not able to write test question to KA. DCPP has no testable action in the procedure to reduce containment radiation. Randomly replaced with APE003 AK3.04 026 A2.02 T2/G1 DCPP does not have auto recirculation transfer.

Randomly replaced with: 026 K4.01 T2/G1 103 A2.05 Rejected, DCPP does not have emergency cont. entry. Unable to write to RO level.

Randomly replaced with 103 A1.01 T2/G2 055 A3.03 KA A3.03 states: Ability to monitor automatic operation of the CARS, including:

Automatic diversion of CARS exhaust.

Not applicable to DCPP.

Randomly selected: 014 K5.01 T2/G2 086 A4.06 Not applicable at DCPP, randomly replaced with 086 A4.05 Rev 0

ES-401 PWR Examination Outline Form ES-401-2 Facility: DCPP Printed: 07/28/2014 Date Of Exam: 08/08/2014 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 0 0 0 0 0 0 0 3 3 6 Emergency 2 0 0 0 N/A 0 0 0 0 2 2 4

& N/A Abnormal Tier Plant Totals 0 0 0 0 0 0 0 5 5 10 Evolutions 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 5 2.

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

3. Generic Knowledge And 0 7 Abilities Categories 0 0 0 0 2 2 2 1 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.

07/28/2014 11:24:04 am 1

PWR SRO Examination Outline Printed: 07/28/2014 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000022 Loss of Rx Coolant Makeup / 2 X AA2.01 - Whether charging line leak 3.8 1 exists 000040 Steam Line Rupture - Excessive X 2.4.21 - Knowledge of the parameters 4.6 1 Heat Transfer / 4 and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

000054 Loss of Main Feedwater / 4 X 2.1.28 - Knowledge of the purpose and 4.1 1 function of major system components and controls.

000056 Loss of Off-site Power / 6 X 2.4.4 - Ability to recognize abnormal 4.7 1 indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

000062 Loss of Nuclear Svc Water / 4 X AA2.04 - The normal values and upper 2.9* 1 limits for the temperatures of the components cooled by SWS W/E04 LOCA Outside Containment / 3 X EA2.1 - Facility conditions and 4.3 1 selection of appropriate procedures during abnormal and emergency operations K/A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 07/28/2014 11:23:32 am 1

PWR SRO Examination Outline Printed: 07/28/2014 Facility: DCPP ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KA Topic Imp. Points 000037 Steam Generator Tube Leak / 3 X AA2.09 - System status, using 3.4* 1 independent readings from redundant Condensate air ejector exhaust monitor 000069 Loss of CTMT Integrity / 5 X 2.2.25 - Knowledge of the bases in 4.2 1 Technical Specifications for limiting conditions for operations and safety limits.

W/E03 LOCA Cooldown - Depress. / 4 X 2.4.18 - Knowledge of the specific 4.0 1 bases for EOPs.

W/E10 Natural Circ. / 4 X EA2.2 - Adherence to appropriate 3.9 1 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 07/28/2014 11:23:39 am 1

PWR SRO Examination Outline Printed: 07/28/2014 Facility: DCPP ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 003 Reactor Coolant Pump X A2.01 - Problems with RCP 3.9 1 seals, especially rates of seal leak-off 004 Chemical and Volume Control X A2.03 - Boundary isolation 4.2 1 valve leak 010 Pressurizer Pressure Control X 2.4.47 - Ability to diagnose 4.2 1 and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

013 Engineered Safety Features X A2.01 - LOCA 4.8 1 Actuation 073 Process Radiation Monitoring X 2.4.30 - Knowledge of 4.1 1 events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 07/28/2014 11:23:46 am 1

PWR SRO Examination Outline Printed: 07/28/2014 Facility: DCPP ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KA Topic Imp. Points 034 Fuel Handling Equipment X A2.01 - Dropped fuel 4.4 1 element 041 Steam Dump/Turbine Bypass X 2.3.14 - Knowledge of 3.8 1 Control radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

068 Liquid Radwaste X A2.04 - Failure of automatic 3.3 1 isolation K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 07/28/2014 11:23:52 am 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 07/28/2014 Facility: DCPP Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.2 Knowledge of operator responsibilities during all 4.4 1 modes of plant operation.

2.1.29 Knowledge of how to conduct system lineups, 4.0 1 such as valves, breakers, switches, etc.

Category Total: 2 Equipment Control 2.2.6 Knowledge of the process for making changes to 3.6 1 procedures.

2.2.14 Knowledge of the process for controlling 4.3 1 equipment configuration or status.

Category Total: 2 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.7 1 normal or emergency conditions.

2.3.11 Ability to control radiation releases. 4.3 1 Category Total: 2 Emergency Procedures/Plan 2.4.12 Knowledge of general operating crew 4.3 1 responsibilities during emergency operations.

Category Total: 1 Generic Total: 7 07/28/2014 11:23:58 am 1

ES-401 SRO - Record of Rejected K/As Form ES-401-4 Tier / Group Randomly Selected K/A Reason for Rejection T1/G1 APE027 AA2.17 KA statement states: Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: Allowable RCS temperature difference vs. reactor power No plausible tie to PWR design to test PPC malfunction to temperature/reactor power difference.

Randomly replaced with APE 040 G2.4.21 T1/G1 APE065 G2.4.31 Knowledge of annunciators alarms and alarm respone procedures as they apply to IA malfunctions is RO knowledge. Not able to write to SRO level.

Randomly replaced with APE056 G2.4.4 T1/G2 APE003 G2.1.30 Ability to operate controls is RO knowledge.

Randomly replaced with E10 EA2.2 T1/G2 APE059 AA2.05 Similar KA tested in level 2 (068 A2.04)

Randomly replaced with E03 G2.4.18 T2/G1 003G2.4.31 Knowledge of alarm response for RCP is RO knowledge.

Randomly replaced with 073 G2.4.30 T2/G1 004A2.15 RO knowledge, unable to write to SRO level Randomly replaced with 004 A2.03 T2/G2 033 G2.4.50 Alarm response and operation of controls is RO knowledge.

Randomly replaced with 041 G2.3.14 T1/G1 059 A2.12 Unable to write question to SRO level.

Randomly replaced with 003 A2.01

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Diablo Canyon Date of Examination: 08/11/2014 Examination Level: RO SRO Operating Test Number: L121 Administrative Topic Type Describe activity to be performed (See Note) Code*

Determine Ultimate Heat Sink Temperature Conduct of Operations 2.1.23 Ability to perform specific system and integrated plant M, R procedures during all modes of operation (NRCL121-A1) (4.3)

(modified from bank LJACO-02R)

Determine Boration/Dilution Req for Power Rise Conduct of Operations 2.1.25 Ability to interpret reference materials, such as graphs, M, R curves, tables, etc.

(NRCL121-A2) (3.9)

(modified from L081 NRC ADMRO1)

Perform Outage Safety Checklist Equipment Control 2.2.37 Ability to determine operability and/or availability of D, R safety related equipment.

(NRCL121-A3) (3.6)

(bank: LJAEC-01R ; previously used in L061C NRC ADM02)

Review Liquid Radwaste Discharge Checklist Radiation Control 2.3.11 Ability to control radiation releases.

M, R (3.8)

(NRCL121-A4) (modified from L061C NRC ADM04)

Emergency Procedures/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 5 are required.

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

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

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

ES 301, Page 22 of 27 Rev 0 Rev 0: Initial Submittal

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Diablo Canyon Date of Examination: 08/11/2014 Examination Level: RO SRO Operating Test Number: L121 Administrative Topic Type Describe activity to be performed (See Note) Code*

Verify Determination of Ultimate Heat Sink Temp Conduct of Operations 2.1.23 Ability to perform specific system and integrated plant M, R procedures during all modes of operation (NRCL121-A5) (4.4)

(modified from LJACO-02S)

Determine Boration/Dilution Req for Power Rise Conduct of Operations 2.1.25 Ability to interpret reference materials, such as graphs, M, R curves, tables, etc.

(NRCL121-A6) (4.2)

(modified from L081 NRC ADMRO1)

Verify Outage Safety Checklist Equipment Control 2.2.37 Ability to determine operability and/or availability of M, R safety related equipment.

(NRCL121-A7) (4.6)

(modified from bank LJAEC-01R ; previously used in L061C NRC ADM02)

Review Liquid Radwaste Discharge Checklist Radiation Control 2.3.11 Ability to control radiation releases.

M, R (4.3)

(NRCL121-A8) (modified from L061C NRC ADM04)

Classification of a FH Accident in Containment Emergency Procedures/Plan 2.4.41 Knowledge of the emergency action level thresholds D, R and classifications.

(NRCL121-A9) (4.6)

(direct from bank - LJE-017)

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

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

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

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

ES 301, Page 22 of 27 Rev 0 Rev 0: Initial Submittal

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Diablo Canyon Date of Examination: 08/11/2014 Exam Level: RO SRO-I SRO-U Operating Test Number: L121 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. (S1) (001.A2.03) Verify Misaligned Rod Is Not Stuck (LJC-066) D,S 1
b. (S2) (013.A4.01) Manually Isolate Phase A Components (LJC-026) A,D,EN,L,S 2
c. (S3) (055.EA1.07) Energize Vital Busses From 230 KV System A,L,N,S 6
d. (S4) (022.A4.01) Respond to High CFCU Vibration A,N,S 5
e. (S5) (073.A4.01) Respond to High Radiation on RE-17A/B N,S 7
f. (S6) (002.A4.02) Initiate a Nat Cir Cooldown (LJC-046) M,L,S 4P
g. (S7) (059.A2.07) Perform Immediate Actions for MFW Pump Trip A,M,S 4S (NRCLJC051051)
h. (S8) (006.A4.05) Align RHR for Hot Leg Recirc (NRCL081LJC-S3) A,L,D,S 3 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. (P1) (067.AA1.08) Manually Operate the Cardox System (LJP-138A) A,D,E 8
j. (P2) (068.AA1.21) Align 480V Bus G for Control from HSDP (LJP-007) D,E,L 6
k. (P3) (061.A2.04) Align Alternate AFW from the FWST (LJP-104A) D,E,L,R 4S

@ 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 ES-301, Page 23 of 27 Rev 2 Rev 2: Revs follow initial submittal

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Diablo Canyon Date of Examination: 08/11/2014 Exam Level: RO SRO-I SRO-U Operating Test Number: L121 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. (S1) (001.A2.03) Verify Misaligned Rod Is Not Stuck (LJC-006) D,S 1
b. (S2) (013.A4.01) Manually Isolate Phase A Components (LJC-026) A,D,EN,L,S 2
c. (S3) (055.EA1.07) Energize Vital Busses From 230 KV System A,L,N,S 6
d. (S4) (022.A4.01) Respond to High CFCU Vibration A,N,S 5
e. (S5) (073.A4.01) Respond to High Radiation on RE-17A/B N,S 7 f.
g. (S7) (059.A2.07) Perform Immediate Actions for MFW Pump Trip A,M,S 4S (NRCLJC051051)
h. (S8) (006.A4.05) Align RHR for Hot Leg Recirc (NRCL081LJC-S3) A,L,D,S 3 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. (P1) (067.AA1.08) Manually Operate the Cardox System (LJP-138A) A,D,E 8
j. (P2) (068.AA1.21) Align 480V Bus G for Control from HSDP (LJP-007) D,E,L 6
k. (P3) (061.A2.04) Align Alternate AFW from the FWST (LJP-104A) D,E,L,R 4S

@ 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 ES-301, Page 23 of 27 Rev 1 Rev 1: Revs follow initial submittal

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Diablo Canyon Date of Examination: 08/11/2014 Exam Level: RO SRO-I SRO-U Operating Test Number: L121 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function a.

b. (S2) (013.A4.01) Manually Isolate Phase A Components (LJC-026) A,D,EN,L,S 2
c. (S3) (055.EA1.07) Energize Vital Busses From 230 KV System A,L,N,S 6 d.
e. (S5) (073.A4.01) Respond to High Radiation on RE-17A/B N,S 7 f.

g.

h.

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

i. (P1) (067.AA1.08) Manually Operate the Cardox System (LJP-138A) A,D,E 8 j.
k. (P3) (061.A2.04) Align Alternate AFW from the FWST (LJP-104A) D,E,L,R 4S

@ 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 ES-301, Page 23 of 27 Rev 1 Rev 1: Rev follows initial submittal

Appendix D (rev 9) Required Operator Actions Form ES-D-1 Facility: Diablo Canyon (PWR) Scenario No: 1 Op-Test No: L121 NRC Examiners: Operators:

Initial Conditions: 10E-8 with AFW in service, MOL, 1660 ppm boron Turnover: At OP L-2, step 6.1.25, ready to raise power to 2%. Continue to raise power, and stabilize at 2%.

Event Malf Event Event No No. Type* Description 1 N/A R(ATC) Raise reactor power from 10E-8 to 2% per OP L-2, sec 6.1 2 XMT_RCS6_3 SRO PT-403, RCS Wide Range Pressure Transmitter, fails low (TS 3.3.3.A, ECG 7.8) (Used for SRO TS/ECG Only) 3 PMP_CCW2_MTRF C (BOP, Component Cooling Water Pump 1-2 (CCW Pp 1-2) overcurrent trip.

SRO) (AP-11; TS 3.7.7.A) 4 PMP_TUR2 C (BOP, Thermal overload of AC Bearing Oil Pump (AP-29).

OVERLOAD_DEV_FAIL SRO) 5 XMT_MSS1_3 I (SRO, PT-507, Steam Generator Header Pressure Transmitter, slow failure low ATC) causing Group I dumps to close. (AP-5) 6 MAL_RCS3A 0.06 C (ALL) RCS leak ramps in over 1 minute. Leak is within the capacity of charging (60 gpm), but requires second pump to be started. (AP-1, TS 3.4.13.A) 7 MAL_RCS3A 0.75 M (ALL) 700 gpm SBLOCA requiring Safety Injection (SI) - (Auto SI failed; manual SI is required CT).

8 MAL_PPL5A/B M (ALL) ATWS, Both manual trip and 13D/E fail.

9 PMP_CVC1 C (BOP) On SI, running CCPs trip on OC, standby pump fail to autostart - CT )

PMP_CVC2

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L121 NRC ES-D-1-01 r2.doc Page 1 of 3 Rev 2

Appendix D (rev 9) Required Operator Actions Form ES-D-1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES301-4) Actual Attributes

1. Total malfunctions (5-8) (Events 2,3,4,5,6,7,8,9) 8
2. Malfunctions after EOP entry (1-2) (Events 8&9) 2
3. Abnormal events (2-4) (AP-11,29,5,1) 4
4. Major transients (1-2) (Events 7&8) 2
5. EOPs entered/requiring substantive actions (1-2) (E-1) 1
6. EOP contingencies requiring substantive actions (0-2) (FR-S.1) 1
7. Critical tasks (2-3)(See Scenario Summary) 2 L121 NRC ES-D-1-01 r2.doc Page 2 of 3 Rev 2

SCENARIO

SUMMARY

- NRC #1

1. Control rods are used to raise power from 10E-8 Amps (IR) to 2% per OP L-2, Hot Standby to Startup Mode, step 6.1.25.
2. PT-403, RCS Wide Range Pressure Transmitter, fails low. Crew responds to PK05-07, Subcooling Margin Lo/Lo-Lo and PK05-09, RVLIS Lo Lvl RVLIS/SCMM Trouble and identifies affected instrumentation. Shift Foreman addresses TS 3.3.3.A, Post Accident Monitoring Instrumentation and ECG 7.8, Accident Monitoring Instrumentation.
3. Component Cooling Water Pump CCW 1-2 trips on overcurrent and CCW 1-3 must be started manually (auto-start blocked) per direction in PK01-09 or as directed by OP AP-11, Malfunction of Component Cooling Water System, Section A. T.S. 3.7.7, Vital Component Cooling Water (CCW) System, is entered for one loop of CCW inoperable.
4. AC Lube Oil Pump trips on thermal overload. Crew responds to PK12-16, Turbine Lube Oil System and is directed to OP AP-29, Main Turbine Malfunction to start the DC Backup Pump (autostart failed).
5. PT-507, Steam Generator Header Pressure Transmitter, slowly fails low causing Group I dumps to close.

Crew diagnoses the failure and takes manual control of Hand Controller HC-507. OP AP-5, Malfunction of Eagle 21 Protection or Control Channel is used to address the failure and return primary and secondary to normal bands.

6. 60 gpm RCS leak develops on Loop 1, ramping in over 1 minute. Crew evaluates plant symptoms and enters OP AP-1, Excessive Reactor Coolant System Leakage, which directs starting of a second charging pump to maintain pressurizer level. Shift Foreman enters T.S. 3.4.13.A, RCS Operational Leakage based on the estimated leak size.
7. 700 gpm SBLOCA on Loop 1 cold leg. Auto Safety Injection (SI) fails to actuate, requiring manual SI (Critical Task E-0D: Manually initiate Safety Injection before transitioning to any E-1, E-2, or E-3 series procedure)**.
8. Crews attempt to trip reactor from the control room is unsuccessful. Shift Foreman enters EOP E-0 (Reactor Trip or Safety Injection) and transitions to EOP FR-S.1, Response to Nuclear Power Generation

/ ATWS.

9. On SI, running CCPs trip on overcurrent. Remaining ECCS CCP fails to autostart, but can be started manually. (Critical Task E-0I: Establish flow from at least one high-head ECCS pump before transition out of E-0)**.
10. After addressing ATWS condition, crew transitions through E-0 (Reactor Trip or Safety Injection) and E-1 (Loss of Reactor or Secondary Coolant) to E-1.2 (Post LOCA Cooldown and Depressurization).

The scenario is terminated at entry into E-1.2, Post LOCA Cooldown and Depressurization.

L121 NRC ES-D-1-01 r2.doc Page 3 of 3 Rev 2

Appendix D (rev 9) Required Operator Actions Form ESD1 Facility: Diablo Canyon (PWR) Scenario No.: 3 OpTest No.: L121NRC Examiners: Operators:

Initial Conditions: 75%, MOL, 1014 ppm boron Turnover: Bus H Work Week: AFW 12 OOS, D/G 11 OOS Maintenance in progress on PCV20.

CCP 11 In Service.

Event Malf Event Event No No. Type* Description 1 MAL_NIS6D 200 (ramp I (ALL) NI44, Power Range Nuclear Instrument, slowly fails high causing in slowly) unwarranted rod motion (TS 3.3.1.D, E,S,T; ECGs 37.2, 37.3) (AP 5) 2 PMP_CND2 C (SRO, Condensate Booster Pump 13 Trips on overcurrent. Standby fails BLOCK_AUTO_STRT BOP) to autostart (AP15).

PMP_CND3_MTRF 15.0 3 MAL_RCS4F 35 delay=0 C (ALL) 35 gpm tube leak ramps in over 2 minutes on S/G 12, requiring ramp=120 R (ATC) power reduction. (TS 3.4.15.A) (AP3) 4 MAL_CWS2C 1.3 C (SRO, Condenser inleakage in SW quadrant requiring 25 MW/min ramp delay=0 ramp=2 BOP) (AP20) 5 MAL_RCS4F 400 M (ALL) S/G 12 ruptures (400 gpm) requiring Safety Injection.

delay=0 ramp=120 6 VLV_SIS3_1 1 C (BOP) Charging Injection Outlet Valves 8801A/B fail to open on SI, VLV_SIS4_1 1 requiring manual opening to establish high head ECCS injection (CT) 7 insert MAL_MSS1B M (ALL) Main Steam Line Break on S/G 12 inside containment 3500000.0 cd='fnispr lt downstream of flow restrictor on Rx Trip resulting in 5.0' delay=0 ramp=60 faulted/ruptured S/G (CT) 8 insert VLV_MSS7_2 1.0 C (BOP) Main Steam Isolation Valves s on leads 1 & 2 fail to close in auto, insert VLV_MSS8_2 1.0 but can be closed manually delIA VLV_MSS7_2 2 delIA VLV_MSS8_2 2

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor L121 NRC ESD103 r2.doc Page 1 of 3 Rev 2

Appendix D (rev 9) Required Operator Actions Form ESD1 Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES3014) Actual Attributes

1. Total malfunctions (5-8) (Events 1,2,3,4,5,6,7,8) 8
2. Malfunctions after EOP entry (1-2) (Events 6,8) 2
3. Abnormal events (2-4) (AP5, AP15, AP3, AP20) 4
4. Major transients (1-2) (Event 5,7) 2
5. EOPs entered/requiring substantive actions (1-2) (E2, E3) 2
6. EOP contingencies requiring substantive actions (0-2) (terminate @ ECA3.1 entry) 0
7. Critical tasks (2-3) (See Scenario Summary) 2 L121 NRC ESD103 r2.doc Page 2 of 3 Rev 2

SCENARIO

SUMMARY

- NRC #3

1. Power Range Nuclear Instrument NI44 slowly fails high causing inward rod motion. Crew diagnoses failure, and once motion is deemed unwarranted, takes rods to manual. Failure is addressed per OP AP5, Malfunction of Eagle 21 Protection or Control Channel, which removes the failed channel from service and directs the Shift Foreman to address Tech Specs 3.3.1.D,E,S,T Reactor Trip System Instrumentation; ECG 37.2 Axial Flux Difference (AFD) monitoring, and ECG 3.73 (Quadrant Power Tilt Ratio Alarms).
2. Condensate Booster Pump 13 trips and standby pump fails to autostart. Crew responds by manually starting standby pump and following guidance of OP AP15, Loss of Feedwater Flow.
3. S/G 12 develops a 35 gpm tube leak over a two minute period. Crew determines leak rate and enters OP AP3, Steam Generator Tube Failure. Leak is also evaluated per OP O4, Primary to Secondary Steam Generator Tube Leak Detection, which directs crew to reduce power by 50% in the next hour and be in Mode 3 within two hours. Shift Foreman determines TS 3.4.13.A, RCS Operations Leakage applies.
4. A saltwater leak develops in the SW quadrant of the condenser, requiring the crew to raise the ramp rate to 25 MW/min per OP AP20, Condenser Tube Leak.
5. S/G 12 ruptures during ramp, requiring crew to initiate a Safety Injection and enter EOP E0, Reactor Trip or Safety Injection.
6. On the SI, two of the charging injection isolation valves fail to open, but are opened manually in order to supply highhead ECCS injection. (Critical Task E0D: Establish high head ECCS flow prior to exiting EOP E0) **
7. On the Reactor Trip, a Main Steam Line Break occurs on S/G 12 inside containment, downstream of the flow restrictor, resulting in a faulted/ruptured condition. The S/G will be isolated per EOP E2, Faulted S/G Isolation (Critical Task E2A: Isolation of Faulted S/G initiated before transition out of EOP E2) **
8. Main Steam Isolation Valves on steam leads 1 and 2 fail to isolate and are closed manually by the crew. The crew will continue to mitigate the casualty following the guidance of EOP E3, Steam Generator Tube Rupture, and transition to EOP ECA3.1, SGTR with Loss of Reactor Coolant -

Subcooled Recovery Desired.

The scenario is terminated once crew transitions to ECA 3.1, SGTR with Loss of Reactor Coolant - Subcooled Recovery.

L121 NRC ESD103 r2.doc Page 3 of 3 Rev 2

Appendix D (rev 9) Required Operator Actions Form ESD1 Facility: Diablo Canyon (PWR) Scenario No.: 4 OpTest No.: L121NRC Examiners: Operators:

Initial Conditions: 100%, MOL, 961 ppm boron Turnover: Bus H Work Week: AFW 12 OOS, D/G 11 OOS Maintenance in progress on PCV20.

CCP 11 In Service.

Event Malf Event Type* Event No No. Description 1 XMT_CVC20_3 I (SRO, BOP) VCT level transmitter LT114 gradually fails high causing letdown flow to divert to the LHUTs. Automakeup commences when actual level falls to 14% (AP19);

2 MAL_SEI1 .15 delay=0 ramp=5 C (SRO, BOP) Pressurizer Pressure Control Valve PCV456 slowly drifts VLV_PZR5_2 0.25 delay=0 open following small seismic and can not be closed.

ramp=5 Associated block valve is closed to isolate the PORV (AP13)

(TS 3.4.11.B, CT) 3 R(ALL) Call from Grid Control Center for Unit 1 backdown order to shed 350 MW within 10 minutes due to grid disturbance (AP25) 4 MAL_ROD3A_ROD B10 C (ALL) Dropped rod and urgent failure at 855 MW inhibits auto rod MAL_ROD3A STATIONARY motion and requires rods to be taken to manual (AP12C)

(TS 3.1.4.B).

5 MAL_SEI1 .17 delay=0 ramp=6 M (ALL) Second seismic results in full load rejection. Rods are still in MAL_SYD3 56 delay=3 manual and crew must trip Rx based on first step of AP2.

ramp=30 6 MAL_SEI1 .3 delay=0 ramp=6 C(SRO, BOP) Loss of Startup immediately following Rx Trip. D/G 13 fails MAL_SYD2 0 to auto start but can be manually started.

7 MAL_RCS1D 50%_dba M (ALL) Strong aftershock results in LBLOCA. ECCS Charging pumps MTRF 15 cd='jpplsia or jpplsib' and Safety Injection Pump 11 trip on overcurrent reducing the amount of high head injection.

PMP_SIS1_MTRF 15.0 cd='jpplsia or jpplsib' 8 PMP_RHR1 BLOCK_AUTO_STRT C (BOP) Residual Heat Removal Pump 11 and Containment Spray PMP_CSS1 BLOCK_AUTO_STRT Pump 11 fail to autostart, but may be manually started (CTs).

L121 NRC ESD104 r2.doc Page 1 of 3 Rev 2

Appendix D (rev 9) Required Operator Actions Form ESD1

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) (from form ES3014) Actual Attributes
1. Total malfunctions (5-8) (Events 1,2,4,5,6,7,8) 7
2. Malfunctions after EOP entry (1-2) (Events 6,7,8) 3
3. Abnormal events (2-4) (AP19, AP25, AP12C, AP2) 4
4. Major transients (1-2) (Events 5&7) 2
5. EOPs entered/requiring substantive actions (1-2) (E0.1, E1) 2
6. EOP contingencies requiring substantive actions (0-2) (ECA0.3) 1
7. Critical tasks (2-3)(See Scenario Summary) 3 L121 NRC ESD104 r2.doc Page 2 of 3 Rev 2

SCENARIO

SUMMARY

- NRC #4

1. Volume Control Tank (VCT) level channel LT114 fails high, causing letdown to divert to the LHUTs.

Automatic reactor makeup will maintain VCT level above 14%. The crew diagnoses the level channel failure by comparing other VCT parameters, and addresses issue following OP AP19, Malfunction of the Reactor Makeup Control System guidance. LCV112A control is set to the VCT position.

2. Small seismic causes Pressurizer Pressure Control Valve PCV456 to slowly drift open and must be isolated using the associated 8000C block valve. Shift Forman enters TS 3.4.11.B Pressurizer Power Operated Relief Valves (PORVs). (Critical Task: Isolate PORV prior to pressurizer pressure lowering to 1950 psig (low pressurizer pressure Rx trip setpoint)).
3. Grid Control Center (GCC) calls with a backdown order for DCPP due to grid disturbance. Shift Manager directs Unit 1 to shed 350 MW in the next 10 minutes. Crew commences ramp using guidance of OP AP 25, Rapid Load Reduction or Shutdown to reduce load.
4. At 855 MW, a Rod Control Urgent Failure occurs and rod B10 is drops. Crew places rod control in manual and enters OP AP12C, Dropped Control Rod. Turbine is used to return Tave to Tref. Shift Foreman enters TS 3.1.4.B Rod Group Alignments.
5. A large seismic event occurs, resulting in a 500kV grid instability/underfrequency condition. Unit separates from the grid. Crew enters OP AP2, Full Load Rejection, and trips the reactors based on unavailability of auto rod control.
6. Crew enters E0, Reactor Trip or Safety Injection, and transitions into E0.1, Reactor Trip Response to stabilize the plant. Startup power is lost and D/G 13 fails to autostart due to a shutdown relay, reducing vital 4kV power to a single bus (D/G 11 out of service from initial conditions). ECA0.3, Restore 4kV Buses is implemented in parallel with E0.1. D/G 13 shutdown relay is reset from the control room and the diesel started in manual.
7. A large aftershock occurs resulting in a LBLOCA. ECCS CCPs (High Head Injection) and SIP 11 (Intermediate Head Injection) all trip on overcurrent. Crew reenters E0, Reactor Trip or Safety Injection, and transitions to E1, Loss of Reactor or Secondary Coolant.
8. RHRP 11 (Low Head Injection) and CSP 11 (Containment Spray) fail to autostart, but may be manually started (Critical Task E0H: Manually start at least one low head ECCS pump before transition out of E0 and Critical Task E0E: Manually actuate at least the minimum required complement of containment cooling equipment before an extreme (redpath) challenge develops to the containment critical safety function.)

The scenario is terminated once crew has completed actions of EOP E1 and is waiting to transition to Cold Leg Recirc.

L121 NRC ESD104 r2.doc Page 3 of 3 Rev 2

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