ML121080577

PVNGS-2012-03-FINAL-Outlines

ML121080577
Person / Time
Site:	Palo Verde
Issue date:	03/16/2012
From:	Division of Reactor Safety IV
To:	Arizona Public Service Co
References
Download: ML121080577 (29)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Palo Verde REV 1 Date Of Exam: 03/16/2012 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 2 3 4 3 3 3 18 0 0 0 Emergency 2 2 2 2 N/A 2 1 0 9 0 0 0

& N/A Abnormal Tier Plant Totals 4 5 6 5 4 3 27 0 0 0 Evolutions 1 3 2 3 4 2 2 4 2 2 2 2 28 0 0 0 2.

2 1 1 1 1 1 1 2 0 1 1 0 10 0 0 0 0 Plant Systems Tier 0 0 0 4 3 4 5 3 3 6 2 3 3 2 38 Totals 1 2 3 4 1 2 3 4

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

REV 1

PWR RO Examination Outline REV 1 Facility: Palo Verde 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 000007 Reactor Trip - Stabilization - X EA2.03 - Reactor trip breaker position 4.2 1 Recovery / 1 000008 Pressurizer Vapor Space Accident / X AK2.01 - Valves 2.7* 1 3

000009 Small Break LOCA / 3 X EK3.28 - Manual ESFAS initiation 4.5 1 requirements 000011 Large Break LOCA / 3 X EK2.02 - Pumps 2.6* 1 000022 Loss of Rx Coolant Makeup / 2 X AK3.02 - Actions contained in SOPs 3.5 1 and EOPs for RCPs, loss of makeup, loss of charging, and abnormal charging 000025 Loss of RHR System / 4 X AA2.07 - Pump cavitation 3.4 1 000026 Loss of Component Cooling Water / X AK3.03 - Guidance actions contained in 4.0 1 8 EOP for Loss of CCW 000027 Pressurizer Pressure Control System X 2.4.45 - Ability to prioritize and 4.1 1 Malfunction / 3 interpret the significance of each annunciator or alarm.

000029 ATWS / 1 X EK1.03 - Effects of boron on reactivity 3.6 1 000038 Steam Gen. Tube Rupture / 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.

000055 Station Blackout / 6 X EK3.01 - Length of time for which 2.7 1 battery capacity is designed 000056 Loss of Off-site Power / 6 X AA2.17 - Operational status of PZR 3.4 1 backup heaters 000057 Loss of Vital AC Inst. Bus / 6 X 2.4.50 - Ability to verify system alarm 4.2 1 setpoints and operate controls identified in the alarm response manual.

000058 Loss of DC Power / 6 X AK1.01 -Battery charger equipment 2.8 1 and instrumentation 000065 Loss of Instrument Air / 8 X AA1.03 - Restoration of systems served 2.9 1 by instrument air when pressure is regained 000077 Generator Voltage and Electric Grid X AA1.05 - Engineered safety features 3.9 1 Disturbances / 6 CE/E05 Steam Line Rupture - Excessive X EK2.2 - Facility's heat removal systems, 3.7 1 Heat Transfer / 4 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 REV 1

PWR RO Examination Outline REV 1 Facility: Palo Verde 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 CE/E06 Loss of Main Feedwater / 4 X EA1.2 - Operating behavior 3.4 1 characteristics of the facility K/A Category Totals: 2 3 4 3 3 3 Group Point Total: 18 REV 1

PWR RO Examination Outline REV 1 Facility: Palo Verde 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 000001 Continuous Rod Withdrawal / 1 X AA1.07 - RPI 3.3 1 000005 Inoperable/Stuck Control Rod / 1 X AK3.06 - Actions contained in EOP for 3.9 1 inoperable/stuck control rod 000028 Pressurizer Level Malfunction / 2 X AK1.01 - PZR reference leak 2.8* 1 abnormalities 000060 Accidental Gaseous Radwaste Rel. / X AK2.01 - ARM system, including the 2.6 1 9 normal radiation-level indications and the operability status 000068 Control Room Evac. / 8 X AK2.02 - Reactor trip system 3.7 1 000069 Loss of CTMT Integrity / 5 X AA2.01 - Loss of containment integrity 3.7 1 CE/A13 Natural Circ. / 4 X AK1.2 - Normal, abnormal and 3.2 1 emergency operating procedures associated with (Natural Circulation Operations)

CE/A16 Excess RCS Leakage / 2 X AK3.3 - Manipulation of controls 3.3 1 required to obtain desired operating results during abnormal, and emergency situations CE/E09 Functional Recovery X EA1.1 - Components, and functions of 4.2 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features K/A Category Totals: 2 2 2 2 1 0 Group Point Total: 9 REV 1

PWR RO Examination Outline REV 1 Facility: Palo Verde 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 A1.05 - RCS flow 3.4 1 003 Reactor Coolant Pump X K6.04 - Containment 2.8 1 isolation valves affecting RCP operation 004 Chemical and Volume Control X K1.04 - RCPS, including 3.4 1 seal injection flows 005 Residual Heat Removal X K5.03 - Reactivity effects of 2.9* 1 RHR fill water 005 Residual Heat Removal X K3.07 - Refueling 3.2* 1 operations 006 Emergency Core Cooling X K1.03 - RCS 4.2 1 007 Pressurizer Relief /Quench X A2.05 - Exceeding PRT 3.2 1 Tank high-pressure limits 008 Component Cooling Water X K2.02 - CCW pump, 3.0* 1 including emergency backup 010 Pressurizer Pressure Control X K5.01 -Determination of 3.5 1 condition of fluid in PZR, using steam tables 012 Reactor Protection X A4.04 - Bistable, trips, reset 3.3* 1 and test switches 012 Reactor Protection X K4.06 - Automatic or 3.2 1 manual enable/disable of RPS trips 013 Engineered Safety Features X K4.03 - Main Steam 3.9 1 Actuation Isolation System 022 Containment Cooling X A4.01 - CCS fans 3.6 1 026 Containment Spray X A3.01 - Pump starts and 4.3 1 correct MOV positioning 039 Main and Reheat Steam X K3.03 - AFW pumps 3.2* 1 059 Main Feedwater X A1.03 - Power level 2.7* 1 restrictions for operation of MFW pumps and valves 061 Auxiliary/Emergency X K4.02 - AFW automatic 4.5 1 Feedwater start upon loss of MFW pump, S/G level, blackout, or safety injection 062 AC Electrical Distribution X K4.03 - Interlocks between 2.8* 1 automatic bus transfer and breakers 062 AC Electrical Distribution X A3.01 - Vital ac bus 3.0 1 amperage 063 DC Electrical Distribution X 2.1.27 - Knowledge of 3.9 1 system purpose and/or function.

063 DC Electrical Distribution X K2.01 - Major DC loads 2.9* 1 064 Emergency Diesel Generator X A1.08 - Maintaining 3.1 1 minimum load on ED/G (to REV 1

PWR RO Examination Outline REV 1 Facility: Palo Verde 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 prevent reverse power) 064 Emergency Diesel Generator X K6.07 - Air receivers 2.7 1 073 Process Radiation Monitoring X 2.2.39 - Knowledge of less 3.9 1 than or equal to one hour Technical Specification action statements for systems.

076 Service Water X A2.01 - Loss of SWS 3.5* 1 076 Service Water X K1.19 - SWS emergency 3.6* 1 heat loads 078 Instrument Air X K3.02 - Systems having 3.4 1 pneumatic valves and controls 103 Containment X A1.01 -Containment 3.7 1 pressure, temperature, and humidity K/A Category Totals: 3 2 3 4 2 2 4 2 2 2 2 Group Point Total: 28 REV 1

PWR RO Examination Outline REV 1 Facility: Palo Verde 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 001 Control Rod Drive X A4.03 - CRDS mode control 4.0 1 002 Reactor Coolant X K3.03 - Containment 4.2 1 016 Non-nuclear Instrumentation X A3.01 - Automatic selection 2.9* 1 of NNIS inputs to control systems 017 In-core Temperature Monitor X K1.01 - Plant computer 3.2* 1 028 Hydrogen Recombiner and X A1.02 - Containment 3.4* 1 Purge Control pressure 029 Containment Purge X A1.03 - Containment 3.0* 1 pressure, temperature, and humidity 033 Spent Fuel Pool Cooling X K4.01 -Maintenance of 2.9 1 spent fuel level 041 Steam Dump/Turbine Bypass X K6.03 - Controller and 2.7 1 Control positioners, including ICS, S/G, CRDS 072 Area Radiation Monitoring X K5.01 -Radiation theory, 2.7 1 including sources, types, units, and effects 075 Circulating Water X K2.03 - Emergency/essential 2.6* 1 SWS pumps K/A Category Totals: 1 1 1 1 1 1 2 0 1 1 0 Group Point Total: 10 REV 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline REV 1 Facility: Palo Verde Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.26 Knowledge of industrial safety procedures (such 3.4 1 as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

2.1.37 Knowledge of procedures, guidelines, or 4.3 1 limitations associated with reactivity management.

Category Total: 2 Equipment Control 2.2.14 Knowledge of the process for controlling 3.9 1 equipment configuration or status.

2.2.15 Ability to determine the expected plant 3.9 1 configuration using design and configuration control documentation, such as drawings, line-ups, tagouts, etc.

2.2.44 Ability to interpret control room indications to 4.2 1 verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Category Total: 3 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.2 1 normal or emergency conditions.

2.3.5 Ability to use radiation monitoring systems, such 2.9 1 as fixed radiation monitors and alarms, portable survey instruments, personal monitoring equipment, etc.

Category Total: 2 Emergency Procedures/Plan 2.4.5 Knowledge of the organization of the operating 3.7 1 procedures network for normal, abnormal, and emergency evolutions.

2.4.16 Knowledge of EOP implementation hierarchy and 3.5 1 coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

2.4.31 Knowledge of annunciator alarms, indications, or 4.2 1 response procedures.

Category Total: 3 Generic Total: 10 REV 1

Rev 1 PVNGS License Examination Record of Rejected K/As Exam Date 03/16/12 PVNGS Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/As RO Exam 1/1 4.2 015/017 Unable to write RO question. 4.2 077 AA1.05 AK1.01 1/1 4.2 022 AK3.01 No PVNGS application. 4.2 022 AK3.02 1/1 4.2 025 AA1.04 Oversampled on the RO and SRO exams. 4.2 025 AA2.07 1/1 4.2 026 AA2.02 Oversampled on the RO exam. 4.2 026 AK3.03 1/2 4.2 024 AK1.02 Similar to another Question on RO exam. 4.2 028 AK1.01 1/2 4.4 A11 AK3.1 This is SRO Knowledge. 4.4 A16 AK3.3 2/1 3.4 003 A2.05 No PVNGS Application. 3.4 003 A1.05 2/1 3.7 012 K4.09 Unable to write RO question. 3.7 012 K4.06 2/1 3.2 013 K5.01 This is NLO Knowledge. 3.2 013 K4.03 2/1 3.4 061 K5.03 This is NLO Knowledge. 3.4 005 K5.03 2/1 3.4 061 K3.02 Similar to another question on RO exam. 3.4 061 K4.02 2/1 2.1.32 Similar to another question on RO exam. 2.1.27 2/1 3.8 078 K4.01 Similar to another question on SRO exam. 3.8 078 K3.02 2/2 3.1 001 A4.01 Similar to another question on RO Exam. 3.1 001 A4.03 2/2 3.5 029 A2.03 Unable to write RO question. 3.5 029 A1.03 3 2.2.15 Unable to write RO question. 2.2.35 3 2.2.44 Could not write a generic question. 2.2.12 3 2.4.45 Similar to another question on RO Exam. 2.4.5 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Facility: Palo Verde REV 1 Date Of Exam: 03/16/2012 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 4 2 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 6 4 10 Evolutions 1 0 0 0 0 0 0 0 0 0 0 0 0 4 1 5 2.

2 0 0 0 0 0 0 0 0 0 0 0 0 0 2 1 3 Plant Systems Tier 6 2 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 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.

REV 1

PWR SRO Examination Outline REV 1 Facility: Palo Verde 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

000011 Large Break LOCA / 3 X 2.4.41 - Knowledge of the emergency 4.6 1 action level thresholds and classifications.

000025 Loss of RHR System / 4 X 2.4.6 - Knowledge of EOP mitigation 4.7 1 strategies.

000038 Steam Gen. Tube Rupture / 3 X EA2.15 - Pressure at which to maintain 4.4 1 RCS during S/G cooldown 000056 Loss of Off-site Power / 6 X AA2.09 - Operational status of reactor 2.9 1 building cooling unit 000057 Loss of Vital AC Inst. Bus / 6 X AA2.19 - The plant automatic actions 4.3 1 that will occur on the loss of a vital ac electrical instrument bus CE/E05 Steam Line Rupture - Excessive X EA2.2 - Adherence to appropriate 4.2 1 Heat Transfer / 4 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals: 0 0 0 0 4 2 Group Point Total: 6 REV 1

PWR SRO Examination Outline REV 1 Facility: Palo Verde 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 2.2.38 - Knowledge of conditions and 4.5 1 limitations in the facility license.

000024 Emergency Boration / 1 X AA2.06 - When boron dilution is taking 3.7 1 place CE/A16 Excess RCS Leakage / 2 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.

CE/E09 Functional Recovery X EA2.2 - Adherence to appropriate 4.0 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 REV 1

PWR SRO Examination Outline REV 1 Facility: Palo Verde 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 004 Chemical and Volume Control X A2.26 - Low VCT pressure 3.0 1 006 Emergency Core Cooling X A2.04 - Improper discharge 3.8 1 pressure 010 Pressurizer Pressure Control X A2.02 - Spray valve failures 3.9 1 059 Main Feedwater X 2.4.11 -Knowledge of 4.2 1 abnormal condition procedures.

078 Instrument Air X A2.01 - Air dryer and filter 2.9 1 malfunctions K/A Category Totals: 0 0 0 0 0 0 0 4 0 0 1 Group Point Total: 5 REV 1

PWR SRO Examination Outline REV 1 Facility: Palo Verde 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 002 Reactor Coolant X 2.2.40 - Ability to apply 4.7 1 Technical Specifications for a system.

041 Steam Dump/Turbine Bypass X A2.02 - Steam valve stuck 3.9 1 Control open 072 Area Radiation Monitoring X A2.03 - Blown 2.9 1 power-supply fuses K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 REV 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline REV 1 Facility: Palo Verde Form ES-401-3 Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.14 Knowledge of criteria or conditions that require 3.1 1 plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

2.1.25 Ability to interpret reference materials, such as 4.2 1 graphs, curves, tables, etc.

Category Total: 2 Equipment Control 2.2.11 Knowledge of the process for controlling 3.3 1 temporary design changes.

2.2.18 Knowledge of the process for managing 3.9 1 maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

Category Total: 2 Radiation Control 2.3.11 Ability to control radiation releases. 4.3 1 Category Total: 1 Emergency Procedures/Plan 2.4.38 Ability to take actions called for in the facility 4.4 1 emergency plan, including supporting or acting as emergency coordinator if required.

2.4.40 Knowledge of SRO responsibilities in emergency 4.5 1 plan implementation.

Category Total: 2 Generic Total: 7 REV 1

Rev 1 PVNGS License Examination Record of Rejected K/As Exam Date 03/16/12 PVNGS Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/As SRO Exam 1/1 057 AA2.20 PVNGS does not have a vital ac interlock that can be bypassed to restore normal operation. Replaced with 4.2 057 AA2.19 2/1 010 2.4.20 PVNGS EOPs do not contain any notes on PPCS. Replaced with 3.3 010 A2.02 2/1 064 A2.10 This KA is not at the SRO level. Replaced with 3.8 078 A2.01 2/2 011 A2.05 Loss of PZR Heaters has no effect on PLCS. Replaced with 041 A2.02 Rev 1

ES-301 Administrative Topics Outline Form ES-301-1 PVNGS Facility: _______________________________ 03/19/12 Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: __________

Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine ability to stand shift with training and license proficiency time. (2.1.4)

Conduct of Operations N,R In Lower Mode determine Pressurizer level and RCS volume to be drained to the Refueling Water Tank (RWT). (2.1.25)

Conduct of Operations M,R Tech Review a permit (clearance) (2.2.13)

Equipment Control N,R Determine the proper REP task and RCA entry requirements. (2.3.7)

D Radiation Control 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 all 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

ES-301 Administrative Topics Outline Form ES-301-1 PVNGS Facility: _______________________________ 03/19/12 Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: __________

Administrative Topic Type Describe activity to be performed (see Note) Code*

Determine if manning is met with medical and training requirements.

(2.1.4)

Conduct of Operations N,R Determine "if time shutdown" is met and makeup flow requirements for mid-loop (2.1.20)

Conduct of Operations N,R Identify LCOs and Conditions associated with the numerous Main Steam Isolation Valve pressures.

Equipment Control M,R (2.2.22)

Determine hold points exceeded, approval needed, and which AO will perform the task (2.3.4)

M,R Radiation Control Determine Classification, Protective Action Recommendation and Release status (2.4.41)

D,R 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 all 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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 PVNGS Facility: _____________________________ 03/19/12 Date of Examination: ______________

Exam Level: RO SRO-I SRO-U Operating Test No.: _______________

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

a. Perform Containment Power Access Purge (3.8 029 A2.03) D 8

b. Perform actions for a loss of letdown (3.1 004 A2.07) N,A 1

c. Startup second MFP (3.4 039 A4.03) N,A 4S

d. Fill a SIT (3,3 006 A1.13) N 3

e. Pump RDT with high temperature (3,5 007 A 2.05) L,N 5

f. Reset inadvertent MSIS (3.2 013 A4.01) L,D,A 2

g. Restore offsite power to PBA-S03 (powered from DG A) (3.6 062 A4.01) D 6

h. Place CS B in service on SDC (3.4 005 A4.01) L,D 4P In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Align SDC valves during a Control Room Fire (4.2 067 AA2.16) L,N,A,E,R 4P

j. Operation of AFA-P01 from Remote Shutdown Panel (3.4 061 A3.01) L,D,E,P 4S

k. Align offsite power to PBB per Appendix C of 40AO-9ZZ19 (3.6 062 A2.06) D,EN,E, A 6

@ 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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 PVNGS Facility: _____________________________ 03/19/12 Date of Examination: ______________

Exam Level: RO SRO-I SRO-U Operating Test No.: _______________

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

a. Perform Containment Power Access Purge (3.8 029 A2.03) D 8

b. Perform actions for a loss of letdown (3.1 004 A2.07) N,A 1

c. Fill a SIT (3.3 006 A1.13) N 3

d. Pump RDT with high temperature (3.5 007 A2.05) L,N 5

e. Reset inadvertent MSIS (3.2 013 A 4.01) L,D,A 2

f. Restore offsite power to PBA-S03 (powered from DG A) (3.6 062 A 4.01) D 6

g. ESD with no CIAS, CSAS with CIAS valves that fail to close (3.7 012 A 4.02) L,N,A,EN 7 h.

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

i. Align SDC valves during a Control Room Fire (4.2 067 AA2.16) L,N,A,E,R 4P

j. Operation of AFA-P01 from Remote Shutdown Panel (3.4 061 A3.01) L,D,E,P 4S

k. Align offsite power to PBB per Appendix C of 40AO-9ZZ19 (3.6 062 A2.06) D,EN,E,A 6

@ 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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 PVNGS Facility: _____________________________ 03/19/12 Date of Examination: ______________

Exam Level: RO SRO-I SRO-U Operating Test No.: _______________

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

a. Perform Containment Power Access Purge (3.8 029 A2.03) D 8

b. Perform actions for a loss of letdown (3.1 004 A2.07) N,A 1

c. ESD with no CIAS, CSAS with CIAS valves that fail to close (3.7 012 A 4.02) L,N,A,EN 7 d.

e.

f.

g.

h.

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

i. Align SDC valves during a Control Room Fire (4.2 067 AA2.16) L,N,A,E,R 4P

j. Operation of AFA-P01 from Remote Shutdown Panel (3.4 061 A3.01) L,D,E,P 4S k.

@ 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

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __1 Op-Test No: 2012 Examiners: Operators:

Initial Conditions: (100% power, MOC).

Turnover: Unit 1 is at 100% power (250 EFPD). Auxiliary Feedwater Pump A and Containment Spray A are tagged out.

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

1 None N Shift Turbine Cooling water pumps.

CO/SRO 2 cmTRCV05CHNLT227_4 C Volume Control Tank level transmitter, CHN-LT-227 fails low RO/SRO causing a boration. Crew takes action to return CCP suction to the Volume Control Tank.

3 mfRM01A I Control Room monitor, RU-29, fails high. Crew will bypass CREFAS A.

CO/SRO 4 cmCPCC06EWAP01_5 C Essential Cooling water pump A fails to auto start on CREFAS actuation. RO will start EW pump A.

(In setup) RO/SRO (TS) 5 mfTH06A f:0.02 C Steam Generator 1 Tube Leak ALL 40AO-9ZZ02, Excessive RCS Leakrate (TS) 6 mfED16C C Loss of Class DC power PKC-M43.

CO/SRO 40AO-9ZZ13, Loss of Class Instrument or Control Power (T/S) 7 mfTH06A f:50 M Steam Generator 1 Tube Leak degrades to a Rupture.

ALL 40EP-9EO04, Steam Generator Tube Rupture 8 cmCPSI01SIAP02_5 C HPSI pump A fails to auto start on SIAS/CIAS actuation (In setup) RO/SRO 9 mfRX01 f:0 I Tave fails low, Requires manual control of Main Feedwater CO/SRO flow.

CRITICAL TASK - Reset MSIS during cooldown to prevent unmonitored release to public.

End Faulted SG is isolated per Faulted SG is isolated point Standard Appendix 113, SG 1 Isolation CRITICAL TASK -Isolate faulted SG within 70 minutes of initiation of SGTR.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 of 2

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is ORANGE.

Train B is protected equipment.

AF B and AF N are protected.

CS B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Vibration shop reported that in a review of data they found some unusual readings with Turbine Cooling Water pump A. A vibration technician and AO are have been briefed and are standing by for a TCW pump shift. Appendix D of 40OP-9TC01 has been completed.

Equipment out of service:

Auxiliary Feedpump A (AFA-P01) is tagged out due to a noisy bearing. LCO 3.7.5 conditions a and b have been entered. Expected to return to service in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

CS A is tagged out for scheduled maintenance. LCO 3.6.6 condition a has been entered. Expected to return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Planned shift activities:

Remove the A Turbine Cooling Water pump from service. The pre-start checklist has been completed and the area operator is standing by.

NUREG-1021, Revision 9 2 of 2

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __2 Op-Test No: 2012 Examiners: Operators:

Initial Conditions: (100% power, MOC).

Turnover: Unit 1 is at 100% power (250 EFPD). AFA-P01 and Containment Spray A are tagged out.

Event No. Malf. No. Event Type* Event Description 1 None N Shift from Hydraulic Fluid Pump B to Pump A per section 6.7 of CO/SRO 40OP-9C001, Electro-Hydraulic Control System.

2 mfNI02C f:0 I Control Channel 2 fails low (50% Power indicated). Crew selects CO/SRO channel 1 at the RRS system panel.

40AO-9ZZ16, RRS Malfunctions 3 mfTH01A f:0.01 C Small RCS leak. Crew takes action per section 3 of ~16 gpm RO/SRO 40AO-9ZZ02, Excessive RCS Leakrate (TS) 4 mfAN_1A03D1 C LOP relay failure. Crew responds using 41AL-1RK1A (1A03D) doeED_ZLS037271DS_W1 CO/SRO Crew determines that a LOP should not have occurred and takes action to bypass the appropriate relays per 40OP-9SA01 doRP_ZLSAAC02ALOP1_ (TS)

W1 5 IOR dims_ZDSGEUV170 R -RO An MSIV goes closed. Crew responds per 40AL-9RK6A and begins a down power to less than 65% power.

C - CO/SRO 6 cmCPTP01CENP01B_6 C Stator Cooling Pump B trips with standby pump failing to auto CO/SRO start.

7 mfTH01A f:3 M LOCA RCS leak degrades requiring a reactor trip.

ALL 40EP-9EO03, Loss of Coolant Accident 8 Scenario file no SI/CI C SIAS/CIAS/MSIS fail to automatically initiate.

RO/SRO CRITICAL TASK - Initiate SI flow when the SIAS setpoint has been exceeded prior to completing Step 4 of the LOCA procedure.

9 cmCPRH05SIBP03_6 C CS pump B trips on an 86 lockout RO/SRO CRITICAL TASK -Initiate CS flow when the CSAS setpoint has been exceeded prior to completing step 3 of CTPC-2 of the Functional Recovery Procedure.

40EP-9EO09, Functional Recovery Procedure End Scenario may be ended once point SIAS and CSAS flow have been established using LPSI.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 of 2

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is ORANGE.

Train B is protected equipment.

AF B and AF N are protected.

CS B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

Auxiliary Feedpump A (AFA-P01) is tagged out due to a noisy bearing. LCO 3.7.5 conditions a and b have been entered. Expected to return to service in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

CS A is tagged out for scheduled maintenance. LCO 3.6.6 condition a has been entered. Expected to return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Planned shift activities:

The crew needs to shift EHC pumps from B to A to support vibration readings. The vibration tech is standing by.

NUREG-1021, Revision 9 2 of 2

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __3 Op-Test No: 2012 Examiners: Operators:

Initial Conditions: (2% power, MOC).

Turnover: Unit 1 is at 2% power (200 EFPD). AFA-P01 and Containment Spray A are tagged out.

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

1 None N Shift the MFP Lube oil pumps per 4.9 of 40OP-9FT02, Feedwater Pump Turbine B.

CO/SRO 2 cmAVRC03RCEPV100F_1 C Pressurizer spray valve fails open.

RO/SRO 3 mfRP06L1 C Inadvertent AFAS, B train AFW pumps and valves align to initiate AFW flow to the SGs. Crew takes actions to terminate mfRP06L2 CO/SRO flow and resulting power increase.

(TS) 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations 4 cmCNCV04CHNFIC243_2 I A seal injection controller will fail closed in automatic f:100 requiring the crew to take manual control of the controller RO/SRO 5 mfED10B C NBN-X04 faults and the DG breaker does not close causing a LOP of class 4160 bus, PBB-S04 cmBKEG03PBBS04B_3 RO/SRO 40AO-9ZZ12, Degraded Electrical.

(TS) 6 mfRD10B M Continuous CEA withdrawal. Crew places CEDMCS in ALL STANDBY then trips the reactor per:

40AO-9ZZ11, CEA Malfunctions 7 mfRD03G C Multiple CEAs stick out on the reactor trip.

mfRD03L RO/SRO CRITICAL TASK - Crew establishes > 44 gpm boration prior to completing the SPTAs.

mfRD03M 40EP-9EO02, Reactor Trip 8 cmAVMC01CDNHV45A_1 Loss of Main Condenser Vacuum.

9 mfFW21A C Trip of AFN-P01 RO/CO/SRO CRITICAL TASK - Implement the FRP to restore power to PBB-S04 and establish AFW flow to the SGs prior to completing MVAC-1.

40EP-9EO09, Functional Recovery Procedure End Crew has restored AFW flow to point the SGs

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 of 2

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 is at 2% power.

The plant has been at 2% power for 2 days awaiting repair of AFA-P01.

The core is presently at 250 EFPD.

Risk Management Action Level is ORANGE.

Train B is protected equipment.

AF B and AF N are protected.

CS B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

CEDMCS is in Manual Sequential Steam Bypass Master Controller SGN-PIC-1010 is in Local Setpoint with SBCV 1004 and 1006 in manual Pressurizer is in Boron Equalization AFN-P01 is in service feeding the SGs thru the Feedwater Isolation bypasses (SGN-HS-1143/1145)

Maintenance on the breaker was completed on Main Lube Oil pump LON-P07B at the end of last shift and it is ready to be tested.

Equipment out of service:

Auxiliary Feedpump A (AFA-P01) is tagged out due to a noisy bearing. LCO 3.7.5 conditions a and c were entered. Expected to return to service in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

CS A is tagged out for scheduled maintenance. LCO 3.6.6 condition a has been entered. Expected to return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Planned shift activities:

Shift the running and standby lube oil pumps on Main Feedpump B.

NUREG-1021, Revision 9 2 of 2

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __4 Op-Test No: 2012 Examiners: Operators:

Initial Conditions: (100% power, MOC).

Turnover: Unit 1 is at 100% power (250 EFPD). AFA-P01 and Containment Spray A are tagged out.

Event No. Malf. No. Event Type* Event Description 1 None N Shift Steam Bypass Master Controller, SGN-PIC-1010 from manual to automatic mode of operation.

CO/SRO 2 mfTRRX11SGCPT1013C_4 I Channel C SG 1 pressure transmitter fails low requiring multiple parameters to be placed in bypass. (SGC-PI-1013C)

CO/SRO (TS) 3 cmTRCV19RCALT110X_4 I Pressurizer level transmitter X fails low. Crew selects channel Y on pressurizer heater and level control selectors.

RO/SRO (TS) 4 mfCH01B C Loss of Control Element Drive Mechanism cooling. HCN-A02A and A02C fans fail to auto-start mfCH01D CO/SRO 40AO-9ZZ20, Loss of HVAC 5 mfMC01A R -RO Loss of condenser vacuum requiring the crew to downpower.

C - CO/SRO 40AO-9ZZ07, Loss of Condenser Vacuum 6 mfCV11A f:100 RCP 1A seal failure. Crew evaluates the status of the affected RCP.

40AO-9ZZ04, Reactor Coolant Pump Emergencies 7 cmCPRC02RCEP01A_6 M RCP 1A trips but PPS fails to initiate a reactor trip. RO opens mfRP04A ALL L03B2 and L10B2 breakers on B01.

mfRP04C CRITICAL TASK - Trip the Reactor prior to completion of mfRD12A SPTAs 8 mfED02 M After the Reactivity Safety Function is addressed a Loss of mfEG06B ALL Offsite Power will occur. DG B will trip when it starts.

40EP-9EO07, Loss of Offsite Power/Loss of Forced Circulation 9 cmCPCC08SPAP01_5 C Spray Pond pump A fails to auto start.

RO/SRO CRITICAL TASK - Starts SPA-P01 prior to DG A running > 3 minutes with no cooling water.

CRITICAL TASK - Establish feed to at least one SG using AFN-P01 prior to lifting primary safeties.

40EP-9EO09, FRP (MVAC-3)

End Once the crew has verified point that Natural Circulation flow has been established NUREG-1021, Revision 9 1 of 2

Appendix D Scenario Outline Form ES-D-1

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Turnover Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is ORANGE.

Train B is protected equipment.

AF B and AF N are protected.

CS B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

I&C have completed testing on the SBCS master controller SGN-PIC-1010 and it can be returned to automatic operation.

Equipment out of service:

Auxiliary Feedpump A (AFA-P01) is tagged out due to a noisy bearing. LCO 3.7.5 conditions a and b have been entered. Expected to return to service in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

CS A is tagged out for scheduled maintenance. LCO 3.6.6 condition a has been entered. Expected to return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Planned shift activities:

Shift SGN-PIC-1010 from local/auto to remote/auto mode of operation.

NUREG-1021, Revision 9 2 of 2