Text

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)
	v • d • e

REV 1 ES-401 Facility:

Palo Verde PWR Examination Outline Form ES-401-2 2

3 4

3 3

3 2

2 2

2 1

0 4

5 6

5 4

3 3

2 3

4 2

2 4

2 2

1 1

2 0

1 1

0 4

3 4

5 3

3 6

2 3

3 2

2 3

RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*

1.

Emergency Abnormal Plant Evolutions 1

1 2

2 Tier Totals Tier Totals 2.

Plant Systems 1

2 3

4

3. Generic Knowledge And Abilities Categories 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.

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.

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.

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.

Note:

Date Of Exam:

03/16/2012 28 18 9

27 10 38 10 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).

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.

SRO-Only Points A2 G*

0 0

0 1

2 3

4 0

0 0

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.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

N/A N/A Total 0

0 REV 1

REV 1 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points ES - 401 Facility:

Palo Verde E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EA2.03 - Reactor trip breaker position 4.2 1

X 000007 Reactor Trip - Stabilization -

Recovery / 1 AK2.01 - Valves 2.7*

1 X

000008 Pressurizer Vapor Space Accident /

3 EK3.28 - Manual ESFAS initiation requirements 4.5 1

X 000009 Small Break LOCA / 3 EK2.02 - Pumps 2.6*

1 X

000011 Large Break LOCA / 3 AK3.02 - Actions contained in SOPs and EOPs for RCPs, loss of makeup, loss of charging, and abnormal charging 3.5 1

X 000022 Loss of Rx Coolant Makeup / 2 AA2.07 - Pump cavitation 3.4 1

X 000025 Loss of RHR System / 4 AK3.03 - Guidance actions contained in EOP for Loss of CCW 4.0 1

X 000026 Loss of Component Cooling Water /

8 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.

4.1 1

X 000027 Pressurizer Pressure Control System Malfunction / 3 EK1.03 - Effects of boron on reactivity 3.6 1

X 000029 ATWS / 1 2.2.44 - Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

4.2 1

X 000038 Steam Gen. Tube Rupture / 3 EK3.01 - Length of time for which battery capacity is designed 2.7 1

X 000055 Station Blackout / 6 AA2.17 - Operational status of PZR backup heaters 3.4 1

X 000056 Loss of Off-site Power / 6 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

4.2 1

X 000057 Loss of Vital AC Inst. Bus / 6 AK1.01 - Battery charger equipment and instrumentation 2.8 1

X 000058 Loss of DC Power / 6 AA1.03 - Restoration of systems served by instrument air when pressure is regained 2.9 1

X 000065 Loss of Instrument Air / 8 AA1.05 - Engineered safety features 3.9 1

X 000077 Generator Voltage and Electric Grid Disturbances / 6 EK2.2 - Facility's heat removal systems, 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 3.7 1

X CE/E05 Steam Line Rupture - Excessive Heat Transfer / 4 REV 1

REV 1 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points ES - 401 Facility:

Palo Verde E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR RO Examination Outline Form ES-401-2 EA1.2 - Operating behavior characteristics of the facility 3.4 1

X CE/E06 Loss of Main Feedwater / 4 18 2

3 4

3 3

3 K/A Category Totals:

Group Point Total:

REV 1

REV 1 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points ES - 401 Facility:

Palo Verde E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR RO Examination Outline Form ES-401-2 AA1.07 - RPI 3.3 1

X 000001 Continuous Rod Withdrawal / 1 AK3.06 - Actions contained in EOP for inoperable/stuck control rod 3.9 1

X 000005 Inoperable/Stuck Control Rod / 1 AK1.01 - PZR reference leak abnormalities 2.8*

1 X

000028 Pressurizer Level Malfunction / 2 AK2.01 - ARM system, including the normal radiation-level indications and the operability status 2.6 1

X 000060 Accidental Gaseous Radwaste Rel. /

9 AK2.02 - Reactor trip system 3.7 1

X 000068 Control Room Evac. / 8 AA2.01 - Loss of containment integrity 3.7 1

X 000069 Loss of CTMT Integrity / 5 AK1.2 - Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations) 3.2 1

X CE/A13 Natural Circ. / 4 AK3.3 - Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations 3.3 1

X CE/A16 Excess RCS Leakage / 2 EA1.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 4.2 1

X CE/E09 Functional Recovery 9

2 2

1 0

K/A Category Totals:

Group Point Total:

REV 1

REV 1 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Palo Verde PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A1.05 - RCS flow 3.4 1

X 003 Reactor Coolant Pump K6.04 - Containment isolation valves affecting RCP operation 2.8 1

X 003 Reactor Coolant Pump K1.04 - RCPS, including seal injection flows 3.4 1

X 004 Chemical and Volume Control K5.03 - Reactivity effects of RHR fill water 2.9*

1 X

005 Residual Heat Removal K3.07 - Refueling operations 3.2*

1 X

005 Residual Heat Removal K1.03 - RCS 4.2 1

X 006 Emergency Core Cooling A2.05 - Exceeding PRT high-pressure limits 3.2 1

X 007 Pressurizer Relief/Quench Tank K2.02 - CCW pump, including emergency backup 3.0*

1 X

008 Component Cooling Water K5.01 - Determination of condition of fluid in PZR, using steam tables 3.5 1

X 010 Pressurizer Pressure Control A4.04 - Bistable, trips, reset and test switches 3.3*

1 X

012 Reactor Protection K4.06 - Automatic or manual enable/disable of RPS trips 3.2 1

X 012 Reactor Protection K4.03 - Main Steam Isolation System 3.9 1

X 013 Engineered Safety Features Actuation A4.01 - CCS fans 3.6 1

X 022 Containment Cooling A3.01 - Pump starts and correct MOV positioning 4.3 1

X 026 Containment Spray K3.03 - AFW pumps 3.2*

1 X

039 Main and Reheat Steam A1.03 - Power level restrictions for operation of MFW pumps and valves 2.7*

1 X

059 Main Feedwater K4.02 - AFW automatic start upon loss of MFW pump, S/G level, blackout, or safety injection 4.5 1

X 061 Auxiliary/Emergency Feedwater K4.03 - Interlocks between automatic bus transfer and breakers 2.8*

1 X

062 AC Electrical Distribution A3.01 - Vital ac bus amperage 3.0 1

X 062 AC Electrical Distribution 2.1.27 - Knowledge of system purpose and/or function.

3.9 1

X 063 DC Electrical Distribution K2.01 - Major DC loads 2.9*

1 X

063 DC Electrical Distribution A1.08 - Maintaining minimum load on ED/G (to 3.1 1

X 064 Emergency Diesel Generator REV 1

REV 1 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Palo Verde PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 prevent reverse power)

K6.07 - Air receivers 2.7 1

X 064 Emergency Diesel Generator 2.2.39 - Knowledge of less than or equal to one hour Technical Specification action statements for systems.

3.9 1

X 073 Process Radiation Monitoring A2.01 - Loss of SWS 3.5*

1 X

076 Service Water K1.19 - SWS emergency heat loads 3.6*

1 X

076 Service Water K3.02 - Systems having pneumatic valves and controls 3.4 1

X 078 Instrument Air A1.01 - Containment pressure, temperature, and humidity 3.7 1

X 103 Containment 28 3

2 3

4 2

2 K/A Category Totals:

4 2

2 2

2 Group Point Total:

REV 1

REV 1 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Palo Verde PWR RO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 A4.03 - CRDS mode control 4.0 1

X 001 Control Rod Drive K3.03 - Containment 4.2 1

X 002 Reactor Coolant A3.01 - Automatic selection of NNIS inputs to control systems 2.9*

1 X

016 Non-nuclear Instrumentation K1.01 - Plant computer 3.2*

1 X

017 In-core Temperature Monitor A1.02 - Containment pressure 3.4*

1 X

028 Hydrogen Recombiner and Purge Control A1.03 - Containment pressure, temperature, and humidity 3.0*

1 X

029 Containment Purge K4.01 - Maintenance of spent fuel level 2.9 1

X 033 Spent Fuel Pool Cooling K6.03 - Controller and positioners, including ICS, S/G, CRDS 2.7 1

X 041 Steam Dump/Turbine Bypass Control K5.01 - Radiation theory, including sources, types, units, and effects 2.7 1

X 072 Area Radiation Monitoring K2.03 - Emergency/essential SWS pumps 2.6*

1 X

075 Circulating Water 10 1

1 1

2 0

0 K/A Category Totals:

1 1

1 Group Point Total:

REV 1

Facility:

Palo Verde Generic Category KA KA Topic Imp.

Points Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 REV 1 PWR RO Examination Outline 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

3.4 1

Conduct of Operations 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.

4.3 1

2 Category Total:

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

3.9 1

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

3.9 1

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

4.2 1

3 Category Total:

2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

3.2 1

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

2.9 1

2 Category Total:

2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

3.7 1

Emergency Procedures/Plan 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

3.5 1

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

4.2 1

3 Category Total:

10 Generic Total:

REV 1

Rev 1 Rev 1 PVNGS License Examination Record of Rejected K/As Exam Date 03/16/12 PVNGS Form ES-401-4 Tier /

Group Randomly Selected K/As Reason for Rejection RO Exam 1 / 1 4.2 015/017 AK1.01 Unable to write RO question. 4.2 077 AA1.05 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 Facility:

Palo Verde PWR Examination Outline Form ES-401-2 0

0 0

RO K/A Category Points Tier Group Total K1 K2 K3 K4 K5 A1 A2 A3 A4 K6 G*

1.

Emergency Abnormal Plant Evolutions 1

1 2

2 Tier Totals Tier Totals 2.

Plant Systems 1

2 3

4

3. Generic Knowledge And Abilities Categories 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.

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.

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.

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.

Note:

Date Of Exam:

03/16/2012 0

0 0

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).

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.

SRO-Only Points A2 G*

4 2

2 2

6 4

4 1

2 1

2 2

2 1

2 3

4 10 4

6 5

3 8

7 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.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

N/A N/A Total 0

6 REV 1

REV 1 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points

ES - 401 Facility:

Palo Verde E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 PWR SRO Examination Outline Form ES-401-2 2.4.41 - Knowledge of the emergency action level thresholds and classifications.

4.6 1

X 000011 Large Break LOCA / 3 2.4.6 - Knowledge of EOP mitigation strategies.

4.7 1

X 000025 Loss of RHR System / 4 EA2.15 - Pressure at which to maintain RCS during S/G cooldown 4.4 1

X 000038 Steam Gen. Tube Rupture / 3 AA2.09 - Operational status of reactor building cooling unit 2.9 1

X 000056 Loss of Off-site Power / 6 AA2.19 - The plant automatic actions that will occur on the loss of a vital ac electrical instrument bus 4.3 1

X 000057 Loss of Vital AC Inst. Bus / 6 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 4.2 1

X CE/E05 Steam Line Rupture - Excessive Heat Transfer / 4 6

0 0

4 2

K/A Category Totals:

Group Point Total:

REV 1

REV 1 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points ES - 401 Facility:

Palo Verde E/APE # / Name / Safety Function Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 PWR SRO Examination Outline Form ES-401-2 2.2.38 - Knowledge of conditions and limitations in the facility license.

4.5 1

X 000003 Dropped Control Rod / 1 AA2.06 - When boron dilution is taking place 3.7 1

X 000024 Emergency Boration / 1 2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

4.7 1

X CE/A16 Excess RCS Leakage / 2 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 4.0 1

X CE/E09 Functional Recovery 4

0 0

2 2

K/A Category Totals:

Group Point Total:

REV 1

REV 1 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Palo Verde PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 A2.26 - Low VCT pressure 3.0 1

X 004 Chemical and Volume Control A2.04 - Improper discharge pressure 3.8 1

X 006 Emergency Core Cooling A2.02 - Spray valve failures 3.9 1

X 010 Pressurizer Pressure Control 2.4.11 - Knowledge of abnormal condition procedures.

4.2 1

X 059 Main Feedwater A2.01 - Air dryer and filter malfunctions 2.9 1

X 078 Instrument Air 5

0 0

4 1

K/A Category Totals:

0 0

0 Group Point Total:

REV 1

REV 1 K1 KA Topic Imp.

K2 K3 A1 A2 G

Points K4 K5 A3 K6 A4 ES - 401 Sys/Evol # / Name Facility:

Palo Verde PWR SRO Examination Outline Plant Systems - Tier 2 / Group 2 Form ES-401-2 2.2.40 - Ability to apply Technical Specifications for a system.

4.7 1

X 002 Reactor Coolant A2.02 - Steam valve stuck open 3.9 1

X 041 Steam Dump/Turbine Bypass Control A2.03 - Blown power-supply fuses 2.9 1

X 072 Area Radiation Monitoring 3

0 0

2 1

K/A Category Totals:

0 0

0 Group Point Total:

REV 1

Facility:

Palo Verde Generic Category KA KA Topic Imp.

Points Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 REV 1 PWR SRO Examination Outline 2.1.14 Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

3.1 1

Conduct of Operations 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

4.2 1

2 Category Total:

2.2.11 Knowledge of the process for controlling temporary design changes.

3.3 1

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

3.9 1

2 Category Total:

2.3.11 Ability to control radiation releases.

4.3 1

Radiation Control 1

Category Total:

2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.

4.4 1

Emergency Procedures/Plan 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.

4.5 1

2 Category Total:

7 Generic Total:

REV 1

Rev 1 Rev 1 PVNGS License Examination Record of Rejected K/As Exam Date 03/16/12 PVNGS Form ES-401-4 Tier /

Group Randomly Selected K/As Reason for Rejection 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

ES-301, Page 22 of 27 ES-301 Administrative Topics Outline Form ES-301-1 Facility: _______________________________

Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: __________

Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations Conduct of Operations Equipment Control 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)

PVNGS 03/19/12

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

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

M,R Tech Review a permit (clearance) (2.2.13)

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

D

ES-301, Page 22 of 27 ES-301 Administrative Topics Outline Form ES-301-1 Facility: _______________________________

Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: __________

Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations Conduct of Operations Equipment Control 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)

PVNGS 03/19/12

Determine if manning is met with medical and training requirements.

(2.1.4)

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

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

(2.2.22)

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

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

D,R

ES-301, Page 23 of 27 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _____________________________

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.

b.

c.

d.

e.

f.

g.

h.

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

j.

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature

(L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1

- / - /

1 (control room system)

1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 PVNGS 03/19/12

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

D 8

Perform actions for a loss of letdown (3.1 004 A2.07)

N,A 1

Startup second MFP (3.4 039 A4.03)

N,A 4S Fill a SIT (3,3 006 A1.13)

N 3

Pump RDT with high temperature (3,5 007 A 2.05)

L,N 5

Reset inadvertent MSIS (3.2 013 A4.01)

L,D,A 2

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

D 6

Place CS B in service on SDC (3.4 005 A4.01)

L,D 4P Align SDC valves during a Control Room Fire (4.2 067 AA2.16)

L,N,A,E,R 4P Operation of AFA-P01 from Remote Shutdown Panel (3.4 061 A3.01)

L,D,E,P 4S Align offsite power to PBB per Appendix C of 40AO-9ZZ19 (3.6 062 A2.06)

D,EN,E, A 6

ES-301, Page 23 of 27 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _____________________________

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.

b.

c.

d.

e.

f.

g.

h.

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

j.

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature

(L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1

- / - /

1 (control room system)

1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 PVNGS 03/19/12

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

D 8

Perform actions for a loss of letdown (3.1 004 A2.07)

N,A 1

Fill a SIT (3.3 006 A1.13)

N 3

Pump RDT with high temperature (3.5 007 A2.05)

L,N 5

Reset inadvertent MSIS (3.2 013 A 4.01)

L,D,A 2

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

D 6

ESD with no CIAS, CSAS with CIAS valves that fail to close (3.7 012 A 4.02)

L,N,A,EN 7

Align SDC valves during a Control Room Fire (4.2 067 AA2.16)

L,N,A,E,R 4P Operation of AFA-P01 from Remote Shutdown Panel (3.4 061 A3.01)

L,D,E,P 4S Align offsite power to PBB per Appendix C of 40AO-9ZZ19 (3.6 062 A2.06)

D,EN,E,A 6

ES-301, Page 23 of 27 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: _____________________________

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.

b.

c.

d.

e.

f.

g.

h.

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

j.

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature

(L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1

- / - /

1 (control room system)

1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 PVNGS 03/19/12

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

D 8

Perform actions for a loss of letdown (3.1 004 A2.07)

N,A 1

ESD with no CIAS, CSAS with CIAS valves that fail to close (3.7 012 A 4.02)

L,N,A,EN 7

Align SDC valves during a Control Room Fire (4.2 067 AA2.16)

L,N,A,E,R 4P Operation of AFA-P01 from Remote Shutdown Panel (3.4 061 A3.01)

L,D,E,P 4S

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 1 of 2 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 No.

Malf. No.

Event Type*

Event Description 1

None N

CO/SRO Shift Turbine Cooling water pumps.

2 cmTRCV05CHNLT227_4 C

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

3 mfRM01A I

CO/SRO Control Room monitor, RU-29, fails high. Crew will bypass CREFAS A.

4 cmCPCC06EWAP01_5 (In setup)

C RO/SRO (TS)

Essential Cooling water pump A fails to auto start on CREFAS actuation. RO will start EW pump A.

5 mfTH06A f:0.02 C

ALL (TS)

Steam Generator 1 Tube Leak 40AO-9ZZ02, Excessive RCS Leakrate 6

mfED16C C

CO/SRO (T/S)

Loss of Class DC power PKC-M43.

40AO-9ZZ13, Loss of Class Instrument or Control Power 7

mfTH06A f:50 M

ALL Steam Generator 1 Tube Leak degrades to a Rupture.

40EP-9EO04, Steam Generator Tube Rupture 8

cmCPSI01SIAP02_5 (In setup)

C RO/SRO HPSI pump A fails to auto start on SIAS/CIAS actuation 9

mfRX01 f:0 I

CO/SRO Tave fails low, Requires manual control of Main Feedwater flow.

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

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

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 2 of 2 Turnover Unit 1 is at 100% power.

Plant conditions:

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.

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 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

Equipment out of service:

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

Planned shift activities:

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 1 of 2 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

CO/SRO Shift from Hydraulic Fluid Pump B to Pump A per section 6.7 of 40OP-9C001, Electro-Hydraulic Control System.

2 mfNI02C f:0 I

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

40AO-9ZZ16, RRS Malfunctions 3

mfTH01A f:0.01 C

RO/SRO (TS)

Small RCS leak. Crew takes action per section 3 of ~16 gpm 40AO-9ZZ02, Excessive RCS Leakrate 4

mfAN_1A03D1 doeED_ZLS037271DS_W1 doRP_ZLSAAC02ALOP1_

W1 C

CO/SRO (TS)

LOP relay failure. Crew responds using 41AL-1RK1A (1A03D)

Crew determines that a LOP should not have occurred and takes action to bypass the appropriate relays per 40OP-9SA01 5

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

6 cmCPTP01CENP01B_6 C

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

7 mfTH01A f:3 M

ALL LOCA RCS leak degrades requiring a reactor trip.

40EP-9EO03, Loss of Coolant Accident 8

Scenario file no SI/CI C

RO/SRO SIAS/CIAS/MSIS fail to automatically initiate.

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

RO/SRO CS pump B trips on an 86 lockout 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 point Scenario may be ended once SIAS and CSAS flow have been established using LPSI.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 2 of 2 Turnover Unit 1 is at 100% power.

Plant conditions:

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.

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 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

Equipment out of service:

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

Planned shift activities:

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 1 of 2 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 No.

Malf. No.

Event Type*

Event Description 1

None N

CO/SRO Shift the MFP Lube oil pumps per 4.9 of 40OP-9FT02, Feedwater Pump Turbine B.

2 cmAVRC03RCEPV100F_1 C

RO/SRO Pressurizer spray valve fails open.

3 mfRP06L1 mfRP06L2 C

CO/SRO (TS)

Inadvertent AFAS, B train AFW pumps and valves align to initiate AFW flow to the SGs. Crew takes actions to terminate flow and resulting power increase.

40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations 4

cmCNCV04CHNFIC243_2 f:100 I

RO/SRO A seal injection controller will fail closed in automatic requiring the crew to take manual control of the controller 5

mfED10B cmBKEG03PBBS04B_3 C

RO/SRO (TS)

NBN-X04 faults and the DG breaker does not close causing a LOP of class 4160 bus, PBB-S04 40AO-9ZZ12, Degraded Electrical.

6 mfRD10B M

ALL Continuous CEA withdrawal. Crew places CEDMCS in STANDBY then trips the reactor per:

40AO-9ZZ11, CEA Malfunctions 7

mfRD03G mfRD03L mfRD03M C

RO/SRO Multiple CEAs stick out on the reactor trip.

CRITICAL TASK - Crew establishes > 44 gpm boration prior to completing the SPTAs.

40EP-9EO02, Reactor Trip 8

cmAVMC01CDNHV45A_1 Loss of Main Condenser Vacuum.

9 mfFW21A C

RO/CO/SRO Trip of AFN-P01 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 point Crew has restored AFW flow to the SGs

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 2 of 2 Turnover Unit 1 is at 2% power.

Plant conditions:

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.

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 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

Equipment out of service:

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

Planned shift activities:

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 1 of 2 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

CO/SRO Shift Steam Bypass Master Controller, SGN-PIC-1010 from manual to automatic mode of operation.

2 mfTRRX11SGCPT1013C_4 I

CO/SRO (TS)

Channel C SG 1 pressure transmitter fails low requiring multiple parameters to be placed in bypass. (SGC-PI-1013C) 3 cmTRCV19RCALT110X_4 I

RO/SRO (TS)

Pressurizer level transmitter X fails low. Crew selects channel Y on pressurizer heater and level control selectors.

4 mfCH01B mfCH01D C

CO/SRO Loss of Control Element Drive Mechanism cooling. HCN-A02A and A02C fans fail to auto-start 40AO-9ZZ20, Loss of HVAC 5

mfMC01A R -RO C - CO/SRO Loss of condenser vacuum requiring the crew to downpower.

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 mfRP04A mfRP04C mfRD12A M

ALL RCP 1A trips but PPS fails to initiate a reactor trip. RO opens L03B2 and L10B2 breakers on B01.

CRITICAL TASK - Trip the Reactor prior to completion of SPTAs 8

mfED02 mfEG06B M

ALL After the Reactivity Safety Function is addressed a Loss of 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

RO/SRO Spray Pond pump A fails to auto start.

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 point Once the crew has verified that Natural Circulation flow has been established

Appendix D Scenario Outline Form ES-D-1 NUREG-1021, Revision 9 2 of 2

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Turnover Unit 1 is at 100% power.

Plant conditions:

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.

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 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

Equipment out of service:

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

Planned shift activities:

ML121080577

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