ML121080617

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PVNGS-2012-03-Draft-Outlines
ML121080617
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 03/16/2012
From:
NRC Region 4
To:
Arizona Public Service Co
Thomas Farina
References
Download: ML121080617 (32)
v • d • e


Text

REV 0 ES-401 Facility:

Palo Verde PWR Examination Outline Form ES-401-2 3

3 3

3 3

3 2

2 2

2 1

0 5

5 5

5 4

3 3

2 3

3 3

2 3

3 2

2 2

1 1

1 1

1 1

1 1

1 1

0 4

3 4

4 4

3 4

4 3

3 2

2 3

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 0

0 0

0 0

0 0

0 0

0 0

0 1

2 3

4 0

0 0

0 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 0

5(90 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 AK1.01 - Natural circulation in a nuclear reactor power plant 4.4 1

X 000015/000017 RCP Malfunctions / 4 AK3.01 - Adjustment of RCP seal backpressure regulator valve to obtain normal flow 2.7 1

X 000022 Loss of Rx Coolant Makeup / 2 AA1.04 - Closed cooling water pumps 2.8*

1 X

000025 Loss of RHR System / 4 AA2.02 - The cause of possible CCW loss 2.9 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 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 5(9

5(90 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 3

3 3

3 3

3 K/A Category Totals:

Group Point Total:

5(9

5(90 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 AK1.02 - Relationship between boron addition and reactor power 3.6 1

X 000024 Emergency Boration / 1 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 EK3.1 - Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics 3.2 1

X CE/A11 RCS Overcooling - PTS / 4 EK1.2 - Normal, abnormal and emergency operating procedures associated with (Natural Selection Operations) 3.2 1

X CE/A13 Natural Circ. / 4 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

2 2

1 0

K/A Category Totals:

Group Point Total:

5(9

REV 0 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 A2.05 - Effects of VCT pressure on RCP seal leakoff flows 2.5 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 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 K4.09 - Separation of control and protection circuits 2.8 1

X 012 Reactor Protection A4.04 - Bistable, trips, reset and test switches 3.3*

1 X

012 Reactor Protection K5.01 - Definitions of safety train and ESF channel 2.8 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 K5.03 - Pump head effects when control valve is shut 2.6 1

X 061 Auxiliary/Emergency Feedwater K3.02 - S/G 4.2 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 K2.01 - Major DC loads 2.9*

1 X

063 DC Electrical Distribution 2.1.32 - Ability to explain and apply system limits and precautions.

3.8 1

X 063 DC Electrical Distribution K6.07 - Air receivers 2.7 1

X 064 Emergency Diesel Generator A1.08 - Maintaining 3.1 1

X 064 Emergency Diesel Generator REV 0

REV 0 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 minimum load on ED/G (to prevent reverse power) 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 K4.01 - Manual/automatic transfers of control 2.7 1

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

X 103 Containment 28 3

2 3

3 3

2 K/A Category Totals:

3 3

2 2

2 Group Point Total:

REV 0

REV 0 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 A4.01 - Controls for CCWS 3.1 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 A2.03 - Startup operations and the associated required valve lineups 2.7 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

1 1

0 K/A Category Totals:

1 1

1 1

1 Group Point Total:

REV 0

Facility:

Palo Verde Generic Category KA KA Topic Imp.

Points Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 5(90

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:

2.4.16 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

Emergency Procedures/Plan 2.4.31 Knowledge of annunciator alarms, indications, or response procedures.

4.2 1

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

4.1 1

3 Category Total:

10 Generic Total:

REV 0

5(90 ES-401 Facility:

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

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 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

0 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

3 2

2 1

3 2

2 1

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

5 REV 0

K1 KA Topic Imp.

K2 K3 A1 A2 G

Points REV 0 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 AA2.20 - Interlocks in effect on loss of ac vital electrical instrument bus that must be bypassed to restore normal equipment operation 3.9 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

0 0

4 2

K/A Category Totals:

Group Point Total:

REV 0

K1 KA Topic Imp.

K2 K3 A1 A2 G

PointsU 5(9

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

0 0

2 2

K/A Category Totals:

Group Point Total:

REV 0

REV 0 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 2.4.20 - Knowledge of operational implications of EOP warnings, cautions, and notes.

4.3 1

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

4.2 1

X 059 Main Feedwater A2.10 - Unloading (reduction of generated power) in steps over a period of time 2.9 1

X 064 Emergency Diesel Generator 5

0 0

0 0

3 2

K/A Category Totals:

0 0

0 0

0 Group Point Total:

REV 0

REV 0 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 A2.05 - Loss of PZR heaters 3.7 1

X 011 Pressurizer Level Control A2.03 - Blown power-supply fuses 2.9 1

X 072 Area Radiation Monitoring 3

0 0

0 0

2 1

K/A Category Totals:

0 0

0 0

0 Group Point Total:RE REV 0

Facility:

Palo Verde Generic Category KA KA Topic Imp.

Points Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 REV 0 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 0

Rev 0 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 NONE NONE NONE

Rev 0 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 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 Administrative Topics Outline Form ES-30'1-1 Facility: PVNGS Date of Examination: 03/19/12 Examination Level: RO 0 SRO D Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Notel 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 M,R drained to the Refueling Water Tank (RWT). (2.1.25)

Conduct of Operations Tech Review a permit (clearance) (2.2.13)

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

Radiation Control D

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 lopics, 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 (;c, 1)

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

ES-301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-30'1-1 Facility: PVNGS Date of Examination: 03/19/12 Examination Level: RO D SRO 0 Operating Test Number:

Administrative Topic Type I

Describe activity to be performed I

(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 N,R mid-loop (2.1.20)

Conduct of Operations Identify unit differences and applicable LCO due to loss of AC Inverter.

(2.2.3, 2.2.22)

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

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

Emergency Procedures/Plan NOTE: All items (5 total) are required fOI" 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 (5 3 for ROs; 5 4 fOI" SROs & RO retakes)

(N)ew or (M)odified from bank (2: 1)

(P)revious 2 exams (5 1; randomly selected)

ES-301, Page 22 of 27

.:;;;E...:;;S_-3;;..O;;..1:-________

C;;..o;:..:n:..;,.t::.r.=.o.;...1 ::....;R...:;;..o,;om/l n-Plant Systems Outline Form ES-301-2 Facility: PVNGS Date of Examination:

03/19/12 Exam Level: RO[~ SRO-I 0 SRO-U 0 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 (3.80.29 A2.D3)

L,D 8

b. Boration (normal path doesn't work) (3.2 0.0.4 A4.D7)

L,N,A 1

c. Startup second MFP (34 0.39 A4.D3)

N 4S

d. FiliaSIT (3,3DD6A1.13)

N 3

e. Pump RDT with hi9h temperature (3,50.0.7 A 20.5)

L,N,A 5

f.

Reset inadvertent MSIS (3.2 0.13 A4.D1)

L,D,A 2

g. Restore offsite power to PBA-SD3 (powered from DG 'A') (3.60.62 A4.Di)

D 6

h. Place CS B in service on SDC (3.4 0.0.5 A4.D1)

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 0.67 AA2.16)

N,A,E,R 4P

j. Operation of AFA-PD1 from Remote Shutdown Panel (34 0.61 A3.D1)

D,E 4S

k. Align offsite power to PBB per Appendix C of 4o.AO-9ZZ19 (3.6 0.62 A2.D6)

D,EN,E 6

All RO and 8RO-1 conlml mom (and ;n-planl),y,'em, mu,' be d;fferenl and,erve d;fferenl,alely ;J 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

- / - I ?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 L1/?1/.~1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-30'1-2 Facility: PVNGS Date of Examination:

03/19/12 Exam Level: ROD SRO-I 0 SRO-U 0 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)

L,D 8

b. Boration (normal path doesn't work) (3.2 004 ;'\\4.07)

L,N,A 1

c. FiliaSIT (3.3006A1.13)

N 3

d. Pump ROT with high temperature (3.5007 A2.05)

L,N.A 5

e. Reset inadvertent MSIS (3.2 013 A 4.01)

L,D.A 2

f.

Restore offsite power to PBA-S03 (powered from OG 'A') (3.6062 A 4.01)

D 6

g. ESO with no CIAS, CSAS with CIAS valves that fail to close (3.7012 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 SOC valves. during a Control Room Fire (4.2067 AA2.16)

N,A,E,R 4P

j. Operation of AFA-P01 from Remote Shutdown Panel (3.4 061 A3.01)

D,E 4S

k. Align offsite power to PBB per Appendix C of 40AO-9ZZ19 (3.6 062 A2.06)

D,EN,E 6

All RO and SRO-I control room (anc! 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 1 SRO-I 1 SRO-U (A)ltemate path 4-6 1 4-6 1 2-3 (C)ontrol room (O)irect from bank

'o9/s8/-;4 (E)mergency or abnormal in-plant

.1/;.1;;'1 (EN)gineered safety feature 1 ;.1 (control room system)

(L)ow-Power 1 Shutdown

1/~1/~1 (N)ew or (M)odified from bank including 1 (A)

~2/221 1 (P)revious 2 exams s 3 1 s 3 1 s 2 (randomly selected)

(R)CA 21/21/~1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-30'1-2 Facility: PVNGS Date of Examination: 03/19/12 Exam Level: ROO SRO-I 0 SRO-U 0 Operating Test No.:

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System 1 JPM Title Type Code*

Safety Function

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

L,D 8

b. Boration (normal path doesn't work) (3.2 004 }lA.07)

L,N,A 1

c. ESD with no CIAS, CSAS with CIAS valves that fail to close (3.7012 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)

N,A,E,R 4P

j. Operation of AFA-P01 from Remote Shutdown Panel (3.4 061 A3.01)

D,E 4S

k.

All RO and SRO-I control room (ane! 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/~1/21 (EN)gineered safety feature

- / -

1 21 (control room system)

(L)ow-Power I Shutdown 1/;,11?1 (N)ew or (M)odified from bank including 1 (A)

,2/22/21 (P)revious 2 exams s; 31 <; 31 <; 2 (randomly selected)

(R)CA

,1/;>11 1

(S)imulator ES-301, Page 23 of 27

Appendix D

Scenario Outline Form ES-D-l Facility: PVNGS Scenario No.: _~I-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.

I~

Malf. No.

Event Description 1

None N

Shift Turbine Cooling water pumps.

CO/SRO 2

cmTRCV05CHNL T227 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 mfRMOIA I

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

4 cmCPCC06EW APO I 5 C

Essential Cooling water pump "A" fails to auto staI1 on (In setup)

RO/SRO CREF AS actuation. RO will start EW pump "A".

(TS) 5 mffH06A 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 (TiS) 7 mffH06A f:50 1\\1 Steam Generator 1 Tube Leak degrades to a Rupture.

ALL 40EP-9E004, Steam Generator Tube Rupture 8

cmCPSIOlSIAP02 5 C

BPSI pump "A" fails to auto start on SIAS/CIAS actuation (In setup)

RO/SRO 9

mfRX01 f:0 J

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 CRITICAL TASK -Isolate faulted SG within 70 minutes of Isolation initiation of SGTR.

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-l 021, Revision 9 10f2

Appendix D

Scenario Outline 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.

Form ES-D-l Vibration shop repo:rted that in a review of data they found some unusual readings with Turbine Cooling Water pump "A". A vibration technician lllnd AO are have been briefed and are standing by for a TCW pump shift. Appendix "D" of 400P-9TCOl has been completed.

Equipment out of service:

Auxiliary Feedpump 'A' (AFA-P01) is tagged out due to a noisy bearing.

CS 'A' is tagged out for scheduled maintenance.

Planned shift activities:

Remove the "B" Turbine Cooling Water pump from service.

NUREG-1 021, Revision 9 20f2

Appendix D

Scenario Outline Form ES-D-l 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-POI and Containment Spray 'A' are tagged out.

Event No.

Malf. No.

Event Type*

Event Description 1

None N

Shift from Hydraulic Fluid Pump 8 to Pump A per section 4.7 of CO/SRO 400P-9COO I, Electro-Hydraulic Control System.

2 mfN102C f:O 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

mfTHOIA 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 IA03DI C

LOP relay failure. Crew responds using 41 AL-I RK I A (1 A03 D) doeED ZLS03727IDS WI CO/SRO Crew determines that a LOP should not have occurred and takes action to bypass the appropriate relays per 400P-9SAO 1 doRP ZLSAAC02ALOPI (TS)

WI 5

lOR dims ZDSGEUV170 R-RO An MSN goes closed. Crew responds per 40AL-9RK6A and N - CO/SRO begins a down power to less than 65% power.

6 cmCPTPO 1 CENPO 18 6 C

Stator Cooling Pump '8' trips with standby pump failing to auto CO/SRO start.

7 mffHO 1 A f:3 M

LOCA RCS leak degrades requiring a reactor trip.

ALL 40EP-9E003, Loss of Coolant Accident 8

Scenario file noSIICI C

SIAS/CIAS/MSrS fail to automatically initiate.

RO/SRO CRITCAL TASK - Initiate SI flow when the SIAS setpoint has been exceeded.

9 cmCPRH05SIBP03 6 C

CS pump "13" trips on an 86 lockout RO/SRO CRITCAL TASK -Initiate CS flow when the CSAS setpoint has been exceeded.

40EP-9E009, Functional Recovery Procedure End Scenario may bt! ended once point SIAS and CSAS flow have been established using LPSI.

  • (N)ormal, (R )eacti vi ty, (I)nstrument, ( C)omponent, (M)ajor NUREG-1 021, Revision 9 1 01'2

Appendix D

Scenario Outline Turnover Plant conditiol1ls:

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-POI) is tagged out due to a noisy bearing.

CS 'A' is tagged out for scheduled maintenance.

Planned shift activities:

Form ES-D-l The crew needs to shift EHC pumps from B to A to support vibration readings. The vibration tech is standing by.

NUREG-1 021, Revision 9 201'2

Appendix D

Scenario Outline Form ES-D-l Facility: PVNGS Scenario I

Op-TestNo:_ 2012 Examiners:

Operators:

Initial Conditions: (2% power, MOC).

Turnover: Unit 1 is at 4% power (200 EFPD). AFA-P01 and Containment Spray 'A' are tagged out.

Malf. No.

Event Description No.

1 None N

Shift the MFP Lub~: oil pumps per 4.9 of 400P-9FT02, CO/SRO Feedwater Pump Turbine B.

2 cmAVRC03RCEPV100F 1 C

Pressurizel: spray valve fails open.

RO/SRO 3

mfRP06L1 C

Inadvertent AF AS, "B" train AFW pumps and valves align to mfRP06L2 CO/SRO initiate AFW flow to the SGs. Crew takes actions to terminate 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 RO/SRO requiring the crew to take manual control ofthe controller f---.

5 mfEDI0B C

NBN-X04 faults and DG "B breaker fails to close causing a cmBKEG03PBBS04B 3 RO/SRO LOP of class 4160 bus, PBB-S04 (TS) 40AO-9ZZ12, Degraded Electrical.

6 mfRDIOB 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.

mfRD03M 40EP-9E002, Reactor Trip 8

cmAVMC01CDNHV45A 1 C

Loss of Main Condenser Vacuum. CO must shift feedwater CO/SRO flow to AFN-POl.

9 mfFW21A C

Trip of AFN-POI CO/SRO CRITICAL TASK - Implement the FRP to restore power to PBB-S04 and establish AFW flow to the SGs.

40EP-9E009, Functional Recovery Procedure End Crew has restored AFW flow to point the SGs

  • (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1 021, Revision 9 10f2

Appendix D

Scenario Outline Turnover Plant conditions:

Unit 1 is at 2% power.

The plant has been at 2% power for 2 days awaiting repair of AFA-PO 1.

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.

Form ES-D-l Maintenance was completed on Main Lube: Oil pump LON-P07B at the end of last shift and it is ready a be tested.

Equipment out of service:

Auxiliary Feedpump 'A' (AFA-P01) is tagged out due to a noisy bearing.

CS 'A' is tagged out for scheduled maintenance.

Planned shift activities:

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

NUREG-1 021, Revision 9 2 of2

Appendix D

Scenario Outline Form ES-D-I Facility: PYNGS Scenario No.'

4 Op-Test No:

2012 Examiners:

Operators:

Initial Conditions: (100% power, MOC).

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

Event No.

Malf. No.

Event 11 Event Description 1

None N

Shift Steam Bypass Master Controller, SGN-PIC-l 010 from CO/SRO manual to automatic mode of operation.

2 mfTRRXIISGCPTI013C 4 I

Channel "C" SG I pressure transmitter fails low requiring CO/SRO multiple parameters to be placed in bypass. (SGC-PI-l 013C)

(TS) 3 cmTRCY19RCALTI10X 4 I

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

(TS) 4 mfCHOIA C

Loss of Control Element Drive Mechanism cooling. HCN-A02B mfCHOIC CO/SRO and A02D fans fail to auto-start 40AO-9ZZ20, Loss of HV AC 5

mfMCOIA R-RO Loss of condenser vacuum requiring the crew to downpower.

N - CO/SRO 40AO-9ZZ07, Loss of Condenser Vacuum 6

mfCVIIA f: 1 00 C

RCP lA seal failure. Crew evaluates the status ofthe affected SRO RCP.

40AO-9ZZ04, Reactor Coolant Pump Emergencies 7

cmCPRC02RCEPO 1 A 6 M

RCP 1 A trips but PPS fails to initiate a reactor trip. RO opens mfRP04A ALL L03B2 and L 1 OB2 breakers on BO I.

mfRP04C CRITICAL TASK - Trip the Reactor prior to completion of mfRD12A SPTAs 8

mfED02 C

After the Reactivity Safety Function is addressed a Loss of mfEG06B ALL Offsite Power will occur. DG "B" will trip when it starts.

40EP-9E007, Loss of Offsite Power/Loss of Forced Circulation 9

cmCPCC08SP APO 1 5 C

Spray Pond pump "A" fails to auto stat1.

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

CRITICAL T ASK-Establish feed to at least one SG using AFN-P01.

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

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-l 021, Revision 9 I of I

Appendix D

Scenario Outline Turnover Plant conditiol1ls:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is ORANGE.

Train 8 is protected equipment.

AF '8' and AF 'N' are protected.

CS '8' is protected.

PC is NOT recircing the RWT.

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

Form ES-D-I I&C have completed testing on the SBCS master controller SGN-PIC-J 0 10 and it can be returned to automatic operation.

Equipment out of service:

Auxiliary Feedpump 'A' (A FA-PO J) is tagged out due to a noisy bearing.

CS 'A' is tagged out for scheduled maintenance.

Planned shift activities:

Shift SGN-PIC-J 010 from manual to automatic mode of operation.

NUREG-l 021, Revision 9 20f2

=E~S~-3~O~1~ ______________ ~T~r=a~n~sl:*e:~n~t=a~n=d~E~v~e~n~t~C~h~e=c~k~lis~t~ _________ ~F~o_r~m~E=S~-~

Date of Exam:

3/16-3/24/2012 Operating Test No.:

A E

Scenarios P

V 1

2 3

4 T

M P

E L

N CREW CREW CREW CREW 0

I I

T POSITION POSITION POSITION POSITION T

N I

C S

A B

S A

B S

A B

S A

B A

M A

T R

T 0

R T

0 R

T 0

R T

0 L

U N

Y 0

C P

0 C

P 0

C P

0 C

P M(*)

T P

E R

I U RO RX 0

1 1 0 NOR 1,5 2

1 1

1 Ri, R5, I/G 2,4,5 2,4,6 7

4 4

2 R9,R11,

,8 R13 MAJ 7

7 2

2 2

1 TS 0

0 2

2 RO RX 5

1 1

1 0

NOR 1

1 1

1 1

R2,R10, I/G 3,5, 3,8, 7

4 4

2

R12, 6,9 9

R14 MAJ 7

7 2

2 2

1 TS 0

0 2

2 RO RX 0

1 1

0 NOR 1,5 1

3 1

1 1

R3,R7 I/G 2,4,5 2,4,6 3,8,9 10 4

4 2

,8 MAJ 7

7 6

3 2

2 1

TS 0

0 2

2 RO RX 5

1 1

1 0 NOR 1

1 2

1 1

1 R4, R6, I/G 3,5, 3,

3,8,9 10 4

4 2

R8 6,9 8,9 MAJ 7

7 6

3 2

2 1

TS 0

0 2

RO RX 0

1 1

NOR 1

1 1

1 Ri5 I/G 2,4,5 3,8,9 7

4 4

2

,8 MAJT" 6

2 2

2 1

TS 0

0 2

2

rde Date of Exam:

3/16-3/24/2012 Operating Test No.:

A E

Scenarios P

V 1

2

3.

4 T

M P

E L

N CREW CHEW CREW CREW 0

I I

T POSITION POSITION POSITION POSITION T

N I

C S

A B

S

.A.

B S

A B

S A

B A

M A

T R

T 0

R T

0 R

T 0

R T

0 L

U N

Y 0

C P

0

('

P 0

C P

0 C

P M(*)

T P

E R

I U SRO-U RX 0

1 1

0 NOR 1

2 1

1 1

U1, U5 lIe 2,3,4 2,3,4 14 4

4 2

,~),6,

,5,7, B,9 8,9 MAJ 7

6 2

2 ~E TS 4,5,6 3,5 5

0 2

2 SRO-U RX 0

1 1 0 NOR 1,5 1

3 1

1 1

U2,U3 lie 2,3,4 2,3,4 13 4

4 2

,6,8,

,5,7, 9

8,9 MAJ 7

6 2

2 I 2 1

TS 3,4 3,5 4

0 2

2 SRO-U RX 0

1 1

0 NOR 1,5 1

3 1

1 1

U4 lie 2,4,6 2,3,4 10 4

4 2

,5,7, 8,9 MAJ 7

6 2

2 2

1 TS 3,5 2

0 2

SRO-I RX 0

1 1

0 NOR 1

1,5 3

1 1

1 11,12,13, lIe 2,3,4 2,3,4 2,4,5 17 4

4 2

14,15

,Ei,6,

,6,8,

,7 8,9 9

MAJ 7

7 6

1 TS 4,5,6 3,4 5

0 2

2 SRO-I RX

5 1

1 1 0 NOR 1

1 2

1 1

1 16 lIe 2,3,4 38, 2,3,4 17 4

4 2

,EI,6, 9

,5,7, 8,9 8,9 MAJ 7

7 6

3 2

2 1

TS 4,5,6 3,5 5

0 2

2

Date of Exam:

3/16-3/24/2012 Operating Test No.:

A E

Scenarios P

V 1

2 3

4 T

M P

E L

N CREW CHEW CREW CREW 0

I I

T POSITION POSITION POSITION POSITION T

N I

C S

A B

S A

B S

A B

S A

B A

M A

T R

T 0

R T

0 R

T 0

R T

0 L

U N

Y 0

C P

0

('

P 0

C P

0 C

P M(*)

T P

E R

I U

SRO-I RX 0

1 1

0 NOR 1

1,5 3

1 1

1 17 IIC 3,5, 2,3,4 2,4,5 14 4

4 2

6,9

,6,8,

,7 9

MAJ 7

7 6

3 2

2 1

TS

-l 3,4 2

0 2

2 Scenario RX 5

1 1

0 4(spare)

NOR 1,5 1,5 1

1 1

totals IIC 3,

2,4,8 4

4 2

8,9 MAJ 7

7 7

2 2

1 TS 2,3 0

2 2

Instructions:

1.

Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one IIC malfunction can be credited toward the two IIC malfunctions required for the ATC position.

2.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3.

Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

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