ML17172A692

Section 1 - Draft Administrative Documents

ML17172A692
Person / Time
Site:	North Anna
Issue date:	06/22/2017
From:	Virginia Electric & Power Co (VEPCO)
To:	NRC/RGN-II
References
Download: ML17172A692 (44)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: NORTH ANNA POWER STATION Date of Exam:

JUNE 2016 Tier Group RO K/A Category Points SRO-Only Points K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G* Total A2 G* Total 1. Emergency & Abnormal Plant Evolutions 1 3 3 3 N/A 3 3 N/A 3 18 3 3 6 2 1 1 2 2 2 1 9 2 2 4 Tier Totals 4 4 5 5 5 4 27 5 5 10 2. Plant Systems 1 3 2 2 2 3 3 2 3 2 3 3 28 3 2 5 2 1 1 1 1 1 1 1 0 1 1 1 10 0 1 2 3 Tier Totals 4 3 3 3 4 4 3 3 3 4 4 38 4 4 8 3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 2 2 3 3 1 2 2 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). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category). 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 with justification; 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 a category 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.

G* Generic K/As

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions

- Tier 1/Group 1 (RO / SRO) E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G* K/A Topic(s)

IR # 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization

- Recovery / 1 X 007EA2.06: Ability to determine or interpret the following as they apply to a reactor trip:

Occurrence of a reactor trip 4.3 000008 Pressurizer Vapor Space Accident / 3 X X 008AK1.01:

Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: Thermodynamics and flow characteristics of open or leaking valves. 008AG2.4.20: 008AK1.01:

Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space Accident: Knowledge of the operational implications of EOP warnings, cautions, and notes 3.2 4.3 000009 Small Break LOCA / 3 X 009EG2.4.21: Knowledge of the parameters and logic used to assess the status of safety lfunctions, such as reactivity control, core cooling and heat removal, reactor lcoolant system integrity, containment conditions, radioactivity release control, letc.

4.0 000011 Large Break LOCA / 3 X 011EA1.09: Ability to operate and monitor Core flood tank initiation as they apply to a Large Break LOCA 4.3 000015/17 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup / 2 X 022A2.02: Knowledge of the interrelations between the Loss of Reactor Coolant Makeup and Charging pump problems. 3.2 000025 Loss of RHR System / 4 X 025AK1.01: Knowledge of the operational implications of the Loss of RHR System during all modes of operation as they apply to Loss of Residual Heat Removal System:

3.9 000026 Loss of Component Cooling Water / 8 000027 Pressurizer Pressure Control System Malfunction / 3 X 027AK2.03: Knowledge of the interrelations between the Pressurizer Pressure Control Malfunctions and Controllers and positioners 2.6 000029 ATWS / 1 X 029EK3.03: Knowledge of the reasons for Opening BIT inlet and outlet valves as the apply to the ATWS.

3.7 000038 Steam Gen. Tube Rupture /

3 X 038EK3.03: Knowledge of the reasons for Automatic actions associated with high radioactivity in S/G sample lines as the apply to the SGTR.

3.6 000040 (BW/E05; CE/E05; W/E12) Steam Line Rupture

- Excessive Heat Transfer / 4 X 040AK2.01: Knowledge of the interrelations between the Steam Line Rupture and the valves.

2.6 000054 (CE/E06) Loss of Main Feedwater / 4 X X 054AG2.4.20: Knowledge of the operational implications of EOP warnings, cautions, and notes.

054AG2.1.19: Ability to use plant computers to evaluate system or component status.

3.8 3.8 000055 Station Blackout / 6 X X 055EA1.02: Ability to operate and monitor Manual ED/G start as applied to a Station Blackout 055EA2.03: Ability to determine or interpret actions necessary to restore power as they apply to a Station Blackout. 4.3 4.7 Tier 1 / Group 1 (RO / SRO) Page 1 of 2

000056 Loss of Off

-site Power / 6 X 056AK3.01: Knowledge of the reasons order and time to initiation of power for the load sequencer as they apply to the Loss of Offsite Power:

3.5 000057 Loss of Vital AC Inst. Bus / 6 X 057AA2.02: Ability to determine and interpret Core flood tank pressure and level indicators as they apply to the Loss of Vital AC Instrument Bus.

3.7 000058 Loss of DC Power / 6 X X 058AG2.4.11: Knowledge of abnormal condition procedures.

058AG2.1.20: Ability to interpret and execute procedure steps. 4.0 4.6 000062 Loss of Nuclear Svc Water / 4 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / 3 X WE04EK1.1: Knowledge of the operational implications of the Components, capacity, and function of emergency systems as they apply to the LOCA Outside Containment.

3.5 W/E11 Loss of Emergency Coolant Recirc. / 4 X WE11EK2.2: Knowledge of the interrelations between the Loss of Emergency Coolant Recirculation and 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.

3.9 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 X X WE05EA1.1: Ability to operate and / or monitor components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. as they apply to the Loss of Secondary Heat Sink.

WE05EA2.2: Ability to determine and interpret adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments as they apply to the Loss of Secondary Heat Sink.

4.1 4.3 000077 Generator Voltage and Electric Grid Disturbances / 6 X 077AA2.05: Ability to determine and interpret operational status of offsite circuit as they apply to Generator Voltage and Electric Grid Disturbances.

3.2 K/A Category Totals:

3 3 3 3 3/3 3/3 Group Point Total:

18/6 Tier 1 / Group 1 (RO / SRO) Page 2 of 2

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions

- Tier 1/Group 2 (RO / SRO) E/APE # / Name / Safety Function K 1 K 2 K 3 A 1 A 2 G* K/A Topic(s)

IR # 000001 Continuous Rod Withdrawal / 1 X 001AA2.04: Ability to determine and interpret reactor power and its trend as they apply to the Continuous Rod Withdrawal 4.3 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 X 028AK1.01: Knowledge of the operational implications of PZR reference leak abnormalities as they apply to PZR Level Control Malfunctions:

2.8 000032 Loss of Source Range NI / 7 X 032AA2.04: Ability to determine and interpret satisfactory source

-range/intermediate

-range overlap as they apply to the Loss of Source Range Nuclear Instrumentation 3.1 000033 Loss of Intermediate Range NI / 7 X 033AK3.01: Knowledge of the reasons for the termination of startup following loss of intermediate range instrumentation .

3.2 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak

/ 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid Radwaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 X X 060AK2.01: Knowledge of the interrelations between the Accidental Gaseous Radwaste

Release and the ARM system, including the normal radiation

-level indications and the operability status

. 060AG2.4.30: Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. 2.6 4.1 000061 ARM System Alarms / 7 X 061AA2.03: Ability to determine and interpret setpoints for alert and high alarms as they apply to the Area Radiation Monitoring (ARM) System Alarms. 3.3 000067 Plant Fire On

-site / 8 X 067AA1.05: Ability to operate and / or monitor plant and control room ventilation systems as they apply to the Plant Fire on Site.

3.0 000068 (BW/A06) Control Room Evac. / 8 X 068AK3.17: Knowledge of the reasons for injection of boric acid into the RCS as they apply to the Control Room Evacuation

. 3.7 000069 (W/E14) Loss of CTMT Integrity / 5 X WE14EG2.4.21: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

4.6 000074 (W/E06&E07)

Inad. Core Cooling

/ 4 000076 High Reactor Coolant Activity / 9 X 076AA2.03: Ability to determine and interpret RCS radioactivity level meter as they apply to the High Reactor Coolant Activity

. 2.5 W/EO1 & E02 Rediagnosis

& SI Termination

/ 3 W/E13 Steam Generator Over

-pressure / 4 W/E15 Containment Flooding / 5 Tier 1 / Group 2 (RO / SRO) Page 1 of 2 W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI

-X/Y / 7 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X WE09EG2.4.31: Knowledge of annunciator alarms , indications , or response procedures

. BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling

- PTS / 4 X WE08EA1.1: Ability to operate and / or monitor components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and

manual features as they apply to Pressurized Thermal Shock.

3.8 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals:

1 1 2 2 2/2 1/2 Group Point Total:

9/4

Tier 1 / Group 2 (RO / SRO) Page 2 of 2

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2/Group 1 (RO / SRO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G* K/A Topic(s)

IR # 003 Reactor Coolant Pump X

X 003K5.02: Knowledge of the operational implications of effects of RCP coastdown on RCS parameters as they apply to the RCP S. 003K6.14: Knowledge of the effect of a loss or malfunction on the starting requirements will have on the RCPS

. 2.8 2.6 004 Chemical and Volume Control X 004A2.22: Ability to (a) predict the impacts of a mismatch of letdown and changing flows on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of the mismatch. 3.2 005 Residual Heat Removal X X 005A1.07: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RHRS controls including Determination of test acceptability by comparison of recorded valve response times with Tech

-Spec requirements

. 005A2.01: Ability to (a) predict the impacts of

failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

2.5 2.7 006 Emergency Core Cooling X

X 006K5.07: Knowledge of the operational implications expected temperature levels in various locations of the RCS due to various plant conditions as they apply to ECCS

. 006K6.05: Knowledge of the effect of a loss or malfunction of HPI/LPI cooling water wi ll have on the ECCS.

2.7 3.0 007 Pressurizer Relief/Quench Tank X 007G2.1.20: Ability to interpret and execute procedure steps.

4.6 008 Component Cooling Water X 008K2.02: Knowledge of bus power supplies to CCW pump, including emergency backup

. 3.0 010 Pressurizer Pressure Control X 010K6.02: Knowledge of the effect of a loss or malfunction of the PZR will have on the PZR PCS. 3.2 012 Reactor Protection X X 012K4.04: Knowledge of RPS design

feature(s) and/or interlock(s) which provide for redundancy. 012A2.04: Ability to (a) predict the impacts of faulty or erratic operation of detectors and function generators on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations

3.1 3.2 Tier 2 / Group 1 (RO / SRO) Page 1 of 3

013 Engineered Safety Features Actuation X X 013A4.01: Ability to manually operate and/or monitor in the control room

ESFAS-initiated equipment which fails to actuate

. 013A2.04: Ability to (a) predict the impacts of the loss of instrument bus on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

4.5 4.2 022 Containment Cooling X 022K4.05: Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following:

Containment cooling after LOCA destroys ventilation ducts 2.6 025 Ice Condenser 026 Containment Spray X 026A1.06: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including:

Containment spray pump cooling 2.7 039 Main and Reheat Steam X X 039K5.08: Knowledge of the operational implications of the effect of steam removal on reactivity as applied to the MRSS

. 039A2.03: Ability to (a) predict the impacts of

Indications and alarms for main steam and area radiation monitors (during SGTR) on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

3.6 3.7 059 Main Feedwater X 059A3.02: Ability to monitor automatic operation of the MFW, including programmed levels of the S/G

. 2.9 061 Auxiliary/Emergency Feedwater X 061K2.03: Knowledge of bus power supplies to the following

AFW diesel driven pump 4.0 062 AC Electrical Distribution X X 062A2.11: Ability to (a) predict the impacts of the aligning standby equipment with correct emergency power source (D/G) on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those

malfunctions or operations

. 062G2.4.11: Knowledge of abnormal condition procedures.

3.7 4.0 063 DC Electrical Distribution X 063K3.01: Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following:

ED/G. 3.7 064 Emergency Diesel Generator X X 064A4.01: Ability to manually operate and/or monitor in the control room

Local and remote operation of the ED/G

. 064K3.03: Knowledge of the effect that a loss or malfunction of the ED/G system will have on the following:

ED/G (manual loads)

. 4.0 3.6 073 Process Radiation Monitoring X 073K1.01: Knowledge of the physical connections and/or cause

-effect relationships between the PRM system and those systems served by PRMs

. 3.6 Tier 2 / Group 1 (RO / SRO) Page 2 of 3

076 Service Water X X X 076A3.02: Ability to monitor automatic operation of the SWS, including emergency heat loads

. 076A4.01: Ability to manually operate and/or monitor in the control room:

SWS pumps 076G2.1.25: Ability to interpret reference materials, such as graphs, curves, tables, etc. 3.7 2.9 4.2 078 Instrument Air X X 078G2.1.31: Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

078K1.05: Knowledge of the physical connections and/or cause

-effect relationships between the IAS and MSIV air. 4.6 3.4 103 Containment X X 103K1.03: Knowledge of the physical connections and/or cause

-effect relationships between the containment system and shield building vent system. 103G2.2.38: Knowledge of conditions and limitations in the facility license.

3.1 4.5 K/A Category Point Totals:

3 2 2 2 3 3 2 3/3 2 3 3/2 Group Point Total:

28/5

Tier 2 / Group 1 (RO / SRO) Page 3 of 3

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems

- Tier 2/Group 2 (RO / SRO) System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G* K/A Topic(s)

IR # 001 Control Rod Drive 002 Reactor Coolant X 002K5.10: Knowledge of the operational implications of the relationship between reactor power and RCS differential temperature a s they apply to the RCS 3.6 011 Pressurizer Level Control X 011K4.05: Knowledge of PZR LCS design feature(s) and/or interlock(s) which provide for PZR level inputs to RPS

. 3.7 014 Rod Position Indication X 014A1.02: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS controls, including Control rod position indication on control room panels

. 3.2 015 Nuclear Instrumentation X 015G2.2.25: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

4.2 016 Non-Nuclear Instrumentation 017 In-Core Temperature Monitor X 017K6.01: Knowledge of the effect of a loss or malfunction of the following ITM system components

Sensors and detectors

. 2.7 027 Containment Iodine Removal X 027K2.01: Knowledge of bus power supplies to the following: Fans. 3.1 028 Hydrogen Recombiner and Purge Control X 028A2.01: Malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Hydrogen recombiner power setting, determined by using plant data book 3.6 029 Containment Purge X 029K1.05: Knowledge of the physical connections and/or cause

-effect relationships between the Containment Purge System and Containment air cleanup and recirculation system

. 2.9 033 Spent Fuel Pool Cooling X 033G2.2.3: Knowledge of the design, procedural, and operational differences between units.

2.7 034 Fuel Handling Equipment 035 Steam Generator X 035A4.01: Ability to manually operate and/or monitor in the control room

Fill of dry S/G 2.7 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal X 055K3.01: Knowledge of the effect that a loss or malfunction of the CARS will have on the Main condenser 2.5 056 Condensate Tier 2 / Group 2 (RO / SRO) Page 1 of 2

068 Liquid Radwaste X 068A3.01: Ability to monitor automatic operation of the Liquid Radwaste System including Evaporator pressure control

. 2.5 071 Waste Gas Disposal X 07 1G2.4.21: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

4.6 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection K/A Category Point Totals:

1 1 1 1 1 1 1 0/1 1 1 1/2 Group Point Total:

10/3

Tier 2 / Group 2 (RO / SRO) Page 2 of 2

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: NORTH ANNA POWER STATION Date of Exam: JUNE 2016 Category K/A # Topic RO SRO-Only IR # IR # 1. Conduct of Operations 2.1.14 Knowledge of criteria or conditions that require plant

-wide announcements, such as pump starts, reactor trips, mode changes, etc.

3.1 2.1.36 Knowledge of procedures and limitations involved in core alterations.

3.0 2.1.40 Knowledge of refueling administrative requirements.

3.9 2.1. Subtotal 2 1 2. Equipment Control 2.2.20 Knowledge of the process for managing troubleshooting activities 2.6 2.2.40 Ability to apply Technical Specifications for a system.

3.4 2.2.14 Knowledge of the process for controlling equipment configuration or status 4.3 2.2.21 Knowledge of pre

- and post-maintenance operability requirements.

4.1 Subtotal 2 2 3. Radiation Control 2.3.11 Ability to control radiation releases 3.8 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high

-radiation areas, aligning filters, etc.

3.2 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

2.9 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

3.8 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

3.1 2.3. Subtotal 3 2 4. Emergency Procedures / Plan 2.4.14 Knowledge of general guidelines for EOP usage.

3.8 2.4.26 Knowledge of facility protection requirements, including fire brigade and portable firefighting equipment usage.

3.1 2.4.39 Knowledge of RO responsibilities in emergency plan implementation. l 3.9 2.4.27 Knowledge of "fire in the plant" procedures.

3.9 2.4.30 Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator.

4.1 2.4. Subtotal 3 2 Tier 3 Point Total 10 7