Text

04- Draft Outlines
	ML14140A111
Person / Time
Site:	Waterford
Issue date:	04/02/2014
From:	Chris Steely; Operations Branch IV
To:	;
	laura hurley
References
	Download: ML14140A111 (64)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: Waterford 3 (RO Exam Outline) Date of Exam: April 2, 2014 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

1. 1 3 3 3 3 3 3 18 6 Emergency &

Abnormal 2 1 2 1 N/A 2 2 N/A 1 9 4 Plant Evolutions Tier Totals 4 5 4 5 5 4 27 10 1 3 2 3 3 2 2 3 2 3 3 2 28 5 2.

Plant 2 1 1 1 1 1 1 1 1 1 1 0 10 3 Systems Tier Totals 4 3 4 4 3 3 4 3 4 4 2 38 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 2 3 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

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

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

2014 NRC Revision 1

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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 EK2.1 - Knowledge of the interrelations between the 000007 (BW/E02&E10; CE/E02) Reactor X (Reactor Trip Recovery) and the following: Components, 3.3 1 Trip - Stabilization - Recovery / 1 and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

AA2.01 - Ability to determine and interpret the following 000008 Pressurizer Vapor Space X as they apply to the Pressurizer Vapor Space Accident: 3.9 1 Accident / 3 RCS pressure and temperature indicators and alarms EK2.03 - Knowledge of the interrelations between the 000009 Small Break LOCA / 3 X small break LOCA and the following: S/Gs 3.0 1 2.4.11 -Knowledge of abnormal condition procedures.

000011 Large Break LOCA / 3 X 4.0 1 AK3.04 - Knowledge of the reasons for the following 000015/17 RCP Malfunctions / 4 X responses as they apply to the Reactor Coolant Pump 3.1 1 Malfunctions (Loss of RC Flow): Reduction of power to below the steady state power- to-flow limit AA1.01 -Ability to operate and / or monitor the following 000022 Loss of Rx Coolant Makeup / 2 X as they apply to l the Loss of Reactor Coolant Makeup: 3.4 1 CVCS letdown and charging AK1.01 - Knowledge of the operational implications of 000025 Loss of RHR System / 4 X the following concepts as they apply to Loss of Residual 3.9 1 Heat Removal System: Loss of RHRS during all modes of operation 000026 Loss of Component Cooling Water / 8 AA2.15 - Ability to determine and interpret the following 000027 Pressurizer Pressure Control X as they apply to the Pressurizer Pressure Control 3.7 1 System Malfunction / 3 Malfunctions: Actions to be taken if PZR pressure instrument fails high EA1.06 - Ability to operate and monitor the following as 000029 ATWS / 1 X they apply to a ATWS: Operating switches for normal 3.2 1 charging header isolation valves EK1.02 - Knowledge of the operational implications of 000038 Steam Gen. Tube Rupture / 3 X the following concepts as they apply to the SGTR: Leak 3.2 1 rate vs. pressure drop 2.1.27 - Knowledge of system purpose and/or function.

000040 (BW/E05; CE/E05; W/E12) X 3.9 1 Steam Line Rupture - Excessive Heat Transfer / 4 EK2.1 - Knowledge of the interrelations between the 000054 (CE/E06) Loss of Main X (Loss of Feedwater) and the following: Components, and 3.3 1 Feedwater / 4 functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features EK1.01 - Knowledge of the operational implications of 000055 Station Blackout / 6 X the following concepts as they apply to the Station 3.3 1 Blackout : Effect of battery discharge rates on capacity AA2.40 - Ability to determine and interpret the following 000056 Loss of Off-site Power / 6 X as they apply to the Loss of Offsite Power: Service water 3.3 1 pump ammeter and flowmeter AK3.01 - Knowledge of the reasons for the following 000057 Loss of Vital AC Inst. Bus / 6 X responses as they apply to the Loss of Vital AC 4.1 1 Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus 2014 NRC Revision 1

AK3.02 - Knowledge of the reasons for the following 000058 Loss of DC Power / 6 X responses as they apply to the Loss of DC Power: Actions 4.0 1 contained in EOP for loss of dc power 2.2.36 - Ability to analyze the effect of maintenance 000062 Loss of Nuclear Svc Water / 4 X activities, such as degraded power sources, on the status 3.1 1 of limiting conditions for operations.

AA1.01 - Ability to operate and / or monitor the 000065 Loss of Instrument Air / 8 X following as they apply to the Loss of Instrument Air: 2.7 1 Remote manual loaders W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18/6 2014 NRC Revision 1

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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 AA1.06 - Ability to operate and / or monitor the 000003 Dropped Control Rod / 1 X 4.0 1 following as they apply to the Dropped Control Rod: RCS pressure and temperature AA2.03 - Ability to determine and interpret the 000005 Inoperable/Stuck Control Rod / 1 X 3.5 1 following as they apply to the Inoperable / Stuck Control Rod: Required actions if more than one rod is stuck or inoperable 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 2.1.25 - Ability to interpret reference materials, 000032 Loss of Source Range NI / 7 X 3.9 1 such as graphs, curves, tables, etc.

000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 AA2.15 - Ability to determine and interpret the 000037 Steam Generator Tube Leak / 3 X 3.4 1 following as they apply to the Steam Generator Tube Leak: Magnitude of atmospheric radioactive release if cool-down must be completed using steam dump or atmospheric reliefs 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 AK1.01 - Knowledge of the operational 000061 ARM System Alarms / 7 X 2.5 1 implications of the following concepts as they apply to Area Radiation Monitoring (ARM)

System Alarms: Detector limitations 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity / 5 EK2.09 - Knowledge of the interrelations 000074 (W/E06&E07) Inad. Core Cooling / 4 X 2.6 1 between the and the following Inadequate Core Cooling: Controllers and positioners AK3.06 - Knowledge of the reasons for the 000076 High Reactor Coolant Activity / 9 X 3.2 1 following responses as they apply to the High Reactor Coolant Activity : Actions contained in EOP for high reactor coolant activity W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 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 2014 NRC Revision 1

BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 AK2.2 - Knowledge of the interrelations between CE/A16 Excess RCS Leakage / 2 X 3.0 1 the (Excess RCS Leakage) and the following:

Facilitys 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.

EA1.3 -Ability to operate and / or monitor the CE/E09 Functional Recovery X 3.6 1 following as they apply to the (Functional Recovery): Desired operating results during abnormal and emergency situations.

K/A Category Point Totals: 1 2 1 2 2 1 Group Point Total: 9/4 2014 NRC Revision 1

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 K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K6.02 - Knowledge of the effect of a loss or 003 Reactor Coolant Pump X malfunction on the following will have on 2.7 1 the RCPS: RCP seals and seal water supply A2.18 - Ability to (a) predict the impacts of 004 Chemical and Volume X the following malfunctions or operations on 3.1 1 Control the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High VCT level K6.03 - Knowledge of the effect of a loss or 005 Residual Heat Removal X malfunction on the following will have on 2.5 1 the RHRS: RHR heat exchanger K3.02 - Knowledge of the effect that a loss 006 Emergency Core Cooling X X or malfunction of the ECCS will have on the 4.3 1 following: Fuel K4.25 - Knowledge of ECCS design 2.8 1 feature(s) and/or interlock(s) which provide for the following: Concentrated boric acid supply to RWST K1.03 - Knowledge of the physical 007 Pressurizer Relief/Quench X X connections and/or cause-effect relationships 3.0 1 Tank between the PRTS and the following systems: RCS K4.01 - Knowledge of PRTS design feature(s) and/or interlock(s) which provide 2.6 1 for the following: Quench tank cooling K3.02 - Knowledge of the effect that a loss 008 Component Cooling Water X X or malfunction of the CCWS will have on 2.9 1 the following: CRDS A1.02 - Ability to predict and/or monitor 2.9 1 changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including: CCW temperature A2.01 - Ability to (a) predict the impacts of 010 Pressurizer Pressure Control X the following malfunctions or operations on 3.3 1 the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Heater failures K5.01 - Knowledge of the operational 012 Reactor Protection X implications of the following concepts as the 3.3 1 apply to the RPS: DNB 013 Engineered Safety Features X A4.03 - Ability to manually operate and/or 4.5 1 Actuation monitor in the control room: ESFAS initiation 022 Containment Cooling X X K2.01 - Knowledge of power supplies to the 3.0 1 following: Containment cooling fans A3.01 - Ability to monitor automatic operation of the CCS, including: Initiation of 4.1 1 safeguards mode of operation 2014 NRC Revision 1

025 Ice Condenser This system is not part of plant design, but included in random selection process.

A1.03 - Ability to predict and/or monitor 026 Containment Spray X changes in parameters (to prevent exceeding 3.5 1 design limits) associated with operating the CSS controls including: Containment sump level K4.04 - Knowledge of MRSS design 039 Main and Reheat Steam X feature(s) and/or interlock(s) which provide 2.9 1 for the following: Utilization of steam pressure program control when steam dumping through atmospheric relief/dump valves, including T-ave. limits A3.03 - Ability to monitor automatic 059 Main Feedwater X X operation of the MFW, including: Feedwater 2.5 1 pump suction flow pressure 2.1.28 - Knowledge of the purpose and 4.1 1 function of major system components and controls.

A1.05 -Ability to predict and/or monitor 061 Auxiliary/Emergency X changes in parameters (to prevent exceeding 3.6 1 Feedwater design limits) associated with operating the AFW controls including: AFW flow/motor amps A4.01 - Ability to manually operate and/or 062 AC Electrical Distribution X monitor in the control room: All breakers 3.3 1 (including available switchyard) 2.4.8 - Knowledge of how abnormal 063 DC Electrical Distribution X operating procedures are used in conjunction 3.8 1 with EOPs.

K2.03 - Knowledge of bus power supplies to 064 Emergency Diesel Generator X the following: Control power 3.2 1 K5.03 - Knowledge of the operational 073 Process Radiation X implications as they apply to concepts as 2.9 1 Monitoring they apply to the PRM system: Relationship between radiation intensity and exposure limits K1.20 - Knowledge of the physical 076 Service Water X X connections and/or cause- effect 3.4 1 relationships between the SWS and the following systems: AFW K3.07 - Knowledge of the effect that a loss or malfunction of the SWS will have on the 3.7 1 following: ESF loads K1.02 - Knowledge of the physical 078 Instrument Air X X connections and/or cause-effect relationships 2.7 1 between the IAS and the following systems:

Service air A4.01 - Ability to manually operate and/or monitor in the control room: Pressure gauges 3.1 1 A3.01 - Ability to monitor automatic 103 Containment X operation of the containment system, 3.9 1 including: Containment isolation K/A Category Point Totals: 3 2 3 3 2 2 3 2 3 3 2 Group Point Total: 28/5 2014 NRC Revision 1

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 K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K4.05 - Knowledge of CRDS design feature(s) 001 Control Rod Drive X and/or interlock(s) which provide for the 3.9 1 following: Boration and dilution.

002 Reactor Coolant A3.02 - Ability to monitor automatic operation 011 Pressurizer Level Control X of the PZR LCS, including: Reactor power 2.6 1 014 Rod Position Indication K6.03 - Knowledge of the effect of a loss or 015 Nuclear Instrumentation X malfunction on the following will have on the 2.6 1 NIS: Component interconnections K5.01 - Knowledge of the operational 016 Non-nuclear Instrumentation X implication of the following concepts as they 2.7 1 apply to the NNIS: Separation of control and protection circuits K1.02 - Knowledge of the physical connections 017 In-core Temperature Monitor X and/or cause-effect relationships between the 3.3 1 ITM system and the following systems: RCS 027 Containment Iodine Removal A1.02 - Ability to predict and/or monitor 028 Hydrogen Recombiner X changes in parameter (to prevent exceeding 3.4 1 and Purge Control design limits) associated with operating the HRPS controls including: Containment pressure K3.01 - Knowledge of the effect that a loss or 029 Containment Purge X malfunction of the Containment Purge System 2.9 1 will have on the following: Containment parameters 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment Randomly selected this system for a RO question. Accounted for in SRO exam per ES-401-2 instructions.

035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste A2.02 - Ability to (a) predict the impacts of the 071 Waste Gas Disposal X following malfunctions or operations on the 3.3 1 Waste Gas Disposal System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Use of waste gas release monitors, radiation, gas flow rate, and totalizer 072 Area Radiation Monitoring 2014 NRC Revision 1

K2.03 - Knowledge of bus power supplies to 075 Circulating Water X the following: Emergency/essential SWS 2.6 1 pumps 079 Station Air A4.02 - Ability to manually operate and/or 086 Fire Protection X monitor in the control room: Fire Detection 3.5 1 Panels K/A Category Point Totals: 1 1 1 1 1 1 1 1 1 1 0 Group Point Total: 10/3 2014 NRC Revision 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Waterford 3 (RO Exam Outline) Date of Exam: April 2, 2014 Category K/A # Topic RO SRO-Only IR # IR #

Knowledge of individual licensed operator responsibilities related to 2.1.4 shift staffing, such as medical requirements, no-solo operation, 3.3 1 maintenance of active license status, 10CFR55, etc.

1. Ability to coordinate personnel activities outside the control room.

Conduct 2.1.8 3.4 1 of Operations Knowledge of RO duties in the control room during fuel handling, such 2.1.44 as responding to alarms from the fuel handling area, communication 3.9 1 with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

2.1.

Subtotal 3 Ability to perform pre-startup procedures for the facility, including 2.2.1 operating those controls associated with plant equipment that could 4.5 1 affect reactivity.

Knowledge of pre- and post-maintenance operability requirements.

2. 2.2.21 2.9 1 Equipment 2.2.

Control Subtotal 2 Ability to use radiation monitoring systems, such as fixed radiation 2.3.5 monitors and alarms, portable survey instruments, personnel monitoring 2.9 1 equipment, etc.

Knowledge of radiation monitoring systems, such as fixed radiation

3. 2.3.15 monitors and alarms, portable survey instruments, personnel monitoring 2.9 1 Radiation equipment, etc.

Control 2.3.

Subtotal 2 Knowledge of the organization of the operating procedures network for 2.4.5 normal, abnormal, and emergency evolutions. 3.7 1 Knowledge of low power/shutdown implications in accident (e.g., loss

4. 2.4.9 of coolant accident or loss of residual heat removal) mitigation 3.8 1 Emergency strategies.

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

2.4.

Subtotal 3 Tier 3 Point Total 10 7 2014 NRC Revision 1

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 2/1 025 Ice Condenser This system was selected for a question in the RO exam. Since this system is not part of the Waterford 3 design, another system was randomly selected for the question.

1/1 022 Loss of Reactor Originally selected AK2 area for a question. None of the K/A Coolant Makeup statements had an Importance Rating above 2.5. Reselected 026 Loss of Component Cooling Water in the AK2 area. Reselected an AA1 area question for 022 Loss of Reactor Coolant Makeup.

1/1 026 Loss of Reselected an AK2 area for a question (see previous item). There Component Cooling are no specific KA statements provided. Reselected AK2 question Water (CCW) under 009 Small Break LOCA.

1/1 065 Loss of Originally selected an AK2 area for the question. There are no KA Instrument Air statements that are above a 2.5 Importance Rating. Reselected an EK2 KA statement under E06 Loss of Main Feedwater. Reselected an AA1 KA statement for 065 Loss of Instrument Air.

2/1 073 Process Originally selected an A3 area for the question. There are no KA Radiation statements available. Reselected an A3 KA statement under 103 Monitoring Containment. Reselected a K5 statement under 073 Process Radiation Monitoring.

2/2 055 Condenser Air Originally selected an A2 area for the question. There are no KA Removal statements that are above a 2.5 Importance Rating. Reselected the A2 area under 071 Waste Gas Disposal.

2/2 086 Fire Protection Originally selected a K2 area for the question. There are no KA statements available. Reselected the K2 KA statement under 075 Circulating Water. Reselected the A4 KA statement under 086 Fire Protection.

2/1 076 Service Water Originally selected K1.15 for Service Water. There is no System relationship at Waterford 3 between TCCW/ACC and the FPS.

Randomly selected another system for the K1 Statement for 076 Service Water. The system selected was K1.20, AFW.

2/2 086 Fire Protection Originally selected A4.06 for the Halon System. There is no Halon System. Systems at Waterford 3. Randomly selected another K/A for the A4 Statement for 086, Fire Protection System. The K/A selected was A4.02, Fire Detection Panels.

1/1 029 Anticipated Originally selected EA1.06 for Operating switches for normal charging Transient Without header isolation valves. Waterford 3 does not operate charging isolation Scram (ATWS) valves for an ATWS event. Randomly selected another K/A for the EA1 Statement for 029 Anticipated Transient Without Scram (ATWS). The K/A selected was EA1.12, M/G set power supply and Reactor Trip Breakers 2014 NRC Revision 1

2014 NRC Revision 1 ES-401 PWR Examination Outline Form ES-401-2 Facility: Waterford 3 (SRO Exam Outline) Date of Exam: April 2, 2014 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

1. 1 18 3 3 6 Emergency &

Abnormal 2 N/A N/A 9 2 2 4 Plant Evolutions Tier Totals 27 5 5 10 1 28 3 2 5 2.

Plant 2 10 1 1 1 3 Systems Tier Totals 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 2 1 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).