ML082681110
| ML082681110 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 09/24/2008 |
| From: | Duke Energy Corp |
| To: | NRC/RGN-II |
| References | |
| 50-369/08-301, 50-370/08-301, ES-401, ES-401-2 50-369/08-301, 50-370/08-301 | |
| Download: ML082681110 (11) | |
Text
Draft Submittal (Pink Paper)
Senior Reactor Operator Written Exam
ES-401 DRAFT PWR Examination Outline Form ES-401-2 McGuire 2008 NRC Facility: Date of Exam: 5/12/2008 Exam RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *
- 1. 1 3 3 3 3 3 3 18 3 3 6 Emergency
& 2 1 2 1 2 2 1 9 2 2 4 Plant Tier Evolutions 4 5 4 5 5 4 27 5 5 10 Totals 1 2 2 3 3 2 3 2 2 3 3 3 28 3 2 5 2.
Plant 2 1 1 1 1 1 1 1 1 1 1 0 10 0 2 1 3 Systems Tier 3 3 4 4 3 4 3 3 4 4 3 38 5 3 8 Totals 1 2 3 4 1 2 3 4
- 3. Generic Knowledge & Abilities 10 7 Categories 3 3 2 2 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable KIA 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 KIA 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 that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding elimination of inappropriate KIA 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 KAs 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 KIA categories.
7.* The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 KIA's
- 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) 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 KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10CFR55.43
/ McGuire 2008 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 II EAPE # / Name Safety Function I K1 I K2 I K3 I A1 I A2 IG I KIA Topic(s) I Imp. I Q# ~
2.1.27 - Conduct of Operations: Knowledge 009 / Small Break LOCA / 3 X 4.0 76 of system purpose and / or function.
2.1.25 - Conduct of Operations: Ability to 026/ Loss of Component Cooling X interpret reference materials, such as 4.2 77 Water /8 graphs, curves, tables, etc.
EA2.01 - Ability to determine or interpret 029 / Anticipated Transient Without X the following as they apply to a ATWS: 4.7 78 Scram (ATWS) /1 Reactor nuclear instrumentation EA2.05 - Ability to determine or interpret the following as they apply to a Station 055 / Station Blackout / 6 X 3.7 79 Blackout: When battery is approaching fUlly discharged AA2.18 - Ability to determine and interpret the following as they apply to the Loss of 056 / Loss of Off-site Power / 6 X Offsite Power: Reactor coolant 4.0 80 temperature, pressure, and PZR level recorders 2.4.21 - Emergency Procedures / Plan:
Knowledge of the parameters and logic used to assess the status of safety 058 / Loss of DC Power / 6 X functions, such as reactivity control, core 4.6 81 cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
2.4.46 - Emergency Procedures / Plan:
007 / Reactor Trip /1 X Ability to verify that the alarms are 4.2 39 consistent with the plant conditions.
AA1.03 - Ability to operate and / or monitor the following as they apply to the 008 / Pressurizer Vapor Space X Pressurizer Vapor Space Accident: Turbine 2.8 40 Accident/3 bypass in manual control to maintain header pressure EK2.03 - Knowledge of the interrelations 009 / Small Break LOCA / 3 X between the small break LOCA and the 3.0 41 following: S/Gs EK3.06 - Knowledge of the reasons for the following responses as the apply to the 011 / Large Break LOCA / 3 X 4.3 42 Large Break LOCA: Actuation of Phase A and B during LOCA initiation AA1.16 - Ability to operate and / or monitor the following as they apply to the Reactor 015 /17 / Reactor Coolant Pump X Coolant Pump Malfunctions (Loss of RC 3.2 43 Malfunctions / 4 Flow): Low power reactor trip block status lights AA2.04 - Ability to determine and interpret 022 / Loss of Reactor Coolant the following as they apply to the Loss of X 2.9 44 Makeup /2 Reactor Coolant Pump Makeup: How long PZR level can be maintained within limits AK2.03 - Knowledge of the interrelations between the Loss of Residual Heat 025 / Loss of Residual Heat X Removal System and the following: 2.7 45 Removal System /4 Service water or closed cooling water pumps AK1.03 - Knowledge of the operational implications of the following concepts as 027 / Pressurizer Pressure Control X they apply to Pressurizer Pressure Control 2.6 46 System Malfunction / 3 Malfunctions: Latent heat of vaporization/condensation EK2.06 - Knowledge of the interrelations 029/ Anticipated Transient Without X between the and the following an ATWS: 2.9 47 Scram (ATWS) /1 Breakers, relays, and disconnects
! McGuire 2008 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 i EAPE # / Name Safety Function I K1 I K2 I K3 I A1 I A2 I G I KIA Topic(s) Imp. I Q# II EK3.02 - Knowledge of the reasons for the following responses as the apply to the 055 / Station Blackout / 6 X 4.3 48 Station Blackout: Actions contained in EOP for loss of offsite and onsite power AA1.12 - Ability to operate and / or monitor 056 / Loss of Off-site Power / 6 X the following as they apply to the Loss of 3.2 49 Offsite Power: Reactor building cooling unit AK3.01 - Knowledge of the reasons for the following responses as they apply to the 057 / Loss of Vital AC Electrical X Loss of Vital AC Instrument Bus: Actions 4.1 50 Instrument Bus / 6 contained in EOP for loss of vital ac electrical instrument bus AK1.01 - Knowledge of the operational implications of the following concepts as 058 / Loss of DC Power / 6 X they apply to Loss of DC Power: Battery 2.8 51 charger eauipment and instrumentation AA2.06 - Ability to determine and interpret the following as they apply to the Loss of 062 / Loss of Nuclear Service.
X Nuclear Service Water: The length of time 2.8 52 Water / 4 after the loss of CCW flow to a component before that component may be damaged AA2.08 - Ability to determine and interpret the following as they apply to the Loss of 065/ Loss of Instrument Air /8 X 2.9 53 Instrument Air: F.ailure modes of air-operated eauipment EK1.2 - Knowledge of the operational implications of the following concepts as they apply to the (LOCA Outside E04/ LOCA Outside Containment /
X Containment): Normal, abnormal and 3.5 54 3
emergency operating procedures associated with (LOCA Outside Containment).
2.1.23 - Conduct of Operations: Ability to E11 / Loss of Emergency Coolant perform specific system and integrated X plant procedures during all modes of plant 4.3 55 Recirculation / 4 operation.
E12 / Uncontrolled Depressurization 2.1.20 - Conduct of Operations: Ability to X 4.6 56 of all Steam Generators / 4 interpret and execute procedure steps.
KIA Category Totals: 3 3 3 3 6 6 Group Point Total:
I 18/6 I
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DRAFT McGuire 2008 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 i EAPE # / Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) I Imp. I Q# i AA2.02 - Ability to determine and interpret the following as they apply to the Dropped 003 / Dropped Control Rod / 1 X 2.8 82 Control Rod: Signal inputs to rod control system AA2.05 - Ability to determine and interpret the following as they apply to the Loss of 033 / Loss of Intermediate Range X Intermediate Range Nuclear 3.1 83 Nuclear Instrumentation / 7 Instrumentation: Nature of abnormality, from rapid survey of control room data 2.2.38 - Equipment Control: Knowledge of 059 / Accidental Liquid RadWaste X conditions and limitations in the facility 4.5 84 Release /9 license.
2.1.20 - Conduct of Operations: Ability to E06 / Degraded Core Cooling /4 X 4.6 85 interpret and execute procedure steps.
AA1.02 - Ability to operate and / or monitor 005 / Inoperable/Stuck Control Rod / the following as they apply to the X 3.7 57 1 Inoperable / Stuck Control Rod: Rod selection switches AA2.03 - Ability to determine and interpret the following as they apply to the 024/ Emergency Boration / 1 X Emergency Boration: Correlation between 2.9 58 boric acid controller setpoint and boric acid flow AK1.01 - Knowledge of the operational 032 / Loss of Source Range Nuclear X implications of the following concepts as 2.5 59 Instrumentation / 7 Effects of voltaQe chanQes on performance AA1.02 - Ability to operate and / or monitor 033/ Loss of Intermediate Range the following as they apply to the Loss of X 3.0 60 Nuclear Instrumentation / 7 Intermediate Range Nuclear Instrumentation: Level trip bypass AK2.01 - Knowledge of the interrelations 036 / Fuel Handling Incidents / 8 X between the Fuel Handling Incidents and 2.9 61 the following: Fuel handling equipment AA2.12 - Ability to determine and interpret the following as they apply to the Plant 067 / Plant Fire On-site / 8 X 2.9 62 Fire on Site: Location of vital equipment within fire zone AK3.01 - Knowledge of the reasons for the following responses as they apply to the 069/ Loss of Containment Integrity /
X Loss of Containment Integrity: Guidance 3.8 63 5
contained in EOP for loss of containment inteQrity AK2.01 - Knowledge of the interrelations 076 / High Reactor Coolant Activity / between the High Reactor Coolant Activity X 2.6 64 9 and the following: Process radiation monitors 2.4.8 - Emergency Procedures / Plan:
Knowledge of how abnormal operating E02 / SI Termination / 3 X 3.8 65 procedures are used in conjunction with EOP's.
KIA Category Totals: 1 2 1 2 4 3 Group Point Total:
I 9/4
l 200~
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DRAFT McGuire NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A Q System # / Name G Imp.
1 2 3 4 5 6 1 2 3 4 #
A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) 010 Pressurizer Pressure based on those predictions, use X 3.6 86 Control procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Heater failures A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based 026 Containment Spray X on those predictions, use procedures to 4.4 87 correct, control, or mitigate the consequences of those malfunctions or operations: Failure of ESF 2.4.4 - Emergency Procedures / Plan:
Ability to recognize abnormal 061 Auxiliary/Emergency indications for system operating X 4.7 88 Feedwater parameters which are entry-level conditions for emergency and abnormal operating procedures.
2.2.4 - Equipment Control: (multi-unit license) Ability to explain the variations 073 Process Radiation X in control board layouts, systems, 3.6 89 Monitoring instrumentation and procedural actions between units at a facilitv.
A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to 076 Service Water X 3.1 90 correct, control, or mitigate the consequences of those malfunctions or operations: Service water header pressure K1.08 - Knowledge of the physical connections and/or cause-effect 003 Reactor Coolant Pump X relationships between the RCPS and 2.7 1 the following systems: Containment isolation K5.46 - Knowledge of the operational implications of the following concepts 004 Chemical and Volume as they apply to the CVCS: Reason for X 2.5 2 Control going solid in PZR (collapsing steam bubble): make sure no steam is in PRT when PORV is opened to drain RCS K2.03 - Knowledge of bus power 005 Residual Heat Removal X supplies to the following: RCS pressure 2.7 3 boundary motor-operated valves A4.01 - Ability to manually operate 006 Emergency Core Cooling X and/or monitor in the control room: 4.1 4 Pumps A3.01 - Ability to monitor automatic 007 Pressurizer Relief/Quench operation of the PRTS, including:
X 2.7 5 Tank Components which discharge to the PRT K2.02 - Knowledge of bus power 008 Component Cooling Water X , supplies to the following: CCW pump, 3.0 6 includina emeraencv backup K4.01 - Knowledge of CCWS design feature(s) and/or interlock(s) which 008 Component Cooling Water X 3.1 7 provide for the following: Automatic start of standby pump
ES-401 4 Form ES-401-2 DRAF McGuire 2008 NRC Exam
( Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A Q System # / Name G Imp.
1 2 3 4 5 6 1 2 3 4 #
K1.07 - Knowledge of the physical connections and/or cause-effect 010 Pressurizer Pressure X relationships between the PZR PCS 2.9 8 Control and the following systems:
Containment A3.03 - Ability to monitor automatic 012 Reactor Protection X operation of the RPS. including: Power 3.4 9 supply K6.03 - Knowledge of the effect of a 012 Reactor Protection X loss or malfunction of the following will 3.3 10 have on the RPS: Trip 10Qic circuits K4.08 - Knowledge of ESFAS design 013 Engineered Safety X feature(s) and/or interlock(s) which 3.1 11 Features Actuation provide for the following Redundancy A2.05
- Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based 022 Containment Cooling X on those predictions, use procedures to 3.1 12 correct, control, or mitigate the consequences of those malfunctions or operations: Major leak in CCS K6.01 - Knowledge of the effect of a loss or malfunction of the following will 025 Ice Condenser X have on the ice condenser system: 3.4 13 Upper and lower doors of the ice condenser K5 01 - Knowledge of operational implications of the following concepts 025 Ice Condenser X as they apply to the ice condenser 3.0 14 system: Relationships between pressure and temperature 2.2.22 - Equipment Control: Knowledge 026 Containment Spray X of limiting conditions for operations and 4.0 15 safety limits.
K3.02 - Knowledge of the effect that a loss or malfunction of the CSS will have 026 Containment Spray X on the following: Recirculation spray 4.2 16 system A4.04 - Ability to manually operate 039 Main and Reheat Steam X and/or monitor in the control room: 3.8 17 Emergency feedwater pump turbines K4.07 - Knowledge of MRSS design feature(s) and/or interlock(s) which 039 Main and Reheat Steam X 3.4 18 provide for the following: Reactor building isolation A 1.03 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated 059 Main Feedwater X 2.7 19 with operating the MFW controls including: Power level restrictions for operation of MFW pumps and valves.
K3.01 - Knowledge of the effect that a 061 AUXiliary/Emergency X loss or malfunction of the AFW will 4.4 20 Feedwater have on the foliowinQ: RCS A3.05 - Ability to monitor automatic operation of the ac distribution system, 062 AC Electrical Distribution X 3.5 21 including: Safety-related indicators and controls A 1.01 - Ability to predict and/or monitor changes in parameters associated with 063 DC Electrical Distribution X operating the dc electrical system 2.5 22 controls including: Battery capacity as it is affected by discharQe rate
ES-401 DRAFT 4 McGuire 2008 NRC Exam Form ES-401-2 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A Q System # / Name G Imp.
1 2 3 4 5 6 1 2 3 4 #
K6.08 - Knowledge of the effect of a 064 Emergency Diesel loss or malfunction of the following will X 3.2 23 Generator have on the ED/G system: Fuel oil storage tanks A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) 073 Process Radiation based on those predictions, use X 2.5 24 Monitoring procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Erratic or failed power supply 2.4.30 - Emergency Procedures / Plan; Knowledge of events related to system operation / status that must be reported 076 Service Water X 2.7 25 to internal organizations or external agencies, such as the state, the NRC, or the transmission svstem operator.
K3.07 - Knowledge of the effect that a 076 Service Water X loss or malfunction of the SWS will 3.7 26 have on the following: ESF loads 2.4.35 - Emergency Procedures / Plan:
Knowledge of local auxiliary operator 078 Instrument Air X 3.8 27 tasks during emergency and the resultant operational effects.
A4.01 - Ability to manually operate
( 103 Containment X and/or monitor in the control room:
Flow control, pressure control, and 3.2 28 temperature control valves, including pneumatic valve controller KIA Category Totals: 2 2 3 3 2 3 2 5 3 3 5 Group Point Total:
I 28/5
ES-401 5 Form ES-401-2 DRAFT McGuire 2008 NRC Exam
( Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A A Q System # / Name G Imp.
1 2 3 4 5 6 1 2 3 4 #
2.1.7 - Conduct of Operations: Ability to evaluate plant performance and make 015 Nuclear Instrumentation X operational judgments based on 4.7 91 operating characteristics, reactor behavior, and instrument interpretation.
A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the HRPS; and (b) based on those predictions, use Procedures to correct, control, or 028 Hydrogen Recombiner and X mitigate the consequences of those 4.0 92 Purge Control malfunctions or operations: The hydrogen air concentration in excess of limit flame propagation or detonation with resulting equipment dam-age in containment A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the SAS; and (b) based 079 Station Air X on those predictions, use Procedures 3.2 93 to correct, control, or mitigate the consequences of those malfunctions or operations:: Cross-connection with lAS K4.03 - Knowledge of RPIS design feature(s) and/or interlock(s) which 014 Rod Position Indication X 3.2 29 provide for the following: Rod Bottom lights K6.01 - Knowledge of the effect of a 017 In-core Temperature loss or malfunction of the following ITM X 2.7 30 Monitor system components: Sensors and detectors K2.01 - Knowledge of bus power 015 Nuclear Instrumentation X supplies to the following: NIS channels, 3.3 31 System components, and interconnections K1.01 - Knowledge of the physical connections and/or cause-effect 028 Hydrogen Recombiner and relationships between the HRPS and X 2.5 32 Purge Control the following systems: Containment annulus ventilation system (including pressure limits)
A4.04 - Ability to manually operate 029 Containment Purge X and/or monitor in the control room: 3.5 33 Containment Evacuation signal K3.01 - Knowledge of the effect that a loss or malfunction of the Spent Fuel 033 Spent Fuel Pool Cooling X 2.6 34 Pool Cooling System will have on the following: Area ventilation systems A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the S/GS; and (b) based on those predictions, use procedures 035 Steam Generator X 3.2 35 to correct, control, or mitigate the consequences of those malfunctions or operations: Unbalanced flows to the S/Gs A3.03 - Ability to monitor automatic 041 Steam OumplTurbine X operation of the SOS, including: Steam 2.7 36 Bypass Control flow
Form ES-401-2 McGuire 200~ NRC Exam ES-401 DRAFT Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A A Q System # / Name G Imp.
1 2 3 4 5 6 1 2 3 4 #
A 1.06 - Ability to predict and/or monitor changes in parameters(to prevent exceeding design limits) associated 071 Waste Gas Disposal X 2.5 37 with Waste Gas Disposal System operating the controls including:
Ventilation system K5.03 - Knowledge of the operational implication of the following concepts as 086 Fire Protection X they apply to the Fire Protection 3.1 38 System: Effect of water spray on electrical components KIA Category Totals: 1 1 1 1 1 1 1 3 1 1 1 Group Point Total:
I 12/3
ES-401 DRA eric Knowledge and Abilities Outline (Tier3) Form ES-401-3
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Facility: McGuire 2008 NRC Exam Date: 5/12/2008 RO SRO-Only Category KIA # Topic IR Q# IR Q#
Knowledge of the fuel-handling responsibilities of 2.1.35 3.9 94 SRO's.
Ability to make accurate, clear and concise logs, 2.1.18 3.6 66
- 1. records, status boards, and reports.
Conduct Knowledge of facility requirements for controlling 2.1.13 2.5 67 of Operations vital/controlled access.
Ability to coordinate personnel activities outside 2.1.8 3.4 68 the control room.
Subtotal 3 1 Knowledge of the process for conducting special 2.2.7 3.6 95 or infrequent tests.
Knowledge of limiting conditions for operations 2.2.22 4.7 96 and safety limits.
- 2. Ability to apply technical specifications for a Equipment 2.2.40 3.4 69 system.
Control 2.2.13 Knowledge of tagging and clearance procedures. 4.1 70 Knowledge of the process for making changes to 2.2.6 3.0 71 procedures.
Subtotal 3 2 Knowledge of radiation or containment hazards 2.3.14 that may arise during normal, abnormal, or 3.8 97 emergency conditions or activities.
2.3.6 Ability to approve release permits 3.8 98 3.
Radiation Knowledge of radiation exposure limits under 2.3.4 3.2 72 Control normal or emergency conditions.
2.3.11 Ability to control radiation releases. 3.8 73 Subtotal 2 2 Ability to verify that the alarms are consistent 2.4.46 4.2 99 with the plant conditions.
Knowledge of how abnormal operating 2.4.8 4.5 100
- 4. procedures are used in conjunction with EOP's.
Emergency Procedures / 2.4.17 Knowledge of EOP terms and definitions. 3.9 74 Plan 2.4.14 Knowledge of general guidelines for EOP usage. 3.8 75 Subtotal 2 2 Tier 3 Point Total 10 7