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2010-06-Final-Written Exam Outlines
	ML101890725
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Site:	Grand Gulf
Issue date:	06/25/2010
From:	; NRC Region 4
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ES-401 BWR Examination Outline - RO Form ES-401-1 Facility: Date of Exam: June 25, 2010 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 4 4 4 2 20 7 Emergency &

Abnormal Plant 2 0 1 0 N/A 2 1 N/A 3 7 3 Evolutions Tier Totals 3 4 4 6 5 5 27 10 1 3 2 1 3 1 2 4 2 4 3 1 26 5 2.

Plant 2 2 0 1 2 1 0 1 1 1 1 2 12 3 Systems Tier Totals 5 2 2 5 2 2 5 3 5 4 3 38 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 Categories 3 3 2 2 10 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.

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ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 295001 Partial or Complete Loss of Forced X Ability to operate and/or monitor the 3.1 6 Core Flow Circulation / 1 & 4 following as they apply to PARTIAL OR H COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: AA1.07 Nuclear boiler instrumentation system 295003 Partial or Complete Loss of AC / 6 X Knowledge of the reasons for the following 3.7 38 responses as they apply to PARTIAL OR H COMPLETE LOSS OF A.C. POWER:

AK3.05 Reactor SCRAM 295004 Partial or Total Loss of DC Pwr / 6 X Knowledge of the interrelations between 3.3 11 PARTIAL OR COMPLETE LOSS OF H D.C. POWER and the following: AK2.03 D.C. bus loads 295005 Main Turbine Generator Trip / 3 X Ability to operate and/or monitor the 3.6 13 following as they apply to MAIN H TURBINE GENERATOR TRIP: AA1.02 RPS 295006 SCRAM / 1 X Knowledge of the operational implications 3.7 3 of the following concepts as they apply to F SCRAM: AK1.03 Reactivity control 295016 Control Room Abandonment / 7 295018 Partial or Total Loss of CCW / 8 X Knowledge of the operational implications 3.5 25 of the following concepts as they apply to H PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

AK1.01 Effects on component/system operations 295019 Partial or Total Loss of Inst. Air / 8 X Knowledge of the interrelations between 2.8 39 PARTIAL OR COMPLETE LOSS OF H INSTRUMENT AIR and the following:

AK2.06 Offgas system 295021 Loss of Shutdown Cooling / 4 X Knowledge of the operational implications 3.9 40 of the following concepts as they apply to H LOSS OF SHUTDOWN COOLING:

AK1.03 Adequate core cooling 295023 Refueling Acc / 8 X Knowledge of the interrelations between 3.2 21 REFUELING ACCIDENTS and the F following: AK2.04 RMCS/Rod control and information system 1

295024 High Drywell Pressure / 5 X Ability to determine and/or interpret the 3.8 24 following as they apply to HIGH H DRYWELL PRESSURE: EA2.03 Suppression pool level 295025 High Reactor Pressure / 3 X Knowledge of the reasons for the following 3.7 42 responses as they apply to HIGH F REACTOR PRESSURE: EK3.09 Low-low set initiation 295026 Suppression Pool High Water X Ability to determine and/or interpret the 3.8 14 Temp. / 5 following as they apply to SUPPRESSION H POOL HIGH WATER TEMPERATURE:

EA2.02 Suppression pool level 295027 High Containment Temperature / 5 X 2.4.18 Knowledge of the specific bases for 3.3 7 EOPs F 295028 High Drywell Temperature / 5 X Ability to determine and/or interpret the 4.1 50 following as they apply to HIGH H DRYWELL TEMPERATURE: EA2.04 Drywell pressure 295030 Low Suppression Pool Wtr Lvl / 5 X Knowledge of the reasons for the following 3.6 43 responses as they apply to LOW H SUPPRESSION POOL WATER LEVEL:

EK3.03 RCIC operation 295031 Reactor Low Water Level / 2 X Ability to operate and/or monitor the 4.3 30 following as they apply to REACTOR H LOW WATER LEVEL: EA1.04 High pressure core spray 295037 SCRAM Condition Present X Ability to determine and/or interpret the 4.3 20 and Reactor Power Above APRM Downscale or Unknown / 1 following as they apply to SCRAM H CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: EA2.03 SBLC tank level 295038 High Off-site Release Rate / 9 X Knowledge of the reasons for the following 3.9 5 responses as they apply to HIGH OFF- F SITE RELEASE RATE: EK3.02 System isolations 600000 Plant Fire On Site / 8 X 2.1.30 Ability to locate and operate 4.4 26 components, including local controls. F 700000 Generator Voltage and Electric Grid X Ability to operate and/or monitor the 3.6 44 Disturbances / 6 following as they apply to GENERATOR F VOLTAGE AND ELECTRIC GRID DISTURBANCES: AA1.01 Grid frequency and voltage K/A Category Totals: 3 3 4 4 4 2 Group Point Total: 20 2

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 X 2.2.42 Ability to recognize system parameters 3.9 15 that are entry-level conditions for Technical F Specifications.

295008 High Reactor Water Level / 2 X Knowledge of the interrelations between 3.6 73 HIGH REACTOR WATER LEVEL and the H following: AK2.03 Reactor water level control 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 X Ability to determine and/or interpret the 3.9 31 following as they apply to INADVERTENT H REACTIVITY ADDITION: AA2.02 Reactor period 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 X Ability to operate and/or monitor the 3.1 64 following as they apply to LOSS OF CRD F PUMPS: AA1.01 CRD hydraulic system 295029 High Suppression Pool Wtr Lvl / 5 X 2.4.45 Ability to prioritize and interpret the 4.1 32 significance of each annunciator or alarm. H 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment X 2.4.4 Ability to recognize abnormal 4.5 17 Ventilation High Radiation / 9 indications for system operating parameters F that are entry-level conditions for emergency and abnormal operating procedures.

295035 Secondary Containment High Differential Pressure / 5 3

295036 Secondary Containment High X Ability to operate and/or monitor the 3.2 27 Sump/Area Water Level / 5 following as they apply to SECONDARY H CONTAINMENT HIGH SUMP/AREAWATER LEVEL: EA1.01 Secondary containment equipment and floor drain systems 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: 0 1 0 2 1 3 Group Point Total: 7 4

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)

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 X Knowledge of electrical power 2.7 12 supplies to the following: K2.03 F Initiation logic 203000 RHR/LPCI: Injection Mode X Ability to predict and/or monitor 3.7 65 changes in parameters associated with H operating the RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) controls including: A1.08 Emergency generator loading 205000 Shutdown Cooling X Ability to manually operate and/or 3.6 45 monitor in the control room: A4.03 H SDC/RHR discharge valves 206000 HPCI 207000 Isolation (Emergency)

Condenser 209001 LPCS X Knowledge of electrical power 2.5 1 supplies to the following: K2.02 Valve F power 209002 HPCS X Ability to monitor automatic 3.7 10 operations of the HIGH PRESSURE H CORE SPRAY SYSTEM (HPCS) including: A3.04 System flow 211000 SLC X Ability to monitor automatic 3.5 46 operations of the STANDBY LIQUID H CONTROL SYSTEM including:

A3.01 Pump discharge pressure 212000 RPS X Ability to (a) predict the impacts of 3.7 47 the following on the REACTOR H PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.02 RPS bus power supply failure 215003 IRM X Knowledge of the effect that a loss or 3.0 8 malfunction of the following will have H on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: K6.04 Detectors 5

215004 Source Range Monitor X Ability to (a) predict the impacts of 3.4 48 the following on the SOURCE H RANGE MONITOR (SRM)

SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.02 SRM inop condition 215005 APRM / LPRM X Ability to predict and/or monitor 3.0 28 changes in parameters associated with H operating the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM controls including: A1.07 APRM (gain adjustment factor)

X Knowledge of the effect that a loss or 3.6 29 malfunction of the REACTOR CORE H ISOLATION COOLING SYSTEM 217000 RCIC (RCIC) will have on following: K3.04 Adequate core cooling X Knowledge of the operational 3.1 49 implications of the following concepts H as they apply to REACTOR CORE ISOLATION COOLING SYSTEM (RCIC): K5.02 Flow indication 218000 ADS X Knowledge of the effect that a loss or 3.8 51 malfunction of the following will have H on the AUTOMATIC DEPRESSURIZATION SYSTEM:

K6.03 Nuclear boiler instrument system (level indication) 223002 PCIS/Nuclear Steam X Knowledge of the physical connections 3.3 52 Supply Shutoff and/or cause- effect relationships between F

PRIMARY CONTAINMENT ISOLATION SYSTEM / NUCLEAR STEAM SUPPLY SHUT-OFF and the following: K1.02 Reactor water cleanup 239002 SRVs X Knowledge of RELIEF/SAFETY 3.7 53 VALVES design feature(s) and/or F interlocks which provide for the following: K4.09 Manual opening of the SRV 259002 Reactor Water Level X Ability to manually operate and/or 3.5 54 Control monitor in the control room: A4.11 H High level lockout reset controls 261000 SGTS X Ability to monitor automatic 3.2 55 operations of the STANDBY GAS F TREATMENT SYSTEM including:

A3.01 System flow 6

262001 AC Electrical X Knowledge of A.C. ELECTRICAL 3.6 56 Distribution DISTRIBUTION design feature(s) and/or H

interlocks which provide for the following: K4.06 Redundant power sources to vital buses 262002 UPS (AC/DC) X Knowledge of UNINTERRUPTABLE 3.1 57 POWER SUPPLY (A.C./D.C.) design F

feature(s) and/or interlocks which provide for the following: K4.01 Transfer from preferred power to alternate power supplies X Knowledge of the physical connections 3.2 66 and/or cause-effect relationships between H

D.C. ELECTRICAL DISTRIBUTION 263000 DC Electrical and the following: K1.02 Battery charger Distribution and battery X Ability to monitor automatic 3.2 74 operations of the D.C. ELECTRICAL F DISTRIBUTION including: A3.01 Meters, dials, recorders, alarms, and indicating lights X Ability to predict and/or monitor 3.0 69 changes in parameters associated with H operating the EMERGENCY GENERATORS (DIESEL/JET) 264000 EDGs controls including: A1.09 Maintaining minimum load on emergency generator (to prevent reverse power)

X 2.1.28 Knowledge of the purpose and 4.1 75 function of major system components F and controls.

300000 Instrument Air X Knowledge of the connections and / or 3.1 2 cause effect relationships between F INSTRUMENT AIR SYSTEM and the following: K1.05 Main Steam Isolation Valve air X Ability to predict and / or monitor 2.8 62 400000 Component Cooling changes in parameters associated with H Water operating the CCWS controls including: A1.02 CCW temperature X Ability to manually operate and / or 3.1 58 monitor in the control room: A4.01 H CCW indications and control K/A Category Point Totals: 3 2 1 3 1 2 4 2 4 3 1 Group Point Total: 26 7

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)

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 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive X Ability to manually operate 2.6 35 Mechanism and/or monitor in the control F room: A4.01 CRD mechanism temperature 201004 RSCS 201005 RCIS X 2.2.44 Ability to interpret control 4.2 67 room indications to verify the H status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU X Knowledge of REACTOR 2.9 18 WATER CLEANUP SYSTEM F design feature(s) and/or Interlocks which provide for the following: K4.03 Over temperature protection for system components 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling X Knowledge of the operational 2.9 70 Mode implications of the following F concepts as they apply to RHR/LPCI: TORUS /

SUPPRESSION POOL COOLING MODE : K5.04 Heat exchanger operation 223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode X Knowledge of the physical 3.1 36 connections and/or cause effect F relationships between RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE and the following: K1.13 Containment instrumentation 8

230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup X Ability to (a) predict the impacts 2.8 16 of the following on the FUEL H POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.03 Low surge tank level/high level 234000 Fuel Handling Equipment X Knowledge of the physical 3.2 68 connections and/or cause-effect F relationships between FUEL HANDLING EQUIPMENT and the following: K1.01 239001 Main and Reheat Steam X 2.4.4 Ability to recognize 4.5 33 abnormal indications for system F operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux. X Ability to predict and/or monitor 2.7 34 changes in parameters associated H with operating the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS controls including: A1.04 Steam flow 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas X Knowledge of the effect that a 3.5 9 loss or malfunction of the H OFFGAS SYSTEM will have on following: K3.01 Condenser vacuum 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC X Ability to monitor automatic 3.3 59 operations of the CONTROL F ROOM HVAC including: A3.01 Initiation/reconfiguration 9

290002 Reactor Vessel Internals X Knowledge of REACTOR 3.1 37 VESSEL INTERNALS design F feature(s) and/or interlocks which provide for the following:K4.02 Separation of fluid flow paths within the vessel K/A Category Point Totals: 2 0 1 2 1 0 1 1 1 1 2 Group Point Total: 12 10

ES-401 Generic Knowledge and Abilities Outline (Tier 3) - RO Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

2.1.13 Knowledge of facility requirements for controlling 2.5 22 vital/controlled access. F 1.

Conduct 2.1.18 Ability to make accurate, clear, and concise logs, 3.6 23 of Operations records, status boards, land reports. F 2.1.32 Ability to explain and apply system limits and 3.8 60 precautions. F Subtotal 3 Ability to perform pre-startup procedures for the 4.5 71 2.2.1 facility, including operating those controls associated F with plant equipment that could affect reactivity.

2.

Equipment 2.2.6 Knowledge of the process for making changes to 3.0 61 Control procedures. F 2.2.7 Knowledge of the process for conducting special or 2.9 4 infrequent tests. F Subtotal 3 2.3.7 Ability to comply with radiation work permit 3.5 41 requirements during normal or abnormal conditions. H

3. 2.3.13 Knowledge of radiological safety procedures 3.4 19 Radiation pertaining to licensed operator duties, such as F Control response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Subtotal 2 4.

2.4.18 Knowledge of the specific bases for EOPs. 3.3 72 Emergency Procedures / F Plan 2.4.29 Knowledge of the emergency plan. 3.1 63 H

Subtotal 2 Tier 3 Point Total 10 11

ES-401 Record of Rejected K/As - RO Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 600000 2.4.9 Could not write an RO-level question for this KA that would not be double-jeopardy with the context of an already-written (and preferred) SRO-level question (#77). Re-sampled within the Generics and replaced by: 2.1.30.

1/2 295022 AA1.03 Could not write an operationally valid question for this KA (i.e.,

GGNS operators are not in the least bit focused on Recirc system behavior upon trip of a CRD Pump). Re-sampled within AA1 and replaced by: AA1.01.

1/2 295035 EK3.02 Could not create any operationally-valid, RO-level question for 295035 that would not pose a double-jeopardy concern for already-written (and preferred) question #5. Re-sampled within Tier 1 Group 2 and then across the KA Categories; replaced by: 295008 AK2.03.

2/1 218000 K6.01 The only type of operationally-valid RO-level question for this KA has already been included on the pre-NRC Audit Exam for this LOT Class. Weve decided it is to remain on that exam. Re-sampled within K6 and replaced by: K6.03.

3 2.1.27 NRC review of the initial exam submittal determined that the originally sampled KA (2.1.37) was an inappropriate fit for a Tier 3 type question. Per Chief Examiners direction, re-sampled within Tier 3, Category 1 and replaced by 2.1.18.

SYSTEMS DELETED 201002 Reactor Manual Control System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

201004 Rod Sequence Control System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

201006 Rod Worth Minimizer System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

214000 Rod Position Information System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

215002 Rod Block Monitor System - System is not part of BWR-6 design. Functions of this system are incorporated into the Rod Control & Information System (201005).

206000 High Pressure Coolant Injection (HPCI) - System is not part of BWR-6 design.

207000 Isolation (Emergency) Condenser - System is not part of BWR-6 design.

12

230000 RHR/LPCI: Torus/Pool Spray Mode - System is not part of the BWR-6 Mark III Containment design.

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ES-401 BWR Examination Outline - SRO Form ES-401-1 Facility: Date of Exam: June 25, 2010 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 20 2 5 7 Emergency &

Abnormal Plant 2 N/A N/A 7 1 2 3 Evolutions Tier Totals 27 3 7 10 1 26 1 4 5 2.

Plant 2 12 1 2 3 Systems Tier Totals 38 2 6 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 Categories 2 2 1 2 7 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).