Text

2008-12-Final Outlines
	ML090200104
Person / Time
Site:	River Bend
Issue date:	11/21/2008
From:	; NRC Region 4
To:	;
References
	Download: ML090200104 (34)
	v • d • e

ES-401 BWR Examination Outline (RO) Form ES-401-1 Facility: River Bend Station Date of Exam: 12/1/2008 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 2 1 4 7 4 2 20 7 Emergency &

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

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

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

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.

Revision 2

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 1 (AK3.04) Knowledge of the reason for a reactor 3.4 1 Core Flow Circulation / 1 & 4 scram as it applies to a partial or complete loss of forced core flow circulation.

295003 Partial or Complete Loss of AC / 6 1 (AA2.03) Ability to determine and/or interpret 3.2 2 battery status as it applies to a partial or complete loss of AC power.

295004 Partial or Total Loss of DC Pwr / 6 1 (AA1.01) Ability to operate and/or monitor the 3.3 3 DC electrical distribution system during a partial or complete loss of DC power.

295005 Main Turbine Generator Trip / 3 1 (AA1.02) Ability to operate and/or monitor RPS 3.6 4 following a Main Turbine or Generator trip.

295006 SCRAM / 1 1 (AK2.02) Knowledge of the interrelations 3.8 5 between SCRAM and reactor water level control.

295016 Control Room Abandonment / 7 1 (G.2.4.4) Ability to recognize abnormal 4.5 6 indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures as they relate to control room abandonment.

295018 Partial or Total Loss of CCW / 8 1 (AK3.07) Knowledge of the reasons for the cross 3.1 7 connecting of backup systems as it applies to the partial or complete loss of component cooling water.

295019 Partial or Total Loss of Inst. Air / 8 1 (G.2.4.47) Ability to diagnose and recognize 4.2 8 trends in an accurate and timely manner utilizing the appropriate control room reference material during a partial or total loss of instrument air.

295021 Loss of Shutdown Cooling / 4 1 (AK3.05) Knowledge of the reason for 3.6 9 establishing alternate heat removal paths during a loss of shutdown cooling.

295023 Refueling Acc / 8 1 (AA1.06) Ability to operate or monitor neutron 3.3 10 monitoring during a refueling accident.

295024 High Drywell Pressure / 5 1 (EK3.06)Knowledge of the reasons for Reactor 4.0 11 Scram as it applies to High Drywell Pressure.

295025 High Reactor Pressure / 3 295026 Suppression Pool High Water 1 (EA1.01) Ability to operate and/or monitor 4.1 12 Temp. / 5 suppression pool cooling as it applies to a suppression pool high water temperature.

295027 High Containment Temperature / 5 1 (EA1.03) Ability to operate and/or monitor 3.5 13 emergency depressurization as it applies to High Containment Temperature.

295028 High Drywell Temperature / 5 1 (EK1.02) Knowledge of the operational 2.9 14 implications of equipment environmental qualifications as they apply to high drywell temperature.

Revision 2

295030 Low Suppression Pool Wtr Lvl / 5 1 (EA2.01) Ability to determine and/or interpret 4.1 15 suppression pool level as it applies to a low suppression pool water level.

295031 Reactor Low Water Level / 2 1 (EA1.06) Ability to operate and/or monitor the 4.4 16 automatic depressurization system as it applies to a reactor low water level.

295037 SCRAM Condition Present 1 (EK1.01) Knowledge of the operational 4.1 17 and Reactor Power Above APRM implications of reactor pressure effects on Downscale or Unknown / 1 reactor power as they apply to an ATWS.

295038 High Off-site Release Rate / 9 1 (EA2.03) Ability to determine and/or interpret 3.5 18 the Radiation Levels during a High Offsite Release Rate.

600000 Plant Fire On Site / 8 1 (AA1.09) Ability to operate and/or monitor the 2.5 19 plant fire zone panel (including detector location) during a Plant Fire On Site.

700000 Generator Voltage and Electric Grid 1 (AA2.06) Ability to determine and/or interpret 3.4 20 Disturbances / 6 generator frequency limitations as they apply to Generator Voltage and Electrical Grid Disturbances.

K/A Category Totals: 2 1 4 7 4 2 Group Point Total: 20/7 Revision 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 1 (AK2.04) Knowledge of the interrelations between 3.2 21 loss of main condenser vacuum and the reactor/turbine pressure regulating system.

295007 High Reactor Pressure / 3 1 (AK2.06) Knowledge of the interrelations between 3.5 22 High Reactor Pressure and NSSSS.

295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 1 (AK1.01) Knowledge of the operational implications 4.0 23 of containment pressure as it applies to a High Containment Temperature.

295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 1 (G.2.2.12) Knowledge of surveillance procedures 3.7 24 associated with High Suppression Pool Temperature.

295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 1 (AA2.03) Ability to determine and/or interpret CRD 3.1 25 mechanism temperature as it applies to a Loss of CRD Pumps.

295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment 1 (EK2.01) Knowledge of the interrelations between 3.8 26 Area Radiation Levels / 9 High Secondary Containment Area Radiation Levels and the area radiation monitoring system.

295034 Secondary Containment 1 (EK3.02) Knowledge of the reasons for starting 4.1 27 Ventilation High Radiation / 9 SBGT as it applies to a Secondary Containment Ventilation High Radiation condition.

295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: 1 3 1 0 1 1 Group Point Total: 7/3 Revision 2

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 203000 RHR/LPCI: Injection 1 1 (A1.02) Ability to predict and/or monitor 3.9 28 Mode changes in reactor pressure associated with the operating ofRHR/LPCI injection mode.

(A3.01) Ability to monitor automatic valve 3.8 29 operation of the RHR/LPCI injection mode 205000 Shutdown Cooling 1 (K3.03) Knowledge of the effect that a loss or 3.8 30 malfunction of the Shutdown Cooling System will have on reactor temperatures (moderator, vessel, flange) 206000 HPCI 207000 Isolation (Emergency)

Condenser 209001 LPCS 1 1 (K2.01) Knowledge of the electrical power 3.0 31 supply to the pump.

(A3.01) Ability to monitor automatic valve operations of LPCS. 3.6 32 209002 HPCS 1 (A3.06) Ability to monitor lights and alarms 2.8 33 associated automatic operation of HPCS.

211000 SLC 1 (A1.03) Ability to predict and/or monitor 3.6 34 changes in pump discharge pressure associated with operating the Standby Liquid Control System.

212000 RPS 1 (K3.09) Knowledge of the effect that a loss or 3.2 35 malfunction of RPS will have on the magnitude of heat energy that must be absorbed by the containment during accident/transient conditions.

215003 IRM 1 (K4.04) Knowledge of the IRM design feature 2.9 36 and/or interlocks that provide for varying system sensitivity levels using range switches.

215004 Source Range Monitor 1 (A2.02) Ability to predict the impact of an SRM 3.4 37 inop and based on those predictions, use procedures to correct, control, or mitigate the consequences of that condition.

215005 APRM / LPRM 1 (K2.02) Knowledge of electrical power supplies 2.6 38 to APRM channels.

217000 RCIC 1 (A3.04) Ability to monitor system flow during 3.6 39 automatic operation of RCIC.

218000 ADS 1 (A4.09) Ability to manually operate and/or 3.9 40 monitor suppression pool temperature in the control room.

Revision 2

223002 PCIS/Nuclear Steam 1 (K4.07) Knowledge of NSSSS design features 2.8 41 Supply Shutoff which provide for physical separation of system components (to prevent localized environmental factors, electrical faults, and physical events from impairing system response).

239002 SRVs 1 (K3.02) Knowledge of the effect that a loss or 4.2 42 malfunction of the Relief/Safety Valves will have on reactor over pressurization.

259002 Reactor Water Level 1 (K1.03) Knowledge of the physical connections 3.8 43 Control and/or cause-effect relationships between Reactor Water Level Control System and reactor water level.

261000 SGTS 1 1 (K3.01) Knowledge of the effect that a loss or 3.3 44 malfunction of the Standby Gas Treatment System will have on secondary containment and environment differential pressure.

(A4.09) Ability to manually operate and/or 2.7 45 monitor ventilation valves and dampers in the control room.

262001 AC Electrical 1 1 (K5.02) Knowledge of the operational 2.6 46 Distribution implications of breaker control as it applies to the AC electrical distribution system.

(A4.03) Ability to manually operate and/or 3.2 47 monitor local operation of breakers in the control room.

262002 UPS (AC/DC) 1 (K4.01) Knowledge of the UPS design feature 3.1 48 and/or interlocks which provide for the transfer from preferred power to alternate power supplies.

263000 DC Electrical 1 1 (K1.02) Knowledge of the physical connections 3.2 49 Distribution and/or cause-effect relationships between DC electrical distribution system and the battery charger and batteries.

(A2.02) Ability to predict the impact of a loss of 2.6 50 ventilation during charging and based on those predictions, use procedures to correct, control, or mitigate the consequence of this condition.

264000 EDGs 1 (A1.03) Ability to predict and/or monitor 2.8 51 changes in operating voltages, currents, and temperatures associated with the Emergency Diesel Generators.

300000 Instrument Air 1 (A2.01) Ability to predict the impact of air 2.9 52 dryer and filter malfunctions on the Instrument Air System and based on those predictions, use procedures to correct, control, or mitigate the consequences of this condition.

400000 Component Cooling 1 (K4.01) Knowledge of the CCW design feature 3.4 53 Water and/or interlocks which provide for the automatic start of the standby pump.

K/A Category Point Totals: 2 2 4 4 1 0 3 3 4 3 0 Group Point Total: 26/5 Revision 2

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 K5 K A A A A G K/A Topic(s) IR #

1 2 3 4 6 1 2 3 4 201001 CRD Hydraulic 1 (G.2.2.39) Knowledge of less than or 3.9 54 equal to one hour Technical Specification action statements for CRD Hydraulics.

201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 1 (A1.01) Ability to predict and/or monitor 3.2 55 changes in first stage shell pressure associated with RCIS.

201006 RWM 202001 Recirculation 1 (K6.09) Knowledge of the effect that a 3.4 56 loss of reactor water level will have on the Recirculation System.

202002 Recirculation Flow Control 1 (K1.09) Knowledge of the physical 3.1 57 connections and/or cause effect relationships between Recirculation Flow Control and reactor water level.

204000 RWCU 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst. 1 (A1.03) Ability to predict and/or monitor 2.9 58 changes in parameters associated with operating the Nuclear Boiler Instrumentation including surveillance testing.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 1 (K4.02) Knowledge of Fuel Handling 3.3 59 Equipment design features and/or interlocks which provide for prevention of control rod movement during core alterations.

239001 Main and Reheat Steam 1 (G.2.4.20) Knowledge of the operational 3.8 60 implications of EOP warnings, cautions, and notes as related to main and reheat steam..

239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux. 1 (A3.05) Ability to monitor operation of 3.0 61 main turbine generator and control valve automatic operation.

Revision 2

256000 Reactor Condensate 259001 Reactor Feedwater 1 (K1.05) Knowledge of the physical 3.2 62 connections and/or cause-effect relationships between Reactor Feedwater System and Condensate.

268000 Radwaste 271000 Offgas 1 (K5.11) Knowledge of the operational 2.6 63 implications of the necessity of reducing the relative humidity of carbon bed filters in the Offgas System.

272000 Radiation Monitoring 286000 Fire Protection 1 (A4.05) Ability to manually operate and 3.3 64 or monitor the fire pump in the main control room.

288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals 1 (K6.01) Knowledge ot the effect that a 2.8 65 loss or malfunction of the CRD Hydraulic system will have on Reactor Vessel Internals.

K/A Category Point Totals: 2 0 0 0 1 2 2 1 1 1 2 Group Point Total: 12/3 Revision 2

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 #

2.1.19 Ability to use plant computers to evaluate system or 3.9 66 component status.

1.

2.1.29 Knowledge of how to conduct system lineups, such as 4.1 67 Conduct of Operations valves, breakers, switches, etc.

2.1.34 Knowledge of primary and secondary plant chemistry 2.7 68 limits.

2.1.

Subtotal 2.2.17 Knowledge of the process for managing maintenance 2.6 70

2. activities during plant operations, such as risk assessments, Equipment work prioritization, and coordination with the transmission Control system operator.

2.2.18 Knowledge of the process for managing maintenance 2.6 71 activities during shutdown operations, such as risk assessments, work prioritization, etc.

2.2.23 Ability to track Technical Specification limiting conditions 3.1 69 for operations 2.2.

2.2.

Subtotal 2.3.15 Knowledge of radiation monitoring systems, such as fixed 2.9 73

3. radiation monitors and alarms, portable survey Radiation instruments, personnel monitoring equipment, etc.

Control 2.3.7 Ability to comply with radiation work permit requirements 3.5 72 during normal or abnormal conditions.

2.3.

Subtotal 2.4.1 Knowledge of EOP entry conditions and immediate action 4.6 74 steps.

4.

2.4.5 Knowledge of the organization of the operating procedures 3.7 75 Emergency Procedures / network for normal, abnormal, and emergency evolutions.

Plan 2.4.

2.4.

Subtotal Tier 3 Point Total 10 7 Revision 2

ES-401 Record of Rejected K/As RO Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 295024 EK3.08 Containment spray is not applicable to RBS design. Re-selected 295024 EK3.05.

1/1 600000 AA1.07 Importance rating <2.5. Based on review of Plant Safety Analysis performance of this action is not of high significance. Re-selected 600000 AA1.09 1/1 295021 AK3.04 This function is not performed in the associated abnormal operating procedure. Re-selected. 295021 AK3.05 2/1 203000 A1.07 Importance rating <2.5. Based on review of Plant Safety Analysis performance of this action is not of high significance. Re-selected 203000 A1.02 2/1 259002 K1.07 Rod worth minimizer is not applicable to RBS design. Re-selected 259002 K1.03.

2/1 261000 A4.05 RBS is equipment with a Mark III containment, this KA therefore is not applicable. Re-selected 261000 A4.09 2/1 400000 K5.01 Importance rating <2.5. Based on review of Plant Safety Analysis knowledge of this item and associated actions is not of high significance. Re-selected 400000 A4.01 2/2 201001 K3 K3s were oversampled in T2G1 while K5 and Generics had <2 topics selected. In order to balance the Tier, two K3 topics were randomly selected to be rejected in favor of a K5 and a Generic. In this case, re-selected 201001 G2.2.39.

2/2 271000 K3 K3s were oversampled T2G1 while K5 and Generics had <2 topics selected. In order to balance the Tier, two K3 topics were randomly selected to be rejected in favor of a K5 and a Generic. In this case, 271000 K5.11 3 G.2.2.5 Importance rating <2.5 and is of no particular importance to the site at the RO level. Re-selected G.2.2.12 1/1 295024 EK3.05 Rejected due high drywell pressure not being a condition that requires RPV flooding. Reselected 295024 EK3.06 1/1 295038 EA2.02 Rejected due to this not being a function performed by the Reactor Operator. Reselected 295038 EA2.03 1/2 295002 AK2.06 Rejected due to low operational validity for discriminatory RO level question. Reselected 295002 AK2.04 Revision 2

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/2 295034 EK3.03 Rejected due to inability to write a discriminatory RO level question. Reselected 295034 EK3.02 3 G 2.2.12 This KA was on both the 2004 and 2007 NRC Exams. Randomly selected KA G.2.2.23 3 G 2.3.11 This KA was on both the 2004 and 2007 NRC Exams. Randomly selected KA G.2.3.7 to replace.

2/2 234000 A2.03 Rejected due to inability to write a discriminatory RO level question. Reselected 234000 K4.02.

Revision 2

ES-401 BWR Examination Outline SRO Form ES-401-1 Facility: River Bend Station Date of Exam: 11/21/2008 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 0 3 3 Evolutions Tier Totals 27 2 8 10 1 26 3 2 5 2.

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

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