ML090270030
| ML090270030 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/18/2008 |
| From: | NRC/RGN-II |
| To: | |
| References | |
| 05000324/2008-302, 05000325/2008-302 | |
| Download: ML090270030 (11) | |
Text
Draft Submittal (Pink Paper)
DRAFT Written Exam Quality Checklist (ES-401-6)
& Written Exam Sample Plan
ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Date of Exam: HI Exam Level: RO ~ SRO 1&
Initial Item Description a
- 1. Questions and answers are technicall accurate and ap licable to the facilit .
- 2. a. NRC KJAs are referenced for all questions.
- b. Facilit learnin ob'ectives are referenced as available.
- 4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from the last 2 NRC licensin exams, consult the NRR OL ro ram office.
- 5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
X the audit exam was systematically and randomly developed; or
_ the audit exam was completed before the license exam was started; or
_ the examinations were developed independently; or
_ the licensee certifies that there is no duplication; or
_ other (explain)
- 6. Bank use meets limits (no more than 75 percent Bank Modified New from the bank, at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only 0/0 /1..\
question distribution(s) at ri ht.
- 7. Between 50 and 60 percent of the questions on the RO Memory CIA exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels; enter the actual RO / SRO question distribution s at ri ht.
- 8. References/handouts provided do not give away answers or aid in the elimination of distractors.
- 9. Question content conforms with specific KIA statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.
- 10. Question ps chometric quality and format meet the uidelines in ES Appendix B.
- 11. The exam contains the required number of one-point, multiple choice items; the total is correct and a rees with the value on the cover sheet.
Printed Name / Signature Date
- a. Author
- b. Facility Reviewer (*)
- c. NRC Chief Examiner (#)
- d. NRC Regional Supervisor Note:
- The facility reviewer's initials/signature are not applicable for NRC-developed examinations.
- Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
r
ES-401 BWR Examination Outline Form ES-401-1 tJ 1LJ..JP7 Facility: Brunswick Date of Exam: Oct 27,2008
( Tier Group RO KIA Category Points K K K K K K A A A A G A2 SRO-Only Points G* Total 1 2 3 4 5 6 1 2 3 4
- Total
- 1. 1 6 2 4 3 3 2 20 4 3 7 Emergency &
Abnormal Plant 2 2 2 1 N/A 1 1 N/A 0 7 2 1 3 Evolutions Tier Totals 8 4 5 4 4 2 27 6 4 10 1 4 2 3 2 3 2 2 2 1 2 3 26 3 2 5 2.
Plant 2 1 1 2 0 1 1 2 1 1 0 2 12 2 1 3 Systems Tier Totals 5 3 5 2 4 3 4 3 2 2 5 38 5 3 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 2 2 2 1 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 (Le., 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/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 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 KlAs having an importance rating (lR) 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 KlAs.
B. On the following pages, enter the KIA 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 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 10 CFR 55.43.
ES-401 2 Form ES-401-1 I ES-401 BWR Examination Outline Form E 1::.
lutions - Tier 1/Group 1 eRO I SROl
( E/APE # I Name I Safety Function K 1
K 2
K A 3 1 A
2 G KIA Topic(s) IR #
295001 Partial or Complete Loss of Forced X AA2.03: Actual core flow 3.3/3.3 Core Flow Circulation 11 & 4 295003 Partial or Complete Loss of AC I 6 X AKl.03: Knowledge of the operational implications of 2.9/3.2 the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF A.C.
POWER - Under voltage/degraded voltage effects on electrical loads 295004 Partial or Total Loss of DC Pwr 16 X X AK1.02: Redundant D.C. power supplies 3.2/3.4 AA2.01 Cause of partial or complete loss of D.C. 3.2/3.6 power 295005 Main Turbine Generator Trip / 3 X AK3.07: Knowledge of the reasons for the following 3.8/3.8 responses as they apply to MAIN TURBINE GENERATOR TRIP - Bypass valve operation 295006 SCRAM / 1 X G2.2.3 (multi-unit license) Knowledge of the design, 3.8/3.9 procedural, and operational differences X between units.
G2.2.37: Ability to determine operability and/or 3.6/4.6 availability of safety related equipment.
295016 Control Room Abandonment! 7 X AA 1.08: Reactor pressure 4.0/4.0 295018 Partial or Total Loss of CCW /8 X X AK1.01: Effects on component/system operations 3.5/3.6 AA2.03: Cause for partial or complete loss 3.213.5 295019 Partial or Total Loss of Inst. Air /8 X AK3.01: Backup air system supply: 3.3/3.4 295021 Loss of Shutdown Cooling / 4 X AA2.05: Reactor vessel metal temperature 3.4/3.5 295023 Refueling Ace / 8 X G2.4.8: Knowledge of how abnormal operating 3.8/4.5 procedures are used in Iconjunction with EOPs.
295024 High Drywell Pressure / 5 X EK1.01: Drywell integrity: 3.9/4.0 295025 High Reactor Pressure / 3 X EK2.08: Knowledge of the interrelations between 3.7/3.7 HIGH REACTOR PRESSURE and the following - Reactor/turbine pressure regulating system 295026 Suppression Pool High Water X X EA 1.01: Containment spray 3.2/3.4 Temp. / 5 EA2.03 Reactor pressure Mark-III 3.3/3.3 295027 High Containment Temperature / 5 .X EK2.04 SPDS/ERIS/CRIDS/GDS: Mark-III 2.6/3.2 295028 High Drywell Temperature / 5 X EK1.02: E'l uipment environmental qualification 2.9/3.1 295030 Low Suppression Pool Wtr Lvi / 5 X G2.1.7: Ability to evaluate plant performance and 4.4/4.7 make operational judgments Ibased on operating characteristics, reactor behavior, and instrument interpretation.
295031 Reactor Low Water Level / 2 X X EK3.04 Steam cooling 4.0/4.3 G2.2.39: Knowledge of less than or equal to one 3.9/4.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> Technical Specification action statements for systems.
295037 SCRAM Condition Present X EA2.03: SBLC tank level 4.3/4.4 and Reactor Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 X EK3.02: System isolations 3.9/4.2 600000 Plant Fire On Site / 8 X AK1 .02: Knowledge of the operation applications of 2.9/3.1 the following concepts as they apply to Plant Fire On Site - Fire Fighting
700000 Generator Voltage and Electric Grid X X AK1.03: Under-excitation 3.3/3.4 Disturbances 1 6 AA2.04: VARs outside capability curve 3.6/3.6
( KIA Category Totals: 6 2 4 3 3
/
4 2
/
3 Group Point Total: 2 0
1 7
(
(
ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1
( EIAPE # I Name I Safety Function Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I SRO)
K K K A A G KIA Topic(s) IR #
1 2 3 1 2 295002 Loss of Main Condenser Vac I 3 295007 High Reactor Pressure I 3 X G2.1.7: Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor 4.4/4.7 behavior, and instrument interpretation.
295008 High Reactor Water Levell 2 X AK2.03: Knowledge of the interrelations between 3.6/3 .7 HIGH REACTOR WATER LEVEL and the following - Reactor water level control 295009 Low Reactor Water Levell 2 X AK2.01: Knowledge of the interrelations between 3.9/4.0 LOW REACTOR WATER LEVEL and the following - Reactor water level indication 295010 High Drywell Pressure I 5 X AK1.03: Knowledge of the operational implications of 3.2/3.4 the following concepts as they apply to HIGH DRYWELL PRESSURE -
Temperature increases 295011 High Containment Temp 15 X AK1.01: Containment pressure: Mark-III 4.0/4.1 295015 Incomplete SCRAM 11 X AA2.02: Control rod position 4.1/4.2 295022 Loss of CRD Pumps 11 X AA2.02 Ability to determine and/or interpret the 3.3/3.4 following as they apply to LOSS OF CRD PUMPS* CRD system status 295032 High Secondary Containment X EK3.01: Knowledge of the reasons for the following 3.5/3.8 Area Temperature 15 responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE - Emergencylnormal depressurization 295034 Secondary Containment X EA 1.03: Ability to operate andlor monitor the 4.0/3.9 Ventilation High Radiation I 9 following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION - Secondary containment ventilation 295035 Secondary Containment High X EA2.03: Ability to determine and/or interpret the 3.4/3.8 DiffefEMtial Pressure I 5 following as they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL - Cause of the high water level KIA Category Point Totals: 2 2 1 1 1 1 Group Point Total: 7 I I 2 3 th ....
(
( ES-401 BWR Examination Outline Plant Systems - Tier 2/Group 1 (RO / SRO)
Form ES-401-1 System # / Name K K K K K K A A A A G KIA Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 203000 RHRlLPCI: Injection X X K5.02: Knowledge of the operational 3.3/3.7 Mode implications of the following concepts as they apply to RHRlLPCI : INJECTION MODE (PLANT SPECIFIC) - Core cooling methods 3.2/3.4 A2.01: Ability to (a) predict the impacts of the following on the RHRlLPCI: INJECTION MODE (PLANT SPECIFIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of
't hose abnormal conditions or operations* Inadequate net positive suction head 205000 Shutdown Cooling X K2.01: Knowledge of electrical power 3.1/3.1 supplies to the following - Pump motors 206000 HPCI X 2.4.14: Knowledge of general guidelines 3.8/4.5 for EOP usage 207000 Isolation (Emergency) X X K2.02: Knowledge of electrical power 3.5/3.7 Condenser supplies to the following - Initiation X logic 2.2.17 Knowledge ofthe process for 2.6/3.8 managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.
2.2.37 Ability to determine operability and/or availability of safety related 3.6/4.6 equipment.
209001 LPCS X A4.02: Ability to manually operate and/or 3.5/3.4 monitor in the control room -
Suction valves 209002 HPCS X K1.12: Knowledge of the physical 3.4/3.6 connections and/or causeeffect relationships between HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) and the following
- Reactor vessel 211000 SLC X K5.02: Knowledge of the operational 2.8/3.0 implications of the following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM - Chugging (as it pertains to boron mixing) 212000 RPS X A2.15: Ability to (a) predict the impacts 3.7/3.8 of the following on the REACTOR PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations - Load rejection
2150031RM X A4.07: Ability to manually operate and/or 3.6/3.6 monitor in the control room -
Verification of proper functioning/
operability
( 215004 Source Range Monitor X K4.01 : Knowledge of SOURCE RANGE MONITOR (SRM) SYSTEM design feature(s) and/or interlocks which provide for the following - Rod 3.7/3.7 withdrawal blocks 215005 APRM / LPRM X A3.03: Ability to monitor automatic 3.3/3.3 operations of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM inciudiClf! - Meters and recorders 217000 RCIC X X K1.01 : Knowledge of the physical 3.5/3.5 connections and/or causeeffect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following
- Condensate storage and transfer system 3.3/3.3 A2.OS: Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations - D.C .~ower loss 218000 ADS X A2.01 : Ability to (a) predict the impacts of 4.1/4.3 the following on the AUTOMATIC DEPRESSURIZATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations - Small steam line break LOCA 223002 PCIS/Nuclear Steam X X K4.08: Knowledge of PRIMARY 3.3/3.7 Supply Shutoff CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF design feature(s) and/or interlocks which provide for the following - tManual defeating of selected isolations during specified emergency conditions K6.08: Knowledge of the effect that a loss or malfunction of the following will 3.5/3.7 have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF - Reactor
~otection system 239002 SRVs X K6.03: Knowledge of the effect that a 2.7/2.9 loss or malfunction of the following will have on the RELIEF/SAFETY VALVES -
A.C. power: Plant-Specific 259002 Reactor Water Level X A 1.05: Ability to predict and/or monitor 2.9/2.9 Control changes in parameters associated
(. with operating the REACTOR WATER LEVEL CONTROL SYSTEM controls including -
FWRV/startup level control position
261000 SGTS X A 1.02: Ability to predict and/or monitor 3.1/3.2 changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including - Primary containment
( 262001 AC Electrical X X pressure K3.04: Knowledge of the effect that a loss 3,1/3.3 Distribution or malfunction of the AC.
ELECTRICAL DISTRIBUTION will have on following - Uninterruptible power supply A2.03: Ability to (a) predict the impacts of 3.9/4.3 the following on the AC.
ELECTRICAL DISTRIBUTION ;
and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations - Loss of off-site power 262002 UPS (AC/DC) X X K1.16: Knowledge of the physical 3.1/3.2 connections and/or causeeffect relationships between NINTERRUPTABLE POWER SUPPLY (A.C.!D.C.) and the following - MSIVs K3.02: Knowledge of the effect that a loss 2.9/2.0 or malfunction of the UNINTERRUPTABLE POWER SUPPLY (AC.!D.C.) will have on following - Recirculation pump speed 263000 DC Electrical X K2.01 : Knowledge of electrical power 3.1/3.4 Distribution supplies to the following - Major D.C. loads 264000 EDGs X X K5.06: Knowledge of the operational 3.4/3.5 implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEUJET) - Load sequencing 2.4.41: Knowledge of the emergency 2.9/4.6 action level thresholds and classifications 300000 Instrument Air X 2.1.20: Ability to interpret and execute 4.6/4.6 procedure steps 400000 Component Cooling X K1.03: Knowledge of the physical 2.7/3.0 Water connections and / or cause-effect relationships between CCWS and the following - Radiation monitoring systems KIA Category Point Totals: 4 2 3 2 3 2 2 2 1 2 3 Group Point Total: 26/
/ / 5 3 2
ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 2iRO / SRQL
( System # / Name K 1
K*
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G KIA Topic(s) IR #
201001 CRD Hydraulic 201002 RMCS X 201003 Control Rod and Drive ~
Mechanism 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation /X 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe /X 215002 RBM -= -
216000 Nuclear Boiler Inst. X
/'
219000 RHRllPCI: Torus/Pool Cooling X Mode 223001 Primary CTMT and Aux.
226001 RHRllPCI: CTMT Spray Mode --
X 230000 RHRllPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup ~
234000 Fuel Handling Equipment 239001 Main and Reheat Steam -)(
239003 MSIV leakalle Control Irx-1\.../
241000 ReactoriTurbine Pressure Regulator 245000 Main Turbine Gen. / Aux.
256000 Reactor Condensate I~
259001 Reactor Feedwater 268000 Radwaste
../
271000 Offgas X 272000 Radiation Monitoring X 286000 Fire Protection 288000 Plant Ventilation Irx
~
290001 Secondary CTMT 290003 Control Room HVAC j
290002 Reactor Vessel Internals X KIA Category Point Totals: I I 2 0 I I 2 I I 0 2 Group Point Total: 1213
/ /
2 I
( ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:
Category KIA # Topic RO SRO-Only IR # IR #
2.1.1 Knowled2e of conduct of operations requirements 4.2 X
( 1.
Conduct 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance lof active license status, 3.3 X of Operations 10CFR55, etc 2.1.7 Ability to evaluate plant performance and make operational 4.4 X judgments based on operating characteristics, reactor behavior, and instrument interpretation 2.1.17 Ability to make accurate clear, and concise verbal reports 4.0 X 2.1.19 Ability to use plant computers to evaluate system or component 3.9 X status 2.1.
Subtotal 3 2 2.2.4 (multi-unit license) Ability to explain the variations in control 3.6 X board/control room layouts, systems, instrumentation, and procedural actions between units at a facility 2.
Equipment 2.2.6 Knowledge of the process for making changes to procedures 3.0 X Control 2.2.12 Knowled2e of surveillance procedures I
- 4.1 X 2.2.18 Knowledge of the process for managing maintenance activities 2.6 X during shutdown operations, such as risk assessments, work prioritization, etc 2.220 Knowledge of the process for managing troubleshooting 3.8 X activities 2.2.
Subtotal 3 2 2.3.6 Ability to approve release permits 3.8 X 2.3.12 3.2 X
- 3. 2.3.14 Knowledge of radiation or contamination hazards that may 3.4 X Radiation arise during normal, abnormal, or emergency conditions or Control activities 2.3.15 Knowledge of radiation monitoring systems, such as fixed 3.1 X radiation monitors and alarms, portable survey instruments personnel monitorin21 equipment etc 2.3.
2.3.
Subtotal 2 2 2.4.9 Knowledge oflow power/shutdown implications in accident 3.8 X (e.g., loss of coolant accident or loss of residual heat removal)
- 4. mitigation strategies Emergency 2.4.27 Knowled2e of "fire in the plant" procedures 3.9 X Procedures /
Plan 2.4.45 Ability to prioritize and interpret the significance of each 4.1 X annunciator or alarm 2.4.
2.4.
2.4.
Subtotal 2 1
( Tier 3 Point Total 10 7