ML102920661
| ML102920661 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 07/20/2010 |
| From: | Goff C B Exelon Generation Co, Exelon Nuclear |
| To: | Caruso J G, Dapas M L Region 1 Administrator |
| Hansell S | |
| Shared Package | |
| ML100560247 | List: |
| References | |
| TAC U01767 | |
| Download: ML102920661 (32) | |
Text
Limerick Generating Station www.exeloncorp.com 3146 Sanatoga Road Nuclear Pottstown, PA 19464 10CFR 55.40 July 20, 2010 Mr. Marc Dapas, Ac t ing Regional Administrator U. S. Nuclear Regulatory Region 475 Allendale King of Prussia, PA Limerick Generating Station, Units 1 and 2 Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353
Subject:
Initial License Operator Program Exam Outlines
Reference:
NRC letter dated 6/14/10 SRO & RO Initial Exams-LGS
Dear Sir:
As requested in the referenced letter, the following NUREG-1021 required have been provided to Mr. J. Caruso regarding the Initial Operator Licensing Exams be administered beginning on October 4, 2010 at Limerick Generating ES-201-2 Exam Outline Quality ES-201-3 Examination Security ES-301-1 Administrative Topics ES-301-2 Control Roomlln-plant Systems ES-301-5 Transient and Event ES-401-1 BWR Exam ES-401-3 Generic Knowledge and Abilities ES-401-4 Record of Rejected ES-D-1 Scenario If you have any questions or need additional information, please contact Mr. Corey at (610)
Sincerely, Manager-Operator Training Exelon Generation Corp.
Enclosures:
Documents stated above to Mr. J. Caruso only cc: J. Caruso, USNRC, Region I (w/encl) S. Hansell, USNRC Region I (wlo encl) E. DiPaolo, USNRC Senior Resident Inspector, LGS (wlo encl) Document Control Desk, USNRC, Washington, DC (wlo encl) bcc: W. Maguire -GML5-1 (w/o encl) E. Callan -GML 5-1 (w/o encl) P. Gardner -GML 5-1 (w/o encl) R. Dickinson
-LLC3-1 (w/o encl) C. Goff -LLC-3-1 (w/o encl) E. Pierce -LLC-3-1 (w/o encl) J. Hunter III -SSB 2-4 (w/o encl) A. Columbus -SSB 4-2 (w/o PA DERBRP Inspector, LGS 5MB2-4 (w/o 27 July 2010 Review Comments for T -75 Day Limerick Exam Outline Submittal The exam outline was hand delivered to the Regional office on Tuesday, 7/20 and comments were provided per telecom on 7/27/10. The outline was developed using a BWR Owners Group Random Generator software.
The audit exam is being developed independently by a different staff person in a separate area with no communications in so far as the written exam. The NRC operating tests were developed with no overlap with the topics planned for the audit exam. Scenarios The scenario outlines are all new. Requested that narratives be provided next week which include the proposed Critical Tasks for each scenarios.
Admin JPMs RO topic Shift Turnover Checklist will be designed for classroom administration
-change "S" to "R" on outline. RO topic to Activate Site Evacuation is planned for HI Rad situation with announcement suggested to include activation of emergency organization also SRO topic Shift Turnover Checklist A.1.1 will be designed for classroom administration change "S" to "R" on outline. This will include TS implications SRO topic Pre Control Rod Withdrawal Checks will also include TS implications.
Simulator JPMs Three proposed alt path JPMs involve securing equip due to hi vibs (b) or hi temp (c & e) and in addition only one new and one modified JPM which is at the minimum the rest from the bank suggested replacing RCIC JPM with a new alt path JPMs. In addition, for the 5 JPMs designated for SROUs 2 of the 5 were from the last 2008 NRC exam. Suggested replacing a or g. Written SRO Outline The following KIA question topics did not appear to be SRO level topics: 1, 2, 3, 6, 8, 9, 10, 13, 14,17,94,95,98,96.
Written RO Outline Cautioned not to write questions involving simply asking what the power supplies are to a component directly ex. air compressors.
Written Examination Outline Form ES-401-1 Facility:
201ONRCRO Date of Exam: RO KIA Category Points SRO-Only Points Tier Group K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G
- Total A2 G* Total l. Emergency
& Plant Evolutions 1 2 Tier Totals 3 2 5 4 1 5 3 1 4 <.'
4 3 .1 it. 1 !.... Ixi. ..*. 5 4 1< . 3 1 4 20 7 27 7 3 10 1 3 2 3 2 3 2 2 3 2 2 2 26 5 2. Plant 2 1 1 2 1 1 1 1 1 I 1 1 12 3 Systems Tier Totals 4 3 5 3 4 3 3 4 3 3 3 38 8 1 2 3 4 1 2 3 4 3. Generic Knowledge
& Abilities 7 Categories 3 3 2 2 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). Note: l. 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 +/-l 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. 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.l.b of ES-401, for guidance regarding elimination of inappropriate KIA statements. 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. Absent a plant specific priority, only those KAs having an importance rating (IR) of2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively. Select SRO topics for Tiers I and 2 from the shaded systems and KIA categories. 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.I.b of ES-401 for the applicable KIA's 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. 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 IOCFR55.43 2 Form ES-401-1 2010 NRC Written Examination Emergency and Abnormal Plant Evolutions
-Tier 1 Group EAPE # / Name Safety KIA Topic(s) EKLOI -Knowledge of the operational implications of the following concepts as 295037 SCRAM Conditions they apply to SCRAM CONDITION Present and Reactor Power Above X PRESENT AND REACTOR POWER 4.1 39 APRM Downscale or Unknown I I ABOVE APRM DOWNSCALE OR UNKNOWN: Reactor pressure effects on reactor power AKI.02 -Knowledge of the operational 295001 Partial or Complete Loss of implications of the following concepts as Forced Core Flow Circulation I I & X they apply to PARTIAL OR COMPLETE 3.3 40 4 LOSS OF FORCED CORE FLOW ClRCULA TION : Powerlflow distribution I
of the operational 295006 SCRAM I I s of the following concepts as 3.7 41 they apply to SCRAM: Reactivity control AK2.0I -Knowledge of the interrelations 295016 Control between CONTROL ROOM 4.4 42 Abandonment I ABANDONMENT and the Remote shutdown panel:
AK2.05 -Knowledge of the 295019 Partial or Total Loss between PARTIAL OR COMPLETE3.4 43 Ins!. Air LOSS OF INSTRUMENT AIR and following:
Main steam EK2.18 -Knowledge of the 295024 High Drywell Pressure I 5 X between HIGH DRYWELL PRESSURE 3.3 44 and the following:
Ventilation EK3.01 Knowledge of the reasons for the following responses as they apply to 295026 Suppression Pool High SUPPRESSION POOL HIGH WATER 3.8 45 Water Temp. IS TEMPERATURE:
Emergency/normal depressurization AK3.05 Knowledge of the reasons for the following responses as they apply to 295005 Main Turbine Generator MAIN TURBINE GENERATOR TRIP: 2.S 46 Trip 13 Extraction steam/moisture separator isolations AK3.03 Knowledge of the reasons for the following responses as they apply to 295018 Partial or Total Loss PARTIAL OR COMPLETE LOSS OF3.1 47COMPONENT COOLING Securing individual components equipment AA 1.01 Ability to operate and/or 295023 Refueling Ace the following as they apply to 3.3 48 Model REFUELING ACCIDENTS:
containment EA 1.04 Ability to operate and/or 295038 High Off-site Release the following as they apply to HIGH 2.8 49SITE RELEASE SPDS/ERIS/CRIDS/GDS:
EA1.01 Ability to operate and/or 295028 High Drywell the following as they apply to HIGH3.8 50DRYWELL TEMPERATURE: spray:
AA2.04 Ability to determine 295021 Loss of Shutdown interpret the following as they apply to 3.6 51 14 LOSS OF SHUTDOWN COOLING: Reactor water temperature Partial or Total Loss of DC AA2.04 -Ability to determine and/or 3.2 52 r interpret the following as they apply to 2 Form ES-401-1 2010 !\IRC Written Examination Emergency and Abnormal Plant Evolutions
-Tier 1 Group / Name Safety KIA Topic(s) PARTIAL OR COMPLETE LOSS OF D.C. POWER: System lineups EA2.06 Ability to determine and/or interpret the following as they apply to 295025 High Reactor Pressure I 3 3.7 53 HIGH REACTOR PRESSURE:
Reactor water level 2.1.23 -Conduct of Operations:
Ability to 295030 Low Suppression Pool perform specific system and integrated 4.3 54 Water Levell plant procedures during all modes of plant operation.
2.2.4 Equipment Control: (multi-unit license} Ability to explain the variations in 295003 Partial or Complete Loss of X control board layouts, systems, 3,6 55 AC/6 instrumentation and procedural actions between units at a facility.
2.4,8 Emergency Procedures
/ Plan: Knowledge of how abnormal operating 600000 Plant Fire On-site I 8 3,8 56 procedures are used in conjunction with EOP's. AA 1.01 -Ability to operate and/or monitor the following as they apply to 700000 Generator Voltage and X GENERATOR VOLTAGE AND 3.6 57 Electric Grid Disturbances ELECTRIC GRID DISTURBANCES: frequency and EK2.02 Knowledge of the 295031 Reactor Low Water Levell between REACTOR LOW 3.8 58LEVEL and the following:
Reactor pressure KI A Category Totals: 3 4 3 4 3 3 Group Point Total: 20 I ES-401 3 Form ES-401-1 2010 !\IRC Written Examination Emergency and Abnormal Plant Evolutions Tier 1 Group EAPE # I Name Safety Function KIA Topic(s) EKI.02 Knowledge of the operational 295033 High Secondary implications of the following concepts as Containment Area Radiation Levels X they apply to HIGH SECONDARY 3,9 59 19 CONTAINMENT AREA RADIATION LEVELS: Personnel EK2.04 Knowledge of the 295035 Secondary Containment between SECONDARY X 3.3 60 High Differential Pressure I 5 HIGH DIFFERENTIAL PRESSURE and the following:
Blow-out panels: Plant-Specific AK3,02 Knowledge of the reasons for the 295022 Loss of CRD Pumps I I X following responses as they apply to LOSS 2,9 61 OF CRD PUMPS: CRDM high temperature EAL03 Ability to operate and/or monitor 295036 Secondary Containment the following as they apply to SECONDARY X 2,8 62 High Sumpl Area Water Levell 5 CONTAINMENT HIGH SUMPIAREA WATER LEVEL: Radwaste EA2,03 Ability to determine and/or 295029 High Suppression Pool interpret the following as they apply to HIGH X 3.4 63 Water Levell 5 SUPPRESSION POOL WATER LEVEL: Dryweillcontainment water level 2,1.7-Conduct of Operations:
Ability to evaluate plant performance and make 295014 Inadvertent Reactivity X operational judgments based on operating 4.4 64 Addition!
1 characteristics.
reactor behavior, and instrument interpretation.
AKI,02 Knowledge of the operational implications of the following concepts as 295012 High Drywel\ Temperature X they apply to HIGH DRYWELL 3.1 65 15 TEMPERATURE' Reactor power level control KIA Category Totals: 2 1 1 1 1 1 Group Point Total: 7 I ES-401 4 Form ES-401-1 2010 NRC Written Examination Plant Systems -Tier 2 Group System # / Name G Imp. Q# KI.I2 Knowledge of the physical connections and/or cause-effect 223002 PCIS/Nuclear Steam Supply Shutoff X relationships between PRIMARY CONTAINMENT ISOLATlON SYSTEM/NUCLEAR STEAM 31 1 SUPPLY SHUT-OFF and the Standby gas treatment system K1.05* Knowledge of the physical connections and/or cause-effect relationships between 264000 EDGs X EMERGENCY GENERATORS
- 3. 2 (DIESEUJET) and the following:
Emergency generator fuel oil supply system 203000 RHRlLPCI:
Injection Mode X K2.02 Knowledge of electrical power supplies to the following:
Valves K2.01 Knowledge of electrical 300000 Instrument Air X power supplies to the following:
Instru K3.01 Knowledge of the effect that a loss or malfunction of the 205000 Shutdown Cooling X SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING 3.3 5 MODE) will have on following:
Reactor pressure K3.08 -Knowledge of the effect that a loss or malfunction of the AVERAGE POWER RANGE 215005 APRM / LPRM X MONITOR/LOCAL POWER 30 6 RANGE MONITOR SYSTEM will have on following:
core thennal calculations K4.02 Knowledge of SOURCE RANGE MONITOR (SRM) 215004 Source Range Monitor X SYSTEM design feature(s) and/or 3.4 7 interlocks which provide for the followinq:
Reactor SCRAM siQnals K4.05 -Knowledge of A.C. ELECTRICAL DISTRIBUTION 26200 1 AC Electrical Distribution X design feature(s) and/or interlocks which provide for the following:
3.4 8 Paralleling of A.C. sources (synchroscope)
K5.02 -Knowledge of the operational implications of the 217000 RCIC X following concepts as they apply to REACTOR CORE ISOLATION 3.1 9 COOLING SYSTEM (RCIC): Flow indication K5.07 -Knowledge of the operational implications of the 211000 SLC X following concepts as they apply to 2.7 10 STANDBY LIQUID CONTROL SYSTEM: Tank heater operation ES-401 4 Form ES-401-1 2010 NRC RO Written Examination Outline Plant Systems -Tier 2 Group 1 System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G K6.11 -Knowledge of the effect that a loss or malfunction of the 206000 HPCI X following will have on the HIGH PRESSURE COOLANT INJECTION SYSTEM: Nuclear boiler instrumentation:
BWR-2,3,4 K6.01 -Knowledge of the effect that a loss or malfunction of the 263000 DC Electrical Distribution X following will have on the D.C. ELECTRICAL DISTRIBUTION:
A.C. electrical distribution A 1.06 -Ability to predict and/or monitor changes in parameters associated with operating the 215003 IRM X INTERMEDIATE RANGE MONITOR (IRM) SYSTEM controls including:
Lights and alarms A 1.04 -Ability to predict and/or monitor changes in parameters associated with operating the 261000 SGTS X STANDBY GAS TREATMENT SYSTEM controls including:
Secondary containment differential pressure A2.02 -Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and 239002 SRVs X (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Leaky SRV A2.04 -Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those 209001 LPCS X predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
D.C. failures A3.02 -Ability to monitor automatic operations of the REACTOR 212000 RPS X PROTECTION SYSTEM including:
Individual system relay status: Plant-Specific A3.01 -Ability to monitor automatic operations of the CCWS including:
400000 Component Cooling Water X Setpoints on instrument signal levels for normal operations,warnings, and trips that are applicable to the CCWS A4.03 -Ability to manually operate 218000 ADS X and/or monitor in the control room: ADS logic reset Imp. Q# 3.6 II 3.2 12 3.3 13 3.0 14 3.1 IS 2.9 16 3.2 17 3.0 18 4.2 19 ES-401 4 Form ES-401-1 2010 NRC RO Written Examination Outline Plant Systems -Tier 2 Group 1 System # / Name K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G A4.03 -Ability to manually operate 259002 Reactor Water Level Control X and/or monitor in the control room: All individual component controllers when transferring from manual to automatic modes 2.2.22 -Equipment Control: 262002 UPS (ACIDC) X Knowledge of limiting conditions for operations and safety limits. 2.1.28 -Knowledge of conduct of operations requirements:
262002 UPS (AC/DC) X Knowledge of the purpose and function of major system components and controls .. > A2.03 -Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL 26200 I AC Electrical Distribution X 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 K3.02 -Knowledge of the effect that a loss or malfunction of the 211000 SLC X <> STANDBY LIQUID CONTROL SYSTEM will have on following:
Core spray line break detection system: Plant-Specific K1.08 Knowledge of the physical connections and/or cause-effect 261oo0SGTS X relationships between STANDBY GAS TREATMENT SYSTEM and the following:
Process radiation monitoring system K5.04 -Knowledge of the operational implications of the following concepts as they apply to 215005 APRM I LPRM X AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM: LPRM detector location and core symmetry KIA Category Totals: 3 2 3 2 3 2 2 13 2 2 2 Group Point Total: Imp. Q# 3.8 20 4.0 21 4.1 22 3.9 23 3.0 24 2.8 25 2.9 26 I 26 ES-401 5 Form ES-401-1 2010 NRC Written Examination Plant Systems -Tier 2 Group System # I Name K 1 A 3 A 4 G 215002 RBM 201001 CRD Hydraulic 286000 Fire Protection 288000 Plant Ventilation X X X X 241000 ReactorlTurbine Pressure Regulator X 22600 1 RHRlLPCI:
CTMT Spray Mode 201003 Control Rod and Drive Mechanism X X 272000 Radiation Monitoring X 230000 RHRlLPCI:
Torus/Pool Spray Mode 290003 Control Room HV AC 233000 Fuel Pool Cooling/Cleanup X X X KI.02 -Knowledge of the physical connections and/or cause-effect relationships between ROD BLOCK MONITOR SYSTEM and the following:
LPRM: BWR-3,4,5 K2.02 -Knowledge of electrical power supplies to the following:
Scram valve solenoids K3.02 Know ledge of the effect that a loss or malfunction of the FIRE PROTECTION SYSTEM will have on following:
Personnel protection K4.02 -Knowledge of PLANT VENTILATION SYSTEMS design feature(s) and/or interlocks which provide for the following:
Secondary containment isolation K5.05 -Knowledge of the operational Implications of the following concepts as they apply to REACTOR/TURBINE PRESSURE REGULATING SYSTEM: Turbine inlet pressure vs. turbine load K6.11 -Knowledge of the effect that a loss or malfunction of the following will have on the RHRlLPCI:
CONTAINMENT SPRAY SYSTEM MODE: Component cooling water systems A 1.01 -Ability to predict and/or monitor changes in parameters associated with operating the CONTROL ROD AND DRIVE MECHANISM controls including:
Reactor power A2.07 -Ability to predict the impacts of the following on the RADIATION MONITORING SYSTEM; and {b} based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Hydrogen injection operation:
Plant-Specific A3.01 Ability to monitor automatic operations of the RHRlLPCI:
TORUS/SUPPRESSION POOL SPRAY MODE including:
Valve operation A4.01 -Ability to manually operate and/or monitor in the control room: Initiate/reset system 2.2.37 Equipment Control: Ability to determine operability and! or availability of safety related equipment.
Imp. Q# 3.2 27 36 28 3.2 29 3.7 30 2.8 31 2.8 32 3.7 33 2.8 34 3.4 3S 3.2 36 3.6 37 ES-401 5 Form ES-40 1-1 System # I Name K 1 K 2 271000 Off-gas KIA Category Totals: 1 1 2010 NRC Written Examination Plant Systems -Tier 2 Group K K K K A A A A G Imp. Q#3 4 5 6 1 2 3 4 K3.01 -Knowledge of the effect that a loss or malfunction of the X 3.5 38 OFFGAS SYSTEM will have on following:
Condenser vacuum 1 1 1 1 1 1 1 1 Group Point Total: 12 I Generic Knowledge and Abilities Outline (Tier 3) Form ES-40 1-3 Facility:
2010 NRC Date: SRO-Only Category KIA Topic IR Q# IR Q# Ability to interpret and execute procedure 4.6 66 steps.1. Ability to perform specific system and Conduct 2.1.23 integrated plant procedures during all modes 4.3 67 of Operations of plant operation.
Knowledge of administrative requirements for temporary management directives, such as 2.7 74 standing orders, night orders, Operations memos, etc. *
./.....*.. 3 Ii/i .*****.*.. Ability to determine the expected plant configuration using design and configuration
- 2. 3.9 68 control documentation, such as drawings, line-ups, tag-outs, etc. Control Knowledge of the process for conducting 2.9 69 special or infrequent tests. Ability to apply technical specifications for a 3.4 75 s;tstem.
3 3. -Radiation Control Knowledge of Radialogical Safety Principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling 3.2 70 responsibilities, access to locked high-radiation areas, aligning filters, etc. Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 2.9 71 portable survey instruments, personell monitoring eguiement, etc. !
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Subtotal 4. Emergency Procedures I 2.4.49 Plan 2.4.4 SUbtotal Tier 3 Point Total " 2 "",' Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
4.6 4.5 72 73 I"'" ,',' i' I'.**.'.**.***,'.'*"".*
- .,**,..* 7 Written Examination Outline Form ES-401-1 Facility: Date of Exam: 10/04/10 Tier Group K K Total A2 G* Total1
- 20 4 3 7 2 7 1 2 1. & Plant Tier 27 5 5 10 Totals 26 3 2 5 2. 2 12 1 3Tier 38 5 3 8 Totals 1 2 3 4 1 2 3 4 3. Generic Knowledge
& Abilities 7 Categories 2 2 2 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). Note: 1. 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 +/-l 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. 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. 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. Absent a plant specific priority, only those KAs 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. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7.* The (G) KI As in Tiers I 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. Lb of ES-401 for the applicable KIA's 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. 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 IOCFR55.43 ES-401 2 Form ES-401-1 2010 Written Examination Emergency and Abnormal Plant Evolutions
-Tier 1 Group EAPE # I Name Safety Function KIA Topic(s) AA2,01 -Ability to determine andlor 295004 Partial or Total Loss of DC Pwr/6 X interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Cause of partial or complete loss of D,c' power EA2.06 -Ability to determine andlor 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown I I X interpret the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Reactor pressure AA2.IS Ability to determine and interpret 600000 Plant Fire On-site I 8 X the following as they apply to PLANT FIRE ON SITE: Requirements for establishing a fire watch 295028 High Drywell Temperature I 5 X 2.2.37 -Equipment Control: Ability to determine operability and I or availability of safety related equipment.
2.4.30 -Emergency Procedures I Plan; Knowledge of events related to system 295025 High Reactor Pressure I 3 X operation I status that must be reported to internal organizations or external agencies.
such as the state, the NRC, or the transmission system operator.4, I 2.4.34 -Emergency Procedures I Plan: 295023 Refueling Acc Cooling Mode/8 X Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects, EA2.02 Ability to determine andlor 295038 High Off-site Release Rate I 9 X interpret the following as they apply to HIGH OFF-SITE RELEASE RATE: Total number of curies released KIA Category Totals: 0 0 0 0 4 3 Group Point Total: 3,6 I 4.1 2 3.5 4,6 3 4 5 4.1 3.3 I 6 7 7 3 Form ES-401-1 2010 Written Examination Emergency and Abnormal Plant Evolutions
-Tier 1 Group EAPE # I Name Safety KIA Topic(s) EA2.0 I -Ability to determine andlor interpret the following as they apply to 295035 Secondary Containment High X SECONDARY CONTAINMENT HIGH 3.9 8 Differential Pressure I 5 DIFFERENTIAL PRESSURE:
Secondary containment pressure:
Plant-Specific 2.4.46 Emergency Procedures
/ Plan: 295013 High Suppression Pool X Ability to verify that the alarms are 42 9 Temperature / 5 consistent with the plant conditions.
2.4.35 -Emergency Procedures I 295014 Inadvertent Reactivity Knowledge of local auxiliary operator 4.0 10 Addition during emergency and the resultant operational effects. Kf A Category Totals: 0 0 0 Group Point Total: 3 I ES-401 4 Form ES-401-1 2010 Written Examination Plant Systems -Tier 2 Group K K K K K K A A A A System # / Name G Imp. Q#1 2 3 4 5 6 1 2 3 4 A2.03 Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM; and (b) 202001 Recirculation System X based on those predictions.
use procedures to correct. control. or 3.7 II mitigate the consequences of those abnormal conditions or operations:
Single recirculation pump trip A2.02 -Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) 215004 Source Range Monitor X SYSTEM; and (b) based on those predictions, use procedures to correct, 3.7 12 control, or mitigate the consequences of those abnormal conditions or operations:
SRM inop condition 2.4.49 -Emergency Procedures
/ Plan: Ability to perform without reference to 217000 RCIC X procedures those actions that require 4.4 13 of
-2.2.39 -Equipment Control: Knowledge 218000 ADS X of less than one hour technical specification action statements for 4.5 14 systems. A2.01 -Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR 215003 IRM X (IRM) SYSTEM; and (b) based on those predictions, use procedures to correct, 3.2 15 control, or mitigate the consequences of those abnormal conditions or operations:
Power supply degraded KI A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: I 5 ES-401 5 Form ES-401-1 2010 Written Examination Plant Systems -Tier 2 Group K K K K K System # I Name 1 2 3 4 5 259001 Reactor Feedwater 204000 RWCU 234000 Fuel Handling Equipment K/A Category Totals: 0 0 0 X 1 0 K A A A A G 6 1 2 3 4 A2.03 -Ability to (a) predict the impacts of the following on the REACfOR FEEDWATER SYSTEM; X and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Loss of condensate pump( s) 2.4.2 -Emergency Procedures
/ Plan: X Knowledge of system set points, interlocks and automatic actions assoeiated with EOP entry conditions.
K4.01 Prevention of core alterations during control rod movements 0 0 1 0 0 1 Group Point Total: Imp. Q# 3.6 16 4.6 17 4.1 t1 I ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility:
2010 SRO Date: Category KIA # Topic RO IR Q# SRO-Only IR Q# 2.1.13 Knowledge of facility requirements for controlling vitalI controlled access. 3.2 94 1 . Conduct of Operations Subtotal I", >J li'",%"t 1 2.2.7 Knowledge of the process for conducting special or infrequent tests. 3.6 95 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.7 98 2. Equipment Control Subtotal 2 Knowledge of radiation monitoring systems, 2.3.15 such as fixed radiation monitors and alarms, portable survey instruments, personnel 3.1 96 monitoring equipment, etc. 2.3.11 Ability to control radiation releases.
4.3 99 3. Radiation Control Subtotal .i 2 4. Emergency 2.4.44 Knowledge of emergency plan protective action recommendations.
4.4 97 Procedures!
Knowledge of the parameters and logic used Plan to assess the status of safety functions, such 2.4.21 as reactivity control, core cooling and heat removal, reactor coolant system integrity, 4.6 100 containment conditions, radioactivity release control, etc.
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Subtotal
}'. Tier 3 Point Total 10 !iii ?
ES-401 Record of Rejected KI As Form ES-401-4 Tier I Group Randomly Selected KIA Reason for Rejection RO 1/2 295014 Inadvertent Reactivity Addition, 2.2.42 2.2.42-Equipment Control: Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
Reason for Rejection:
There are no entry-level conditions for Technical Specifications for Inadvertent Reactivity Addition.
Randomly reselected another item within 295014 G: 2.1.7-Conduct of Operations:
Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
RO 2/1 300000 Instrument Air, K2.02 K2.02 -Knowledge of electrical power supplies to the following:
Emergency air compressor Reason for Rejection:
Equipment not applicable to LGS Randomly reselected another item within 300000 K2: K2.01 -Knowledge of electrical power supplies to the following:
Instrument air compressor RO 2/1 263000 DC Electrical Distribution, K6.02 K6.02 -Knowledge of the effect that a loss or malfunction of the following will have on the D.C. ELECTRICAL DISTRIBUTION:
Battery ventilation Reason for Rejection:
Loss of battery ventilation does not result in plant conditions that can be used to develop a discriminating question for a control room operator.
Randomly reselected another item within 263000 K6: K6.01 -Knowledge of the effect that a loss or malfunction of the following will have on the D.C. ELECTRICAL DISTRIBUTION
- A.C. electrical distribution RO 2/1 262002 UPS (AC/DC), 2.4.21 2.4.21 -Emergency Procedures 1 Plan: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. Reason for Rejection:
There are no UPS related functions that impact parameters and logic used to assess the status of safety functions.
Randomly reselected another item within 262002 G: Knowledge of conduct of operations requirements:
Knowledge of the purpose and function of major system components and controls.
RO 2/2 272000 Radiation Monitoring, A2.14 A2.14 -Ability to predict the impacts of the following on the RADIATION MONITORING SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Loss of, or inadequate, shielding Reason for Rejection:
there are no operations related AOPIEOP procedures for loss of, or inadequate, shielding for a radiation monitoring.
Randomly reselected another item within 272000 A2: A2.07 -Ability to predict the impacts of the following on the RADIATION MONITORING SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Hydrogen injection operation:
Plant-Specific SRO 2/1 300000 Instrument Air, A2.01 A2.01 -Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
Air dryer and filter malfunctions Reason for Rejection:
For air dryer and filter malfunctions, control room personnel take no action to correct, control, or mitigate the consequences other than to dispatch appropriate personnel.
All other actions are performed locally. Randomly reselected another item: 300000 A2 only contains 1 item. For this reason randomly selected a different system A2 item: 202001 Recirculation System, A2.03 Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Single recirculation pump trip RO 1/1 295016 Control Room Abandonment AK2.03 -Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and the following:
Control room HVAC Reason for Rejection:
There are no directions provided for an RO to take regarding Control Room Abandonment due to Control Room HVAC. Additionally, there are no directions provided for an RO to take with regards to MCR HVAC during Control Room Abandonment.
Randomly reselected another item within 295016 AK2 item: AK2.01 Remote shutdown panel: Plant-Specific RO 211 262001 AC Electrical Distribution A2.08 -Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Opening a disconnect under load Reason for Rejection:
All disconnects at Limerick require operator action to operate, therefore there are no situations in which a disconnect would be opened under load that would not involve operator error. Furthermore, there are no procedural actions for an RO to take to correct, control, or mitigate the consequences of a disconnect intentionally opened under load. Randomly reselected another item within 262001 A2 Item: A2.03 Loss of off-site power ES-301 Administrative Topics Outline Form ES-301-1 Facility:
LGS Examination Level: RO [8J Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Procedures/Plan SRO D Type Code* N'; N,R D,R,P M,S Date of Examination:
10104/10 Operating Test Number: ILT09-1 Describe activity to be performed G.2.1.3 Shift Turnover Checklist G .2.2.12 Review ST 04 7 -370-1, Pre Control Rod Withdrawal Check G.2.3.11 Gaseous Effluent Release Rate Determination (2008 RO A3) G.2.4.12 Activate Site Evacuation Alarm )/t' f1 J tL /lNPcx.J tJCf tltl£..l1/r NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; S 4 for SROs & RO retakes) (N)ew or (M)odified from bank (;?: 1) (P)revious 2 exams (S 1; randomly selected)
Administrative Topics Outline Form ES-301-1 Facility:
LGS Date of Examination:
Examination Level: RO DSRO l8] Operating Test Number: Administrative Topic Type Describe activity to be performed (see Note) Code* Conduct of Operations G.2.1.3 Shift Turnover CheckJ:bsL Conduct of Operations G.2.1.8 Coordinate Personnel Outside the Control Equipment Control G.2.2.12 Review ST-6-047-370-1, Pre Control Rod Withdrawal Check Radiation Control G.2.3.6 Review and Approve a Liquid Waste Discharge Permit, (2008 SRO Emergency D,R G.2.4.21 Make an E-plan Procedures/Plan (0131 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria: (C)ontrol room, (S)imulator, or (D)irect from bank 3 for ROs; 4 for SROs & (N)ew or (M)odified from bank (P)revious 2 exams 1; randomly Control Roomnn-Plant Systems Outline Form ES-301-2 Facilitv:
LGS Date of Examination:
10/04/10 Exam Level: RO SRO-I D SRO-U D Operating Test No.: lLT09-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function a. CRD Hydraulic System / Perform Reactor, Startup, Alternate A,D,L,S,P 1 Path (2008 ..'PM A) b. Manually place a RFP in Service, Alternate Path N,A,S 2 c. RCIC slow start, High Bearing oil temp (0002) A,D,S 4 d. Primary Containment N2 Makeup (0523) D,S 5 e. Transfer D13 from 101 to 201 (0519) A,D,S 6 1. Control Rod Exercise Test (0107) D,S 7 g. Camp Cooling Water I Align RECW for DW Cooling (2008 JPM G) A, D, EN, S, 8 P h. Manually Isolate the RE Enclosure (0022) D,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Bypassing and Removing the *A RPS and UPS Static Inverter from D,R 6 Service (0203) j. Alignment of Equipment or Operation of Shutdown Cooling (Fire E, M, L, R, 4 Safe Shutdown)
(0267) k. RO, SRO-I , SRO-U, Scram and MSIV closure from the AER A,D,E,L,R 7 (0261) All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Criteria for RO I SRO-II SRO-U (A)lternate path 4-6/4-6/2-3 (C)ontrol room (D)irecl frorn bank (E)rnergency or abnormal in-plant (EN)gineered safety feature -I -/ (control room system) (L)ow-Power
/ Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams 3/ 5 3/5 2 (randomly selected) (R)CA IS)imulator Control Roomlln-Plant Systems Outline Form ES-301-2 Facilitv:
LGS Date of Examination:
Exam Level: RO [J SRO-I 18l SRO-U 0 Operating Test No.: Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System I JPM Title Type Code* Safety Function a. CRD Hydraulic System 1 Perform Reactor, Startup, Alternate A,D,L,S,P Path (2008 ..IPM b. Manually place a RFP in Service, Alternate N,A,S 2 c. RCIC slow start, High Bearing oil temp A,D,S 4 d. Primary Containment N2 Makeup D,S 5 i e. TransferD13from 101 to 201 A,D,S 6 Comp Cooling Water 1 Align RECW for DW Cooling (2008 JPM G) A, D. EN, S, g. Manually Isolate the RE Enclosure D,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for i. Bypassing and Removing the *A RPS and UPS Static Inverter D,R 6 i Service (0203) I j. Alignment of Equipment or Operation of Shutdown Cooling (Fire E, M, L, R, Safe Shutdown) K Scram and MSIV closure from the AER (0261 A, D, L, R 7 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; alf 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Criteria for RO / SRO-I 1 SRO-U (A)lternate path 4-6 1 4-6 1 2-3 (C)ontrol room (D)irect from bank s;9/s;8/S;4 (E}mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature -I -I 2:1 (control room system) (L)ow-Power 1 Shutdown 2:1/2:1/2:1 (N)ew or (M)odified from bank including 1 (A) 2:2/2:2/2:1 (P)revious 2 exams s; 3 1 s; 3 / s; 2 (randomly selected) (R)CA 2:1/2:1/2:1 i (S)imulator ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facilitv:
LGS Date of Examination:
Exam Level: RO D SRO-I D SRO-U I8l Operating Test No.: Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System 1 JPM Title a. CRD Hydraulic System 1 Perform Reactor, Startup, Alternate Path (2008 JPM A) b. Manually place a RFP in Service, Alternate Path c. d. e. f. g. Comp Cooling Water 1 Align RECW for DW Cooling (2008 JPM G) In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for i. Bypassing and Removing the *A RPS and UPS Static Inverter from Service (0203) j. Alignment of Equipment or Operation of Shutdown Cooling (Fire Safe Shutdown)
(0267) K Type Code* Safety Function A,D, L,S, P 1 N,A,S 2 4 5 6 7 A, D, EN, S, 8 P 9 D,R 6 E, M, L, R 4 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power
/ Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (R)CA (S)imulator Criteria for RO / SRO-I / SRO-U 4-6 / 4-6 / 2-3 -/ -/ (control room system) 3 / 3 / 2 (randomly selected)
Appendix Required Operator Actions Form ES-D-2 Appendix Scenario Outline Form ES-D-1 Facility:
Limerick 1 & Scenario No.: 2 Op-Test No.: 1 Examiners:
____________
_ Operators:
Initial Conditions:
Reactor Power is 19%, Unit 2 100% power Turnover: Unit 1 is in OPCON 1, Reactor Power is approximately 19% GP-2, Normal Plant Startup is in progress and complete through step 3.4.25. Rod Pull Sheet sequence step #22, Group 5 is complete, Step #23 is in progress, with rod 10-11 at 00 and going to position 12 GP-2, App. 3, Startup of the Main Turbine is in progress and complete through step 3.3.7 All MCR annunciators in alarm are understood and expected due to present plant condition. "1 B" RFP is in AUTO through the 108B Both recirc pumps are operating at 28% speed "1 A" and "1 B" Condensate pumps are in service "1 B" and "1 C" Circ water pumps are in service RWCU is in service with "1 A" pump and both F/Ds "1 B" DW Chiller in service All ECCS are operable All available Deep Bed Demins are in service 4 Condensate Filter Demins are in service Inoperable/Out of Service Equipment and ETR 1 A EHC pump needs to be removed from service Planned Evolutions: Swap EHC pumps from 1A to 1 B per S31.6.C, Swapping operating EHC Pumps Continue with GP-2, and GP-2, App. 3 activities in support of plant startup. Regulatory Action Log has been reviewed and no equipment is known to be INOP which would affect continuing the startup.
Appendix D Required Operator Actions Form ES-D-2 ...Event No. 1 N/A 2 N/A 3 MPROO4B 4 MED282C 5 MCC074C 6 MRP029D MRP407C MSL197 7 MRD024 8 MEH108 * (N' e* N-BOP N-SRO R-RO TS,I-SRO I-RO C-BOP TS,C-SRO C-SRO C-RO C-BOP M C-RO C-BOP C-SRO C-RO Event Description
.... EHC pumps Pull control rods per GP-2 in support of plant startup. APRM Fails Inoperable Loss of Div III Loss of Condenser ATWS Rod Drive Control System Turbine Bypass valves ment, (C)omponent (M)ajor Appendix Scenario Outline Form ES-D-1 Facility:
Limerick 1 & Scenario No.: 4 Op-Test No .. 1
'1-'""QlUI Initial Unit 1 at 75% power. Unit 2 is at 100%
Inoperable/Out of Service Equipment and
- Outboard MSIV HV-41-1 F028A inadvertently closed due to an instrument air leak
- Repairs complete on HV-41-1 F028A instrument air Planned
- Open the MSIV HV-41-1 F028A per S41.3.B
- Raise power to 100% power per GP-5 Attachment
- 1. The RE is not in the control room. ...1 N/A 2 N/A 3 MRR504B 4 MCW484A MCW486B 5 VIM123A01 MRP445 MHP446a MHP446B 7 ,", 8 MFW244B 9 MAD141 D Event Type* N-SRO N-BOP R-RO N-SRO C-RO C-BOP TS,C-SRO C-BOP C-SRO C-BOP TS,C-SRO M I-RO C-RO C-BOP C-SRO Event Description Open Outboard MSIV HV-41-1 F028A Raise Power to 100% Reactor Recirc Pump 1 B Shaft Shear TECW pump A Trip, B TECW fails to auto start RWCU A pump vibration, and Low Flow HPCI Steam leak RPS Failure "A" RFP Steam Supply Valve Fails E SRV fails closed NRC Scenario #4 -2010 Limerick Operating Page 1 of 21 Appendix D Scenario Outline Form ES-D-1 Facility:
Limerick 1 & 2 Scenario No.: 5 Op-Test No.: Examiners:
Initial Reactor Power is 58%, Unit 2 100%
Inoperable/Out of Service Equipment and Planned
- Maintain 100% power
- Place HPCI in Full Flow Test, using the Manual Quick Start Method per S55.1.o for oil sampling.
- Completion of oil sampling is expected to take 15 minutes .
- HPCI will be shutdown when sampling is complete Event Malf. No. No. 1 N/A 2 MHP448B 3 MFH564A 4 MVI231A MDG420A 5 MCU575 MCU195A MCU195B MCU195C 6 MRR440A 7 MRH172C MCS183B 8 MRH171 B MRH528C Event Type* N-BOP N-SRO C-BOP TS, C-SRO C-SRO R-RO C-BOP TS, C-SRO C-RO M M C-BOP C-BOP C-SRO C-RO Start HPCI using Manual Quick Start Method ! HPCI Flow controller failure 2A Feedwater Heater Isolation Div 1 LOCA Signal. D11 fails to start Unisolable Steam leak will occur in RWCU Regen Heat Exchanger Room. LOCA via "1 A" "C" RHR pump and "B" Core Spay pump fail to auto Failure of B RHR pump and "Aft RHR drywell Spray valves * (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NRC Scenario # -2010 Limerick Operating Test Page 1 of 17