ML16085A255
| ML16085A255 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/22/2015 |
| From: | Isham P Exelon Generation Co |
| To: | Brian Fuller Operations Branch I |
| Shared Package | |
| ML15135A302 | List: |
| References | |
| TAC U01920 | |
| Download: ML16085A255 (17) | |
Text
ES-401 Written Examination Outline Form ES-401-1 Facility: Nine Mile Point Unit 2 Date of Exam: November 2015 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Tota Total 1 2 3 4 5 6 1 2 3 4
- I A2 G* 1. 1 4 4 3 3 3 3 20 4 3 7 Emergency 2 2 1 1 1 1 1 7 2 1 3 & Plant Tier Evolutions Totals 6 5 4 4 4 4 27 6 4 10 1 3 3 2 3 2 2 2 2 2 3 2 26 2 3 5 2. Plant 2 1 1 1 1 1 1 1 1 1 1 2 12 0 1 2 3 Systems Tier Totals 4 4 3 4 3 3 3 3 3 4 4 38 3 5 8 3. Generic Knowledge & Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 3 2 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRG revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding elimination of inappropriate KIA statements. 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution. 5. Absent a plant specific priority, only those KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively. 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories. 7.* The generic (G) Kl As in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIA's 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals(#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 1 OCFR55.43 ES-401 2 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) AA2.05 -Ability to determine and/or 295021 Loss of Shutdown x interpret the following as they apply to Cooling I 4 LOSS OF SHUTDOWN COOLING : Reactor vessel metal temoerature AA2.01 -Ability to determine and/or 295004 Partial or Total Loss of interpret the following as they apply to DC Pwr I 6 x PARTIAL OR COMPLETE LOSS OF D.C. POWER : Cause of partial or comolete loss of D.C. cower EA2.02 -Ability to determine and/or 295030 Low Suppression Pool x interpret the following as they apply to Water Level I 5 LOW SUPPRESSION POOL WATER LEVEL : Suooression oool temoerature 295019 Partial or Total Loss of 2.4.18 -Emergency Procedures I Plan: Inst. Air I 8 x Knowledge of the specific bases for EOPs. 2.2.42 -Equipment Control: Ability to 295018 Partial or Total Loss of x recognize system parameters that are ccw /8 entry-level conditions for Technical Specifications 2.4.8 -Emergency Procedures I Plan: 295038 High Off-site Release x Knowledge of how abnormal operating Rate I 9 procedures are used in conjunction with EOP's. EA2.05 -Ability to determine and/or 295025 High Reactor Pressure I x interpret the following as they apply to 3 HIGH REACTOR PRESSURE: Decay heat qeneration. AK1 .01 -Knowledge of the operational implications of the following concepts as 295018 Partial or Total Loss of x they apply to PARTIAL OR COMPLETE ccw /8 LOSS OF COMPONENT COOLING WATER: Effects on componenVsystem ooerations AK1 .02 -Knowledge of the operational implications of the following concepts as 700000 Generator Voltage and x they apply to GENERATOR VOLTAGE Electric Grid Disturbances AND ELECTRIC GRID DISTURBANCES and the following: Over-excitation. AK1 .03 -Knowledge of the operational 295006 SCRAM I 1 x implications of the following concepts as they apply to SCRAM : Reactivity control AK2.05 -Knowledge of the 295021 Loss of Shutdown interrelations between LOSS OF x SHUTDOWN COOLING and the Cooling I 4 following: Fuel pool cooling and cleanup system AK2.01 -Knowledge of the 600000 Plant Fire On-site I 8 x interrelations between PLANT FIRE ON SITE and the following: Sensors, detectors and valves EK2.06 -Knowledge of the 295026 Suppression Pool High interrelations between SUPPRESSION x POOL HIGH WATER TEMPERATURE Water Temp. I 5 and the following: Suppression pool level 295037 SCRAM Conditions x EK3.08 -Knowledge of the reasons for Present and Reactor Power the followinq resoonses as thev aoolv to Imp. Q# 3.5 76 3.6 77 3.9 78 4.0 79 4.6 80 4.5 81 3.6 82 3.5 39 3.3 40 3.7 41 2.7 42 2.6 43 3.5 44 3.6 45 ES-401 2 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Above APRM Downscale or SCRAM CONDITION PRESENT AND Unknown I 1 REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: ATWS circuitry: Plant-Specific EK3.03 -Knowledge of the reasons for 295038 High Off-site Release the following responses as they apply to x HIGH OFF-SITE RELEASE RATE: Rate I 9 Control room ventilation isolation: Plant-Specific EK3.02 -Knowledge of the reasons for 295025 High Reactor Pressure x the following responses as they apply to /3 HIGH REACTOR PRESSURE : Recirculation pump trip: Plant-Specific AA 1.02 -Ability to operate and/or 295016 Control Room monitor the following as they apply to Abandonment I 7 x CONTROL ROOM ABANDONMENT : Reactor/turbine pressure regulating svstem AA 1.04 -Ability to operate and/or 295005 Main Turbine x monitor the following as they apply to Generator Trip I 3 MAIN TURBINE GENERATOR TRIP: Main aenerator controls AA 1.01 -Ability to operate and/or 295023 Refueling Ace Cooling x monitor the following as they apply to Mode I 8 REFUELING ACCIDENTS : Secondary containment ventilation EA2.04 -Ability to determine and/or 295030 Low Suppression Pool interpret the following as they apply to x LOW SUPPRESSION POOL WATER Water Level I 5 LEVEL : Drywell/ suppression chamber differential pressure: Mark-1&11 AA2.06 -Ability to determine and/or 295001 Partial or Complete interpret the following as they apply to Loss of Forced Core Flow x PARTIAL OR COMPLETE LOSS OF Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION : Nuclear boiler instrumentation AA2.04 -Ability to determine and/or 295004 Partial or Total Loss of x interpret the following as they apply to DCPwr/6 PARTIAL OR COMPLETE LOSS OF D.C. POWER : System lineups 295028 High Drywell 2.4.1 -Emergency Procedures I Plan: Temperature I 5 x Knowledge of EOP entry conditions and immediate action steps. 295003 Partial or Complete 2.2.37 -Equipment Control: Ability to Loss of AC I 6 x determine operability and/or availability of safety related equipment. 2.4.9 -Emergency Procedures I Plan: 295024 High Drywell Pressure I Knowledge of low power I shutdown x implications in accident (e.g., loss of 5 coolant accident or loss of residual heat removal) mitiaation strateaies. EK1 .01 -Knowledge of the operational 295031 Reactor Low Water x implications of the following concepts as Level I 2 they apply to REACTOR LOW WATER LEVEL : Adequate core cooling AK2.04 -Knowledge of the 295019 Partial or Total Loss of interrelations between PARTIAL OR x COMPLETE LOSS OF INSTRUMENT Inst. Air I 8 AIR and the following: Reactor water cleanup Imp. Q# 3.7 46 3.9 47 2.9 48 2.7 49 3.3 50 3.5 51 3.2 52 3.2 53 4.6 54 3.6 55 3.8 56 4.6 57 2.8 58 ES-401 2 Nine Mile Point Unit 2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) KIA Category Totals: 4 4 3 3 3/4 3/3 Group Point Total: Form ES-401-1 Imp. Q# 20!7 ES-401 3 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) EA2.03 -Ability to determine and/or 295033 High Secondary interpret the following as they apply to Containment Area Radiation x HIGH SECONDARY CONTAINMENT Levels I 9 AREA RADIATION LEVELS : Cause of hiah area radiation 295036 Secondary 2.4.41 -Emergency Procedures I Plan: Containment High Sump/Area x Knowledge of the emergency action Water Level/ 5 level thresholds and classifications. EA2.02 -Ability to determine and I or 500000 High CTMT Hydrogen interpret the following as they apply to x HIGH PRIMARY CONTAINMENT Conc. / 5 HYDROGEN CONCENTRATIONS: Oxvaen monitorina system availabilitv AK1 .01 -Knowledge of the operational 295020 Inadvertent Cont. implications of the following concepts as Isolation I 5 & 7 x they apply to INADVERTENT CONTAINMENT ISOLATION: Loss of normal heat sink AK2.02 -Knowledge of the 295012 High Drywall x interrelations between HIGH DRYWELL Temperature I 5 TEMPERATURE and the following: Drvwell coolino AK3.01 -Knowledge of the reasons for 295010 High Drywall Pressure x the following responses as they apply to 15 HIGH DRYWELL PRESSURE : Drywall ventino AA 1.04 -Ability to operate and/or 295009 Low Reactor Water x monitor the following as they apply to Level I 2 LOW REACTOR WATER LEVEL: Reactor water cleanup EA2.03 -Ability to determine and/or 295029 High Suppression Pool x interpret the following as they apply to Water Level I 5 HIGH SUPPRESSION POOL WATER LEVEL : Drywall/containment water level 295035 Secondary 2.2.39 -Equipment Control: Knowledge of less than one hour technical Containment High Differential x specification action statements for Pressure I 5 systems. EK1 .0 -Knowledge of the operational 295034 Secondary implications of the following concepts as Containment Ventilation High x they apply to SECONDARY Radiation I 9 CONTAINMENT VENTILATION HIGH RADIATION: Radiation Releases KIA Category Totals: 2 1 1 1 1/2 1/1 Group Point Total: Imp. Q# 4.2 83 4.6 84 3.5 85 3.7 59 3.6 60 3.8 61 2.7 62 3.4 63 3.9 64 4.1 65 I 7/3 ES-401 System #I Name K K 1 2 203000 RHR/LPCI: Injection Mode 211000 SLC 217000 RCIC 262002 UPS (AC/DC) 300000 Instrument Air 300000 Instrument Air x 263000 DC Electrical x Distribution 215004 Source Range x Monitor 209001 LPCS x 218000 ADS Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K A A2 A A G 3 4 5 6 1 3 4 A2.14 -Ability to (a) predict the impacts of the following on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) ; and (b) x based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: lnitiatinq loqic failure A2.04 -Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM ; and (b) based on x those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadequate system flow 2.1.23 -Ability to perform x specific system and integrated plant procedures during all modes of plant operation. 2.2.40 -Ability to apply x Technical Specifications for a system. 2.1.20 -Conduct of Operations: x Ability to interpret and execute procedure steps. K1 .04 -Knowledge of the connections and I or cause effect relationships between INSTRUMENT AIR SYSTEM and the following: Cooling water to compressor K1 .04 -Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECTRICAL DISTRIBUTION and the followino: Ground detection K2.01 -Knowledge of electrical power supplies to the following: SAM channels/detectors K2.03 -Knowledge of electrical power supplies to the following: Initiation logic K3.01 -Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM x will have on following: Restoration of reactor water level after a break that does not depressurize the reactor when required Imp Q# 3.9 86 3.4 87 4.4 88 4.7 89 4.6 90 2.8 1 2.6 2 2.6 3 2.9 4 4.4 5 ES-401 K K System # I Name 1 2 203000 RHR/LPCI: Injection Mode 211000 SLC 209002 HPCS 215003 IRM 264000 EDGs 212000 RPS 217000 RCIC 259002 Reactor Water Level Control 400000 Component Cooling Water Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K A A2 A A G 3 4 5 6 1 3 4 K3.03 -Knowledge of the effect that a loss or malfunction of the x RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) will have on followino: Adeauate core coolino K4.05 -Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) x and/or interlocks which provide for the following: Dispersal of boron upon injection into the vessel K4.02 -Knowledge of HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) design x feature(s) and/or interlocks which provide for the following: Prevents over filling reactor vessel: Plant-Soecific. K5.01 -Knowledge of the operational implications of the x following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: Detector operation K5.06 -Knowledge of the operational implications of the x following concepts as they apply to EMERGENCY GENERATORS (DIESEUJET): Load sequencina K6.04 -Knowledge of the effect that a loss or malfunction of the x following will have on the REACTOR PROTECTION SYSTEM : D.C. electrical distribution K6.03 -Knowledge of the effect that a loss or malfunction of the x following will have on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC): Suppression cool water supply A 1.04 -Ability to predict and/or monitor changes in parameters associated with operating the x REACTOR WATER LEVEL CONTROL SYSTEM controls including: Reactor water level control controller indications A 1.01 -Ability to predict and I or monitor changes in parameters x associated with operating the CCWS controls including: CCW flow rate Imp Q# 4.6 6 3.4 7 3.4 8 2.6 9 3.4 10 2.8 11 3.5 12 3.6 13 2.8 14 ES-401 System # I Name K K 1 2 261000 SGTS 239002 SRVs 262001 AC Electrical Distribution 215005 APRM I LPRM 223002 PCIS/Nuclear Steam Supply Shutoff 262002 UPS (AC/DC) 205000 Shutdown Cooling 300000 Instrument Air Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K A A2 A A G 3 4 5 6 1 3 4 A2.11 -Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM ; and (b) based on x those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment pressure A2.03 -Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, x use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck open SRV A3.01 -Ability to monitor x automatic operations of the A.C. ELECTRICAL DISTRIBUTION includinq: Breaker triooinq A3.02 -Ability to monitor automatic operations of the x AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including: Full core display A4.04 -Ability to manually x operate and/or monitor in the control room: System indicating lights and alarms A4.01 -Ability to manually operate and/or monitor in the x control room: Transfer from alternative source to preferred source 2.4.21 -Emergency Procedures I Plan: Knowledge of the parameters and logic used to assess the status of safety x functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. 2.2.44 -Equipment Control: Ability to interpret control room indications to verify the status x and operation of a system, and understand how operator actions and directives affect plant and system conditions. Imp Q# 3.2 15 4.1 16 3.1 17 3.5 18 3.5 19 2.8 20 4.0 21 4.2 22 ES-401 System # I Name K K 1 2 215003 IRM x 223002 PCIS/Nuclear Steam Supply Shutoff 262001 AC Electrical Distribution 212000 RPS x KIA Category Totals: 3 3 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K A A2 A A G 3 4 5 6 1 3 4 K1 .06 -Knowledge of the physical connections and/or cause-effect relationships between INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and the following: APRM SCRAM signals: Plant-Specific K4.02 -Knowledge of PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM x SUPPLY SHUT-OFF design feature(s) and/or interlocks which provide for the following: Testability A4.03 -Ability to manually x operate and/or monitor in the control room: Local operation of breakers K2.01 -Knowledge of electrical power supplies to the following: RPS motor-aenerator sets 2 3 2 2 2 2/2 2 3 2/3 Group Point Total: Imp Q# 3.9 23 2.7 24 3.2 25 3.2 26 I 26/5 ES-401 System # I Name K K K 1 2 3 241000 Reactor/Turbine Pressure Regulator 259001 Reactor Feedwater 219000 RHR/LPCI: Torus/Pool Cooling Mode 239001 Main and Reheat Steam x 256000 Reactor Condensate x 286000 Fire Protection x 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Generator and Auxiliary Systems 214000 RPIS Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 2 K K K A A2 A A G 4 5 6 1 3 4 A2.07 -Ability to (a) predict the impacts of the following on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM ; and (b) based on x those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of Condenser Vacuum 2.4.30 -Emergency Procedures I Plan; Knowledge of events related to system operation I x status that must be reported to internal organizations or external agencies, such as the state, the NRC, or the transmission svstem operator. 2.4.47 -Emergency Procedures I Plan: Ability to diagnose and x recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. K1 .05 -Knowledge of the physical connections and/or cause-effect relationships between MAIN AND REHEAT STEAM SYSTEM and the following: Moisture separator reheaters: Plant-Specific K2.01 -Knowledge of electrical power supplies to the following: System pumps K3.03 -Knowledge of the effect that a loss or malfunction of the FIRE PROTECTION SYSTEM will have on following: Plant orotection K4.1 O -Knowledge of REACTOR/TURBINE PRESSURE REGULATING x SYSTEM design feature(s) and/or interlocks which provide for the following: Turbine Shell Warmina: EHC Onlv K5.02 -Knowledge of the operational implications of the following concepts as they apply x to MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS: Turbine operation and limitations K6.02 -Knowledge of the effect that a loss or malfunction of the x following will have on the ROD POSITION INFORMATION SYSTEM : Position indication orobe Imp. Q # 3.7 91 4.1 92 4.2 93 2.8 27 2.7 28 3.6 29 2.5 30 2.8 31 2.7 32 ES-401 System #I Name K K K 1 2 3 215001 Traversing In-core Probe 272000 Radiation Monitoring 233000 Fuel Pool Cooling/Cleanup 290001 Secondary CTMT 202001 Recirculation 201001 CRD Hydraulic KIA Category Totals: 1 1 1 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 2 K K K A A2 A A G 4 5 6 1 3 4 A 1.01 -Ability to predict and/or monitor changes in parameters x associated with operating the TRAVERSING IN-CORE PROBE controls including: Radiation levels: (Not-BWR1) A2.11 -Ability to (d) predict the impacts of the following on the RADIATION MONITORING SYSTEM ; and (b) based on those predictions, use x procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Leakage and/or breaks from contaminated systems to atmosphere or to other process svstems A3.02 -Ability to monitor automatic operations of the x FUEL POOL COOLING AND CLEAN-UP including: Pump trip(s) A4.12 -Ability to manually operate and/or monitor in the x control room: Reactor building differential pressure: Plant-Specific 2.4.31 -Emergency Procedures x I Plan: Knowledge of annunciator alarms, indications, or response procedures 2.1.23 -Conduct of Operations: Ability to perform specific x system and integrated plant procedures during all modes of plant operation. 1 1 1 1 1/1 1 1 212 Group Point Total: Imp. Q # 2.8 33 3.4 34 2.6 35 3.3 36 4.2 37 4.3 38 I 12/3 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Nine Mile Point Unit 2 Date: 11/30/15 RO SRO-Only Category KIA# Topic IR Q# IR Q# Ability to use procedures to determine the 2.1.43 effects on reactivity of plant changes, such as 4.3 94 RCS temperature, secondary plant, fuel depletion, etc. 2.1.25 Ability to interpret reference materials, such 4.2 98 as graphs, curves, tables, etc. 1. Conduct of Operations 2.1.13 Knowledge of facility requirements for 2.5 66 controllinq vital I controlled access. 2.1.28 Knowledge of the purpose and function of 4.1 67 major system components and controls. Subtotal 2 2 2.2.38 Knowledge of conditions and limitations in 4.5 95 the facility license. 2.2.23 Ability to track Technical Specification 4.6 99 limitinq conditions for operations. 2. Ability to manipulate the console controls as Equipment 2.2.2 required to operate the facility between 4.6 68 Control shutdown and designated power levels. 2.2.22 (Equipment Control: Knowledge of limiting 4.0 69 conditions for operations and safety limits. 2.2.12 Knowledge of surveillance procedures. 3.7 74 Subtotal 3 2 Ability to use radiation monitoring systems, 2.3.5 such as fixed radiation monitors and alarms, 2.9 96 portable survey instruments, personell monitorinq equipment, etc. 3. Radiation Knowledge of Radialogical Safety Control Procedures pertaining to licensed operator 2.3.13 duties, such as response to radiation monitor 3.4 70 alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc. 2.3.4 Knowledge of radiation exposure limits under 3.2 71 normal or emergency conditions.
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Subtotal 2 1 Ability to diagnose and recognize trends in 2.4.47 an accurate and timely manner utilizing the 4.2 97 aooropriate control room reference material. 2.4.28 Knowledge of procedures relating to a 4.1 100 security event. Knowledge of EOP implementation hierarchy 4. 2.4.16 and coordination with other support 3.5 72 Emergency procedures or guidelines such as, operating procedures, AOP's and SAMG's. Procedures I Knowledge of procedures relating to a Plan 2.4.28 security event. 3.2 73 Knowledge of the parameters and logic used to assess the status of safety functions, such 2.4.21 as reactivity control, core cooling and heat 4.0 75 removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. Subtotal 3 2 Tier 3 Point Total 10 7 ES-401 Record of Rejected Kl A's Form ES-401-4 Tier I Group Randomly Selected KIA Reason for Rejection Question 30 241000 An operationally relevant question at the appropriate Reactor/Turbine Pressure license level could not be written for the randomly Regulator sampled KA. K4.16 Knowledge of 212 REACTOR/TURBINE Randomly re-sampled KA 241000 K4.10 -Knowledge PRESSURE REGULATING of REACTOR/TURBINE PRESSURE REGULATING SYSTEM design feature(s) SYSTEM design feature(s) and/or interlocks which and/or interlocks which provide for the following: Turbine Shell Warming: EHC provide for the following: Only Reactor Cooldown Question 36 209001 An operationally relevant question at the appropriate Secondary Containment license level could not be written for the randomly sampled KA. 212 A4.12 -Ability to manually operate and/or monitor in the control room: Surveillance Randomly re-sampled KA 209001 A4.01 -Ability to testing: Plant-Specific manually operate and/or monitor in the control room: Reactor building differential pressure: Plant-Specific Question 6 218000 Question concept overlaps with question #5 concept for Automatic Depressurization the randomly sampled KA. System K3.03 Knowledge of the 2/1 effect that a loss or malfunction of the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) Randomly re-sampled KA 203000 K3.04 -Knowledge will have on following: of the effect that a loss or malfunction of the RHR/LPCI: Automatic depressurization INJECTION MODE (PLANT SPECIFIC) will have on loqic following: Adequate core cooling Question 22 300000 An operationally relevant question at the appropriate license level could not be written for the randomly Instrument Air sampled KA. 2/1 Randomly re-sampled KA 300000 2.2.44 -Equipment 2.2.40 -Equipment Control: Control: Ability to interpret control room indications to verify the status and operation of a system, and Ability to apply technical understand how operator actions and directives affect specifications for a system plant and system conditions. Question 31 201004 System has been retired, unable to write a question for RSCS the randomly sampled KA. K5.03 -Knowledge of the 212 operational implications of the following concepts as they apply to ROD Randomly re-sampled KA 203000 K5.02 -Knowledge of SEQUENCE Group notch the operational implications of the following concepts as control limits and rod they apply to RHR/LPCI: INJECTION MODE (PLANT density: BWR-4,5 SPECIFIC): Core cooling methods ES-401 Record of Rejected K/A's Form ES-401-4 Question 37 202001 An operationally relevant question at the appropriate Recirculation license level could not be written for the randomly sampled KA. 2.4.41 -Emergency 2/2 Procedures I Plan: Knowledge of the emergency action level Randomly re-sampled KA 202001 2.4.31 -Emergency thresholds and Procedures I Plan: Knowledge of annunciator alarms, classifications indications, or response procedures Question 54 295028 An operationally relevant question at the appropriate High Drywell Temperature/5 license level could not be written for the randomly sampled KA. 2.4.49 -Emergency 1 /1 Procedures I Plan: Ability to perform without reference to procedures those actions that require immediate Randomly re-sampled KA 295028 2.4.1 -Emergency operation of system Procedures I Plan: Knowledge of EOP entry conditions components and controls. and immediate action steps Question 55 295003 NMP2 is a standalone unit. Partial or Complete Loss of AC/6 1/1 2.2.3 -Equipment Control: (multi-unit license) Knowledge of the design, Randomly re-sampled KA 295003 2.2.37 -Equipment procedural, and operational Control: Ability to determine operability and/or differences between units availability of safety related equipment. Question 65 295034 An operationally relevant question at the appropriate Secondary Containment license level could not be written for the randomly Ventilation High Radiation I sampled KA. 9 EK1 .01-Knowledge of the 1/2 operational implications of the following concepts as they apply to SECONDARY CONT Al NM ENT Randomly re-sampled KA 295034 EK1 .02 -Knowledge VENTILATION HIGH of the operational implications of the following concepts RADIATION: Personnel as they apply to SECONDARY CONT Al NM ENT protection VENTILATION HIGH RADIATION: Radiation Releases. Question 69 2.2.4 NMP2 is a standalone unit. Suppression Pool High Water Temp. I 5 3 2.2.4 -Equipment Control: (multi-unit license) Knowledge of the design, Randomly re-sampled KA 295003 2.2.22 -Equipment procedural, and operational Control: Knowledge of limiting conditions for operations differences between units and safety limits. Question 31 201004 RSCS Randomly sampled system does not exist at this facility 2/2 K5.03 -Knowledge of the operational implications of the following concepts as ES-401 Record of Rejected K/A's Form ES-401-4 they apply to ROD Randomly re-sampled KA 245000 K5.02 -Knowledge SEQUENCE Group notch of the operational implications of the following control limits and rod concepts as they apply to MAIN TURBINE density: BWR-4,5 GENERATOR AND AUXILIARY SYSTEMS: Turbine operation and limitations Question 80 295018 An operationally relevant question at the appropriate Partial or Total Loss of CCW license level could not be written for the randomly /8 sampled KA. Knowledge of less than one hour technical specification action statements is RO level of knowledge 1 /1 2.2.39 -Equipment Control: per NUREG1021 ES401, attachment 2. Knowledge of less than one hour technical specification Randomly re-sampled KA 295018 2.2.42-Equipment action statements for Control: Ability to recognize system parameters that are systems. entry-level conditions for Technical Specifications An operationally relevant question at the appropriate Question 81 295038 license level could not be written for the randomly High Off-site Release Rate I sampled KA. 9 1/1 2.4.20 -Emergency Procedures I Plan: Knowledge of operational implications of EOP Randomly re-sampled KA 295038 2.4.8 -Emergency warnings, cautions, and Procedures I Plan: Knowledge of how abnormal notes. operating procedures are used in conjunction with EOP's. Question 88 217000 An operationally relevant question at the appropriate license level could not be written for the randomly RCIC sampled KA. The question can be answered solely by knowing "systems knowledge", i.e., how the system 2/1 works, flowpath, logic, component location per 2.1.27 -Conduct of NUREG1021 ES401, attachment 2. Operations: Knowledge of Randomly re-sampled KA 217000 2.1 .23 -Ability to system purpose and I or function. perform specific system and integrated plant procedures during all modes of plant operation. Question 90 300000 An operationally relevant question at the appropriate Instrument Air license level could not be written for the randomly sampled KA. The question can be answered solely by knowing "systems knowledge", i.e., how the system 2/1 works, flowpath, logic, component location per NUREG1021 ES401, attachment 2. 2.1 .30 -Conduct of Randomly re-sampled KA 300000 2.1.20 -Conduct of Operations: Ability to locate and operate components, Operations: Ability to interpret and execute procedure includinq local controls. steps. Question 98 2.1.44 An operationally relevant question at the appropriate license level could not be written for the randomly 2.1 .44 -Conduct of sampled KA. 3 Operations: Knowledge of RO duties in the control room during fuel handling such as responding to alarms from the fuel ES-401 Record of Rejected Kl A's Form ES-401-4 handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting Randomly re-sampled KA 2.1 .25 -Ability to interpret instrumentation. reference materials, such as Qraphs, curves, tables, etc. Question 89 262002 An operationally relevant question at the appropriate UPS (AC/DC) license level could not be written for the randomly sampled KA. There is not enough of a direct tie between the UPS system and the Emergency Procedures I Plan. 1/2 2.4.46 -Emergency Procedures I Plan: Ability to verify that the alarms are consistent with the plant Randomly re-sampled KA 262002 2.2.40 -Ability to conditions. apply Technical Specifications for a system. Question 91 241000 Reactor/Turbine Pressure Regulator An operationally relevant question at the appropriate A2.23 -Ability to (a) predict license level could not be written for the randomly the impacts of the following sampled KA. Resampled by Chief Examiner direction. on the REACTOR/TURBINE Randomly re-sampled KA 241000 A2.07 -Ability to (a) PRESSURE REGULATING 2/2 SYSTEM; and (b) based on predict the impacts of the following on the REACTOR/TURBINE PRESSURE REGULATING those predictions, use SYSTEM ; and (b) based on those predictions, use procedures to correct, procedures to correct, control, or mitigate the control, or mitigate the consequences of those abnormal conditions or consequences of those operations: Loss of Condenser Vacuum abnormal conditions or operations: Turbine high eccentricity ES-401 Written Examination Outline Form ES-401-1 Facility: Nine Mile Point Unit 2 Date of Exam: November 2015 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Tota Total 1 2 3 4 5 6 1 2 3 4
- I A2 G* 1. 1 4 4 3 3 3 3 20 4 3 7 Emergency 2 2 1 1 1 1 1 7 2 1 3 & Plant Tier Evolutions Totals 6 5 4 4 4 4 27 6 4 10 1 3 3 2 3 2 2 2 2 2 3 2 26 2 3 5 2. Plant 2 1 1 1 1 1 1 1 1 1 1 2 12 0 1 2 3 Systems Tier Totals 4 4 3 4 3 3 3 3 3 4 4 38 3 5 8 3. Generic Knowledge & Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 3 2 3 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two). 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRG revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding elimination of inappropriate KIA statements. 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution. 5. Absent a plant specific priority, only those KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively. 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories. 7.* The generic (G) Kl As in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIA's 8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals(#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams. 9. For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 1 OCFR55.43 ES-401 2 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) AA2.05 -Ability to determine and/or 295021 Loss of Shutdown x interpret the following as they apply to Cooling I 4 LOSS OF SHUTDOWN COOLING : Reactor vessel metal temoerature AA2.01 -Ability to determine and/or 295004 Partial or Total Loss of interpret the following as they apply to DC Pwr I 6 x PARTIAL OR COMPLETE LOSS OF D.C. POWER : Cause of partial or comolete loss of D.C. cower EA2.02 -Ability to determine and/or 295030 Low Suppression Pool x interpret the following as they apply to Water Level I 5 LOW SUPPRESSION POOL WATER LEVEL : Suooression oool temoerature 295019 Partial or Total Loss of 2.4.18 -Emergency Procedures I Plan: Inst. Air I 8 x Knowledge of the specific bases for EOPs. 2.2.42 -Equipment Control: Ability to 295018 Partial or Total Loss of x recognize system parameters that are ccw /8 entry-level conditions for Technical Specifications 2.4.8 -Emergency Procedures I Plan: 295038 High Off-site Release x Knowledge of how abnormal operating Rate I 9 procedures are used in conjunction with EOP's. EA2.05 -Ability to determine and/or 295025 High Reactor Pressure I x interpret the following as they apply to 3 HIGH REACTOR PRESSURE: Decay heat qeneration. AK1 .01 -Knowledge of the operational implications of the following concepts as 295018 Partial or Total Loss of x they apply to PARTIAL OR COMPLETE ccw /8 LOSS OF COMPONENT COOLING WATER: Effects on componenVsystem ooerations AK1 .02 -Knowledge of the operational implications of the following concepts as 700000 Generator Voltage and x they apply to GENERATOR VOLTAGE Electric Grid Disturbances AND ELECTRIC GRID DISTURBANCES and the following: Over-excitation. AK1 .03 -Knowledge of the operational 295006 SCRAM I 1 x implications of the following concepts as they apply to SCRAM : Reactivity control AK2.05 -Knowledge of the 295021 Loss of Shutdown interrelations between LOSS OF x SHUTDOWN COOLING and the Cooling I 4 following: Fuel pool cooling and cleanup system AK2.01 -Knowledge of the 600000 Plant Fire On-site I 8 x interrelations between PLANT FIRE ON SITE and the following: Sensors, detectors and valves EK2.06 -Knowledge of the 295026 Suppression Pool High interrelations between SUPPRESSION x POOL HIGH WATER TEMPERATURE Water Temp. I 5 and the following: Suppression pool level 295037 SCRAM Conditions x EK3.08 -Knowledge of the reasons for Present and Reactor Power the followinq resoonses as thev aoolv to Imp. Q# 3.5 76 3.6 77 3.9 78 4.0 79 4.6 80 4.5 81 3.6 82 3.5 39 3.3 40 3.7 41 2.7 42 2.6 43 3.5 44 3.6 45 ES-401 2 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Above APRM Downscale or SCRAM CONDITION PRESENT AND Unknown I 1 REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: ATWS circuitry: Plant-Specific EK3.03 -Knowledge of the reasons for 295038 High Off-site Release the following responses as they apply to x HIGH OFF-SITE RELEASE RATE: Rate I 9 Control room ventilation isolation: Plant-Specific EK3.02 -Knowledge of the reasons for 295025 High Reactor Pressure x the following responses as they apply to /3 HIGH REACTOR PRESSURE : Recirculation pump trip: Plant-Specific AA 1.02 -Ability to operate and/or 295016 Control Room monitor the following as they apply to Abandonment I 7 x CONTROL ROOM ABANDONMENT : Reactor/turbine pressure regulating svstem AA 1.04 -Ability to operate and/or 295005 Main Turbine x monitor the following as they apply to Generator Trip I 3 MAIN TURBINE GENERATOR TRIP: Main aenerator controls AA 1.01 -Ability to operate and/or 295023 Refueling Ace Cooling x monitor the following as they apply to Mode I 8 REFUELING ACCIDENTS : Secondary containment ventilation EA2.04 -Ability to determine and/or 295030 Low Suppression Pool interpret the following as they apply to x LOW SUPPRESSION POOL WATER Water Level I 5 LEVEL : Drywell/ suppression chamber differential pressure: Mark-1&11 AA2.06 -Ability to determine and/or 295001 Partial or Complete interpret the following as they apply to Loss of Forced Core Flow x PARTIAL OR COMPLETE LOSS OF Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION : Nuclear boiler instrumentation AA2.04 -Ability to determine and/or 295004 Partial or Total Loss of x interpret the following as they apply to DCPwr/6 PARTIAL OR COMPLETE LOSS OF D.C. POWER : System lineups 295028 High Drywell 2.4.1 -Emergency Procedures I Plan: Temperature I 5 x Knowledge of EOP entry conditions and immediate action steps. 295003 Partial or Complete 2.2.37 -Equipment Control: Ability to Loss of AC I 6 x determine operability and/or availability of safety related equipment. 2.4.9 -Emergency Procedures I Plan: 295024 High Drywell Pressure I Knowledge of low power I shutdown x implications in accident (e.g., loss of 5 coolant accident or loss of residual heat removal) mitiaation strateaies. EK1 .01 -Knowledge of the operational 295031 Reactor Low Water x implications of the following concepts as Level I 2 they apply to REACTOR LOW WATER LEVEL : Adequate core cooling AK2.04 -Knowledge of the 295019 Partial or Total Loss of interrelations between PARTIAL OR x COMPLETE LOSS OF INSTRUMENT Inst. Air I 8 AIR and the following: Reactor water cleanup Imp. Q# 3.7 46 3.9 47 2.9 48 2.7 49 3.3 50 3.5 51 3.2 52 3.2 53 4.6 54 3.6 55 3.8 56 4.6 57 2.8 58 ES-401 2 Nine Mile Point Unit 2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) KIA Category Totals: 4 4 3 3 3/4 3/3 Group Point Total: Form ES-401-1 Imp. Q# 20!7 ES-401 3 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) EA2.03 -Ability to determine and/or 295033 High Secondary interpret the following as they apply to Containment Area Radiation x HIGH SECONDARY CONTAINMENT Levels I 9 AREA RADIATION LEVELS : Cause of hiah area radiation 295036 Secondary 2.4.41 -Emergency Procedures I Plan: Containment High Sump/Area x Knowledge of the emergency action Water Level/ 5 level thresholds and classifications. EA2.02 -Ability to determine and I or 500000 High CTMT Hydrogen interpret the following as they apply to x HIGH PRIMARY CONTAINMENT Conc. / 5 HYDROGEN CONCENTRATIONS: Oxvaen monitorina system availabilitv AK1 .01 -Knowledge of the operational 295020 Inadvertent Cont. implications of the following concepts as Isolation I 5 & 7 x they apply to INADVERTENT CONTAINMENT ISOLATION: Loss of normal heat sink AK2.02 -Knowledge of the 295012 High Drywall x interrelations between HIGH DRYWELL Temperature I 5 TEMPERATURE and the following: Drvwell coolino AK3.01 -Knowledge of the reasons for 295010 High Drywall Pressure x the following responses as they apply to 15 HIGH DRYWELL PRESSURE : Drywall ventino AA 1.04 -Ability to operate and/or 295009 Low Reactor Water x monitor the following as they apply to Level I 2 LOW REACTOR WATER LEVEL: Reactor water cleanup EA2.03 -Ability to determine and/or 295029 High Suppression Pool x interpret the following as they apply to Water Level I 5 HIGH SUPPRESSION POOL WATER LEVEL : Drywall/containment water level 295035 Secondary 2.2.39 -Equipment Control: Knowledge of less than one hour technical Containment High Differential x specification action statements for Pressure I 5 systems. EK1 .0 -Knowledge of the operational 295034 Secondary implications of the following concepts as Containment Ventilation High x they apply to SECONDARY Radiation I 9 CONTAINMENT VENTILATION HIGH RADIATION: Radiation Releases KIA Category Totals: 2 1 1 1 1/2 1/1 Group Point Total: Imp. Q# 4.2 83 4.6 84 3.5 85 3.7 59 3.6 60 3.8 61 2.7 62 3.4 63 3.9 64 4.1 65 I 7/3 ES-401 System #I Name K K 1 2 203000 RHR/LPCI: Injection Mode 211000 SLC 217000 RCIC 262002 UPS (AC/DC) 300000 Instrument Air 300000 Instrument Air x 263000 DC Electrical x Distribution 215004 Source Range x Monitor 209001 LPCS x 218000 ADS Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K A A2 A A G 3 4 5 6 1 3 4 A2.14 -Ability to (a) predict the impacts of the following on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) ; and (b) x based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: lnitiatinq loqic failure A2.04 -Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM ; and (b) based on x those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadequate system flow 2.1.23 -Ability to perform x specific system and integrated plant procedures during all modes of plant operation. 2.2.40 -Ability to apply x Technical Specifications for a system. 2.1.20 -Conduct of Operations: x Ability to interpret and execute procedure steps. K1 .04 -Knowledge of the connections and I or cause effect relationships between INSTRUMENT AIR SYSTEM and the following: Cooling water to compressor K1 .04 -Knowledge of the physical connections and/or cause-effect relationships between D.C. ELECTRICAL DISTRIBUTION and the followino: Ground detection K2.01 -Knowledge of electrical power supplies to the following: SAM channels/detectors K2.03 -Knowledge of electrical power supplies to the following: Initiation logic K3.01 -Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM x will have on following: Restoration of reactor water level after a break that does not depressurize the reactor when required Imp Q# 3.9 86 3.4 87 4.4 88 4.7 89 4.6 90 2.8 1 2.6 2 2.6 3 2.9 4 4.4 5 ES-401 K K System # I Name 1 2 203000 RHR/LPCI: Injection Mode 211000 SLC 209002 HPCS 215003 IRM 264000 EDGs 212000 RPS 217000 RCIC 259002 Reactor Water Level Control 400000 Component Cooling Water Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K A A2 A A G 3 4 5 6 1 3 4 K3.03 -Knowledge of the effect that a loss or malfunction of the x RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) will have on followino: Adeauate core coolino K4.05 -Knowledge of STANDBY LIQUID CONTROL SYSTEM design feature(s) x and/or interlocks which provide for the following: Dispersal of boron upon injection into the vessel K4.02 -Knowledge of HIGH PRESSURE CORE SPRAY SYSTEM (HPCS) design x feature(s) and/or interlocks which provide for the following: Prevents over filling reactor vessel: Plant-Soecific. K5.01 -Knowledge of the operational implications of the x following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: Detector operation K5.06 -Knowledge of the operational implications of the x following concepts as they apply to EMERGENCY GENERATORS (DIESEUJET): Load sequencina K6.04 -Knowledge of the effect that a loss or malfunction of the x following will have on the REACTOR PROTECTION SYSTEM : D.C. electrical distribution K6.03 -Knowledge of the effect that a loss or malfunction of the x following will have on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC): Suppression cool water supply A 1.04 -Ability to predict and/or monitor changes in parameters associated with operating the x REACTOR WATER LEVEL CONTROL SYSTEM controls including: Reactor water level control controller indications A 1.01 -Ability to predict and I or monitor changes in parameters x associated with operating the CCWS controls including: CCW flow rate Imp Q# 4.6 6 3.4 7 3.4 8 2.6 9 3.4 10 2.8 11 3.5 12 3.6 13 2.8 14 ES-401 System # I Name K K 1 2 261000 SGTS 239002 SRVs 262001 AC Electrical Distribution 215005 APRM I LPRM 223002 PCIS/Nuclear Steam Supply Shutoff 262002 UPS (AC/DC) 205000 Shutdown Cooling 300000 Instrument Air Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K A A2 A A G 3 4 5 6 1 3 4 A2.11 -Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM ; and (b) based on x those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment pressure A2.03 -Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, x use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck open SRV A3.01 -Ability to monitor x automatic operations of the A.C. ELECTRICAL DISTRIBUTION includinq: Breaker triooinq A3.02 -Ability to monitor automatic operations of the x AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including: Full core display A4.04 -Ability to manually x operate and/or monitor in the control room: System indicating lights and alarms A4.01 -Ability to manually operate and/or monitor in the x control room: Transfer from alternative source to preferred source 2.4.21 -Emergency Procedures I Plan: Knowledge of the parameters and logic used to assess the status of safety x functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. 2.2.44 -Equipment Control: Ability to interpret control room indications to verify the status x and operation of a system, and understand how operator actions and directives affect plant and system conditions. Imp Q# 3.2 15 4.1 16 3.1 17 3.5 18 3.5 19 2.8 20 4.0 21 4.2 22 ES-401 System # I Name K K 1 2 215003 IRM x 223002 PCIS/Nuclear Steam Supply Shutoff 262001 AC Electrical Distribution 212000 RPS x KIA Category Totals: 3 3 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K A A2 A A G 3 4 5 6 1 3 4 K1 .06 -Knowledge of the physical connections and/or cause-effect relationships between INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and the following: APRM SCRAM signals: Plant-Specific K4.02 -Knowledge of PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM x SUPPLY SHUT-OFF design feature(s) and/or interlocks which provide for the following: Testability A4.03 -Ability to manually x operate and/or monitor in the control room: Local operation of breakers K2.01 -Knowledge of electrical power supplies to the following: RPS motor-aenerator sets 2 3 2 2 2 2/2 2 3 2/3 Group Point Total: Imp Q# 3.9 23 2.7 24 3.2 25 3.2 26 I 26/5 ES-401 System # I Name K K K 1 2 3 241000 Reactor/Turbine Pressure Regulator 259001 Reactor Feedwater 219000 RHR/LPCI: Torus/Pool Cooling Mode 239001 Main and Reheat Steam x 256000 Reactor Condensate x 286000 Fire Protection x 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Generator and Auxiliary Systems 214000 RPIS Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 2 K K K A A2 A A G 4 5 6 1 3 4 A2.07 -Ability to (a) predict the impacts of the following on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM ; and (b) based on x those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of Condenser Vacuum 2.4.30 -Emergency Procedures I Plan; Knowledge of events related to system operation I x status that must be reported to internal organizations or external agencies, such as the state, the NRC, or the transmission svstem operator. 2.4.47 -Emergency Procedures I Plan: Ability to diagnose and x recognize trends in an accurate and timely manner utilizing the appropriate control room reference material. K1 .05 -Knowledge of the physical connections and/or cause-effect relationships between MAIN AND REHEAT STEAM SYSTEM and the following: Moisture separator reheaters: Plant-Specific K2.01 -Knowledge of electrical power supplies to the following: System pumps K3.03 -Knowledge of the effect that a loss or malfunction of the FIRE PROTECTION SYSTEM will have on following: Plant orotection K4.1 O -Knowledge of REACTOR/TURBINE PRESSURE REGULATING x SYSTEM design feature(s) and/or interlocks which provide for the following: Turbine Shell Warmina: EHC Onlv K5.02 -Knowledge of the operational implications of the following concepts as they apply x to MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS: Turbine operation and limitations K6.02 -Knowledge of the effect that a loss or malfunction of the x following will have on the ROD POSITION INFORMATION SYSTEM : Position indication orobe Imp. Q # 3.7 91 4.1 92 4.2 93 2.8 27 2.7 28 3.6 29 2.5 30 2.8 31 2.7 32 ES-401 System #I Name K K K 1 2 3 215001 Traversing In-core Probe 272000 Radiation Monitoring 233000 Fuel Pool Cooling/Cleanup 290001 Secondary CTMT 202001 Recirculation 201001 CRD Hydraulic KIA Category Totals: 1 1 1 Form ES-401-1 Nine Mile Point Unit 2 Written Examination Outline Plant Systems -Tier 2 Group 2 K K K A A2 A A G 4 5 6 1 3 4 A 1.01 -Ability to predict and/or monitor changes in parameters x associated with operating the TRAVERSING IN-CORE PROBE controls including: Radiation levels: (Not-BWR1) A2.11 -Ability to (d) predict the impacts of the following on the RADIATION MONITORING SYSTEM ; and (b) based on those predictions, use x procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Leakage and/or breaks from contaminated systems to atmosphere or to other process svstems A3.02 -Ability to monitor automatic operations of the x FUEL POOL COOLING AND CLEAN-UP including: Pump trip(s) A4.12 -Ability to manually operate and/or monitor in the x control room: Reactor building differential pressure: Plant-Specific 2.4.31 -Emergency Procedures x I Plan: Knowledge of annunciator alarms, indications, or response procedures 2.1.23 -Conduct of Operations: Ability to perform specific x system and integrated plant procedures during all modes of plant operation. 1 1 1 1 1/1 1 1 212 Group Point Total: Imp. Q # 2.8 33 3.4 34 2.6 35 3.3 36 4.2 37 4.3 38 I 12/3 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Nine Mile Point Unit 2 Date: 11/30/15 RO SRO-Only Category KIA# Topic IR Q# IR Q# Ability to use procedures to determine the 2.1.43 effects on reactivity of plant changes, such as 4.3 94 RCS temperature, secondary plant, fuel depletion, etc. 2.1.25 Ability to interpret reference materials, such 4.2 98 as graphs, curves, tables, etc. 1. Conduct of Operations 2.1.13 Knowledge of facility requirements for 2.5 66 controllinq vital I controlled access. 2.1.28 Knowledge of the purpose and function of 4.1 67 major system components and controls. Subtotal 2 2 2.2.38 Knowledge of conditions and limitations in 4.5 95 the facility license. 2.2.23 Ability to track Technical Specification 4.6 99 limitinq conditions for operations. 2. Ability to manipulate the console controls as Equipment 2.2.2 required to operate the facility between 4.6 68 Control shutdown and designated power levels. 2.2.22 (Equipment Control: Knowledge of limiting 4.0 69 conditions for operations and safety limits. 2.2.12 Knowledge of surveillance procedures. 3.7 74 Subtotal 3 2 Ability to use radiation monitoring systems, 2.3.5 such as fixed radiation monitors and alarms, 2.9 96 portable survey instruments, personell monitorinq equipment, etc. 3. Radiation Knowledge of Radialogical Safety Control Procedures pertaining to licensed operator 2.3.13 duties, such as response to radiation monitor 3.4 70 alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc. 2.3.4 Knowledge of radiation exposure limits under 3.2 71 normal or emergency conditions.
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Subtotal 2 1 Ability to diagnose and recognize trends in 2.4.47 an accurate and timely manner utilizing the 4.2 97 aooropriate control room reference material. 2.4.28 Knowledge of procedures relating to a 4.1 100 security event. Knowledge of EOP implementation hierarchy 4. 2.4.16 and coordination with other support 3.5 72 Emergency procedures or guidelines such as, operating procedures, AOP's and SAMG's. Procedures I Knowledge of procedures relating to a Plan 2.4.28 security event. 3.2 73 Knowledge of the parameters and logic used to assess the status of safety functions, such 2.4.21 as reactivity control, core cooling and heat 4.0 75 removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. Subtotal 3 2 Tier 3 Point Total 10 7 ES-401 Record of Rejected Kl A's Form ES-401-4 Tier I Group Randomly Selected KIA Reason for Rejection Question 30 241000 An operationally relevant question at the appropriate Reactor/Turbine Pressure license level could not be written for the randomly Regulator sampled KA. K4.16 Knowledge of 212 REACTOR/TURBINE Randomly re-sampled KA 241000 K4.10 -Knowledge PRESSURE REGULATING of REACTOR/TURBINE PRESSURE REGULATING SYSTEM design feature(s) SYSTEM design feature(s) and/or interlocks which and/or interlocks which provide for the following: Turbine Shell Warming: EHC provide for the following: Only Reactor Cooldown Question 36 209001 An operationally relevant question at the appropriate Secondary Containment license level could not be written for the randomly sampled KA. 212 A4.12 -Ability to manually operate and/or monitor in the control room: Surveillance Randomly re-sampled KA 209001 A4.01 -Ability to testing: Plant-Specific manually operate and/or monitor in the control room: Reactor building differential pressure: Plant-Specific Question 6 218000 Question concept overlaps with question #5 concept for Automatic Depressurization the randomly sampled KA. System K3.03 Knowledge of the 2/1 effect that a loss or malfunction of the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) Randomly re-sampled KA 203000 K3.04 -Knowledge will have on following: of the effect that a loss or malfunction of the RHR/LPCI: Automatic depressurization INJECTION MODE (PLANT SPECIFIC) will have on loqic following: Adequate core cooling Question 22 300000 An operationally relevant question at the appropriate license level could not be written for the randomly Instrument Air sampled KA. 2/1 Randomly re-sampled KA 300000 2.2.44 -Equipment 2.2.40 -Equipment Control: Control: Ability to interpret control room indications to verify the status and operation of a system, and Ability to apply technical understand how operator actions and directives affect specifications for a system plant and system conditions. Question 31 201004 System has been retired, unable to write a question for RSCS the randomly sampled KA. K5.03 -Knowledge of the 212 operational implications of the following concepts as they apply to ROD Randomly re-sampled KA 203000 K5.02 -Knowledge of SEQUENCE Group notch the operational implications of the following concepts as control limits and rod they apply to RHR/LPCI: INJECTION MODE (PLANT density: BWR-4,5 SPECIFIC): Core cooling methods ES-401 Record of Rejected K/A's Form ES-401-4 Question 37 202001 An operationally relevant question at the appropriate Recirculation license level could not be written for the randomly sampled KA. 2.4.41 -Emergency 2/2 Procedures I Plan: Knowledge of the emergency action level Randomly re-sampled KA 202001 2.4.31 -Emergency thresholds and Procedures I Plan: Knowledge of annunciator alarms, classifications indications, or response procedures Question 54 295028 An operationally relevant question at the appropriate High Drywell Temperature/5 license level could not be written for the randomly sampled KA. 2.4.49 -Emergency 1 /1 Procedures I Plan: Ability to perform without reference to procedures those actions that require immediate Randomly re-sampled KA 295028 2.4.1 -Emergency operation of system Procedures I Plan: Knowledge of EOP entry conditions components and controls. and immediate action steps Question 55 295003 NMP2 is a standalone unit. Partial or Complete Loss of AC/6 1/1 2.2.3 -Equipment Control: (multi-unit license) Knowledge of the design, Randomly re-sampled KA 295003 2.2.37 -Equipment procedural, and operational Control: Ability to determine operability and/or differences between units availability of safety related equipment. Question 65 295034 An operationally relevant question at the appropriate Secondary Containment license level could not be written for the randomly Ventilation High Radiation I sampled KA. 9 EK1 .01-Knowledge of the 1/2 operational implications of the following concepts as they apply to SECONDARY CONT Al NM ENT Randomly re-sampled KA 295034 EK1 .02 -Knowledge VENTILATION HIGH of the operational implications of the following concepts RADIATION: Personnel as they apply to SECONDARY CONT Al NM ENT protection VENTILATION HIGH RADIATION: Radiation Releases. Question 69 2.2.4 NMP2 is a standalone unit. Suppression Pool High Water Temp. I 5 3 2.2.4 -Equipment Control: (multi-unit license) Knowledge of the design, Randomly re-sampled KA 295003 2.2.22 -Equipment procedural, and operational Control: Knowledge of limiting conditions for operations differences between units and safety limits. Question 31 201004 RSCS Randomly sampled system does not exist at this facility 2/2 K5.03 -Knowledge of the operational implications of the following concepts as ES-401 Record of Rejected K/A's Form ES-401-4 they apply to ROD Randomly re-sampled KA 245000 K5.02 -Knowledge SEQUENCE Group notch of the operational implications of the following control limits and rod concepts as they apply to MAIN TURBINE density: BWR-4,5 GENERATOR AND AUXILIARY SYSTEMS: Turbine operation and limitations Question 80 295018 An operationally relevant question at the appropriate Partial or Total Loss of CCW license level could not be written for the randomly /8 sampled KA. Knowledge of less than one hour technical specification action statements is RO level of knowledge 1 /1 2.2.39 -Equipment Control: per NUREG1021 ES401, attachment 2. Knowledge of less than one hour technical specification Randomly re-sampled KA 295018 2.2.42-Equipment action statements for Control: Ability to recognize system parameters that are systems. entry-level conditions for Technical Specifications An operationally relevant question at the appropriate Question 81 295038 license level could not be written for the randomly High Off-site Release Rate I sampled KA. 9 1/1 2.4.20 -Emergency Procedures I Plan: Knowledge of operational implications of EOP Randomly re-sampled KA 295038 2.4.8 -Emergency warnings, cautions, and Procedures I Plan: Knowledge of how abnormal notes. operating procedures are used in conjunction with EOP's. Question 88 217000 An operationally relevant question at the appropriate license level could not be written for the randomly RCIC sampled KA. The question can be answered solely by knowing "systems knowledge", i.e., how the system 2/1 works, flowpath, logic, component location per 2.1.27 -Conduct of NUREG1021 ES401, attachment 2. Operations: Knowledge of Randomly re-sampled KA 217000 2.1 .23 -Ability to system purpose and I or function. perform specific system and integrated plant procedures during all modes of plant operation. Question 90 300000 An operationally relevant question at the appropriate Instrument Air license level could not be written for the randomly sampled KA. The question can be answered solely by knowing "systems knowledge", i.e., how the system 2/1 works, flowpath, logic, component location per NUREG1021 ES401, attachment 2. 2.1 .30 -Conduct of Randomly re-sampled KA 300000 2.1.20 -Conduct of Operations: Ability to locate and operate components, Operations: Ability to interpret and execute procedure includinq local controls. steps. Question 98 2.1.44 An operationally relevant question at the appropriate license level could not be written for the randomly 2.1 .44 -Conduct of sampled KA. 3 Operations: Knowledge of RO duties in the control room during fuel handling such as responding to alarms from the fuel ES-401 Record of Rejected Kl A's Form ES-401-4 handling area, communication with fuel storage facility, systems operated from the control room in support of fueling operations, and supporting Randomly re-sampled KA 2.1 .25 -Ability to interpret instrumentation. reference materials, such as Qraphs, curves, tables, etc. Question 89 262002 An operationally relevant question at the appropriate UPS (AC/DC) license level could not be written for the randomly sampled KA. There is not enough of a direct tie between the UPS system and the Emergency Procedures I Plan. 1/2 2.4.46 -Emergency Procedures I Plan: Ability to verify that the alarms are consistent with the plant Randomly re-sampled KA 262002 2.2.40 -Ability to conditions. apply Technical Specifications for a system. Question 91 241000 Reactor/Turbine Pressure Regulator An operationally relevant question at the appropriate A2.23 -Ability to (a) predict license level could not be written for the randomly the impacts of the following sampled KA. Resampled by Chief Examiner direction. on the REACTOR/TURBINE Randomly re-sampled KA 241000 A2.07 -Ability to (a) PRESSURE REGULATING 2/2 SYSTEM; and (b) based on predict the impacts of the following on the REACTOR/TURBINE PRESSURE REGULATING those predictions, use SYSTEM ; and (b) based on those predictions, use procedures to correct, procedures to correct, control, or mitigate the control, or mitigate the consequences of those abnormal conditions or consequences of those operations: Loss of Condenser Vacuum abnormal conditions or operations: Turbine high eccentricity