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{{#Wiki_filter:}} | {{#Wiki_filter:ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility Date of Exam: Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G | ||
* Total A2G* Total1. Emergency & Abnormal Plant Evolutions 1 N/A N/A 18 6 2 9 4Tier Totals 27 102. Plant Systems 1 28 5 2 10 3 Tier Totals 38 8 3.Generic Knowledge and AbilitiesCategories 1 2 3 4 10 1 2 3 4 7 1.Ensure that at least two topics from every applicable K/A category are sampled within each tier of the ROand SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the ATier Totals@in each K/A category shall not be less than two). 2.The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3.Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regardingthe elimination of inappropriate K/A statements. 4.Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.5.Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively. 6.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories. 7. *The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. 8.On the following pages, enter the K/A numbers, a brief description of each topic, the topics= importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note | |||
# 1 does not apply). Use duplicate pages for RO and SRO-only exams. 9.For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43. 334433121111455544223233232221111111121133434434433332222124372164103221532027387261233580 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4Ability to perform specific system and integrated plant procedures during all modes of plant operation.295001G2.1.234.34.4Partial or Complete Loss of AC / 6Station blackout: Plant-Specific.....................295003AK1.063.84.0Partial or Total Loss of DC Pwr / 6Battery charger.......................................295004AK2.013.13.1Main Turbine Generator Trip / 3Reactor SCRAM........................................295005AK3.013.83.8SCRAM / 1RPS...................................................295006AA1.014.24.2Control Room Abandonment / 7Reactor SCRAM.........................................295016AK3.014.14.2Partial or Total Loss of CCW / 8System loads..........................................295018AK2.013.33.4Partial or Total Loss of Inst. Air / 8Status of safety-related instrument air system loads (see AK2.1 - AK2.19)..................................295019AA2.023.63.7Loss of Shutdown Cooling / 4Reactor recirculation.................................295021AK2.073.13.2295023AA1.0Refueling Acc / 83.3.High Drywell Pressure / 5Standby gas treatment/FRVS: Plant-Specific...........295024EA1.203.53.6Page 1 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1High Reactor Pressure / 3Alternate rod insertion: Plant-Specific..............295025EK3.064.24.4Suppression Pool High Water Temp. / 5Knowledge of the purpose and function of major system components and controls.295026G2.1.284.14.1295028EA2.0High Drywell Temperature / 5Reactor 3.3.9Low Suppression Pool Wtr Lvl / 5Ability to verify that the alarms are consistent with the plant conditions.295030G2.4.464.24.2Reactor Low Water Level / 2Natural circulation: Plant-Specific..................295031EK1.023.84.1SCRAM Condition Present and Power Above APRM Downscale or Unknown | |||
/ 1Shutdown margin.......................................295037EK1.073.43.8High Off-site Release Rate / 9Stack-gas monitoring system: Plant-Specific..........295038EA1.013.94.2Plant Fire On Site / 8Actions contained in the abnormal procedure for plant fire on site600000AK3.042.83.4Generator Voltage and Electric Grid DistrurbancecsOperational status of offsite circuit700000AA2.053.23.8Page 2 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G2 BWR EXAMINATION OUTLINEFORM ES-401-1Low Reactor Water Level / 2Ability to prioritize and interpret the significance of each annunciator or alarm.295009G2.4.454.14.3High Off-site Release Rate / 9Condenser air removal system: Plant-Specific.........295017AA1.063.23.2Inadvertent Cont. Isolation / 5 & 7Standby gas treatment system/FRVS: Plant-Specific....295020AK2.113.23.4295029EK2.0High Suppression Pool Wtr Lvl / 5HPC3.3.High Secondary Containment Area Temperature / 5Area temperature......................................295032EA2.013.83.8Secondary Containment Ventilation High Radiation / 9Personnel protection..................................295034EK1.013.84.1Secondary Containment High Sump/Area Water Level / 5Isolating affected systems............................295036EK3.033.53.6Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1RHR/LPCI: Injection ModeInadequate room cooling203000A2.082.93.0Shutdown CoolingMotor operated valves205000K2.022.52.7HPCIReactor pressure control: BWR-2,3,4206000K3.023.83.8LPCSAbility to execute procedure steps.209001G2.1.204.64.6SLCAbility to shutdown the reactor in certain conditions211000K3.014.34.4RPSPerform individual control rod SCRAM testing212000A4.133.43.6IRMChanging detector position215003K5.033.03.1Source Range MonitorSRM channels/detectors215004K2.012.62.8APRM / LPRMIRM/APRM recorder215005A4.013.23.1APRM / LPRMAssignment of LPRM's to specific APRM channels215005K5.062.52.6RCICPrevent water hammer: Plant-Specific217000K4.012.82.8Page 1 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1ADSKnowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.218000G2.4.302.74.1ADSNuclear boiler instrument system218000K1.033.73.8PCIS/Nuclear Steam Supply ShutoffTestability223002K4.022.72.9SRVsAir (Nitrogen) supply: Plant-Specific239002K6.023.43.5Reactor Water Level ControlTDRFP speed: TDRFP259002A1.072.62.6SGTSSuppression pool261000K1.032.93.1AC Electrical DistributionBreaker tripping262001A3.013.13.2UPS (AC/DC)Motor generator outputs262002A1.022.52.9UPS (AC/DC)Static inverter262002K6.032.72.9DC Electrical DistributionMeters, dials, recorders, alarms and indicating lights263000A3.013.23.3EDGsOpening normal and/or alternate power to emergency bus264000A2.063.43.4Page 2 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1Instrument AirContainment air system300000K3.012.72.9Instrument AirFilters300000K5.132.92.9Component Cooling WaterLoss of CCW pump400000A2.013.33.4Component Cooling WaterValves400000K6.012.72.8Page 3 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1CRD HydraulicReactor power201001A3.062.82.8Control Rod and Drive MechanismCRD drive pressure201003A1.022.82.8Recirculation Flow ControlScoop tube operation: BWR-2,3,4202002A3.033.13.0RBMInitiation point (30%): BWR-3,4,5215002K4.032.93.0Primary CTMT and Aux.Ability to prioritize and interpret the significance of each annunciator or alarm.223001G2.4.454.14.3Fuel Handling EquipmentInterlock failure234000A2.013.33.7Reactor/Turbine Pressure RegulatorTurbine inlet pressure vs. turbine load241000K5.052.82.9Main Turbine Gen. / Aux.Generator controls245000A4.023.12.9Reactor FeedwaterRFP turbine seal system: TDRFP's-Only259001K6.102.52.5RadwasteReactor building equipment drains: Plant-Specific268000K1.032.62.9Radiation MonitoringStack gas radiation monitoring system272000K2.032.52.8Page 1 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1Fire ProtectionPersonnel protection286000K3.023.23.4Page 2 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T3 BWR EXAMINATION OUTLINEFORM ES-401-1Conduct of operationsKnowledge of conduct of operations requirements.G2.1.13.84.2Conduct of operationsAbility to execute procedure steps.G2.1.204.64.6Conduct of operationsKnowledge of how to conduct system lineups, such as valves, breakers, switches, etc.G2.1.294.14.0Equipment ControlAbility to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.G2.2.14.54.4Equipment ControlKnowledge of the process for controlling equipment configuration or statusG2.2.143.94.3Equipment ControlKnowledge of the process for conducting special or infrequent testsG2.2.72.93.6Radiation ControlKnowledge of radiation monitoring systemsG2.3.152.93.1Radiation ControlAbility to comply with radiation work permit requirements during normal or abnormal conditionsG2.3.73.53.6Emergency Procedures/PlansKnowledge of EOP entry conditions and immediate action steps.G2.4.14.64.8Emergency Procedures/PlansKnowledge of the parameters and logic used to assess the status of safety functionsG2.4.214.04.6Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1Partial or Complete Loss of AC / 6Knowledge of the purpose and function of major system components and controls.295003G2.1.284.14.1Main Turbine Generator Trip / 3Electrical distribution status........................295005AA2.083.23.3Control Room Abandonment / 7Drywell pressure......................................295016AA2.053.83.9Partial or Total Loss of CCW / 8System pressure.......................................295018AA2.052.92.9Partial or Total Loss of Inst. Air / 8 295019AA2.03.3.High Reactor Pressure / 3Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.295025G2.4.302.74.1295031G2.1.2Reactor Low Water Level / 23.94Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T1G2 BWR EXAMINATION OUTLINEFORM ES-401-1Loss of Main Condenser Vac / 3Condenser vacuum/absolute pressure....................295002AA2.012.93.1295010AA2.0High Drywell Pressure / 5Drywell 3.3.High Secondary Containment Area Radiation Levels / 9Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.295033G2.4.474.24.2Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1SLCAbility to use plant computer to evaluate system or component status.211000G2.1.193.93.8IRM.215003G2.2.4.SGTSLow system flow261000A2.012.93.1EDGsLoss of off-site power during full-load testing264000A2.073.53.7Component Cooling WaterHigh/low surge tank level400000A2.022.83.0Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1CRD HydraulicValve openings201001A2.112.62.7Control Rod and Drive MechanismReactor Scram201003A2.054.14.1Traversing In-core ProbeAbility to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions215001G2.2.444.24.4Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T3 BWR EXAMINATION OUTLINEFORM ES-401-1Conduct of operations.G2.1.3.Conduct of operationsKnowledge of primary and secondary chemistry limitsG2.1.342.73.5Equipment ControlKnowledge of the process for controlling equipment configuration or statusG2.2.143.94.3Equipment ControlKnowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.G2.2.253.24.2Radiation ControlKnowledge of radiation monitoring systemsG2.3.152.93.1Emergency Procedures/PlansKnowledge of fire protection procedures.G2.4.253.33.7Emergency Procedures/PlansKnowledge of the emergency plan.G2.4.293.14.4Page 1 of 11:35 PM03/03/2015 ILT 1510 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Examination Level: RO Operating Test Number: 15-10 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations - 1 D,R JPM - 557 Placing an RPS Channel in Trip Conduct of Operations - 2 N,R JPM - 675 Determine The Required Action For Control Rod Withdrawal (Calculate Period) Equipment Control D,R JPM - 680 Perform Jet Pump Mismatch And Operability Radiation Control P,R JPM - 544 Review a Radiological Survey Map 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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes) (N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected) (S)imulator ILT 1510 Administrative Topics Outline Form ES-301-1 Reactor Operator Conduct of Operation 1. JPM - 557 Title: Placing an RPS Channel in Trip | |||
== Description:== | |||
Given Turbine Stop Valve #3 limit switches failed the surveillance 3-SR-3.3.1.1.14(8I) Turbine Stop Valve Closure - RPS Trip (Channel A1/A2) and RPT Trip (System A & B) Logic System Functional Test. The RO is going to determine the correct number and location of the RPS Fuses to remove to place the channel in the tripped condition. The task is completed when both fuses are identified in to 3-OI-99 Reactor Protection System. A hard copy of 3-OI-99 will be provided. K/A: 2.1.25; Ability to interpret reference materials, such as graphs, curves, tables, etc. 2. JPM - 675 Title: Determine the required action for rod pull (calculate period) | |||
== Description:== | |||
Provided initial IRM reading and a Doubling Time with a second set of IRM readings, the RO will calculate the current period and determine that it is faster than procedurally allowed and he will indicate that the rod should be reinserted. K/A: 2.1.37; Knowledge of procedures, guidelines, or limitations associated with reactivity management. Equipment Control 1. JPM - 680 Title: Perform Jet Pump Mismatch and Operability SR (Alternate Path) | |||
== Description:== | |||
Provided with Jet Pump Instrument reading and a copy of the surveillance, the RO is going to determine 2-SR-3.4.2.1, Jet Pump Mismatch and Operability is not met for Jet Pump 15. K/A: 2.2.12; Knowledge of surveillance procedures. Radiation Control 1. JPM - 544 Title: Review a Radiological Survey Map | |||
== Description:== | |||
Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM. K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions. | |||
ILT 1501 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Examination Level: SRO Operating Test Number: 15-10 Administrative Topic (see Note) Type Code | |||
* Describe activity to be performed Conduct of Operations M,R JPM - 678 Shift Staffing - SRO Conduct of Operations N,R JPM - 677 Fuel Handling / fuel storage, determine compliance with guidelines. Equipment Control M,R JPM - 676 Review Completed SR (SRO) Radiation Control P,R JPM - 544 Review a Radiological Survey Map Emergency Plan M,R JPM - 679 Upgrade PAR on wind shift. 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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes) (N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected) (S)imulator ILT 1501 Administrative Topics Outline Form ES-301-1 Senior Reactor Operator Conduct of Operation 1. JPM - 678 Title: Shift Staffing - SRO | |||
== Description:== | |||
Provided with a crew complement, the SRO determines if his staff meets the minimum shift requirements. The list of people appears to be below the minimum; however an SRO can be moved down to an RO position to fill the Crew Complement. The Emergency Responder position is also down one, so a callout is required. K/A: 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc. | |||
: 2. JPM - 677 Title: Fuel Handling fuel storage, determines compliance with guidelines. | |||
== Description:== | |||
Provided with Nuclear Fuel Storage physical locations and configurations, the SRO must determine if the fuel is being stored within the guidance of the procedure. In this case there are new fuel bundles stored in locations that are not allowed. K/A: 2.1.35 Knowledge of the fuel-handling responsibilities of SROs. Equipment Control 1. JPM - 676 Title: Review Completed SR (SRO) | |||
== Description:== | |||
Provided a completed SR-3.4.2.1 that the Unit Operator completed on his shift, the SRO is to review the SR for completeness and accuracy. The SR is filled out incorrectly and identified as meeting the surveillance requirements, however the surveillance requirements are not met and the SRO must identify that and determine the correct LCO. K/A: 2.2.22; Knowledge of limiting conditions for operations and safety limits Radiation Control 1. JPM - 544 Title: Review a Radiological Survey Map | |||
== Description:== | |||
Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM. K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions. Emergency Plan 1. JPM - 679 Title: Upgrade PAR on wind shift | |||
== Description:== | |||
Provided an EPIP-5 General Emergency declaration form and new information about meteorological conditions determine that the PAR needs to be adjusted to include a new sector for sheltering. That will require the SRO to fill out another form with the new information. K/A: 2.4.44; Knowledge of emergency plan protective action recommendations ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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. JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 e. JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3 f. JPM 669 EOI-Appendix-14A N2 Makeup To Primary ContainmentN,S 5 g. JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6 h. JPM 190 Respond to Off-Gas Post-Treatment Radiation HI-HI-HI (RO Only) A,M,P,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9 k. JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D 6 | |||
* 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures a. JPM 80A Title: Respond to a Control Rod Drift In. IAW AOI-85-5 | |||
== Description:== | |||
While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. as he continues with the surveillance multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI-85-5, Rod Drift In. Once scram report is given the JPM will end. | |||
K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm | |||
: b. JPM 276 Title: EHC Auto Cooldown | |||
== Description:== | |||
The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end. K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure | |||
: c. JPM 672A Title: Loss Of Reference APRM To Rod Block Monitor (RBM) | |||
== Description:== | |||
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed, to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end. | |||
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5 | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures d. JPM 257A Title: EOI Appendix-6E Injection Subsystem Lineup CS System II | |||
== Description:== | |||
The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF | |||
(-162 in) the JPM will end. | |||
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level | |||
: e. JPM 670A Title: EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow | |||
== Description:== | |||
The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end. K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure | |||
: f. JPM 669 Title: EOI-Appendix-14A N2 Makeup To Primary Containment | |||
== Description:== | |||
The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end. | |||
K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures g. JPM 631 Title: Restore Offsite Power to 4KV shutdown board at PNL 9-23 | |||
== Description:== | |||
The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end. K/A: 262001 A.C. Electrical Distribution; A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages | |||
: h. JPM 190 Title: Respond to Off-Gas Post-Treatment Radiation HI-HI-HI(RO Only) | |||
== Description:== | |||
The BOP Operator will respond to OFF-GAS POST TREATMENT RADIATION HI-HI-HI annunciator. The operator will close FCV-66-28, OFF-GAS SYSTEM ISOLATION VALVE and then perform immediate actions of AOI-66-2, Off-gas Post-treatment Radiation Hi-Hi-Hi. The operator will reduce core flow to 50-60% and then insert a manual reactor scram. The operator will continue with subsequent actions. Once the standby Stack Dilution fan is started the JPM will end. | |||
K/A: 271000 Offgas System: A2.16; Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of offgas system loop seals (2.9/3.2) | |||
: i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps | |||
== Description:== | |||
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end. | |||
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures j. JPM 674 Title: Aligning Emergency EECW Makeup To Spent Fuel Pool | |||
== Description:== | |||
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end. | |||
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level | |||
: k. JPM 307 Title: Start up and synchronize Unit 3 Preferred MMG Set | |||
== Description:== | |||
The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end. | |||
K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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. JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 e. JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3 f. JPM 669 EOI-Appendix-14A N2 Makeup To Primary Containment N,S 5 g. JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9 k. JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D 6 | |||
* 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures a. JPM 80A Title: Respond to a Control Rod Drift In. IAW AOI-85-5 | |||
== Description:== | |||
While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods, the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. As he continues with the surveillance, multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI-85-5, Rod Drift In. Once scram report is given the JPM will end. | |||
K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm | |||
: b. JPM 276 Title: EHC Auto Cooldown | |||
== Description:== | |||
The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end. K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure | |||
: c. JPM 672 Title: Loss Of Reference APRM To Rod Block Monitor (RBM) | |||
== Description:== | |||
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end. | |||
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5 | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures d. JPM 257A Title: EOI Appendix-6E Injection Subsystem Lineup CS System II | |||
== Description:== | |||
The ATC Operator has been directed to in water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF | |||
(-162 in) the JPM will end. | |||
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level | |||
: e. JPM 670A Title: EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow | |||
== Description:== | |||
The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end. K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure | |||
: f. JPM 669 Title: EOI-Appendix-14A N2 Makeup To Primary Containment With | |||
== Description:== | |||
The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end. | |||
K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures g. JPM 631 Title: Restore Offsite Power to 4KV shutdown board at PNL 9-23 | |||
== Description:== | |||
The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end. K/A: 262001 A.C. Electrical Distribution A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages | |||
: i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps | |||
== Description:== | |||
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end. | |||
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required | |||
: j. JPM 674 Title: Aligning Emergency EECW Makeup To Spent Fuel Pool | |||
== Description:== | |||
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end. | |||
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures k. JPM 307 Title: Start up and synchronize Unit 3 Preferred MMG Set | |||
== Description:== | |||
The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end. | |||
K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9 | |||
* 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Upgrade Job Performance Measures b. JPM 276 Title: EHC Auto Cooldown | |||
== Description:== | |||
The BOP Operator will begin commence a cooldown of the reactor plant to 20psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end. | |||
K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure | |||
: c. JPM 672A Title: Loss Of Reference APRM To Rod Block Monitor (RBM) | |||
== Description:== | |||
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared and rod movement has continued the JPM will end. | |||
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5 | |||
: d. JPM 257A Title: EOI Appendix-6E Injection Subsystem Lineup CS System II | |||
== Description:== | |||
The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF | |||
(-162 in) the JPM will end. | |||
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Upgrade Job Performance Measures i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps | |||
== Description:== | |||
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end. | |||
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required | |||
: j. JPM 674 Title: Aligning Emergency EECW Makeup To Spent Fuel Pool | |||
== Description:== | |||
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end. | |||
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level | |||
ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility Date of Exam: Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G | |||
* Total A2G* Total1. Emergency & Abnormal Plant Evolutions 1 N/A N/A 18 6 2 9 4Tier Totals 27 102. Plant Systems 1 28 5 2 10 3 Tier Totals 38 8 3.Generic Knowledge and AbilitiesCategories 1 2 3 4 10 1 2 3 4 7 1.Ensure that at least two topics from every applicable K/A category are sampled within each tier of the ROand SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the ATier Totals@in each K/A category shall not be less than two). 2.The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3.Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regardingthe elimination of inappropriate K/A statements. 4.Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.5.Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively. 6.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories. 7. *The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. 8.On the following pages, enter the K/A numbers, a brief description of each topic, the topics= importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note | |||
# 1 does not apply). Use duplicate pages for RO and SRO-only exams. 9.For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43. 334433121111455544223233232221111111121133434434433332222124372164103221532027387261233580 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4Ability to perform specific system and integrated plant procedures during all modes of plant operation.295001G2.1.234.34.4Partial or Complete Loss of AC / 6Station blackout: Plant-Specific.....................295003AK1.063.84.0Partial or Total Loss of DC Pwr / 6Battery charger.......................................295004AK2.013.13.1Main Turbine Generator Trip / 3Reactor SCRAM........................................295005AK3.013.83.8SCRAM / 1RPS...................................................295006AA1.014.24.2Control Room Abandonment / 7Reactor SCRAM.........................................295016AK3.014.14.2Partial or Total Loss of CCW / 8System loads..........................................295018AK2.013.33.4Partial or Total Loss of Inst. Air / 8Status of safety-related instrument air system loads (see AK2.1 - AK2.19)..................................295019AA2.023.63.7Loss of Shutdown Cooling / 4Reactor recirculation.................................295021AK2.073.13.2295023AA1.0Refueling Acc / 83.3.High Drywell Pressure / 5Standby gas treatment/FRVS: Plant-Specific...........295024EA1.203.53.6Page 1 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1High Reactor Pressure / 3Alternate rod insertion: Plant-Specific..............295025EK3.064.24.4Suppression Pool High Water Temp. / 5Knowledge of the purpose and function of major system components and controls.295026G2.1.284.14.1295028EA2.0High Drywell Temperature / 5Reactor 3.3.9Low Suppression Pool Wtr Lvl / 5Ability to verify that the alarms are consistent with the plant conditions.295030G2.4.464.24.2Reactor Low Water Level / 2Natural circulation: Plant-Specific..................295031EK1.023.84.1SCRAM Condition Present and Power Above APRM Downscale or Unknown | |||
/ 1Shutdown margin.......................................295037EK1.073.43.8High Off-site Release Rate / 9Stack-gas monitoring system: Plant-Specific..........295038EA1.013.94.2Plant Fire On Site / 8Actions contained in the abnormal procedure for plant fire on site600000AK3.042.83.4Generator Voltage and Electric Grid DistrurbancecsOperational status of offsite circuit700000AA2.053.23.8Page 2 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G2 BWR EXAMINATION OUTLINEFORM ES-401-1Low Reactor Water Level / 2Ability to prioritize and interpret the significance of each annunciator or alarm.295009G2.4.454.14.3High Off-site Release Rate / 9Condenser air removal system: Plant-Specific.........295017AA1.063.23.2Inadvertent Cont. Isolation / 5 & 7Standby gas treatment system/FRVS: Plant-Specific....295020AK2.113.23.4295029EK2.0High Suppression Pool Wtr Lvl / 5HPC3.3.High Secondary Containment Area Temperature / 5Area temperature......................................295032EA2.013.83.8Secondary Containment Ventilation High Radiation / 9Personnel protection..................................295034EK1.013.84.1Secondary Containment High Sump/Area Water Level / 5Isolating affected systems............................295036EK3.033.53.6Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1RHR/LPCI: Injection ModeInadequate room cooling203000A2.082.93.0Shutdown CoolingMotor operated valves205000K2.022.52.7HPCIReactor pressure control: BWR-2,3,4206000K3.023.83.8LPCSAbility to execute procedure steps.209001G2.1.204.64.6SLCAbility to shutdown the reactor in certain conditions211000K3.014.34.4RPSPerform individual control rod SCRAM testing212000A4.133.43.6IRMChanging detector position215003K5.033.03.1Source Range MonitorSRM channels/detectors215004K2.012.62.8APRM / LPRMIRM/APRM recorder215005A4.013.23.1APRM / LPRMAssignment of LPRM's to specific APRM channels215005K5.062.52.6RCICPrevent water hammer: Plant-Specific217000K4.012.82.8Page 1 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1ADSKnowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.218000G2.4.302.74.1ADSNuclear boiler instrument system218000K1.033.73.8PCIS/Nuclear Steam Supply ShutoffTestability223002K4.022.72.9SRVsAir (Nitrogen) supply: Plant-Specific239002K6.023.43.5Reactor Water Level ControlTDRFP speed: TDRFP259002A1.072.62.6SGTSSuppression pool261000K1.032.93.1AC Electrical DistributionBreaker tripping262001A3.013.13.2UPS (AC/DC)Motor generator outputs262002A1.022.52.9UPS (AC/DC)Static inverter262002K6.032.72.9DC Electrical DistributionMeters, dials, recorders, alarms and indicating lights263000A3.013.23.3EDGsOpening normal and/or alternate power to emergency bus264000A2.063.43.4Page 2 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1Instrument AirContainment air system300000K3.012.72.9Instrument AirFilters300000K5.132.92.9Component Cooling WaterLoss of CCW pump400000A2.013.33.4Component Cooling WaterValves400000K6.012.72.8Page 3 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1CRD HydraulicReactor power201001A3.062.82.8Control Rod and Drive MechanismCRD drive pressure201003A1.022.82.8Recirculation Flow ControlScoop tube operation: BWR-2,3,4202002A3.033.13.0RBMInitiation point (30%): BWR-3,4,5215002K4.032.93.0Primary CTMT and Aux.Ability to prioritize and interpret the significance of each annunciator or alarm.223001G2.4.454.14.3Fuel Handling EquipmentInterlock failure234000A2.013.33.7Reactor/Turbine Pressure RegulatorTurbine inlet pressure vs. turbine load241000K5.052.82.9Main Turbine Gen. / Aux.Generator controls245000A4.023.12.9Reactor FeedwaterRFP turbine seal system: TDRFP's-Only259001K6.102.52.5RadwasteReactor building equipment drains: Plant-Specific268000K1.032.62.9Radiation MonitoringStack gas radiation monitoring system272000K2.032.52.8Page 1 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1Fire ProtectionPersonnel protection286000K3.023.23.4Page 2 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T3 BWR EXAMINATION OUTLINEFORM ES-401-1Conduct of operationsKnowledge of conduct of operations requirements.G2.1.13.84.2Conduct of operationsAbility to execute procedure steps.G2.1.204.64.6Conduct of operationsKnowledge of how to conduct system lineups, such as valves, breakers, switches, etc.G2.1.294.14.0Equipment ControlAbility to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.G2.2.14.54.4Equipment ControlKnowledge of the process for controlling equipment configuration or statusG2.2.143.94.3Equipment ControlKnowledge of the process for conducting special or infrequent testsG2.2.72.93.6Radiation ControlKnowledge of radiation monitoring systemsG2.3.152.93.1Radiation ControlAbility to comply with radiation work permit requirements during normal or abnormal conditionsG2.3.73.53.6Emergency Procedures/PlansKnowledge of EOP entry conditions and immediate action steps.G2.4.14.64.8Emergency Procedures/PlansKnowledge of the parameters and logic used to assess the status of safety functionsG2.4.214.04.6Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1Partial or Complete Loss of AC / 6Knowledge of the purpose and function of major system components and controls.295003G2.1.284.14.1Main Turbine Generator Trip / 3Electrical distribution status........................295005AA2.083.23.3Control Room Abandonment / 7Drywell pressure......................................295016AA2.053.83.9Partial or Total Loss of CCW / 8System pressure.......................................295018AA2.052.92.9Partial or Total Loss of Inst. Air / 8 295019AA2.03.3.High Reactor Pressure / 3Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.295025G2.4.302.74.1295031G2.1.2Reactor Low Water Level / 23.94Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T1G2 BWR EXAMINATION OUTLINEFORM ES-401-1Loss of Main Condenser Vac / 3Condenser vacuum/absolute pressure....................295002AA2.012.93.1295010AA2.0High Drywell Pressure / 5Drywell 3.3.High Secondary Containment Area Radiation Levels / 9Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.295033G2.4.474.24.2Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1SLCAbility to use plant computer to evaluate system or component status.211000G2.1.193.93.8IRM.215003G2.2.4.SGTSLow system flow261000A2.012.93.1EDGsLoss of off-site power during full-load testing264000A2.073.53.7Component Cooling WaterHigh/low surge tank level400000A2.022.83.0Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1CRD HydraulicValve openings201001A2.112.62.7Control Rod and Drive MechanismReactor Scram201003A2.054.14.1Traversing In-core ProbeAbility to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions215001G2.2.444.24.4Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T3 BWR EXAMINATION OUTLINEFORM ES-401-1Conduct of operations.G2.1.3.Conduct of operationsKnowledge of primary and secondary chemistry limitsG2.1.342.73.5Equipment ControlKnowledge of the process for controlling equipment configuration or statusG2.2.143.94.3Equipment ControlKnowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.G2.2.253.24.2Radiation ControlKnowledge of radiation monitoring systemsG2.3.152.93.1Emergency Procedures/PlansKnowledge of fire protection procedures.G2.4.253.33.7Emergency Procedures/PlansKnowledge of the emergency plan.G2.4.293.14.4Page 1 of 11:35 PM03/03/2015 ILT 1510 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Examination Level: RO Operating Test Number: 15-10 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations - 1 D,R JPM - 557 Placing an RPS Channel in Trip Conduct of Operations - 2 N,R JPM - 675 Determine The Required Action For Control Rod Withdrawal (Calculate Period) Equipment Control D,R JPM - 680 Perform Jet Pump Mismatch And Operability Radiation Control P,R JPM - 544 Review a Radiological Survey Map 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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes) (N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected) (S)imulator ILT 1510 Administrative Topics Outline Form ES-301-1 Reactor Operator Conduct of Operation 1. JPM - 557 Title: Placing an RPS Channel in Trip | |||
== Description:== | |||
Given Turbine Stop Valve #3 limit switches failed the surveillance 3-SR-3.3.1.1.14(8I) Turbine Stop Valve Closure - RPS Trip (Channel A1/A2) and RPT Trip (System A & B) Logic System Functional Test. The RO is going to determine the correct number and location of the RPS Fuses to remove to place the channel in the tripped condition. The task is completed when both fuses are identified in to 3-OI-99 Reactor Protection System. A hard copy of 3-OI-99 will be provided. K/A: 2.1.25; Ability to interpret reference materials, such as graphs, curves, tables, etc. 2. JPM - 675 Title: Determine the required action for rod pull (calculate period) | |||
== Description:== | |||
Provided initial IRM reading and a Doubling Time with a second set of IRM readings, the RO will calculate the current period and determine that it is faster than procedurally allowed and he will indicate that the rod should be reinserted. K/A: 2.1.37; Knowledge of procedures, guidelines, or limitations associated with reactivity management. Equipment Control 1. JPM - 680 Title: Perform Jet Pump Mismatch and Operability SR (Alternate Path) | |||
== Description:== | |||
Provided with Jet Pump Instrument reading and a copy of the surveillance, the RO is going to determine 2-SR-3.4.2.1, Jet Pump Mismatch and Operability is not met for Jet Pump 15. K/A: 2.2.12; Knowledge of surveillance procedures. Radiation Control 1. JPM - 544 Title: Review a Radiological Survey Map | |||
== Description:== | |||
Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM. K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions. | |||
ILT 1501 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Examination Level: SRO Operating Test Number: 15-10 Administrative Topic (see Note) Type Code | |||
* Describe activity to be performed Conduct of Operations M,R JPM - 678 Shift Staffing - SRO Conduct of Operations N,R JPM - 677 Fuel Handling / fuel storage, determine compliance with guidelines. Equipment Control M,R JPM - 676 Review Completed SR (SRO) Radiation Control P,R JPM - 544 Review a Radiological Survey Map Emergency Plan M,R JPM - 679 Upgrade PAR on wind shift. 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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes) (N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected) (S)imulator ILT 1501 Administrative Topics Outline Form ES-301-1 Senior Reactor Operator Conduct of Operation 1. JPM - 678 Title: Shift Staffing - SRO | |||
== Description:== | |||
Provided with a crew complement, the SRO determines if his staff meets the minimum shift requirements. The list of people appears to be below the minimum; however an SRO can be moved down to an RO position to fill the Crew Complement. The Emergency Responder position is also down one, so a callout is required. K/A: 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc. | |||
: 2. JPM - 677 Title: Fuel Handling fuel storage, determines compliance with guidelines. | |||
== Description:== | |||
Provided with Nuclear Fuel Storage physical locations and configurations, the SRO must determine if the fuel is being stored within the guidance of the procedure. In this case there are new fuel bundles stored in locations that are not allowed. K/A: 2.1.35 Knowledge of the fuel-handling responsibilities of SROs. Equipment Control 1. JPM - 676 Title: Review Completed SR (SRO) | |||
== Description:== | |||
Provided a completed SR-3.4.2.1 that the Unit Operator completed on his shift, the SRO is to review the SR for completeness and accuracy. The SR is filled out incorrectly and identified as meeting the surveillance requirements, however the surveillance requirements are not met and the SRO must identify that and determine the correct LCO. K/A: 2.2.22; Knowledge of limiting conditions for operations and safety limits Radiation Control 1. JPM - 544 Title: Review a Radiological Survey Map | |||
== Description:== | |||
Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM. K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions. Emergency Plan 1. JPM - 679 Title: Upgrade PAR on wind shift | |||
== Description:== | |||
Provided an EPIP-5 General Emergency declaration form and new information about meteorological conditions determine that the PAR needs to be adjusted to include a new sector for sheltering. That will require the SRO to fill out another form with the new information. K/A: 2.4.44; Knowledge of emergency plan protective action recommendations ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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. JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 e. JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3 f. JPM 669 EOI-Appendix-14A N2 Makeup To Primary ContainmentN,S 5 g. JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6 h. JPM 190 Respond to Off-Gas Post-Treatment Radiation HI-HI-HI (RO Only) A,M,P,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9 k. JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D 6 | |||
* 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures a. JPM 80A Title: Respond to a Control Rod Drift In. IAW AOI-85-5 | |||
== Description:== | |||
While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. as he continues with the surveillance multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI-85-5, Rod Drift In. Once scram report is given the JPM will end. | |||
K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm | |||
: b. JPM 276 Title: EHC Auto Cooldown | |||
== Description:== | |||
The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end. K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure | |||
: c. JPM 672A Title: Loss Of Reference APRM To Rod Block Monitor (RBM) | |||
== Description:== | |||
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed, to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end. | |||
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5 | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures d. JPM 257A Title: EOI Appendix-6E Injection Subsystem Lineup CS System II | |||
== Description:== | |||
The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF | |||
(-162 in) the JPM will end. | |||
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level | |||
: e. JPM 670A Title: EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow | |||
== Description:== | |||
The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end. K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure | |||
: f. JPM 669 Title: EOI-Appendix-14A N2 Makeup To Primary Containment | |||
== Description:== | |||
The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end. | |||
K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures g. JPM 631 Title: Restore Offsite Power to 4KV shutdown board at PNL 9-23 | |||
== Description:== | |||
The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end. K/A: 262001 A.C. Electrical Distribution; A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages | |||
: h. JPM 190 Title: Respond to Off-Gas Post-Treatment Radiation HI-HI-HI(RO Only) | |||
== Description:== | |||
The BOP Operator will respond to OFF-GAS POST TREATMENT RADIATION HI-HI-HI annunciator. The operator will close FCV-66-28, OFF-GAS SYSTEM ISOLATION VALVE and then perform immediate actions of AOI-66-2, Off-gas Post-treatment Radiation Hi-Hi-Hi. The operator will reduce core flow to 50-60% and then insert a manual reactor scram. The operator will continue with subsequent actions. Once the standby Stack Dilution fan is started the JPM will end. | |||
K/A: 271000 Offgas System: A2.16; Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of offgas system loop seals (2.9/3.2) | |||
: i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps | |||
== Description:== | |||
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end. | |||
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures j. JPM 674 Title: Aligning Emergency EECW Makeup To Spent Fuel Pool | |||
== Description:== | |||
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end. | |||
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level | |||
: k. JPM 307 Title: Start up and synchronize Unit 3 Preferred MMG Set | |||
== Description:== | |||
The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end. | |||
K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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. JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 e. JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3 f. JPM 669 EOI-Appendix-14A N2 Makeup To Primary Containment N,S 5 g. JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9 k. JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D 6 | |||
* 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures a. JPM 80A Title: Respond to a Control Rod Drift In. IAW AOI-85-5 | |||
== Description:== | |||
While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods, the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. As he continues with the surveillance, multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI-85-5, Rod Drift In. Once scram report is given the JPM will end. | |||
K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm | |||
: b. JPM 276 Title: EHC Auto Cooldown | |||
== Description:== | |||
The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end. K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure | |||
: c. JPM 672 Title: Loss Of Reference APRM To Rod Block Monitor (RBM) | |||
== Description:== | |||
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end. | |||
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5 | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures d. JPM 257A Title: EOI Appendix-6E Injection Subsystem Lineup CS System II | |||
== Description:== | |||
The ATC Operator has been directed to in water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF | |||
(-162 in) the JPM will end. | |||
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level | |||
: e. JPM 670A Title: EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow | |||
== Description:== | |||
The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end. K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure | |||
: f. JPM 669 Title: EOI-Appendix-14A N2 Makeup To Primary Containment With | |||
== Description:== | |||
The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end. | |||
K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures g. JPM 631 Title: Restore Offsite Power to 4KV shutdown board at PNL 9-23 | |||
== Description:== | |||
The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end. K/A: 262001 A.C. Electrical Distribution A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages | |||
: i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps | |||
== Description:== | |||
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end. | |||
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required | |||
: j. JPM 674 Title: Aligning Emergency EECW Makeup To Spent Fuel Pool | |||
== Description:== | |||
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end. | |||
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures k. JPM 307 Title: Start up and synchronize Unit 3 Preferred MMG Set | |||
== Description:== | |||
The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end. | |||
K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9 | |||
* 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Upgrade Job Performance Measures b. JPM 276 Title: EHC Auto Cooldown | |||
== Description:== | |||
The BOP Operator will begin commence a cooldown of the reactor plant to 20psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end. | |||
K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure | |||
: c. JPM 672A Title: Loss Of Reference APRM To Rod Block Monitor (RBM) | |||
== Description:== | |||
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared and rod movement has continued the JPM will end. | |||
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5 | |||
: d. JPM 257A Title: EOI Appendix-6E Injection Subsystem Lineup CS System II | |||
== Description:== | |||
The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF | |||
(-162 in) the JPM will end. | |||
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level | |||
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Upgrade Job Performance Measures i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps | |||
== Description:== | |||
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end. | |||
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required | |||
: j. JPM 674 Title: Aligning Emergency EECW Makeup To Spent Fuel Pool | |||
== Description:== | |||
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end. | |||
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level}} | |||
Revision as of 21:40, 28 May 2018
| ML16049A032 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/18/2016 |
| From: | Division of Reactor Safety II |
| To: | Tennessee Valley Authority |
| References | |
| Download: ML16049A032 (32) | |
Text
ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility Date of Exam: Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
- Total A2G* Total1. Emergency & Abnormal Plant Evolutions 1 N/A N/A 18 6 2 9 4Tier Totals 27 102. Plant Systems 1 28 5 2 10 3 Tier Totals 38 8 3.Generic Knowledge and AbilitiesCategories 1 2 3 4 10 1 2 3 4 7 1.Ensure that at least two topics from every applicable K/A category are sampled within each tier of the ROand SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the ATier Totals@in each K/A category shall not be less than two). 2.The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3.Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regardingthe elimination of inappropriate K/A statements. 4.Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.5.Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively. 6.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories. 7. *The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. 8.On the following pages, enter the K/A numbers, a brief description of each topic, the topics= importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note
- 1 does not apply). Use duplicate pages for RO and SRO-only exams. 9.For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43. 334433121111455544223233232221111111121133434434433332222124372164103221532027387261233580 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4Ability to perform specific system and integrated plant procedures during all modes of plant operation.295001G2.1.234.34.4Partial or Complete Loss of AC / 6Station blackout: Plant-Specific.....................295003AK1.063.84.0Partial or Total Loss of DC Pwr / 6Battery charger.......................................295004AK2.013.13.1Main Turbine Generator Trip / 3Reactor SCRAM........................................295005AK3.013.83.8SCRAM / 1RPS...................................................295006AA1.014.24.2Control Room Abandonment / 7Reactor SCRAM.........................................295016AK3.014.14.2Partial or Total Loss of CCW / 8System loads..........................................295018AK2.013.33.4Partial or Total Loss of Inst. Air / 8Status of safety-related instrument air system loads (see AK2.1 - AK2.19)..................................295019AA2.023.63.7Loss of Shutdown Cooling / 4Reactor recirculation.................................295021AK2.073.13.2295023AA1.0Refueling Acc / 83.3.High Drywell Pressure / 5Standby gas treatment/FRVS: Plant-Specific...........295024EA1.203.53.6Page 1 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1High Reactor Pressure / 3Alternate rod insertion: Plant-Specific..............295025EK3.064.24.4Suppression Pool High Water Temp. / 5Knowledge of the purpose and function of major system components and controls.295026G2.1.284.14.1295028EA2.0High Drywell Temperature / 5Reactor 3.3.9Low Suppression Pool Wtr Lvl / 5Ability to verify that the alarms are consistent with the plant conditions.295030G2.4.464.24.2Reactor Low Water Level / 2Natural circulation: Plant-Specific..................295031EK1.023.84.1SCRAM Condition Present and Power Above APRM Downscale or Unknown
/ 1Shutdown margin.......................................295037EK1.073.43.8High Off-site Release Rate / 9Stack-gas monitoring system: Plant-Specific..........295038EA1.013.94.2Plant Fire On Site / 8Actions contained in the abnormal procedure for plant fire on site600000AK3.042.83.4Generator Voltage and Electric Grid DistrurbancecsOperational status of offsite circuit700000AA2.053.23.8Page 2 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G2 BWR EXAMINATION OUTLINEFORM ES-401-1Low Reactor Water Level / 2Ability to prioritize and interpret the significance of each annunciator or alarm.295009G2.4.454.14.3High Off-site Release Rate / 9Condenser air removal system: Plant-Specific.........295017AA1.063.23.2Inadvertent Cont. Isolation / 5 & 7Standby gas treatment system/FRVS: Plant-Specific....295020AK2.113.23.4295029EK2.0High Suppression Pool Wtr Lvl / 5HPC3.3.High Secondary Containment Area Temperature / 5Area temperature......................................295032EA2.013.83.8Secondary Containment Ventilation High Radiation / 9Personnel protection..................................295034EK1.013.84.1Secondary Containment High Sump/Area Water Level / 5Isolating affected systems............................295036EK3.033.53.6Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1RHR/LPCI: Injection ModeInadequate room cooling203000A2.082.93.0Shutdown CoolingMotor operated valves205000K2.022.52.7HPCIReactor pressure control: BWR-2,3,4206000K3.023.83.8LPCSAbility to execute procedure steps.209001G2.1.204.64.6SLCAbility to shutdown the reactor in certain conditions211000K3.014.34.4RPSPerform individual control rod SCRAM testing212000A4.133.43.6IRMChanging detector position215003K5.033.03.1Source Range MonitorSRM channels/detectors215004K2.012.62.8APRM / LPRMIRM/APRM recorder215005A4.013.23.1APRM / LPRMAssignment of LPRM's to specific APRM channels215005K5.062.52.6RCICPrevent water hammer: Plant-Specific217000K4.012.82.8Page 1 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1ADSKnowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.218000G2.4.302.74.1ADSNuclear boiler instrument system218000K1.033.73.8PCIS/Nuclear Steam Supply ShutoffTestability223002K4.022.72.9SRVsAir (Nitrogen) supply: Plant-Specific239002K6.023.43.5Reactor Water Level ControlTDRFP speed: TDRFP259002A1.072.62.6SGTSSuppression pool261000K1.032.93.1AC Electrical DistributionBreaker tripping262001A3.013.13.2UPS (AC/DC)Motor generator outputs262002A1.022.52.9UPS (AC/DC)Static inverter262002K6.032.72.9DC Electrical DistributionMeters, dials, recorders, alarms and indicating lights263000A3.013.23.3EDGsOpening normal and/or alternate power to emergency bus264000A2.063.43.4Page 2 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1Instrument AirContainment air system300000K3.012.72.9Instrument AirFilters300000K5.132.92.9Component Cooling WaterLoss of CCW pump400000A2.013.33.4Component Cooling WaterValves400000K6.012.72.8Page 3 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1CRD HydraulicReactor power201001A3.062.82.8Control Rod and Drive MechanismCRD drive pressure201003A1.022.82.8Recirculation Flow ControlScoop tube operation: BWR-2,3,4202002A3.033.13.0RBMInitiation point (30%): BWR-3,4,5215002K4.032.93.0Primary CTMT and Aux.Ability to prioritize and interpret the significance of each annunciator or alarm.223001G2.4.454.14.3Fuel Handling EquipmentInterlock failure234000A2.013.33.7Reactor/Turbine Pressure RegulatorTurbine inlet pressure vs. turbine load241000K5.052.82.9Main Turbine Gen. / Aux.Generator controls245000A4.023.12.9Reactor FeedwaterRFP turbine seal system: TDRFP's-Only259001K6.102.52.5RadwasteReactor building equipment drains: Plant-Specific268000K1.032.62.9Radiation MonitoringStack gas radiation monitoring system272000K2.032.52.8Page 1 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1Fire ProtectionPersonnel protection286000K3.023.23.4Page 2 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T3 BWR EXAMINATION OUTLINEFORM ES-401-1Conduct of operationsKnowledge of conduct of operations requirements.G2.1.13.84.2Conduct of operationsAbility to execute procedure steps.G2.1.204.64.6Conduct of operationsKnowledge of how to conduct system lineups, such as valves, breakers, switches, etc.G2.1.294.14.0Equipment ControlAbility to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.G2.2.14.54.4Equipment ControlKnowledge of the process for controlling equipment configuration or statusG2.2.143.94.3Equipment ControlKnowledge of the process for conducting special or infrequent testsG2.2.72.93.6Radiation ControlKnowledge of radiation monitoring systemsG2.3.152.93.1Radiation ControlAbility to comply with radiation work permit requirements during normal or abnormal conditionsG2.3.73.53.6Emergency Procedures/PlansKnowledge of EOP entry conditions and immediate action steps.G2.4.14.64.8Emergency Procedures/PlansKnowledge of the parameters and logic used to assess the status of safety functionsG2.4.214.04.6Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1Partial or Complete Loss of AC / 6Knowledge of the purpose and function of major system components and controls.295003G2.1.284.14.1Main Turbine Generator Trip / 3Electrical distribution status........................295005AA2.083.23.3Control Room Abandonment / 7Drywell pressure......................................295016AA2.053.83.9Partial or Total Loss of CCW / 8System pressure.......................................295018AA2.052.92.9Partial or Total Loss of Inst. Air / 8 295019AA2.03.3.High Reactor Pressure / 3Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.295025G2.4.302.74.1295031G2.1.2Reactor Low Water Level / 23.94Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T1G2 BWR EXAMINATION OUTLINEFORM ES-401-1Loss of Main Condenser Vac / 3Condenser vacuum/absolute pressure....................295002AA2.012.93.1295010AA2.0High Drywell Pressure / 5Drywell 3.3.High Secondary Containment Area Radiation Levels / 9Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.295033G2.4.474.24.2Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1SLCAbility to use plant computer to evaluate system or component status.211000G2.1.193.93.8IRM.215003G2.2.4.SGTSLow system flow261000A2.012.93.1EDGsLoss of off-site power during full-load testing264000A2.073.53.7Component Cooling WaterHigh/low surge tank level400000A2.022.83.0Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1CRD HydraulicValve openings201001A2.112.62.7Control Rod and Drive MechanismReactor Scram201003A2.054.14.1Traversing In-core ProbeAbility to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions215001G2.2.444.24.4Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T3 BWR EXAMINATION OUTLINEFORM ES-401-1Conduct of operations.G2.1.3.Conduct of operationsKnowledge of primary and secondary chemistry limitsG2.1.342.73.5Equipment ControlKnowledge of the process for controlling equipment configuration or statusG2.2.143.94.3Equipment ControlKnowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.G2.2.253.24.2Radiation ControlKnowledge of radiation monitoring systemsG2.3.152.93.1Emergency Procedures/PlansKnowledge of fire protection procedures.G2.4.253.33.7Emergency Procedures/PlansKnowledge of the emergency plan.G2.4.293.14.4Page 1 of 11:35 PM03/03/2015 ILT 1510 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Examination Level: RO Operating Test Number: 15-10 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations - 1 D,R JPM - 557 Placing an RPS Channel in Trip Conduct of Operations - 2 N,R JPM - 675 Determine The Required Action For Control Rod Withdrawal (Calculate Period) Equipment Control D,R JPM - 680 Perform Jet Pump Mismatch And Operability Radiation Control P,R JPM - 544 Review a Radiological Survey Map 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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes) (N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected) (S)imulator ILT 1510 Administrative Topics Outline Form ES-301-1 Reactor Operator Conduct of Operation 1. JPM - 557 Title: Placing an RPS Channel in Trip
Description:
Given Turbine Stop Valve #3 limit switches failed the surveillance 3-SR-3.3.1.1.14(8I) Turbine Stop Valve Closure - RPS Trip (Channel A1/A2) and RPT Trip (System A & B) Logic System Functional Test. The RO is going to determine the correct number and location of the RPS Fuses to remove to place the channel in the tripped condition. The task is completed when both fuses are identified in to 3-OI-99 Reactor Protection System. A hard copy of 3-OI-99 will be provided. K/A: 2.1.25; Ability to interpret reference materials, such as graphs, curves, tables, etc. 2. JPM - 675 Title: Determine the required action for rod pull (calculate period)
Description:
Provided initial IRM reading and a Doubling Time with a second set of IRM readings, the RO will calculate the current period and determine that it is faster than procedurally allowed and he will indicate that the rod should be reinserted. K/A: 2.1.37; Knowledge of procedures, guidelines, or limitations associated with reactivity management. Equipment Control 1. JPM - 680 Title: Perform Jet Pump Mismatch and Operability SR (Alternate Path)
Description:
Provided with Jet Pump Instrument reading and a copy of the surveillance, the RO is going to determine 2-SR-3.4.2.1, Jet Pump Mismatch and Operability is not met for Jet Pump 15. K/A: 2.2.12; Knowledge of surveillance procedures. Radiation Control 1. JPM - 544 Title: Review a Radiological Survey Map
Description:
Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM. K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions.
ILT 1501 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Examination Level: SRO Operating Test Number: 15-10 Administrative Topic (see Note) Type Code
- Describe activity to be performed Conduct of Operations M,R JPM - 678 Shift Staffing - SRO Conduct of Operations N,R JPM - 677 Fuel Handling / fuel storage, determine compliance with guidelines. Equipment Control M,R JPM - 676 Review Completed SR (SRO) Radiation Control P,R JPM - 544 Review a Radiological Survey Map Emergency Plan M,R JPM - 679 Upgrade PAR on wind shift. 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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes) (N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected) (S)imulator ILT 1501 Administrative Topics Outline Form ES-301-1 Senior Reactor Operator Conduct of Operation 1. JPM - 678 Title: Shift Staffing - SRO
Description:
Provided with a crew complement, the SRO determines if his staff meets the minimum shift requirements. The list of people appears to be below the minimum; however an SRO can be moved down to an RO position to fill the Crew Complement. The Emergency Responder position is also down one, so a callout is required. K/A: 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.
- 2. JPM - 677 Title: Fuel Handling fuel storage, determines compliance with guidelines.
Description:
Provided with Nuclear Fuel Storage physical locations and configurations, the SRO must determine if the fuel is being stored within the guidance of the procedure. In this case there are new fuel bundles stored in locations that are not allowed. K/A: 2.1.35 Knowledge of the fuel-handling responsibilities of SROs. Equipment Control 1. JPM - 676 Title: Review Completed SR (SRO)
Description:
Provided a completed SR-3.4.2.1 that the Unit Operator completed on his shift, the SRO is to review the SR for completeness and accuracy. The SR is filled out incorrectly and identified as meeting the surveillance requirements, however the surveillance requirements are not met and the SRO must identify that and determine the correct LCO. K/A: 2.2.22; Knowledge of limiting conditions for operations and safety limits Radiation Control 1. JPM - 544 Title: Review a Radiological Survey Map
Description:
Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM. K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions. Emergency Plan 1. JPM - 679 Title: Upgrade PAR on wind shift
Description:
Provided an EPIP-5 General Emergency declaration form and new information about meteorological conditions determine that the PAR needs to be adjusted to include a new sector for sheltering. That will require the SRO to fill out another form with the new information. K/A: 2.4.44; Knowledge of emergency plan protective action recommendations ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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. JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 e. JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3 f. JPM 669 EOI-Appendix-14A N2 Makeup To Primary ContainmentN,S 5 g. JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6 h. JPM 190 Respond to Off-Gas Post-Treatment Radiation HI-HI-HI (RO Only) A,M,P,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9 k. JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D 6
- 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures a. JPM 80A Title: Respond to a Control Rod Drift In. IAW AOI-85-5
Description:
While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. as he continues with the surveillance multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI-85-5, Rod Drift In. Once scram report is given the JPM will end.
K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm
Description:
The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end. K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure
Description:
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed, to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end.
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures d. JPM 257A Title: EOI Appendix-6E Injection Subsystem Lineup CS System II
Description:
The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF
(-162 in) the JPM will end.
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level
Description:
The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end. K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure
- f. JPM 669 Title: EOI-Appendix-14A N2 Makeup To Primary Containment
Description:
The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end.
K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures g. JPM 631 Title: Restore Offsite Power to 4KV shutdown board at PNL 9-23
Description:
The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end. K/A: 262001 A.C. Electrical Distribution; A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages
Description:
The BOP Operator will respond to OFF-GAS POST TREATMENT RADIATION HI-HI-HI annunciator. The operator will close FCV-66-28, OFF-GAS SYSTEM ISOLATION VALVE and then perform immediate actions of AOI-66-2, Off-gas Post-treatment Radiation Hi-Hi-Hi. The operator will reduce core flow to 50-60% and then insert a manual reactor scram. The operator will continue with subsequent actions. Once the standby Stack Dilution fan is started the JPM will end.
K/A: 271000 Offgas System: A2.16; Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of offgas system loop seals (2.9/3.2)
- i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps
Description:
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures j. JPM 674 Title: Aligning Emergency EECW Makeup To Spent Fuel Pool
Description:
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level
- k. JPM 307 Title: Start up and synchronize Unit 3 Preferred MMG Set
Description:
The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end.
K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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. JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 e. JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3 f. JPM 669 EOI-Appendix-14A N2 Makeup To Primary Containment N,S 5 g. JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9 k. JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D 6
- 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures a. JPM 80A Title: Respond to a Control Rod Drift In. IAW AOI-85-5
Description:
While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods, the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. As he continues with the surveillance, multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI-85-5, Rod Drift In. Once scram report is given the JPM will end.
K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm
Description:
The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end. K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure
Description:
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end.
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures d. JPM 257A Title: EOI Appendix-6E Injection Subsystem Lineup CS System II
Description:
The ATC Operator has been directed to in water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF
(-162 in) the JPM will end.
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level
Description:
The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end. K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure
- f. JPM 669 Title: EOI-Appendix-14A N2 Makeup To Primary Containment With
Description:
The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end.
K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures g. JPM 631 Title: Restore Offsite Power to 4KV shutdown board at PNL 9-23
Description:
The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end. K/A: 262001 A.C. Electrical Distribution A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages
- i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps
Description:
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required
Description:
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures k. JPM 307 Title: Start up and synchronize Unit 3 Preferred MMG Set
Description:
The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end.
K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9
- 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Upgrade Job Performance Measures b. JPM 276 Title: EHC Auto Cooldown
Description:
The BOP Operator will begin commence a cooldown of the reactor plant to 20psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end.
K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure
Description:
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared and rod movement has continued the JPM will end.
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5
Description:
The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF
(-162 in) the JPM will end.
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Upgrade Job Performance Measures i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps
Description:
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required
Description:
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level
ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility Date of Exam: Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
- Total A2G* Total1. Emergency & Abnormal Plant Evolutions 1 N/A N/A 18 6 2 9 4Tier Totals 27 102. Plant Systems 1 28 5 2 10 3 Tier Totals 38 8 3.Generic Knowledge and AbilitiesCategories 1 2 3 4 10 1 2 3 4 7 1.Ensure that at least two topics from every applicable K/A category are sampled within each tier of the ROand SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the ATier Totals@in each K/A category shall not be less than two). 2.The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points. 3.Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regardingthe elimination of inappropriate K/A statements. 4.Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.5.Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively. 6.Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories. 7. *The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. 8.On the following pages, enter the K/A numbers, a brief description of each topic, the topics= importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note
- 1 does not apply). Use duplicate pages for RO and SRO-only exams. 9.For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43. 334433121111455544223233232221111111121133434434433332222124372164103221532027387261233580 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4Ability to perform specific system and integrated plant procedures during all modes of plant operation.295001G2.1.234.34.4Partial or Complete Loss of AC / 6Station blackout: Plant-Specific.....................295003AK1.063.84.0Partial or Total Loss of DC Pwr / 6Battery charger.......................................295004AK2.013.13.1Main Turbine Generator Trip / 3Reactor SCRAM........................................295005AK3.013.83.8SCRAM / 1RPS...................................................295006AA1.014.24.2Control Room Abandonment / 7Reactor SCRAM.........................................295016AK3.014.14.2Partial or Total Loss of CCW / 8System loads..........................................295018AK2.013.33.4Partial or Total Loss of Inst. Air / 8Status of safety-related instrument air system loads (see AK2.1 - AK2.19)..................................295019AA2.023.63.7Loss of Shutdown Cooling / 4Reactor recirculation.................................295021AK2.073.13.2295023AA1.0Refueling Acc / 83.3.High Drywell Pressure / 5Standby gas treatment/FRVS: Plant-Specific...........295024EA1.203.53.6Page 1 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1High Reactor Pressure / 3Alternate rod insertion: Plant-Specific..............295025EK3.064.24.4Suppression Pool High Water Temp. / 5Knowledge of the purpose and function of major system components and controls.295026G2.1.284.14.1295028EA2.0High Drywell Temperature / 5Reactor 3.3.9Low Suppression Pool Wtr Lvl / 5Ability to verify that the alarms are consistent with the plant conditions.295030G2.4.464.24.2Reactor Low Water Level / 2Natural circulation: Plant-Specific..................295031EK1.023.84.1SCRAM Condition Present and Power Above APRM Downscale or Unknown
/ 1Shutdown margin.......................................295037EK1.073.43.8High Off-site Release Rate / 9Stack-gas monitoring system: Plant-Specific..........295038EA1.013.94.2Plant Fire On Site / 8Actions contained in the abnormal procedure for plant fire on site600000AK3.042.83.4Generator Voltage and Electric Grid DistrurbancecsOperational status of offsite circuit700000AA2.053.23.8Page 2 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T1G2 BWR EXAMINATION OUTLINEFORM ES-401-1Low Reactor Water Level / 2Ability to prioritize and interpret the significance of each annunciator or alarm.295009G2.4.454.14.3High Off-site Release Rate / 9Condenser air removal system: Plant-Specific.........295017AA1.063.23.2Inadvertent Cont. Isolation / 5 & 7Standby gas treatment system/FRVS: Plant-Specific....295020AK2.113.23.4295029EK2.0High Suppression Pool Wtr Lvl / 5HPC3.3.High Secondary Containment Area Temperature / 5Area temperature......................................295032EA2.013.83.8Secondary Containment Ventilation High Radiation / 9Personnel protection..................................295034EK1.013.84.1Secondary Containment High Sump/Area Water Level / 5Isolating affected systems............................295036EK3.033.53.6Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1RHR/LPCI: Injection ModeInadequate room cooling203000A2.082.93.0Shutdown CoolingMotor operated valves205000K2.022.52.7HPCIReactor pressure control: BWR-2,3,4206000K3.023.83.8LPCSAbility to execute procedure steps.209001G2.1.204.64.6SLCAbility to shutdown the reactor in certain conditions211000K3.014.34.4RPSPerform individual control rod SCRAM testing212000A4.133.43.6IRMChanging detector position215003K5.033.03.1Source Range MonitorSRM channels/detectors215004K2.012.62.8APRM / LPRMIRM/APRM recorder215005A4.013.23.1APRM / LPRMAssignment of LPRM's to specific APRM channels215005K5.062.52.6RCICPrevent water hammer: Plant-Specific217000K4.012.82.8Page 1 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1ADSKnowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.218000G2.4.302.74.1ADSNuclear boiler instrument system218000K1.033.73.8PCIS/Nuclear Steam Supply ShutoffTestability223002K4.022.72.9SRVsAir (Nitrogen) supply: Plant-Specific239002K6.023.43.5Reactor Water Level ControlTDRFP speed: TDRFP259002A1.072.62.6SGTSSuppression pool261000K1.032.93.1AC Electrical DistributionBreaker tripping262001A3.013.13.2UPS (AC/DC)Motor generator outputs262002A1.022.52.9UPS (AC/DC)Static inverter262002K6.032.72.9DC Electrical DistributionMeters, dials, recorders, alarms and indicating lights263000A3.013.23.3EDGsOpening normal and/or alternate power to emergency bus264000A2.063.43.4Page 2 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1Instrument AirContainment air system300000K3.012.72.9Instrument AirFilters300000K5.132.92.9Component Cooling WaterLoss of CCW pump400000A2.013.33.4Component Cooling WaterValves400000K6.012.72.8Page 3 of 31:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1CRD HydraulicReactor power201001A3.062.82.8Control Rod and Drive MechanismCRD drive pressure201003A1.022.82.8Recirculation Flow ControlScoop tube operation: BWR-2,3,4202002A3.033.13.0RBMInitiation point (30%): BWR-3,4,5215002K4.032.93.0Primary CTMT and Aux.Ability to prioritize and interpret the significance of each annunciator or alarm.223001G2.4.454.14.3Fuel Handling EquipmentInterlock failure234000A2.013.33.7Reactor/Turbine Pressure RegulatorTurbine inlet pressure vs. turbine load241000K5.052.82.9Main Turbine Gen. / Aux.Generator controls245000A4.023.12.9Reactor FeedwaterRFP turbine seal system: TDRFP's-Only259001K6.102.52.5RadwasteReactor building equipment drains: Plant-Specific268000K1.032.62.9Radiation MonitoringStack gas radiation monitoring system272000K2.032.52.8Page 1 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1Fire ProtectionPersonnel protection286000K3.023.23.4Page 2 of 21:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9T3 BWR EXAMINATION OUTLINEFORM ES-401-1Conduct of operationsKnowledge of conduct of operations requirements.G2.1.13.84.2Conduct of operationsAbility to execute procedure steps.G2.1.204.64.6Conduct of operationsKnowledge of how to conduct system lineups, such as valves, breakers, switches, etc.G2.1.294.14.0Equipment ControlAbility to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.G2.2.14.54.4Equipment ControlKnowledge of the process for controlling equipment configuration or statusG2.2.143.94.3Equipment ControlKnowledge of the process for conducting special or infrequent testsG2.2.72.93.6Radiation ControlKnowledge of radiation monitoring systemsG2.3.152.93.1Radiation ControlAbility to comply with radiation work permit requirements during normal or abnormal conditionsG2.3.73.53.6Emergency Procedures/PlansKnowledge of EOP entry conditions and immediate action steps.G2.4.14.64.8Emergency Procedures/PlansKnowledge of the parameters and logic used to assess the status of safety functionsG2.4.214.04.6Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T1G1 BWR EXAMINATION OUTLINEFORM ES-401-1Partial or Complete Loss of AC / 6Knowledge of the purpose and function of major system components and controls.295003G2.1.284.14.1Main Turbine Generator Trip / 3Electrical distribution status........................295005AA2.083.23.3Control Room Abandonment / 7Drywell pressure......................................295016AA2.053.83.9Partial or Total Loss of CCW / 8System pressure.......................................295018AA2.052.92.9Partial or Total Loss of Inst. Air / 8 295019AA2.03.3.High Reactor Pressure / 3Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.295025G2.4.302.74.1295031G2.1.2Reactor Low Water Level / 23.94Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T1G2 BWR EXAMINATION OUTLINEFORM ES-401-1Loss of Main Condenser Vac / 3Condenser vacuum/absolute pressure....................295002AA2.012.93.1295010AA2.0High Drywell Pressure / 5Drywell 3.3.High Secondary Containment Area Radiation Levels / 9Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.295033G2.4.474.24.2Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T2G1 BWR EXAMINATION OUTLINEFORM ES-401-1SLCAbility to use plant computer to evaluate system or component status.211000G2.1.193.93.8IRM.215003G2.2.4.SGTSLow system flow261000A2.012.93.1EDGsLoss of off-site power during full-load testing264000A2.073.53.7Component Cooling WaterHigh/low surge tank level400000A2.022.83.0Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T2G2 BWR EXAMINATION OUTLINEFORM ES-401-1CRD HydraulicValve openings201001A2.112.62.7Control Rod and Drive MechanismReactor Scram201003A2.054.14.1Traversing In-core ProbeAbility to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions215001G2.2.444.24.4Page 1 of 11:34 PM03/03/2015 NAME / SAFETY FUNCTION:K1K2K3K4K5K6A1A2A3A4GTOPIC:KAROSROIRES-401, REV 9SRO T3 BWR EXAMINATION OUTLINEFORM ES-401-1Conduct of operations.G2.1.3.Conduct of operationsKnowledge of primary and secondary chemistry limitsG2.1.342.73.5Equipment ControlKnowledge of the process for controlling equipment configuration or statusG2.2.143.94.3Equipment ControlKnowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.G2.2.253.24.2Radiation ControlKnowledge of radiation monitoring systemsG2.3.152.93.1Emergency Procedures/PlansKnowledge of fire protection procedures.G2.4.253.33.7Emergency Procedures/PlansKnowledge of the emergency plan.G2.4.293.14.4Page 1 of 11:35 PM03/03/2015 ILT 1510 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Examination Level: RO Operating Test Number: 15-10 Administrative Topic (see Note) Type Code* Describe activity to be performed Conduct of Operations - 1 D,R JPM - 557 Placing an RPS Channel in Trip Conduct of Operations - 2 N,R JPM - 675 Determine The Required Action For Control Rod Withdrawal (Calculate Period) Equipment Control D,R JPM - 680 Perform Jet Pump Mismatch And Operability Radiation Control P,R JPM - 544 Review a Radiological Survey Map 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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes) (N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected) (S)imulator ILT 1510 Administrative Topics Outline Form ES-301-1 Reactor Operator Conduct of Operation 1. JPM - 557 Title: Placing an RPS Channel in Trip
Description:
Given Turbine Stop Valve #3 limit switches failed the surveillance 3-SR-3.3.1.1.14(8I) Turbine Stop Valve Closure - RPS Trip (Channel A1/A2) and RPT Trip (System A & B) Logic System Functional Test. The RO is going to determine the correct number and location of the RPS Fuses to remove to place the channel in the tripped condition. The task is completed when both fuses are identified in to 3-OI-99 Reactor Protection System. A hard copy of 3-OI-99 will be provided. K/A: 2.1.25; Ability to interpret reference materials, such as graphs, curves, tables, etc. 2. JPM - 675 Title: Determine the required action for rod pull (calculate period)
Description:
Provided initial IRM reading and a Doubling Time with a second set of IRM readings, the RO will calculate the current period and determine that it is faster than procedurally allowed and he will indicate that the rod should be reinserted. K/A: 2.1.37; Knowledge of procedures, guidelines, or limitations associated with reactivity management. Equipment Control 1. JPM - 680 Title: Perform Jet Pump Mismatch and Operability SR (Alternate Path)
Description:
Provided with Jet Pump Instrument reading and a copy of the surveillance, the RO is going to determine 2-SR-3.4.2.1, Jet Pump Mismatch and Operability is not met for Jet Pump 15. K/A: 2.2.12; Knowledge of surveillance procedures. Radiation Control 1. JPM - 544 Title: Review a Radiological Survey Map
Description:
Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM. K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions.
ILT 1501 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Examination Level: SRO Operating Test Number: 15-10 Administrative Topic (see Note) Type Code
- Describe activity to be performed Conduct of Operations M,R JPM - 678 Shift Staffing - SRO Conduct of Operations N,R JPM - 677 Fuel Handling / fuel storage, determine compliance with guidelines. Equipment Control M,R JPM - 676 Review Completed SR (SRO) Radiation Control P,R JPM - 544 Review a Radiological Survey Map Emergency Plan M,R JPM - 679 Upgrade PAR on wind shift. 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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes) (N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected) (S)imulator ILT 1501 Administrative Topics Outline Form ES-301-1 Senior Reactor Operator Conduct of Operation 1. JPM - 678 Title: Shift Staffing - SRO
Description:
Provided with a crew complement, the SRO determines if his staff meets the minimum shift requirements. The list of people appears to be below the minimum; however an SRO can be moved down to an RO position to fill the Crew Complement. The Emergency Responder position is also down one, so a callout is required. K/A: 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.
- 2. JPM - 677 Title: Fuel Handling fuel storage, determines compliance with guidelines.
Description:
Provided with Nuclear Fuel Storage physical locations and configurations, the SRO must determine if the fuel is being stored within the guidance of the procedure. In this case there are new fuel bundles stored in locations that are not allowed. K/A: 2.1.35 Knowledge of the fuel-handling responsibilities of SROs. Equipment Control 1. JPM - 676 Title: Review Completed SR (SRO)
Description:
Provided a completed SR-3.4.2.1 that the Unit Operator completed on his shift, the SRO is to review the SR for completeness and accuracy. The SR is filled out incorrectly and identified as meeting the surveillance requirements, however the surveillance requirements are not met and the SRO must identify that and determine the correct LCO. K/A: 2.2.22; Knowledge of limiting conditions for operations and safety limits Radiation Control 1. JPM - 544 Title: Review a Radiological Survey Map
Description:
Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM. K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions. Emergency Plan 1. JPM - 679 Title: Upgrade PAR on wind shift
Description:
Provided an EPIP-5 General Emergency declaration form and new information about meteorological conditions determine that the PAR needs to be adjusted to include a new sector for sheltering. That will require the SRO to fill out another form with the new information. K/A: 2.4.44; Knowledge of emergency plan protective action recommendations ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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. JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 e. JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3 f. JPM 669 EOI-Appendix-14A N2 Makeup To Primary ContainmentN,S 5 g. JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6 h. JPM 190 Respond to Off-Gas Post-Treatment Radiation HI-HI-HI (RO Only) A,M,P,S 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9 k. JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D 6
- 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures a. JPM 80A Title: Respond to a Control Rod Drift In. IAW AOI-85-5
Description:
While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. as he continues with the surveillance multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI-85-5, Rod Drift In. Once scram report is given the JPM will end.
K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm
Description:
The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end. K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure
Description:
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed, to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end.
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures d. JPM 257A Title: EOI Appendix-6E Injection Subsystem Lineup CS System II
Description:
The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF
(-162 in) the JPM will end.
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level
Description:
The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end. K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure
- f. JPM 669 Title: EOI-Appendix-14A N2 Makeup To Primary Containment
Description:
The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end.
K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures g. JPM 631 Title: Restore Offsite Power to 4KV shutdown board at PNL 9-23
Description:
The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end. K/A: 262001 A.C. Electrical Distribution; A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages
Description:
The BOP Operator will respond to OFF-GAS POST TREATMENT RADIATION HI-HI-HI annunciator. The operator will close FCV-66-28, OFF-GAS SYSTEM ISOLATION VALVE and then perform immediate actions of AOI-66-2, Off-gas Post-treatment Radiation Hi-Hi-Hi. The operator will reduce core flow to 50-60% and then insert a manual reactor scram. The operator will continue with subsequent actions. Once the standby Stack Dilution fan is started the JPM will end.
K/A: 271000 Offgas System: A2.16; Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of offgas system loop seals (2.9/3.2)
- i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps
Description:
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator Job Performance Measures j. JPM 674 Title: Aligning Emergency EECW Makeup To Spent Fuel Pool
Description:
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level
- k. JPM 307 Title: Start up and synchronize Unit 3 Preferred MMG Set
Description:
The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end.
K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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. JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 e. JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3 f. JPM 669 EOI-Appendix-14A N2 Makeup To Primary Containment N,S 5 g. JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9 k. JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D 6
- 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures a. JPM 80A Title: Respond to a Control Rod Drift In. IAW AOI-85-5
Description:
While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods, the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. As he continues with the surveillance, multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI-85-5, Rod Drift In. Once scram report is given the JPM will end.
K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm
Description:
The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end. K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure
Description:
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end.
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures d. JPM 257A Title: EOI Appendix-6E Injection Subsystem Lineup CS System II
Description:
The ATC Operator has been directed to in water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF
(-162 in) the JPM will end.
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level
Description:
The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end. K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure
- f. JPM 669 Title: EOI-Appendix-14A N2 Makeup To Primary Containment With
Description:
The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end.
K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures g. JPM 631 Title: Restore Offsite Power to 4KV shutdown board at PNL 9-23
Description:
The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end. K/A: 262001 A.C. Electrical Distribution A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages
- i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps
Description:
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required
Description:
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Instant Job Performance Measures k. JPM 307 Title: Start up and synchronize Unit 3 Preferred MMG Set
Description:
The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end.
K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) controls including: Motor generator outputs ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 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 b. JPM 276 EHC Auto Cooldown D,L,S 4 c. JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM) A,N,S 7 d. JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8 j. JPM 674 Aligning Emergency EECW Makeup To Spent Fuel PoolE,N,R 9
- 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 Criteria for RO / SRO-I / SRO-U (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 4-6/4-6/2-3 < 9/< 8/<4 > 1/> 1/>1 >1/>1/>1 (control room system) >1/>1/>1 > 2/> 2/>1 < 3/< 3/< 2 (randomly selected) >1/>1/>1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Upgrade Job Performance Measures b. JPM 276 Title: EHC Auto Cooldown
Description:
The BOP Operator will begin commence a cooldown of the reactor plant to 20psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end.
K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure
Description:
The ATC Operator will begin raising reactor power to achieve 40% per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared and rod movement has continued the JPM will end.
K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5
Description:
The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF
(-162 in) the JPM will end.
K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Senior Reactor Operator Upgrade Job Performance Measures i. JPM 673A Title: Automatic Start Failure of A & C Fire Pumps
Description:
The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.
K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required
Description:
The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.
K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level