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| number = ML110980756
| number = ML110980756
| issue date = 04/04/2011
| issue date = 04/04/2011
| title = Browns Ferry Initial Exam 2011-301 Draft Administrative Documents
| title = Initial Exam 2011-301 Draft Administrative Documents
| author name =  
| author name =  
| author affiliation = NRC/RGN-II/DRS/OLB
| author affiliation = NRC/RGN-II/DRS/OLB
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=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:ES-401, Rev. 9                                  BWR Examination Outline                                          Form ES-401-1 Facility:  BROWNS FERRY                            Date of Exam: February 2011 RO K/A Category Points                                  SRO-Only Points Tier            Group KKKKKKAAAAG                                                        A2          G*        Total 1    2    3  4    5  6    1    2    3    4          Total
: 1.                          343                        43                        20          3          4          7 Emergency &
Abnormal Plant 2          T E T                        1  1              1      7          1          2          3 N!A                  NIA EvolUtions                            6    4                  5  4                                              6          10 Tier Totals                                                              27 1        23233                    33221                    2      26          2          3          5
: 2.                          1    1    1    12      1    11            1    1 2                                                1                12    01              2          3 Plant Systems        Tier Totals                    4    5  4    4  3    3    2    3      38          3          5          8
: 3. Generic Knowledge and Abilities                1        2        3        4          10      1      2    3      4      7 Categories 3        3          2        2                  2      2    2      1
: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in TierS of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
: 2. The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate by +/- I from that specified in the table based on NRC revisions. The final RO exam musttotal 75 points and the SRO-only exam must total 25 points.
: 3. Systemslevolutions 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 regarding the elimination of inappropriate K/A statements.
: 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
: 5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
: 6. Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories.        -
: 7. The generic (G) K/As in Tiers I 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-oniy exams.
: 9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K1A 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.
 
ES-401, REV 9                                              T1G1 BWR EXAMINATION OUTLINE                                                        FORM ES-401-1 KA            NAME / SAFETY FUNCTION:                    IR      K1 K2 K3 K4 KS K6 Al A2 A3 A4 G    TOPIC:
Rb    SRO 295001AK102  Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 3.3  3.5      LI [] H El H    El Li [1 LI LI Power/flow distribution 295003G2.4.6  Partial or Complete Loss of AC /6      3.7    4.7 [1  Li El Li  fl H fl ü LI LI    j  Knowledge symptom based EOP mitigation strategies.
295004AA1 .03 Partial or Total Loss of DC Pwr / 6    3.4    3.6 H LI H LI El H          H H H H    AC. electrical distribution 295005AK1.0l  Main Turbine Generator Trip /3        4.0    4.1      LI LI LI LI LI LI LI LI LI fl  Pressure effects on reactor power 295006AA1.05  SCRAM/i                                4.2    4.2 LI LI LI LI LI LI [] LI Li LI LI    Neutron monitoring system 295016G2.t28  Control Room Abandonment / 7          4.1  4.1  Fl Li
                                                                .      LI LI LI LI LI LI LI LI      Knowledge of the purpose and function of major system components and controls.
295018AA2.O1  Partial or Total Loss of CCW / 8      3.3  3.4  LI LI LI LI LI LI LI        LI LI LI Component temperatures 2950 19AK3.03  Partial or Total Loss of Inst. Air / 8 3.2  3.2  Li LI i LI LI LI LI LI LI LI LI      Service air isolations: Plant-Specific 295021 AK2.O1  Loss of Shutdown Cooling / 4          3.6  3.7  LI      LI LI LI LI LI LI LI LI LI  Reactor water temperature        ..
295023AA1 03  Refuelin Acc Cooling Mode / 8          3.3  3.6  Li LI H LII Li H il H H H H          Fuel handling equipment 295024EK3.08  High Drywell Pressure / 5              3.7  4.1  LI LI ] El LI LI El Li H LI H        Containment spray: Plant-Specific Page lof2                                                      5/4/2010 2:19PM
 
ES-401, REV 9                                            T1G1 BWR EXAMINATION OUTLINE                                                    FORM ES-401-1 KA              NAME / SAFETY FUNCTION:                IR    Kl K2 K3 K4 K5 KG Al A2 A3 A4 G  TOPIC:
RO    SRO 295025EA1.04  High Reactor Pressure /3            3.8  3.9                                  HPCI: Plant-Specific
[2 LI Li [1 F] F] S1 [1 fl LI []
295026EK2.02  Suppression Pool High Water Temp. / 3.6    3.8 fl l Li LI Li Li LI LI Li [1 H    Suppression pool spray: Plant-Specific 5
295028EK1.O1  High Drywell Temperature 15        3.5    3.7    H Li Li Li L I I Li LI LI Li  Reactor water level measurement 295030G2.1 .31 Low Suppression Pool Wtr Lvi /5    4.6    4.3                                  Ability to locate control room switches, controls and Li LI LI Li Li Li LI Li Li LI    indications and to determine that they are correctly reflecting the desired plant lineup.
OI
)d 295031 EKS    Reactor Low Water Level / 2        4.4    4.7 Li H [i [2 Li LI LI LI Li Li U    Core coverage 295037EA2.06  SCRAM Condition Present and Power  4.0    4.1 Li Li LI Li H H H        H Li Li  Reactor pressure Above APRM Downscale or Unknown
                  /1 295038EK2.l0  High 0ff-site Release Rate /9      3.2    3.4 Li [I Li Li Li LI Li [2 Li Li Li  Condenser air removal system 600000AA2.13  Plant Fire On Site / 8              3.2    3.8 [U] H LI Li LI LI Li    LI U] U] Need for emergency plant shutdown 700000AK2.07  Generator Voltage and Electric Grid 3.6    3.7 LI I] LI LI LI Li 2 Li Li Li Li  Turbine / Generator control Distrurbancecs Page 2 of 2                                                5/4/2010 2:19PM
 
ES-401, REV 9                                            TIG2 BWR EXAMINATION OUTLINE                                                  FORM ES-401-1 KA            NAME I SAFETY FUNCTION:                  IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO 295002AK1.03  Loss of Main Condenser Vac /3        3.6  3.8    fl                            Loss of heat sink 29501 4G2.450 Inadvertent Reactivity Addition / 1 4.2    4.0 [ Li                            Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
295022AA1.01  Loss of CRD Pumps / 1              3.1    3.2 j]    LI LI                      CR0 hydraulic system 295029EK2.02  High Suppression Pool Wtr Lvi! 5    3.4    3.6                                  H PCI: Plant-Specific 295034EA202  Secondary Containment Ventilation High Radiation ! 9 3.7    4.2 ri    LI LI LI LI LI    LI LI LI Cause of high radiation levels 295036EK3.01  Secondary Containment High          2.6    2.8 LI F]    LI LI LI LI LI LI LI LI Emergency depressurization Sum p/Area Water Level / 5 500000EK2.09  High CTMT Hydrogen Conc. /5        3.0    3.3 LI (J LI LI LI LI LI LI LI LI LI Drywell nitrogen purge system Page loll                                                  5/4/2010 2:19PM
 
ES-401, REV 9                              T2G1 BWR EXAMINATION OUTLINE                                                      FORM ES-401-1 KA          NAME/SAFETY FUNCTION:        IR    1<1 K2 K3 K4 KS K6 Al A2 A3 A4 G    TOPIC:
RO    SRO 2030001<3.04  RHR/LPCI: Injection Mode 4.6                                            Adequate core cooling 4.6 LI LI      LI LI L] LI LI LI LI LI 205000G2.2.22 Shutdown Cooling        4.0      LI LI LI Li Li rj ri [1 LI LI        Knowledge of limiting conditions for operations and safety hmits.
206000A3.05  HPCI                    4.3  4.3 LI LI LI LI LI LI LI LI        LI LI Reactor water level: BWR-23,4 2090011<1.07  LPCS                    2.5  2.7      LI LI LI LI LI Li LI LI LI LI    D.C. electrical power 21 1000A2.07  SLC                      2.9  3.2 LI LI LI LI LI    [1  LI [ LI LI LI Valve closures 212000A4.03  RPS                      3.9  3.9 LI      LI LI LI LI LI LI LI      LI Provide manual select rod insertion: Plant-Specific.
2150031<2.01  IRM                      2.5  2.7  LI      LI LI LI LI LI LI LI LI LI    IRM channels/detectors 215004K5.01  Source Range Monitor    2.6  2.6                                        Detector operation LI LI LI LI [i LI LI Li LI LI LI kThource Range Monitor            2.82.8    Li LI r1ErILILILILI LI                Changing detector position 3.o9 215005Ael    APRM I LPRM              3.                                              Four rod display: Plant-Specific 3.5  LI LI LI LI LI [1 LI LI        LI LI 2170001<2.02  RCIC                    2.8  2.9  LI i] LI Li L. LI LI LI [1 LI LI      ROtC initiation signals (logic)
Page 1 of 3                                                  5/4/2010 2:19PM
 
ES-401, REV 9                                        T2G1 BWR EXAMINATION OUTLINE                                                  FORM ES-401-1 KA          NAME / SAFETY FUNCTION:              IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
2CY-                                  RO    SRO 217000K    RCIC                              2.7    2.8 LI    [1 H [] ri LI [] [] H fl  RCIC flow controfler 218000G2.1.7 ADS                              4.4    4.7 H LI Li Li Li Li LI [1 Li  (1 [ Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
223002K4.O2  PCIS/Nuclear Steam Supply Shutoff 2.7    2.9 Li Li H II LI LI LI LI Li LI H  Testability 223002K405  PCIS/Nuclear Steam Supply Shutoff 2.9    3.1 H H H      LI H H H H LI H    Single failures will not impair the function ability of the system 239002K1.01  SAys                              3.8          Li H H H H H Li Li Li H      Nuclear boiler 259002A1.O1  Reactor Water Level Control      3.8    3.8 H H H LI H LI l H H H H        Reactor water level 261000K4.O5SGTS                                2.6    2.8 H H H II H H H H H H H          Fission product gas removal 262001 K3.04 AC Electrical Distribution        3.1  - 3.3    FJ[7 H Li H Li H H H        Uninterruptible power supply 262002A2.02  UPS (AC/DC)                      2.5    2.7 H H H H H LI Li I] Li LI H      Over voltage 263000K6.02  DC Electrical Distribution        2.5    2.6 H H Li H H iI [I H H Li H      Battery ventilation 264000K5 05  EDGs                                        H Li H L      Li LI Li L L H  Paralleling A C power sources Page 2 of 3                                                  5/4/2010 2:19PM
 
ES-401, REV 9                              T2G1 BWR EXAMINATION OUTLINE                                              FORM ES-401-1 KA          NAME I SAFETY FUNCTION:    IR    Ki K2 K3 K4 K5 1<6 Al A2 A3 A4 G TOPIC:
7
      ,Lc7:                        RO    SRO 3OOOOO(6    Instrument Air          2.6  2.5                                  Service air refusal valve 300000K6.12  Instrument Air          2.9  2.9 flfl[1flr]L]fl[]DL1              ?Breakers, relays and disconnects 400000A1.O1  Component Cooling Water 2.8  2.8                                  CCW flow rate 400000A1.04  Component Cooling Water 2.8  2.8                                  Surge Tank Level Page 3 of 3                                              5/4/2010 2:19PM
 
ES-401, REV 9                                        T2G2 BWR EXAMINATION OUTLINE                                                FORM ES-401-1 KA            NAME I SAFETY FUNCTION:              IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO 201001 K5MS                                                                                Indications of pump runout: Plant-Specific CRD Hydraulic                    2.7  2.7 11 Li LI LI 1 LI LI LI LI LI LI 201003K1.01  Control Rod and Drive Mechanism  3.2  3.3    LI LI LI LI LI LI LI LI LI LI Control rod drive hydraulic system 215001K4.01  Traversing In-core Probe          3.4  3.5 LI LI LI 11 DDE [1 LI LI LI      Primary containment isolation: Mark-I&ll(Not-5WR1) 21900092.4.31 RHR/LPCI: Torus/Pool Cooling Mode 4.2  4.1 LI LI Li Li LI LI LIE LI Li ()    Knowledge of annunciators alarms, indications or response procedures 23C)000K2.02  RHR/LPCI: Torus/Pool Spray Mode  2.8  2.9 LI 1l LI LI LI LI LI DELI        Pumps 234000A4.02  Fuel Handling Equipment          3.4  3.7 LIE Ti LI LIE LI LI LI        LI Control rod drive sys m
                                                                                            /fV/Zt&#xe9; 259001 K5.03  Reactor Feedwater                2.8  2.8 LILILILI JLI LI LIED LI          Turbine operation: TDRFPs-Only 271000K3.02  Otfgas                                      LIELI LIE LI LiED LI              Off-site radioactive release rate 288000A3.O1  Plant Ventilation                3.83.8    LIEILILI DLI          b LILI LI  Isolation/initiation signals 290001A1.01  Secondary CTMT                    3.1  3.1 [ILl ELI LI LI (?I LI LI LI LI    Systemlineups 290002A201    Reactor Vessel Internals          3.7  4.0 Dr]LIELILIrI[uDLi                LOCA Page 1 of 2                                              5/4/2010 2:19PM
 
ES-401, REV 9                            T2G2 BWR EXAMINATION OUTLINE                                              FORM ES-401-1 KA        NAME I SAFETY FUNCTION:    IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G    TOPIC:
RO    SRO 29O0O3l4  Control Room HVAC      2.6  2.8 LI LI El El L      [1 LI LI LI El Fire protection: Plant-Specific Page2of 2                                                5/4/2010 2:19PM
 
ES-401, REV 9                                    T3 BWR EXAMINATION OUTUNE                                                      FORM ES-401-1 KA          NAME / SAFETY FUNCTION:          IR      Kl K2 K3 K4 K5 K6 Al A2 A3 A4 0 TOPIC:
RO    SRO 32.1.25    Conduct of operations        3.9  4.2  TI [1                            Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.
32.1.27    Conduct of operations        3.9    4    {    fl Li Li Li Li LI            Knowledge of system purpose and or function.
32.1.28    Conduct of operations        4.1    4.1                                    Knowledge of the purpose and function of major system TI Li    Li components and controls.
G2.2.2      Equipment Control            4.6    4.1                                    Ability to manipulate the console controls as required to Li Li Li Li Li Li LI Li Li Li operate the facility between shutdown and designated power levels.
02.2.39    Equipment Control            3.9    4.5  Li Li Li Li Li Li Li Li Li LI    Knowledge of less than one hour technical specification action statements for systems.
02.2.43    Equipment Control            3.0    3.3  Li Li Li Li Li Li Li Li Li Li    Knowledge of the process used to track inoperable alarms G2.3.13    Radiation Control            3.4    3.8  Li Li Li Li Li Li Li Li Li Li    Knowledge of radiological safety procedures pertaining to licensed operator duties G2.35      Radiation Control          2.9    2.9  H H Li Li Li Li Li Li Li Li      Ability to use radiation monitoring systems 02.4.42    Emergency Procedures/Plans  2.6  3.8        i] Li Li Li Li Li Li Li Li  Knowledge of emergency response facilities.
G2.4.47    Emergency Procedures/Plans  4.2  4.2  H F] Li Li Li Li Li Li Li Li      Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
Page 1 of 1                                                5/4/2010 2:19 PM
 
ES-401, REV 9                                      SRO T1G1 BWR EXAMINATION OUTUNE                                                  FORM ES-401-1 KA            NAME I SAFETY FUNCTION:                IR    Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO    SRO 295001AA2.02  Partial or Complete Loss of Forced 3.1 3.2 LILILILILILILI1LILILI            Neutron monitoring  .
Core Flow Circulation /1 & 4 29500502.1.32 Main Turbine Generator Trip / 3    3.8  4.0 LILILILILIL1L                  Ability to explain and apply all system limits and precautions.
29501602.1.7  Control Room Abandonment /7        4.4  4.7 LJ[iLILILILILILILILILi          Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
29502102.4.4  Loss of Shutdown Cooling / 4      4.5  4.7 LI LI LILILILILILILILI          Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
295024EA2.08  High Drywell Pressure / 5          3.6  4.0 LI LI tiLILILILILIEiE1          Drywell radiation levels 295028EA2.02  High Drywell Temperature / 5      3.8  3.9 LI El LI LI LI LI LI i LI LI LI Reactor pressure 295038G2.4.9  High Off-site Release Rate / 9    3.8  4.2 LI LI LI LI LI LI LI LI LI LI  Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.
Page 1 of                                                  5/4/2010 2:19PM
 
ES-401, REV 9                                    SRO T1G2 BWR EXAMINATION OUTLINE                                                  FORM ES-401-1 KA            NAME / SAFETY FUNCTION:              IR    Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:
RO    SRO 29501732.2.44 High Off-site Release Rate 19    4.2  4.4                            fl  Ability 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 conditions 295029324.47  High Suppression Pool Wtr Lvi! 5 4.2    4.2                            fl  Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
295032EA2.02
.            High Secondary Containment Area  3.3  3.5 [. [j      fl  [J            Equipmentoperability Temperature 15 Page 1 of 1                                                  5/4/2010 2:19PM
 
ES-401, REV 9                              SRO T2G1 BWR EXAMINATION OUTLINE                                                    FORM ES-401-1 KA          NAME! SAFETY FUNCTION:          IR    Ki 1(2 1(3 K4 K5 K6 Al A2 A3 A4 G TOPIC:
RO    SRO 203000G2.2.4 RHR/LPCI: Injection Mode    3.6    3.6 El LI LI [1 El El El El El El []  (multkinit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural
                  /                                                                  actions between untts at a facility Knowledge of the emergency action level thresholds and 25O2OX41    Reactor Water Level Control  2.9  4.6 LI LI El El El El El El El El    classifications.
261000A2.12  SGTS                        3.2  3.4 El El Li [.1 El El El 1 El El El  High fuel pool ventilation radiation: Plant-Specific.
264000A2.09  EIJGs                        3.7  4.1 r1 [1 El El El El El ] El El Li  Loss of A.C. power Ability to analyze the effect of maintenance activities, 300000G22.36 lnstrumentAir              3.1    4.2 El El El El LI Li Li Li El El 1i  such as degraded power sources, on the status of limiting conditions of operations Page 1 of 1                                                  5/4/2010 2:19PM
 
ES-401, REV 9                            SRO T2G2 BWR EXAMINATION OUTLINE                                                      FORM ES-401-1 KA            NAME / SAFETY FUNCTION:      IR    Kl 1(2 1(3 1(4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO f                J D Carryunder 202001A213    Recirculation          2.6    2.8 fl fl  j                  J  jj 204000G2.4.34  RWCU                    4.2    4.1 ri []      [] [J        [J [] []    Knowledge of RO tasks performed outside the main control room during an emergency and the resultant S                                                                                        operational effects 271 000G2.2.40 Oflgas                  3.4  4.7 flL1DThDL                            Ability to apply technical specifications for a system.
Page 1 of 1                                                    5/4/2010 2:19PM
 
ES-401, REV 9                            SRO T3 BWR EXAMINATION OUTLINE                                                    FORM ES-401-1 KA        NAME / SAFETY FUNCTION:        IR    Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G  TOPIC:
RO    SRO G2.1.3    Conduct of operations      3.7  3.9    fl [j [j  3      [] [1 F]    Knowledge of shift or short term relief turnover practices.
G2.1.4    Conduct of operations      3.3  3.8 H [1 LI LI LI LI LI LI LI        Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license statur, 10CFR55 etc.
G2.223    Equipment Control          3.1  4.6 H H LI LI LI LI LI LI LI LI      Ability to track Technical Specification limiting conditions operations.
G2.2.44    Equipment Control          4.2  4.4 [] Li LI LI LI LI LI LI LI LI    Ability 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 conditions G2.3.12    Radiation Control          3.2  3.7 Li Li LI LI LI LI LI LI LI LI    Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.7    Radiation Control          3.5  3.6 H H LI LI LI LI LI LI LI LI      Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.22    Emergency Procedures/Plans 3.6  4.4 LI LI LI Li LI Li Li LI LI LI [J Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.
Page lof 1                                                    5/4/2010 2:19PM
 
HLT 1102                      Administrative Topics Outline                      Form ES-301-1 f) /zdr Facility:  Browns Ferry NPP                Date of Examination:    2/7/2011 Examination Level:      RO                Operating Test Number:      1 102 Administrative Topic      Type                    Describe activity to be performed (see Note)        Code
* Conduct of Operations        N      2.1.7 2-SR-2 Drywell Floor and Equipment Drain Log Calculation Conduct of Operations        N      2.1.29 Determination of Verification Method for Listed Valves Equipment Control            N      2.2.41 Determination of Isolation Boundary for RFPT Seal Injection Pump2Bor3B Radiation Control            D      2.3.4 Radiation Exposure Limits under Emergency Conditions Emergency Plan 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 (D)irect from bank (< 3 for ROs; <4 for SROs and RO retakes)
(N)ew or (M)odifled from bank (> 1)
(P)revious 2 exams (< 1; randomly selected)
(S)imulator
 
HLT 1102                      Administrative Topics Outline                      Form ES-301-1 Facility:  Browns Ferry NPP                Date of Examination:    2/7/201 1 Examination Level:      SRO                Operating Test Number:      1 102 Administrative Topic      Type                    Describe activity to be performed (see Note)        Code
* Conduct of Operations        N      2.1.7 2-SR-2 Drywell Floor and Equipment Drain Log Calculation Conduct of Operations        N      2.1.29 Determination of Verification Method for Listed Valves Equipment Control            N      2.2.37 Determine the effect that a loss of sump pumps in an RHRSW room has on Operability and Maintenance Rule Availability of RHRSW and EECW Pumps Radiation Control            D      2.3.4 Radiation Exposure Limits under Emergency Conditions Emergency Plan              N      2.4.41 E-plan notification GE 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 (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
 
ES-301                        Control Roomlln-Plant Systems Outline                                  Form ES-301-2 Facility:    Browns Ferry NPP                            Date of Examination:          2/7/2011 Exam Level: RO                                          Operating Test No.:          1102 Control Room Systems0 (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)
Safety System I JPM Title                                Type Code*
Function
: a. CRD Pump Trip        <  900 psig Reactor Pressure                              A, L, N, S                1
: b. RFPT Trip Recovery                                                              L, N, S                2
: c. Alternate RPV Pressure Control Drains                                            D, L, S                4
: d. Restore RX and RF Zone Ventilation Following Isolation                        D, EN, S                5
: e. Energize 4 KV SD BDs A, C and D from Unit 3 DGs                                A, M, S                6
: f. Trip Signal Inhibited for NUMAC Rad Monitor-90-141/143                            C, D                7
: g. CAD to Drywell Control Air                                                      A, M, S                8
: h. Jumper Offgas Post Treat High Rad and Depressurize RPV                            C, L, N                9 In-Plant Systems 0 (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
: i. Removal of RPS Scram Fuses                                                        D, E                  7
: j. Stuck Open SRV                                                                A, E, N, R                3
: k. SSI Operator Manual Actions                                                      A, N, E                8
@          All RO and SRO-l 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 I SRO-l I SRO-U (A)lternate path                                                                      4-6 (5)
(C)ontrol room                                                                          (2)
(D)irect from bank                                                                    9 (4)
(E)mergency or abnormal in-plant                                                        1 (3)
(EN)gineered safety feature                                              -  I (control room system) (1)
(L)ow-Power I Shutdown                                                                > 1 (4)
(N)ew or (M)odified from bank including 1 (A)                                            2 (7)
(P)revious 2 exams                                                            3 (0) (randomly selected)
(R)CA                                                                                  > 1 (1)
(S)imulator                                                                              (6)}}

Latest revision as of 05:02, 11 March 2020

Initial Exam 2011-301 Draft Administrative Documents
ML110980756
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 04/04/2011
From:
NRC/RGN-II/DRS/OLB
To:
Tennessee Valley Authority
References
50-259/11-301, 50-260/11-301, 50-296/11-301
Download: ML110980756 (15)
v • d • e


Text

ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility: BROWNS FERRY Date of Exam: February 2011 RO K/A Category Points SRO-Only Points Tier Group KKKKKKAAAAG A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

1. 343 43 20 3 4 7 Emergency &

Abnormal Plant 2 T E T 1 1 1 7 1 2 3 N!A NIA EvolUtions 6 4 5 4 6 10 Tier Totals 27 1 23233 33221 2 26 2 3 5

2. 1 1 1 12 1 11 1 1 2 1 12 01 2 3 Plant Systems Tier Totals 4 5 4 4 3 3 2 3 38 3 5 8
3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 2 2 2 1
1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in TierS of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/- I from that specified in the table based on NRC revisions. The final RO exam musttotal 75 points and the SRO-only exam must total 25 points.

3. Systemslevolutions 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 regarding the elimination of inappropriate K/A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories. -
7. The generic (G) K/As in Tiers I 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. 1 does not apply). Use duplicate pages for RO and SRO-oniy exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K1A 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.

ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:

Rb SRO 295001AK102 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 3.3 3.5 LI [] H El H El Li [1 LI LI Power/flow distribution 295003G2.4.6 Partial or Complete Loss of AC /6 3.7 4.7 [1 Li El Li fl H fl ü LI LI j Knowledge symptom based EOP mitigation strategies.

295004AA1 .03 Partial or Total Loss of DC Pwr / 6 3.4 3.6 H LI H LI El H H H H H AC. electrical distribution 295005AK1.0l Main Turbine Generator Trip /3 4.0 4.1 LI LI LI LI LI LI LI LI LI fl Pressure effects on reactor power 295006AA1.05 SCRAM/i 4.2 4.2 LI LI LI LI LI LI [] LI Li LI LI Neutron monitoring system 295016G2.t28 Control Room Abandonment / 7 4.1 4.1 Fl Li

. LI LI LI LI LI LI LI LI Knowledge of the purpose and function of major system components and controls.

295018AA2.O1 Partial or Total Loss of CCW / 8 3.3 3.4 LI LI LI LI LI LI LI LI LI LI Component temperatures 2950 19AK3.03 Partial or Total Loss of Inst. Air / 8 3.2 3.2 Li LI i LI LI LI LI LI LI LI LI Service air isolations: Plant-Specific 295021 AK2.O1 Loss of Shutdown Cooling / 4 3.6 3.7 LI LI LI LI LI LI LI LI LI LI Reactor water temperature ..

295023AA1 03 Refuelin Acc Cooling Mode / 8 3.3 3.6 Li LI H LII Li H il H H H H Fuel handling equipment 295024EK3.08 High Drywell Pressure / 5 3.7 4.1 LI LI ] El LI LI El Li H LI H Containment spray: Plant-Specific Page lof2 5/4/2010 2:19PM

ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 KG Al A2 A3 A4 G TOPIC:

RO SRO 295025EA1.04 High Reactor Pressure /3 3.8 3.9 HPCI: Plant-Specific

[2 LI Li [1 F] F] S1 [1 fl LI []

295026EK2.02 Suppression Pool High Water Temp. / 3.6 3.8 fl l Li LI Li Li LI LI Li [1 H Suppression pool spray: Plant-Specific 5

295028EK1.O1 High Drywell Temperature 15 3.5 3.7 H Li Li Li L I I Li LI LI Li Reactor water level measurement 295030G2.1 .31 Low Suppression Pool Wtr Lvi /5 4.6 4.3 Ability to locate control room switches, controls and Li LI LI Li Li Li LI Li Li LI indications and to determine that they are correctly reflecting the desired plant lineup.

OI

)d 295031 EKS Reactor Low Water Level / 2 4.4 4.7 Li H [i [2 Li LI LI LI Li Li U Core coverage 295037EA2.06 SCRAM Condition Present and Power 4.0 4.1 Li Li LI Li H H H H Li Li Reactor pressure Above APRM Downscale or Unknown

/1 295038EK2.l0 High 0ff-site Release Rate /9 3.2 3.4 Li [I Li Li Li LI Li [2 Li Li Li Condenser air removal system 600000AA2.13 Plant Fire On Site / 8 3.2 3.8 [U] H LI Li LI LI Li LI U] U] Need for emergency plant shutdown 700000AK2.07 Generator Voltage and Electric Grid 3.6 3.7 LI I] LI LI LI Li 2 Li Li Li Li Turbine / Generator control Distrurbancecs Page 2 of 2 5/4/2010 2:19PM

ES-401, REV 9 TIG2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295002AK1.03 Loss of Main Condenser Vac /3 3.6 3.8 fl Loss of heat sink 29501 4G2.450 Inadvertent Reactivity Addition / 1 4.2 4.0 [ Li Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

295022AA1.01 Loss of CRD Pumps / 1 3.1 3.2 j] LI LI CR0 hydraulic system 295029EK2.02 High Suppression Pool Wtr Lvi! 5 3.4 3.6 H PCI: Plant-Specific 295034EA202 Secondary Containment Ventilation High Radiation ! 9 3.7 4.2 ri LI LI LI LI LI LI LI LI Cause of high radiation levels 295036EK3.01 Secondary Containment High 2.6 2.8 LI F] LI LI LI LI LI LI LI LI Emergency depressurization Sum p/Area Water Level / 5 500000EK2.09 High CTMT Hydrogen Conc. /5 3.0 3.3 LI (J LI LI LI LI LI LI LI LI LI Drywell nitrogen purge system Page loll 5/4/2010 2:19PM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME/SAFETY FUNCTION: IR 1<1 K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:

RO SRO 2030001<3.04 RHR/LPCI: Injection Mode 4.6 Adequate core cooling 4.6 LI LI LI LI L] LI LI LI LI LI 205000G2.2.22 Shutdown Cooling 4.0 LI LI LI Li Li rj ri [1 LI LI Knowledge of limiting conditions for operations and safety hmits.

206000A3.05 HPCI 4.3 4.3 LI LI LI LI LI LI LI LI LI LI Reactor water level: BWR-23,4 2090011<1.07 LPCS 2.5 2.7 LI LI LI LI LI Li LI LI LI LI D.C. electrical power 21 1000A2.07 SLC 2.9 3.2 LI LI LI LI LI [1 LI [ LI LI LI Valve closures 212000A4.03 RPS 3.9 3.9 LI LI LI LI LI LI LI LI LI Provide manual select rod insertion: Plant-Specific.

2150031<2.01 IRM 2.5 2.7 LI LI LI LI LI LI LI LI LI LI IRM channels/detectors 215004K5.01 Source Range Monitor 2.6 2.6 Detector operation LI LI LI LI [i LI LI Li LI LI LI kThource Range Monitor 2.82.8 Li LI r1ErILILILILI LI Changing detector position 3.o9 215005Ael APRM I LPRM 3. Four rod display: Plant-Specific 3.5 LI LI LI LI LI [1 LI LI LI LI 2170001<2.02 RCIC 2.8 2.9 LI i] LI Li L. LI LI LI [1 LI LI ROtC initiation signals (logic)

Page 1 of 3 5/4/2010 2:19PM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

2CY- RO SRO 217000K RCIC 2.7 2.8 LI [1 H [] ri LI [] [] H fl RCIC flow controfler 218000G2.1.7 ADS 4.4 4.7 H LI Li Li Li Li LI [1 Li (1 [ Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

223002K4.O2 PCIS/Nuclear Steam Supply Shutoff 2.7 2.9 Li Li H II LI LI LI LI Li LI H Testability 223002K405 PCIS/Nuclear Steam Supply Shutoff 2.9 3.1 H H H LI H H H H LI H Single failures will not impair the function ability of the system 239002K1.01 SAys 3.8 Li H H H H H Li Li Li H Nuclear boiler 259002A1.O1 Reactor Water Level Control 3.8 3.8 H H H LI H LI l H H H H Reactor water level 261000K4.O5SGTS 2.6 2.8 H H H II H H H H H H H Fission product gas removal 262001 K3.04 AC Electrical Distribution 3.1 - 3.3 FJ[7 H Li H Li H H H Uninterruptible power supply 262002A2.02 UPS (AC/DC) 2.5 2.7 H H H H H LI Li I] Li LI H Over voltage 263000K6.02 DC Electrical Distribution 2.5 2.6 H H Li H H iI [I H H Li H Battery ventilation 264000K5 05 EDGs H Li H L Li LI Li L L H Paralleling A C power sources Page 2 of 3 5/4/2010 2:19PM

ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 1<6 Al A2 A3 A4 G TOPIC:

7

,Lc7: RO SRO 3OOOOO(6 Instrument Air 2.6 2.5 Service air refusal valve 300000K6.12 Instrument Air 2.9 2.9 flfl[1flr]L]fl[]DL1 ?Breakers, relays and disconnects 400000A1.O1 Component Cooling Water 2.8 2.8 CCW flow rate 400000A1.04 Component Cooling Water 2.8 2.8 Surge Tank Level Page 3 of 3 5/4/2010 2:19PM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 201001 K5MS Indications of pump runout: Plant-Specific CRD Hydraulic 2.7 2.7 11 Li LI LI 1 LI LI LI LI LI LI 201003K1.01 Control Rod and Drive Mechanism 3.2 3.3 LI LI LI LI LI LI LI LI LI LI Control rod drive hydraulic system 215001K4.01 Traversing In-core Probe 3.4 3.5 LI LI LI 11 DDE [1 LI LI LI Primary containment isolation: Mark-I&ll(Not-5WR1) 21900092.4.31 RHR/LPCI: Torus/Pool Cooling Mode 4.2 4.1 LI LI Li Li LI LI LIE LI Li () Knowledge of annunciators alarms, indications or response procedures 23C)000K2.02 RHR/LPCI: Torus/Pool Spray Mode 2.8 2.9 LI 1l LI LI LI LI LI DELI Pumps 234000A4.02 Fuel Handling Equipment 3.4 3.7 LIE Ti LI LIE LI LI LI LI Control rod drive sys m

/fV/Zté 259001 K5.03 Reactor Feedwater 2.8 2.8 LILILILI JLI LI LIED LI Turbine operation: TDRFPs-Only 271000K3.02 Otfgas LIELI LIE LI LiED LI Off-site radioactive release rate 288000A3.O1 Plant Ventilation 3.83.8 LIEILILI DLI b LILI LI Isolation/initiation signals 290001A1.01 Secondary CTMT 3.1 3.1 [ILl ELI LI LI (?I LI LI LI LI Systemlineups 290002A201 Reactor Vessel Internals 3.7 4.0 Dr]LIELILIrI[uDLi LOCA Page 1 of 2 5/4/2010 2:19PM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 29O0O3l4 Control Room HVAC 2.6 2.8 LI LI El El L [1 LI LI LI El Fire protection: Plant-Specific Page2of 2 5/4/2010 2:19PM

ES-401, REV 9 T3 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 0 TOPIC:

RO SRO 32.1.25 Conduct of operations 3.9 4.2 TI [1 Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

32.1.27 Conduct of operations 3.9 4 { fl Li Li Li Li LI Knowledge of system purpose and or function.

32.1.28 Conduct of operations 4.1 4.1 Knowledge of the purpose and function of major system TI Li Li components and controls.

G2.2.2 Equipment Control 4.6 4.1 Ability to manipulate the console controls as required to Li Li Li Li Li Li LI Li Li Li operate the facility between shutdown and designated power levels.

02.2.39 Equipment Control 3.9 4.5 Li Li Li Li Li Li Li Li Li LI Knowledge of less than one hour technical specification action statements for systems.

02.2.43 Equipment Control 3.0 3.3 Li Li Li Li Li Li Li Li Li Li Knowledge of the process used to track inoperable alarms G2.3.13 Radiation Control 3.4 3.8 Li Li Li Li Li Li Li Li Li Li Knowledge of radiological safety procedures pertaining to licensed operator duties G2.35 Radiation Control 2.9 2.9 H H Li Li Li Li Li Li Li Li Ability to use radiation monitoring systems 02.4.42 Emergency Procedures/Plans 2.6 3.8 i] Li Li Li Li Li Li Li Li Knowledge of emergency response facilities.

G2.4.47 Emergency Procedures/Plans 4.2 4.2 H F] Li Li Li Li Li Li Li Li Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

Page 1 of 1 5/4/2010 2:19 PM

ES-401, REV 9 SRO T1G1 BWR EXAMINATION OUTUNE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295001AA2.02 Partial or Complete Loss of Forced 3.1 3.2 LILILILILILILI1LILILI Neutron monitoring .

Core Flow Circulation /1 & 4 29500502.1.32 Main Turbine Generator Trip / 3 3.8 4.0 LILILILILIL1L Ability to explain and apply all system limits and precautions.

29501602.1.7 Control Room Abandonment /7 4.4 4.7 LJ[iLILILILILILILILILi Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

29502102.4.4 Loss of Shutdown Cooling / 4 4.5 4.7 LI LI LILILILILILILILI Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

295024EA2.08 High Drywell Pressure / 5 3.6 4.0 LI LI tiLILILILILIEiE1 Drywell radiation levels 295028EA2.02 High Drywell Temperature / 5 3.8 3.9 LI El LI LI LI LI LI i LI LI LI Reactor pressure 295038G2.4.9 High Off-site Release Rate / 9 3.8 4.2 LI LI LI LI LI LI LI LI LI LI Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

Page 1 of 5/4/2010 2:19PM

ES-401, REV 9 SRO T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 KS K6 Al A2 A3 A4 G TOPIC:

RO SRO 29501732.2.44 High Off-site Release Rate 19 4.2 4.4 fl Ability 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 conditions 295029324.47 High Suppression Pool Wtr Lvi! 5 4.2 4.2 fl Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

295032EA2.02

. High Secondary Containment Area 3.3 3.5 [. [j fl [J Equipmentoperability Temperature 15 Page 1 of 1 5/4/2010 2:19PM

ES-401, REV 9 SRO T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION: IR Ki 1(2 1(3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 203000G2.2.4 RHR/LPCI: Injection Mode 3.6 3.6 El LI LI [1 El El El El El El [] (multkinit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural

/ actions between untts at a facility Knowledge of the emergency action level thresholds and 25O2OX41 Reactor Water Level Control 2.9 4.6 LI LI El El El El El El El El classifications.

261000A2.12 SGTS 3.2 3.4 El El Li [.1 El El El 1 El El El High fuel pool ventilation radiation: Plant-Specific.

264000A2.09 EIJGs 3.7 4.1 r1 [1 El El El El El ] El El Li Loss of A.C. power Ability to analyze the effect of maintenance activities, 300000G22.36 lnstrumentAir 3.1 4.2 El El El El LI Li Li Li El El 1i such as degraded power sources, on the status of limiting conditions of operations Page 1 of 1 5/4/2010 2:19PM

ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Kl 1(2 1(3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO f J D Carryunder 202001A213 Recirculation 2.6 2.8 fl fl j J jj 204000G2.4.34 RWCU 4.2 4.1 ri [] [] [J [J [] [] Knowledge of RO tasks performed outside the main control room during an emergency and the resultant S operational effects 271 000G2.2.40 Oflgas 3.4 4.7 flL1DThDL Ability to apply technical specifications for a system.

Page 1 of 1 5/4/2010 2:19PM

ES-401, REV 9 SRO T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1.3 Conduct of operations 3.7 3.9 fl [j [j 3 [] [1 F] Knowledge of shift or short term relief turnover practices.

G2.1.4 Conduct of operations 3.3 3.8 H [1 LI LI LI LI LI LI LI Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license statur, 10CFR55 etc.

G2.223 Equipment Control 3.1 4.6 H H LI LI LI LI LI LI LI LI Ability to track Technical Specification limiting conditions operations.

G2.2.44 Equipment Control 4.2 4.4 [] Li LI LI LI LI LI LI LI LI Ability 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 conditions G2.3.12 Radiation Control 3.2 3.7 Li Li LI LI LI LI LI LI LI LI Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.7 Radiation Control 3.5 3.6 H H LI LI LI LI LI LI LI LI Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.22 Emergency Procedures/Plans 3.6 4.4 LI LI LI Li LI Li Li LI LI LI [J Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

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HLT 1102 Administrative Topics Outline Form ES-301-1 f) /zdr Facility: Browns Ferry NPP Date of Examination: 2/7/2011 Examination Level: RO Operating Test Number: 1 102 Administrative Topic Type Describe activity to be performed (see Note) Code

  • Conduct of Operations N 2.1.7 2-SR-2 Drywell Floor and Equipment Drain Log Calculation Conduct of Operations N 2.1.29 Determination of Verification Method for Listed Valves Equipment Control N 2.2.41 Determination of Isolation Boundary for RFPT Seal Injection Pump2Bor3B Radiation Control D 2.3.4 Radiation Exposure Limits under Emergency Conditions Emergency Plan 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 (D)irect from bank (< 3 for ROs; <4 for SROs and RO retakes)

(N)ew or (M)odifled from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

(S)imulator

HLT 1102 Administrative Topics Outline Form ES-301-1 Facility: Browns Ferry NPP Date of Examination: 2/7/201 1 Examination Level: SRO Operating Test Number: 1 102 Administrative Topic Type Describe activity to be performed (see Note) Code

  • Conduct of Operations N 2.1.7 2-SR-2 Drywell Floor and Equipment Drain Log Calculation Conduct of Operations N 2.1.29 Determination of Verification Method for Listed Valves Equipment Control N 2.2.37 Determine the effect that a loss of sump pumps in an RHRSW room has on Operability and Maintenance Rule Availability of RHRSW and EECW Pumps Radiation Control D 2.3.4 Radiation Exposure Limits under Emergency Conditions Emergency Plan N 2.4.41 E-plan notification GE 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 (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

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Browns Ferry NPP Date of Examination: 2/7/2011 Exam Level: RO Operating Test No.: 1102 Control Room Systems0 (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

Safety System I JPM Title Type Code*

Function

a. CRD Pump Trip < 900 psig Reactor Pressure A, L, N, S 1
b. RFPT Trip Recovery L, N, S 2
c. Alternate RPV Pressure Control Drains D, L, S 4
d. Restore RX and RF Zone Ventilation Following Isolation D, EN, S 5
e. Energize 4 KV SD BDs A, C and D from Unit 3 DGs A, M, S 6
f. Trip Signal Inhibited for NUMAC Rad Monitor-90-141/143 C, D 7
g. CAD to Drywell Control Air A, M, S 8
h. Jumper Offgas Post Treat High Rad and Depressurize RPV C, L, N 9 In-Plant Systems 0 (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)
i. Removal of RPS Scram Fuses D, E 7
j. Stuck Open SRV A, E, N, R 3
k. SSI Operator Manual Actions A, N, E 8

@ All RO and SRO-l 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 I SRO-l I SRO-U (A)lternate path 4-6 (5)

(C)ontrol room (2)

(D)irect from bank 9 (4)

(E)mergency or abnormal in-plant 1 (3)

(EN)gineered safety feature - I (control room system) (1)

(L)ow-Power I Shutdown > 1 (4)

(N)ew or (M)odified from bank including 1 (A) 2 (7)

(P)revious 2 exams 3 (0) (randomly selected)

(R)CA > 1 (1)

(S)imulator (6)

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