ES-401 PWR Examination Outline Form ES-401-2

Facility: Date of Exam:

RO KJA Category Points SRO-Only Points Tier Group

K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4 * Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal 2 1 1 2 N/A 2 1 N/A 2 9 2 2 4 Plant

Tier Totals 4 Evolutions 4 5 5 4 5 27 5 5 10

1 3 3 3 3 2 2 3 2 3 2 2 28 2 3 5 2.

Plant 2 I I I I 0 I I I I I I 10 1 0 2 3 Systems

Tier Totals 4 4 4 4 2 3 4 3 4 3 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 1 2

Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines {i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by ±1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those KIAs having an importance rating {IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.* The generic {G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings {IRs) for the applicable license level, and the point totals {#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 {Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals {#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

ES-401 2 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO I SRO)

E/APE # / Name / Safety Function K K K A A2 G K/A Topic(s) IR #1231

— —

— 007EK1 .06; Knowledge of the operational000007 (BW/E02&E1 0; CE/E02) Reactor X implications of the relationship of emergencyTrip - Stabilization - Recovery / I feedwater flow to S/C and decay heat removal

following reactor trip as it applies to the reactortrip.

OO8AK1 .01; Knowledge of the operational000008 Pressurizer Vapor Space X implications of the thermodynamics and flow 3.2Accident / 3 characteristics of open or leaking valves as

they apply to a Pressurizer Vapor SpaceAccident.

X OOBAG2.2.37; Ability to determine operability 4.6and/or availability of safety related equipment.

009EK2.03; Knowledge of the interrelations000009 Small Break LOCA / 3 X

— between the small break LOCA and the S/Cs. 30— — —

— O11EA1.14; Ability to operate and monitor the000011 Large Break LOCA / 3 X Subcooling margin monitors as they apply to a

Large Break LOCA.

000015/17 RCP Malfunctions/4 X 015AG2.4.45; Ability to prioritize and interpret 4.1the significance of each annunciator or alarm.

015AA2.10; Ability to determine and interpret 3.7

When to secure RCPs on loss of cooling orseal injection as it applies to the ReactorCoolant Pump Malfunctions (Loss of RC Flow).

000022 Loss of Rx Coolant Makeup / 2 — — — — —

025AK1 .01; Knowledge of the operational000025 Loss of RHR System 14 X implications of the loss of RHRS during all

modes of operation as it applies to Loss ofResidual Heat Removal System.

025AG2.4.45; Ability to prioritize and interpretX the significance of each annunciator or alarm. 4.1

026AK3.03; Knowledge of the reasons for the000026 Loss of Component Cooling X guidance actions contained In EOP for Loss of 4.0Water / 8 CCW as they apply to the Loss of Component

Cooling Water.—

— 027AK2.03; Knowledge of the interrelations000027 Pressurizer Pressure Control X between the Pressurizer Pressure Control 2.6System Malfunction / 3 — — — — —

— Malfunctions and Controllers and positioners.

000029 ATWS/1 — — — —

038EG2.2.38; Knowledge of conditions and000038 Steam Gen. Tube Rupture) 3 X limitations in the facility license.

BEO5EK3.2; Knowledge of the reasons for000040 (BW/E05; CE/E05; W/E12) X normal, abnormal and emergency operating 3.5Steam Line Rupture - Excessive Heat procedures associated with (Excessive HeatTransfer / 4 Transfer) as they apply to the (Excessive Heat

Transfer).

000054 (CE/E06) Loss of Main X 054AA1 .04; Ability to operate and / or monitor 4.4Feedwater / 4 HPI, under total feedwater loss conditions as it

applies to the Loss of Main Feedwater (MFW).

054AA2.03; Ability to determine and interpret

x the conditions and reasons for AFW pump 4.2startup as they apply to the Loss of MainFeedwater (MFW).

= —

— 055EA2.03; Ability to determine or interpret000055 Station Blackout / 6 X Actions necessary to restore power as they 39

apply_to_a_Station_Blackout.

056AA2.43; Ability to determine and interpret000056 Loss of Off-site Power / 6 X

the Occurrence of a turbine trip as it applies to 39

the Loss of Offsite Power.— — —

— 057AA1 .06; Ability to operate and / or monitor000057 Loss of Vital AC Inst. Bus/6 X Manual control of components forwhich

automatic control is lost as they apply to the

Loss_of Vital_AC_Instrument_Bus.—

— O5BAA2.01; Ability to determine and interpret000058 Loss of DC Power / 6 X that a loss of dc power has occurred and 4.1

verification that substitute power sources have

come on line as it applies to the Loss of DCPower.

000062 Loss of Nuclear Svc Water! 4 —

065AA2.05; Ability to determine and interpret000065 Loss of Instrument Air! 8 X when to commence plant shutdown if

instrument air pressure is decreasing as itapplies_to_the_Loss_of_Instrument Air.

W!E04 LOCA Outside Containment / 3 — —

W!E1 1 Loss of Emergency CoolantRecirc./4 — — — — — —

BW!EO4EK3.01; Knowledge of the reasons forBW!E04; W!E05 Inadequate Heat X the facility operating characteristics duringTransfer - Loss of Secondary Heat Sink! 4 transient conditions, including coolant

chemistry and the effects of temperature,

pressure, and reactivity changes and operating

limitations and reasons for these operating

characteristics as they apply to the Inadequate

Heat_Transfer.— —

— 077AK2.03; Knowledge of the interrelations000077 Generator Voltage and Electric X between Generator Voltage and Electric Grid 3.0Grid Disturbances / 6 Disturbances and sensors, detectors,

indicators.BE1OEG2.4.31; Knowledge of annunciators

BE1O Post-Trip Stabilization X alarms, indications or response procedures. 42

B/EO2EG2.2.3; (multi-unit license) KnowledgeB!E02 Vital System Status Verification X of the design, procedural, and operational 3.8

differences between units.

K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6

ES-401 3 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2Emergency and Abnorm Plant Evolubons -Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G K/A Topic(s) IR #1 231

000001 Continuous Rod Withdrawal / 1

000003 Dropped Control Rod / 1 — — — — — —

000005 Inoperable/Stuck Control Rod / 1005AA2.03; Ability to determine andinterpret the required actions if morethan one rod is stuck or inoperableas they apply to the Inoperable /Stuck Control Rod.

000024 Emergency Boration / 1

000028 Pressurizer_Level_Malfunction_/_2

000032 Loss of Source Range NI / 7032AK3.01; Knowledge of the

3.2reasons for startup termination onsource-range loss as it applies to theLoss of Source Range NuclearInstrumentation.

000033 Loss of Intermediate Range NI / 7 — — — — — —

000036 (BW/A08) Fuel Handling Accident / 8 — — — — — —

000037 Steam Generator Tube Leak / 3037AA1 .11; Ability to operate and /or monitor pressurizer levelindication as it applies to a SteamGenerator Tube Leak.

000051 Loss of Condenser Vacuum 14

000059 Accidental Liquid RadWaste Rel. / 9

000060 Accidental Gaseous Radwaste Rel. / 9 X060AG2.2.36; Ability to analyze the

3.1effect of maintenance activities, suchas degraded power sources, on thestatus of limiting conditions for

— — — —— operations.

00006 1 ARM System Alarms / 7

000067 Plant Fire On-site /8 X 067 AG2. 1.20: Ability to execute 4.6procedure steps.

000068 (BW/A06) Control Room Evac. / 8 X 068AG2.4.3: Ability to identify post- 3.9accident instrumentation.

000069 (W/E14) Loss of CTMT Integrity / 5

000074 CJV/E06&E07) Inad. Core Cooling / 4 — — — — — —

000076 High Reactor Coolant Activity / 9 076G2.3.5: Ability to use radiation2.9

monitoring systems, such as fixedradiation monitors and alarms,portable survey instruments,personnel monitoring equipment, etc.

W/EO1 & E02 Rediagnosis & SI Termination / 3

W/E1 3 Steam Generator Over-pressure / 4

W/E15 Containment Flooding / 5

W/E16 High Containment Radiation / 9

BW/A01 Plant Runback / 1BAO1AA2.1; Ability to determine andinterpret the facility conditions andselection of appropriate proceduresduring abnormal and emergencyoperations as they apply to the(Plant Runback).

BW/A02&A03 Loss of NNI-XIY / 7 X BA03AK1 .3; Knowledge of the 3.0

operational implications of

annunciators and conditions

indicating signals, and remedial

actions associated with the (NNI-Y)

— — — —— as they apply to the (Loss of NNI-Y).

BW/A04 Turbine Trip / 4BWA04A1 .92; Ability to operate

3 2and / or monitor the operating

behavior characteristics of the facility

— — — —— as they apply to the Turbine Trip.

BW/A05 Emergency Diesel Actuation /6 XBAO5AA2.l ; bilit’ to determine and

interpret facility conditions and

selection of appropriate procedures

during abnormal and emergency

operations as they apply to the

— — — —— (Emergency Diesel Actuation).

BW/A07 Flooding / 8

BW/A08 Refueling Canal Level Decrease /8

BW/E03 Inadequate Subcooling Margin /4 X BEO3EK2. 1; Knowledge of the

interrelations between the

(Inadequate Subcooling Margin) and

Components, and functions of

control and safety systems, including

instrumentation, signals, interlocks,

failure modes, and automatic and

manual features.

BW/E08; W/E03 LOCA Cooldown - Depress. / 4 BWEO8EK3.01; Knowledge of the

reasons for the facility operating

characteristics during transient

conditions, including coolant

chemistry and the effects of

temperature, pressure, and reactivity

changes and operating limitations

and reasons for these operating

characteristics as they apply to the

LOCA Cooldown.

BW/E09; CE/Al 3; W/E09&El0 Natural Circ. /4

BW/E13&E14 EOP Rules and Enclosures

CE/All; W/E08 RCS Overcooling - PTS /4

CE/Al 6 Excess RCS Leakage / 2

CE/E09 Functional Recovery

K/A Category Point Totals: 1 1 2 2 1/2 Group Point Total: 9/4

ES-401 4 Form ES-.401-2

ES-401 PWR Examination Outline Form ES-401-2—

— Dt Systems -ller2/Grqypj/ SRO) =

System # / Name K K K K K K A A2 A A G K/A Topic(s) IR #234561 34

003K5.02; Knowledge of the003 Reactor Coolant Pump X operational implications of effects of 2.8

RCP coastdown on RCS parametersas they apply to the RCPS.

003A2.02; Ability to (a) predict thex impacts of the effects of conditions 39

which exist for an abnormalshutdown of an RCP in comparisonto a normal shutdown of an RCP:and (b) based on those predictions,use procedures to correct, control, ormitigate the consequences.

— —

— 004A1 .06; Ability to predict and/or004 Chemical and Volume X monitor changes in parameters 3.0Control (to prevent exceeding design limits)

associated with operating the CVCScontrols including VCT level.

004G2.2.3; (multi-unit license)X Knowledge of the design, procedural 3.9

and operational differences betweenunits.

—

— 005K6.03; Knowledge of the effect of005 Residual Heat Removal X a loss or malfunction on the RHR 2.5

heat exchanger will have on theRHRS.

X 4.2005G2.4.47; Ability to diagnose andrecognize trends in an accurate andtimely manner utilizing theappropriate control room referencematerial.006G2.4.45; Ability to prioritize and

006 Emergency Core Cooling X interpret the significance of each 4.1

annunciator_or_alarm.007G2.2.36; Ability to analyze the

007 Pressurizer Relief/Quench X effect of maintenance activities, such 3.1Tank as degraded power sources, on the

status of limiting conditions ofoperations.

X 007K3.01; Knowledge of the effect 3.3that a loss or malfunction of thePRTS_will_have_on_containment.008A2.04; Ability to (a) predict the

008 Component Cooling Water X impacts of the PRMS alarm on theCCWS, and (b) based on thosepredictions, use procedures tocorrect, control, or mitigate theconsequences.01 0K4.03; Knowledge of PZR PCS

010 Pressurizer Pressure Control X design feature(s) and/or interlock(s) 3.8

which provide for Over pressurecontrol.

012A2.05; Ability to (a) predict theimpacts of Faulty or erratic operationof detectors and function generatorson the RPS; and (b) based on thosepredictions, use procedures tocorrect, control, or mitigate theconsequences.

012K4.09; Knowledge of RPS designfeature(s) and/or interlock(s) whichprovide for separation of control andprotection circuits.

012A2.06; Ability to (a) predict theimpacts of failure of RPS signal totrip the reactor on the RPS; and (b)basedon those predictions, use proceduresto correct, control, or mitigate theconsequences.

012 Reactor Protection

x

x

x

3.1

2.8

4.7

013A3.02; Ability to monitor013 Engineered Safety Features X automatic operation of the ESFAS 4.1Actuation including Operation of actuated

equipment.

X 3.601 3K2.01; Knowledge of bus powersupplies to ESFAS/safeguards

— — —— equipment control.

022 Containment Cooling X 022A4.04; Ability to manually 3.1operate and/or monitor in the controlroom valves in the CCS.

X 022K2.01; Knowledge of power 3.0supplies to the containment cooling

025 Ice Condenser

026 Containment Spray X automatic operation of the CSS, 3.9including verification that coolingwater is supplied to the containmentspray_heat_exchanger.

039 Main and Reheat Steam X 039A3.02; Ability to monitor 3.1automatic operation of the MRSS,including isolation of the MRSS.

039K5.08; Knowledge of the3 6X

operational implications of the effectof steam removal on reactivity as itapplies to the MRSS.059A1 .03; Ability to predict and/or

059 Main Feedwater X monitor changes in parameters 2.7(to prevent exceeding design limits)associated with operating the MFWcontrols including Power levelrestrictions for operation of MFWpumps and valves.

059K1.04; Knowledge of the physical 3.4connections and/or cause-effect

X relationships between the MFW andthe S/GS water level control system.

061 Auxiliary/Emergency X 061 K5.05, Knowledge of the 2.7Feedwater operational implications of feed line

voiding and water hammer as theyapply to the AFW.

062K1 .02; Knowledge of the physical062 AC Electrical Distribution X connections and/or cause-effect 4.1

relationships between the acdistribution system and the EDIG.063K4.01 Knowledge of DC

063 DC Electrical Distribution X electrical system design feature(s) 2.7and/or interlock(s) which provide formanual/automatic transfers ofcontrol.064K1 .04; Knowledge of the physical

064 Emergency Diesel Generator X connections and/or cause-effect 3.6relationships between the ED/Gsystem and the DC distributionsystem.073A1 .01; Ability to predict and/or

073 Process Radiation X monitor changes in parameters 3.2Monitoring (to prevent exceeding design limits)

associated with operating the ARMsystem controls including radiationlevels.

073K3.01; Knowledge of the effectX that a loss or malfunction of the ARM 3.2

system will have on the containmentventilation isolation.076K3.01; Knowledge of the effect

076 Service Water X that a loss or malfunction of the SWS 3.4will have on the closed cooling watersystem.

078 Instrument Air X 078K2.02; Knowledge of bus power 3.3supplies to the Emergency air

— — — — — — — — —— compressor. —

103 Containment X 103A4.04; Ability to manually 3.5operate and/or monitor in the controlroom phase A and phase B resets.

103G2.1 .31; Ability to locate controlX room switches, controls and

indications and to determine thatthey are correctly reflecting thedesired plant lineup.

F KJA Category Point Totals: f3 [ 2 [ 2 [ 2/2 f2 [ 2/3 f Group Point Total: [ 28/5

ES-401 5 Form ES-401-2

ES-401 PWR Examination Outline Form ES-401-2PlanL Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A2 A A G K/A Topic(s) IR #1 234561 34

001 Control Rod Drive

002 Reactor Coolant X 002G2.2.40; Ability to apply technical 4.7

— — —— specifications for a system.

011 Pressurizer Level Control

014A2.06; Ability to (a) predict the014 Rod Position Indication X impacts of the loss of LVDT on the 3.0

RPIS; and (b) based on those onthose predictions, use procedures tocorrect, control, or mitigate the

— — —— consequences. —

015 Nuclear Instrumentation X 015G2.2.12; Knowledge of 3.7surveillance procedures.

016 Non-nuclear Instrumentation X 016A3.02; Ability to monitor 2.9automatic operation of the NNIS,including relationship between meterreadings and actual parametervalue.

017 In-core Temperature Monitor — — — —

027 Containment Iodine Removal

028 Hydrogen RecombinerandPurgeControl

—

029 ContainmentPurge — — — —

033 Spent Fuel Pool Cooling — — — — —

034 Fuel Handling Equipment X 034A4.02; Ability to manually 3.5operate and/or monitor in the controlroom neutron levels.

035 Steam Generator

041 K4.1 1; Knowledge of SDS design041 Steam Dump/Turbine X feature(s) and/or interlock(s) which 2.8Bypass Control — — —

— provide for the T-aveiT-ref. program. —

045 Main Turbine Generator

055 Condenser Air Removal

056A2.04; Ability to (a) predict the056 Condensate X impacts of the loss of condensate 2.6

pumps on the Condensate System;and (b) based on those predictions,use procedures to correct, control, ormitigate_the_consequences.

068K6.10; Knowledge of the effect of068 Liquid Radwaste X a loss or malfunction on the radiation 2.5

monitors will have on the LiquidRadwaste_System.

071K3.04; Knowledge of the effect071 Waste Gas Disposal X that a loss or malfunction of the 2.7

Waste Gas Disposal System willhave on the Ventilation system.

072A1 .01; Ability to predict and/or072 Area Radiation Monitoring X monitor changes in parameters (to 3

prevent exceeding design limits)associated with operating the ARMsystem controls including radiation

. levels.

4.6072G2.4.41; Knowledge of the

X emergency action level thresholdsand classifications.

075 Circulating Water X 075K2.03; Knowledge of bus power 2.6supplies to emergency/essential

SWSpumps.

—

079K1 .01; Knowledge of the physical079 Station Air X connections and/or cause-effect 3.0

relationships between the SAS andthe lAS.

086 Fire Protection

K/A Category Point Totals: 1 [ 1 [ I 1 0 1 1 1/1 [ 1 1 1/2 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

LFacility: Date of Exam:

Category KIA# Topic RO SRO-OnIy

IR # IR

Knowledge of industrial safety procedures (such as2.1.26

rotating equipment, electrical, high temperature, high pressure,

1

caustic, chlorine, oxygen and hydrogen).

Conduct 2.1.34 Knowledge of primary and secondary chemistry limits 2.7

of Operations Knowledge of procedures, guidelines or limitations associated

with reactivity management

Ability to make accurate, clear and concise logs, records, status2.1.18 boardsandreports. 3.8

2.1.32Ability to explain and apply all system limits and precautions.

4.0

2.1.

Subtotal 3 2

2.2.13 Knowledge of tagging and clearance procedures. 4.1

2.2.12 Knowledge of surveillance procedures. 3.7

2 2 2 37Ability to determine operability and/or availability of safety related

3 6. . .

equipment.Equipment

Control 2.2.19 Knowledge of maintenance work order requirements. 3.4

Knowledge of the process for conducting special or infrequent2.2.7

tests. 3.6

2.2.7

Subtotal 3 2

2.3.11 Ability to control radiation releases. 3.8

Ability to comply with radiation work permit requirements during -

2.3.7normal or abnormal conditions.

3. .

. 2.3.15 Knowledge of radiation monitoring systems. 3.1Radiation

Control 2.3.

2.3.

2.3.

Subtotal 2 1

Knowledge of the bases for prioritizing safety functions during2.4.22

abnormal/emergency operations.3.6

Ability to recognize abnormal indications for system -

4. 2.4.4operating parameters which are entry-level conditions for

Emergency emergency and abnormal operating procedures.

Procedures I,

Knowledge of EOP entry conditions and immediate action steps.

Plan.4. i 4.8

Ability to verify system alarm setpoints and operate controls2.4.50 identified in the alarm response manual. 4.0

2.4.

2.4.

Subtotal 2 2

Tier3PointTotal 10 10 7 7

ES-301 Administrative Topics Outline Form ES-301-1

Facility: Oconee Date of Examination: 12/09/13

Examination Level: RO SRO Operating Test Number: 1

Administrative Topic (see Note)

Type Code*

Describe activity to be performed

Conduct of Operations [KA GEN 2.1.25 (3.9/4.2)] (27 min)

N,R Admin-143, Manually Calculate Core Tilt due to Loss of the OAC (RO Only)

Conduct of Operations [KA GEN 2.1.37 (4.3/4.6)] (20 min)

M, R Admin-145, Calculate Run Time for Deborating Demineralizer (Both)

Equipment Control [KA G2.2.14 (3.9/4.3)] (30 min)

M, R

Admin-212 Determine LTOP Requirements (RO Only)

Radiation Control [KA G2.3.12 (3.2/3.7)] (10 min)

D, R Admin-307, Determine Posting and Access requirements of the LPI Room Based on Plan View (Both)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (≤ 3 for ROs; ≤ 4 for SROs & RO retakes) (N)ew or (M)odified from bank (≥ 1) (P)revious 2 exams (≤ 1; randomly selected)

X

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

Facility: Oconee Date of Examination: 12/09/13 Exam Level: RO X SRO-I SRO-U Operating Test No.: 1

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. CRO-115, Withdraw Control Rod Group One to 50% OP/1/A/1105/019 (Control Rod Drive System) Encl. 4.3 (Withdrawal Of Safety Rod Group to 50%) [KA: 001 A4.06 (2.9/3.2)] (14 min)

M, L, S 1

b. CRO-223, Bypass ES Subsystem 2 OP/1/A/1105/014 Encl. 4.9 (Removal and Restoration of ES Channels) [KA: SYS 013 A4.02 (4.3/4.4)] (10 min)

D, S 2

c. CRO-404, Alignment of Condensate Recirc Unit 1 EOP Encl. 5.23 (Alignment of Condensate Recirc) [KA: APE 054 G2.1.20 (4.6/4.6)] (10 min)

D, A, S, E, L 4S

d. CRO-414, Swapping LPI Modes – High Pressure Mode to LPI Normal Decay Heat Mode

OP/1/A/1104/004, Enclosure 4.15 (Swapping LPI Modes – High Press Mode to LPI Normal Mode)

[KA: 005 A4.01 (3.6*/3.4)] (15 min)

D, L, S 4P

e. CRO-508, ES Channels 5 and 6 Recovery Unit 1 EOP Encl. 5.41 (ES Recovery) [KA: 103 A4.04 (3.5*/3.5*)] (10 min)

N, EN, L, S 5

f. CRO-606, Energize Main Feeder Buses from CT-5 Unit 1 EOP Encl. 5.38 (Restoration of Power) [KA: EPE 055 EA2.03 (3.9/4.7)] (15 min)

M, A, L, S 6

g. CRO-803, Perform Required Actions For a Turbine Building Flood AP/10 (Uncontrollable Flooding of Turbine Building) [KA: APE BW/A07 AA1.3 (3.3/3.5)] (15 min)

D, A, L, S 8

h. CRO-903, Release GWD Tank OP/1&2/A/1104/018 Encl. 4.9 (GWD Tank Release) [KA: 071 A4.26 (3.1/3.9) (20 min)

M, A, S 9

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. NLO-400, Station ASW Pump Alignment EOP Encl. 5.10 Station ASW Pump Alignment

[KA: BW/E04 EA1.1 (4.4/4.2)] (16 min) D, R, E, L 4S

j. CRO-607, Activate the SSF From the SSF Control Room AP/25 (SSF EOP) [KA: 062 A2.11 (3.7/4.1)] (12 min)

D, E, L 6

k. NLO-700, Restoration of ICS AUTO Power AP/023 (Loss of ICS Power) Encl. 5.2 (Restoration of ICS AUTO Power) [KA: BW/A02 AA1.3 (3.4/3.6)] (16 min)

D, A, E 7

@ 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 (control room system) ≥ 1 / ≥ 1 / ≥ 1 ≥ 2 / ≥ 2 / ≥ 1 ≤ 3 / ≤ 3 / ≤ 2 (randomly selected) ≥ 1 / ≥ 1 / ≥ 1

ES-301 Administrative Topics Outline Form ES-301-1

Facility: Oconee Date of Examination: 12/09/13

Examination Level: RO SRO Operating Test Number: 1

Administrative Topic (see Note)

Type Code*

Describe activity to be performed

Conduct of Operations GEN 2.1.25 (3.9/4.2) (35 min)

N,R Admin-144, Manually calculate Core Tilt due to Loss of the OAC and determine any required actions and completions times (SRO Only)

Conduct of Operations GEN 2.1.37 (4.3/4.6) (20 min)

M, R Admin-145, Calculate Run Time for Deborating Demineralizer (Both)

Equipment Control [KA G2.2.18 (2.6/3.9)] (25 min)

M, R Admin-241, Complete Plant Configuration Sheet (Time to Core Boil) (SRO Only)

Radiation Control G2.3.12 (3.2/3.7) (10 min)

D, R Admin-307, Determine Posting and Access requirements of the LPI Room Based on Plan View (Both)

Emergency Plan G2.4.38 (2.4/4.4) (20 min)

M,R Admin-413, Determine Emergency Classification and Complete the Emergency Notification Form (SRO Only)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (≤ 3 for ROs; ≤ 4 for SROs & RO retakes) (N)ew or (M)odified from bank (≥ 1) (P)revious 2 exams (≤ 1; randomly selected)

X

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

Facility: Oconee Date of Examination: 12/09/13 Exam Level: RO SRO-I SRO-U X Operating Test No.: 1

Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. N/A

b. N/A

c. N/A

d. N/A

e. CRO-508, ES Channels 5 and 6 Recovery Unit 1 EOP Encl. 5.41 (ES Recovery) [KA: 103 A4.04 (3.5*/3.5*)] (10 min)

N, EN, L, S 5

f. CRO-606, Energize Main Feeder Buses from CT-5 Unit 1 EOP Encl. 5.38 (Restoration of Power) [KA: EPE 055 EA2.03 (3.9/4.7)] (15 min)

M, A, L, S 6

g. N/A

h. CRO-903, Release GWD Tank OP/1&2/A/1104/018 Encl. 4.9 (GWD Tank Release) [KA: 071 A4.26 (3.1/3.9) (20 min)

M, A, S 9

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. NLO-400, Station ASW Pump Alignment EOP Encl. 5.10 Station ASW Pump Alignment

[KA: BW/E04 EA1.1 (4.4/4.2)] (16 min)

D, R, E, L 4S

j. N/A

k. NLO-700, Restoration of ICS AUTO Power AP/023 (Loss of ICS Power) Encl. 5.2 (Restoration of ICS AUTO Power) [KA: BW/A02 AA1.3 (3.4/3.6)] (16 min)

D, A, E 7

@ 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 (control room system) ≥ 1 / ≥ 1 / ≥ 1 ≥ 2 / ≥ 2 / ≥ 1 ≤ 3 / ≤ 3 / ≤ 2 (randomly selected) ≥ 1 / ≥ 1 / ≥ 1