ML17261B167

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Draft - Outlines (Folder 2)
ML17261B167
Person / Time
Site: Oyster Creek
Issue date: 02/10/2016
From: Brian Fuller
Operations Branch I
To:
Exelon Generation Co
Shared Package
ML15219A259 List:
References
TAC U01929
Download: ML17261B167 (26)
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ES-401 Written Examination Outline Form ES-401-1 Oyster Creek Initial NRC Facility: Date of Exam: 02/01/16 Exam Juflt2o/"'

RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 3 4 4 3 3 3 20 4 3 7 Emergency

& 2 2 1 1 1 1 1 7 1 2 3 Plant Tier Evolutions 5 5 5 4 4 4 27 5 5 IO Totals 1 3 2 3 2 2 3 2 3 2 2 2 26 3 2 5 2.

Plant 2 1 1 1 1 1 1 1 2 1 1 1 12 0 1 2 3 Systems Tier 4 3 4 3 3 4 3 5 3 3 3 38 4 4 8 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge & Abilities IO 7 Categories 2 3 3 2 1 2 2 2 Note: 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 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 that are not included on the outline should be added. Refer to section D. l.b of ES-401, for guidance regarding elimination of inappropriate Kl 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 KAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1and2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D. l .b of ES-401 for the applicable K/A's

8. On the following pages, enter the Kl A numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals(#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note
  1. 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 10CFR55.43

ES-401 2 Form ES-401-1 Oyster Creek Initial NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

EA2.03 - Ability to determine and/or 295031 Reactor Low Water Level I interpret the following as they apply to 2

x REACTOR LOW WATER LEVEL :

4.2 76 Reactor pressure EA2.04 - Ability to determine and/or 295028 High Drywell Temperature interpret the following as they apply to 15 x HIGH DRYWELL TEMPERATURE:

4.2 77 Drvwell pressure EA2.02 - Ability to determine and/or interpret the following as they apply to 295037 SCRAM Conditions SCRAM CONDITION PRESENT AND Present and Reactor Power Above x REACTOR POWER ABOVE APRM 4.2 78 APRM Downscale or Unknown I 1 DOWNSCALE OR UNKNOWN : Reactor water level 2.1.25 - Conduct of Operations: Ability to 295038 High Off-site Release Rate 19 x interpret reference materials, such as graphs, 4.2 79 curves, tables, etc.

2.4.31 - Emergency Procedures I Plan:

295006 SCRAM I 1 x Knowledge of annunciator alarms, 4.1 80 indications, or response procedures.

2.1.32 - Conduct of Operations: Ability to 29502 l Loss of Shutdown Cooling

/4 x explain and apply all system limits and 4.0 81 precautions.

EA2.0l - Ability to determine and/or interpret the following as they apply to 295026 Suppression Pool High Water Temp. I 5 x SUPPRESSION POOL HIGH WATER 4.2 82 TEMPERATURE: Suppression pool water temperature AKl.01 - Knowledge of the operational implications of the following concepts as 295018 Partial or Total Loss of they apply to PARTIAL OR COMPLETE CCW/8 x LOSS OF COMPONENT COOLING 3.5 39 WATER : Effects on component/system operations EKl .01 - Knowledge of the operational 295026 Suppression Pool High implications of the following concepts as Water Temp. I 5 x they apply to SUPPRESSION POOL HIGH 3.0 40 WATER TEMPERATURE: PumpNPSH AKl.06 - Knowledge of the operational implications of the following concepts as 295003 Partial or Complete Loss of AC 16 x they apply to PARTIAL OR COMPLETE 3.8 41 LOSS OF A.C. POWER : Station Blackout:

Plant Specific EK2. l 1 - Knowledge of the interrelations 295031 Reactor Low Water Level 12 x between REACTOR LOW WATER LEVEL 4.4 42 and the following: Reactor protection svstem EK2.03 - Knowledge of the interrelations 295028 High Drywell between HIGH DRYWELL Temperature I 5 x TEMPERATURE and the following:

3.6 43 Reactor water level indication EK2.01 - Knowledge of the interrelations 295025 High Reactor Pressure I 3 x between HIGH REACTOR PRESSURE 4.1 44 and the followino: RPS AK3.03 - Knowledge of the reasons for the following responses as they apply to 295019 Partial or Total Loss of Inst. Air I 8 x PARTIAL OR COMPLETE LOSS OF 3.2 45 INSTRUMENT AIR : Service air isolations: Plant-Soecific 295023 Refueling Ace Cooling AK3.03 - Knowledge of the reasons for Mode/ 8 x the followina responses as they apply to 3.3 46

ES-401 2 Form ES-401-1 Oyster Creek Initial NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1

  1. I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

REFUELING ACCIDENTS: Ventilation Isolation AK3.04 - Knowledge of the reasons for the following responses as they apply to 600000 Plant Fire On-site I 8 x PLANT FIRE ON SITE: Actions 2.8 47 contained in the abnormal procedure for olant fire on site AA 1.01 - Ability to operate and/or monitor the following as they apply to 295004 Partial or Total Loss of DCPwr/6 x PARTIAL OR COMPLETE LOSS OF 3.3 48 D.C. POWER: D.C. electrical distribution svstems AA 1.04 - Ability to operate and/or 295021 Loss of Shutdown Cooling monitor the following as they apply to

/4 x LOSS OF SHUTDOWN COOLING :

3.7 49 Alternate heat removal methods AA 1.04 - Ability to operate and/or 295006 SCRAM I 1 x monitor the following as they apply to 3.1 50 SCRAM : Recirculation svstem AA2.01 - Ability to determine and/or 295005 Main Turbine Generator interpret the following as they apply to Trip/3 x MAIN TURBINE GENERATOR TRIP:

2.6 51 Turbine speed EA2.07 - Ability to determine and/or interpret the following as they apply to 295037 SCRAM Conditions SCRAM CONDITION PRESENT AND Present and Reactor Power Above x REACTOR POWER ABOVE APRM 4.0 52 APRM Downscale or Unknown I 1 DOWNSCALE OR UNKNOWN :

Containment conditions/isolations AA2.05 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and Electric Grid Disturbances x GENERATOR VOLTAGE AND 3.2 53 ELECTRIC GRID DISTURBANCES:

Operational status of offsite circuit.

295030 Low Suppression Pool 2.4.6 - Emergency Procedures I Plan:

Water Level I 5 x Knowledoe of EOP mitigation strateqies.

3.7 54 2.2.37 - Equipment Control: Ability to 295024 High Drywell Pressure I 5 x determine operability and/or availability 3.6 55 of safety related eauipment 2.4.11 - Emergency Procedures I Plan:

295016 Control Room Abandonment I 7 x Knowledge of abnormal condition 4.0 56 procedures.

EK2.03 - Knowledge of the interrelations 295038 High Off-site Release Rate between HIGH OFF-SITE RELEASE 19 x RATE and the following: Plant 3.6 57 ventilation systems AK3.05 - Knowledge of the reasons for the following responses as they apply to 29500 I Partial or Complete Loss PARTIAL OR COMPLETE LOSS OF of Forced Core Flow Circulation I x FORCED CORE FLOW CIRCULATION 3.2 58 1&4

Reduced loop operating requirements:

Plant-Specific KJA Category Totals: 3 4 4 3 3/4 3/3 Group Point Total:

I 2017

ES-401 3 Form ES-401-1 Oyster Creek Initial NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE #I Name Safety Function K1 K2 K3 A1 A2 G KIA Topic(s) Imp. Q#

EA2.04 - Ability to determine and I or interpret the following as they apply to 500000 High CTMT Hydrogen Cone. I 5 x HIGH PRIMARY CONTAINMENT 3.3 83 HYDROGEN CONCENTRATIONS:

Combustible limits for wetwell 2.2.42 - Equipment Control: Ability to 295029 High Suppression Pool recognize system parameters that are entry-Water Level I 5 x level conditions for Technical 4.6 84 SnPCifications.

2.2.37 - Equipment Control: Ability to 295022 Loss of CRD Pumps I 1 x detem1ine operability and I or availability of 4.6 85 safety related eauioment.

EKl.02 - Knowledge of the operational 295033 High Secondary implications of the following concepts as 3.

Containment Area Radiation x they apply to HIGH SECONDARY 9

59 Levels I 9 CONTAINMENT AREA RADIATION LEVELS : Personnel protection EK2.01 - Knowledge of the interrelations between SECONDARY CONTAINMENT 295035 Secondary Containment 3.6 High Differential Pressure I 5 x HIGH DIFFERENTIAL PRESSURE and 60 the following: Secondary containment ventilation AK3.04 - Knowledge of the reasons for the 295002 Loss of Main Condenser following responses as they apply to LOSS 3.

Vac I 3 x OF MAIN CONDENSER VACUUM : 4 61 Bypass valve closure AAl.02 - Ability to operate and/or monitor the following as they apply to HIGH 3.

295010 High Drywell Pressure I 5 x DRYWELL PRESSURE: Drywell t1oor and 6 62 equipment drain sumps AA2.03 - Ability to determine and/or 295020 Inadvertent Cont. interpret the following as they apply to 3.

Isolation I 5 & 7 x INADVERTENT CONTAINMENT 7 63 ISOLATION : Reactor power 2.4.45 - Emergency Procedures I Plan:

295034 Secondary Containment 4.

Ventilation High Radiation I 9 x Ability to prioritize and interpret the I

64 significance of each annunciator or alarm.

EKI .01 - Knowledge of the operational 295029 High Suppression Pool implications of the following concepts as 3.

Water Level I 5 x they apply to HIGH SUPPRESSION POOL 4 65 WATER LEVEL : Containment integrity KIA Category Totals: 2 1 1 1 1/1 1/2 Group Point Total:

I 713

ES-401 4 Form ES-401-1 Oyster Creek Initial NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System# I Name A2 G Q#

1 2 3 4 5 6 1 3 4 A2.02 - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those 400000 Component Cooling predictions, use procedures to Water x correct, control, or mitigate the 3.0 86 consequences of those abnormal operation: High/low surge tank level A2.0I - Ability to (a) predict the impacts of the following on the INS1RUMENT AIR SYSTEM and (b) based on those predictions. use 3CXJOOO Instrument Air x procedures to correct. control. or 2.8 87 mitigate the consequences of those abnormal operation: Air dryer and filter malfunctions 2.2.38 - F4uipment Control:

209001 LPCS x Knowledge of conditions and 4.5 88 limitations in the facilitv license.

2.4.41 - Emergency Procedures I Plan: Knowledge of the emergency 205000 Shutdown Cooling x action level thresholds and 4.6 89 classifications.

A2.03 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETY VALYES ; and (b) based on those predictions, use 239002 SRVs x procedures to correct, control, or 4.2 90 mitigate the consequences of those abnormal conditions or operations:

Stuck open SRV Kl.04 - Knowledge of the physical connections and/or cause- effect relationships between 264000EDGs x EMERGENCY GENERATORS 3.2 I (DIESEUJET) and the following:

Emergency generator cooling water system K1 .01 - Knowledge of the physical connections and/or 259002 Reactor Water Level cause- effect relationships Control x between REACTOR WATER 3.8 2 LEVEL CONTROL SYSTEM and the followinq: RPS K2.01 - Knowledge of electrical 207000 Isolation (Emergency) power supplies to the following:

Condenser x Motor operated valves: BWR-3.6 3 2,3 K2.01 - Knowledge of electrical 300000 Instrument Air x power supplies to the following: 2.8 4 Instrument air compressor K3.02 - Knowledge of the effect that a loss or malfunction of the D.C. ELECTRICAL 263000 DC Electrical Distribution x DISTRIBUTION will have on 3.5 5 following: Components using D.C. control power (i.e.

breakers)

ES-401 4 Form ES-401-1 Oyster Creek Initial NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G Q#

1 2 3 4 5 6 1 3 4 K3.03 - Knowledge of the effect that a loss or malfunction of the REACTOR PROTECTION 212000RPS x SYSTEM will have on following:

3.3 6 Local power range monitoring system: Plant-Specific K4.01 - Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design 262002 UPS (AC/DC) x feature(s) and/or interlocks 3.1 7 which provide for the following:

Transfer from preferred power to alternate oower suoolies K4.06 - Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM 215005 APRM I LPRM x design feature(s) and/or 2.6 8 interlocks which provide for the following: Effects of detector aqinq on LPRM/APRM readinqs K5.05 - Knowledge of the operational implications of the following concepts as they apply 239002 SRVs x to RELIEF/SAFETY VALVES:

2.6 9 Discharge line quencher operation K5.01 - Knowledge of the operational implications of the following concepts as they apply to STANDBY LIQUID 211000 SLC x CONTROL SYSTEM : Effects of 2.7 10 the moderator temperature coefficient of reactivity on the boron K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the 215003 IRM x INTERMEDIATE RANGE 3.0 11 MONITOR (IRM) SYSTEM:

Detectors K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the 261000 SGTS x STANDBY GAS TREATMENT 2.9 12 SYSTEM : Process radiation monitorina A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 218000ADS x AUTOMATIC 3.4 13 DEPRESSURIZATION SYSTEM controls including: ADS valve tail pipe temperatures

ES-401 4 Form ES-401-1 Oyster Creek Initial NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System #I Name A2 G Q#

1 2 3 4 5 6 1 3 4 A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT 223002 PCIS/Nuclear Steam Supply Shutoff x ISOLATION 3.5 14 SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including: System indicating lights and alarms A2.11 - Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION ; and (b) based 262001 AC Electrical on those predictions, use Distribution x procedures to correct, control, or 3.2 15 mitigate the consequences of those abnormal conditions or operations: Degraded system voltaoes A2.11 - Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) 205000 Shutdown Cooling x based on those predictions, use 2.5 16 procedures to correct, control, or mitigate the consequences of those abnormal conditions Recirculation pump trips: Plant-Specific A3.04 - Ability to monitor automatic operations of the 209001 LPCS x LOW PRESSURE CORE 3.7 17 SPRAY SYSTEM including:

Svstem flow A3.04 - Ability to monitor automatic operations of the 215004 Source Range Monitor x SOURCE RANGE MONITOR 3.6 18 (SRM) SYSTEM including:

Control rod block status A4.01 - Ability to manually 400000 Component Cooling operate and/or monitor in the Water x control room: CCW indications 3.1 19 and control A4.03 - Ability to manually 263000 DC Electrical operate and/or monitor in the Distribution x control room: Battery discharge 2.7 20 rate: Plant-Specific 2.4.9 - Emergency Procedures I Plan: Knowledge of low power I 205000 Shutdown Cooling x shutdown implications in 3.8 21 accident (e.g. LOCA or loss of RHR) mitioation strateoies.

2.4.50 - Emergency Procedures I Plan: Ability to verify system 264000EDGs x alarm setpoints and operate 4.2 22 controls identified in the alarm response manual.

ES-401 4 Form ES-401-1 Oyster Creek Initial NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System #I Name A2 G Q#

1 2 3 4 5 6 1 3 4 K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the 215005 APRM I LPRM x AVERAGE POWER RANGE 3.1 23 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM :

Detectors K1 .13 - Knowledge of the physical connections and/or cause- effect relationships 212000RPS x between REACTOR 3.5 24 PROTECTION SYSTEM and the followina: Containment pressure A2.04 - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those 400000 Component Cooling predictions, use procedures to Water x correct, control, or mitigate the 2.9 25 consequences of those abnormal operation: Radiation monitorina svstem alarm K3.01 - Knowledge of the effect that a loss or malfunction of the 259002 Reactor Water Level Control x REACTOR WATER LEVEL 3.8 26 CONTROL SYSTEM will have on following: Reactor water level KIA Category Totals: 3 2 3 2 2 3 2 3/3 2 2 212 Group Point Total:

I 26/5

ES-401 5 Form ES-401-1 Oyster Creek Initial NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System #I Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

A2.07 - Ability to (a) predict the impacts of the following on the ROD WORTH MINIMIZER SYSTEM (RWH) (PLANT SPECIFIC); and (b) based on those 201006RWM x predictions, use procedures to 2.8 91 correct. control, or mitigate the consequences of those abnormal conditions or operations: RWM hardware/software failure: P-Soec 2.4.45 - Emergency Procedures I 233000 Fuel Pool Plan: Ability to prioritize and Cooling/Cleanup x interpret the significance of each 4.3 92 annunciator or alarm.

2.1.7 *Conduct of Operations:

Ability to evaluate plant 245000 Main Turbine Gen. I performance and make operational Aux.

x judgments based on operating 4.7 93 characteristics, reactor behavior, and instrument interpretation.

Kl.01 - Knowledge of the physical connections and/or cause- effect relationships between MAIN 245000 Main Turbine Gen. I Aux.

x TURBINE GENERATOR AND 3.2 27 AUXILIARY SYSTEMS and the following: A C. electrical distribution K2.0l - Knowledge of electrical power supplies to the following:

259001 Reactor Feedwater x Reactor feedwater pump(s):

3.3 28 Motor* Driven-Only K3.03 - Knowledge of the effect that a loss or malfunction of the RHR/LPCI: CONTAINMENT SPRAY SYSTEM MODE will 226001 RHR/LPCI: CTMT Spray Mode x have on following: 2.9 29 Containment/drywell/suppression chamber components, continued operation with elevated pressure and/or temperature and/or level K4.05 - Knowledge of CONTROL ROD AND DRIVE 201003 Control Rod and MECHANISM design feature(s)

Drive Mechanism x and/or interlocks which provide 3.2 30 for the following: Rod position indication KS.01 - Knowledge of the operational implications of the following concepts as they apply 214000RPIS x to ROD POSITION 2.7 31 INFORMATION SYSTEM :

Reed switches K6.02 - Knowledge of the effect that a loss or malfunction of the 234000 Fuel Handling following will have on the FUEL Equipment x HANDLING EQUIPMENT:

2.8 32 Reactor manual control system:

Plant-Specific

ES-401 5 Form ES-401-1 Oyster Creek Initial NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A Q System #I Name A2 G Imp.

1 2 3 4 5 6 1 3 4 #

A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 201002RMCS x REACTOR MANUAL 2.8 33 CONTROL SYSTEM controls including: CAD Drive Water Flow A2.19 - Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM; and (b) based on those predictions, use procedures to 202001 Recirculation x correct, control, or mitigate the 3.1 34 consequences of those abnormal conditions or operations: Loss of A.C. power:

Plant-Specific A3.01 - Ability to monitor automatic operations of the 290003 Control Room HV AC x CONTROL ROOM HVAC 3.3 35 including:

lnitiation/reconfiauration A4.05 - Ability to manually 204000RWCU x operate and/or monitor in the 2.9 36 control room: System pressure 2.4.30 - Emergency Procedures I Plan; Knowledge of events related to system operation I 233000 Fuel Pool status that must be reported to Cooling/Cleanup x internal organizations or 2.7 37 external agencies, such as the state, the NRC, or the transmission system operator.

A2.08 - Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM ; and (b) based on those predictions, use 271000 Off-gas x procedures to correct, control, 2.5 38 or mitigate the consequences of those abnormal conditions or operations: A.C. distribution failures KIA Category Totals: 1 1 1 1 1 1 1 211 1 1 1/2 Group Point Total:

I 12/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Oyster Creek Initial NRC Exam Date: 02/01/16 RO SRO-Only Category KIA# Topic IR Q# IR Q#

Knowledge of refueling administrative 2.1.40 3.9 94 requirements Knowledge of industrial safety procedures 1.

(such as rotating equipment, electrical, high Conduct 2.1.26 3.4 66 temperature, high pressure, caustic, chlorine, of Operations oxygen and hydrogen).

Knowledge of conduct of operations 2.1.1 3.8 67 requirements.

Subtotal 2 1 Knowledge of the process for conducting 2.2.7 3.6 95 soecial or infreauent tests.

Knowledge of the process for managing maintenance activities during power 2.2.17 operations, such as risk assessments, work 3.8 99 prioritization, coordination with the transmission svstem operator.

2.

Equipment Control Knowledge of the process for controlling 2.2.14 3.9 68 equipment confiquration or status.

Ability to determine Technical Specification 2.2.35 3.6 69 Mode of Operation.

2.2.12 Knowledge of surveillance procedures. 3.7 75 Subtotal 3 2 2.3.11 Ability to control radiation releases. 4.3 96 Knowledge of radiation or contamination hazards that may arise during normal, 2.3.14 3.8 98 abnormal, or emergency conditions or

3. activities.

Radiation Control Knowledge of radiation or containment hazards that may arise during normal, 2.3.14 3.4 70 abnormal, or emergency conditions or activities.

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of Radialogical Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor 2.3.13 3.4 71 alarms, containment entry requirements, fuel handling responsibilities, access to locked hiqh radiation areas, aliqninq filters, etc.

Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.5 2.9 74 portable survey instruments, personell monitorinq equipment, etc.

Subtotal 3 2 Knowledge of the bases for prioritizing safety 2.4.22 functions during abnormal/emergency 4.4 97 operations.

Knowledge of the bases for prioritizing 2.4.23 emergency procedure implementation during 4.4 100 emeroencv operations.

4.

Emergency Knowledge of facility protection Procedures I 2.4.26 requirements, including fire brigade and 3.1 72 Plan portable fire fiqhtinq equipment usaqe.

Ability to recognize abnormal indications for system operating parameters that are entry-2.4.4 4.5 73 level conditions for emergency and abnormal operatinq procedures.

Subtotal 2 2 Tier 3 Point Total 10 7

ES-401 Record of Rejected K/A's Form ES-401-4 Tier I Group Randomly Selected KIA Reason for Rejection Question 33: Unable to develop discriminating question at the 201002 A 1.05 - Ability to predict appropriate license level.

and/or monitor changes in parameters associated with Randomly resampled 201002 A1.01 -Ability to 212 operating the REACTOR predict and/or monitor changes in parameters MANUAL CONTROL SYSTEM associated with operating the REACTOR controls including: Local reactor MANUAL CONTROL SYSTEM controls including:

power CRD drive water flow Unable to develop discriminating question at the Question 40:

appropriate license level and avoid testing GFES 295026 EK1 .02 - Knowledge of knowledge.

the operational implications of the 1/1 following concepts as they apply Randomly resampled EK1 .01 - Knowledge of the to SUPPRESSION POOL HIGH operational implications of the following concepts WATER TEMPERATURE: Steam as they apply to SUPPRESSION POOL HIGH Condensation WATER TEMPERATURE: Pump NPSH Question 41: Unable to avoid overlap with question 20.

295003 AK1 .01 - Knowledge of the operational implications of the Randomly resampled AK1 .06 - Knowledge of the 1/1 following concepts as they apply operational implications of the following concepts to PARTIAL OR COMPLETE as they apply to PARTIAL OR COMPLETE LOSS LOSS OF A.G. POWER : Effect of OF A.G. POWER : Station Blackout: Plant battery discharqe rate on capacity Specific Question 46:

Unable to avoid overlap with question 32.

295023 AK3.02 - Knowledge of the reasons for the following Randomly resampled AK3.03 - Knowledge of the 1/1 responses as they apply to reasons for the following responses as they apply REFUELING ACCIDENTS :

to REFUELING ACCIDENTS : Ventilation Interlocks associated with fuel Isolation handling equipment Question 61:

Specified relationship does not exist.

295002 AK3.03 - Knowledge of the reasons for the following Randomly resampled AK3.04 - Knowledge of the 1/2 responses as they apply to LOSS reasons for the following responses as they apply OF MAIN CONDENSER to LOSS OF MAIN CONDENSER VACUUM:

VACUUM : Reactor feedpump Bypass valve closure turbine trip: Plant-Specific Unable to develop discriminating question at the Question 67 appropriate license level.

3 2.1.17 - Ability to make accurate, clear, and concise verbal reports Randomly resampled 2.1.1 - Knowledge of conduct of operations requirements.

Unable to develop a question at the appropriate license level.

Question 73 2.4.40 - Knowledge of the SRO's Randomly resampled 2.4.4 - Ability to recognize 3 responsibilities in emergency plan abnormal indications for system operating implementation parameters that are entry-level conditions for emergency and abnormal operating procedures.

ES-401 Record of Rejected K/A's Form ES-401-4 Unable to develop a question at the appropriate Question 55 license level.

2.2.38 - Equipment Control:

1/1 Knowledge of conditions and Randomly resampled 2.2.37 - Ability to determine limitations in the facility license. operability and/or availability of safety related equipment Question 57 The specified relationship does not exist.

295038 - EK2.11 - Knowledge of the interrelations between HIGH Randomly resampled 295038 EK2.03 -

1/1 OFF-SITE RELEASE RATE and Knowledge of the interrelations between HIGH the following: MSIV leakage OFF-SITE RELEASE RATE and the following:

control: Plant-Specific Plant ventilation systems Question 44 295025 - EK2.10 - Knowledge of Unable to avoid overlap with question 62.

the interrelations between HIGH 1/1 REACTOR PRESSURE and the Randomly resampled EK2.01 - Knowledge of the following: interrelations between HIGH REACTOR SPDS/ERIS/CRIDS/GDS: Plant- PRESSURE and the following: RPS Soecific Question 79 295038 High Off-site Release Unable to develop a question at the appropriate Rate I 9 - 2.1.31 - Conduct of license level.

Operations: Ability to locate 1/1 control room switches, controls, Randomly resampled 2.1.25 - Conduct of and indications, and to determine Operations: Ability to interpret reference materials, that they correctly reflect the such as graphs, curves, tables, etc.

desired plant lineup.

Question 98 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator Unable to develop a question at the duties, such as response to appropriate license level.

3/3 radiation monitor alarms, containment entry Randomly resampled 2.3.14 -

requirements, fuel handling responsibly, access to locked high radiation areas, aligning filters, etc

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oyster Creek Date of Examination: 2/2016 Examination Level: RO Operating Test Number: NRC 2016 Administrative Topic (see Note) Type Describe activity to be performed Code*

Perform Week 4 of 680.4.007, Safety Related Equipment Conduct of Operations D, R Verification KA 2.1.29 (4.1) Procedure 680.4.007 P, R Calculate Identified Leak Rate Conduct of Operations KA2.1.20(4.6) Procedure351.2(11-1 NRC)

Explain RPS Manual Scram Circuit Using Prints Equipment Control N,R KA 2.2.41 (3.5) GE 237E566 I

i I

.. I

........ .., :U;;;ilik~W.1Li.;.;~.,

  • rJ~ ... ;;.,,rr:t;i;. ~..."~~

Actions for External Security Threats Emergency Plan N,R KA 2.4.28 (3.2) Procedure ABN-41 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (S 3 for ROs; :s; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: O~ster Creek Date of Examination: 2/2016 Examination Level: SRO Operating Test Number: NRC 2016 Administrative Topic (see Note) Type Describe activity to be performed Code*

Review a Completed Pre-Critical Checkoff Conduct of Operations D,R KA 2.1.23 (4.4) Procedure 201 Review Request to Allow LPRM (input into APRM)

P, R Bypass (11-1 NRC)

Conduct of Operations KA 2.1.9 (4.5) Procedure 403 Explain RPS Manual Scram Circuit Using Prints and Determine Technical Specification Requirements for Equipment Control N,R RPS Manual Scram Pushbutton KA 2.2.41 (3.9) GE 237E566 Authorize Emergency Exposures Radiation Control D, R KA 2.3.4 (3.7) EP-AA-113 Actions for External Security Threats and Emergency Plan N,R EAL determination KA 2.4.41 (4.6) Procedure ABN-41 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (s 3 for ROs; s 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (~ 1)

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oyster Creek Date of Examination: 2/2016 Exam Level: R01SRO-l1SRO-U Operating Test No.: NRC 2016 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SR0-1!

System I JPM Title Type Code* Safety Function

a. Perform Control Rod Exercising Test (Or a rod sequence N,S,A 1 exchange) - uncoupled Rod KA 201003 A2.02 (3.7/3.8) ABN-6
b. Sequential Loss of Service water N,S,A 8 KA 400000 K1.01 (3.2/3.3)ABN-18
c. Place Second RWCU Pump in Service (RO Only) M,S 2 KA 204000 A4.01 (3.1/3.0) Procedure 303
d. Partial MSIV Stroke Test N,S,A 3 KA 239001 A4.01 (4.2/4.0) Procedure 602.4.004
e. Cool Down the RPV Using IC Tube Side Vents D,S,A,EN 4 KA 295021 AA1.04 (3.7/3.7) SP-15
f. Place H2/02 Monitoring in Service D,S, L 5 KA 500000 EA1 .01 (3.4/3.3) SP-39
g. Startup of the Turbine Building Ventilation System D,S,A,L 9 KA 288000 A4.01 (3.1/2.9) Procedure 328
h. APRM Gain Adjustment D,S 7 215005 A4.03 (3.2/3.3) 202.1-9 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Vent the Scram Air Header 1 P,R,E KA 295037 EA1.05 (3.9/4.0) SP21 2012 NRC
j. Startup EOG 1 for Peaking Operation 6 KA 264000 K4.07 (3.3/3.4) Procedure 341 D
k. Line up to Vent the Torus through the Hardened Vent P, E 5 KA 295024 EA 1.14 (3.4/3.5) SP-35 2012 NRC
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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-I / SRO-U A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irect from bank  :>9/S8/S4 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature 2:1 I 2:1 I;:; 1 (control room system)

(L)ow-Power I Shutdown i::1/C::1/i::1 (N)ew or {M)odified from bank including 1(A) 2:2/2:2/i::1 (P)revious 2 exams  ::; 3 / s 3 / :s 2 (randomly selected)

(R)CA <::1/<::1/<::1 (S)imulator Possible Pairings:

A - alone B - alone C Then D E Then F G Then H

Appendix D Scenario Outline Form ES-D-1 Facility: Oyster Creek Scenario No.: Scenario-1 Op-Test No.: NRC 2016 Examiners: Operators:

Initial Conditions:

  • 100% power
  • Risk is Yellow Turnover:
  • Lower power to 95% using recirculation flow IAW 1001.22-3, Core Maneuvering Daily Instruction Sheet.
  • Following the power reduction Backwash B North Condenser IAW procedure 323.6 Event Malf. No. Event Event No. Type* Description R- Lower reactor power with recirc.

1 N/A ATC, SRO 301.2 Reactor Recirculation system N- Backwash the Condenser 2 NIA BOP, SRO 323.6 Backwashing condensers C-CRD Pump Trip ATC, BKR-3 SRO RAP-H7c, Charg wtr press lo CRD002 TS-T.S 3.4 SRO C-BOP, IC Tube Leak MAL- SRO 4 EMG-3200.12, Radioactivity Release Control ICS002A SRO- T.S. 3.8 T.S C- GEMAC Reference Leg Leak MAL-5 ATC, ABN-17, Feedwater system abnormal conditions NSS012E SRO C-MAL- BOP, EPR Fails low 6 SRO TCS010 ABN-9, Electric Pressure regulator Malfunction

Respond to 'B' CRD pump to trip and Responds to an HCU BKR- C- accumulator failure ABN-1,Reactor Scram 7

CRD001 ALL EMG-3200.01a EOP RPV-No ATWS SRV- M- MSIV's close and Safety Valve Lifts after Scram 8

NSS001C ALL EMG-3200.02 Primary Containment Control C- Trip of Containment Spray Pump BKR-9 BOP, CNS008 EMG-3200.02 Primary Containment Control SRO

  • (N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)ajor Facility: Oyster Creek Scenario No.: Scenario 1 Op-Test No.: NRC 2016
2. Malfunctions after EOP entry (1-2)

Events 8,9 2

3. Abnormal events (2-4)

Events 5,6, 7 3

4. Major transients (1-2)

Event 8 1

5. EOPs entered/requiring substantive actions (1-2)

Primary Containment/ RPV Control No-ATWS 2

6. EOP contingencies requiring substantive actions (0-2) 0
7. EOP Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1.0 Given an isolable leak outside the Reactor Building , the crew must isolate the leak, in accordance with Rad Release control.

CT-2.0 Given a loss of all CRD, the crew must insert a manual reactor scram in accordance with ABN-1.

CT-3.0 The crew must initiate containment spray to restore and maintain <281°f or when containment pressure exceeds 12 psig IAW Primary Containment Control.

Appendix D Scenario Outline Form ES-D-1 Facility: Oyster Creek Scenario No.: Scenario 2 Op-Test No.: NRC 2016 Examiners: Operators:

Initial Conditions:

  • 100% power
  • Air Compressor #3 is tagged OOS
  • EOG #2 Out of service Turnover:
  • Diesel Generator #2 has been out of service for 2 days due to failure to start during the load test. It is scheduled to be returned to service the next day. The diesel load test for #1 diesel is due next shift. Fire diesel #1 is out of service until next shift for quarterly PMs.
  • Swap RBCCW pumps IAW 309.2 Event Malf. No. Event Event No. Type* Description N-1 NIA BOP, Swap RBCCWpumps SRO MAL-C- RWCU isolable leak (failure of one isolation valve)

RCU013 BOP, EMG-3200.11, Secondary Containment Control 2 VLV- SRO RCU001 TS- T.S. 3.5 SRO C-All Loss of VMCC 1B2 MAL-3 TS- ABN-51, Loss of VMCC 1B2 EDS004B SRO T.S. 3.7 C-MAL- ATC, CRD Flow Control Failure 4 SRO CRD001A ABN-6, Control Rod Malfunctions MAL- R-ATC, OFF-Gas Deflagration/ with condenser vacuum leak OGS003 SRO ABN-25, OFF-Gas Deflagration 5

MAL-C- ABN-14, Loss of Condenser Vacuum CFW017 BOP

Loss of Stator Cooling MAL-C-

6 GEA005A, ABN-11 Loss of Generator Stator Cooling ALL B

ABN-1 Reactor Scram M- Electric A TWS 7 ATWS.CAE ALL EMG-3200.01 B RPV control-With ATWS C- Failure of Turbine Bypass Fails MAL-8 BOP, TCS006D-I EMG-3200.01 B, RPV control w/atws SRO

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Facility: Oyster Creek Scenario No.: Scenario 2 Op-Test No.: NRC 2016
1. Malfunctions after EOP entry (1-2)

Events 7,8 2

2. Abnormal events (2-4)

Events 3,4,5,6 4

3. Major transients (1-2)

Event7 1

4. EOPs entered/requiring substantive actions (1-2)

RPV Control No-ATWS 1

5. EOP contingencies requiring substantive actions (0-2)

RPV Control With A TWS 1

6. EOP Critical tasks (2-3) 4 CRITICAL TASK DESCRIPTIONS:

CT- Given a failure to scram, the crew must terminate and prevent injection in accordance with EOP SP-17.

CT- Given a failure to scram, the crew must recommence injection to the reactor in accordance with EOP SP-19.

CT - Given a failure to scram, the crew must vent the scram air header in accordance with EOP SP-21.

CT - Given an isolable leak from RWCU, the crew must isolate the RWCU system in accordance with secondary Containment Control

Appendix D Scenario Outline Form ES-D-1 Facility: Oyster Creek Scenario No.: Scenario 3 Op-Test No.: NRC 2016 Examiners: Operators:

Initial Conditions:

  • 97% power
  • Main Generator voltage control is in Manual
  • Risk is Yellow Turnover:
  • Place the AVR in automatic service IAW 336.1, section 8, starting on step 8.2 Even Malf. No. Event Event t No. Type* Description N-BOP, Return the AVR to service.

1 N/A SRO 336.1 24 KV main generator electric system R-ATC, EMRV Spuriously opens SRO MAL-2 ABN-40, Stuck open EMRV NSS025E C-BOP T.S 4.5.L TS-SRO MAL- C-ATC CRD high temperature alarm 3 CRD013_3 SRO RAP-H5c CRD Hi Temp 403 C-BOP Trip of 1A3 MAL- SRO 4 ABN-46, Loss of 1A3 EDS003C TS-SRO T.S -3.7 MAL-RBC001A RBCCW Pump Trip Leads to Reactor Scram 5 C-ALL MAL- ABN-19 RBCCW failure response RBC001B MAL- LOCA in Primary Containment 6 M-ALL NSS017A EMG-3200.02 Primary Containment Control Containment Spray Fails to Swap to DW Spray Mode VLV- C-BOP, 7 EMG-SP29 Initiation of the containment Spray system for Drywell CNS005 SRO Sprays

RUN FLD.CAE RPV level flashing 8 M-ALL NOLEVEL. EMG-3200.0SA RPV flooding-No ATWS CAE

  • (N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)aior Facility: Oyster Creek Scenario No.: Scenario 3 Op-Test No.: NRC 2016
1. Malfunctions after EOP entry (1-2)

Events 7,8 2

2. Abnormal events (2-4)

Events 2,4,5 3

3. Major transients (1-2)

Event 6,8 2

4. EOPs entered/requiring substantive actions (1-2)

RPV control No-ATWS, Primary Containment 2

5. EOP contingencies requiring substantive actions (0-2)

ED No-ATWS, RPV Flooding No-ATWS 2

6. EOP Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1.0 Given a failed open EMRV, the crew will need to take action to close the EMRV in accordance with ABN-40, Stuck open EMRV.

CT-2.0 Given a LOCA in Primary Containment with challenges to RPV level control, the crew must implement EOP SP-58, Feed and Condensate System and/or EOP SP-60, Core Spray operation, to restore RPV water level.

CT-3.0 Given a LOCA in Primary Containment with Drywell parameters degrading beyond the capacity of the Containment Spray system, the crew will perform an Emergency Depressurization of the Reactor.

Appendix D Scenario Outline Form ES-D-1 Facility: Oyster Creek Scenario No.: Scenario (Spare) Op-Test No.: NRC 2016 Examiners: Operators:

Initial Conditions: The plant is operating at <5% power during a reactor startup. Turbine warming is inprog Turnover: Raise Reactor Power with Control rods Event Malf. No. Event Event No. Type* Description R-ATC, Raise Reactor Power with Rods 1 N/A SRO 302.1 Control Rod Drive System MAL- C-ALL Control Rod Drifts Out 2 CRD005-1431 ABN-6 Control Rod Malfunctions I-ATC, APRM Fails High MAL- SRO 3 403 LPRM-APRM system operations NIS021A TS-SRO T.S. 3.1.1 C-BOP, Loss of VACP-1 LOA- SRO 4 ABN-58 Instrument Power Failures EDS137 TS-SRO T.S. 3.7 C-BOP, Respond to trip of Control Room Vent Fan B SRO 5 ANN-L-4f 331.1 Control Room HVAC TS-SRO T.S. 3.17.B MAL- Loss of Bus 1A Causes a Reactor Scram 6 C-All EDS001a ABN-1 Reactor Scram MAL- ATWS - Rods Insert With ARI RPS006 EMG-3200.018 RPV control with ATWS 7 C-All MAL-RPS005

MAL-I CS 003A Steam Leak into Reactor Building From unisolable Isolation VLV- Condenser 8 M-All ICS005 EMG-3200.02 Secondary Containment Control VLV-ICS006

  • (N)ormal, (R)eactivity (l)nstrument, (C)omponent, (M)aior Facility: Oyster Creek Scenario No.: Scenario 4 Op-Test No.: NRC 2016
1. Malfunctions after EOP entry (1-2)

Events 8,9 2

2. Abnormal events (2-4)

Events 2,4 2

3. Major transients (1-2)

Event 8 1

4. EOPs entered/requiring substantive actions (1-2)

RPV Control No-ATWS 1

5. EOP contingencies requiring substantive actions (0-2)

Emergency Depressurize No-ATWS, 2 Secondary Containment

6. EOP Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1.0 Given a drifting control rod which fails to remain inserted with RMCS, the crew must scram the control rod in accordance with ABN-6.

CT-2.0 Given an un-isolable steam leak into the Reactor Building, the crew must Anticipate Reactor Slowdown and/or Emergency Depressurize the Reactor when two maximum safe parameters are challenged.

CT-3.0 Given a Reactor Scram with rods failing to insert, the crew must manually initiate ARI to insert control rods, in accordance with EOP RPV-with ATWS.

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