ML101620058

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Final Outlines (Folder 3)
ML101620058
Person / Time
Site: Oyster Creek
Issue date: 04/30/2010
From:
Exelon Nuclear
To: D'Antonio J
Operations Branch I
Hansell, S L, RI/DRS/OB, 610-337-5046
Shared Package
ML092470040 List:
References
50-219/10-301, TAC U01771
Download: ML101620058 (26)
v • d • e


Text

ES-401 Written Examination Outline Form ES-401-1 Oyster Creek ILT 09-1 Facility:

Date of Exam:

May 17,2010 NRC Exam Outline

3. Generic Knowledge & Abilities RO KIA Category Points SRO-Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total

1.

1 3

4 3

3 3

4 20 3

4 7

Emergency 2

1 1

1 1

1 2

7 1

2 3

Plant Evolutions Tier Totals 4

5 4

4 4

6 27 4

6 10 1

2 3

2 3

2 3

2 3

2 3

2 26 2

3 5

2.

Plant 2

1 1

1 1

1 1

I 2

1 1

1 12 0

2 1

3 Systems Tier Totals 3

4 3

4 3

4 3

4 3

4 3

38 4

4 8

1 2

3 4

I 2

3 4

10 7

Categories 2

2 3

3 1

2 2

2 Note:

1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and SRO-only outlines (i.e., except for one category in Tier 3 ofthe 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 fmal 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 must total 75 points and the SRO-only exam must total 25 points.

3.

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

4.

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

5.

Absent a plant specific priority, only those KAs having an importance rating (IR) of2.5 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.

I I

7.*

The generic (G) KlAs in Tiers I 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.l.b ofES-401 for the applicable KIA's

8.

On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (JR) 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. Iffuel 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 KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to IOCFR55.43

ES-401 2

Form ES-401-1 ILT 09-1 NRC Exam Outline Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # I Name Safety Function KIA Topic(s)

EA2.02 - Ability to detennine and/or 295028 High Drywell Temperature interpret the following as they apply to X

3.9 I

15 HIGH DRYWELL TEMPERATURE :

Reactor Ilressure AA2.01 - Ability to detennine and/or interpret the following as they apply to 295019 Partial or Total Loss of X

PARTIAL OR COMPLETE LOSS OF 3.6 2

Inst. Air 18 INSTRUMENT AIR : Instrument air system pressure AA2.03 - Ability to detennine and/or interpret the following as they apply to 295018 Partial or Total Loss of X

PARTIAL OR COMPLETE LOSS OF 3.5 3

CCW/8 COMPONENT CooUNG WATER :

Cause for partial or complete loss 2.4.18 - Emergency Procedures I Plan:

295006 SCRAM I 1 X

4.0 4

Knowledge of the specific bases for EOPs.

2.4.11 - Emergency Procedures I Plan:

295038 High Offsite Release Rate X

Knowledge of abnonnal condition 4.2 5

procedures.

295037 SCRAM Conditions 2.4.20 - Emergency Procedures I Plan:

Present and Reactor Power Above X

Knowledge ofoperational implications of 4.3 6

APRM Downscale or Unknown I I EOP warnings, cautions, and notes.

700000 Generator Voltage and 2.2.40 - Equipment Control: Ability to apply X

4.7 7

Electric Grid Disturbances technical specifications for a system.

EKI.05 - Knowledge ofthe operational implications of the following concepts as 295025 High Reactor Pressure 13 X

4.4 39 they apply to HIGH REACTOR PRESSURE: Exceeding safety limits AKl.02 - Knowledge of the operation applications ofthe following concepts as 600000 Plant Fire On-site I 8 X

2.9 40 they apply to Plant Fire On Site: Fire Fighting AK I.05 - Knowledge of the operational implications of the following concepts as 295004 Partial or Total Loss of DC X

they apply to PARTIAL OR COMPLETE 3.3 41 Pwr /6 LOSS OF D.C. POWER : Loss of breaker I

protection EK2.07 - Knowledge of the interrelations 2~5030 Low Suppression Pool between LOW SUPPRESSION POOL X

3.5 42 Water Level l 5 WATER LEVEL and the following:

Downcomerl horizontal vent submergence AK2.01 - Knowledge of the interrelations 29501 8 Partial or Total Loss of between PARTIAL OR COMPLETE X

3.3 43 CCW /8 LOSS OF COMPONENT COOLING WATER and the following: System loads AK2.03 - Knowledge of the interrelations 295021 Loss of Shutdown Cooling between LOSS OF SHUTDOWN X

3.6 44 14 COOLING and the following:

RHRlshutdown cooling EK3.04 - Knowledge of the reasons for 295031 Reactor Low Water Level the following responses as they apply to X

4.0 45 12 REACTOR LOW WATER LEVEL :

I Steam cooling EK3.01 - Knowledge of the reasons for the following responses as they apply to 295037 SCRAM Conditions SCRAM CONDITION PRESENT AND Present and Reactor Power Above X

REACTOR POWER ABOVE APRM 4.1 46 APRM Downscale or Unknown II DOWNSCALE OR UNKNOWN :

Recirculation pump trip/runback: Plant-I Specific

ES-401 2

Form ES-401-1 IL T 09-1 NRC Exam Outline Written Examination Outline Emergency and Abnormal Plant Evolutions -- Tier 1 Group 1

  1. / Name Safety Function KiA Topic(s)

AK3.02 - Knowledge ofthe reasons for 295023 Refueling Acc Cooling the following responses as they apply to X

3.4 47 ModelS REFUELING ACCIDENTS: Interlocks associated with fuel handling equipment AA1.01 - Ability to operate and/or 29500 I Partial or Complete Loss monitor the following as they apply to ofForced Core Flow Circulation II X

PARTIAL OR COMPLETE LOSS OF 3.5 48

&4 FORCED CORE FLOW CIRCULATION

Recirculation System EA1.01 - Ability to operate and/or 295038 High Off-site Release Rate monitor the following as they apply to X

19 HIGH OFF-SITE RELEASE RATE:

Stack-gas monitoring AA1.04 - Ability to operate and/or 295016 Control Room monitor the following as they apply to X

50 Abandonment /7 CONTROL ROOM ABANDONMENT:

A.C. electrical distribution f

AA2.01 - Ability to determine and/or interpret the following as they apply to 295019 Partial or Total Loss of X

PARTIAL OR COMPLETE LOSS OF 3.5 51 Inst. Air IS INSTRUMENT AIR: Instrument air system pressure AA2.03 - Ability to determine and/or 295006 SCRAM I I interpret the following as they apply to 4.0 52 SCRAM : Reactor water level AA2.04 - Ability to determine and/or 295003 Partial or Complete Loss interpret the following as they apply to X

3.5 53 ofAC/6 PARTIAL OR COMPLETE LOSS OF A.C. POWER: System lineups 2.4.47 - Emergency Procedures / Plan:

Ability to diagnose and recognize trends 295026 Suppression Pool High X

in an accurate and timely manner 4.2 54 Water Temp. /5 utilizing the appropriate control room reference material.

2.2.42 - Equipment Control: Ability to 295005 Main Turbine Generator recognize system parameters that are X

3.9 5

Trip/3 entry-level conditions for Technical Specifications.

2.2.37 - Ability to determine operability 295024 High Drywell Pressure I 5 X

and/or availability of safety related 3.6 56 ent.

2.4.4 - Emergency Procedures I Plan:

Ability to recognize abnormal indications 700000 Generator Voltage and X

for system operating parameters which 4.5 57 Electric Grid Disturbances are entry-level conditions for emergency and abnormal operating procedures.

EK2.02 Knowledge of the interrelations 295028 High Drywell Temperature between HIGH DRYWELL X

3.2 58

/5 TEMPERATURE and the following:

Components internal to the drywell KJA Cat~:gory Totals:

3 4

3 3

3/3 4/4 Group Point Total:

2017 I

ES-401 3

Form ES-401-1 ILT 09-1 NRC Exam Outline Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # I Name Safety Function KIA Topic(s)

AA2.02 - Ability to detennine and/or 295009 Low Reactor Water Levell interpret the following as they apply to X

3.7 8

2 LOW REACTOR WATER LEVEL: Steam f10wlfeed flow mismatch 295008 High Reactor Water Level 2.1.20 - Conduct ofOperations: Ability to X

4.6 9

12 interpret and execute procedure steps.

2.1.23 - Conduct ofOperations: Ability to 2950 \\3 High Suppression Pool perfonn specific system and integrated plant X

4.4 10 Temperature I 5 procedures during all modes of plant operation.

AKI.03 - Knowledge of the operational 295017 High Off-site Release implications of the following concepts as X

3.8 59 Rate/9 they apply to HIGH OFF-SITE RELEASE RATE: Protection of the general public EK2.01 - Knowledge of the interrelations between SECONDARY CONTAINMENT 295035 Secondary Containment 3.6 X

HIGH DIFFERENTIAL PRESSURE and 60 High Differential Pressure I 5 the following: Secondary containment ventilation EKJ.OI - Knowledge of the reasons for the 295033 High Secondary following responses as they apply to HIGH 3.

Containment Area Radiation X

SECONDARY CONT AlNMENT AREA 61 3

Levels I 9 RADIATION LEVELS : Emergency I

depressurization EAI.04 - Ability to operate and/or monitor the following as they apply to 295034 Secondary Containment 4.

X SECONDARY CONTAINMENT 62 Ventilation High Radiation I 9 I

VENTI LATION HIGH RADIATION :

SBGT/FRVS: Plant-Specific AA2.02 - Ability to detennine and/or 295002 Loss ofMain Condenser interpret the following as they apply to

3.

X 63 Vac/3 LOSS OF MAIN CONDENSER VACUUM 2

I

Reactor power: Plant-Specific I

2.1.7 - Ability to evaluate plant performance and make operational 2r 007 High Reactor pre:sure I 3 X

judgments based on operating 4.4 64 characteristics, reactor behavior, and instrument interpretation.

I 2.2.2 - Ability to manipulate the console controls as required to operate the 295022 Loss ofCRD Pumps I I X

4.6 65 facility between shutdown and designated power levels.

KIA Category Totals:

1 1

1 1

1/1 2/2 Group Point Total:

I 7/3

ES-401 4

Form ES-401-1 IL T 09-1 NRC Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 K

K K

K K

K A

A A

Imp System # / Name A2 G

Q#

1 2

3 4

5 6

1 3

4 261000 SGTS 215004 Source Range Monitor I

I 2lIOOd LC 263000 DC Electrical Distribution I

400000 Component Cooling Water II i

I 212000 RPS r

223002 PCISlNuclear Stearn Supply Shutoff 262001 AC Electrical Distribution 263000 DC Electrical Distribution A2.07 - Ability to (a) predict the impacts ofthe following on the STANDBY GAS TREATMENT SYSTEM ; and (b) based on those X

predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C.

electrical failure A2.01 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM ; and (b) based on X

those predictions, use procedures to correct, control, or mitigate the consequences ofthose abnormal conditions or operations: Power supply degraded 2.4.4 - Emergency Procedures /

Plan: Ability to recognize abnormal indications for system X

operating parameters that are entry-level conditions for emergency and abnormal operatinJj procedures.

2.1.30 - Conduct ofOperations:

X Ability to locate and operate components, including local controls.

2.4.16 - Knowledge of EOP implementation hierarchy and coordination with other support X

procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

KI.OI - Knowledge ofthe physical connections and/or cause-effect X

relationships between REACTOR PROTECTION SYSTEM and the following: Nuclear instrumentation K1.02 - Knowledge of the physical connections and/or cause-effect relationships X

between PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the Reactor water cleanup K2.01 - Knowledge of electrical X

power supplies to the following:

Off-site sources of power K2.01 - Knowledge of electrical X

power supplies to the following:

Major D.C. loads 2.8 2.9 4.7 4.0 4.4 3.7 3.3 3.3

3. 1 I I 12 13 14 15 1

2 3

4

ES-401 4

Form ES-401-1 ILT 09-1 NRC Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 r-'

K3.08 - Knowledge of the effect that a loss or malfunction of the AVERAGE POWER RANGE 215005.APRM I LPRM X

MONITOR/LOCAL POWER 3.0 5

RANGE MONITOR SYSTEM will have on following: Core thermal calculations K3.03 - Knowledge of the effect that a loss or malfunction of the 259002 Reactor Water Level Control X

REACTOR WATER LEVEL CONTROL SYSTEM will have 2.7 6

on following: Rod worth minimizer: Plant-Specific K4.08 - Knowledge of RELIEF/SAFETY VALVES design feature(s) and/or 239002 SRVs interlocks which provide for the 3.6 7

following: Opening of the SRV from either an electrical or mechanical signal K4.01 - Knowledge of CCWS 400000 Component Cooling Water X

design feature(s) and or interlocks which provide for the following: Automatic start of 3.4 8

standby pump K5.02 - Knowledge ofthe operational implications of the following concepts as they apply 205000 Shutdown Cooling X

to SHUTDOWN COOLING 2.8 9

SYSTEM (RHR SHUTDOWN COOLING MODE) : Valve operation K5.05 - Knowledge of the operational implications of the 264000EDGs X

following concepts as they apply to EMERGENCY 3.4 10 GENERATORS (DIESEL/JET):

Paralleling A.C. power sources K6.04 - Knowledge of the effect that a loss or malfunction of the 261000 SOTS X

following will have on the STANDBY GAS TREATMENT 2.9 11 SYSTEM: Process radiation monitoring K6.03 - Knowledge of the effect that a loss or malfunction of the 262002 UPS (ACIDC)

X following will have on the UNINTERRUPTABLE POWER 2.7 12 SUPPLY (A.C.lD.C.) : AC electrical power A 1.07 - Ability to predict and/or monitor changes in parameters associated with operating the 209001 LPCS X

LOW PRESSURE CORE 3.0 13 SPRAY SYSTEM controls including: Emergency generator 10adinQ

ES-401 4

Form ES-401-1

  1. 1 Name 218000 ADS 215003 [RM 300000 Instrument Air 207000 Isolation (Emergency)

Condenser 211000 SLC 215004 Source Range Monitor 259002 Reactor Water Level Control 215005 APRM I LPRM 264000EOOs 215004 Source Range Monitor ILT 09-1 NRC Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K

K K A

A A

A2 G

1 2

3 4

5 6 1

3 4

A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the X

AUTOMATIC DEPRESSURIZATION SYSTEM controls including: ADS valve tail pipe temperatures A2,04 - Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM; and (b) based on those predictions, X

use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Up scale or down scale trips A3.02 - Ability to monitor automatic operations of the X

INSTRUMENT AIR SYSTEM including: Air temperature A3,03 - Ability to monitor automatic operations of the X

ISOLATION (EMERGENCY)

CONDENSER including:

Reactor water level: BWR-2,3 A2.02 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those predictions, use X

procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure of explosive valve to fire A4.06 - Ability to manually X

operate and/or monitor in the control room: Alarms and lights A4.03 - Ability to manually operate and/or monitor in the control room: All individual X

component controllers when transferring from manual to automatic modes 2.4.6 - Emergency Procedures /

X Plan: Knowledge of EOP mitigation strategies.

2.4.3 - Emergency Procedures I X

Plan: Ability to identify post-accident instrumentation.

K2.01 - Knowledge of electrical X

power supplies to the following:

SRM channels/detectors Imp 3.4 3,7 2,9 3.5 3.6 3.2 3.8 3.7 3.7 2.6 Q#

14 15 16 I7 18 19 20 21 22 23

ES-401 4

Form ES-401-1 IL T 09-1 NRC Exam Outline Written Examinaticm Outline Plant Systems - Tier 2 Group 1 K6.01 - Knowledge of the effect that a loss or malfunction of the 239002 SRVs X

following will have on the RELIEF/SAFETY VALVES:

3.2 24 Nuclear boiler instrument system (pressure indication)

A4.17 - Ability to manually 212000RPS X

operate and/or monitor in the control room: Perform alternate 4.1 25 reactivityl shutdown operations K4.01 - Knowledge of (INSTRUMENT AIR SYSTEM) 300000Ins~entlUr X

design feature(s) and or interlocks which provide for the 2.8 26 following: ManuaVautomatic transfers of control KIA Category Totals:

2 3

2 3

2 3

2 2/2 2

3 213 Group Point Total:

I 2615

ES-401 5

Form ES-401-1 System # / Name 2nOOO Radiation Monitoring 215001 Traversing In-core Probe 259001 Reactor Feedwatet I

I I

I 241000 ReactorlTurbine Pressure Regulator I

22600 I RHRILPCI: CTMT Spray M ode 20 1003 Control Rod and Drive Mechanism I

I I

2 ~002fMCS 22300 I Primary CTMT and Aux.

I I

201 006 RWM I

233000 Fuel Pool Cooling/Cleanup ILT 09-1 NRC Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 2 K

K K

K K

K A

A A

A2 G

1 2

3 4

5 6

1 3

4 A2.03 - Ability to predict the impacts ofthe following on the RADIATION MONITORING SYSTEM ; and (b) based on those X

predictions, use procedures to correct, control, or mitigate the consequences ofthose abnormal conditions or operations: A.C.

electrical failure 2.2.22 - Equipment Control:

X Knowledge oflimiting conditions for operations and safety limits.

A2.08 - Ability to (a) predict the impacts ofthe following on the REACTOR FEEDWATER SYSTEM ; and (b) based on those X

predictions, use procedures to correct, control, or mitigate the consequences ofthose abnormal conditions or operations: Loss of DC electrical power K 1.l4 - Knowledge ofthe physical connections and/or cause-effect relationships between X

REACTORITURBINE PRESSURE REGULATING SYSTEM and the following: A.C.

electrical power K2.02 - Knowledge ofelectrical X

power supplies to the following:

Pumps KJ.O I - Knowledge ofthe effect that a loss or malfunction ofthe X

CON TROL ROD AND DRIVE MECHANISM will have on following: Reactor power K4.06 - Knowledge of REACTOR MANUAL X

CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following:

Emergency In rod insertion K5.01 - Knowledge of the operational implications of the X

following concepts as they apply to PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES :

Vacuum breaker/relief operation K6.01 - Knowledge of the effect that a loss or malfunction of the X

following wi" have on the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) :

Power Supply A 1.01 - Ability to predict and/or monitor changes in parameters X

associated with operating the FUEL POOL COOLING AND CLEAN-UP controls including:

Surge tank level Q

Imp.

3.1 16 4.7 17 2.6 18 2.8 27 2.9 28 3.2 29 3.5 30 3.1 31 2.8 32 2.6 33

ES-401 5

Form ES-401-1 ILT 09-1 NRC Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 2 System # I Name K

1 KKKAA2 4

5 6

1 A

3 A

4 G

Imp.

Q A2.07 - Ability to (a) predict the impacts of the following on the TRAVERSING IN-CORE PROBE; and (b) based on 215001 Traversing In-core Probe X

those predictions, use procedures to correct, control, or mitigate the consequences of 3.4 34 those abnormal conditions or operations: Failure to retract during accident conditions:

Mark-I&II(Not-BWR1 )

A3.05 - Ability to monitor automatic operations of the 204000 RWCU X

REACTOR WATER CLEANUP 2.8 35 SYSTEM including: Reactor water temperature A4.01 - Ability to manually 201001 CRD Hydraulie X

operate and/or monitor in the 3.1 36 control room: CRD pumps 2.4.34 - Emergency Procedures I Plan: Knowledge of RO tasks 259001 Reactor Feedwater X

performed outside the main control room during an 4.2 37 emergency and the resultant operational effects.

A2.03 - Ability to (a) predict the impacts of the following on the REACTOR VESSEL INTERNALS; and (b) based on 290002 Reactor Vessel Intemals X

those predictions, use procedures to correct, control, 3.6 38 or mitigate the consequences of those abnormal conditions or KJA Category Totals:

1 1

1 1

1 1

1 212 operations: Control rod drop

~.",.e..

Group Point Total:

I 12/3

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

Form ES-401-3 Oyster Creek ILT 09-1 NRC Exam Facility:

Date:

May 17, 2010 Outline RO SRO-Only Category KJA#

Topic IR Q#

IR Q#

Ability to perform specific system and 2.1.23 integrated plant procedures during all modes 4.4 19 of plant operation.

1.

Ability to make accurate, clear and concise Conduct 2.1.18 3.6 66 logs, records, status boards, and reports.

of Operations Knowledge of the station's requirements for 2.1.38 verbal communications when implementing 3.7 67 procedures.

Subtotal 2

1 Knowledge of the process for managing maintenance activities during power 2.2.17 operations, such as risk assessments, work 3.8 20 prioritization, coordination with the transmission system operator.

Ability to analyze the effect of maintenance activities, such as degraded power sources, 2.2.36 4.2 24 on the status of limiting conditions for operations.

2.

Equipment Control Ability to analyze the effect of maintenance activities, such as degraded power sources, 2.2.36 3.1 68 on the status of limiting conditions for operations.

Knowledge of the process for controlling 2.2.14 3.9 69 equipment configuration or status.

Subtotal 2

2

3.

Knowledge of radiation exposure limits under 2.3.4 3.7 21 Radiation normal or emergency conditions.

Control Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3.15 3.1 23 portable survey instruments, personnel monitoring equipment, etc.

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 2.3.5 2.3.11 Subtotal 2.4.50 2.4.40

4.

Emergency Procedures I 2.4.25 Plan 2.4.46 2.4.2 Subtotal Tier 3 Point Total Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Ability to control radiation releases.

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Knowledge of SRO responsibilities in emergency plan implementation.

Knowledge of fire protection procedures.

Ability to verify that the alarms are consistent with the plant conditions.

Knowledge of system set pOints, interlocks and automatic actions associated with EOP entry conditions.

2.9 71 3.8 74 3

2 4.0 22 4.5 25 3.3 72 4.2 73 4.5 75 3

2 10 7

ES-401

=

Randomly Tier,..

Selected KIA 1--

215005 R02/1 K3.08 262002 RO 2/1 K6.01 300000 RO 2/1 A3.02 211000 RO 2/1 A2.02 223001 R02/2 K5.01 201006 R02/2 K6.01 204000 R02/2 A3.05 259001 R02/2 2.4.34 290002 R02/2 A2.05 600000 RO 1/1 AK1.02 295021 RO 1/1 AK2.03 295001 RO 1/1 AA1.01 Record of Rejected KIA's Form ES-401-4 Reason for Rejection 215005 K3.0'1 was very close in content to another KA in the outline (212000 K1.01: Relation between APRMs and RPS) and has been replaced. KA 215005 K3.08 (3.0/3.4) was randomly selected as a replacement.

262002 K6.03 UPS at Oyster Creek (Vital AC) does not utilize static inverters. KA 262002 K6.01 (2.7/2.9) was randomly selected as a replacement.

300000 K2.011 This KA is on the candidates' audit examination. KA 300000 A3.02 (2.9/2.7) was randomly selected as a replacement.

211000 A3.01 This KA is related to the automatic operation of the SLC System. The SLC System at Oyster Creek has no automatic operation. 211000 A2.02 (3.6/3.9) was randomly selected as a replacement.

223001 K5.10 An operationally relevant question could not be developed. KA 223001 K5.01 (3.1/3.3) was randomly selected as a replacement.

201006 K6.04 The RWM does not lose functionality upon the loss of the Process Computer. KA 201006 K6.01 (2.8/3.2) was randomly selected as a replacement.

204000 A3.02 There is no automatic response of the RWCU System related to reactor water quality. KA 204000 A3.05 (2.8/2.8) was randomly selected as a replacement.

2710002.4.34 An operationally relevant question could not be developed. KA 259001 G2.4.34 (4.2/4.1) was randomly selected as a replacement.

290002 A2.0~1 An operationally relevant question could not be developed. KA 290002 A2.05 (3.7/4.2) was randomly selected as a replacement.

600000 AK1.01 An operationally relevant question could not be developed. KA 600000 AK1.02 (2.9/3.1) was randoml~r selected as a replacement.

295021 AK2.06 An operationally relevant question could not be developed. KA 295021 AK2.03 (3.6/3.6) was randomly selected as a replacement.

295001 AA1'()3 This KA is very close to question on the candidates' audit exam. 295001 AA1.01 (3.513.6) was randomly selected as a replacement.

ES-401 RO 1/1 RO 1/1 RO 1/2 RO 1/2 R03 R03 R03 SRO 1/1 SRO 2/1 SRO 2/1 SRO 2/1 SRO 2/2 SR03 SR03 295038 EA1.07 295005 G2.2.37 295007 G2.1.7 295022 G2.2.2 G2.2.36 G2.2.14 G2.4.2 295038 G2.4.11 211000 G2.4.4 263000 G2.1.30 400000 G2.4.16 259001 A2.08 G2.2.36 G2.4.40 Record of Rejected KIA's Form ES-401-4 295038 EA 1.05 The PASS System is neither monitored nor operated by Licensed Operators. KA 295038 EA 1.01 (3.9/4.2) was randomly selected as a replacement.

295005 G2.2.4 This KA applies to a dual-unit facility.

Oyster Creek is a single-unit facility. KA 259005 G2.2.37 (3.6/4.6) was randomly selected as a replacement.

295007 G2.1.27 An operationally relevant question could not be developed. KA 295007 G2.1.7 (4.4/4.7) was randomly selected as a replacement.

295022 G2.2.25 There is no safety limit associated with loss of CRD Pumps and LCO bases for loss of CRD Pumps is not appropriate at the RO level. KA 295022 G2.2.2 (4.6/4.1) was randomly selected as a replacement.

G2.2.39 This KA is not appropriate at the RO level. KA G2.2.36 (3.1/4.2) was randomly selected as a replacement.

G2.2.17 An operationally relevant question could not be developed. G2.2.14 (3.9/4.3) was randomly selected as a replacement.

G2.4.22 An operationally relevant question could not be developed. G2.4.2 (4.5/4.6) was randomly selected as a replacement.

295030 G2.4..11 Oyster Creek has no abnormal condition proc;edure (ABN) related to low Suppression Pool water level. KA 295038 G2.4.11 (4.0/4.2) was randomly selected as a replacement.

223002 G2.4..34 An operationally relevant question could not be developed. KA 211000 G2.4.4 (4.5/4.7) was randomly selected as a replacement.

300000 G2.1.. 30 An operationally relevant question could not be developed. KA 213000 G2.1.30 (4.4/4.0) was randomly selected as a replacement.

400000 G2.4.3 An operationally relevant question could not be developed. KA 400000 G2.4.16 (3.5/4.4) was randomly selected as a replacement.

239001 A2.06 An operationally relevant question could not be developed. KA 259001 A2.08 (2.5/2.6) was randomly selected as a replacement.

G2.2.39 An operationally relevant question could not be developed. KA G2.2.36 (3.1/4.2) was randomly selected as a replacement.

G2.4.27 An operationally relevant question could not be developed. KA G2.4.40 (2.7/4.5) was randomly

ES-401 Record of Rejected KIA's Form ES-401-4 selected as a replacement.

295017 AK1.03 An operationally relevant question 295017 RO 1/2 could not be developed. KA 295017 AK1.02 (3.8/4.3)

AK1.02 was randomly selected as a replacement.

ES*301 Administrative

()DICS Outline Form ES*301*1 Facility: O~ster Creek Date of Examination: Ma~ 17, 2010 Examination Level: RO 0 SRO [8J Operating Test Number: OC 2010 Administrative Topic Type Describe activity to be performed (See Note)

Code*

Coordinate Personnel Activities Outside the Control Conduct of Operations N,R Room: G2.1.8 (4.1)

Conduct of Operations M,R Apply Work Hour Rules; G2.1.5 (3.9)

Review Completed Surveillance Test 619.3.016, High Equipment Control N,R Drywell Pressure Scram Test And Calibration; G2.2.12 (4.1 )

Determine Recommendation for Kllssuance for Off-site Radiation Control N,R Emergency Workers And On-site Personnel During An Emergency; G2.3.14 (3.8)

Classify An Emergency And Initiate A State/Local Emergency Procedures/Plan M,R Notification Form and PAR Notification Form; G2.4.40 (4.5)

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

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: O~ster Creek Date of Examination: Ma~ 17,2010 Examination Level: RO r8l SRO D Operating Test Number: OC 2010 Administrative Topic Type Describe activity to be performed (See Note)

Code*

Determine Thermal Limit Restrictions with the EPR Out of Conduct of Operations N,R Service lAW 202.1; G2.1.7 (4.4) [RO Admin JPM1]

Perform Week 4 of 680.4.007, Safety Related Equipment Conduct of Operations D,S Verification; G2.1.29 (4.1) [RO Admin JPM2]

Perform Manual Core Heat Balance Calculation lAW Equipment Control D,R,P 1001.6; G2.2.12 (3.7) [RO Admin JPM3]

Radiation Control Perform Actions of Shift Communicator During an Emergency Procedures/Plan M,S Emergency; G2.4.39 (3.9) [RO Admin JPM4]

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

ES 301, Page 22 of 27

ES*301 Control Roomlln-Plant Systems Outline Form ES-301-2

~------------------------------

Facility Oy:ster Creek Date of Examination: May: 17, 2010 Exam Level: RO 0 SRO-ID SRO-U [8'J Operating Test Number: OC 2010 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a.
b.
c.
d. Shutdown Core Spray with Actuating Signals Present (Alternate Path);

D,A,EN 4

209001 A4.01 (3.8/3.6) [Sim4]

e. Purge the Primary Containment (Alternate Path); 223001 A4.07 (4.2/4.1)

N,A 5

[SimS]

f. De-energize 1A1 Transformer by Cross-tieing USS 1A1 to USS 1 B1; N, L 6

262001 A 1.05 (3.2/3.5) [Sim6]

g.
h.

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

i. Vent the Control Rod Drive Over Piston Volume; 201003 A2.01 (3.4/3.6)

D,R, E 1

[Plant1]

j. Inject the CST via Core Spray; 209001 Ai.08 (3.3/3.2) [Plant2]

D,R, E 2

k.

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-II SRO-U (A)lternate path 4-61 4-6 I 2-3 (C )ontrol room (D}irect from bank
.91 ::.8 1 ::. 4 (E)mergency or abnormal in-plant
1 I
1 I ::: 1 (EN}gineered safety feature

- I

/ ::: 1 (control room system (L)ow-Power 1Shutdown

1 I
.1

/ :::. 1 (N)ew or (M)odified from bank including 1(A)

21 :::.2 1 :::. 1 (P)revious 2 exams
s. 31 :s.3 1 ::. 2 (randomly selected)

(R)CA

1 / :::.1 1 :::. 1 (S)imulator ES-301, Page-23 of 27

ES*301 Control Room/In-Plant....l:Ol'ornco Outline Form ES*301*2 Facility: Oyster Creek Date of Examination: May 17, 2010 Exam Level: RO [8J SRO-I D SRO-U D Operating Test Number: OC 2010 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System I JPM Title Type Code*

Function

a. Perform Recirculation Pumps Trip Circuitry Test, 603.4.001 wI Multiple P, D,A 1

Recirculation Pump Trips (Alternate Path); 202001 A2.04 (3,7/3,8) [Sim

~IPM11 b, Shutdown Second RWCU Pump; 204000 A4,01 (3,1/3,0) [Sim JPM2]

D 2

c, Transfer to the MPR and Raise RPV Pressure; 241000 A4.01 (3.8/3,8)

M 3

[Sim JPM3]

d, Shutdown Core Spray with Actuating Signals Present (Alternate Path);

D,A,EN 4

209001 A4,01 {3.8/3,6} [Sim JPM4]

e, Purge the Primary Containment (Alternate Path); 223001 A4.07 (4.2/4,1)

N,A 5

[Sim JPM5]

f. De-energize 1A1 Transformer by Cross-tieing USS 1A1 to USS 1B1; N, L 6

262001 At,05 (3.2/3.5) [Sim JPM6]

~a Substitute Control Rod Position in the RWM and Initiate the M

7 Ops Mode; 201006 A4.02 (2.9/2.9) [Sim JPM7]

h. Restart RB Ventilation System with Fan Failure (AltE~rnate Path); 288000 N,A 9

A4,01 (3.1/2,9) [Sim JPM8]

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

i. Vent the Control Rod Drive Over Piston Volume; 201003 A2.01 (3.4/3.6)

D,R, E 1

[Plant JPM1]

j, Inject the CST via Core Spray; 209001 A1.08 (3.3/3.2) [Plant JPM2]

D,R,E 2

k, Swap Static Chargers from C1 to C2; 263000 K1.02 (3.2/3.3) [Plant D,R 6

JPM3]

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 1SRO-I I SRO-U I

(A)lternate path 4-6/ 4-6 2-3 (C)ontrol room (D)irect from bank

~9/ ~8

~4 (E)rnergency or abnormal in-plant

~ 1 /

~1 / ~ 1 (EN)gineered safety feature

/

/ ~ 1 (control room system (L)ow-Power / Shutdown

~ 1 /

~1 / ~ 1 (N)ew or (M)odified from bank including 1 (A)

~2/ ~2 / ~ 1 (P)revious 2 exams

~ 3 /

~3 / ~ 2 (randomly selected)

(R)CA

~ 1 /

~1 / ~ 1 (S )imulator ES-301, Page 23 of 27

ES*301 Control Room/In-Plant ~U'II:I'I:Io""Ct Outline Form ES-301*2 Facility O~ster Creek Date of Examination: Ma~ 17, 2010 Exam Level: RO 0 SRO-I ~ SRO-U 0 Operating Test Number: OC 2010 IControl Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title I Type Code*

Safety Function r----"

a. Perform Recirculation Pumps Trip Circuitry Test, 603.4.001 w/ Multiple P,D,A 1

Recirculation Pump Trips (Alternate Path); 202001 A2.04 (3.7/3.8)

[Sim1]

b.
c. Transfer to the MPR and Raise RPV Pressure; 241000 A4.01 (3.8/3.8)

M 3

[Sim3]

d. Shutdown Core Spray with Actuating Signals Present (Alternate Path);

D,A, EN 4

209001 A4.01 (3.8/3.6) [Sim4]

e. Purge the Primary Containment (Alternate Path); 223001 A4.07 (4.2/4.1)

N,A 5

[Sim5]

f. De-energize 1 A 1 Transformer by Cross-tieing USS 1 A 1 to USS 1 B 1; N, L 6

262001 A1.05 (3.2/3.5) [Sim6)

g. Delete a Substitute Control Rod Position in the RWM and Initiate the M

7 Power Ops Mode; 201006 A4.02 (2.9/2.9) [Sim7j

h. Restart RB Ventilation System with Fan Failure (Altj~rnate Path); 288000 N,A 9

A4.01 (3.1/2.9) [Sim8]

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

L Vent the Control Rod Drive Over Piston Volume; 201003 A2.01 (3.4/3.6)

D,R, E 1

[Plant1)

j. Inject the CST via Core Spray; 209001 A 1.08 (3.3/3.2) [Plant2]

D, R, E 2

k. Swap Static Chargers from C1 to C2; 263000 K1.02 (3.2/3.3) [Plant2]

D,R 6

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I/ SRO-U I

(A)lternate path 4-6/ 4-6 / 2-3 (C)ontrol room (D)irect from bank

~91 ~8 / ~4 (E)mergency or abnormal in-plant

~ 1 /

~1 I ~ 1 (EN)gineered safety feature

/

I ~ 1 (control room system (L)ow-Power / Shutdown

~ 1 I

~1 / ~ 1 (N)ew or (M)odified from bank including 1 (A)

~21 ~2 I ~ 1 (P)revious 2 exams

~ 31

~3 I ~ 2 (randomly selected)

(R)CA

~ 1 1 ~1 / ~ 1 (S)imulator ES-301, Page 23 of 27

Oyster Creek 09-1 NRC Exam Scenario SCElnario Outline Facility: Oyster Creek Scenario No.:.-4 Op Test No.: OC 2010 Examiners:

Operators:

Initial Conditions:

14% power during a startup (IC 152)

The RWM is Inoperable and Bypassed Control Room HVC System A is inoperable Turnover:

Startup in progress Event Description 1

NA N

BOP Swaps Service Water Pumps 2

NA R

ATC Withdraws control rods to raise reactor power 3

MAL-C ATC Respond to indications of a stuck control rod CRDOO7 MAL-C BOP 4

Respond to the loss of Vital Bus 1 B2 EDSOO4B TS SRO LOA RCP003 MAL-C BOP Responds to Recirculation Pump C inner seal failure, then 5

RCPOO3C TS SRO outer seal failure MAL RCPOO4C 6

MAL-C ATC Responds to an open EMRV leading to a manual scram NSS025C CAEP

'7 M

All s to an electric A TWS ATWS PMP SLCOO1A 8

PMP-C RO Respond to Standby Liquid Control Pump shaft break SLCOO2A (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC SIM SCENARIO 4 Page 1 of 26

Oyster Creek 09-1 NRC Exam Scenario Sc!nario Outline Facility: Oyster Creek Scenariio No.: ~

Op Test No.: OC 2010 Examiners:

Operators:

Initial Conditions:

The plant Is at 100% power Air Compressor 3 is tagged out of service Turnover:

Reduce power lAW the ReMA Perform 323.6, Backwashing Condensers Event No.

Malf. No.

Event Type*

Event Description 1

NA R

ATC Reduces reactor power with recirculation flow to 97%

Performs Condenser A North Condenser Backwash 2

NA N

BOP procedure MAL-Respond to Standby Liquid Control System 1 loss of squib 3

TS SRO SLCOO3A continuity BKR RFCOO1 4

C BOP Respond to abnormalities on Recirculation Pump A MAL RFCOO2A MAL-C 5

All Respond to the loss of 480 VAC USS 1 A2 EDSOO3B TS BKR CRDOO1 MAL-Respond to CRD Pump NC08B trip leads to a manual 6

C ATC CRD010 scram; Four control rods remain at position 48 MAL CRDOO7 MAL M

NSSOO5C 7

All Respond to primary coolant leak in the Drywell MAL C

PCNOO8 8

VLV-C All Respond to the loss of Drywell Sprays CNSOO5 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC SIM SCENARIO 3 Page 1 of 31

Oyster Creek 09-1 NRC Exam Scenario SCE!nario Outline Facility: Oyster Creek Scenario No.: ~

Op Test No.: OC 2010 Examiners:

Operators:

Initial Conditions:

The plant is at 90% power

Perform Anticipatory Scram Turbine Stop Valve Closure Test (>45% Load), 619.4.002 Raise reactor power to rated No.

Event Type*

Event Description Perform Anticipatory Scram Turbine Stop Valve Closure 1

NA N

BOP Test (>45% Load), 619.4.002 2

NA R

ATC Raise reactor power to 100% with Recirculation Flow ICH NSS118A I

ATC Responds to RE05B RPV water level instrument failure 3

RLY-TS SRO (low) without the expected Y2 scram response on RPS 1 RPS010B 4

MAL-C BOP Responds to trip of Stearn Packing Exhauster 1 MSSOO5A CNH FWHOO1B 5

CNH-C ATC Responds to partial loss of feedwater heating FWH004B CNH FWHOO7B MAL-I BOP 6

Responds to EMRV acoustic monitor failure (NR108C)

NSS026C TS SRO MAL-Responds to rising main steam and offgas radiation 7

M All RSXOO1 monitors due to fuel failures VLV ICSOO5 VLV-Responds to unisolable Isolation Condenser steam leak 8

C All Icsooe with fuel failures leading to Emergency Depressurization MAL ICSOO3A (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC SIM SCENARIO 2 Page 1 of 25

Oyster Creek 09-1 I\\lRC Exam Scenario Scenario Outline Facility: Oyster Creek Scenario No.: -1 Op Test No.: OC 2010 Examiners:

Operators:

Initial Conditions:

  • The plant is at 97% power
  • RWCU Pump B is tagged out of service
  1. 3 air compressor is tagged out of service Turnover:

Event Type* I Event No.

Description I

I I

I 1

NA N

BOP Perform Automatic Scram Contactor Test, 619.4.025 2

NA R

ATC Withdraw control rods lAW the ReMA ATC MAL C

3 CRDOO5_18 BOP Responds to a continuously outward drifting control rod 35 TS SRO VLV RCUOO1 VLV RCUOO4 C

BOP Responds to RWCU System high pressure and failure of 4

BKR-TS SRO system to automatically isolate RCUOO1 MAL RCUOO7 MAL-I ATC Respond to leak in GEMAC water level indicators ID13A 5

NSS012E TS SRO and ID13C MAL 6

C ATC Respond to multiple drifting control rods CRDOO6 MAL-Respond to an RPV coolant leak in the Primary 7

M All NSSOO5 Containment MAL OEDOO1B Respond to the loss of Startup Transformer Band MFRV A a

C All MAL-Closure FWCOO3A (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC SIM SCENARIO 1 Page 1 of 28

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