ML112130525

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Final Outlines (Folder 3)
ML112130525
Person / Time
Site: Oyster Creek
Issue date: 07/11/2011
From:
Exelon Nuclear
To: Todd Fish
Operations Branch I
Hansell S
Shared Package
ML110030666 List:
References
TAC U01831
Download: ML112130525 (25)
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Text

ES-401 Written Examination Outline Form ES-401-1 Oyster Creek ILT 10-1 Facility:

Date of Exam:

07/11/11 NRC Exam Outline Tier Grou P

K 1

K 2

RO KIA Category Points K

K K

K A

A A

3 4

5 6

1 2

3 A

4 G

Tota I

SRO-Only Points A2 G*

Total

1.

1 3

4 3

3 4

3 20 4

3 7

Emergenc y

2 1

1 1

1 1

2 7

1 2

3 Plant Evolutions Tier Total 4

5 4

4 5

5 27 5

5 10 s

2 2

2 2

3 2

3 2

2 3

3 26 3

2 5

2.

Plant 2

1 1

2 1

1 1 1 1

1 1

1 12 o 11 2

3 Systems Tier Total 3

3 4

3 4

3 4

3 3

4 4

38 4

4 8

s

3. Generic Knowledge & Abilities Categories 1

2 FR 3

2 4

3 10 ITH1:

4 1

7 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 paint 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.1.b of ES-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) 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) KlAs 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 KIA's

8.

On the following pages, enter the KIA 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 does not apply). Use duplicate pages for RO and SRO-onlyexams.

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

ES-401 Written Examination Outline Form ES-401-1 linked to 10CFR55.43

ES-401 2

Oyster Creek IL T 10-1 NRC Exam Outline Written Examination Outline Emergency and Abnormal Plant Evolutions -- Tier 1 Group 1 IEAPE # I Name Safety Function IK1 295006 SCRAM 11 295004 Partial or Total Loss of DCPwr/6 295003 Partial or Complete LossofAC/6 295026 Suppression Pool High Water Temp. 15 295037 SCRAM Conditions Present and Reactor Power Above APRM Downscale or Unknown I 1 295021 loss of Shutdown Cooling 14 295030 Low Suppression Pool Water Level 15 700000 Generator Voltage and X

Electric Grid Disturbances 295004 Partial or Total Loss of X

DCPwr/6 295005 Main Turbine X

Generator Trip I 3 295023 Refueling Acc Cooling Mode/8 295038 High Off-site Release Rate 19 295028 High Drywall Temperature 15 295031 Reactor Low Water Level 12 KIA Topic(s)

IK2 IK3 IA 1 I A2 I G I I

X X

X

}I AA2.05 - Ability to detennine and/or X

interpret the following as they apply to SCRAM: Whether a reactor SCRAM has occurred AA2.01 - Ability to determine and/or interpret the following as they apply to X

PARTIAL OR COMPLETE LOSS OF D.C. POWER: Cause of partial or complete loss of D.C. power AA2.05 - Ability to detennine and/or interpret the following as they apply to X

PARTIAL OR COMPLETE LOSS OF A.C. POWER: Whether a partial or complete loss of A.C. power has occurred X

2.2.38 - Knowledge of conditions and limitations in the facility license.

2.4.8

  • Emergency Procedures I Plan:

X Knowledge of how abnormal operating procedures are used in conjunction v.1th EOP's.

2.4.45 - Ability to prioritize and interpret X

the significance of each annunciator or alann.

EA2.03 - Ability to detennine and/or X

interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Reactor pressure AK1.01 - Knowledge of the operational implications of the following concepts as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES and the following:

Over-excitation AK1.05 - Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Loss of breaker protection AK1.01 - Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP: Pressure effects on reactor power AK2.02 - Knowledge of the interrelations between REFUELING ACCIDENTS and the following: Fuel pool coolin!:! and cleanup system EK2.03 - Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following:

Plant ventilation systems EK2.01 - Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following:

Drywall spray: Mark-I&II EK3.04 - Knowledge of the reasons for the following responses as they apply to REACTOR LOW WATER LEVEL:

Steam cooling limp.

Q#

4.6 1

3 4.5 5

'k3 6

3.9 7

3.3 39

t3 40 4.0 41 2.9 42 3.6 43 3.7 44 4.0 45

ES-401 2

Form ES-401-1 Oyster Creek ILT 10-1 NRC Exam Outline Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function KIA Topic(s)

AK3.02 - Knowledge of the reasons for 295021 Loss of Shutdown the following responses as they apply to X

~.3 46 Cooling 14 LOSS OF SHUTDOWN COOLING:

FeedinQ and bleedinQ reactor vessel EK3.04 - Knowledge of the reasons for 295024 High Drywall Pressure /

the following responses as they apply to X

3.7 47 5

HIGH DRYWELL PRESSURE:

EmerQencv depressurization AA 1.09 - Ability to operate and/or monitor the following as they apply to +

295016 Control Room X

CONTROL ROOM ABANDONMENT:

4.0 48 Abandonment / 7 Isolation/emergency condenser(s):

"'c AA 1.03 - Ability to operate and/or monitor the following as they apply to 295003 Partial or Complete X

PARTIAL OR COMPLETE LOSS OF 4.4 49 LossofAC/6 A.C. POWER: Systems necessary to assure safe plant shutdown EA 1.06 - Ability to operate and/or 295025 High Reactor Pressure monitor the following as they apply to X

4.5 50 13 HIGH REACTOR PRESSURE: Isolation condenser: Plant-Specific EA2.03 - Ability to determine and/or 295026 Suppression Pool High interpret the following as they apply to X

3.9 51 WaterTemp./5 SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor pressure AA2.02 - Ability to determine and interpret the following as they apply to 600000 Plant Fire On-site / 8 X

2.8 PLANT FIRE ON SITE: Damper position AA2.01 - Ability to determine and/or interpret the fonowing as they apply to 295018 Partial or Total Loss of X

PARTIAL OR COMPLETE LOSS OF 3.3 53 CCW/8 COMPONENT COOLING WATER:

eratures 2.1.31 - Ability to locate control room 295019 Partial or Total Loss of switches, controls, and indications. and X

4.6 54 Inst. Air 18 to determine that they correctly reflect the desired plant lineup.

2.4.4 - Ability to recognize abnormal indications for system operating 295006 SCRAM /1 X

parameters that are entry-level 4.5 55 conditions for emergency and abnormal operatinQ procedures.

2.4.20 - Emergency Procedures / Plan:

295025 High Reactor Pressure X

Knowledge of operational implications

t8 56 13 of EOP warnings, cautions. and notes.

AA2.03 - Ability to determine and/or 295001 Partial or Complete interpret the following as they apply to Loss of Forced Core Flow X

PARTIAL OR COMPLETE LOSS OF 3.3 57 Circulation /1 & 4 FORCED CORE FLOW CIRCULATION

Actual core flow EK2.14 - Knowledge of the 295037 SCRAM Conditions interrelations between SCRAM Present and Reactor Power CONDITION PRESENT AND X

3.6 58 Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown 11 DOWNSCALE OR UNKNOWN and the following: RPIS: Plant-Specific KIA Category Totals:

3 4

3 3

414 3/3 Group Point Total:

I 20n

ES-401 3

Form ES-401-1 Oyster Creek IL T 10-1 NRC Exam Outline Written Examination Outline Emergency and Abnormal Plant Evolutions.- Tier 1 Group 2 EAPE # I Name Safety Function KIA Topic(s}

EA2.01 - Ability to determine andtor 295033 High Secondary interpret the following as they apply to Containment Area Radiation X

HIGH SECONDARY CONTAINMENT 3.9 8

Levels 19 AREA RADIATION LEVELS: Area radiation levels 2.1.32 - C.onduct of Operations: AbIlity to 295029 High Suppression Pool X

explain and apply all system limits and 4.0 9

Water Level 15 precautions.

2.2.44 - Equipment Control: Ability to interpret control room indications to 295020lnadvertentCont verify the status and operation of a X

4.4 10 Isolation 15 & 7 system. and understand how operator actions and directives effect plant and system oonditions.

EK1.03 - Knowledge of the operational implications of the following concepts as 295032 High Secondary they apply to HIGH SECONDARY 3.

Containment Area Temperature X

CONTAINMENT AREA 59 5

15 TEMPERATURE: Secondary containment leakage detection: Plant-Specific AK2.01 - Knowledge of the interrelations between HIGH 295013 High Suppression Pool 3.6 X

SUPPRESSION POOL 60 Temperature f 5 TEMPERATURE and the following:

Suppression pool cooling AK3.05 - Knowledge of the reasons for 295010 High Drywall Pressure the following responses as they apply to

3.

X 61 15 HIGH DRYWELL PRESSURE:

5 Temperature monitoring AA 1.06 - Ability to operate and/or monitor the following as they apply to 295002 Loss of Main 3.

X LOSS OF MAIN CONDENSER 62 Condenser Vac I 3 0

VACUUM: Reactorlturbine pressure regulating system AA2.01 - Ability to determine and/or 295022 Loss of CRD Pumps I interpret the following as they apply to

3.

X 63 1

LOSS OF CRD PUMPS: Accumulator 5

pressure 2.4.35 - Emergency Procedures I Plan:

295036 Secondary Knowledge of local auxiliary operator 3.

Containment High Sump/Area X

64 tasks during emergency and the 8

Water Level 15 resultant operational effects.

2.4.8 - Emergency Procedures I Plan:

295009 Low Reactor Water Knowledge of how abnormal operating

3.

X 65 Level 12 procedures are used in conjunction with 8

EOP*s.

KIA category Totals:

1 I 1 1

1/1 212 Group Point Total:

I 7/3 1

ES-401 4

Form ES-401-1 Oyster Creek ILT 10-1 NRC Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 System # I Name KKK K K 1

2 345 G

A2.04 - Ability to (a) predict the Impacts of the following on the REACTOR WATER LEVEL 259002 Reactor Water Level Control System X

CONTROL SYSTEM and (b) based on those predictions. use procedures to correct, control, or mitigate the consequences of those abnormal operation: RFP runout condition: Plant-Specific A2.15 - Ability to (a) predict the Impacts of the foIlo'Ning on the STANDBY GAS TREATMENT SYSTEM; and (b) based on 261000SGTS X

those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High area radiation bY refuel bridge: Plant~ecific 2.4.9 - Emergency Procedures I Plan: Knowiedge of low power I 218000 ADS X

shutdown implications in accident (e.g.* loss of coolant a(:cident or loss of residual heat removal) mitigation strategies.

2.4.46 - Emergency Procedures 215005 APRM I LPRM X

I Plan: Ability to verify that the alarms are consistent 'Nith the

"'plant conditions.

A2.01 - Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on 212000 RPS X

those predictions, use procedures to correct. control, or mitigate the consequences of those abnormal conditions or operations: RPS motor-generator set failure K 1.06 - Knowledge of the physical connections and/or cause-effect relationships 218000 ADS X

between AUTOMATIC DEPRESSURIZATION SYSTEM and the following: Safety/relief valves K1.05 - Knowledge of the physical connections and/or cause-effect relationships 205000 Shutdown Cooling X

between SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following: Component cooling water ~stems 400000 Component Cooling Water X

K2.02 - Knowledge of electrical power supplies to the following:

CCWvalves Imp Q#

3.1 11 3.4 12 4.2 13 4.2 14 3.9 15

~1.9 1

3.1 2

.2.9

ES-401 4

Form ES-401-1 Oyster Creek ILT 10-1 NRC Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A2 A

3 A

4 G

Imp Q#

263000 DC Electrical Distribution 209001 LPCS 207000 Isolation (Emergency) Condenser 223002 PCIS/Nuclear Steam Supply Shutoff 212000 RPS 264000 EDGs 262001 AC Electrical Distribution 262002 UPS (AC/DC) 215004 Source Range Monitor K2.01 - Knowledge of electrical X

power supplies to the following:

Maior D.C. loads K3.03 - Knowledge of the effect that a loss or malfunction of the X

LOW PRESSURE CORE SPRAY SYSTEM will have on following: Emergency aenerators K3.02 - Knowledge of the effect that a loss or malfunction of the ISOLATION (EMERGENCY)

X CONDENSER will have on following: Reactor water level (EPG's address the isolation condenser as a water source):

BWR-2,3 K4.06 - Knowledge of PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF design X

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

Once initiated, system reset requires deliberate operator action K4.03 - Knowledge of REACTOR PROTECTION SYSTEM design feature(s)

X and/or interlocks which provide for the following: The prevention of supplying power to a given RPS bus from multiple sources simultaneously K5.06 - Knowledge of the operational implications of the X

following concepts as they apply to EMERGENCY GENERATORS (DIESEUJET):

Load seQuencina K5.01 - Knowledge of the operational implications of the following concepts as they X

apply to A.C. ELECTRICAL DISTRIBUTION: Principle involved with paralleling two A.C. sources K6.01 - Knowledge of the effect that a loss or malfunction of the X

following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C.!D.C.) : A.C.

electrical power K6.04 - Knowledge of the effect that a loss or malfunction of the X

following will have on the SOURCE RANGE MONITOR (SRH) SYSTEM: Detectors 3.1 2.9 3.8 3.4

~I.O 3.4

~1.1 2.7 2.9 4

5 6

7 8

9 10 11 12

ES-401 4

Form ES-401-1 Oyster Creek ILT 10-1 NRC Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G

1 2 3

4 5

6 1

3 4

~

259002 Reactor Water Level Control 261000 SGTS 215005 APRM / LPRM 239002SRVs 2150031RM 211000 SLC 300000 Instrument Air 263000 DC Electrical Distribution 223002 PCIS/Nuclear Steam Supply Shutoff 261000 SGTS A 1.05 - Ability to predict and/or monitor changes in parameters associated with operating the X

REACTOR WATER LEVEL CONTROL SYSTEM controls including: FWRVlstartup level control position: Plant-Specific.

A1.04 - Ability to predict and/or monitor changes in parameters associated with operating the X

STANDBY GAS TREATMENT SYSTEM controls including:

Secondary containment differential pressure A2.05 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITORILOCAL POWER RANGE MONITOR SYSTEM; X

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions Loss of recirculation flow signal A2.05 - Ability to (a) predict the impacts of the following on the RELIEF/SAFETYVALVES; and (b) based on those predictions, X

use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low reactor pressure A3.03 - Ability to monitor automatic operations of the X

INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including: RPS status A4.06 - Ability to manually X

operate and/or monitor in the control room: RWCU system isolatio ific Ability to manually X

and/or monitor in the am: Pressure~~es A4.01 - Ability to manually operate and/or monitor in the X

control room: Major breakers and control power fuses: Plant-Specific 2.'1.30 - Conduct of Operations:

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

2.4.31 - Emergency Procedures X

I Plan: Knowledge of annunciator alarms. indications, or response procedures.

2.9 3.0 3.5

~i.2 3.7 3.9 2.6 3.3 4.4 4.2 13 14 15 16 17 18 19 20 21 22

4 Form ES-401-1 Oyster Creek IL T 10-1 NRC Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 1 KKKKKKAA2 A A System # 1Name G

1 2

3 4 561 3

4 K5.04 - Knowledge of the operational implications of the following concepts as they apply 211000 SLC X

3.1 23 to STANDBY LIQUID CONTROL SYSTEM: Explosive valve A3.01 - Ability to monitor automatic operations of the UNINTERRUPTABLE POWER 262002 UPS (ACfDC) 2.8 24 SUPPLY (A.C.fD.C.) including:

Transfer from preferred to alternate source A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 264000EDGs X

3.0 25 EMERGENCY GENERATORS (DIESEUJET) controls including:

Lube oil temperature 2.4.47 - Emergency Procedures 1Plan: Ability to diagnose and recognize trends in an accurate 218000 ADS X

4.2 26 and timely manner utilizing the appropriate control room reference material.

KIA category Totals:

2 2

2 2

2 2

3 3/3 3

2 3/2 Group Point Total:

I 2615

ES-401 5

Form ES-401-1 System # / Name 256000 Reactor Condensate 201002 RMCS 215001 Traversing In-Core Probe 215001 Traversing In-core Probe 201001 CRD Hydraulic 239001 Main and Reheat Steam 201003 Control Rod and Drive Mechanism 202002 Recirculation Flow Control 241000 Reactorrrurbine Pressure Regulating System 219000 RHRlLPCI:

Torus/Suppression Pool Cooling Mode Oyster Creek ILT 10-1 NRC Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A2 1 2 3 4 5

6 1

~ ~ ~

A2.15

  • AbiHty to (a) predict the impacts of the following on the REACTOR CONDENSATE SYSTEM; and (b) based on X

those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Abnormal water Quality 2.2.40 - Ability to apply X

Technical Specifications for a syStem.

2.1.32 - Ability to explain and X

apply system limits and precautions.

K 1.10

  • Knowledge of the physical connections and/or cause-effect relationships X

bEltween TRAVERSING IN*

CORE PROBE and the following: Area radiation monitoring system: (Not-BWR1)

K2.05 - Knowledge of electrical X

power supplies to the following:

Alternate rod insertion valve solenoids: PlanM~pecific K3.16 - Knowledge of the effect that a loss or malfunction of the X

MAIN AND REHEAT STEAM SYSTEM will have on following:

Relief/safety valves K4.02 - Knowledge of CONTROL ROD AND DRIVE X

MECHANISM design feature(s) and/or interlocks which provide for the following: Detection of an uncoupled rod K5.02 - Knowledge of the operational implications of the X

following concepts as they apply to RECIRCULATION FLOW CONTROL SYSTEM:

Feedback signals K6.07 Knowledge of the effect that a loss or malfunction of the following will have on the X

REACTORrrURBINE PRESSURE REGULATING SYSTEM: Turbine inlet pressure A1.07

  • AbiHty to predict andlor monitor changes in parameters associated with operating the X

RHRlLPCI:

TORUS/SUPPRESSION POOL COOLING MODE controls including: Emergency generator loading Q

Imp.

3.3 16 4.7 17 4.0 18 2.6 27 4.5 28 3.6 29 a.8 30 2.6 31 3.4 32

~1.2 33

ES-401 5

Form ES-401-1 Oyster Creek IL T 10-1 NRC Exam Outline Written Examination Outline Plant Systems - Tier 2 Group 2 System # 1Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A2 A

3 A

4 G

A2.06 - Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM; and (b) based on those 202001 Recirculation X

predictions. use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadvertent recirculation flow decrease A3.02 - Ability to monitor 234000 Fuel Handling Equipment X

automatic operations of the FUEL HANDLING EQUIPMENT including: tlnter10ck operation A4.02 - Ability to manually 259001 Reactor Feedwater X

operate and/or monitor in the control room: Manually start/control a RFPrrDRFP 2.1.28 - Conduct of Operations:

204QOORWCU X

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

K3.02 - Knowledge of the effect 216000 Nuclear Boiler Instrumentation X

that a loss or malfunction of the NUCLEAR BOILER Instrumentation will have on following: PCIS/NSSSS KIA Category Totals:

2 1

1 1

1 1

112 Group Point Total:

a Imp.

~1.6 34 3.1 35 3.9 36 4.1 37 4.0 38 I

12/3

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

Form ES-401-3 Oyster Creek IL T 10-1 NRC Facility:

Date:

07/11/11 Exam Outline Category KIA #

2.1.36 2.1.37

1.

Conduct of Operations 2.1.20 2.1.28 Subtotal 2.2.22 2.2.11

2.

2.2.1 Equipment Control 2.2.36 2.2.2 Subtotal

3.

2.3.11 Radiation Control 2.3.4 2.3.15 RO SRO-Only Topic IR Q#

IR Q#

Knowledge of procedures and limitations 4.1 19 involved in core alterations.

Knowledge of procedures, guidelines, or limitations associated with reactivity 4.13 23 management.

Ability to interpret and execute procedure 4.6 66 steps.

Knowledge of the purpose and function of 4.1 67 major system components and controls.

2 2

Knowledge of limiting conditions for 4.7 20 operations and safety limits.

Knowledge of the process for controlling 3.3 25 temporary design changes.

l---J-Ability to perform pre-startup procedures for the facility, including operating those controls 4.5 68 associated with plant equipment that could affect reactivity.

I Ability to analyze the effect of maintenance activities, such as degraded power sources, 3.1 69 on the status of limiting conditions for operations.

Ability to manipulate the console controls as required to operate the facility between 4.6 74 shutdown and designated power levels.

3 2

Ability to control radiation releases.

4.3 21 Knowledge of radiation exposure limit.s under 3.7 24 normal or emergency conditions.

Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.9 70 portable survey instruments, personnel monitoring equipment, etc.

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

Form ES-401-3 Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such as 2.3.12 containment entry requirements. fuel handling 3.2 71 responsibilities, access to locked high-radiation areas. aligning filters. etc.

Subtotal 2

2 2.4.6 Knowledge of EOP mitigation strategies.

4.:r 22

4.

2.4.27 Knowledge of "fire in the plant" procedures.

3.4 72

  • Emergency Procedures /

Plan 2.4.1 Knowledge of EOP entry conditions and immediate action steps.

Knowledge of the bases for prioritizing safety 4.6 73 2.4.22 functions during abnormal/emergency 3.6 75 operations.

Subtotal 3

1 Tier 3 Point Total 10 7

ES-401 Record of Rejected KIA's Form ES-401-4 Randomly Tier I Group Reason for Rejection Selected KIA 211000 A3.06 - Oyster Creek does not have an 2/1 RO 211000 A4.06 automatic SLC initiation. A new KIA was randomly selected.

300000 A4.01 - KIA rejected due to overlap with RO question #19. Could not generate a question which 2/1 RO 263000 A4.01 would discriminate from question #19. A new KIA was randomly selected.

211000 A2.03 - KIA rejected due to overlap with Audit 2/1 RO 211000 K5.04 Exam question #17 and NRC Simulator Scenario #2.

A new KIA was randomly selected.

2950262.2.38 - KIA rejected due to no ties to Suppression Pool in the Facility License. A new KIA 1/1 SRO 2950262.2.25 was randomly selected. [KIA 295026 2.2.38 un rejected due to being able to tie Suppression Pool temperature to the Facility License].

2950192.2.38 - KIA rejected due to no ties to 1/1 RO 2950192.1.31 Instrument Air in the Facility License. A new KIA was randomly selected.

201002 2.2.4 - KIA rejected due to Oyster Creek not 2/2 SRO 2010022.240 having a multi-unit license. A new KIA was randomly selected.

233000 2.1.31 - KIA rejected due to not having a 2/2 SRO 233000 2.1.34 10CFR55.43(b) link and KIA 2.1.31 being RO level of knowledge. A new KIA was randoml~ selected.

2.2.3 - KIA rejected due to Oyster Creek not having a 3RO 2.2.1 multi-unit license. A new KIA was randomly selected.

2.2.17 - KIA supports testing at the SRO-Only level, 3RO 2.2.2 but NOT at the RO level due to job responsibilities. A new KIA was randomly selected.

2.3.15 - KIA rejected due to overlap with RO question 3SRO 2.3.11

  1. 70 (also KIA 2.3.15). A new KIA was randomly selected.

2.4.1 - KIA rejected due to supporting testing at the 3SRO 2.4.6 RO level, but not SRO-Only level due to job responsibilities. A new KIA was randomly selected.

234000 K6.07 - An operationally relevant question could not be written due to a loss of RBHVAC having 2/2 RO 241000 K6.07 no specific affect on Fuel Handling Equipment. A new KIA was randomly selected.

256000 A 1.07 - An operationally relevant question 2/2RO 219000 A 1.07 could not be written at an LOD level greater than 1. A new KIA was randomly selected.

~001A2.06 202001 A2.13 - KIA rejected due to being associated

ES-401 2/2 RO 234000 A3.02 2/2 RO 259001 A4.02 2/2RO 216000 K3.02 1/1 RO 295006 2.4.4 1/1 RO 295025 2.4.20 1/2 RO 295032 EK1.03 1/1 SRO 295021 2.4.45 1/1 SRO 295030 EA2.03 2/1SRO 259002 A2.04 2/1 SRO 261000 A2.15 2/1 SRO 212000 A2.11 2/2 SRO 256000 A2.15 2/2 SRO 215001 2.1.32 1/1 RO 700000 AK1.02 1/1 RO 600000 AA2.02 Record of Rejected KIA's Form ES-401-4 with Generic Fundamentals. A new KIA was randomly I selected.

I 290003 A3.02 - KIA rejected due to the Control Room HVAC not having any automatic initiations/failures during a fire. A new KIA was randomly selected.

259001 A4.06 - KIA rejected due to being associated i

with Generic Fundamentals. A new KIA was randomly i selected.

226001 K3.02 - KIA rejected due to concept overlap with NRC Simulator scenario #3 and Audit simulator scenario #1. A new KIA was randomly selected.

295006 2.4.34 - There are no RO tasks outside the Control Room for a Scram, only non-Licensed Operator Tasks. A new KIA was randomly selected.

2950302.4.20 - Low Torus Level EOP does not have any warnings, cautions, or notes. A new KIA was randomly selected.

295032 EK 1.04 - Unable to develop three credible or plausible distracters. A new KIA was randomly selected.

295021 2.4.35 - Unable to develop an operationally relevant question. A new KIA was randomly selected.

295030 EA2.04 - KIA rejected due to overlap with Audit SRO question #2 (also KIA 295030 EA2.04). A new KIA was randomly selected.

400000 A2.04 - Could not develop an operationally relevant question connecting monitors to a CCW system at Oyster Creek. A new KIA was randomly selected.

261000 A2.14 - Could not develop an operationally relevant question. A new KIA was randomly selected.

262001 A2.10 - KIA supports testing at the RO level, but no the SRO-Only level due to job responsibilities.

A new KIA was randomly selected.

214000 A2.01 - There are no operationally relevant abnormal, emergency, or Tech Spec actions for a failed RPIS reed switch. A new KIA was randomly selected.

233000 2.1.34 - Oyster Creek does not have any chemistry speCifications in the Technical Specifications. KIA rejected and a new KIA was randomly selected.

700000 AK1.01 - KIA related to Generic Fundamentals; concept tested on NRC GFE exam. A new KIA was randomly selected.

600000 AA2.16 - KIA rejected due to not being able to

ES-401 3RO 2.1.20 3RO 2.4.27 Record of Rejected KIA's Form ES-401-4 write a non-discriminatory question at the RO level. A new KIA was randomly selected.

2.1.39 - KIA rejected due to being non-discriminatory at the RO level. A new KIA was randomly selected.

2.4.19 - KIA rejected due to being non-discriminatory at the RO level. A new KIA was randomly selected.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oy:ster Creek Date of Examination: 7/11/11 Examination Level: RO I2l SRO 0 Operating Test Number: ILT 10-1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

Perform Week 4 of 680.4.007, Safety Related Equipment Conduct of Operations P,S Verification; G2.1.29 (4.1) [NRC Admin JPM1 (RO)]

Perform Core Thermal Limits Verification; G2.1.7 (4.4)

Conduct of Operations D,R

[NRC Admin JPM2 (RO)]

Equipment Control Application of Radiation Exposure Limits lAW Procedure Radiation Control D,R RP-AA-203; G2.3.4 (3.2) [NRC Admin JPM3 (RO)]

Determine Primary Containment Water Level lAW EMG-Emergency Procedures/Plan M,R SP28; G2.4.21 (4.0) [NRC Admin JPM4 (RO)]

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 G; 3 for ROs; 5. 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (?: 1)

(P)revious 2 exams (5. 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Administrative Outline Form ES-301-1 Facility: O:tster Creek Date of Examination: 7/11/11 Examination Level: RO D SRO I25J Operating Test Number: ILT 10-1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

Review the Technical Specification Log Sheet; G2.1.3 Conduct of Operations N,R (3.9) [NRC SRO Admin JPM1]

Review a Completed Pre-Critical Checkoff lAW Procedure Conduct of Operations P,R 201; G2.1.23 (4.4) [NRC SRO Admin JPM2]

Review the acceptance criteria for surveillance procedure 609.3.022, "A" Isolation Condenser Isolation Test and Equipment Control D,R Calibration A1 Sensors First; G2.2.12 (4.1) [NRC SRO Admin JPM3]

Authorize TIP Room Entry; G2.3.13 (3.8) [NRC SRO Radiation Control D,R Admin JPM4]

Determine Primary Containment Water Level lAW EMG-Emergency Procedures/Plan M,R SP28 and determine required action; G2.4.21 (4.6) [NRC SRO Admin JPM5]

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 (:s 3 for ROs;.:s. 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2:, 1)

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

ES 301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: O:tster Creek Date of Examination: 7/11/11 Exam Level: RO IZl SRO-I 0 SRO-U D Operating Test Number: ILT 10-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title

a. Perform Core Spray Surveillance with faulted Core Spray Pump lAW 610.4.002, Core Spray Pump Operability Test (Alternate Path): 209001 A4.01 (3.8/3.6) [NRC Sim JPM1]
b. Perform Anticipatory Scram Turbine Stop Valve Closure Test, 619.4.002 with 1/2 RPS Actuation; 245000 A4.07 (2.9/2.9) [NRC Sim JPM2]
c. Cool down the RPV using the Isolation Condenser tube side vents lAW EMG-SP15, Alternate Pressure Control Systems - IC Tube Side Vents (Alternate Path); 295021 AA1.04 (3.7/3.7) [NRC Sim JPM3]
d. Place the H2/02 monitoring system in service lAW EMG-SP39, Placing The H2/02 Monitoring System In Service; 500000 EA 1.01 (3.4/3.3)

[NRC Sim JPM4]

! e. Transfer 4160 VAC Bus lA to the Startup Transformers (Alternate Path);

262001 K4.02 (2.9/3.3) [NRC Sim..IPM5]

f. Perform an APRM Gain Adjustment; 215005 A4.03 (3.213.3) [NRC Sim JPM 6]
g. Inject Fire Water via the Core Spray System lAW SP-20, Low Pressure Injection During An ATWS; 286000 A4.06 (3.4/3.4) [NRC Sim JPM7]
h. Startup of the Turbine Building Ventilation System lAW 328, The Turbine Building Heating And Ventilation System (Alternate Path); 288000 A4.01 (3.1/2.9) [NRC Sim JPM8]

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

i. Vent the scram air header lAW EMG-SP21, Alternate Insertion of Control Rods; 295037 EA 1.05 (3.9/4.0) [NRC Plant JPM1]
j. Add makeup from Fire Water to the Isolation Condensers lAW 307, Isolation Condenser System; 207000 K1.06 (3.3/3.7) [NRC Plant JPM3]
k. Operate Service Water Pump 1-2 from Local Shutdown Panel '1 B3 (LSP 1 B3) lAW 346, Operation of the Remote and Local Shutdown Panels; 295016 AA 1.07 (4.2I4.3) [NRC Plant JPM2)
  • This plant JPM will be performed on the Simulator replica of LSP-l B3.

Type Code*

Safety Function D,A,S 2

P, D, L, S 3

M, A, L, EN, 4

S N, L, S 5

D,A,S 6

M,S 7

N,S 8

P, 0, A, L, S 9

0, R

1 0, L, R 4

D, EN, S*

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

~!3 /

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

.::=. "I /

.::=.1

/.::=. 1 (EN)gineered safety feature

- /

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

.::=. "I /

.::=.1

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

.::=.:u

.::=.2 /.::=. 1 (P)revious 2 exams

~:3 /

~3 / ~ 2 (randomly selected)

(R)CA

.::=. "I /

.::=.1

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: O)lster Creek Date of Examination: 7/11/11 Exam Level: RO D SRO-, [81 SRO-U D Operating Test Number: ILT 10-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title

a. Perform Core Spray Surveillance with faulted Core Spray Pump lAW 61004.002, Core Spray Pump Operability Test (Alternate Path); 209001 A4.01 (3.8/3.6) [NRC Sim JPM1J
b. Perform Anticipatory Scram Turbine Stop Valve Closure Test, 61904.002 with 1/2 RPS Actuation; 245000 A4.07 (2.9/2.9) [NRC Sim JPM2]
c. Cool down the RPV using the Isolation Condenser tube side vents lAW EMG-SP15, Alternate Pressure Control Systems - IC Tube Side Vents (Alternate Path); 295021 AA1.04 (3.7/3.7)-[NRC Sim "IPM3]
d. Place the H2/02 monitoring system in service lAW EMG-SP39, Placing The H2I02 Monitoring System In Service; 500000 EA 1.01 (304/3.3)

[NRC Sim JPM4]

Transfer 4160 VAC Bus 1A to the Startup Transformers (Alternate Path);

262001 K4.02 (2.9/3.3) [NRC Sim JPM5]

f. Perform an APRM Gain Adjustment; 215005 A4.03 (3.2/3.3) [NRC Sim JPM 6)
g.

. h. Startup of the Turbine Building Ventilation System lAW 328, The Turbine Building Heating And Ventilation System (Alternate Path); 288000 A4.01 (3.1/2.9) [NRC Sim JPM8]

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

i. Vent the scram air header lAW EMG-SP21, Alternate Insertion of Control Rods; 295037 EA1.05 (3.9/4.0) [NRC Plant "IPM1]
j. Add makeup from Fire Water to the Isolation Condensers lAW 307, Isolation Condenser System; 207000 K1.06 (3.3/3.7) [NRC Plant JPM3]
k. Operate Service Water Pump 1-2 from Local Shutdown Panel '1 B3 (LSP 1 B3) lAW 346, Operation of the Remote and Local Shutdown Panels; 295016 AA1.07 (4.214.3) [NRC Plant JPM2)
  • This plant JPM will be performed on the Simulator replica of LSP-1 B3.

Safety Type Code*

Function D,A,S 2

P, 0, L, S 3

M, A, L, EN, 4

S N,L,S 5

D,A,S 6

M,S 7

P,'D, A, L, S 9

D,E,R 1

D,L, R 4

0, EN, S*

7 i

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 4-6/ 4-6 / 2-3 (C)ontrol room (D)irect from bank s9/ s8 / S4 (EN)gineered safety feature

- / -

1 ;::, 1 (control room system (P)revious 2 exams S31 s3 / S 2 (randomly s~lected)

(S)imulator (E)mergency or abnormal in-plant

, 'I /
,1

/ ;::, 1 (L)ow-Power 1Shutdown

, 'I /
,1

/ ;::, 1 (N)ewor (M)odified from bank including 1 (A)

,2/ ;
:,2 1 ;::, 1 (R)CA
,11 ;
:,1 1 ;::, 1 ES-301, Page 23 of 27

ILT 10-1 NRC Scenario 2 (NEW)

Scenario Outline Facility: Oyster Creek Scenario No.: ~

Op Test No.: 10-1 NRC Examiners:

Operators:

Initial Conditions:

97% power Main Generator voltage control is in Manual Turnover:

Place the amplidyne in automatic service lAW 336.1, section 8 Raise reactor power to 100% with recirculation flow Event No.

Mal Type*

Event Description 1

NA N

BOP Return the Amplidyne to seNice lAW 336.1.

Raise reactor power to 100% with recirculation flow 2

NA R

ATC (REMA).

ICH-Respond to RPV High Pressure Instrument RE15 to 3

TS SRO NSS026A Isolation Condenser Initiation Logic Failing High.

MAL-I ATC 4

Respond to APRM 2 failing INOP.

NIS021B TS SRO MAL 5

C BOP Respond to trip of Steam Packing Exhauster 1.

MSSOO5A ATC MAL-C Respond to the E EMRV lifting leading the crew to a 6

BOP NSS025E TS manual scram.

SRO CAEP 7

ATWS M

Crew Respond to an Electric ATWS.

PMP SLCOO1A 8

C Crew Respond to a Standby Liquid Control Pump shaft break.

PMP SLCOO2A (N)ormal, (R)eactivity, (I}nstrument, (C}omponent, (M)ajor Transient, (TS) Tech Specs IL T 10-1 NRC Scenario 2 Page 1 of 23

ILT 10-1 NRC Scenario 3 (NEW)

Scenario Outline Facility: Oyster Creek Scenario No.: ~

Op Test No.: 10-1 NRC Examiners:

Operators:

Initial Conditions:

  • 75% power
  • TBCCW Pump 2 is tagged out of service Turnover:
  • Lower power to 70% using recirculation flow lAW 1001.22-3, Core Maneuvering Daily Instruction Sheet

Event Description 1

NA R

ATC Lower reactor power to 70% using recirculation flow 2

NA N

BOP Continue backwashing Main Condenser Half B South BKR-C ATC 3

Respond to a CRD Pump A trip CRDOO2 TS SRO 4

MAL-I BOP Respond to the EPR setpoint failing low TCS010 SWI C

BOP 5

TBS027C Respond to a trip of Control Room Vent Fan B TS SRO ANN-L4f MAL-I ATC Respond to a variable leg leak in the A and C GEMAC 6

NSS012E TS SRO RPV level indicators ID13A and ID13C 7

BKR-M Crew Respond to a loss of all CRD Flow CRDOO1 8

MAL-M Crew Respond to a Safety Valve lifting post scram NSS016A MAL-Respond to a trip of the operating Containment Spray 9

CNSOO4A-C Crew D

Pump (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs IL T 10-1 NRC Scenario 3 Page 1 of 28

ILT 10-1 I\\JRC Scenario 4 (NEW)

Scenario Outline Facility: Oyster Creek Scenario No.: ~

Op Test No.: 10-1 NRC Examiners:

Operators:

Initial Conditions:

100% power Dilution pump 2 is tagged out of service Turnover:

No evolutions are planned during this shift

  • Event No.

Malt. No.

Event Type*

Event Description 1

ATC Respond to CRD Flow Control Valve failed closed.

I CRD IC C

BOP 2

Respond to a leak in Isolation Condenser ShEll! A.

ICS~

TS SRO IND-R ATC Condensate Pump A experiences high amps requiring a 3

CFW018 C

BOP rapid power reduction and securing of Condensate Pump.

ANN-K-2B MAL*

C RCP003D BOP 4

Respond to Recirculation Pump D total seal failure.

MAL-TS SRO RCPOO4D

.1 5

v ATC Respond to multiple drifting control rods.

c~

Respond to a Torus Leak requiring entry into Primary 6

PCN007 M

Crew Containment Control.

VLV-Respond to Core Spray system suction valves being 7

CSSOO1, C

Crew 009 mechanically seized when lining up the CST to the Torus.

Respond to a Torus leak increase requiring the crew to II a

MAL-M Crew PCN007 Emergency Depressurize.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs ILT 10-1 NRC Scenario 4 Page 1 of 25

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