ML14167A298

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Draft Outlines (Folder 2)
ML14167A298
Person / Time
Site: Oyster Creek
Issue date: 04/02/2014
From: Ridosh J
Exelon Nuclear Generation Corp
To:
Operations Branch I
Shared Package
ML13333A261 List:
References
TAC- U01893
Download: ML14167A298 (23)
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Text

ILT 13-1 NRC Scenario 1 (New)

Scenario Outline Facility: Oyster Creek Scenario No.: 1 Op Test No.: 13*1 NRC Examiners:

Operators:

Initial Conditions:

2% power with mode switch in STARTUP Control rod withdrawal is in progress Air Compressor #3 is tagged OOS RWM is tagged OOS lnerting the Primary Containment is on hold for a nitrogen delivery Steam chest warming is in progress Turnover:

Continue with rod withdrawal. Complete step 1 0 Group 3-1 starting at rod 26*23. When rod pulls are complete wait for further direction from Reactor Engineering. Timing of rod position 00-02 is not required and Continuous Rod Withdrawal is authorized per Reactor Engineering.

Event No.

Malf. No.

Event Type*

Event Description 1

N/A R

ATC Raise reactor power with control rods lAW the ReMA MAL-2 CRD007_

c ATC Stuck control rod (26-23) 2623 3

ICH-c BOP ICS003A TS SAO Leak in Isolation Condenser Shell B 4

MAL-c BOP Loss of VMCC 1 B2 EDS0048 TS SAO 5

MAL-c BOP The in-service RBCCW pump trips RBC001A MAL-The standby RBCCW pump also trips resulting in a loss 6

RBC0018 c

ATC of all RBCCW flow which requires the ATC to scram the reactor; eiQht rods fail to insert 7

MAL-M Crew Steam leak in Drywell NSS017A 8

MAL-c Crew CAD Flow Control Valve fails closed CRD001A (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs ILT 13-1 NRC Scenario 1 Page 1 of 26

IL T 13-1 NRC Scenario 2 (New)

Scenario Outline Facility: Oyster Creek Scenario No.: ~

Op Test No.: 13-1 NRC Examiners:

Operators:

Initial Conditions:

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

Place the AVR in automatic service lAW 336.1, section 8, starting at Step 8.2 Raise reactor power to 100% with recirculation flow Event No.

Malf. No.

Event Type*

Event Description 1

N/A N

BOP Return the AVA to service lAW 336.1.

2 N/A R

ATC Raise reactor power to 100% with recirculation flow.

3 MAL-c BOP Trip of Steam Packing Exhauster 1.

MSS005A MAL-NIS020F I

ATC APRM 6 fails upscale with a failure of Y2 scram on 4

RLY-

RPS003B, TS SAO RPS2.

0048 5

MAL-c BOP Trip of USS 1 A3.

EDS003C TS SAO ICH-6

TSii5A, c

ATC Turbine high vibration requiring a manual scram.

TSIOi4A MAL-CFWOi28 Feedwater line break with failure of Feedwater check SRV-7 CFW002B M

Crew valves and loss of all Feedwater and Condensate SRV-Pumps.

CFW003B VLV-8

CSS004, c

Crew Failure of Core Spray Isolation Valves to auto open.

006, Oi i, 012 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs IL T 13-1 NRC Scenario 2 Page 1 of 26

ILT 13-1 NRC Scenario 3 (Modified)

Scenario Outline Facility: Oyster Creek Scenario No.:~

Op Test No.: 13-1 NRC Examiners:

Operators:

Initial Conditions:

95% power EDG-2 is OOS for maintenance Surveillance 636.4.003, Diesel Generator Load Test, is in progress on EDG-1 An operator is stationed at EDG-1 for the surveillance All EDG-1 diesel alarms are in their normal state Turnover:

Complete surveillance 636.4.003, Diesel Generator Load Test, starting at step 6.7, due to a question of operability (oil sight glass was low on the last shift)

Event No.

Malt. No.

Event Type*

Event Description 1

MAL-c BOP Trip of EDG-1 during performance of surveillance DGN004A TS SAO 636.4.003.

MAL-I ATC 2

NIS019_0 TS BOP LPRM 28-25A upscale failure (input to APRM 4).

18A SAO MAL-c ATC 3

CRD005 -

TS BOP Outward drifting control rod (rod 18-11 ).

18-11 SAO 4

MAL-A ATC Fuel failure requiring power reduction with recirc RXS001 flow 5

MAL-M Crew Fuel failure will increase requiring a reactor scram RXS001 and reactor isolation MAL-Isolation Condenser B tube leak with steam valves ICS002B M

6 VLV-c Crew failing to close leads to RPV Emergency

ICS007, Depressurization 008 (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs IL T 13-1 NRC Scenario 3 Page 1 of 20

ES-401 Written Examination Outline Form ES-401-1 Facility:

IL T 13-1 NRC Written Exam Date of Exam:

05/19/14 RO KIA Category Points SRO-Only Points Tier Group K

K K

K K

K A

A A

A G

Tota 1

2 3

4 5

6 1

2 3

4 I

A2 G*

Total 1

3 3

3 4

3 4

20 3

4 7

1.

Emergency 2

1 1

2 1

1 1

7 2

1 3

Plant Tier Evolutions Total 4

4 5

5 4

5 27 5

5 10 s

1 3

2 2

3 2

3 2

2 3

2 2

26 3

2 5

2.

Plant 2

1 1

1 1

1 1

1 1

2 1

1 12 0

2 1

3 Systems Tier Totals 4

3 3

4 3

4 3

3 5

3 3

38 5

3 8

3. Generic Knowledge & Abilities 1

2 3

4 1

2 3

4 10 7

Categories 3

2 3

2 2

2 2

1 Note

1.

Ensure that at least two topics from every applicable KJA 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 KJA 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.1.b of ES-401, for guidance regarding elimination of inappropriate KJA 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 KJA categories.

7.*

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 KJA's

8.

On the following pages, enter the KJA 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-only exams.

9.

For Tier 3, select topics from Section 2 of the KJA Catalog, and enter the KJA 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

ILT 13-1 NRC Written Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions-Tier 1 Group 1 EAPE #I Name Safety Function KJA Topic(s)

AA2.02-Ability to determine and/or 295018 Partial or Total Loss of interpret the following as they apply to CCW/8 X

PARTIAL OR COMPLETE LOSS OF 3.2 1

COMPONENT COOLING WATER:

Cooling water temQ_erature EA2.02 -Ability to determine and/or 295031 Reactor Low Water X

interpret the following as they apply to 4.2 2

Level I 2 REACTOR LOW WATER LEVEL:

Reactor power EA2.04-Ability to determine and/or 295030 Low Suppression Pool interpret the following as they apply to X

LOW SUPPRESSION POOL WATER 3.7 3

Water Level I 5 LEVEL : Drywelll suppression chamber differential pressure: Mark-1&11 2.4.4 1 - Emergency Procedures I Plan:

295026 Suppression Pool High Water Temp. I 5 X

Knowledge of the emergency action 4.6 4

level thresholds and classifications.

2.4.9-Emergency Procedures I Plan:

295028 High Drywell Knowledge of low power I shutdown X

implications in accident (e.g., loss of 4.2 5

Temperature I 5 coolant accident or loss of residual heat removal) mitigation strategies.

2.4.45-Emergency Procedures I Plan:

295038 High Off-site Release X

Ability to prioritize and interpret the 4.3 6

Rate 19 significance of each annunciator or jalarm.

2.2.44-Ability to interpret control room 295021 Loss of Shutdown indications to verify the status and Cooling 14 X

operation of a system. and understand 4.4 7

how operator actions and directives affect plant and system conditions.

AK1.02-Knowledge of the operational implications of the following concepts as 700000 Generator Voltage and X

they apply to GENERATOR VOLTAGE 3.3 39 Electric Grid Disturbances AND ELECTRIC GRID DISTURBANCES and the following:

Over-excitation.

EK1.03-Knowledge of the operational 295031 Reactor Low Water implications of the following concepts as Level/2 X

they apply to REACTOR LOW WATER 3.7 40 LEVEL : Water level effects on reactor power AK1.02 - Knowledge of the operational 600000 Plant Fire On-site I 8 X

implications of the following concepts 2.9 41 as they apply to Plant Fire On Site: Fire Fiqhtinq AK2.01 - Knowledge of the 295016 Control Room interrelations between CONTROL Abandonment I 7 X

ROOM ABANDONMENT and the 4.4 42 following: Remote shutdown panel:

Plant-Specific AK2.01 - Knowledge of the 295001 Partial or Complete interrelations between PARTIAL OR Loss of Forced Core Flow X

COMPLETE LOSS OF FORCED CORE 3.6 43 Circulation 11 & 4 FLOW CIRCULATION and the following: Recirculation system AK2.01 - Knowledge of the 295004 Partial or Total Loss of X

interrelations between PARTIAL OR 3.1 44 DC Pwrl6 COMPLETE LOSS OF D.C. POWER and the following: Battery charger

ES-401 2

ILT 13-1 NRC Written Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions-Tier 1 Group 1 EAPE #I Name Safety Function KJA Topic(s)

AK3.02-Knowledge of the reasons for 295023 Refueling Ace Cooling X

the following responses as they apply to 3.4 45 Mode /8 REFUELING ACCIDENTS : Interlocks associated with fuel handling equipment AK3.04 - Knowledge of the reasons for 295005 Main Turbine X

the following responses as they apply to 3.2 46 Generator Trip I 3 MAIN TURBINE GENERATOR TRIP:

Main generator trip AK3.01 - Knowledge of the reasons for 295003 Partial or Complete the following responses as they apply to X

PARTIAL OR COMPLETE LOSS OF 3.3 47 Loss of AC /6 A.C. POWER : Manual and auto bus transfer AA1.03-Ability to operate and/or 295006 SCRAM /1 X

monitor the following as they apply to 3.7 48 SCRAM : Reactor/turbine pressure regulating system EA 1.01 -Ability to operate and/or 295037 SCRAM Conditions monitor the following as they apply to Present and Reactor Power X

SCRAM CONDITION PRESENT AND 4.6 49 Above APRM Downscale or REACTOR POWER ABOVE APRM Unknown /1 DOWNSCALE OR UNKNOWN :

Reactor Protection System EA 1.01 -Ability to operate and/or 295028 High Drywell X

monitor the following as they apply to 3.8 50 Temperature I 5 HIGH DRYWELL TEMPERATURE:

Drywell spray: Mark-1&11 EA2.06-Ability to determine and/or 295025 High Reactor Pressure X

interpret the following as they apply to 3.7 51

/3 HIGH REACTOR PRESSURE: Reactor water level AA2.01 -Ability to determine and/or 295019 Partial or Total Loss of interpret the following as they apply to lnst. Air /8 X

PARTIAL OR COMPLETE LOSS OF 3.5 52 INSTRUMENT AIR: Instrument air system pressure EA2.01 -Ability to determine and/or 295038 High Off-site Release

  • x interpret the following as they apply to 3.3 53 Rate /9 HIGH OFF-SITE RELEASE RATE:

tOff-site 2.1.23-Conduct of Operations: Ability 295018 Partial or Total Loss of X

to perform specific system and 4.3 54 CCW/8 integrated plant procedures during all modes of plant operation.

295026 Suppression Pool High 2.2.22-Equipment Control: Knowledge X

of limiting conditions for operations and 4.0 55 Water Temp. I 5 safety_ limits.

295024 High Drywell Pressure I 2.2.37-Equipment Control: Ability to 5

X determine operability and/or availability 3.6 56 of safety related equiQ_ment.

295030 Low Suppression Pool 2.4.1 - Emergency Procedures I Plan:

Water Level/ 5 X

Knowledge of EOP entry conditions and 4.6 57 immediate action steps.

AA 1.05-Ability to operate and/or 295021 Loss of Shutdown X

monitor the following as they apply to 3.0 58 Cooling /4 LOSS OF SHUTDOWN COOLING :

Reactor recirculation KJA Category Totals:

3 3

3 4

3/3 4/4 Group Point Total:

l 2017

ES-401 3

ILT 13-1 NRC Written Exam Written Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions-Tier 1 Group 2 EAPE #I Name Safety Function KIA Topic(s) 295008 High Reactor Water 2.1.20- Conduct of Operations: Ability Level/2 X

to interpret and execute procedure 4.6 8

steps AA2.02-Ability to determine and/or 295009 Low Reactor Water X

interpret the following as they apply to 3.7 9

Level I 2 LOW REACTOR WATER LEVEL

  • Steam flow/feed flow mismatch EA2.01 Ability to determine and/or 295036 Secondary interpret the following as they apply to SECONDARY CONTAINMENT HIGH Containment High Sump/Area X

SUMP/AREA WATER LEVEL:

3.2 10 Water Level I 5 Operability of components within the affected area AK1.02-Knowledge of the operational 295017 High Off-site Release implications of the following concepts as Rate /9 X

they apply to HIGH OFF-SITE 3.8 59 RELEASE RATE : Protection of the general public EK2.06-Knowledge of the 295034 Secondary interrelations between SECONDARY Containment Ventilation High X

CONTAINMENT VENTILATION HIGH 3.9 60 Radiation I 9 RADIATION and the following:

PCIS/NSSSS: Plant-Specific EK3.01 - Knowledge of the reasons for 295032 High Secondary the following responses as they apply to Containment Area Temperature X

HIGH SECONDARY CONTAINMENT 3.5 61

/5 AREA TEMPERATURE:

Emergency/normal depressurization AA1.01 -Ability to operate and/or 295010 High Drywell Pressure X

monitor the following as they apply to 3.4 62

/5 HIGH DRYWELL PRESSURE : Drywell ventilation/cooling AA2.02-Ability to determine and/or 295007 High Reactor Pressure X

interpret the following as they apply to 4.1 63

/3 HIGH REACTOR PRESSURE : Reactor power 295033 Secondary 2.4.2 - Emergency Procedures/Plan:

Containment Area Radiation X

Knowledge of system set points, 4.5 64 Levels /9 interlocks and automatic actions associated with EOP entry conditions.

AK3.04-Knowledge of the reasons for 295002 Loss of Main X

the following responses as they apply to 3.4 65 Condenser Vac I 3 LOSS OF MAIN CONDENSER VACUUM: Bypass valve closure KIA Category Totals:

1 1

2 1

1/2 1/1 Group Point Total:

I 7/3

ES-401 System #I Name K

K K

1 2

3 212000 RPS 259002 Reactor Water Level Control 209001 LPCS 262001 AC Electrical Distribution 261000 SGTS 212000 RPS X

215005 APRM I LPRM X

209001 LPCS X

239002 SRVs X

4 Form ES-401-1 ILT 13-1 NRC Written Exam Written Examination Outline Plant Systems-Tier 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

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

those predictions. use procedures to correct. control, or mitigate the consequences of those abnormal conditions or operations: RPS motor-generator set failure A2.04-Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM ; and (b)

X based on those predictions, use procedures to correct control, or mitigate the consequences of those abnormal conditions or operations: RFP runout condition: Plant-Specific 2.4.47 - Emergency Procedures I Plan: Ability to diagnose and X

recognize trends in an accurate and timely manner !utilizing the appropriate control room reference material.

2.2.40- Equipment Control:

X Ability to apply Technical Specifications for a system.

A2.07 Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM : and (b) based on X

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

electrical failure K 1. 05 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR PROTECTION SYSTEM and the following: Process radiation monitoring system K1.02 - Knowledge of the physical connections and/or cause-effect relationships between AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and the following: IRM K2.01 - Knowledge of electrical power supplies to the following:

Pump power K2.01 - Knowledge of electrical power supplies to the following:

SRV solenoids Imp Q#

3.9 11 3.1 12 4.2 13 4.7 14 2.8 15 3.3 1

3.7 2

3.0 3

2.8 21

ES-401 System # I Name K

K K

1 2

3 261000 SGTS X

215003 IRM X

300000 Instrument Air 223002 PCIS/Nuclear Steam Supply Shutoff 263000 DC Electrical Distribution 262001 AC Electrical Distribution 205000 Shutdown Cooling 264000 EDGs 211000 SLC 4

Form ES-401-1 ILT 13-1 NRC Written Exam Written Examination Outline Plant Systems-Tier 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

K3. 05 - Knowledge of the effect that a loss or malfunction of the STANDBY GAS TREATMENT SYSTEM will have on following:

Secondary containment radiation/ contamination levels K3.04-Knowledge of the effect that a loss or malfunction of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM will have on following: Reactor power indication K4.02 - Knowledge of (INSTRUMENT AIR SYSTEM)

X design feature(s) and or interlocks which provide for the following: Cross-over to other air systems K4.03-Knowledge of PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM X

SUPPLY SHUT-OFF design feature(s) and/or interlocks which provide for the following:

Manual initiation capability:

Plant -Soecific K5.01 - Knowledge of the operational implications of the following concepts as they apply X

to D.C. ELECTRICAL DISTRIBUTION : Hydrogen generation during battery charaina K5.02 - Knowledge of the operational implications of the X

following concepts as they apply to A. C. ELECTRICAL DISTRIBUTION: Breaker control K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the X

SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) : A.C.

electrical power K6.03-Knowledge of the effect that a loss or malfunction of the X

following will have on the EMERGENCY GENERATORS (DIESEL/JET) : Lube oil oumos A1.01 -Ability to predict and/or monitor changes in parameters X

associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including:

Tank level Imp Q#

3.2 5

3.6 6

3.0 7

3.5 17 2.6 9

2.6 10 3.3 11 3.5 12 3.6 13

ES-401 System #I Name K

K K

1 2

3 259002 Reactor Water Level Control 215004 Source Range Monitor 400000 Component Cooling Water 207000 Isolation (Emergency) Condenser 218000 ADS 262002 UPS (AC/DC) 239002 SRVs 264000 EDGs 261000 SGTS 259002 Reactor Water X

Level Control 4

Form ES-401-1 ILT 13-1 NRC Written Exam Written Examination Outline Plant Systems -Tier 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

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

associated with operating the REACTOR WATER LEVEL CONTROL SYSTEM controls including: Reactor water level A2.01 -Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM ; and (b) based X

on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Power supply degraded A2.02-Ability to (a) predict the impacts of the following on the CCWS and (b) based on those X

predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation: High/low surge tank level A3.03-Ability to monitor automatic operations of the X

ISOLATION (EMERGENCY)

CONDENSER including:

Reactor water level: BWR-2,3 A3.09-Ability to monitor automatic operations of the X

AUTOMATIC DEPRESSURIZATION SYSTEM including: Reactor vessel water level A4.01 -Ability to manually operate and/or monitor in the X

control room: Transfer from alternative source to preferred source A4.04-Ability to manually X

operate and/or monitor in the

  • control room: Suppression pool temperature 2.2.40- Equipment Control:

X Ability to apply technical specifications for a system.

2.2.42-Equipment Control::

Ability to recognize system X

parameters that are entry-level conditions for Technical

~ecifications.

K1.04-Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following: Reactor feedwater flow Imp Q#

3.8 14 2.7 15 2.8 16 3.5 8

4.1 18 2.8 19 4.3 20 3.4 4

3.9 22 3.5 23

ES-401 System #I Name K

K K

1 2

3 218000 ADS 263000 DC Electrical Distribution 400000 Component Cooling Water KIA Category Totals:

3 2

2 4

Form ES-401-1 ILT 13-1 NRC Written Exam Written Examination Outline Plant Systems -Tier 2 Group 1 K

K K

A A2 A

A G

4 5

6 1

3 4

K4.01 - Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM X

design feature(s) and/or interlocks which provide for the following: Prevent inadvertent initiation of ADS IC>gjc A3.01 -Ability to monitor automatic operations of the D.C.

X ELECTRICAL DISTRIBUTION including: Meters, dials, recorders, alarms, and indicating lights K6.04 - Knowledge of the effect X

that a loss or malfunction of the following will have on the CCWS: Pum_Qs 3

2 3

2 2/3 3

2 2/2 Group Point Total:

Imp Q#

3.7 24 3.2 25 3.0 26 I 2615

ES-401 System # I Name K

K K

1 2

3 223001 Primary CTMT and Aux.

201003 Control Rod and Drive Mechanism 202001 Recirculation System 256000 Reactor X

Condensate 201001 CRD Hydraulic X

288000 Plant Ventilation X

245000 Main Turbine Gen.

I Aux.

204000 RWCU 290003 Control Room HVAC 5

Form ES-401-1 ILT 13-1 NRC Written Exam Written Examination Outline Plant Systems-Tier 2 Group 2 K

K K

A A2 A

A G

4 5

6 1

3 4

A2.07 -Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those X

predictions, use procedures to correct control. or mitigate the consequences of those abnormal conditions or operations: High drywell pressure 2.4.11 - Emergency Procedures X

I Plan: Knowledge of abnormal condition procedures.

A2.02 -Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM:

and (b) based on those X

predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation svstem leak K1.22-Knowledge of the physical connections and/or cause-effect relationships between REACTOR CONDENSATE SYSTEM and the followinq: Offqas system K2.02 - Knowledge of electrical power supplies to the following:

Scram valve solenoids K3.05 - Knowledge of the effect that a loss or malfunction of the PLANT VENTILATION SYSTEMS will have on following: Reactor building pressure: Plant-Specific K4.05 - Knowledge of MAIN TURBINE GENERATOR AND X

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

Turbine protection K5.05-Knowledge of the operational implications of the X

following concepts as they apply to REACTOR WATER CLEANUP SYSTEM : Flow controllers K6.01 - Knowledge of the effect that a loss or malfunction of the X

following will have on the CONTROL ROOM HVAC:

Electrical power Imp.

Q 4.3 16 4.2 17 3.9 18 2.8 27 3.6 28 3.1 29 2.9 30 2.6 31 2.7 32

ES-401 System #I Name K

K K

1 2

3 233000 Fuel Pool Cooling/Cleanup 202001 Recirculation System 271000 Off-gas 241000 Reactor/Turbine Pressure Regulator 290002 Reactor Vessel Internals 202002 Recirculation Flow Control KIA Category Totals:

1 1

1 5

Form ES-401-1 ILT 13-1 NRC Written Exam Written Examination Outline Plant Systems -Tier 2 Group 2 K

K K

A A2 A

A G

4 5

6 1

3 4

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

associated with operating the FUELPOOLCOOUNGAND CLEAN-UP controls including:

Surge tank level A2.17 -Ability to (a) predict the impacts of the following on the RECIRCULATION SYSTEM; and (b) based on those X

predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of seal cooling water A3.05-Ability to monitor automatic operations of the X

OFFGAS SYSTEM including:

System indicating lights and alarms A4.11 - Ability to manually X

operate and/or monitor in the control room: Turbine speed 2.2.22 - Equipment Control:

X Knowledge of limiting conditions for 01=1erations and safety limits.

A3.03 - Ability to monitor automatic operations of the X

RECIRCULATION FLOW CONTROL SYSTEM including:

Scoop tube operation: BWR-2,3,4 1

1 1

1 1/2 2

1 1/1 Group Point Total:

Imp.

Q 2.6 33 3.1 34 2.9 35 3.1 36 4.0 37 3.1 38 I

12/3

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

Form ES-401-3 Facility:

ILT 13-1 NRC Written Exam Date:

05/19/14 RO SRO-Only Category K/A#

Topic IR Q#

IR Q#

2.1.20 Ability to interpret and execute procedure 4.6 19 steps.

Knowledge of individual licensed operator responsibilities related to shift staffing, such 2.1.4 as medical requirements, "no-solo" operation, 3.8 25 maintenance of active license status, 1 OCFR55. etc.

1' Conduct of Operations 2.1 '1 Knowledge of conduct of operations 3.8 66 requirements.

2.1.8 Ability to coordinate personnel activities 3.4 67 outside the control room.

2.1.19 Ability to use plant computers to evaluate 3.9 75 system or component status.

Subtotal 3

2 2.2.21 Knowledge of pre-and post-maintenance 4.1 20 operability_ requirements.

2.2.37 Ability to determine operability and I or 4.6 23 availability of safety related equipment

2.

Equipment 2.2.14 Knowledge of the process for controlling 3.9 68 Control equiQment configuration or status.

2.2.22 Knowledge of limiting conditions for 4.0 69 operations and safety limits.

Subtotal 2

2 Knowledge of radiation or contamination 2.3.14 hazards that may arise during normal.

3.8 21 abnormal, or emergency conditions or activities.

Knowledge of radiation monitoring systems, 2.3.15 such as fixed radiation monitors and alarms.

3.1 24 portable survey instruments, personnel

3.

monitoring equipment, etc.

Radiation Control Knowledge of Radiological Safety Procedures pertaining to licensed operator 2.3.13 duties, such as response to radiation monitor 3.4 70 alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, 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.

2.3.11 Ability to control radiation releases.

3.8 74 Subtotal 3

2 2.4.45 Ability to prioritize and interpret the 4.3 22 significance of each annunciator or alarm.

4.

Emergency 2.4.17 Knowledge of EOP terms and definitions.

3.9 72 Procedures I Ability to prioritize and interpret the Plan 2.4.45 significance of each annunciator or 4.1 73 alarm.

Subtotal 2

1 Tier 3 Point Total 10 7

ES-401 Record of Rejected KIA's Form ES-401-4 Tier I Group Randomly Reason for Rejection Selected KIA KIA 295038 2.4.4 supports testing at the RO level, but not the 111 SRO 295038 2.4.45 SRO-Only level due to job responsibilities. KIA was rejected and a new KIA was randomly selected.

KIA 2.1.44 supports testing at the RO level, but not the SRO-Only 3 SRO 2.1.4 level due to job responsibilities. KIA was rejected and a new KIA was randomly selected.

KIA 2.4.35 supports testing at the RO level, but not the SRO-Only 3SRO 2.4.45 level due to job responsibilities. KIA was rejected and a new KIA was randomly selected.

KIA 295023 AK3.05 applies to a BWR-1. Oyster Creek is a 111 RO 295023 AK3.02 BWR-2. KIA was rejected and a new KIA was randomly selected.

3 RO 2.2.22 KIA 2.2.3 applies to a multi-unit site. Oyster Creek is a single unit site. KIA was rejected and a new KIA was randomly selected.

KIA 295028 EA 1.02 was rejected due to overlap with RO 111 RO 295028 EA1.01 question #62, KIA 295010 AA 1.01. A new KIA was randomly selected.

KIA 295022 AK3.02 was rejected due not being able to develop 112 RO 295002 AK3.04 three credible distractors at the RO level. A new KIA was randomly selected.

KIA 290001 K1.02 was rejected due not being able to develop 212 RO 256000 K1.22 three credible distractors at the RO level. A new KIA was randomly selected.

KIA 295035 2.1.27 was rejected due to not being able to develop 112 RO 295033 2.4.2 three credible distractors at the RO level. A new KIA was randomly selected at the RO level. A new KIA was randomly selected.

KIA 2.3.13 supports testing at the RO level, but not the SRO-Only 3 SRO 2.3.15 level due to job responsibilities. KIA was rejected and a new KIA was randomly selected.

KIA 201003 2.4.50 supports testing at the RO level, but not the 212 SRO 201003 2.4.11 SRO-Only level due to job responsibilities. KIA was rejected and a new KIA was randomly selected.

KIA 295003 AK3.07 was rejected due to not being able to 111 RO 295003 AK3.01 develop three credible distractors at the RO level. A new KIA was randomly selected at the RO level. A new KIA was randomly selected.

KIA 295033 2.1.27 was rejected due to not being able to develop 112 RO 295033 2.4.2 three credible distractors at the RO level. A new KIA was randomly selected at the RO level. A new KIA was randomly selected.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oyster Creek Date of Examination: 05/19/14 Examination Level: RO [gl SRO D Operating Test Number: 13-1 NRC Administrative Topic Type Describe activity to be performed (See Note)

Code*

Conduct of Operations M,R Determine Bulk Drywell Temperature; 2.1.20 (4.6) [RO Admin JPM 1]

Conduct of Operations D,R Plot RPV Heatup Rate During a Startup; 2.1.25 (3.9) [RO Admin JPM 2]

Equipment Control D,R Perform a Manual Core Heat Balance Calculation lAW 1001.6; 2.2.12 (3.7) [RO Admin JPM 3]

Radiation Control Emergency Procedures/Plan M,R Review a Completed State/Local Notification Form; 2.4.39 (3.9) [NRC RO Admin JPM 4]

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: Oyster Creek Date of Examination: 05/19/14 Examination Level: RO 0 SRO 1Z1 Operating Test Number: 13-1 NRC Administrative Topic Type Describe activity to be performed (See Note)

Code*

Conduct of Operations D,R Determine Operator Qualifications Using LMS; 2.1.8 (4.1)

[SRO Admin JPM 1]

Conduct of Operations M,R Apply Work Hour Rules; 2.1.5 (3.9) [SRO Admin JPM 2]

Review Completed Surveillance Test 619.3.016, RPS I Equipment Control N,R High Drywell Pressure Scram Test And Calibration; 2.2.12 (4.1) [SRO Admin JPM 3]

Radiation Control D,R Determine Recommendation of Kl Issuance During an Emergency; 2.3.14 (3.8) [SRO Admin JPM 4]

Emergency Procedures/Plan D,R Classify an Emergency Event and Initiate a State/Local Notification Form; 2.4.41 (4.6) [SRO Admin JPM 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 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: O~ster Creek Date of Examination: 05/19/14 Exam Level: RO [gl SR0-1 D SRO-U D Operating Test Number: 13-1 NRC Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a. Shutdown the Second RWCU Pump with a high NRHX temperature M,A,S 2

alarm and isolation failure (Alternate Path); 204000 A4.01 (3.1/3.0) [NRC Sim JPM 1]

b. Bypass an Inoperable Acoustic Monitor for EMRV NR 1 08E; 239002 M,EN,S 3

A4.03 (3.8/3.9) [NRC Sim JPM 2]

c. Add Makeup to the Isolation Condenser System (Alternate Path);

D,A,S 4

207000 A3.05 (3.6/3.8) [NRC Sim JPM 3]

d. Purging the Primary Containment with Elevated Stack Radiation P,A, EN,S 5

(Alternate Path); 223001 A4.07 (4.2/4.1) [NRC Sim JPM 4]

e. De-energize 1A 1 Transformer by Cross-tieing USS 1A 1 to USS 181; D,S,L 6

262001 A 1.05 (3.2/3.5l[NRC Sim JPM 5]

f. Perform the Anticipatory Scram Turbine Stop Valve Closure Test D,A,S 7

(Alternate Path); 212000 A2.19 (3.8/3.9) [NRC Sim JPM 6]

g. Swap Instrument Air Compressors; 300000 K4.04 (2.8/2.9) [NRC Sim M, S 8

JPM 7J

h. Swap Control Room Ventillation Fans (Alternate Path); 290003 A4.02 D,A,S 9

(2.8/2.8) [NRC Sim JPM 8}

In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

i. Control CRD in the plant Post-Scram lAW SP-3; 201001 A1.03 (2.9/2.8)

P, L,R, E 1

[NRC Plant JPM 1]

j. Align Core Spray System to the Condensate Storage Tank for Emergency D,R,L,E 2

Operations; 295030 EA 1.06 _(_3.4/3.4)LNRC Plant JPM 2]

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

6 JPM 3]

All RO and SR0-1 control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SR0-1 I SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank

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

_ 1 I
_1 I :::_ 1 (EN)gineered safety feature I

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

_ 1 I
_1 I :::_ 1 (N)ew or (M)odified from bank including 1 (A)
_21
2 I
::_ 1 (P)revious 2 exams

~ 3 I

~3 I ~ 2 (randomly selected)

(R)CA

_ 1 I
_1 I ;:_ 1 (S)imulator ES-301, Page 23 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oyster Creek Date of Examination: 05/19/14 Exam Level: RO D SR0-1 [8:1 SRO-U D Operating Test Number: 13-1 NRC Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a. Shutdown the Second RWCU Pump with a high NRHX temperature M,A,S 2

alarm and isolation failure (Alternate Path); 204000 A4.01 (3.1/3.0) [NRC Sim JPM 1]

b. Bypass an Inoperable Acoustic Monitor for EMRV NR1 08E; 239002 M, EN, S 3

A4.03 (3.8/3.9) [NRC Sim JPM 2]

c. Add Makeup to the Isolation Condenser System (Alternate Path);

D,A,S 4

207000 A3.05 (3.6/3.8) [NRC Sim JPM 3]

d. Purging the Primary Containment with Elevated Stack Radiation P,A,EN,S 5

(Alternate Path); 223001 A4.07 (4.2/4.1) [NRC Sim JPM 4]

e.
f. Perform the Anticipatory Scram Turbine Stop Valve Closure Test D,A,S 7

(Alternate Path); 212000 A2.19 (3.8/3.9) [NRC Sim JPM 6]

g. Swap Instrument Air Compressors; 300000 K4.04 (2.8/2.9) [NRC Sim M,S 8

JPM 7]

h. Swap Control Room Ventillation Fans (Alternate Path); 290003 A4.02 D,A,S 9

(2.8/2.8) [NRC Sim JPM 8]

In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

i. Control CRD in the plant Post-Scram lAW SP-3; 201001 A1.03 (2.9/2.8)

P,L,R,E 1

[NRC Plant JPM 1]

j. Align Core Spray System to the Condensate Storage Tank for Emergency D, R, L, E 2

Operations; 295030 EA1.06 (3.4/3.4) [NRC Plant JPM 2]

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

6 JPM 3]

All RO and SR0-1 control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SR0-11 SRO-U (A)Iternate path 4-61 4-6 I 2-3 (C)ontrol room (D)irect from bank

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

~ 1 I

~1 I ~ 1 (EN)gineered safety feature

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

~ 1 I

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

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

~31.S3 I ~ 2 (randomly selected)

(R)CA

~ 1 I

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Oyster Creek Date of Examination: 05119114 Exam Level: RO 0 SR0-1 0 SRO-U 1ZJ Operating Test Number: 13-1 NRC Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a. Shutdown the Second RWCU Pump with a high NRHX temperature M,A,S 2

alarm and isolation failure (Alternate Path); 204000 A4.01 (3.113.0) [NRC Sim JPM 1J

b. Bypass an Inoperable Acoustic Monitor for EMRV NR 1 08E; 239002 M, EN,S 3

A4.03 (3.813.9) [NRC Sim JPM 2]

c.
d.
e.
f.
g.
h. Swap Control Room Ventillation Fans (Alternate Path); 290003 A4.02 D,A,S 9

(2.812.8) [NRC Sim JPM 8]

In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

i. Control CRD in the plant Post-Scram lAW SP-3; 201001 A1.03 (2.912.8)

P, L, R, E 1

[NRC Plant JPM 1]

j.
k. Swap Static Chargers from C1 to C2; 263000 K1.02 (3.213.3) [NRC Plant D

6 JPM 3]

All RO and SR0-1 control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO I SR0-11 SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank

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

~ 1 I

~1 I ~ 1 (EN)gineered safety feature

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

~ 1 I

~1 I ~ 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 I

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

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