ML17261B165

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Final Outlines (Folder 3)
ML17261B165
Person / Time
Site: Oyster Creek
Issue date: 02/10/2016
From: Brian Fuller
Operations Branch I
To:
Exelon Generation Co
Shared Package
ML15219A259 List:
References
TAC U01929
Download: ML17261B165 (24)
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Text

ES-401 Written Examination Outline Form ES-401-1 Oyster Creek Initial NRC Facility: Date of Exam: 02/01116 Exam RO Kl A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 * -- .- -- -

I. 1 3 4 4 3 3 3 20 4 3 7

~

Emergency

& 2 2 1 1 1 1 1 7 1 2 3

*~

Plant Tier Evolutions 5 5 5 4 4 4 27 5 5 10 Totals I 3 2 3 2 2 3 2 3 2 2 2 26 3 2 5 2.

Plant 2 1 1 1 1 2 0 1 2 1 1 1 12 0 1 2 3

-~

Systems Tier 4 3 4 3 4 3 3 5 3 3 3 38 4 4 8 Totals

-* -~~ *----~- --~-

3. Generic Knowledge & Abilities 1 2 3 4 I 2 3 4 I IO -*----- 7 Categories 2 3 3 2 1 2 2 2

-~

Note: I. 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 Kl A 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+/- 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. I. b of ES-40 L for guidance regarding elimination of inappropriate Kl A statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant specific priority, only those KAs having an importance rating (JR) 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 I and 2 from the shaded systems and Kl A categories.

7.* The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of th.: KIA Catalog. but the topics must be relevant to the applicable evolution or system. Refer to Section D. I .b of ES-401 for the applicable K/A'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. I 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. !Rs. and point totals(#) on Form ES-401-3. Limit SRO selections to K/As tha~_<_1~e_lin_k~d__to l_O.fFR554~

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

EA2.03 - Ability to determine and/or 295031 Reactor Low Water Level I interpret the following as they apply to 2 x REACTOR LOW WATER LF.VF.L

  • 4.2 76 Reactor pressure F.A2.04 - Ability to determine and/or 295028 High Orywell Temperature interpret the following as the) apph to 4

)( 0 77 5 I !IGH DR YWEl.l. TLMPIR.\ll 'RL Drywell pressure EA2.02 - Ability to dckrmu1e and/or interpret the following as they apply to 295037 SCRAM Conditions Present and Reactor Power Above ){'" SCRAM CONDITION PRESENT AND 4.2 78 REACTOR POWER ABOVE APRM Al'RM Do\\nscalc or Unknown I I DOWNSCALE OR lJNKNOW"i : Reactor water level 2.1.25 - Conduct of Operations Ability to 295038 I !igh Ort~sitc Release Rate I 9 x interpret reference materials. such as graphs, 4.2 79 curves. tabks. etc.

2.4 31 - Emergency l'rocedurcs 'l'lan 295006 SCRAM I I x Knowledge or annunciator alarms. 41 8()

indications. or response procedures.

2.1.32 - Conduct of Operati1ms i\bilit\ to 295021 Loss of Shutdown Cooling 14 x explain and apply all" stem 1111111.s mid 4 (I XI precaul ions.

EA2 01 - Abilitv to dctcrmu1c and/or interpret the following as they apply to 295026 Suppression Pool High Water Temp. I 5 x SUPPRESSION POOL HIGHWATER 4.2 82 TEMPERATURE: Supprcssim pool water temperature AKl.O! - Knowledge of the operatima!

implications of the following concepts as 295018 Partial or Total Loss of they apply to PARTIAL OR COMPLETE ccw /8 x LOSS OF COMPONENT COOLING 3.5 39 I

'M **

  • WATER : Effects on component/system operations EKI.01 - Knowledge of the operational 295026 Suppression Pool High implications of the following concepts as Water Temp. I 5 x they apply to SUPPRESSION POOL HIGH 3.0 *10 WATER TEMPERATURE* Pump NPSH AK! .06 - Knowledge of the operatimal implications of the following concepts as 295003 Partial or Complete Loss of AC I 6 x they apply to PARTIAL OR COMPLETE 3.8 41 LOSS OF A.C. POWER : Station Blackout:

Plant Specific EK2. l I - Knowledge of the interrelations 29503 I Reactor Low Water Level I2 x between REACTOR LOW WATER LEVEL 4.4 42 and the following: Reactor protection system EK2.03 - Knowledge of the interrelations 295028 High Drywell between HIGH DRYWELL l'cmperature I 5 x TEMPERATURE and the following:

3.6 43 Reactor water level indication EK2.01 - Knowledge of the interrelations 295025 I ligh Reactor Pressure I 3 x between HIGH REACTOR PRESSURE 4.1 44 and the following RPS AK3. 03 - Knowledge of the reasons for the following responses as they apply to 295019 Partial or Tota! Loss of Inst. Air I 8 x PARTIAL OR COMPLETE LOSS OF 3.2 45

'**'*** ' INSTRUMENT AIR : Service air isolations: Plant-Specific 295023 Refueling AecCoo!ing AK3.03 - Knowledge of the reasons for Mode I 8 x . the followinQ responses as they apply to 3.3 46

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

REFUELING ACCIDENTS . Ventilation Isolation AK3.04 - Knowledge of the reasons for the following responses as they apply to 600000 Plant Fire On-site I 8 x PLANT FIRE ON SITE: Actions 2.8 47 contained in the abnormal procedure for olant fire on site

' AA 1.01 - Ability to operate and/or monitor the following as they apply to 295004 Partial or Total Loss of DCPwr/6 x PARTIAL OR COMPLETE LOSS OF 3.3 48 A

D.C. POWER: D.C. electrical distribution svstems AA 1 04 - Ability to operate and/or 295021 Loss of Shutdown Cooling monitor the following as they apply to 14 x LOSS OF SHUTDOWN COOLING :

3.7 19 Alternate heat removal methods AA 1.01 - Ability to operate and/or monitor the following as they apply to 295001 Partial or Complete Loss of Forced Core Flow Circulation x PARTIAL OR COMPLETE LOSS OF 3.5 50 FORCED CORE FLOW CIRCULATION:

Recirculation svstem AA2.01 - Ability to determine and/or 295005 Main Turbine Generator interpret the following as they apply to Trip I 3 x MAIN TURBINE GENERATOR TRIP:

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

Containment conditions/isolations AA2.05 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage and Electric Grid Disturbances x GENERATOR VOLTAGE AND 3 .2 53 ELECTRIC GRID DISTURBANCES Ooerational status of offsite circuit.

295030 Low Suppression Pool 2.4.6 - Emergency Procedures I Plan:

Water Level I 5 x Knowledae of EOP mitic:iation strategies.

3.7 54 2.2.37 - Equipment Control: Ability to 295024 High Drywell Pressure I 5 x determine operability and/or availability 3.6 55 of safetv related equipment

,, 2.4.11 - Emergency Procedures I Plan:

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

EK2.03 - Knowledge of the interrelations 295038 High Off-site Release Rate between HIGH OFF-SITE RELEASE 19 x RATE and the following: Plant 3.6 57 ventilation svstems AK3.05 - Knowledge of the reasons for the following responses as they apply to 295001 Partial or Complete Loss PARTIAL OR COMPLETE LOSS OF of Forced Core Flow Circulation I x FORCED CORE FLOW CIRCULATION 3.2 58 1&4

Reduced loop operating requirements:

Plant-Soecific K/A Category Totals: 3 4 4 3 3/4 3/3 Group Point Total 1 20/7

ES-401 3 Form ES-401-1 Oyster Creek Initial NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 16=E=A=P=E=#~/=N=am~e=S=a=fe=ty~F=u=nc=t=io=n:d,,=K=1:d.=K=2=='==K=3=='==A=1='~A=2:d.~G~~~~~~=K=/A~T=o=p=ic=(s=)~~~~~~'-lm~~l~~~]

EA2.04 - Ability to detcnm1e and I or interpret the following as they apply to

'iOOOOO High CTMT Hydrogen c*onc. I 5 x HIGH PRIMARY CONTAINMENT 3.3 83 HYDROGEN CONCENTRATIONS:

Combustible limits for wctwcll 2.2.42 - Equipment Control: Ahility to 295029 High Suppression Pool recognize system parameters that arc entry-Water Level I 5 x level conditions for Technical 4.6 84 Specifications.

2.2.37 - Equipment Control Ahility tn 295026 - Suppression pool high water temperature x determine opcrahilitv and I or a\ ailahility of 4h X'i safety rdated equiprnrnt EK 1.02 - Knowledge ofthe operational 295033 High Secondary implications of the following concepts as 3.

Containment Area Radiation x they apply to HIGH SECONDARY 9

59 Levels I 9 CONTAINMENT AREA RADIATION LEVELS : Personnel protection EK2.0I - Knowledge of the interrelations between SECONDARY CONTAINMENT 295035 Secondary Containment 3.6 High Differential Pressure I 5 x HIGH DIFFERENTIAL PRESSURE and 60 the following: Secondary containment ventilation AK3.04 - Knowledge of the reasons !Or the 295002 Loss of Main Condenser following responses as they apply to LOSS 3.

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

2950 I 0 High Drywell Pressure I 5 x DRYWELL PRESSURE: Drywell floor and 6 62 equipment drain sumps AA2.03 - Ability to determine and/or 295020 Inadvertent Cont. interpret the following as they apply to 3 Isolation I 5 & 7 x INADVERTENT CONTAINMENT 7 63 ISOLATION : Reactor power 2.4.45 - Emergency Procedures I Plan:

295034 Secondary Containment 4.

Ventilation High Radiation I 9 x Ability to prioritize and interpret the 1

64 significance of each annunciator or alarm.

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

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

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

1 2 3 4 5 6 1 3 4 I A2.02 - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those 400000 Component Cooling predictions, use procedures to Water x correct, control. or mitigate the 30 86 consequence:, DI' tll<lse abnormal operation I ligj1'lDw surge tank kvel A2.0 I - Ability to (al predict the impacts or tht: i(1llLl\\ ing on the INSTRUMENT AIR SYSTEM mid (b) based on those pn:drctions, use

.lOOOOO Instrument Air x procedures to correct, control, or 2.8 87 mitigate the consequences of those abnormal operation: Air dryer and filter malfunctions 2.2.38 - Equipmrnt Control:

209001 LPCS x Knowledge of eonditiom and 4.5 88 limitations in the facility license.

2.4.41 - f'mcrgcnc) Procedures I Plan: Knowledge oi'thc emergency 205000 Shutdown Cooling x action level thresholds md 4(> 8'1 classification>>

i\2 03 - Ability to (al predict the impacts or the l(illtl\\ ing on the IU'.LIEl*/SMLTY Vi\L.VES. and (b) based on those predictions, use 239002 SRVs x procedures to correct, control, or 4.2 l)()

mitigate the consequences of those abnomial conditions or operations:

Stuck open SR V K 1.04 - Knowledge of the physical connections mid/or cause- effect relationships between 264000 EDGs x EMERGENCY GENERATORS 3.2 I (DIESEL/JET) and the following Emergency generator cooling water system K1 01 - Knowledge of the physical connections and/or 259002 Reactor Water Level cause- effect relationships Control x between REACTOR WATER 3.8 2 LEVEL CONTROL SYSTEM and the followina: RPS K2.01 - Knowledge of electrical 207000 Isolation (Emergency) power supplies to the following:

Condenser x Motor operated valves: BWR-3.6 3 2,3 K2.01 - Knowledge of electrical 300000 Instrument Air x power supplies to the following: 2.8 1 Instrument air compressor K3.02 - Knowledge of the effect that a loss or malfunction of the D.C. ELECTRICAL 263000 DC Electrical Distribution x DISTRIBUTION will have on 3.5 5 following: Components using D.C. control power (i.e.

breakers)

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

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

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

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

2.6 9 Discharge line quencher operation K5.03 - Knowledge of the operational implications of the following concepts as they apply 211000 SLC x to STANDBY LIQUID 3.2 IO CONTROL SYSTEM Shutdown Margin K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the 215003 !RM x INTERMEDIATE RANGE 3.0 11 MONITOR (IRM) SYSTEM :

Detectors K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the 261000 SGTS x STANDBY GAS TREATMENT 2.9 12 SYSTEM : Process radiation monitorinq A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 218000 ADS x AUTOMATIC 3 .4 13 DEPRESSURIZATION SYSTEM controls including: ADS valve tail pipe temperatures A 1.01 -Ability to predict and/or monitor changes in parameters associated with operating the PRIMARY CONTAINMENT 223002 PCIS/Nuclear Steam x ISOLATION 3.5 14 Supply Shutoff SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including: System indicating lights and alarms

ES-401 4 Form ES-401-1 Oyster Creek Initial NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A Imp System # I Name A2 G 1 2 3 4 5 6 1 3 4 A2.11 - Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION ; and (b} based 262001 AC Electrical on those predictions, use 15

)( 3.2 Distribution procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Degraded system voltaoes A2.11 - Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) 205000 Shutdown Cooling x based on those predictions, use 2.5 16 procedures to correct, control, or mitigate the consequences of those abnormal conditions Recirculation pump trips: Plant-

  • Specific A3.04 - Ability to monitor automatic operations of the 209001 LPCS x LOW PRESSURE CORE 3.7 17 SPRAY SYSTEM including:

System flow A3.04 - Ability to monitor automatic operations of the 215004 Source Range Monitor x SOURCE RANGE MONITOR 3 (1 18 (SRM) SYSTEM including Control rod block status A4.01 - Ability to manually 400000 Component Cooling operate and/or monitor in the Water x control room: CCW indications 3.1 19 and control A4.03 - Ability to manually 263000 DC Electrical operate and/or monitor in the Distribution x control room: Battery discharge 2.7 20 rate: Plant-Specific 2.4.9 - Emergency Procedures I Plan: Knowledge of low power I 205000 Shutdown Cooling x shutdown implications in 3.8 21 accident (e.g. LOCA or loss of RHR) mitioation strateaies.

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

K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the 215005 APRM I LPRM x *.

AVERAGE POWER RANGE 3.1 23 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM :

Detectors

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

1 2 3 4 5 6 1 3 4 K1 .13 - Knowledge of the physical connections and/or cause- effect relationships 212000 RPS x between REACTOR 3.5 24 PROTECTION SYSTEM and the following: Containment pressure A2.04 - Ability to (a) predict the impacts of the following on the CCWS and (b) based on those 400000 Component Cooling predictions, use procedures to Water x correct, control, or mitigate the 2.9 25 consequences of those abnormal operation: Radiation monitoring system alarm K3.01 - Knowledge of the effect that a loss or malfunction of the 259002 Reactor Water Level Control x REACTOR WATER LEVEL 3.8 26 CONTROL SYSTEM will have on following: Reactor water level Kl A Category Totals: 3 2 3 2 2 3 2

~'~- 2 2 2/2 Group Point Total:

I 26/5

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

1 2 3 4 5 6 1 3 4 #

~

A2.07 - Ahilitv to (a) pn:dict the impacts of the following on the ROD WORT! I MINIMIZER SYSTEM (RWH) (PLANT SPECIFIC): and (b) based on those 201006 RWM x predictions, use procedures to 2.8 91 correct control. or mitigate the consequences or those abnormal conditions or operations: RWM hardware/software failure: !'-Spec 2.4.45 - Emergency Procedures I 2-\3000 h1el Pool Plan: Ahilit\' to prinrrr11c and

( \101ing/C'Jcanup x interpret the '1gmtlcancc ,if each

-I' 92 annunciator or alarm 2.1 7 -(*nnduct of<lpt:ratiuns:

Ability to C\ aluatc plant 245000 Main Turbine Gen. I pcrf(irmancc mid make operational

,\ux.

x _Judgments based on operating

j 7 '!3 characteristics. reactor behavior.

and instrument interpretation.

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

x TURBINE GENERATOR AND 3.2 27 AUXILIARY SYSTEMS and the following: A. C electrical distribution K2.01 - Knowledge of electrical power supplies to the following 259001 Reactor Feedwater x Reactor feedwatcr pump(s) 3.3 28 Motor-Driven-On Iv K3.03 - Knowledge of the effect that a loss or malfllllction of the RHR/LPCI CONTAINMENT SPRAY SYSTEM MODE will 22600 I RHR/LPCI: CTMT Spray Mode x have on following 2.9 29 Containment/drywell/suppression chamber components, continued operation with elevated pressure and/or temperature and/or level K4.05 - Knowledge of CONTROL ROD AND DRIVE 20 I 003 Control Rod and MECHANISM design feature(s)

Drive Mechanism x and/or interlocks which provide 3.2 30 for the following: Rod position indication K5.01 - Knowledge of the operational implications of the following concepts as they apply 214000 RPIS x to ROD POSITION 2.7 31 INFORMATION SYSTEM :

Reed switches K5.02 - Knowledge of the operational implications of the 234000 Fuel Handling Equipment x following concepts as they apply 3.1 32 to fuel handing equipment: Fuel handlina equipment interlocks.

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

1 K

2 K

3 4 K K 5

K 6

A 1

A2 A

3 A

4 G l,m,In A 1.01 - Ability to predict and/or h

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

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

lnitiation/reconfiquration A4.05 - Ability to manually 204000 RWCU x operate and/or monitor in the 2.9 36 control room: System pressure 233000 Fuel Pool 2.4.11 - Knowledge of abnormal Cooling/Cleanup x conditions procedures 2.7 37 A2.08 - Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions, use 271000 Off-gas x procedures to correct, control, 2.5 38 or mitigate the consequences of those abnormal conditions or operations: A.C. distribution failures 1 2/1 1 1 1/2 Group Point Total: 12/3 KIA Category Totals: 1 1 1 1 1 1 I

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

Knowledge of refueling administrative 2.1.40 3.9 94 requirements

-- ~----

  • -~-~** ----~*--

-~-. -- -~

Knowledge of industrial safety procedures 1.

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

Knowledge of conduct of operations 2.1.1 3.8 67 requirements.

Subtotal _ __ t------- 2 1 Knowledge of the process for conducting 2.2.7 36 95 special or infrequent tests. --*- - -------

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

2. ----- ,.__ _____

Equipment Knowledge of individual licensed operator Control related to shift staffing, such as medical 2.1.4 requirements, "no-solo" operation, 3.3 68 maintenance of active license status, 10CFR55, etc *-- ~-

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

2.2.12 Knowledge of surveillance procedures. 3.7 75 Subtotal 3 2 2.3.11 Ability to control radiation releases. 4.3 96 Knowledge of radiation or contamination hazards that may arise during normal, 2.3.14 38 98 I abnormal, or emergency conditions or '

3.

Radiation activities. - - - - - ----- - --

--~-- ~---

l---- --

Control

- - t-------------

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

~ . . .

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

Ability to use radiation monitoring systems, --i--- ---

such as fixed radiation monitors and alarms, 2.3.5 2.9 74 portable survey instruments, personell monitoring equioment, etc.

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

Knowledge of the bases for prioritizing 2.4.23 emergency procedure implementation during 44 100 emeraencv ooerations. --- . . --- ------- L__--~-

- --- - - - f--*

4. -- - - - ' - - - * - - ----- ---- ---- ------

Emergency Knowledge of facility protection Procedures I 2.4.26 requirements, including fire brigade and 3.1 72 Plan portable fire fiahtina eauioment usaae.

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

,___ ___ j -- -

-J

-*-- --**-~- --

Subtotal 2 2

--- -*------ - i Tier 3 Point Total 10 *-'-*-

7 __j

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

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

Explain RPS Manual Scram Circuit Using Prints Equipment Control N,R KA 2.2.41 (3.5) GE 237E566 Actions for External Security Threats Emergency Plan N,R KA 2.4.28 (3.2) Procedure ABN-41 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

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

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

P, R Bypass (11-1 NRC)

Conduct of Operations KA 2.1.9 (4.5) Procedure 403 Explain RPS Manual Scram Circuit Using Prints and Determine Technical Specification Requirements for Equipment Control N,R RPS Manual Scram Pushbutton KA 2.2.41 (3.9) GE 237E566 Authorize Emergency Exposures Radiation Control D,R KA 2.3.4 (3. 7) EP-AA-113 Emergency Plan Emergency Event Classification N,R KA 2.4.29 (4.4)

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

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

System I JPM Title Type Code* Safety Function

a. Perform Control Rod Exercising Test (Or a rod sequence N,S,A 1 exchange) - uncoupled Rod KA 201003 A2.02 (3.7/3.8) ABN-6
b. Sequential Loss of Service water N,S,A 8 KA 400000 K1 .01 (3.2/3.3)ABN-18
c. Place Second RWCU Pump in Service (RO Only) M,S 2 KA 204000 A4.01 (3.1/3.0) Procedure 303
d. Partial MSIV Stroke Test N, S,A 3 KA 239001 A4.01 (4.2/4.0) Procedure 602.4.004
e. Cool Down the RPV Using IC Tube Side Vents D,S,A,EN 4 KA 295021 AA1.04 (3.7/3.7) SP-15
f. Place H2/02 Monitoring in Service D,S, L 5 KA 500000 EA1.01 (3.4/3.3) SP-39
g. Startup of the Turbine Building Ventilation System D,S,A,L 9 KA 288000 A4.01 (3.1/2.9) Procedure 328
h. APRM Gain Adjustment D, S 7 215005 A4.03 (3.2/3.3) 202.1-9 In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Vent the Scram Air Header 1 P,R,E KA 295037 EA1.05 (3.9/4.0) SP21 2012 NRC
j. Startup EDG 1 for Peaking Operation 6 KA 264000 K4.07 (3.3/3.4) Procedure 341 D
k. Line up to Vent the Torus through the Hardened Vent P,E 5 KA 295024 EA1.14 (3.4/3.5) SP-35 2012 NRC
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for RO I SRO-I / SRO-U A)lternate path 4-614-6 I 2-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature ~1 I ~1 I~ 1 (control room system)

(L)ow-Power I Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams :5 3 I :5 3 I :5 2 (randomly selected)

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

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

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

Initial Conditions:

  • 97% power
  • Risk is Yellow Turnover:
  • Lower power to 95% using recirculation flow IAW 1001.22-3, Core Maneuvering Daily Instruction Sheet.
  • Following the power reduction Backwash B North Condenser JAW procedure 323.6 Event Malf. No. Event Event No. Type* Description R- Lower reactor power with recirc.

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

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

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

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

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

Events 8,9 2

3. Abnormal events (2-4)

Events 5,6,7 3

4. Major transients (1-2)

Events 1

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

Primary Containment/ RPV Control No-ATWS 2

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

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

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

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

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

Initial Conditions:

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

RCU013 BOP, EMG-3200.11, Secondary Containment Control 2 VLV- SRO RCU001 TS- T.S. 3.5 SRO C-All Loss of VMCC 1B2 MAL-3 TS- ABN-51, Loss of VMCC 182 EDS004B SRO T.S. 3. 7 C-MAL- ATC, CRD Flow Control Failure 4 SRO CRD001A ABN-6, Control Rod Malfunctions R-MAL- ATC OFF-Gas Deflagration/ with condenser vacuum leak OGS003 C- ABN-25, OFF-Gas Deflagration 5

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

Loss of Stator Cooling MAL-C-

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

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

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

Events 7,8 2

2. Abnormal events (2-4) 4

,___ Events 3,4,5,6

3. Major transients (1-2)

Event 7 1

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

RPV Control No-ATWS 1

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

RPV Control With ATWS 1

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

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

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

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

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

Appendix D Scenario Outline Form ES-0-1 Facility: Oyster Creek Scenario No.: Scenario 3 Op-Test No.: NRC 2016 Examiners: Operators:

Initial Conditions:

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

1 N/A SRO 336.1 24 KV main generator electric system R-ATC, EMRV Spuriously opens SRO MAL-2 ABN-40, Stuck open EMRV NSS025E C-BOP T.S 4.5.L TS-SRO MAL- C-ATC CRD high temperature alarm 3 CRD013 3 SRO RAP-H5c CRD Hi Temp 403 C-BOP Trip of 1A3 MAL- SRO 4 ABN-46, Loss of 1A3 EDS003C TS-SRO T.S -3.7 MAL-RBC001A RBCCW Pump Trip Leads to Reactor Scram 5 C-ALL MAL- ABN-19 RBCCW failure response RBC0018 MAL- LOCA in Primary Containment 6 M-ALL NSS017A EMG-3200.02 Primary Containment Control Containment Spray Fails to Swap to DW Spray Mode VLV- C-BOP, 7 EMG-SP29 Initiation of the containment Spray system for Drywell CNS005 SRO Sprays

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

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

Events 7,8 2

2. Abnormal events (2-4)

Events 2,4,5 3

3. Major transients (1-2)

Event 6,8 2

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

RPV control No-ATWS, Primary Containment 2

f--*

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

ED No-ATWS, RPV Flooding No-ATWS 2

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

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

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

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

Appendix D Scenario Outline Form ES-D-1 Facility: Oyster Creek Scenario No.: Scenario 4 (Spare) Op-Test No.: NRC 2016 Examiners: Operators:

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

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

  • (N)ormal, (R)eactivitv, (l)nstrument, (C)omoonent, (M)aior Facility: Oyster Creek Scenario No.: Scenario 4 Op-Test No.: NRC 20 -----

16

1. Malfunctions after EOP entry (1-2)

Events 8 1

2. Abnormal events (2-4)

Events 2,4 2

3. Major transients (1-2)

Event 8 1

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

RPV Control No-ATWS 1

~-

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

Emergency Depressurize No-ATWS, 2 Secondary Containment

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

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

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

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

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