ML12270A389

Initial Exam 2012-301 Draft Administrative Documents

ML12270A389
Person / Time
Site:	Oconee
Issue date:	09/24/2012
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
Download: ML12270A389 (22)

Text

DRAFT ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

RO K/A Category Points SRO-Only Points Tier Group KIKKKKIKAAAAG A2 G* Total 112 3

5L6 1

2 3 4 *

=

Total

=

1. i 333 33 3 18 3 3 6 Emergency&

Abnormal Plant 2 2 1 1 9 2 2 4 NIA N/A Evolutions Tier Totals 5 4 5 5 4 4 27 5 5 10

= = = = = =

1 33233232322 28 2 3 5 2 11011111111 10 ij 2 Pnt 3 Systems Tier Totals 4 42 4 4 3 4 3 4 3 3 38 5 8

3. GenericknowiedgeandAbilitles 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 1 2 2 2

1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (I.e., except for one category in TIer 3 of the SRO-only outline, the IerTotals@

in each K/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 )4 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 0.1 .b of ES-401 for guidance regarding the elimination of Inappropriate K/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 K/As having an Importance rating (lR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO.oniy portions, respectively.

6. Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories.

7. The generic ((3) K/As In Tiers I and 2 shall be selected from SectIon 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section 0.1 .b of ES.401 for the applicable KAs.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the toplcsimport ance ratings (IRs) 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 (3* 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 K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES.401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.48..

DRAFT

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR 1(1 K2 1(3 1(4 KS K6 Al A2 A3 A4 G TOPIC:

RO SRO 008AK2.0l Pressurizer Vapor Space Accident/3 2.7 2.7 flEIL1 ElELI LI El LI LI Valves 009EK2.03 Small Break LOCA / 3 3 E1iIZ1E LI C] LI Li LI LI LI SJGs 011 EA2.0l Large Break LOCA /3 4.2 LILJEILJ LI LID I LI El LI Actions to be taken based on RCS temperature and pressure saturated and superheated 015AK2.10 RCP Malfunctions / 4 2.8 2.8 flEE1 LI LI LI LID LID RCP indicators and controls 022AK1 .03 Loss of Rx Coolant Makeup /2 3 3.4 IEOEI EIDD LID Relationship between charging flow and PZR level 026AG2.4.49 Loss of Component Cooling Water / 8 4.6 EILIEIEI LI LI LI LI LI LI IJ Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

029EA1 .03 ATWS / 3.5 3.2 OLILILJ LI LI I LI LIE LI Charging pump suction valves from VCT operating switch 038EK1 .02 Steam Gen. Tube Rupture / 3 3.2 3.5 LJLJE1 LILIELI LI LID Leak rate vs. pressure drop 054AG2.4.4 Loss of Main Feedwater / 4 4.5 4.7 LILILILI DLI LI LIE LI Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

055EA2.03 Station Blackout / 6 3.9 4.7 EILIELI DLIDD LID Actions necessary to restore power 056AK3.02 Loss of Off-site Power / 6 4.4 4.7 LI LI I LI LI LI LI LI LI LI LI Actions contained in EOP for loss of offsite power Page 1 of 2 10126/2011 10:46 PM

ES-401, REV 9 T1GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: lB Ki 1(2 1(3 K4 1(5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 057AA1.04 Loss of Vital AC Inst. Bus /6 3.5 3.6 C] C] Li LI LI LI I1 [1 0 0 0 RWST and VCT valves 058AK3.02 Loss of DC Power / 6 4 4.2 Li C] II 0 LI Li Li Li Li El El Actions contained in EOP for loss of dc power 062AA1 .06 Loss of Nuclear Svc Water /4 2.9 2.9 Li fl El Li Q Control of flow rates to components cooled by the SWS 065AG2.i .28 - Loss of Instrument Air /8 4.1 4.1 Li Li Li Li C][] Li Li U Knowledge of the purpose and function of major system components and controls.

iAK1.O1 Generator Voltage and Electric Grid 3.3 3.5 Li Li El L Li LI LI Li Li El Definition of the terms: volts, watts, amps, VARS, power Disturbances / 6 factor BEO4EA2.1 Inadequate Heat Transfer Loss of

- 3.2 4.4 Li Li Li Li OLi Li 1 Li Li Li Facility conditions and selection of appropriate Secondary Heat Sink! 4 procedures during abnormal and emergency operations.

BEO5EK3.3 Steam Line Rupture- Excessive Heat 4.2 3.8 C] El [) U Li El U Li 0 Li [1 Manipulation of controls required to obtain desired Transfer /4 operating results during abnormal, and emergency situations.

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ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 024AK3.O1 Emergency Boration I 1 4.1 4.4 [] fl [] [] [] [] [] [] [] ) [j When emergency boration is required 059AK3.04 Accidental Liquid RadWaste Rd. / 9 3.8 4.3 El Li LI LI LI El El LI El El Actions contained in EOP for accidental liquid radioactive-waste release O6OAK1 .04 Accidental Gaseous Radwaste Rel. / 9 2.5 3.7 [] El El El LI [I El [I El El Calculation of offsite doses due to a release from the power plant 068AA1 .07 Control Room Evac. 18 4.1 4.2 [] [] [] El [J [J [] [] [ PZR heaters 074EK2.02 mad. Core Cooling/ 4 3.9 4 [] [] [] [] [] ] [] [] ] PORV BAO1AG2.1 .31 Plant Runback /1 4.6 4.3 [] J [J [J [] [] [] [] [] ] Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

BAO4AK1 .3 Turbine Trip / 4 3.2 3.3 [] El El El El El El El El El El Annunciators and conditions indicating signals, and remedial actions associated with the (Turbine Trip).

BEO8EA1.1 LOCA Cooldown Depress. / 4

- 4 3.7 El LI El El El El J LI El El El Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

BE14EA2.1 EOP Enclosures 3.4 4 El El El El LI LI El ] LI LI LI Facility conditions and selection of appropriated procedures during abnormal and emergency operations.

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ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 1<3 1<4 1<5 1<6 Al A2 A3 A4 G TOPIC:

RO SRO 003K2.02 Reactor Coolant Pump 2.5 2.6 [] j fl [J [] Q U fl fl [] CCW pumps 004K3.05 Chemical and Volume Control 3.8 4.2 1 U U U U U U Li [] PZR LCS 005A4.04 Residual Heat Removal 3.1 2.9 0 Q (] U U U ULi [J J Controls and indicaticn for closed cooling water pumps 006K6.O1 Emergency Core Cooling 3.4 3* BlTiborated water sources

[] Q C LI LI LI LI LI U U 006K6.10 Emergency Core Cooling 2.6 2.8 U Li U U LI U LI [1 U LI Valves 007G2.1 .7 Pressurizer Relief/Quench Tank 4.4 4.7 0 [] U U C C U U } Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and inslwment interpretation.

007K1 .03 Pressurizer Relief/Quench Tank 3.0 3.2 U C U U U DLI U U U RCS - --_______________

008K4.09 Component Cooling Water 27 2.9 U U U II U LI U U LI U U The standby feature for the CCW pumps 01 0G2.2.42 Pressurizer Pressure Control 3.9 4.6 U LI U U U U LI U U Li } Ability to recognize stem parameters that are entry-level conditions for Technical Specifications 012K1 .04 Reactor Protection 3.2 3.3 U U U U Li U LI U U U RPIS 0131<5.02 Engineered Safety Features Actuation 2.9 3.3 U U U U II U U U U U Li Safety system logic and reliability Page 1 of 3 1W26/2011 10:46PM

ES-401, REV 9 T2G1PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR 1(1 1(2 1(3 1(4 1(5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 022A3.01 Containment Cooling 4.1 4.3 C] C] C] C] [] C] U Initiation of safeguards mode of operation 026K4.02 Containment Spray 3.1 i6 [] [1 [] El [1 U [1 [1 C] U Neutralized boric acid to reduce corrosion and remove inorganic fission product iodine from steam (NAOH) in containment spray 0391(5.01 Main and Reheat Steam 2.9 3.1 C] U El I Cl U [J [] C] C] Definition and causes of steamlwater hammer 059A2.07 Main Feedwater 3.0 3.3 C] C] C] [][J [] C] ] El C] U Tripping of MFW pump turbine 061A1.03 Awdliary/EmergencyFeedwater 3.1 3.6 Cl U C] [] C] [] ] C] [] [] C] Interactions when multi unit systems are cross tied 0611(5.03 Au,dliary/Emergency Feedwater 2.6 2.9 [] El U C] C] DC] [] Cl C] Pump head effects when control valve is shut 062A1 .03 AC Electrical Distribution 2.5 2.8 C] C] [1 U U C] I] U C] U C] Effect on instrumentation and controls of switching power supplies 0621(1.04 AC Electrical Distnbution 3.7 4.2 J [] C]UUUDUUUC] Off-sitepowersources 063A3.01 DC Electrical Distribution 2.7 ai C] C] C] C] UU U U 1C]U Meters, annunciators, dials, recorders and indicating lights 064A1.05 Emergency Diesel Generator 25 25 C] C] C] C] DC] IUU C] El EDIG room temperature 073A4.01 Process Radiation Monitoring 3.9 U C] U U C] C] C] U C] U Effluent release Page 2 of 3 10126/2011 10:46PM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR KI 1<2 1<3 1<4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 0761<2.04 Service Water 2.5 a6 flJJLJrflQQ Reactor building closed coding water 0761<3.02 Service Water 2.5 2.8 DODD1DJfl Secondary closed coding water 078A3.01 Instrument Air 3.1 3.2 [] fl [] [3 [] [3 [3 [3 [] [3 Air pressure 0781<2.02 Instrument Air 3.3 3.5 [3 (} [3 [3 [3 [3 [3 [3 [3 [3 [3 Emergency air conipresscx 103A2.05 Containment 2.9 3.9 [3 [3 [3 [3 [3 [3 [3 J [3 [3 [3 Emergencycontainmententry 1031<4.01 Containment 3.0 3.7

[3 [3 [3 [3 [3 [3 [3 [3 [] [] Vacuum breaker protechon Page 3d 3 10/26/2011 10:46PM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME! SAFETY FUNCTION: IR 1<1 1<2 1<3 K4 K5 1<6 Al A2 A3 A4 G TOPIC:

RO SRO 0011<2.03 Control Rod Drive 2.7 3.1 [] Q LI i:i El E1LEJLI One-line diagram of power supplies to logic circuits 002A3.03 Reactor Coolant 4.4 4.6 CflUE1DE1 EL1U Pressure, temperatures and flows 0151<4.10 Nuclear Instrumentation 3.2 3.5 DEIH1LJI1 El LI Redundant sources of information on power level 028A1 .02 Hydrogen Recombiner and Purge Control LWL1EOL Containment pressure 029A4.04 Containment Purge 3.5 36 ODU Containment evacuation signal 033G2.4.9 Spent Fuel Pool Cooling 3.8 4.2 El LI El Knowledge of low power! shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

056A2.04 Condensate 2.6 2.8 LJLLJE EIUEl Loss of condensate pumps 0681<6.10 Liquid Radwaste 2.5 2.9 EU LID LI LI Radiation monitors 072K5.01 Area Radiation Monitoring 2.7 3.0 E1LEDLH1 LiDDLI Radiation theory, including sources, types, units and effects 079K1 .01 Station Air 3.0 3.1 1ULJD El El El El lAS Page 1 of 10/2612011 10:46PM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: (R 1<1 K2 1<3 K4 K5 KG Al A2 A3 A4 G TOPIC:

RO SRO G2.l.17 Conduct of operations 3.9 4.0 fl El El El [1 El El El El El lJ Abdity to make accurate, clear and conctsa verbal reports.

G2.1 .20 Conduct of operations 4.6 4.6 El El El El El El El El El El ll Ability to execute procedure steps.

G2.1.39 Conductof operations 3.6 4.3 fl C] El El El El El El El El SJ Knowledge of conservative decision making practices G2.2.1 Equipment Control 4.5 4.4 El El El El El El El El El El ll Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

G2.2.39 Equipment Control 3.9 El El El El El El LI El El El lJ Knowledge of less than one hour technical specification action statements for systems.

G2.2.6 Equipment Control 3.0 3.6 El El El El El El El El El El fl Knowledge of the process for making changes to procedures G2.3.1 I Radiation Control 3.8 4.3 El El El El El El El El El El J Ability to control radiation releases.

G2.3.7 Radiation Control 3.5 3.6 El El El El El El El El El El ll Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.29 Emergency Procedures/Plans 3.1 4.4 [1 [1 El El El El El El El El Il Knowledge of the emergency plan.

G2.4.39 Emergency Procedures/Plans 3.9 3.8 El El El El El El El El El El l1 Knowledge of the R0s responsibilities in emergency plan implementation.

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ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 008AA2.30 Pressurizer Vapor Space Accident / 3 DLlOflOflflDDU Inadequate core coding 015AA2.07 RCP Maltunctioris /4 ai 2.9 Calculation of expected vahies of fI in the loop with RCP secured 025AG2.1 .20 Loss of RHR System / 4 4.6 4.6 EDflEDflDOI Ability to execute procedure steps.

054AG2.1.19 Loss of Main Feedwater/4 3.9 3.8 UU1DUELüD Ability to use plant computer to evaluate system or component status.

058AG2.a38 Loss of DC Pcmer /6 3.6 4.5 Knowledge of conditions end limitations in the facility license.

BEO4EA2.1 Inadequate Heat Transfer Loss of

- 3.2 4.4 DDDDOUDDU Facility conditions and sdection of appropriate procedures Secondary Heat Sink /4 during thnormal and emergency operations.

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ES-401, REV9 SRO Ti G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1K2K3K4K5K6AIA2A3A4G TOPIC:

RO SRO 001 AG2.1 .32 Continuous Rod Withdrawal / 1 3.8 4.0 Ability to explain and apply all system limits and precautions.

028AA2.10 Pressurizer Level Malfunction /2 ELL1 Whether the automatic mode for PZR level control is functioning improperly, necessity of shift to manual modes BEO3EA2.2 Inadequate Subcooling Margin / 4 Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.

BE14EG2.4.2 EOP Enclosures 4.5 4.6 Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

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ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTUNE FORM ES-401-2 KA NAME / SAFETY FUNCTION: iR K1 1(2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 006G2.4.20 Emergency Core Cooling 3.8 4.3 1JJ Knowledge of operational implications of EOP warnings, cautions and notes.

007A2.04 Pressurizer Relief/Quench Tank 2.5 2.9 Overpressurization of the waste gas vent header 061 A2.08 Auxiliary/Emergency Feedwater 3.4 3.8 LJDOJ1JJ pump failure or improper operation 063G2.4.18 DC Electrical Distribution 3.3 4.0 Knowledge of the specific bases for EOPs.

064G2.2.22 Emergency Diesel Generator 4.0 4.7 UUOL1LJ Knowledge of limiting conditions for operations and safety limits.

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ES-401, REV9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 01 6A2.02 Non-nuclear Instrumentation 2.9 3.2 Loss of power supply 017G2.2.25 In-core Temperature Monitor 3.2 4.2 jFJJfl Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

068G2.2.40 Liquid Radwaste 3.4 4.7 Ability to apply technical specifications for a system.

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ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR 1(1 K2 K3 1(4 K5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l .43 Conduct of operations 4.1 4.3 [] fl Li [] Li [ Z1 gj Ability to use procedures to determine the effects on reactivity of plant changes G2.2.l 5 Equipment Control 3.9 4.3 [] Li Li Li [] Li Ability to determine the expected plant configuration using design and configuration control documentaion G2.2.40 Equipment Control 3.4 4.7 Li Li Li Li Li Li Li Ability to apply technical specifications for a system.

G2.3.14 Radiation Control 3.4 3.8 Li Li Li Li Li Li Li Li Li Li Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.4 Radiation Control 3.2 3.7 Li Li Li Li Li Li Li Li Li Li Knowledge of radiation exposure limits under normal and emergency conditions G2.4.19 Emergency Procedures/Plans 3.4 4.1 Li Li Li Li Li Li Li Li Li Li Knowledge of EOP layout, symbols and icons.

G2.4.44 Emergency Procedures/Plans 2.4 4.4 Li LI Li Li Li Li Li LI LI El Il Knowledge of emergency plan protective action recommendations.

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ES-301 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 6/11112 Examination Level: RO SRO Operating Test Number: I Administrative Topic Type Describe activity to be performed (see Note) Code*

Admin-120, U3 SFP Boron and Volume Change Conduct of Operations D, R Calculation G 2.1.23 (4.34.4)

(Both) (20 mm)

Admin-127, Diverse verification of reactor Conduct of Operations N,R G 2.1.45 (4.34.3) power (RO Only) (20 mm)

Equipment Control Admin-202, Determine SSF RCMUP Operability M,R (RO Only) (15 mm)

G 2.2.42 (3.9/4.6)

Radiological Control Admin-331, GWD Tank Release paperwork G 2.3.11 (3.8/4.3) N,R (Both) (15 mm)

Emergency Plan N!A NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 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 Administrative Topics Outline Form ES-301-1 Facility: Oconee Date of Examination: 6111112 Examination Level: RO SRO Operating Test Number: I Administrative Topic Type Describe activity to be performed (see Note) Code*

Admin-120, U3 SFP Boron and Volume Change Conduct of Operations D, R Calculation G 2.1.23 (4.3/4.4)

(Both) (20 mm)

Conduct of Operations Admin-141, Calculation of Primary to G 2.1.7 (4.4/4.7) M,R Secondary Leak Rate and Unit Shutdown Requirements (SRO only) (16 mm)

Admin-211, Determine Tech Spec and SLC Equipment Control D,R requirements for inoperable ADV flowpath G 2.2.40 (3.4/4.7)

(SRO only) (20 mm)

Radiological Control Admin-331, GWD Tank Release paperwork N,R G2.3.11 (3.8/4.3) (Both) (15 mm)

Admin-410, Determine Emergency Emergency Plan Classification Upgrade and Protective Action G 2.4.41 (2.9/4.6) D,R Recommendations (SRO only) (20 mm)

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

r ,

3 ES-301 Control R ni/1nP1ait Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 6/11/12 Exam Level: RO SRO-I LI SRO-U LI Operating Test No.: I Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. CR0-I 08, Recover a Dropped Rod OP/i/All 105/019, End. 4.15 (Recovery Of Dropped/Misaligned D, A, S 1 Safety Or Regulating Control Rod with Diamond In Automatic)

[KA: APE 005 AA2.03 (3.5/4.4)]_(15_mm)

b. CRO-208, Sample the Pressurizer and Respond to Indications of RCS Leakage N, A, 5 2 OP/i/A/i 103/004 End. 4.15 (Pzr Sampling)

[KA: SYS 002 A2.01 (4.3/4.4)]_(15_mm)

c. CRO-306, Align HPI/LPI Piggyback Mode EOP End. 5.12, (ECCS Suction Swap to RBES) M, A, EN, L, 3

[KA: EPE 009 EK3.21 (4.2/4.5)] (20 mm) 5

d. CRO-408, Start Fourth Reactor Coolant Pump OP/i/Ni 103/006 End. 4.4 (Starting 1 B2 RCP) D, A, P, L, S 4P

[KA: SYS 003 A4.03 (2.8/2.5)]_(16_mm)

e. CRO-410, Remove Feedwater Pump From Hand Jack D, S 4S OP/i/A/i i06/002B End. 4.12 (Taking 1A FDWPT Off Hand Jack) [KA: SYS 059 A2.li (3.0*3.3*)] (15 mm)

f. CRO-604, Energizing MFB From CT-4 Using Live Bus N, L, S Transfer OP/0/N1106/019 End. 4.11 (Energizing MFB From 6 CT-4 Using Live Bus Transfer)

[KA: SYS 062 A4.01 (3.3/3.1)]_(15_mm)

g. CRO-703, Bypass ES Subsystem 2 N, S, OP/i/Ni 105/014 End. 4.9 (Removal and Restoration of ES 7 Channels)

[KA: SYS 016 A4.01 (2.9*/2.8*)]_(10_mm)

h. CRO-801, Align Intake Canal for Recirc on Dam Failure D, L, S AP/i/Ni700/13 (Dam Failure) 8

[KA: SYS 075 A2.Oi (3.0*/3.2)j (15 mm)

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

i. NLO-200, Align HPI Pump Suction to BWST During a Blackout D, E, L, R 2 EOP End. 5.7 (HPI Pump Operations from ASW Pump Switchgear)

[KA: APE 022 G2.4.35 (3.8/4.0)] (20 mm)

j. NLO-032, Aligning Vacuum Pumps to a Units Vacuum System D, E 4S AP/27 End. 5.1 (Main Vacuum Pump Alignment)

[KA: APE 051 G2.1.20 (4.6/4.6)] (10 mm)

k. NLO-700, Restoration of ICS AUTO Power AP/23 End. 5.2, (Restoration of ICS AUTO Power) D, A, E 7

[KA: BW/A02 AAI.1 (4.0/3.8)] (16 mm)

@ 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 I SRO-l I SRO-U (A)lternate path 4-6 I 4-6 / 2-3 (C)ontrol room (D)irectfrombank 9/814 (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) 2I 2/ 1 (P)revious 2 exams 3 I 3 I 2 (randomly selected)

(R)CA 1I1I1 (S)imulator

ES-301 Controoirftln-Plarit Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 6/11/12 Exam Level: RO SRO-I SRO-U Operating Test No.: I Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. CR0-I 08, Recover a Dropped Rod OP/i/All 105/019, End. 4.15 (Recovery Of Dropped/Misaligned D, A, 5 1 Safety Or Regulating Control Rod with Diamond In Automatic)

[KA: APE 005 AA2.03 (3.5/4.4)] (15 mm)

b. CRO-208, Sample the Pressurizer and Respond to Indications of RCS Leakage N, A, 5 2 OP/1/A11103/004 End. 4.15 (Pzr Sampling)

[KA: SYS 002 A2.01 (4.3/4.4)] (15 mm)

c. CRO-306, Align HPI/LPI Piggyback Mode EOP End. 5.12, (ECCS Suction Swap to RBES) M, A, EN, L, 3

[KA: EPE 009 EK3.21 (4.2/4.5)] (20 mm) 5

d. CRO-408, Start Fourth Reactor Coolant Pump OP/1/A111031006 End. 4.4 (Starting 1B2 RCP) D, A, P, L, S 4P

[KA: SYS 003 A4.03 (2.8/2.5)]_(16_mm)

e. CRO-410, Remove Feedwater Pump From Handjack D, S 4S OP/I/Ni 1061002B End. 4.12 (Taking 1A FDWPT Off Handjack)

[KA: SYS 059 A2.1 1 (3.0*3.3*)] (15 mm)

f. CRO-604, Energizing MFB From CT-4 Using Live Bus N, L, S Transfer OP/0/A11106/019 End. 4.11 (Energizing MFB From 6 CT-4 Using Live Bus Transfer)

[KA: SYS 062 A4.0i (3.3/3.1)] (15 mm)

g. N/A

h. CRO-801, Align Intake Canal for Recirc on Dam Failure D, L, S AP/1/N1700/13 (Dam Failure) 8

[KA: SYS 075 A2.Ol (3.0*/3.2)] (15 mm)

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

I. NLO-200, Align HPI Pump Suction to BWST During a Blackout D, E, L, R 2 EOP End. 5.7 (HPI Pump Operations from ASW Pump Switchgear)

[KA: APE 022 G2.4.35 (3.8/4.0)] (20 mm)

j. NLO-032, Aligning Vacuum Pumps to a Units Vacuum System D, E 4S AP/27 End. 5.1 (Main Vacuum Pump Alignment)

[KA: APE 051 G2.1 .20 (4.6/4.6)] (10 mm)

k. NLO-700, Restoration of ICS AUTO Power AP/23 End. 5.2, (Restoration of ICS AUTO Power) D, A, E 7

[KA: BW/A02 AAI .1 (4.0/3.8)] (16 mm)

@ All RO and SRO-l 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-l / SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irectfrombank 91814 (E)mergency or abnormal in-plant 1 I 1 / 1 (EN)gineered safety feature - I - I 1 (control room system)

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

(R)CA (S)imulator

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Oconee Date of Examination: 6/11/12 Exam Level: RO SRO-I SRO-U Operating Test No.: i Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function a.

b.

c. CRO-306, Align HPI/LPI Piggyback Mode EOP End. 5.12, (ECCS Suction Swap to RBES) M, A, EN, L, 3

[KA: EPE 009 EK3.21 (4.2/4.5)] (20 mm) 5

d. CRO-408, Start Fourth Reactor Coolant Pump 0P111A111031006 End. 4.4 (Starting 1B2 RCP) D, A, P, L, S 4P

[KA: SYS 003 A4.03 (2.8/2.5)]_(16_mm) e.

f.

g.

h. CRO-801, Align Intake Canal for Recirc on Dam Failure D, L, S API1/A11700/13 (Dam Failure) 8

[KA: SYS 075 A2.01 (3.0*13.2)] (15 mm)

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

I. NLO-200, Align HPI Pump Suction to BWST During a Blackout D, E, R 2 EOP End. 5.7 (HPI Pump Operations from ASW Pump Switchgear)

[KA: APE 022 G2.4.35 (3.8/4.0)] (20 mm)

j. N/A

k. NLO-700, Restoration of ICS AUTO Power AP/23 End. 5.2, (Restoration of ICS AUTO Power) D, A, E 7

[KA: BW/A02 AA1 .1 (4.0/3.8)] (16 mm)

@ All RD and SRO-l 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 RD / SRO-l I SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irectfrombank 9/8/4 (E)mergency or abnormal in-plant 1 / 1 / 1 (EN)gineered safety feature - / - / 1 (control room system)

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

(R)CA (S)imulator