ML12342A036

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Initial Exam 2012-301 Draft Administrative Documents
ML12342A036
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 12/06/2012
From:
NRC/RGN-II
To:
Southern Co
References
Download: ML12342A036 (23)
v • d • e


Text

[ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 ft-.

Facility Hatch Date of Exam: 2012 RO KIA Category Points SRO.Only Points Tier Group KKKIKKKAAAAG A2 G* Total 1

=2

=

5 6 1

= =

2 3 4

  • Total
1. i 3 7 Emergency&

2 T T 2 1 1 7 1 2 3 Abnormal Plant NIA NIA Evolutions Tier Totals 6 4 27 6 10 1 32323232222 3 5 261_2

2. 1 1 111 2 111 121 12 0 1 2 3 Plant --

Systems Tier Totals 3 38 3 5 8

3. Generic Knowledge and Abilities 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 1(IA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each KIA category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final 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. Systemsievolutions 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 ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K1A 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 KIM 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 I and 2 from the shaded systems and KM categories.
7. The generic (G) KIM in Tiers I and 2 shall be selected from Section 2 of the KIA Catalog, butthe topics must be relevant to the applicable evolution or system.
8. On the following pages, enter the K1A numbers, a brief description of each topic, the topics importance 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 G on the SRO-only exam, enter iton the left side of Column A2 for Tier 2, Group 2 (Note
  1. 1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. UmItSRO selections to KIAs that are linked to 10 CFR 55.43.

ES-401, REV 9 TIGI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME/SAFETY FUNCTION: IR KI 1(2 1(3 1(4 1(5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295001AK2.05 Partial or Complete Loss of Forced 3.2 3.6 ElL1El [El LI Li LI LI LI El LPCI loop select logic: Plant-Specific Core Flow Circulation Il & 4 295003AK1 .03 Partial or Complete Loss of AC! 6 2.9 3.2 Under voltage/degraded voltage effects on electrical

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loads 295004G2.4.11 Partial or Total Loss of DC PwrI6 4.0 4.2 Knowledge of abnormal condition procedures.

[] [] [] [] [] [] [E El [] El [J 295005AK3.06 Main Turbine Generator Trip /3 3.3 3.3 Realignment of electrical distribution

[] El E] [] [] [] [] [] []

295008AA1.01 SCRAM/I 4.2 4.2 RPS 295016M2.07 Control Room Abandonment /7 3.2 3.4 Suppression chamber pressure El [] LI El El El El El [] El 29501 8AK3.06 Partial or Total Loss of CCW /8 3.3 3.3 Increasing cooling water flow to heat exchangers

[j j [J [3 [ [3 El [3 [3 [3 295019M2.02 Partial or Total Loss of Inst. Air 18 3.6 3.7 Status of safety-related instrument air system loads (see El [3 El LI El [3 [3 [3 [3 [3 295021G2.a4o Loss of Shutdown Cooling /4 3.4 4.7 LI El El LI El El LI LI El LI Ability to apply technical specifications for a system.

295023AA1 .04 Refueling Acc Cooling Mode I 8 3.4 3.7 3 [3 [3 [3 [3 [3 [3 Radiation monitoring equipment 295024EA2.O6 High Drywell Pressure / 5 4.1 4.1 ElElElElElElL1ElElEl Suppression pool temperature Page 1 of 2 12/1/2011 2:56 PM

ES-401, REV 9 TIGI BWR EXAMINATION OUTLINE FORM ES-401-1 KP. NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295025G2.1.27 High Reactor Pressure /3 3.9 4 LI [] [J [] LI [] [] [] Knowledge of system purpose and or function.

295026EK3.04 Suppression Pool High Water Temp. I 3.7 4.1 LI LI LI LI LI LI Li LI LI LI S8LC injection 295028EA1.03 High Drywell Temperature 15 *9 LI LI LI LI LI LI ] LI LI LI LI Drywell cooling system 295030EK1.02 Low Suppression Pool Wtr Lvi /5 3.5 3.8 LI LI LI LI LI LI LI LI LI LI Pump NPSH 295031 EAI .02 Reactor Low Water Level / 2 4.5 4.5 LI LI LI LI LI LI LI LI LI LI High pressure (feedwater) coolant injection: Plant-Specific 295037EK2.O1 SCRAM Condition Present and Power 4.2 4.3 RPS Above APRM Downscale or Unknown LI [] LI LI LI LI LI LI LI LI LI Il 295038EK1 .02 High Off-site Release Rate I9 4.2 4.4 J LI LI LI LI LI LI LI LI LI LI Protection of the general public 600000AKI.02 Plant Fire On Site 18 2,9 3.1 LI LI LI LI LI LI LI LI LI LI Fire Fighting 700000AK2.07 Generator Voltage and Electric Grid 3.6 3,7 LIILILILILILILILILILI TurbIne I Generator control Distrurbancecs Page 2 of 2 1211/2011 2:56 PM

ES-401, REV 9 TIG2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295009AA1 .03 Low Reactor Water Level / 2 3.0 3.1 flEEJE1 Recirculation system: Plant-Specific 295010G2.4.18 High Drywell Pressure 15 3.3 4.0 Knowledge of the specific bases for EOPs.

295013AK2.O1 High Suppression Pool Temp. / 5 3.6 3.7 LDL1L1L1L1E1 Suppression pool cooling 295020AK1 .05 Inadvertent Cont. Isolation 15 & 7 3.3 3.6 Loss of drywell!containment cooling 295032EA1 .05 High Secondary Containment Area 3.7 3.9 Affected systems so as to isolate damaged portions....

Temperature/S 295035E42.02 Secondary Containment High 2.8 4.1 Off-site release rate: Plant-Specific Differential Pressure I 5 500000EK3.07 High CTMT Hydrogen Conc. / 5 3.1 3.7 Operation of drywell vent Page 1 of I 12/1/2011 2:56 PM

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ES-401, REV 9 T2GI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 215005A4.03 APRM I LPRM 3.2 3.3 J Q Q 1J Q Q fl J  ?APRM back panel switches, meters and indicating lights 2170001<2.04 RCIC 2.6 2.6 [] ] [] El [] fl [] Gland seal compressor (vacuum pump) 2180001<1.04 ADS 3.9 4,2 j [ El [1 El [] ] [] [] [] Drywell/containment pressure: Plant-Specific 223002K3.1O PCIS/NuclearSteamSupplyShutoff 2.9 3.1 El [] [] [] [] [] [] [j Reactorwatercleanup 239002A3.02 SRVs 4.3 4.3 [] LI El El EJ El El El El [] SRV operation on high reactor pressure 259002A4.07 Reactor Water Level Control 3.8 3.6 EJ [1 [] [] El El All individual component controllers when transferring from automatic to manual mode 261000A1.O1 SGTS 2.9 3.1 [] Q Q [] [] [] [J System flow 2610001(3.02 SGTS 3.6 3.9 El [1 [] [] El El [] El [J Off-site release rate 262001 G2.4.47 AC Electrical Distribution 4.2 4.2 El [1 [] C] C] El El El [] C] Ability to diagnose and recognize trends In an accurate and timely manner utilizing the appropriate control room reference material.

262002A3.01 2.8 Transfer from preferred to afternate source UPS (AC/DC) 3.1 C] C] C] fl [] [] [] C] fJ C] []

263000A2.02 DC Electrical Distribution 2.6 2.9 El El El El El JJ El El [] Loss of ventilation during charging Page 2 of 3 12/112011 2:56 PM

ES-401, REV 9 T2GI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR 1(1 1(2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 2640001(4.08 EDGs 2.6 2.7 Governor control Q [3 [3 [3 [3 [3 [3 [3 [3 []

3000001(1.02 Instrument Air 2.7 2.8 [] [] [] [1 LI [3 [3 [] [] [3 Service air 3000001(6.04 Instrument Air 2.6 Service air refusal valve 2.5 [3 [1 [3 [3 [3 C] C] [] [3 [3 400000K2.02 Component Cooling Water 2.9 2.9 [3 ] LI [1 [3 [3 [3 [3 [3 [] [3 CCW valves Page3of3 121112011 2:56PM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 201001 K1.11 CRD Hydraulic 2.8 2.8 [] LI LI LI LI [] [] LI [] Reactor water cleanup pumps: Plant-Specific 202001A1.02 Recirculation 3.4 3.4 Jet pump flow J LI J J 2020021(3.03 Reclrculation Flow Control 3.3 3.4 LI LI LI LI LI LI LI [1 LI Reactor water level 204000K4.01 RWCU 2.5 2.5 LI LI LI ] LI LI LI LI [] LI LI Pump protection 2150021(6.04 RBM 2.8 3.0 reference channel: BWR-3,4,5 Li LI LI LI LI [] [] [] [] ] APRM 216000A4.01 Nuclear Boiler Inst. 3.3 3.1 LI LI LI LI LI LI LI LI LI LI Recorders 223001A3.04 Primary CTMT and Aux. 4.2 4.3 LI LI LI LI LI LI LI LI I1 LI LI Containmentldrywell response during LOCA 2330001(2.02 Fuel Pool CoolinglCleanup 2.8 2.9 LI IiI LI LI LI LI LI LI LI LI LI RHR pumps 2340001(5.02 Fuel Handling Equipment 3.1 3.7 LI LI LI LI LI LI LI LI Fuel handling equipment interlocks 241000A2.23 Reactor/Turbine Pressure Regulator 2.6 2.6 LI LI LI LI LI LI LI LI LI LI Turbine high eccentricity 268000A4.01 Radwaste 3.4 3.6 LI LI LI LI LI LI LI LI LI t LI Sump integrators Page 1 of 2 12/1/2011 2:56 PM

ES4OI, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 288000G2.4.9 Fire Protection 3.8 4.2 Knowledge of low power! shutdown implications

[] [] [J fl []

accident (e.g. LOCA or loss of RKR) mitigation strategies.

Page2of2 12/112011 2:56PM

ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Kl 1(2 1(3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1.2 Conduct of operatIons 3 El El El El El El El El El LI Knowledge of operator responsibilities during all modes of plant operation.

G2.1.21 Conduct of operations 3.5 3.6 fl [ El [] El [] El [] Ability verify the controlled procedure copy.

G2.1 .6 Conduct of operations 3.8 4.8 El El El El El El El El El El Ability to manage the control room crew during plant transients.

G2.2.23 Equipment Control 3.1 4.6 El El El El El El El El El El Ability to track Technical Specification limiting conditions for operations.

G22.37 Equipment Control 3.6 4.6 El El El El El El LI El El El Ability to determine operability and/or availability of safety related equipment G2.2.44 Equipment Control 4.2 4.4 El El El El El El El El El El Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions G2.3.13 Radiation Control 3.4 3.8 El El El El El El El El El El Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.14 Radiation Control 3.4 3.8 El El El El El El El El El El Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.4.26 Emergency Procedures/Plans 3.1 3.8 El El El El El El El El El El Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.

G2.4.32 Emergency Procedures/Plans 3.6 4.0 El El El El El El El El El LI liii Knowledge of operator response to loss of all annunciators.

Page 1 of I 12/112011 2:56 PM

ES-401, REV 9 SRO TIGI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 KG Al A2 A3 A4 G TOPIC:

RO SRO 295005G2.2.4 Main Turbine Generator Trip / 3 3.6 3.6 [] [] [] [j El i:j El El El [] I (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units atafacility.

295005AA2.05 SCRAM/i 4.6 4.6 [] [1 [1 El LI El Ii El [I El Whether a reactor SCRAM has occurred 295025G2.4.2 High Reactor Pressure /3 4.5 4.6 LI LI El El LI El LI LI El El Il Knowledge of system set points, interlocks and automatic - -

actions associated with EOP entry conditions.

295026EA2,O1 Suppression Pool High Water Temp. / 5 4.1 4.2 El El El El El El El F] El El El SuppressIon pool water temperature 295030EA2.03 Low Suppression Pool WtrL1 / 5 3.7 3.9 LI LI El El El El El [l El LI El Reactor pressure 295031G2.4.20 Reactor Low Water Level!2 3.8 4.3 [] El LI El El El El El El LI Knowledge of operational iplications of EOP warnings, cautions and notes.

600000G2.2.12 PlantFireOnSite/8 3.7 4.1 El El El LI El DLI El El El Knowledge of surveLance procedures.

Page 1 of 1 12/112011 2:56 PM

ES-401, REV 9 SRO TIG2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Ki 1(2 1(3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 29501 5G2.1.27 Incomplete SCRAM/I EEE1EJLLHThEJO Knowledge of system purpose and or function.

295022AA2.03 Loss of CRD Pumps / I 3.1 3.2 CRD mechanism temperatures 295033G2.4.49 High Secondary Containment Area 4.6 4.4 Ability to perform without reference to procedures those Radiation Levels / 9 actions that require immediate operation of system components and controls.

Page 1 of I 12/1/2011 2:56 PM

ES-401, REV 9 SRO T2GI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 203000G2.4.20 RHRILPCI: injection Mode 3.8 4.3 [] LI [1 LI LI LI LI LI El [] Knowledge of operational implications of EOP warnings, cautions and notes.

215004G2.4.47 Source Range Monitor 4.2 4.2 [] [] [] Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

215005A2.07 APRM I LPRM 3.2 3.4 fl fl LI [] [J L] [] [] [] Recirculation flow channels flow mismatch 261000G2.2.37 SGTS 3.6 4.6 LI El [] LI [] El El [] [] Ability to determine operability and/or availability of safety related equipment 400000A2.O1 Component Cooling Water 3.3 3.4 1J El El El El El Loss of CCW pump Page 1 ofl 12/112011 2:56PM

ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION: IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 230000G2.4.45 RHRILPCI: Torus/Pool Spray Mode 4.1 4.3 Ability to prioritize and interpret the significance of each annunciator or alarm.

259001A2.02 Reactor Feedwater 3.1 EDDHZLD Feedwater heater isolation 290002G2.2.12 Reactor Vessel Internals 3.7 4.1 Knowledge of surveillance procedures.

Page 1 of I 1211/2011 2:56 PM

ES-401, REV 9 SRO T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION: IR 1(1 K2 1(3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 02.1.25 Conduct of operations 3.9 4.2 Ability to interpret reference materials such as graphs,

[] [] [] [] [] [] []

monographs and tables which contain performance data.

02.2.42 Equipment Control 3.9 4.6 LI Li LI LI Li LI LI LI LI Ability to recognize system parameters that are entry-level conditions for Technical Specifications G2.2.43 Equipment Control 3.0 3.3 Knowledge of the process used to track inoperable alarms LI LI LI C] LI LI LI C] C]

02.3.11 Radiation Control 3.8 4.3 LI C] [] [] [] [] C] C] { Ability to control radiation releases 02.3.13 Radiation Control 3.4 3.8 LI C] C] C] C] LI C] Knowledge of radiological safety procedures pertaining to licensed operator duties G2.4.23 EmergencyProcedures/Plans 3.4 Knowledgeofthebasesforprioritizingemergency LI LI LI LI Li LI LI LI LI LI [J procedure implementation during emergency operations.

G2.4.29 Emergency Procedures/Plans 3.1 4.4 C] LI C] LI C] [] C] C] C] C] j Knowledge of the emergency plan.

Page 1 of 1 12/112011 2:56 PM

ES-301 Administrative Topics Outline RO DRAFT

- Form ES-301-1 Facility: PLANT E. I. HATCH HLT 7 Date of Examination: 06/18/2012 Exam Level: RO l1 SRO-l D SRO-U D Operating Test No.: 2012-301 Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations M, R Ui Correct Reactor Water Level for high drywell Admin 2 temperatures. G2.1.35 (3.9 4.2) ALL Conduct of Operations M, R Determine if plant conditions allow a Quick Admin 3 Restart of a Recirculation Pump (15 mm).

G2.1.20 (4.3 4.2) RO ONLY Equipment Control N, R Review HPCI Pump Operability Surveillance (25 Admin 4 mm) G2.2.12 ALL Radiation Control D, R Given a set of exposure conditions, determine the Admin 5 minimum level of authorization required to allow a worker to perform work which will exceed administrative exposure limits. G2.3.4 (2.5 3.1)

ALL 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 SRO5 & RO retakes)

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

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

ES-301 Administrative Topics Outline SRO-l DRAFT Form ES-301-1 Facility: PLANT E. I. HATCH HLT 7 Date of Examination: 06/18/2012 Exam Level: RO D SRO-l SRO-U 0 Operating Test No.: 2012-301 Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations Verify Fuel Movements D R Admin 1 G2.1.35 (3.9) SRO ONLY Conduct of Operations M, R Ui Correct Reactor Water Level for high drywell Admin 2 temperatures. G2.1.35 (3.9 4.2) ALL Equipment Control N, R Review HPCI Pump Operability Surveillance (25 Admin 4 mm) G2.2.12 ALL Radiation Control D, R Given a set of exposure conditions, determine the Admin 5 minimum level of authorization required to allow a worker to perform work which will exceed administrative exposure limits. G2.3.4 (2.5 3.1)

ALL Emergency Procedures/Plan D, 5, R Given Plant Conditions, Determine the Emergency, Admin 6 Classification and complete the ENN Form.

G2.4.29 (4.0) SRO ONLY 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 SRO-l DRAFT Form ES-301-1 Facility: PLANT E. I. HATCH HLT 7 Date of Examination: 06/18/2012 Exam Level: RD D SRO-l li SRO-U El Operating Test No.: 2012-301 Administrative Topic (see Type Describe activity to be performed Note) Code*

Conduct of Operations Verify Fuel Movements D R Admin 1 G2.1.35 (3.9) SRO ONLY Conduct of Operations M, R UI Correct Reactor Water Level for high drywell Admin 2 temperatures. G2.1.35 (3.9 4.2) ALL Equipment Control N, R Review HPCI Pump Operability Surveillance (25 Admin 4 mm) G2.2.12 ALL Radiation Control D, R Given a set of exposure conditions, determine the Admin 5 minimum level of authorization required to allow a worker to perform work which will exceed administrative exposure limits. G2.3.4 (2.5 3.1)

ALL Emergency Procedures/Plan D, 5, R Given Plant Conditions, Determine the Emergency, Admin 6 Classification and complete the ENN Form.

G2.4.29 (4.0) SRO ONLY 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 SRO5 & P0 retakes)

(N)ew or (M)odif led from bank ( 1)

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

ES-301 Administrative Topics Outline RO DRAFT

- Form ES-301-1 Facility: PLANT E. I. HATCH HLT 7 Date of Examination: 06/18/2012 Exam Level: RO l1 SRO-l U SRO-U U Operating Test No.: 2012-301 Administrative Topic (see Type Describe activity to be performed Note> Code*

Conduct of Operations M, R Ui Correct Reactor Water Level for high drywell Admin 2 temperatures. G2.1.35 (3.9 4.2) ALL Conduct of Operations M, R Determine if plant conditions allow a Quick Admin 3 Restart of a Recirculation Pump (15 mm).

G2.1.20 (4.3 4.2) RO ONLY Equipment Control N, R Review HPCI Pump Operability Surveillance (25 Admin 4 mm) G2.2.12 ALL Radiation Control D, R Given a set of exposure conditions, determine the Admin 5 minimum level of authorization required to allow a worker to perform work which will exceed administrative exposure limits. G2.3.4 (2.5 3.1)

ALL 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 Control Room/In-Plant Systems Outline ALL DRAFT Form ES-301-2 Facility: PLANT E. I. HATCH HLT 7 Date of Examination: 06/18/2012 Exam Level: RO RI SRO-l RI SRO-U D Operating Test No.: 2012-301 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 SF-i CR/SIM 1 Withdraw control rods and one Rod A, D, S Reactivity becomes uncoupled.

201003A2.02 (3.7/3.8)

ALL SF-2 CRJSIM 2 Place 2 RFPT in service with RFPT D, S Reactor Water Level Control already at 2100 rpm.

259001A4.02 (3.8/3.7)

ALL SF-3 CRISIM 3 Override and Open MSIVs in an D, S Reactor Pressure Control Emergency. 23900iA4.0i (4.2/4.0)

ALL SF-4 CR/SIM 4 Place HPCI in Pressure Control A, M, S Heat Removal From The Core Mode, after BPVs close.

206000A4.06 (4.3/4.3)

ALL SF-5 CRJSIM 5 RHRILPCI: Containment Spray A, D, S Containment Integrity System Mode! Initiate Drywell spray with a valve 22600 iA2. ii (3.0/3.0) failure.

ALL SF-6 CRJSIM 6 4160 VAC / Transfer an Emergency D, Electrical 4160 VAC F from Normal to Alternate Power 262001A4.0i (3.6/3.7)

Supply.

RO ONLY SF-8 CRISIM 7 Crosstie RHRSW. D, L, S Plant Service System 2i9000A2.15 (RO 3.3!SRO 3.4)

ALL SF-9 CRJSIM 8 Using the Override Switches, Vent A, M, S Radiation Release the Torus with the CAD System.

295038EK1.02 (4.2/4.4)

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

SF-i PLANT 1 SBLC / From Outside the Control A, D, E, L, R Reactivity Room, inject Boron using the SBLC System with 21i000A2.0l (3.5/3.8) failure of first pump to start.

ALL SF-6 PLANT 2 Emergency Generators / Locally close A, N, E Electrical output breaker by flashing field and lowering Hz 26400A3.04 (3.1/3.1) then raising to 60Hz.

ALL SF-8 PLANT 3 During a loss of air, isolate the Fire D, E, R Plant Service System Protection Sprinklers on Unit 2.

286000A2. 10 (2.6/2.7)

ALL

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

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

(R)CA l/1I1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline ALL DRAFT Form ES-301-2 Facility: PLANT E. I. HATCH HLT 7 Date of Examination: 06/18/2012 Exam Level: RO L?1 SRO-l 1 SRO-U D Operating Test No.: 201 2-301 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 SF-i CRJSIM 1 Withdraw control rods and one Rod A, D, S Reactivity becomes uncoupled. 201003A2.02 (3.7/3.8)

ALL SF-2 CR/SIM 2 Place 2 RFPT in service with RFPT D, S Reactor Water Level Control already at 2100 rpm. 259001A4.02 (3.8/3.7)

ALL SF-3 CR!SIM 3 Override and Open MSIVs in an D, S Reactor Pressure Control Emergency. 239001A4.Oi (4.2/4.0)

ALL SF-4 CRJSIM 4 Place HPCI in Pressure Control A, M, S Heat Removal From The Core Mode, after BPVs close. 206000A4.06 (4.3/4.3)

ALL SF-5 CRISIM 5 RHRJLPCI: Containment Spray A, D, S Containment Integrity System Mode / Initiate Drywell spray with a valve 22600 1A2.1 1 (3.0/3.0) failure. ALL SF-6 CR/SIM 6 4160 VAC I Transfer an Emergency D, Electrical 4160 VAC F from Normal to Altemate Power 262001A4.0l (3.6/3.7)

Supply. RO ONLY SF-8 CR/SIM 7 Crosstie RHRSW. D, L, S Plant Service System 219000A2.15 (RO 3.3/SRO 3.4)

ALL SF-9 CR/SIM 8 Using the Override Switches, Vent A, M, Radiation Release the Torus with the CAD System. 295038EK1.02 (4.2/4.4)

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

SFi PLANT 1 SBLC / From Outside the Control A, D, E, L, R Reactivity Room, Inject Boron using the SBLC System with 211000A2.0i (3.5/3.8) failure of first pump to start. ALL SF-6 PLANT 2 Emergency Generators / Locally close A, N, E Electrical output breaker by flashing field and lowering Hz 26400A3.04 (3.1/3.1) then raising to 60Hz. ALL SF-8 PLANT 3 During a loss of air, isolate the Fire D, E, R Plant Service System Protection Sprinklers on Unit 2. 286000A2. 10 (2.6/2.7)

ALL

@ 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 / 2-3 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant 1 / I / 1 (EN)gineered safety feature - / - / 1 (control room system)

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

(R)CA 1 / I / I (S)imulator

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