ML19115A255

301 ADAMS2C Exam Administrative Items

ML19115A255
Person / Time
Site:	Oconee
Issue date:	04/25/2019
From:	Division of Reactor Safety II
To:	Duke Energy Carolinas
References
Download: ML19115A255 (71)

Text

ES-301 Administrative Topics Outline Form ES-301-1 ILT16-1 Facility: Oconee Date of Examination: 06/13/2016 Examination Level: RO X SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations Admin-108, Determine Time for SFP to Reach

[KA:G2.1.25 (3.9/4.2)] M, R 200ºF (Both)

(15 min)

Conduct of Operations Admin-109, Unit 3 SFP Boron and Volume

[KA: G2.1.23 (4.3/4.4)] D, R Change Calculation (RO Only)

(15 min)

Equipment Control Admin-204, Perform SG Downcomer

[KA: G2.2.12 (3.7/4.1)] D, R Temperature Surveillance (RO Only)

(18 min)

Radiological Control Admin-304, Determine the Maximum

[KA: G2.3.4 (3.2/3.7)] M, R Permissible Stay Time Within Emergency Dose (20 min) Limits (EDLs) (Both)

Emergency Plan N/A 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 ( 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 ILT16-1 Facility: Oconee Date of Examination: 06/13/2016 Examination Level: RO SRO X Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations Admin-108, Determine Time for SFP to Reach

[KA:G2.1.25 (3.9/4.2)] M, R 200ºF (Both)

(15 min)

Conduct of Operations Admin-S107, Calculation of Primary to D, R

[KA: G2.1.7 (4.4/4.7 ] Secondary Leak Rate and Unit Shutdown (16 min) Requirements (SRO Only)

Equipment Control Admin-S203, Complete Plant Configuration

[KA G2.2.18 (2.6/3.9)] D, R Sheet (Time to Core Boil) and Determine Any (25 min) Required Actions (SRO Only)

Radiological Control Admin-304, Determine the Maximum

[KA: G2.3.4 (3.2/3.7)] M, R Permissible Stay Time Within Emergency Dose (20 min) Limits (EDLs) (Both)

Emergency Plan Admin-S404, Determine Emergency

[KA G2.4.38 (2.4/4.4)] Classification and Protective Action D, R (20 min) Recommendations (Complete Emergency Notification Form) (SRO Only)

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 ( 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 Form ES-301-2 ILT 16-1 Facility: Oconee Date of Examination: 06/13/16 Exam Level: RO X SRO-I SRO-U Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. RO-103a Withdrawal of Safety Rods Group 1 to 50%

A, D, L, S 1 OP/1/A/1105/019 Encl 4.3 (Withdrawal of Safety Rod Group 1 to 50%)

[KA: 001 G2.2.2 (4.6/4.1)] (15 min)

b. RO-305a Perform Required Actions for a Failed LPI A, D, E, EN, 3 Train L, S EOP Encl 5.1 (ES Actuation)

[KA: EPE 011 EA1.04 (4.4/4.4)] (15 min)

c. RO-S403a Align PSW to HPI Pump Motor Coolers A, E, N, S 4S AP/2/A/1700/024 Encl 5.4 (PSW to HPI Pump Motor Coolers)

[KA: 076 A2.01 (3.5*/3.7*)] (10 min)

d. RO-203 Pressure Makeup to CFT D, S 2 OP/1/A/1104/001 Encl 4.7 (Pressure Makeup to CFTs Using Nitrogen)

[KA: 006 A1.13 (3.5/3.7)] (10 min)

e. RO-P404 Align ECCS Suction to Emergency Sump EOP Encl 5.12 (ECCS Suction Swap to RBES) E, EN, L, M, 4P S

[KA: BW/E08 EA1.1 (4.0/3.7)] (15 min)

f. RO-504a Perform EOP Encl 5.35 A, D, E, L, S 5 EOP Encl 5.35 (Containment Isolation)

[KA: 103 G2.1.23 (4.3/4.4)] (10 min)

g. RO-603a Energize MFBs From CT-5 A, D, L, S 6 EOP Encl 5.38 (Restoration of Power)

[KA: EPE 055 EA1.07 (4.3/4.5)] (15 min)

h. RO-804 Place RB Purge in Operation D, L, S 8 OP/1/A/1102/014 Encl 4.1 (RB Purge Release)

[KA: 029 A2.03 (2.7/3.1)] (15 min)

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

i. AO-501 Place Reactor Building Hydrogen Analyzers in D, E, R 5 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

[KA: 028 G2.1.30 (4.4/4.0)] (15 min)

j. AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire N, E 8 Hose Station)

[KA: 075 G2.1.30 (4.4/4.0)] (20 min)

k. AO-S402 Reset an Emergency FDW Pump Turbine D 4S OP/1/A/1106/006 Encl 4.2 (Resetting TD EFDWP)

[KA: 061 A2.04 (3.4/3.8)] (10 min)

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

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature 1/ 1/ 1 (control room system)

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ILT 16-1 Facility: Oconee Date of Examination: 06/13/16 Exam Level: RO SRO-I X SRO-U Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. RO-103a Withdrawal of Safety Rods Group 1 to 50%

A, D, L, S 1 OP/1/A/1105/019 Encl 4.3 (Withdrawal of Safety Rod Group 1 to 50%)

[KA: 001 G2.2.2 (4.6/4.1)] (15 min)

b. RO-305a Perform Required Actions for a Failed LPI A, D, E, EN, 3 Train L, S EOP Encl 5.1 (ES Actuation)

[KA: EPE 011 EA1.04 (4.4/4.4)] (15 min)

c. RO-S403a Align PSW to HPI Pump Motor Coolers A, E, N, S 4S AP/2/A/1700/024 Encl 5.4 (PSW to HPI Pump Motor Coolers)

[KA: 076 A2.01 (3.5*/3.7*)] (10 min)

d. RO-203 Pressure Makeup to CFT D, S 2 OP/1/A/1104/001 Encl 4.7 (Pressure Makeup to CFTs Using Nitrogen)

[KA: 006 A1.13 (3.5/3.7)] (10 min)

e. RO-P404 Align ECCS Suction to Emergency Sump EOP Encl 5.12 (ECCS Suction Swap to RBES) E, EN, L, M, 4P S

[KA: BW/E08 EA1.1 (4.0/3.7)] (15 min)

f. RO-504a Perform EOP Encl 5.35 A, D, E, L, S 5 EOP Encl 5.35 (Containment Isolation)

[KA: 103 G2.1.23 (4.3/4.4)] (10 min)

g. RO-603a Energize MFBs From CT-5 A, D, L, S 6 EOP Encl 5.38 (Restoration of Power)

[KA: EPE 055 EA1.07 (4.3/4.5)] (15 min)

h. N/A

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

i. AO-501 Place Reactor Building Hydrogen Analyzers in D, E, R 5 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

[KA: 028 G2.1.30 (4.4/4.0)] (15 min)

j. AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire N, E 8 Hose Station)

[KA: 075 G2.1.30 (4.4/4.0)] (20 min)

k. AO-S402 Reset an Emergency FDW Pump Turbine D 4S OP/1/A/1106/006 Encl 4.2 (Resetting TD EFDWP)

[KA: 061 A2.04 (3.4/3.8)] (10 min)

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

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature 1/ 1/ 1 (control room system)

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ILT 16-1 Facility: Oconee Date of Examination: 06/13/16 Exam Level: RO SRO-I SRO-U X Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. RO-103a Withdrawal of Safety Rods Group 1 to 50%

A, D, L, S 1 OP/1/A/1105/019 Encl 4.3 (Withdrawal of Safety Rod Group 1 to 50%)

[KA: 001 G2.2.2 (4.6/4.1)] (15 min)

b. RO-305a Perform Required Actions for a Failed LPI A, D, E, EN, 3 Train L, S EOP Encl 5.1 (ES Actuation)

[KA: EPE 011 EA1.04 (4.4/4.4)] (15 min)

c. RO-S403a Align PSW to HPI Pump Motor Coolers A, E, N, S 4S AP/2/A/1700/024 Encl 5.4 (PSW to HPI Pump Motor Coolers)

[KA: 076 A2.01 (3.5*/3.7*)] (10 min)

d. N/A

e. N/A

f. N/A

g. N/A

h. N/A

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

i. AO-501 Place Reactor Building Hydrogen Analyzers in D, E, R 5 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

[KA: 028 G2.1.30 (4.4/4.0)] (15 min)

j. AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire N, E 8 Hose Station)

[KA: 075 G2.1.30 (4.4/4.0)] (20 min)

k. N/A

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

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature 1/ 1 / 1 (control room system)

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

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

ES-401, Rev. 10 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

1. 1 3 3 3 3 3 3 18 18 3 3 66 Emergency &

2 2 1 2 2 1 1 99 2 2 44 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 5 5 4 4 27 27 5 5 1010 1 3 2 3 3 2 2 3 2 3 2 3 28 28 2 3 55 2.

2 1 1 1 1 1 1 1 1 1 1 0 10 10 1 2 33 Plant Systems Tier Totals 4 3 4 4 3 3 4 3 4 3 3 38 38 5 88

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 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, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).

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 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 (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 K/A categories.

7. *The generic (G) K/As in Tiers 1 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 D.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 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 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 55.43..

ES-401, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 007EK3.01 Reactor Trip - Stabilization - Recovery 4 4.6 Actions contained in EOP for reactor trip

/1 008AK2.02 Pressurizer Vapor Space Accident / 3 2.7 2.7 Sensors and detectors 009EK1.01 Small Break LOCA / 3 4.2 4.7 Natural circulation and cooling, including reflux boiling 011EK2.02 Large Break LOCA / 3 2.6 2.7 Pumps 022AK1.03 Loss of Rx Coolant Makeup / 2 3 3.4 Relationship between charging flow and PZR level 025AK1.01 Loss of RHR System / 4 3.9 4.3 Loss of RHRS during all modes of operation 026AK3.03 Loss of Component Cooling Water / 8 4 4.2 Guidance actions contained in EOP for Loss of CCW 029EK2.06 ATWS / 1 2.9 3.1 Breakers, relays, and disconnects.

038EA1.36 Steam Gen. Tube Rupture / 3 4.3 4.5 Cooldown of RCS to specified temperature 054AA2.08 Loss of Main Feedwater / 4 2.9 3.3 Steam flow-feed trend recorder 056AG2.4.35 Loss of Off-site Power / 6 3.8 4.0 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Page 1 of 2 12/13/2015 10:11 PM

ES-401, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 057AA1.05 Loss of Vital AC Inst. Bus / 6 3.2 3.4 Backup instrument indications 058AG2.1.20 Loss of DC Power / 6 4.6 4.6 Ability to execute procedure steps.

062AA2.04 Loss of Nuclear Svc Water / 4 2.5 2.9 The normal values and upper limits for the temperatures of the components cooled by SWS 065AA2.05 Loss of Instrument Air / 8 3.4 4.1 When to commence plant shutdown if instrument air pressure is decreasing 077AA1.05 Generator Voltage and Electric Grid 3.9 4.0 Engineered Safety Features Disturbances / 6 BE04EK3.2 Inadequate Heat Transfer - Loss of 3.5 4 Normal, abnormal and emergency operating procedures Secondary Heat Sink / 4 associated with (Inadequate Heat Transfer).

BE05EG2.4.5 Steam Line Rupture - Excessive Heat 4.2 4.0 Ability to verify system alarm setpoints and operate Transfer / 4 controls identified in the alarm response manual.

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ES-401, REV 10 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 037AK1.02 Steam Generator Tube Leak / 3 3.5 3.9 Leak rate vs. pressure drop 059AA1.03 Accidental Liquid RadWaste Rel. / 9 3 2.9 Flow rate controller 060AK3.03 Accidental Gaseous Radwaste Rel. / 9 3.8 4.2 Actions contained in EOP for accidental gaseous-waste release 074EA2.04 Inad. Core Cooling / 4 3.7 4.2 Relationship between RCS temperature and main steam pressure BA01AK2.1 Plant Runback / 1 3.7 3.5 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

BA04AK3.2 Turbine Trip / 4 3.4 3.6 Normal, abnormal and emergency operating procedures associated with (Turbine Trip).

BA06AG2.4.6 Shutdown Outside Control Room / 8 3.7 4.7 Knowledge symptom based EOP mitigation strategies.

BE08EA1.3 LOCA Cooldown - Depress. / 4 3.3 3.8 Desired operating results during abnormal and emergency situations.

BE13EK1.2 EOP Rules 3 3.6 Normal, abnormal and emergency operating procedures associated with (EOP Rules).

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ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 003G2.4.20 Reactor Coolant Pump 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.

004K6.10 Chemical and Volume Control 2.7 3.1 Boric acid storage tank/boron injection tank recirculation flow path 005K2.01 Residual Heat Removal 3.0 3.2 RHR pumps 005K4.06 Residual Heat Removal 2.7 3.0 Function of RHR pump miniflow recirculation 006K5.08 Emergency Core Cooling 2.9 3.1 Operation of pumps in parallel 007A1.02 Pressurizer Relief/Quench Tank 2.7 2.9 Maintaining quench tank pressure 007K3.01 Pressurizer Relief/Quench Tank 3.3 3.6 Containment 008A2.03 Component Cooling Water 3.0 3.2 High/low CCW temperature 010K3.01 Pressurizer Pressure Control 3.8 3.9 RCS 012K6.10 Reactor Protection 3.3 3.5 Permissive circuits 013A4.03 Engineered Safety Features Actuation 4.5 4.7 ESFAS initiation Page 1 of 3 12/13/2015 10:11 PM

ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 022G2.4.18 Containment Cooling 3.3 4.0 Knowledge of the specific bases for EOPs.

022K2.02 Containment Cooling 2.5 2.4 Chillers 026K4.05 Containment Spray 2.8 3.3 Prevention of material from clogging nozzles during recirculation 039A2.01 Main and Reheat Steam 3.1 3.2 Flow paths of steam during a LOCA 039A3.02 Main and Reheat Steam 3.1 3.5 Isolation of the MRSS 059A3.07 Main Feedwater 3.4 3.5 ICS 059K1.03 Main Feedwater 3.1 3.3 S/GS 061G2.1.25 Auxiliary/Emergency Feedwater 3.9 4.2 Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

062K1.04 AC Electrical Distribution 3.7 4.2 Off-site power sources 062K4.02 AC Electrical Distribution 2.5 2.7 Circuit breaker automatic trips 063K1.03 DC Electrical Distribution 2.9 3.5 Battery charger and battery Page 2 of 3 12/13/2015 10:11 PM

ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 063K3.02 DC Electrical Distribution 3.5 3.7 Components using DC control power 073A1.01 Process Radiation Monitoring 3.2 3.5 Radiation levels 073K5.01 Process Radiation Monitoring 2.5 3.0 Radiation theory, including sources, types, units and effects 076A1.02 Service Water 2.6 2.6 Reactor and turbine building closed cooling water temperatures.

078A4.01 Instrument Air 3.1 3.1 Pressure gauges 103A3.01 Containment 3.9 4.2 Containment isolation Page 3 of 3 12/13/2015 10:11 PM

ES-401, REV 10 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 002K6.03 Reactor Coolant 3.1 3.6 Reactor vessel level indication 016K5.01 Non-nuclear Instrumentation 2.7 2.8 Separation of control and protection circuits 028K2.01 Hydrogen Recombiner and Purge 2.5 2.8 Hydrogen recombiners Control 035A3.01 Steam Generator 4.0 3.9 S/ G water level control 045K3.01 Main Turbine Generator 2.9 3.2 Remainder of the plant 055K1.06 Condenser Air Removal 2.6 2.6 PRM system 056A2.04 Condensate 2.6 2.8 Loss of condensate pumps 071K4.03 Waste Gas Disposal 2.5 2.6 Tank loop seals 079A4.01 Station Air 2.7 2.7 Cross-tie valves with IAS 086A1.03 Fire Protection 2.7 3.2 Fire doors Page 1 of 1 12/13/2015 10:11 PM

ES-401, REV 10 T3 PWR EXAMINATION OUTLINE FORM ES-401-3 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G2.1.17 Conduct of operations 3.9 4.0 Ability to make accurate, clear and concise verbal reports.

G2.1.39 Conduct of operations 3.6 4.3 Knowledge of conservative decision making practices G2.1.44 Conduct of operations 3.9 3.8 Knowledge of RO duties in the control room during fuel handling.

G2.2.38 Equipment Control 3.6 4.5 Knowledge of conditions and limitations in the facility license.

G2.2.4 Equipment Control 3.6 3.6 (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

G2.2.40 Equipment Control 3.4 4.7 Ability to apply technical specifications for a system.

G2.3.11 Radiation Control 3.8 4.3 Ability to control radiation releases.

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

G2.4.50 Emergency Procedures/Plans 4.2 4.0 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

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ES-401, REV 10 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 008AA2.28 Pressurizer Vapor Space Accident / 3 3.3 3.9 Safety parameter display system indications 015AA2.07 RCP Malfunctions / 4 2.1 2.9 Calculation of expected values of flow in the loop with RCP secured 025AG2.4.46 Loss of RHR System / 4 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.

054AG2.1.31 Loss of Main Feedwater / 4 4.6 4.3 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

058AG2.2.22 Loss of DC Power / 6 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.

BE04EA2.2 Inadequate Heat Transfer - Loss of 3.6 4.4 Adherence to appropriate procedures and operation within Secondary Heat Sink / 4 the limitations in the facility s license and amendments.

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ES-401, REV 10 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 028AG2.4.20 Pressurizer Level Malfunction / 2 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.

037AA2.03 Steam Generator Tube Leak / 3 3.4 3.9 That the expected indication on main steam lines from the S/Gs should show increasing radiation levels BE03EG2.4.30 Inadequate Subcooling Margin / 4 2.7 4.1 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

BE13EA2.2 EOP Rules 3.8 4 Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.

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ES-401, REV 10 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 006G2.4.21 Emergency Core Cooling 4.0 4.6 Knowledge of the parameters and logic used to assess the status of safety functions 007A2.07 Pressurizer Relief/Quench Tank 2.3 2.6 Recirculating quench tank 013G2.2.37 Engineered Safety Features Actuation 3.6 4.6 Ability to determine operability and/or availability of safety related equipment 061A2.02 Auxiliary/Emergency Feedwater 3.4 3.5 Air or MOV failure 063G2.4.41 DC Electrical Distribution 2.9 4.6 Knowledge of the emergency action level thresholds and classifications.

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ES-401, REV 10 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 001G2.2.40 Control Rod Drive 3.4 4.7 Ability to apply technical specifications for a system.

016A2.02 Non-nuclear Instrumentation 2.9 3.2 Loss of power supply 017G2.4.9 In-core Temperature Monitor 3.8 4.2 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

Page 1 of 1 12/13/2015 10:13 PM

ES-401, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-3 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G2.1.2 Conduct of operations 4.1 4.4 Knowledge of operator responsibilities during all modes of plant operation.

G2.2.11 Equipment Control 2.3 3.3 Knowledge of the process for controlling temporary design changes.

G2.2.3 Equipment Control 3.8 3.9 (multi-unit license) Knowledge of the design, procedural and operational differences between units.

G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.16 Emergency Procedures/Plans 3.5 4.4 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.

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

Page 1 of 1 12/13/2015 10:13 PM

ES-301 Administrative Topics Outline Form ES-301-1 ILT16-1 Facility: Oconee Date of Examination: 06/13/2016 Examination Level: RO X SRO Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations Admin-108, Determine Time for SFP to Reach

[KA:G2.1.25 (3.9/4.2)] M, R 200ºF (Both)

(15 min)

Conduct of Operations Admin-109, Unit 3 SFP Boron and Volume

[KA: G2.1.23 (4.3/4.4)] D, R Change Calculation (RO Only)

(15 min)

Equipment Control Admin-204, Perform SG Downcomer

[KA: G2.2.12 (3.7/4.1)] D, R Temperature Surveillance (RO Only)

(18 min)

Radiological Control Admin-304, Determine the Maximum

[KA: G2.3.4 (3.2/3.7)] M, R Permissible Stay Time Within Emergency Dose (20 min) Limits (EDLs) (Both)

Emergency Plan N/A 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 ( 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 ILT16-1 Facility: Oconee Date of Examination: 06/13/2016 Examination Level: RO SRO X Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Conduct of Operations Admin-108, Determine Time for SFP to Reach

[KA:G2.1.25 (3.9/4.2)] M, R 200ºF (Both)

(15 min)

Conduct of Operations Admin-S107, Calculation of Primary to D, R

[KA: G2.1.7 (4.4/4.7 ] Secondary Leak Rate and Unit Shutdown (16 min) Requirements (SRO Only)

Equipment Control Admin-S203, Complete Plant Configuration

[KA G2.2.18 (2.6/3.9)] D, R Sheet (Time to Core Boil) and Determine Any (25 min) Required Actions (SRO Only)

Radiological Control Admin-304, Determine the Maximum

[KA: G2.3.4 (3.2/3.7)] M, R Permissible Stay Time Within Emergency Dose (20 min) Limits (EDLs) (Both)

Emergency Plan Admin-S404, Determine Emergency

[KA G2.4.38 (2.4/4.4)] Classification and Protective Action D, R (20 min) Recommendations (Complete Emergency Notification Form) (SRO Only)

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 ( 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 Form ES-301-2 ILT 16-1 Facility: Oconee Date of Examination: 06/13/16 Exam Level: RO X SRO-I SRO-U Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. RO-103a Withdrawal of Safety Rods Group 1 to 50%

A, D, L, S 1 OP/1/A/1105/019 Encl 4.3 (Withdrawal of Safety Rod Group 1 to 50%)

[KA: 001 G2.2.2 (4.6/4.1)] (15 min)

b. RO-305a Perform Required Actions for a Failed LPI A, D, E, EN, 3 Train L, S EOP Encl 5.1 (ES Actuation)

[KA: EPE 011 EA1.04 (4.4/4.4)] (15 min)

c. RO-S403a Align PSW to HPI Pump Motor Coolers A, E, N, S 4S AP/2/A/1700/024 Encl 5.4 (PSW to HPI Pump Motor Coolers)

[KA: 076 A2.01 (3.5*/3.7*)] (10 min)

d. RO-203 Pressure Makeup to CFT D, S 2 OP/1/A/1104/001 Encl 4.7 (Pressure Makeup to CFTs Using Nitrogen)

[KA: 006 A1.13 (3.5/3.7)] (10 min)

e. RO-P404 Align ECCS Suction to Emergency Sump EOP Encl 5.12 (ECCS Suction Swap to RBES) E, EN, L, M, 4P S

[KA: BW/E08 EA1.1 (4.0/3.7)] (15 min)

f. RO-504a Perform EOP Encl 5.35 A, D, E, L, S 5 EOP Encl 5.35 (Containment Isolation)

[KA: 103 G2.1.23 (4.3/4.4)] (10 min)

g. RO-603a Energize MFBs From CT-5 A, D, L, S 6 EOP Encl 5.38 (Restoration of Power)

[KA: EPE 055 EA1.07 (4.3/4.5)] (15 min)

h. RO-804 Place RB Purge in Operation D, L, S 8 OP/1/A/1102/014 Encl 4.1 (RB Purge Release)

[KA: 029 A2.03 (2.7/3.1)] (15 min)

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

i. AO-501 Place Reactor Building Hydrogen Analyzers in D, E, R 5 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

[KA: 028 G2.1.30 (4.4/4.0)] (15 min)

j. AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire N, E 8 Hose Station)

[KA: 075 G2.1.30 (4.4/4.0)] (20 min)

k. AO-S402 Reset an Emergency FDW Pump Turbine D 4S OP/1/A/1106/006 Encl 4.2 (Resetting TD EFDWP)

[KA: 061 A2.04 (3.4/3.8)] (10 min)

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

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature 1/ 1/ 1 (control room system)

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ILT 16-1 Facility: Oconee Date of Examination: 06/13/16 Exam Level: RO SRO-I X SRO-U Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. RO-103a Withdrawal of Safety Rods Group 1 to 50%

A, D, L, S 1 OP/1/A/1105/019 Encl 4.3 (Withdrawal of Safety Rod Group 1 to 50%)

[KA: 001 G2.2.2 (4.6/4.1)] (15 min)

b. RO-305a Perform Required Actions for a Failed LPI A, D, E, EN, 3 Train L, S EOP Encl 5.1 (ES Actuation)

[KA: EPE 011 EA1.04 (4.4/4.4)] (15 min)

c. RO-S403a Align PSW to HPI Pump Motor Coolers A, E, N, S 4S AP/2/A/1700/024 Encl 5.4 (PSW to HPI Pump Motor Coolers)

[KA: 076 A2.01 (3.5*/3.7*)] (10 min)

d. RO-203 Pressure Makeup to CFT D, S 2 OP/1/A/1104/001 Encl 4.7 (Pressure Makeup to CFTs Using Nitrogen)

[KA: 006 A1.13 (3.5/3.7)] (10 min)

e. RO-P404 Align ECCS Suction to Emergency Sump EOP Encl 5.12 (ECCS Suction Swap to RBES) E, EN, L, M, 4P S

[KA: BW/E08 EA1.1 (4.0/3.7)] (15 min)

f. RO-504a Perform EOP Encl 5.35 A, D, E, L, S 5 EOP Encl 5.35 (Containment Isolation)

[KA: 103 G2.1.23 (4.3/4.4)] (10 min)

g. RO-603a Energize MFBs From CT-5 A, D, L, S 6 EOP Encl 5.38 (Restoration of Power)

[KA: EPE 055 EA1.07 (4.3/4.5)] (15 min)

h. N/A

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

i. AO-501 Place Reactor Building Hydrogen Analyzers in D, E, R 5 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

[KA: 028 G2.1.30 (4.4/4.0)] (15 min)

j. AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire N, E 8 Hose Station)

[KA: 075 G2.1.30 (4.4/4.0)] (20 min)

k. AO-S402 Reset an Emergency FDW Pump Turbine D 4S OP/1/A/1106/006 Encl 4.2 (Resetting TD EFDWP)

[KA: 061 A2.04 (3.4/3.8)] (10 min)

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

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature 1/ 1/ 1 (control room system)

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

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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ILT 16-1 Facility: Oconee Date of Examination: 06/13/16 Exam Level: RO SRO-I SRO-U X Operating Test No.: 1 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code* Safety Function

a. RO-103a Withdrawal of Safety Rods Group 1 to 50%

A, D, L, S 1 OP/1/A/1105/019 Encl 4.3 (Withdrawal of Safety Rod Group 1 to 50%)

[KA: 001 G2.2.2 (4.6/4.1)] (15 min)

b. RO-305a Perform Required Actions for a Failed LPI A, D, E, EN, 3 Train L, S EOP Encl 5.1 (ES Actuation)

[KA: EPE 011 EA1.04 (4.4/4.4)] (15 min)

c. RO-S403a Align PSW to HPI Pump Motor Coolers A, E, N, S 4S AP/2/A/1700/024 Encl 5.4 (PSW to HPI Pump Motor Coolers)

[KA: 076 A2.01 (3.5*/3.7*)] (10 min)

d. N/A

e. N/A

f. N/A

g. N/A

h. N/A

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

i. AO-501 Place Reactor Building Hydrogen Analyzers in D, E, R 5 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

[KA: 028 G2.1.30 (4.4/4.0)] (15 min)

j. AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire N, E 8 Hose Station)

[KA: 075 G2.1.30 (4.4/4.0)] (20 min)

k. N/A

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

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature 1/ 1 / 1 (control room system)

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

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

ES-401, Rev. 10 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

1. 1 3 3 3 3 3 3 18 18 3 3 66 Emergency &

2 2 1 2 2 1 1 99 2 2 44 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 5 5 4 4 27 27 5 5 1010 1 3 2 3 3 2 2 3 2 3 2 3 28 28 2 3 55 2.

2 1 1 1 1 1 1 1 1 1 1 0 10 10 1 2 33 Plant Systems Tier Totals 4 3 4 4 3 3 4 3 4 3 3 38 38 5 88

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 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, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).

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 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 (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 K/A categories.

7. *The generic (G) K/As in Tiers 1 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 D.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 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 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 55.43..

ES-401, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 007EK3.01 Reactor Trip - Stabilization - Recovery 4 4.6 Actions contained in EOP for reactor trip

/1 008AK2.02 Pressurizer Vapor Space Accident / 3 2.7 2.7 Sensors and detectors 009EK1.01 Small Break LOCA / 3 4.2 4.7 Natural circulation and cooling, including reflux boiling 011EK2.02 Large Break LOCA / 3 2.6 2.7 Pumps 022AK1.03 Loss of Rx Coolant Makeup / 2 3 3.4 Relationship between charging flow and PZR level 025AK1.01 Loss of RHR System / 4 3.9 4.3 Loss of RHRS during all modes of operation 026AK3.03 Loss of Component Cooling Water / 8 4 4.2 Guidance actions contained in EOP for Loss of CCW 029EK2.06 ATWS / 1 2.9 3.1 Breakers, relays, and disconnects.

038EA1.36 Steam Gen. Tube Rupture / 3 4.3 4.5 Cooldown of RCS to specified temperature 054AA2.08 Loss of Main Feedwater / 4 2.9 3.3 Steam flow-feed trend recorder 056AG2.4.35 Loss of Off-site Power / 6 3.8 4.0 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Page 1 of 2 12/13/2015 10:11 PM

ES-401, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 057AA1.05 Loss of Vital AC Inst. Bus / 6 3.2 3.4 Backup instrument indications 058AG2.1.20 Loss of DC Power / 6 4.6 4.6 Ability to execute procedure steps.

062AA2.04 Loss of Nuclear Svc Water / 4 2.5 2.9 The normal values and upper limits for the temperatures of the components cooled by SWS 065AA2.05 Loss of Instrument Air / 8 3.4 4.1 When to commence plant shutdown if instrument air pressure is decreasing 077AA1.05 Generator Voltage and Electric Grid 3.9 4.0 Engineered Safety Features Disturbances / 6 BE04EK3.2 Inadequate Heat Transfer - Loss of 3.5 4 Normal, abnormal and emergency operating procedures Secondary Heat Sink / 4 associated with (Inadequate Heat Transfer).

BE05EG2.4.5 Steam Line Rupture - Excessive Heat 4.2 4.0 Ability to verify system alarm setpoints and operate Transfer / 4 controls identified in the alarm response manual.

Page 2 of 2 12/13/2015 10:11 PM

ES-401, REV 10 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 037AK1.02 Steam Generator Tube Leak / 3 3.5 3.9 Leak rate vs. pressure drop 059AA1.03 Accidental Liquid RadWaste Rel. / 9 3 2.9 Flow rate controller 060AK3.03 Accidental Gaseous Radwaste Rel. / 9 3.8 4.2 Actions contained in EOP for accidental gaseous-waste release 074EA2.04 Inad. Core Cooling / 4 3.7 4.2 Relationship between RCS temperature and main steam pressure BA01AK2.1 Plant Runback / 1 3.7 3.5 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

BA04AK3.2 Turbine Trip / 4 3.4 3.6 Normal, abnormal and emergency operating procedures associated with (Turbine Trip).

BA06AG2.4.6 Shutdown Outside Control Room / 8 3.7 4.7 Knowledge symptom based EOP mitigation strategies.

BE08EA1.3 LOCA Cooldown - Depress. / 4 3.3 3.8 Desired operating results during abnormal and emergency situations.

BE13EK1.2 EOP Rules 3 3.6 Normal, abnormal and emergency operating procedures associated with (EOP Rules).

Page 1 of 1 12/13/2015 10:11 PM

ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 003G2.4.20 Reactor Coolant Pump 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.

004K6.10 Chemical and Volume Control 2.7 3.1 Boric acid storage tank/boron injection tank recirculation flow path 005K2.01 Residual Heat Removal 3.0 3.2 RHR pumps 005K4.06 Residual Heat Removal 2.7 3.0 Function of RHR pump miniflow recirculation 006K5.08 Emergency Core Cooling 2.9 3.1 Operation of pumps in parallel 007A1.02 Pressurizer Relief/Quench Tank 2.7 2.9 Maintaining quench tank pressure 007K3.01 Pressurizer Relief/Quench Tank 3.3 3.6 Containment 008A2.03 Component Cooling Water 3.0 3.2 High/low CCW temperature 010K3.01 Pressurizer Pressure Control 3.8 3.9 RCS 012K6.10 Reactor Protection 3.3 3.5 Permissive circuits 013A4.03 Engineered Safety Features Actuation 4.5 4.7 ESFAS initiation Page 1 of 3 12/13/2015 10:11 PM

ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 022G2.4.18 Containment Cooling 3.3 4.0 Knowledge of the specific bases for EOPs.

022K2.02 Containment Cooling 2.5 2.4 Chillers 026K4.05 Containment Spray 2.8 3.3 Prevention of material from clogging nozzles during recirculation 039A2.01 Main and Reheat Steam 3.1 3.2 Flow paths of steam during a LOCA 039A3.02 Main and Reheat Steam 3.1 3.5 Isolation of the MRSS 059A3.07 Main Feedwater 3.4 3.5 ICS 059K1.03 Main Feedwater 3.1 3.3 S/GS 061G2.1.25 Auxiliary/Emergency Feedwater 3.9 4.2 Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

062K1.04 AC Electrical Distribution 3.7 4.2 Off-site power sources 062K4.02 AC Electrical Distribution 2.5 2.7 Circuit breaker automatic trips 063K1.03 DC Electrical Distribution 2.9 3.5 Battery charger and battery Page 2 of 3 12/13/2015 10:11 PM

ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 063K3.02 DC Electrical Distribution 3.5 3.7 Components using DC control power 073A1.01 Process Radiation Monitoring 3.2 3.5 Radiation levels 073K5.01 Process Radiation Monitoring 2.5 3.0 Radiation theory, including sources, types, units and effects 076A1.02 Service Water 2.6 2.6 Reactor and turbine building closed cooling water temperatures.

078A4.01 Instrument Air 3.1 3.1 Pressure gauges 103A3.01 Containment 3.9 4.2 Containment isolation Page 3 of 3 12/13/2015 10:11 PM

ES-401, REV 10 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 002K6.03 Reactor Coolant 3.1 3.6 Reactor vessel level indication 016K5.01 Non-nuclear Instrumentation 2.7 2.8 Separation of control and protection circuits 028K2.01 Hydrogen Recombiner and Purge 2.5 2.8 Hydrogen recombiners Control 035A3.01 Steam Generator 4.0 3.9 S/ G water level control 045K3.01 Main Turbine Generator 2.9 3.2 Remainder of the plant 055K1.06 Condenser Air Removal 2.6 2.6 PRM system 056A2.04 Condensate 2.6 2.8 Loss of condensate pumps 071K4.03 Waste Gas Disposal 2.5 2.6 Tank loop seals 079A4.01 Station Air 2.7 2.7 Cross-tie valves with IAS 086A1.03 Fire Protection 2.7 3.2 Fire doors Page 1 of 1 12/13/2015 10:11 PM

ES-401, REV 10 T3 PWR EXAMINATION OUTLINE FORM ES-401-3 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G2.1.17 Conduct of operations 3.9 4.0 Ability to make accurate, clear and concise verbal reports.

G2.1.39 Conduct of operations 3.6 4.3 Knowledge of conservative decision making practices G2.1.44 Conduct of operations 3.9 3.8 Knowledge of RO duties in the control room during fuel handling.

G2.2.38 Equipment Control 3.6 4.5 Knowledge of conditions and limitations in the facility license.

G2.2.4 Equipment Control 3.6 3.6 (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

G2.2.40 Equipment Control 3.4 4.7 Ability to apply technical specifications for a system.

G2.3.11 Radiation Control 3.8 4.3 Ability to control radiation releases.

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

G2.4.50 Emergency Procedures/Plans 4.2 4.0 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Page 1 of 1 12/13/2015 10:11 PM

ES-401, REV 10 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 008AA2.28 Pressurizer Vapor Space Accident / 3 3.3 3.9 Safety parameter display system indications 015AA2.07 RCP Malfunctions / 4 2.1 2.9 Calculation of expected values of flow in the loop with RCP secured 025AG2.4.46 Loss of RHR System / 4 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.

054AG2.1.31 Loss of Main Feedwater / 4 4.6 4.3 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

058AG2.2.22 Loss of DC Power / 6 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.

BE04EA2.2 Inadequate Heat Transfer - Loss of 3.6 4.4 Adherence to appropriate procedures and operation within Secondary Heat Sink / 4 the limitations in the facility s license and amendments.

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ES-401, REV 10 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 028AG2.4.20 Pressurizer Level Malfunction / 2 3.8 4.3 Knowledge of operational implications of EOP warnings, cautions and notes.

037AA2.03 Steam Generator Tube Leak / 3 3.4 3.9 That the expected indication on main steam lines from the S/Gs should show increasing radiation levels BE03EG2.4.30 Inadequate Subcooling Margin / 4 2.7 4.1 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

BE13EA2.2 EOP Rules 3.8 4 Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.

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ES-401, REV 10 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 006G2.4.21 Emergency Core Cooling 4.0 4.6 Knowledge of the parameters and logic used to assess the status of safety functions 007A2.07 Pressurizer Relief/Quench Tank 2.3 2.6 Recirculating quench tank 013G2.2.37 Engineered Safety Features Actuation 3.6 4.6 Ability to determine operability and/or availability of safety related equipment 061A2.02 Auxiliary/Emergency Feedwater 3.4 3.5 Air or MOV failure 063G2.4.41 DC Electrical Distribution 2.9 4.6 Knowledge of the emergency action level thresholds and classifications.

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ES-401, REV 10 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 001G2.2.40 Control Rod Drive 3.4 4.7 Ability to apply technical specifications for a system.

016A2.02 Non-nuclear Instrumentation 2.9 3.2 Loss of power supply 017G2.4.9 In-core Temperature Monitor 3.8 4.2 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

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ES-401, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-3 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G2.1.2 Conduct of operations 4.1 4.4 Knowledge of operator responsibilities during all modes of plant operation.

G2.2.11 Equipment Control 2.3 3.3 Knowledge of the process for controlling temporary design changes.

G2.2.3 Equipment Control 3.8 3.9 (multi-unit license) Knowledge of the design, procedural and operational differences between units.

G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.16 Emergency Procedures/Plans 3.5 4.4 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.

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

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