ML19115A255

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301 ADAMS2C Exam Administrative Items
ML19115A255
Person / Time
Site: Oconee  Duke Energy icon.png
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 (see Note)

Type Code*

Describe activity to be performed Conduct of Operations

[KA:G2.1.25 (3.9/4.2)]

(15 min)

M, R Admin-108, Determine Time for SFP to Reach 200ºF (Both)

Conduct of Operations

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

(15 min)

D, R Admin-109, Unit 3 SFP Boron and Volume Change Calculation (RO Only)

Equipment Control

[KA: G2.2.12 (3.7/4.1)]

(18 min)

D, R Admin-204, Perform SG Downcomer Temperature Surveillance (RO Only)

Radiological Control

[KA: G2.3.4 (3.2/3.7)]

(20 min)

M, R Admin-304, Determine the Maximum Permissible Stay Time Within Emergency Dose 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 (see Note)

Type Code*

Describe activity to be performed Conduct of Operations

[KA:G2.1.25 (3.9/4.2)]

(15 min)

M, R Admin-108, Determine Time for SFP to Reach 200ºF (Both)

Conduct of Operations

[KA: G2.1.7 (4.4/4.7 ]

(16 min)

D, R Admin-S107, Calculation of Primary to Secondary Leak Rate and Unit Shutdown Requirements (SRO Only)

Equipment Control

[KA G2.2.18 (2.6/3.9)]

(25 min)

D, R Admin-S203, Complete Plant Configuration Sheet (Time to Core Boil) and Determine Any Required Actions (SRO Only)

Radiological Control

[KA: G2.3.4 (3.2/3.7)]

(20 min)

M, R Admin-304, Determine the Maximum Permissible Stay Time Within Emergency Dose Limits (EDLs) (Both)

Emergency Plan

[KA G2.4.38 (2.4/4.4)]

(20 min)

D, R Admin-S404, Determine Emergency Classification and Protective Action 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%

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)

A, D, L, S 1

b. RO-305a Perform Required Actions for a Failed LPI Train EOP Encl 5.1 (ES Actuation)

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

A, D, E, EN, L, S 3

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

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

A, E, N, S 4S

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

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

D, S 2

e. RO-P404 Align ECCS Suction to Emergency Sump EOP Encl 5.12 (ECCS Suction Swap to RBES)

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

E, EN, L, M, S

4P

f.

RO-504a Perform EOP Encl 5.35 EOP Encl 5.35 (Containment Isolation)

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

A, D, E, L, S 5

g. RO-603a Energize MFBs From CT-5 EOP Encl 5.38 (Restoration of Power)

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

A, D, L, S 6

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

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

D, L, S 8

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 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

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

D, E, R 5

j.

AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire Hose Station)

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

N, E 8

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

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

D 4S 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1/ 1/ 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

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%

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)

A, D, L, S 1

b. RO-305a Perform Required Actions for a Failed LPI Train EOP Encl 5.1 (ES Actuation)

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

A, D, E, EN, L, S 3

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

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

A, E, N, S 4S

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

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

D, S 2

e. RO-P404 Align ECCS Suction to Emergency Sump EOP Encl 5.12 (ECCS Suction Swap to RBES)

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

E, EN, L, M, S

4P

f.

RO-504a Perform EOP Encl 5.35 EOP Encl 5.35 (Containment Isolation)

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

A, D, E, L, S 5

g. RO-603a Energize MFBs From CT-5 EOP Encl 5.38 (Restoration of Power)

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

A, D, L, S 6

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 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

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

D, E, R 5

j.

AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire Hose Station)

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

N, E 8

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

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

D 4S 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1/ 1/ 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

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%

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)

A, D, L, S 1

b. RO-305a Perform Required Actions for a Failed LPI Train EOP Encl 5.1 (ES Actuation)

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

A, D, E, EN, L, S 3

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

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

A, E, N, S 4S

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 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

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

D, E, R 5

j.

AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire Hose Station)

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

N, E 8

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1/ 1 / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

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

Tier Group RO K/A Category Points SRO-Only Points K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total

1.

Emergency &

Abnormal Plant Evolutions 1

N/A N/A 18 6

2 9

4 Tier Totals 27 10

2.

Plant Systems 1

28 5

2 10 3

Tier Totals 38 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

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..

3 3

3 3

3 3

2 1

2 2

1 1

5 4

5 5

4 4

3 2

3 3

2 2

3 2

3 2

3 1

1 1

1 1

1 1

1 1

1 0

4 3

4 4

3 3

4 3

4 3

3 3

3 2

1 2

2 2

2 3

3 6

2 2

5 5

10 2

3 1

2 5

18 27 38 9

28 10 4

3 5

8

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Reactor Trip - Stabilization - Recovery

/ 1 Actions contained in EOP for reactor trip 007EK3.01 4

4.6 Pressurizer Vapor Space Accident / 3 Sensors and detectors 008AK2.02 2.7 2.7 Small Break LOCA / 3 Natural circulation and cooling, including reflux boiling 009EK1.01 4.2 4.7 Large Break LOCA / 3 Pumps 011EK2.02 2.6 2.7 Loss of Rx Coolant Makeup / 2 Relationship between charging flow and PZR level 022AK1.03 3

3.4 Loss of RHR System / 4 Loss of RHRS during all modes of operation 025AK1.01 3.9 4.3 Loss of Component Cooling Water / 8 Guidance actions contained in EOP for Loss of CCW 026AK3.03 4

4.2 ATWS / 1 Breakers, relays, and disconnects.

029EK2.06 2.9 3.1 Steam Gen. Tube Rupture / 3 Cooldown of RCS to specified temperature 038EA1.36 4.3 4.5 Loss of Main Feedwater / 4 Steam flow-feed trend recorder 054AA2.08 2.9 3.3 Loss of Off-site Power / 6 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 056AG2.4.35 3.8 4.0 Page 1 of 2 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Loss of Vital AC Inst. Bus / 6 Backup instrument indications 057AA1.05 3.2 3.4 Loss of DC Power / 6 Ability to execute procedure steps.

058AG2.1.20 4.6 4.6 Loss of Nuclear Svc Water / 4 The normal values and upper limits for the temperatures of the components cooled by SWS 062AA2.04 2.5 2.9 Loss of Instrument Air / 8 When to commence plant shutdown if instrument air pressure is decreasing 065AA2.05 3.4 4.1 Generator Voltage and Electric Grid Disturbances / 6 Engineered Safety Features 077AA1.05 3.9 4.0 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 Normal, abnormal and emergency operating procedures associated with (Inadequate Heat Transfer).

BE04EK3.2 3.5 4

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

BE05EG2.4.5 4.2 4.0 Page 2 of 2 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Steam Generator Tube Leak / 3 Leak rate vs. pressure drop 037AK1.02 3.5 3.9 Accidental Liquid RadWaste Rel. / 9 Flow rate controller 059AA1.03 3

2.9 Accidental Gaseous Radwaste Rel. / 9 Actions contained in EOP for accidental gaseous-waste release 060AK3.03 3.8 4.2 Inad. Core Cooling / 4 Relationship between RCS temperature and main steam pressure 074EA2.04 3.7 4.2 Plant Runback / 1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

BA01AK2.1 3.7 3.5 Turbine Trip / 4 Normal, abnormal and emergency operating procedures associated with (Turbine Trip).

BA04AK3.2 3.4 3.6 Shutdown Outside Control Room / 8 Knowledge symptom based EOP mitigation strategies.

BA06AG2.4.6 3.7 4.7 LOCA Cooldown - Depress. / 4 Desired operating results during abnormal and emergency situations.

BE08EA1.3 3.3 3.8 EOP Rules Normal, abnormal and emergency operating procedures associated with (EOP Rules).

BE13EK1.2 3

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

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Reactor Coolant Pump Knowledge of operational implications of EOP warnings, cautions and notes.

003G2.4.20 3.8 4.3 Chemical and Volume Control Boric acid storage tank/boron injection tank recirculation flow path 004K6.10 2.7 3.1 Residual Heat Removal RHR pumps 005K2.01 3.0 3.2 Residual Heat Removal Function of RHR pump miniflow recirculation 005K4.06 2.7 3.0 Emergency Core Cooling Operation of pumps in parallel 006K5.08 2.9 3.1 Pressurizer Relief/Quench Tank Maintaining quench tank pressure 007A1.02 2.7 2.9 Pressurizer Relief/Quench Tank Containment 007K3.01 3.3 3.6 Component Cooling Water High/low CCW temperature 008A2.03 3.0 3.2 Pressurizer Pressure Control RCS 010K3.01 3.8 3.9 Reactor Protection Permissive circuits 012K6.10 3.3 3.5 Engineered Safety Features Actuation ESFAS initiation 013A4.03 4.5 4.7 Page 1 of 3 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Containment Cooling Knowledge of the specific bases for EOPs.

022G2.4.18 3.3 4.0 Containment Cooling Chillers 022K2.02 2.5 2.4 Containment Spray Prevention of material from clogging nozzles during recirculation 026K4.05 2.8 3.3 Main and Reheat Steam Flow paths of steam during a LOCA 039A2.01 3.1 3.2 Main and Reheat Steam Isolation of the MRSS 039A3.02 3.1 3.5 Main Feedwater ICS 059A3.07 3.4 3.5 Main Feedwater S/GS 059K1.03 3.1 3.3 Auxiliary/Emergency Feedwater Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

061G2.1.25 3.9 4.2 AC Electrical Distribution Off-site power sources 062K1.04 3.7 4.2 AC Electrical Distribution Circuit breaker automatic trips 062K4.02 2.5 2.7 DC Electrical Distribution Battery charger and battery 063K1.03 2.9 3.5 Page 2 of 3 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 DC Electrical Distribution Components using DC control power 063K3.02 3.5 3.7 Process Radiation Monitoring Radiation levels 073A1.01 3.2 3.5 Process Radiation Monitoring Radiation theory, including sources, types, units and effects 073K5.01 2.5 3.0 Service Water Reactor and turbine building closed cooling water temperatures.

076A1.02 2.6 2.6 Instrument Air Pressure gauges 078A4.01 3.1 3.1 Containment Containment isolation 103A3.01 3.9 4.2 Page 3 of 3 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Reactor Coolant Reactor vessel level indication 002K6.03 3.1 3.6 Non-nuclear Instrumentation Separation of control and protection circuits 016K5.01 2.7 2.8 Hydrogen Recombiner and Purge Control Hydrogen recombiners 028K2.01 2.5 2.8 Steam Generator S/ G water level control 035A3.01 4.0 3.9 Main Turbine Generator Remainder of the plant 045K3.01 2.9 3.2 Condenser Air Removal PRM system 055K1.06 2.6 2.6 Condensate Loss of condensate pumps 056A2.04 2.6 2.8 Waste Gas Disposal Tank loop seals 071K4.03 2.5 2.6 Station Air Cross-tie valves with IAS 079A4.01 2.7 2.7 Fire Protection Fire doors 086A1.03 2.7 3.2 Page 1 of 1 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T3 PWR EXAMINATION OUTLINE FORM ES-401-3 Conduct of operations Ability to make accurate, clear and concise verbal reports.

G2.1.17 3.9 4.0 Conduct of operations Knowledge of conservative decision making practices G2.1.39 3.6 4.3 Conduct of operations Knowledge of RO duties in the control room during fuel handling.

G2.1.44 3.9 3.8 Equipment Control Knowledge of conditions and limitations in the facility license.

G2.2.38 3.6 4.5 Equipment Control (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

G2.2.4 3.6 3.6 Equipment Control Ability to apply technical specifications for a system.

G2.2.40 3.4 4.7 Radiation Control Ability to control radiation releases.

G2.3.11 3.8 4.3 Radiation Control Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.3.7 3.5 3.6 Emergency Procedures/Plans Knowledge of the emergency plan.

G2.4.29 3.1 4.4 Emergency Procedures/Plans Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

G2.4.50 4.2 4.0 Page 1 of 1 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Pressurizer Vapor Space Accident / 3 Safety parameter display system indications 008AA2.28 3.3 3.9 RCP Malfunctions / 4 Calculation of expected values of flow in the loop with RCP secured 015AA2.07 2.1 2.9 Loss of RHR System / 4 Ability to verify that the alarms are consistent with the plant conditions.

025AG2.4.46 4.2 4.2 Loss of Main Feedwater / 4 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

054AG2.1.31 4.6 4.3 Loss of DC Power / 6 Knowledge of limiting conditions for operations and safety limits.

058AG2.2.22 4.0 4.7 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.

BE04EA2.2 3.6 4.4 Page 1 of 1 10:13 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Pressurizer Level Malfunction / 2 Knowledge of operational implications of EOP warnings, cautions and notes.

028AG2.4.20 3.8 4.3 Steam Generator Tube Leak / 3 That the expected indication on main steam lines from the S/Gs should show increasing radiation levels 037AA2.03 3.4 3.9 Inadequate Subcooling Margin / 4 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

BE03EG2.4.30 2.7 4.1 EOP Rules Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.

BE13EA2.2 3.8 4

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

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Emergency Core Cooling Knowledge of the parameters and logic used to assess the status of safety functions 006G2.4.21 4.0 4.6 Pressurizer Relief/Quench Tank Recirculating quench tank 007A2.07 2.3 2.6 Engineered Safety Features Actuation Ability to determine operability and/or availability of safety related equipment 013G2.2.37 3.6 4.6 Auxiliary/Emergency Feedwater Air or MOV failure 061A2.02 3.4 3.5 DC Electrical Distribution Knowledge of the emergency action level thresholds and classifications.

063G2.4.41 2.9 4.6 Page 1 of 1 10:13 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Control Rod Drive Ability to apply technical specifications for a system.

001G2.2.40 3.4 4.7 Non-nuclear Instrumentation Loss of power supply 016A2.02 2.9 3.2 In-core Temperature Monitor Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

017G2.4.9 3.8 4.2 Page 1 of 1 10:13 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-3 Conduct of operations Knowledge of operator responsibilities during all modes of plant operation.

G2.1.2 4.1 4.4 Equipment Control Knowledge of the process for controlling temporary design changes.

G2.2.11 2.3 3.3 Equipment Control (multi-unit license) Knowledge of the design, procedural and operational differences between units.

G2.2.3 3.8 3.9 Radiation Control Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.12 3.2 3.7 Radiation Control Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.3.7 3.5 3.6 Emergency Procedures/Plans Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.

G2.4.16 3.5 4.4 Emergency Procedures/Plans Knowledge of emergency plan protective action recommendations.

G2.4.44 2.4 4.4 Page 1 of 1 10:13 PM 12/13/2015

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 (see Note)

Type Code*

Describe activity to be performed Conduct of Operations

[KA:G2.1.25 (3.9/4.2)]

(15 min)

M, R Admin-108, Determine Time for SFP to Reach 200ºF (Both)

Conduct of Operations

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

(15 min)

D, R Admin-109, Unit 3 SFP Boron and Volume Change Calculation (RO Only)

Equipment Control

[KA: G2.2.12 (3.7/4.1)]

(18 min)

D, R Admin-204, Perform SG Downcomer Temperature Surveillance (RO Only)

Radiological Control

[KA: G2.3.4 (3.2/3.7)]

(20 min)

M, R Admin-304, Determine the Maximum Permissible Stay Time Within Emergency Dose 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 (see Note)

Type Code*

Describe activity to be performed Conduct of Operations

[KA:G2.1.25 (3.9/4.2)]

(15 min)

M, R Admin-108, Determine Time for SFP to Reach 200ºF (Both)

Conduct of Operations

[KA: G2.1.7 (4.4/4.7 ]

(16 min)

D, R Admin-S107, Calculation of Primary to Secondary Leak Rate and Unit Shutdown Requirements (SRO Only)

Equipment Control

[KA G2.2.18 (2.6/3.9)]

(25 min)

D, R Admin-S203, Complete Plant Configuration Sheet (Time to Core Boil) and Determine Any Required Actions (SRO Only)

Radiological Control

[KA: G2.3.4 (3.2/3.7)]

(20 min)

M, R Admin-304, Determine the Maximum Permissible Stay Time Within Emergency Dose Limits (EDLs) (Both)

Emergency Plan

[KA G2.4.38 (2.4/4.4)]

(20 min)

D, R Admin-S404, Determine Emergency Classification and Protective Action 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%

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)

A, D, L, S 1

b. RO-305a Perform Required Actions for a Failed LPI Train EOP Encl 5.1 (ES Actuation)

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

A, D, E, EN, L, S 3

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

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

A, E, N, S 4S

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

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

D, S 2

e. RO-P404 Align ECCS Suction to Emergency Sump EOP Encl 5.12 (ECCS Suction Swap to RBES)

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

E, EN, L, M, S

4P

f.

RO-504a Perform EOP Encl 5.35 EOP Encl 5.35 (Containment Isolation)

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

A, D, E, L, S 5

g. RO-603a Energize MFBs From CT-5 EOP Encl 5.38 (Restoration of Power)

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

A, D, L, S 6

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

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

D, L, S 8

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 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

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

D, E, R 5

j.

AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire Hose Station)

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

N, E 8

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

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

D 4S 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1/ 1/ 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

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%

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)

A, D, L, S 1

b. RO-305a Perform Required Actions for a Failed LPI Train EOP Encl 5.1 (ES Actuation)

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

A, D, E, EN, L, S 3

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

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

A, E, N, S 4S

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

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

D, S 2

e. RO-P404 Align ECCS Suction to Emergency Sump EOP Encl 5.12 (ECCS Suction Swap to RBES)

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

E, EN, L, M, S

4P

f.

RO-504a Perform EOP Encl 5.35 EOP Encl 5.35 (Containment Isolation)

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

A, D, E, L, S 5

g. RO-603a Energize MFBs From CT-5 EOP Encl 5.38 (Restoration of Power)

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

A, D, L, S 6

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 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

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

D, E, R 5

j.

AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire Hose Station)

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

N, E 8

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

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

D 4S 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1/ 1/ 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

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%

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)

A, D, L, S 1

b. RO-305a Perform Required Actions for a Failed LPI Train EOP Encl 5.1 (ES Actuation)

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

A, D, E, EN, L, S 3

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

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

A, E, N, S 4S

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 Service EOP Encl 5,2 (Placing RB Hydrogen Analyzers in Service)

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

D, E, R 5

j.

AO-803 Supply SSW by the Fire Hose Station AP/1/A/1700/033 Encl 5.6 (Supply of SSW by the Fire Hose Station)

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

N, E 8

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1/ 1 / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1

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

Tier Group RO K/A Category Points SRO-Only Points K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total

1.

Emergency &

Abnormal Plant Evolutions 1

N/A N/A 18 6

2 9

4 Tier Totals 27 10

2.

Plant Systems 1

28 5

2 10 3

Tier Totals 38 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

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..

3 3

3 3

3 3

2 1

2 2

1 1

5 4

5 5

4 4

3 2

3 3

2 2

3 2

3 2

3 1

1 1

1 1

1 1

1 1

1 0

4 3

4 4

3 3

4 3

4 3

3 3

3 2

1 2

2 2

2 3

3 6

2 2

5 5

10 2

3 1

2 5

18 27 38 9

28 10 4

3 5

8

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Reactor Trip - Stabilization - Recovery

/ 1 Actions contained in EOP for reactor trip 007EK3.01 4

4.6 Pressurizer Vapor Space Accident / 3 Sensors and detectors 008AK2.02 2.7 2.7 Small Break LOCA / 3 Natural circulation and cooling, including reflux boiling 009EK1.01 4.2 4.7 Large Break LOCA / 3 Pumps 011EK2.02 2.6 2.7 Loss of Rx Coolant Makeup / 2 Relationship between charging flow and PZR level 022AK1.03 3

3.4 Loss of RHR System / 4 Loss of RHRS during all modes of operation 025AK1.01 3.9 4.3 Loss of Component Cooling Water / 8 Guidance actions contained in EOP for Loss of CCW 026AK3.03 4

4.2 ATWS / 1 Breakers, relays, and disconnects.

029EK2.06 2.9 3.1 Steam Gen. Tube Rupture / 3 Cooldown of RCS to specified temperature 038EA1.36 4.3 4.5 Loss of Main Feedwater / 4 Steam flow-feed trend recorder 054AA2.08 2.9 3.3 Loss of Off-site Power / 6 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 056AG2.4.35 3.8 4.0 Page 1 of 2 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Loss of Vital AC Inst. Bus / 6 Backup instrument indications 057AA1.05 3.2 3.4 Loss of DC Power / 6 Ability to execute procedure steps.

058AG2.1.20 4.6 4.6 Loss of Nuclear Svc Water / 4 The normal values and upper limits for the temperatures of the components cooled by SWS 062AA2.04 2.5 2.9 Loss of Instrument Air / 8 When to commence plant shutdown if instrument air pressure is decreasing 065AA2.05 3.4 4.1 Generator Voltage and Electric Grid Disturbances / 6 Engineered Safety Features 077AA1.05 3.9 4.0 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 Normal, abnormal and emergency operating procedures associated with (Inadequate Heat Transfer).

BE04EK3.2 3.5 4

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

BE05EG2.4.5 4.2 4.0 Page 2 of 2 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Steam Generator Tube Leak / 3 Leak rate vs. pressure drop 037AK1.02 3.5 3.9 Accidental Liquid RadWaste Rel. / 9 Flow rate controller 059AA1.03 3

2.9 Accidental Gaseous Radwaste Rel. / 9 Actions contained in EOP for accidental gaseous-waste release 060AK3.03 3.8 4.2 Inad. Core Cooling / 4 Relationship between RCS temperature and main steam pressure 074EA2.04 3.7 4.2 Plant Runback / 1 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

BA01AK2.1 3.7 3.5 Turbine Trip / 4 Normal, abnormal and emergency operating procedures associated with (Turbine Trip).

BA04AK3.2 3.4 3.6 Shutdown Outside Control Room / 8 Knowledge symptom based EOP mitigation strategies.

BA06AG2.4.6 3.7 4.7 LOCA Cooldown - Depress. / 4 Desired operating results during abnormal and emergency situations.

BE08EA1.3 3.3 3.8 EOP Rules Normal, abnormal and emergency operating procedures associated with (EOP Rules).

BE13EK1.2 3

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

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Reactor Coolant Pump Knowledge of operational implications of EOP warnings, cautions and notes.

003G2.4.20 3.8 4.3 Chemical and Volume Control Boric acid storage tank/boron injection tank recirculation flow path 004K6.10 2.7 3.1 Residual Heat Removal RHR pumps 005K2.01 3.0 3.2 Residual Heat Removal Function of RHR pump miniflow recirculation 005K4.06 2.7 3.0 Emergency Core Cooling Operation of pumps in parallel 006K5.08 2.9 3.1 Pressurizer Relief/Quench Tank Maintaining quench tank pressure 007A1.02 2.7 2.9 Pressurizer Relief/Quench Tank Containment 007K3.01 3.3 3.6 Component Cooling Water High/low CCW temperature 008A2.03 3.0 3.2 Pressurizer Pressure Control RCS 010K3.01 3.8 3.9 Reactor Protection Permissive circuits 012K6.10 3.3 3.5 Engineered Safety Features Actuation ESFAS initiation 013A4.03 4.5 4.7 Page 1 of 3 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Containment Cooling Knowledge of the specific bases for EOPs.

022G2.4.18 3.3 4.0 Containment Cooling Chillers 022K2.02 2.5 2.4 Containment Spray Prevention of material from clogging nozzles during recirculation 026K4.05 2.8 3.3 Main and Reheat Steam Flow paths of steam during a LOCA 039A2.01 3.1 3.2 Main and Reheat Steam Isolation of the MRSS 039A3.02 3.1 3.5 Main Feedwater ICS 059A3.07 3.4 3.5 Main Feedwater S/GS 059K1.03 3.1 3.3 Auxiliary/Emergency Feedwater Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

061G2.1.25 3.9 4.2 AC Electrical Distribution Off-site power sources 062K1.04 3.7 4.2 AC Electrical Distribution Circuit breaker automatic trips 062K4.02 2.5 2.7 DC Electrical Distribution Battery charger and battery 063K1.03 2.9 3.5 Page 2 of 3 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 DC Electrical Distribution Components using DC control power 063K3.02 3.5 3.7 Process Radiation Monitoring Radiation levels 073A1.01 3.2 3.5 Process Radiation Monitoring Radiation theory, including sources, types, units and effects 073K5.01 2.5 3.0 Service Water Reactor and turbine building closed cooling water temperatures.

076A1.02 2.6 2.6 Instrument Air Pressure gauges 078A4.01 3.1 3.1 Containment Containment isolation 103A3.01 3.9 4.2 Page 3 of 3 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Reactor Coolant Reactor vessel level indication 002K6.03 3.1 3.6 Non-nuclear Instrumentation Separation of control and protection circuits 016K5.01 2.7 2.8 Hydrogen Recombiner and Purge Control Hydrogen recombiners 028K2.01 2.5 2.8 Steam Generator S/ G water level control 035A3.01 4.0 3.9 Main Turbine Generator Remainder of the plant 045K3.01 2.9 3.2 Condenser Air Removal PRM system 055K1.06 2.6 2.6 Condensate Loss of condensate pumps 056A2.04 2.6 2.8 Waste Gas Disposal Tank loop seals 071K4.03 2.5 2.6 Station Air Cross-tie valves with IAS 079A4.01 2.7 2.7 Fire Protection Fire doors 086A1.03 2.7 3.2 Page 1 of 1 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 T3 PWR EXAMINATION OUTLINE FORM ES-401-3 Conduct of operations Ability to make accurate, clear and concise verbal reports.

G2.1.17 3.9 4.0 Conduct of operations Knowledge of conservative decision making practices G2.1.39 3.6 4.3 Conduct of operations Knowledge of RO duties in the control room during fuel handling.

G2.1.44 3.9 3.8 Equipment Control Knowledge of conditions and limitations in the facility license.

G2.2.38 3.6 4.5 Equipment Control (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

G2.2.4 3.6 3.6 Equipment Control Ability to apply technical specifications for a system.

G2.2.40 3.4 4.7 Radiation Control Ability to control radiation releases.

G2.3.11 3.8 4.3 Radiation Control Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.3.7 3.5 3.6 Emergency Procedures/Plans Knowledge of the emergency plan.

G2.4.29 3.1 4.4 Emergency Procedures/Plans Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

G2.4.50 4.2 4.0 Page 1 of 1 10:11 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Pressurizer Vapor Space Accident / 3 Safety parameter display system indications 008AA2.28 3.3 3.9 RCP Malfunctions / 4 Calculation of expected values of flow in the loop with RCP secured 015AA2.07 2.1 2.9 Loss of RHR System / 4 Ability to verify that the alarms are consistent with the plant conditions.

025AG2.4.46 4.2 4.2 Loss of Main Feedwater / 4 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

054AG2.1.31 4.6 4.3 Loss of DC Power / 6 Knowledge of limiting conditions for operations and safety limits.

058AG2.2.22 4.0 4.7 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.

BE04EA2.2 3.6 4.4 Page 1 of 1 10:13 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Pressurizer Level Malfunction / 2 Knowledge of operational implications of EOP warnings, cautions and notes.

028AG2.4.20 3.8 4.3 Steam Generator Tube Leak / 3 That the expected indication on main steam lines from the S/Gs should show increasing radiation levels 037AA2.03 3.4 3.9 Inadequate Subcooling Margin / 4 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

BE03EG2.4.30 2.7 4.1 EOP Rules Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.

BE13EA2.2 3.8 4

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

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 Emergency Core Cooling Knowledge of the parameters and logic used to assess the status of safety functions 006G2.4.21 4.0 4.6 Pressurizer Relief/Quench Tank Recirculating quench tank 007A2.07 2.3 2.6 Engineered Safety Features Actuation Ability to determine operability and/or availability of safety related equipment 013G2.2.37 3.6 4.6 Auxiliary/Emergency Feedwater Air or MOV failure 061A2.02 3.4 3.5 DC Electrical Distribution Knowledge of the emergency action level thresholds and classifications.

063G2.4.41 2.9 4.6 Page 1 of 1 10:13 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 Control Rod Drive Ability to apply technical specifications for a system.

001G2.2.40 3.4 4.7 Non-nuclear Instrumentation Loss of power supply 016A2.02 2.9 3.2 In-core Temperature Monitor Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

017G2.4.9 3.8 4.2 Page 1 of 1 10:13 PM 12/13/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 10 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-3 Conduct of operations Knowledge of operator responsibilities during all modes of plant operation.

G2.1.2 4.1 4.4 Equipment Control Knowledge of the process for controlling temporary design changes.

G2.2.11 2.3 3.3 Equipment Control (multi-unit license) Knowledge of the design, procedural and operational differences between units.

G2.2.3 3.8 3.9 Radiation Control Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.12 3.2 3.7 Radiation Control Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.3.7 3.5 3.6 Emergency Procedures/Plans Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.

G2.4.16 3.5 4.4 Emergency Procedures/Plans Knowledge of emergency plan protective action recommendations.

G2.4.44 2.4 4.4 Page 1 of 1 10:13 PM 12/13/2015