Text

Feb 2008 Exam 05000327 & 05000328-08-301 - Final Outlines
	ML080720506
Person / Time
Site:	Sequoyah
Issue date:	02/05/2008
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	50-327/08-301, 50-328/08-301
	Download: ML080720506 (32)
	v • d • e

Final Submittal

(Blue Paper)

FINAL OUTLINES

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ES-401 PWR Examination Outline Form ES-401-2

Facility: Sequoyah Printed: 01/13/2008

Date Of Exam: 01/28/2008

RO KiA Category Points SRO-Only Points

Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 3 3 18 0 0 0

Emergenc

2 1 2 1 N/A 1 2 2 9 0 0 0

& N/A

Abnormal Tier

Plant

Totals 4 5 4 4 5 5 27 0 0 0

Evolutions

1 2 2 3 3 3 2 2 3 2 3 3 28 0 0 0

2.

2 1 1 1 1 1 1 1 0 1 1 1 10 01 0 0 0

Plant

Systems Tier 0 0 0

3 3 4 4 4 3 3 3 3 4 4 38

Totals

1 2 3 4 1 2 3 4

3. Generic Knowledge And

10 0

Abilities Categories

3 2 3 2 0 0 0 0

Note:

1. Ensure that at least two topics from every KIA category are sampled within each tier of the RO and

SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals"

in each KIA category shall not be less than two).

( 2. The point total for each group and tier in the proposed outline must match that specified in the

table. The final point total for each group and tier may deviate by +/-1 from that specified in the

table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam

must total 25 points.

3. 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 ES-401 , Attachment 2, for

guidance regarding the elimination of inappropriate KIA 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 KlAs 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 KIA categories.

7.* The generic (G) KlAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the

topics must be relevant to the applicable evolution or system.

8. On the following pages, enter the KIA 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-onlyexams.

( 9. ForTier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions,

IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to

10 CFR 55.43.

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Emergency and Abnormal Plant EVOlutions - Tier I 1 Group I Form ES-401-2

I TCJAPE # 1 Name 1 Safety Function KI K2 K3 Al A2 G KA Topic Imp. Points

(

000007 Reactor Trip - Stabilization - X EAl.08 - AFW System 4.4 1

Recovery 11

000008 Pressurizer Vapor Space Accident 1 X AA2.29 - The effects of bubble in 3.9 1

3 reactor vessel

000009 Small Break LOCA 13 X EA2.24 - RCP temperature setpoints 2.6 1

000011 Large Break LOCA 13 X EK3.13 - Hot-leg injection/recirculation 3.8 1

000015/000017 RCP Malfunctions 14 X AK2.08 - CCWS 2.6 1

000022 Loss of Rx Coolant Makeup 12 X AA2.03 - Failures of flow control valve 3.1 1

or controller

000025 Loss of RHR System 14 X AK2.05 - Reactor building sump 2.6 1

000026 Loss of Component Cooling Water 1 X AK3.03 - Guidance actions contained in 4.0 1

8 EOP for Loss of CCW

000027 Pressurizer Pressure Control System X AAl.02 - SCR-controlled heaters in 3.1 * 1

Malfunction 13 manual mode

000038 Steam Gen. Tube Rupture 13 X 2.1.3 - Knowledge of shift turnover 3.0 1

practices.

000040 Steam Line Rupture - Excessive X AKl.03 - RCS shrink and consequent 3.8 1

Heat Transfer 1 4 depressurization

( )0055 Station Blackout 16 X 2.4.29 - Knowledge of the emergency 2.6 1

plan.

000056 Loss of Off-site Power 16 X AKl.03 - Definition of subcooling: use 3.1* 1

of steam tables to determine it

000058 Loss of DC Power 16 X AKl.Ol - Battery charger equipment 2.8 1

and instrumentation

000062 Loss of Nuclear Svc Water 14 X AAl.Ol - Nuclear service water 3.1 1

temperature indications

W IE04 LOCA Outside Containment 13 X 2.4.48 - Ability to interpret control 3.5 1

room indications to verify the status and

operation of system, and understand

how operator actions and directives

affect plant and system conditions.

W/E05 Inadequate Heat Transfer - Loss of X EK3.1 - Facility operating 3.4 1

Secondary Heat Sink 14 characteristics during transient

conditions, including coolant chemistry

and the effects of temperature, pressure,

and reactivity changes and operating

limitations and reasons for these

operating characteristics

I

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2

I

':/APE # / Name / Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points

W/E 11 Loss of Emergency Coolant Recirc. / X EK2.2 - Facility's heat removal systems, 3.9 1

4 including primary coolant, emergency

coolant, the decay heat removal

systems, and relations between the

proper operation of these systems to the

operation of the facility

KIA Category Totals: 3 3 3 3 3 3 Group Point Total: 18

(

2

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2

I

7,/APE # / Name / Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points

000001 Continuous Rod Withdrawal / 1 X AK2.05 - Rod motion lights 2.9* 1

000033 Loss of Intermediate Range NI /7 X 2.4.21 - Knowledge of the parameters 3.7 1

and logic used to assess the status of

safety functions including: 1. Reactivity

control; 2. Core cooling and heat

removal; 3. Reactor coolant system

integrity; 4. Containment conditions; 5.

Radioactivity release control.

000036 Fuel Handling Accident / 8 X AKl.O 1 - Radiation exposure hazards 3.5 1

000060 Accidental Gaseous Radwaste ReI. / X AA1.02 - Ventilation system 2.9 1

9

000069 Loss of CTMT Integrity / 5 X 2.4.45 - Ability to prioritize and 3.3 1

interpret the significance of each

annunciator or alarm.

000074 Inad. Core Cooling / 4 X EK3.07 - Starting up emergency 4.0 1

feedwater and RCPs

000076 High Reactor Coolant Activity /9 X AK2.01 - Process radiation monitors 2.6 1

W/E09 Natural Circ. /4 X EA2.1 - Facility conditions and 3.1 1

selection of appropriate procedures

during abnormal and emergency

operations

(

W/E 14 Loss of CTMT Integrity / 5 X EA2.2 - Adherence to appropriate 3.3 1

procedures and operation within the

limitations in the facility's license and

amendments

KIA Category Totals: 1 2 1 1 2 2 Group Point Total: 9

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2

I

Sys/Evol # / Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points

003 Reactor Coolant Pump X K3.04 - RPS 3.9 1

003 Reactor Coolant Pump X 2.3.10 - Ability to perform 2.9 1

procedures to reduce

excessive levels of radiation

and guard against personnel

exposure.

004 Chemical and Volume Control X K5.3l - Purpose of flow 3.0* 1

path around boric acid

storage tank

004 Chemical and Volume Control X A3.08 - Reactor power 3.9 1

005 Residual Heat Removal X A4.03 - RHR temperature, 2.8* 1

PZR heaters and flow, and

nitrogen

006 Emergency Core Cooling X K1.02 - ESFAS 4.3 1

007 Pressurizer Relief/Quench X K3.0l - Containment 3.3 1

Tank

007 Pressurizer Relief/Quench X 2.1.1 - Knowledge of 3.7 1

Tank conduct of operations

requirements.

008 Component Cooling Water X K4.07 - Operation of the 2.6* 1

CCW swing-bus power

supply and its associated

breakers and controls

( J 10 Pressurizer Pressure Control X K6.03 - PZR sprays and 3.2 1

heaters

012 Reactor Protection X K4.04 - Redundancy 3.1 1

013 Engineered Safety Features X K2.0l - ESFAS/safeguards 3.6* 1

Actuation equipment control

022 Containment Cooling X A2.04 - Loss of service 2.9* 1

water

025 Ice Condenser X K5.02 - Heat transfer 2.6* 1

026 Containment Spray X K4.07 - Adequate level in 3.8* 1

containment sump for

suction (interlock)

026 Containment Spray X 2.4.48 - Ability to interpret 3.5 1

control room indications to

verify the status and

operation of system, and

understand how operator

actions and directives affect

plant and system conditions.

039 Main and Reheat Steam X Al.09 - Main steam line 2.5* 1

radiation monitors

059 Main Feedwater X A2.07 - Tripping ofMFW 3.0* 1

pump turbine

059 Main Feedwater X A4.0l - MFW turbine trip 3.1 * 1

indication

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2

I

Sys/Evol # / Name Kl K2 K3 K4 KS K6 Al A2 A3 A4 G KA Topic Imp. Points

061 Auxiliary/Emergency X K5.0l - Relationship 3.6 1

Feedwater between AFW flow and

RCS heat transfer

062 AC Electrical Distribution X Kl.02 - ED/G 4.1 1

063 DC Electrical Distribution X K2.0l - Major DC loads 2.9* 1

064 Emergency Diesel Generator X K6.08 - Fuel oil storage 3.2 1

tanks

073 Process Radiation Monitoring X Al.Ol - Radiation levels 3.2 1

076 Service Water X A2.02 - Service water 2.7 1

header pressure

076 Service Water X A4.02 - SWS valves 2.6 1

078 Instrument Air X K3.0l - Containment air 3.1 * 1

system

103 Containment X A3.0l - Containment 3.9 1

isolation

KIA Category Totals: 2 2 3 3 3 2 2 3 2 3 3 Group Point Total: 28

(

2

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah

ES - 401 Plant Systems - Tier 2 1 Group 2 Form ES-401-2

I

Sys/Evol # 1 Name Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points

011 Pressurizer Level Control X K6.05 - Function ofPZR 3.1 1

level gauges as postaccident

monitors

015 Nuclear Instrumentation X K2.01 - NIS channels, 3.3 1

components, and

interconnections

016 Non-nuclear Instrumentation X K1.l0 - CCS 3.1 * 1

017 In-core Temperature Monitor X K4.03 - Range of 3.1 1

temperature indication

045 Main Turbine Generator X K5.17 - Relationship 2.5* 1

between moderator

temperature coefficient and

boron concentration in RCS

as T IG load increases

055 Condenser Air Removal X A3.03 - Automatic diversion 2.5* 1

of CARS exhaust

068 Liquid Radwaste X A4.01 - Control board for 2.7* 1

boron recovery

071 Waste Gas Disposal X K3.04 - Ventilation system 2.7 1

075 Circulating Water X 2.2.11 - Knowledge of the 2.5 1

process for controlling

temporary changes.

086 Fire Protection X A1.01 - Fire header pressure 2.9 1

( KIA Category Totals: 1 1 1 1 1 1 1 0 1 1 1 Group Point Total: 10

I

(

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 01/13/2008

Facility: Sequoyah Form ES-401-3

Generic Catezorv KA KA Topic Points

Conduct of Operations 2.1.3 Knowledge of shift turnover practices. 3.0 I

2.1.27 Knowledge of system purpose and or function. 2.8 I

2.1.28 Knowledge of the purpose and function of major 3.2 I

system components and controls.

Category Total: 3

Equipment Control 2.2.26 Knowledge of refueling administrative 2.5 I

requirements.

2.2.33 Knowledge of control rod programming. 2.5 I

Category Total: 2

Radiation Control 2.3.2 Knowledge of facility ALARA program. 2.5 I

2.3.9 Knowledge of the process for performing a 2.5 I

containment purge.

(

2.3.10 Ability to perform procedures to reduce excessive 2.9 I

levels of radiation and guard against personnel

exposure.

Category Total: 3

Emergency Procedures/Plan 2.4.16 Knowledge of EOP implementation hierarchy and 3.0 I

coordination with other support procedures.

2.4.22 Knowledge of the bases for prioritizing safety 3.0 I

functions during abnormal/emergency operations.

Category Total: 2

Generic Total: 10

(

Form ES-401-2

Printed: 01/13/2008

SRO-Only Points

A2 G* Total

0 0 0

01 0 0 0

0 0 0

1 2 3 4

0

0 0 0 0

1. Ensure that at least two topics from every KIA category are sampled within each tier of the RO and

SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals"

in each KIA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the

table. The final point total for each group and tier may deviate by +/-1 from that specified in the

table based on NRC revisions. The final RO exam musttotal 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 ES-401, Attachment 2, for