Text

Aug/Sept 2004-301 Exam 50-261/2004-301 Final Written Outlines
	ML050950495
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Site:	Robinson
Issue date:	04/26/2004
From:	; Division of Nuclear Materials Safety II
To:	;
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	50-261/04-301
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Final Submittal

ROBINSON AUG/SEPT 2004

EXAM NO. 05000261/2004-301

AUG. 27 - SEPT. 3, 2004

FINAL SAMPLE PLANS / OUTLINES

ES-401

PWR Examination Outline

Form ES-401-2

Final

Facility:

HB Robinson

Date of Exam:

8/27/2004

RO K/A Category Points

I

Tier

Group

K K K K K K

A A

7

A G

Total

1

2

3

4

5

6

1 2

3

4

1.

1

0

4

7 16

1

18

Emergency

&

2

1 2

1

9

Abnormal

Plant

Tier

2

6

8

2

28

Evolutions

Totals

1

3

4

1

1 5

3

0

4

2

28

2.

Plant

2

1 0

0

1

1 2

2

1 0

10

Systems

Tier

4

2

6

5

2

5

2

38

Totals

3. Generic Knowledge and

1

2

3

4

9

Abilities Categories

2

3

2

Note:

1.

Ensure that at least two topics from every K/A category are sampled within each tier of

the RO outline (i.e., the "Tier Totals" in each K/A category shall not be less than two).

Refer to Section D. 1.c for additional guidance regarding SRO sampling.

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.

Select topics from many systems and evolutions; avoid selecting more than two K/A

topics from a given system or evolution unless they relate to plant-specific priorities.

4.

Systems/evolutions within each group are identified on the associated outline.

5.

The shaded areas are not applicable to the category/tier.

6.*

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. The SRO

K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7.

On the following pages, enter the K/A numbers, a brief description of each topic, the

topics' importance ratings (IR) 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; summarize all the SRO-only knowledge and non-A2 ability categories in the

columns labeled "K" and "A". Use duplicate pages for RO and SRO-only exams.

8.

For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on

Form ES-401-3.

9.

Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate

K/A statements.

NUREG-1021, Draft Revision 9

1

ES-401

HB Robinson

Form ES-401-2

NRC Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier I Group 1

EIAPE #/ Name Safety Function

IG

K1

K2

K3

A1 IA21 NumberT

K/A Topic(s)

Imp. 1Q#1

0

Ability to determine or interpret the following as they apply

40

76

009 / Small Break LOCA

X

EA2.04

to a small break LOCA: PZR level

Emergency Procedures / Plan Ability to perform without

027 / Pressurizer Pressure Control System Malfunction

X

24.49

reference to procedures those actions that require

40

77

3

immediate operation of system components and controls.

ATWS 11 EA2 09

Ability to determine or interpret the following as they apply

45

029 i ATWS / 1

to a ATWS: Occurrence of a main turbine/reactor trip

Emergency Procedures / Plan Ability to verify system

056 / Loss of Off-site Power / 6

X

2,450

alarm setpoints and operate controls identified in the

33

79

alarm response manual.

Ability to determine and interpret the following as they

062 / Loss of Nuclear Svc. Water / 4

X

AA2.02

apply to the Loss of Nuclear Service Water: The cause of

3.6

80

possible CCW loss

E04 / LOCA Outside Containment / 3

2A 2.128

Conduct of Operations: Knowledge of the purpose and

33

81

nX

1

function of major system components and controls.

E05 / Inadequate Heat Transfer - Loss of Secondary

X

2 1 .27

Conduct of Operations: Knowledge of system purpose

29

82

Heat Sink / 4

and or function.

007 / Reactor Trip - Stabilization - Recovery/ 1

X

2.1.20

Conduct of operations: Ability to execute procedure steps.

4.3

39

Ability to determine and interpret the following as they

008 / Pressurizer Vapor Space Accident /3

X

AA2.23

apply to the Pressuizer Vapor Space Accident: Criteria

3.6

40

for throttling high-pressure injection after a small LOCA

009 1 Small Break LOCA / 3

XA1.17

Ability to operate and monitor the following as they apply

34

41

009 Smll rea LOC /

EA.17

to a small break LOCA: PRT

Knowledge of the reasons for the following responses as

oil / Large Break LOCA / 3

X

EK3.03

the apply to the Large Break LOCA: Starting auxiliary feed

4.1

42

pumps and flow, ED/G, and service water pumps

Ability to operate and / or monitor the following as they

015 / 17 / RCP Malfunctions / 4

XAM

.22

apply to the Reactor Coolant Pump Malfunctions (Loss of

4.0

43

RC Flow): RCP seal failure/malfunction

Ability to operate and / or monitor the following as they

025 / Loss of RHR System/4

x

AAI.20

apply to the Loss of Residual Heat Removal System: HPI

2.6

pump control switch, indicators, ammeter running lights,

and flow meter

Ability to determine and interpret the following as they

026 / Loss of Component Cooling Water / 8

X

AA2.02

apply to the Loss of Component Cooling Water: The

2.9

45

cause of possible CCW loss

I

NUREG

Draft Revision 9

ES-401

HB Robinson

Form ES-401-2

NRC Written Examination Outline

Emergency and Abnormal Plant Evolutions- Tier 1 Group 1

I/PE

/ Name Safety Function

GKA1

A2

Number

K/A Topic(s)

Imp.

Q#

Ability to determine and interpret the following as they

X

AA2.10

apply to the Pressurizer Pressure Control Malfunctions:

3.3

46

7 /Pressurizer

heater energizedldeenergized condition

029 / ATWS / 1

X

EAl

Ability to operate and monitor the following as they apply

4.0

47

029/ ARNS/ 1X

E1.0

to a ATWS: Manual rod control

038/Steam Gen. Tube Rupture / 3

X

EAl.19

Ability to operate and monitor the following as they apply

3.4

48

038 Stam en. ubeRupure

3

EA.19

to a SGTR: MFW System status indicator

Ability to operate and / or monitor the following as they

040 / Steam Line Rupture - Excessive Heat Transfer /4

X

AA1.13

apply to the Steam Line Rupture: Steam line isolation

4.2

49

valve indications

Ability to determine and interpret the following as they

054/ Loss of Main Feedwater / 4

X

AA2.08

apply to the Loss of Main Feedwater (MFW): Steam flow-

2.9

50

feed trend recorder

056/ Loss of Oft-site Power/S 6

AA2.56

Ability to determine and interpret the following as they

3B

51

06Looff-tPw/

A

5

apply to the Loss of Offsite Power: RCS T-ave

Ability to determine and interpret the following as they

0571 Loss of Vital AC Inst. Bus / 6

X

AA2.17

apply to the Loss of Vital AC Instrument Bus: System and

3.1

52

component status, using local or remote controls

Knowledge of the reasons for the following responses as

058 / Loss of DC Power / 6

X

AK3.02

they apply to the Loss of DC Power: Actions contained in

4.0

53

EOP for loss of do power

Ability to operate and / or monitor the following as they

Nclear Svc. Water /4

X

A

.07

apply to the Loss of Nuclear Service Water: Flow rates to

2.9

the components and systems that are serviced by the

CCWS; interactions among the components

Knowledge of the reasons for the following responses as

065 / Loss of Instrument Air / S

AK3.03

they apply to the Loss of Instrument Air: Knowing effects

2.9

55

on plant operation of isolating certain equipment from

instrument air

Knowledge of the reasons for the following responses as

they apply to the (Loss of Secondary Heat Sink) RO or

E05 I Inadequate Heat Transfer - Loss of Secondary

X

EK3.4

SRO function as a within the control room team as56

Heat Sink / 4

appropriate to the assigned position, in such a way that

procedures are adhered to and the limitations in the

facilities license and amendments are not violated.

KA Category Point Totals:

5

0

4

7

9

Group Point Total:

25

NUREG-4

-), Draft Revision 9

)

I ES-401

HB Robinson

Form ES-401-2 I

NRC Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 1 Group 2

I

EIAPE # / Name Safety Function

I G I K1 I K2 I K3 I Al I A2

Number

K/A Topic(s)

Imp.

Q#

2.46

Emergency Procedures / Plan Knowledge symptom based

40

83

036 /Fuel Handling Accident / 8

-X

2.46

EOP mitigation strategies.

Ability to determine and interpret the following as they

E

EA2

apply to the (Degraded Core Cooling) Facility conditions

42

84

E06

rinad Core Cooling 4

Eand

selection of appropriate procedures during abnormal

and emergency operations.

Emergency Procedures / Plan Knowledge of EOP

E03 I Post-LOCA Cooldown/Depressurization.

4

x

24 16

implementation hierarchy and coordination with other

40

85

support procedures

Ability to determine and interpret the following as they

El4 4! Loss of CTMT Integrity / 5

X

EA21

apply to the (High Containment Pressure) Facility

38

86

conditions and selection of appropriate procedures during

abnormal and emergency operations.

Ability to determine and interpret the following as they

apply to the (High Containment Radiation) Facility

2.9

73

E16 I High Containment Radiation 9

Econditions

and selection of appropriate procedures during

abnormal and emergency operations.

Knowledge of the interrelations between the Continuous

001 / Continuous Rod Withdrawal /1

X

AK2.01

Rod Withdrawal and the following: Rod bank step

2.9

57

counters

Knowledge of the operational implications of the following

003 / Dropped Control Rod / 1

x

AK1.21

concepts as they apply to Dropped Control Rod: Delta

2.7

58

flux (Al)

Knowledge of the reasons for the following responses as

005 / Inoperable/Stuck Control Rod / 1

x

AK3.02

they apply to the Inoperable / Stuck Control Rod: Rod

3.6

59

insertion limits

024/ Emergency Boration I I

x

AA2.04

Ability to determine and interpret the following as they

3.4

60

apply to the Emergency Boration: Availability of BWST

Conduct of Operations: Ability to perform specific system

028 / Pressurizer Level Malfunction / 2

x

2.1.23

and integrated plant procedures during all modes of plant

3.9

61

operation.

Ability to operate and / or monitor the following as they

068 / Control Room Evac. / 8

X

AA1.02

apply to the Control Room Evacuation: AFW emergency

4.3

62

pump

iI!!M

E02 / Rediagnosis & SI Termination / 3

x

EK1.2

Knowledge of the operational implications or the following

concepts as they apply to the (SI Termination) Normal,

abnormal and emergency operating procedures

associated with (SI Termination).

3.4

63

I

................ )......~

NUREGSý,

Draft Revision 9

ES-401

HB Robinson

Form ES-401-2

NRC Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 1 Group 2

E/ # / Narne Safety Function

G K1K3A1

A2

Number

K/A Topic(s)

Imp.

Q#

Knowledge of the interrelations between the (Degraded

Core Cooling) and the following: Components, and

E06 / Inad. Core Cooling /4

x

EK21

functions of control and safety systems, including

3.6

64

instrumentation, signals, interlocks, failure modes, and

automatic and manual features.

Knowledge of the reasons for the following responses as

they apply to the (Steam Generator Overpressure)

Facility operating characteristics during transient

E13 / Steam Generator Over-pressure /4

X

EK3.1

conditions, including coolant chemistry and the effects of

2.9

65

temperature, pressure, and reactivity changes and

operating limitations and reasons for these operating

characteristics.

K/A Category Point Total:

2

1

14

NUREG-'

Draft Revision 9

5

ES-401

HB Robinson

Form ES-401-2

NRC Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 2 Group 1

FSystem #/Name

G

KI

K2

K3 I K4 I K5

K6

Al

A2

A3

A4

Number

K/A Topics

Imp.

Q#

I

Ability to (a) predict the impacts of the following

malfunctions or operations on the ECCS: and (b) based

006 Emergency Core Cooling

X

A2 12

on those predictions, use procedures to correct, control.

48

86

or mitigate the consequences of those malfunctions or

operations: Conditions requiring actuation of ECCS

Emergency Procedures ! Plan Knowledge of

012 Reactor Protection

x

2.431

annunciators alarms and indications, and use of the

3.4

89

response instructions.

Ability to (a) predict the impacts of the following

malfunctions or operations on the CCS: and (b) based

l

A2 03

on those predictions, use procedures to correct, control.

022 Containment Cooling

A2 03

or mitigate the consequences of those malfunctions or

10

90

operations: Fan motor thermal overload/high-speed

operation

Emergency Procedures/Plan: Ability to verify system

010 Pressurizer Pressure Control

X

2 450

alarm setpoints and operate controls identified in the

33

91

alarm response manual.

Knowledge of the effect that a loss or malfunction of the

003 Reactor Coolant Pump

K3.03

RCPS will have on the following: Feedwater and

2.8

1

emergency feedwater

0

A407

Ability to manually operate and/or monitor in the control

2.6

2

3Reator Coolant Pump

room: RCP seal bypass

004 Chemical and Volume

K

Knowledge of bus power supplies to the following:

33

3

Control

X

Charging Pumps

Ability to (a) predict the impacts of the following

malfunctions or operations on the RHRS, and (b) based

005 Residual Heat Removal

X

A2.04

on those predictions, use procedures to correct, control,

2.9

4

or mitigate the consequences of those malfunctions or

operations: RHR valve malfunction

Knowledge of the physical connections and/or cause-

005 Residual Heat Removal

X

K1.01

effect relationships between the RHRS and the following

3.2

5

systems: CCWS

Ability to predict and/or monitor changes in parameters

006 Emergency Core Cooling

Al 6

(to prevent exceeding design limits) associated with

3.6

6

operating the ECCS controls including: Subcooling

margin

007 Pressurizer Relief/Quenich

X

A4.1 0

Ability to manually operate and/or monitor in the control

Tan

room: Recognition of leaking PORV/code safety

3.6

7

Tank

__________________________

008 Component Cooling Water

X

K2.02

Knowledge of bus power supplies to the following: cOW

3.0

8

1W

pump, including emergency backup

-

NUREG

, Draft Revision 9

ES-401

HB Robinson

Form ES-401-2

NRC Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 2 Group 1

system #/Name

IIK14

K5

K6 I A I A-2 I A3

A4u

-Number

KIA Topics

Imp

Q#

Ability to (a) predict the impacts of the following

malfunctions or operations on the CCWS, and (b) based

008 Component Cooling Water

X

A2.03

on those predictions, use procedures to correct, control,

3.0

9

or mitigate the consequences of those malfunctions or

operations: HigMow CCW temperature

Ability to predict and/or monitor changes in parameters

010 Pressurizer Pressure Control

XAl.04

(to prevent exceeding design limits) associated with

operating the PZR PCS controls including: Effects of

36

10

temperature change during solid operation

012 Reactor Protection

x

K3.02

Knowledge of the effect that a loss or malfunction of the

31

11

I RPS will have on the following: T/G

013 Engineered Safety Features

xKnowledge

of the effect that a loss or malfunction of the

Actuation

X

K3,03

ESFAS will have on the following: Containment

4.3

12

Ability to predict and/or monitor changes in parameters

022 Containment Cooling

X

A1 04

(to prevent exceeding design limits) associated with

32

13

operating the CCS controls including: Cooling water flow

Ability to predict and/or monitor changes in parameters

026 Containment Spray

X

Al.011

(to prevent exceeding design limits) associated with

3.9

14

operating the CSS controls including: Containment

pressure

Ability to predict and/or monitor changes in parameters

039 Main and Reheat Steam

X

A1.06

(to prevent exceeding design limits) associated with

3.0

15

operating the MRSS controls including: Main steam

pressure

Knowledge of the physical connections and/or cause-

039 Main and Reheat Steam

X

K1.09

effect relationships between the MRSS and the following

2.7

16

systems: RMS

Knowledge of the physical connections and/or cause-

056 Condensate

X

K1 .03

effect relationships between the Condensate System

2.6

17

and the following systems: MFW

Knowledge of the effect that a loss or malfunction of the

3.6

16

059 ain eedwter

3.04

MFW will have on the following: RCS

Knowledge of the effect of a loss or malfunction of the

061 Auxildary/Emergency

X

K6.02

following will have on the AFW components: Pumps

2.6

19

FeedwaterI

I

[

Knowledge of ac distribution system design feature(s)

062 AC Electrical Distribution

x

K4.02

and/or interlock(s) which provide for the following: Circuit

2.5

20

breaker automatic trips

063 DCElectrical Dist

n

K.01

Knowledge of bus power supplies to the following: Major

29

21

03DC ElcrclDistribution

X201

dc loads29

1

NUREG-' -'1, Draft Revision 9

7

ES-401

HB Robinson

Form ES-401-2

NRC Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 2 Group 1

iSystem *

KA Topics

Ability to (a) predict the impacts of the following

malfunctions or operations on the ED/G system; and (b)

06

based on those predictions, use procedures to correct,

2.6

22

Emergency Diesel Generator

X

A2.13

control, or mitigate the consequences of those

malfunctions or operations: Consequences of opening

auxiliary feeder bus (ED/G sub supply)

Knowledge of the operational implications as they apply

073 Process Radiation Monitoring

X

K5.02

to concepts as they apply to the PRM system: Radiation

2.5

23

intensity changes with source distance

073 Process Radiation Monitoring

x

A4,02

Ability to manually operate and/or monitor in the control

37

24

room Radiation monitoring system control panel

Conduct of Operations: Ability to recognize indications

076 Service Water

X

2.1.33

for system operating parameters which are entry-level

3.4

25

conditions for technical specifications.

078 Instrument Air

X

K202

Knowledge of bus power supplies to the following

3.3

26

Emergency air compressor

078 Instrument Air

X

A4.01

Ability to manually operate and/or monitor in the control

3.1

27

room: Pressure gauges

103 Containment

X

2.1.2

Conduct of Operations: Knowledge of operator

3.0

28

responsibilities during all modes of plant operation.

K/A Category Point Totals:

4

1

5

0

4

Group Point Tal

32

NUREG- 4 'I1, Draft Revision 9

8

ES-401

HB Robinson

Form ES-401-2

NRC Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 2 Group 2

System #/Name

G

KI

1K2

K3

K4

K5 I K6 I Al 172

A3

A4

Number I

KATopics

Imp.

Q#

Equipment Control Knowledge of bases in technical

029 Containment Purge

X

2 2 25

specifications for limiting conditions for operations and

37

92

safety limits.

Conduct of Operations: Ability to perform specific

034 Fuel Handling Equipment

X

21 23

system and integrated plant procedures during all

4.0

93

modes of plant operation

Knowledge of the operational Implications of the

002 Reactor Coolant

K5

following concepts as they apply to the RCS:

Relationship of pressure and temperature for water

37

29

saturation and subcooling conditions

Ability to predict and/or monitor changes in parameters

nIndication

X

A1.04

(to prevent exceeding design limits) associated with

014 Rod position

operating the RPIS controls, including: Axial and radial

3.5

30

power distribution

015 Nuclear Instrumentation

X

A4.03

Ability to manually operate and/or monitor in the control

3.8

31

Ability to monitor automatic operation of the N NIS,

016 Non-nuclear Instirumentation

X

A3.01

including: Automatic selection of NNIS inputs to control

2.9

32

systems

I

Knowledge of design feature(s) and/or interlock(s)

029 Containment Purge

K4.03

which provide for the following: Automatic purge

3.2

33

isolation

Ability to (a) predict the impacts of the following

malfunctions or operations on the Fuel Handling

034 Fuel Handling Equipment

2.01

System ; and (b) based on those predictions, use

3.6

34

procedures to correct, control, or mitigate the

consequences of those malfunctions or operations:

Dropped fuel element

Knowledge of the physical connections and/or cause-

035 Steam Generator

K1.01

effect relationships between the S/GS and the following

4.2

35

systems: MFW/AFW systems

Knowledge of the effect of a loss or malfunction on the

041 Steam Dump/Turbine Bypass

X

K6.03

following will have on the SDS: Controller and

2.7

36

Control

positioners, including ICS, S/G, CRDS

0G

A3.0

Ability to monitor automatic operation of the MT/G

045 Main Turbine Generator

A3F05

system, including: Electrohydraulic control

2.6

37

NUREG-S,,

Draft Revision 9

ES-401

HB Robinson

Form ES-401-2

NRC Written Examination Outline

Emergency and Abnormal Plant Evolutions - Tier 2 Group 2

System #/Name

K

K1

K2

K3

K4

K5

K6

Al

A2

A3

A4

Number

K/A Topics

Imp.

Q#

Ability to (a) predict the impacts of the following

malfunctions or operations on the Fire Protection

086 Fire Protection

X

A2.01

System; and (b) based on those predictions, use

2,9

3

procedures to correct, control, or mitigate the

consequences of those malfunctions or operations:

Manual shutdown of the FPS

KJA Category Point Totals:

2

1

0

1

2

1

Group Point Total:

12

NUREG-1n'01, Draft Revision 9

10

ES-401

Generic Knowledge and Abilities Outline ('ier3)

Form ES-401-3]

Facility:

HB Robinson

Date of Exam:

8/27/2004

RO

SRO-Only

ML050950495

Text

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