Text

February 50-325/2003-301 Exam Draft Ro/Sro Written Exam Sample Outlines
	ML030840253
Person / Time
Site:	Brunswick
Issue date:	09/09/2002
From:	Ernstes M; Operator Licensing and Human Performance Branch
To:	Keenan J; Carolina Power & Light Co
References
	50-324/03-301, 50-325/03-301
	Download: ML030840253 (26)
	v • d • e

Draft Submittal

BRUNSWICK EXAM

50-2003-301

50-325 & 50-324

FEBRUARY 10 - 14 & 19, 2003

1.

Written Exam Sample outlines (140

BWR RO Examination Outline

Facility: Brunswick

Date of Exam:

2/19/03

Exam Level: RO

K/A Category Points

Tier

Group

-

-*

Point

K

A

G

Total

1_2_3_4_5_6

1

2

3

4

1.

1

2

3

2

13

Emergency &

Abnormal

2

4

3

Plant

3

1

4

Evolutions

Tier

7

6

5

36

Totals

1

3

2

5

2

3

-2

1

3

29

2.

P2an

2

3

1

3

2

1

19

Plant

Systems

3

1

3

Tier

5

6

3

4

5

4

51

1 Totals

I

__

3. Generic Knowledge and Abilities

_ Cat 1

_Cat

2

Cat 3

Cat 4

/

13

L3

3

2

5

Note:

1.

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

each tier (i.e., the "Tier Totals" in each K/A 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 exam must total 100 points.

3.

Select topics from many systems; avoid selecting more than two or three K/A

topics from a given system 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 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.

7.

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

topic, the topics' importance ratings for the SRO license level, and the point

totals for each system and category. K/As below 2.5 should be justified on

the basis of plant-specific priorities. Enter the tier totals for each category in

the table above.

Form ES-401-2 (R8, $1)

ES-401

BWR RO Examination Outline

Form ES-401-2 (R8, $1)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 1

E/APE # / Name / Safety Function

K

A

G

K/A Topic(s)

Imp.

Poin

1

2

3

1

2

1

ts

295005 Main Turbine Generator Trip /3

05

AA1.05 Ability to operate and/or monitor the following as they

3.6/3.6

1

apply to MAIN TURBINE GENERATOR TRIP: Reactor/turbine

pressure regulating system.

295006 SCRAM / 1

06

AA2.06 Ability to determine and/or interpret the following as they

3.5/3.8

1

apply to SCRAM: Cause of reactor SCRAM. (RO ONLY)

295007 High Reactor Pressure / 3

06

AK3.06 Knowledge of the reasons for the following responses as

3.7/3.8

1

they apply to HIGH REACTOR PRESSURE : Reactor/turbine

pressure regulating system operation.

295009 Low Reactor Water Level /2

05

AK1.05 Knowledge of the operational implications of the following

3.3/3.4

11

concepts as they apply to LOW REACTOR WATER LEVEL:

Natural circulation.

295010 High Drywell Pressure /5

01

AA1.01 Ability to operate and/or monitor the following as they

3.4/3.5

1

apply to HIGH DRYWELL PRESSURE: Safety/relief valve

operation.

295014 Inadvertent Reactivity Addition / 1

03

AK2.03 Knowledge of the interrelations between INADVERTENT

3.3/3.4

'1

REACTIVITY ADDITION and the following: Fuel temperature.

295015 Incomplete SCRAM / 1

02

AK1.02 Knowledge of the operational implications of the following

3.914.1

1

concepts as they apply to INCOMPLETE SCRAM: Cooldown

effects on reactor power.

295024 High Drywell Pressure / 5

01

EK3.01 Knowledge of the reasons for the following responses as

3.6/4.0

1

they apply to HIGH DRYWELL PRESSURE : Drywell spray

operation.

295025 High Reactor Pressure / 3

02

2.1.20

EA1.02 Ability to operate and/or monitor the following as they

3.8/3.8

1

apply to HIGH REACTOR PRESSURE: Reactor/turbine pressure

rejir uatinav

sytem.

G3.1.20 Ability to execute procedure steps. (RO ONLY)

4.3/4.2

1

295031 Reactor Low Water Level / 2

2.1.1

G2.1.1 Knowledge of conduct of operations requirements.

3.7/3.8

1

295037 SCRAM Condition Present and Power

05

EK2.05 Knowledge of the interrelations between SCRAM

4.0/4.1

1

Above APRM Downscale or Unknown / 1

CONDITION PRESENT AND REACTOR POWER ABOVE APRM

DOWNSCALE OR UNKNOWN and the following: CRD hydraulic

system.

500000 High Containment Hydrogen Cone. / 5

01

EA2.01 Ability to determine and / or inter pret the following as they

3.1/3.5

1

apply to HIGH PRIMARY CONTAINMENT HYDROGEN

CONCENTRATIONS: Hydrogen monitoring system availability.

K/A Category Totals:

121212 13121 2

GroupPointTotal:

13

ES-401

BWR RO Examination Outline

Form ES-401-2 (R8, $1)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 2

E/APE # / Name / Safety Function

K1

K2

K3

Al

A2

G

K/A Topic(s)

Imp.

Point

s

295001 Partial or Complete Loss of Forced Core

02

AK2.02 Knowledge of the interrelations between PARTIAL OR

3.213.3

1

Flow Circulation / 1 & 4

COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION and

the following: Nuclear boiler instrumentation

295002 Loss of Main Condenser Vacuum / 3

08

02

1K2.08 Knowledge of the interrelations between LOSS OF

3.1/3.2

2

MAINCONDENSER VACUUM and the following: Condenser

circulating water system

3.4/3.4

AK3.02 Knowledge of the reasons for the following responses as

they apply to LOSS OF MAIN CONDENSER VACUUM : Turbine

trip.

295003 Partial or Complete Loss of AC Pwr /6

02

-

AK1.02Knowledge of the operational implications fo the following

3.1/3.4

1

concepts as they appl to PARTIAL OR COMPLETE LOSS OF

A.C. POWER: Load shedding.

295004 Partial or Complete Loss of DC Pwr /6

02

AA2.02 Ability to determine and/or inter ret the following as they

3.5/3.9

1

apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Extent

o partial or complete loss of D. C. power.

295008 High Reactor Water Level / 2

04

AK3.04 Knowledge of the reasons for the following responses as

3.3/3.5

1

they apply to HIGH REACTOR WATER LEVEL: Reactor feed

pump tnp: Plant-Specific

295011 High CTMT Temperature / 5

(Mark II Containment Only) - N/A

295012 High Drywell Temperature /5

02

AA1.02 Ability to operate and/or monitor the following as they apply

3.8/3.8

1

to HIGH DRWELL TEMPERATURE: Drywell cooling system.

295013 High Suppression Pool Temp. /5

03

AKI.03 Knowledge of the operational implications of the following

3.0/3.3

1

concepts as they apply to HIGH SUPPRESSION POOL

TEMPERATURE: Localized heating.

295016 Control Room Abandonment / 7

01

AK3.01 Knowledge of the reasons for the following responses as

4-1/4.2

1

the

ly to CONTROL ROOM ABANDONMENT: Reactor

295017 High Off-site Release Rate / 9

2.1.2

G2.1.2 Knowledge of operator responsibilities during all modes of

3.0/4.0

1

plant operation.

295018 Partial or Complete Loss of CCW / 8

295019 Part. or Comp. Loss of Inst. Air / 8

01

AA1.01 Ability to operate and/or monitor the following as they apply

3.5/3.3

1

to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:

Backup air supply.

295020 Inadvertent Cont. Isolation / 5 & 7

06

AA2.06 Ability to determine and/or interpret the following as they

3.4/3.8

-1

apply to INADVERTENT CONTAINMENT ISOLATION: Cause of

isolation.

295022 Loss of CRD Pumps / 1

2.1.30

2.1.30 Ability to locate and operate components / including local

3.9/3.4

1

i___

__

controls.

295026 High Suppression Pool Water Temp. / 5

04

EK2.04 Knowledge of the interrelations between SUPPRESSION

2.5/2.8

1

POOL HIGH WATER TEMPERATURE and the following:

SPDS/ERIS/CRIDSIGDS.

295027 High Containment Temperature / 5

(Mark Ill Containment Only) - N/A

295028 High Drywell Temperature / 5

01

EK1.01 Knowledge of the operational implications of the following

3.5/3.7

1

concepts as they apply to HIGH DRYWELL TEMPERATURE:

Reactor water level measurement.

295029 High Suppression Pool Water Level / 5

1

Not selected.

295030 Low Suppression Pool Water Level / 5

05

EAI.05 Ability to operate and/or monitor the following as they apply

3.5/3.5

1

to LOW SUPPRESSION POOL WATER LEVEL: HPCI.

295033 High Sec. Cont. Area Rad. Levels / 9

2.3.2

G2.3.2 Knowledge of facility ALARA program. (RO ONLY)

2.5/2.9

1

295034 Sec. Cont. Ventilation High Rad. / 9

02

EKI.02 Knowledge of the operational implications of the following

4.1/4.4

1

concepts as they apply to SECONDARY CONTAINMENT

VENT ILATION HIGH RADIATION: Radiation releases

295038 High Off-site Release Rate / 9

Not selected.

600000 Plant Fire On Site / 8

02

AA2.02 Ability to determine and interpret the following as they

2.8/2.9

1

1 _apply

to PLANT FIRE ON SITE: Damper position. (RO ONLY)

K/A Category Point Totals:

14131313 13

13

JGroup Point Total:

19

ES-401

BWR RO Examination Outline

Form ES-401-2 (R8, Si)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 3

E/APE # / Name / Safety Function

K1

K2

K3

Al

A2

G

K/A Topic(s)

Imp.

Point

s

295021 Loss of Shutdown Cooling / 4

01

AK2.01 Knowledge of the interrelations-between LOSS OF SHUTDOWN

3.6/3.7

1

COOLING and the following: Reactor water temperature.

295023 Refueling Accidents / 8

02

AA2.02 Ability to determine and/or interpret the following as they apply

3.4/3.7

1

to REFUELING ACCIDENTS : Fuel pool level.

295032 High Secondary Containment Area

01

EK3.01 Knowledge of the reasons for the following responses as they

3.5/3.8

1

Temperature / 5

apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE:

Emergency/normal depressurization

295035 Secondary Containment High Differential

01

EKI.01 Knowledge of the operational implications of the following

3.9/4.2

1

Pressure /5

concepts as they apply to SECONDARY CONTAINMENT HIGH

DIFFERENTIAL PRESSURE: Secondary containment integrity.

(RO ONLY)

295036 Secondary Containment High Sump/Area

Not selected.

Water Level / 5

K/A Category Point Totals:

J111 J1 JjIl

Group Point Total:

1

ES-401

BWR RO Examination Outline

Form ES-401-2 (R8, Si)

Plant Systems - Tier 2/Group 1

System # I Name

K1

K2

K3

K4

K5

K6

A1

A2

A3

A4

G

K/A Topic(s)

Imp.

Point

s

201001 CRD Hydraulic

01

K1.01 Knowledge of the physical

3.1/3.1

1

connections and/or cause- effect

relationships between CONTROL ROD

DRIVE HYDRAULIC SYSTEM and the

following: Condensate system.

(RO ONLY)

201002 RMCS

01

02

03

K3.01 Knowled e of the effect that a

3.4/3.4

1

loss or malfunction of the REACTOR

MANUAL CONTROL SYSTEM will

have on following: Ability to move

control rods

RO ONLe)

3.5/3.5

1

4002 K~nyowIede of REACTOR

MANUAL CON

OL SYSTEM design

feature(s) and/or interlocks which

E rovide for the following: Control rod

locks

3.2/3.2

1

A3.03 Ability to monitor automatic

operations of the REACTOR MANUAL

CONTROL SYSTEM including: Rod

drift alarm.

201005 RCIS

Applies to BWR 6 - N/A

202002 Recirculation Flow Control

06

K4.06 Knowledge of RECIRCULATION

3.1/3.1

1

FLOW CONTROL SYSTEM design

feature(s) and/or interlocks which

provide for the following: Recirculation

pump NPSH.

203000 RHR/LPCI: Injection Mode

04

A1.04 Ability to predict and/or monitor

3.6/3.6

1

change in arameters associated with

operating 4h RHLPCI: INJECTION

MODE ontrols including: System

pressure.

206000 HPCI

08

K5.08 Knowled e of the operational

3.0/3.2

1

implications of tbe followin concepts

as they applyto HIGH PRESSUR

COOLANT INJECTION SYSTEM:

Vacuum breaker operation.

207000 Isolation (Emerg.) Condenser

Not applicable to Brunswick.

209001 LPCS

03

K2.03 Knowledge of the electrical

2.9/3.1

1

power supplies o the following:

Initiation (ogie.

209002 HPCS

Not applicable to Brunswick.

211000 SLC

08

A3.08 Ability to monitor automatic

4.2./4.2

1

operations of the STANDBY LIQUID

CONTROL SYSTEM includinq:

I

System initiation: Plant-Specific

212000 RPS

04

2.1.27

K6.04 Knowledge of the effect that a

2.8/3.1

loss or malfuncfion of the followingwill

have on the REACTOR PROTECTION

SYSTEM: D.C. electrical distribution

G2.1.27 Knowled

of system purpose

2.8/2.9

and or function. (RO ONLY)

215003 IRM

07

A4.07 Ability to manually operate

3.6/3.6

and/or monitor in the control room:

Verification of proper functioning I

operability.

(RO ONLY)

215004 SRM

2.2.1

G2.2.1 Abilit to perform pre-startup

3.7/3.6

procedures or the facility / including

q those controls associated

with ,p1an equipment that could affect

reactivity.

215005 APRM / LPRM

06

A4.06 Ability to manually operate

3.6/3.8

and/or monitor in the control room:

Verification of proper functioning /

operability.

216000 Nuclear Boiler Instrumentation

01

K2.01 Knowledge of electrical power

2.8/2.&

supplies to the following: Analog trip

system.

217000 RCIC

01

2.1.28

K1.01 Knowledge of the physical

3.5/3.5

connections and/or cause-effect

relationshi s between REACTOR

CORE ISOLATION COOLING

SYSTEM (RCIC) and the following:

Condensate storage and transfer

ws

stem.

3.2/3.3

G2.1.28 Knowledge of the purpose and

function of major system components

and controls.

218000 ADS

02

A4.02 Ability to manually operate

4.2/4.2

and/or monitor in the control room:

ADS logic initiation.

223001 Primary CTMT and Auxiliaries

03

K4.03 Knowledge of PRIMARY

3.7/3.8

CONTAINMENT SYSTEM AND

AUXILIARIES design feature(s) and/or

interlocks which provide for the

following: Containment/drywell

isolation. (RO Only)

223002 PCIS/Nuclear Steam Supply

07

02

K1.07 Knowledge of the physical

3.4/3.6

Shutoff

connections and/or cause-effect

relationships between PRIMARY

CONTAINMENT ISOLATION

SYSTEM/NUCLEAR STEAM SUPPLY

SHUT-OFF and the following: Reactor

core isolation cooling.

A3.02 Ability to monitor automatic

3.5/35

operation of the PRIMARY

CONTAINMENT ISOLATION

SYSTEM/NUCLEAR STEAM SUPPLY

I SHUT-OFF including: valve closure.

I

239002 SRVs

05

01

K6.05 Knowledge of the effect that a

3.0/3.2

2

loss or malfunction of the following will

have on the RELIEF/SAFETY

VALVES: Discharge line vacuum

breaker

A1.01 Ability to mointor automatic

3.3/3.4

actions of the RELIEF/SAFETY

VALVES including: Tail pipe

temperature

241000 Reactor/Turbine Pressure

05

K6.05 Knowledqe of the effect that a

3.4/3.4

1

Regulator

loss or malfunction of the followins will

have on the REACTOR/TURBINE

PRESSURE REGULATING SYSTEM:

Condenser vacuum.

259001 Reactor Feedwater

07

A2.07 Ability to(a) predict the impacts

3.7/3.8

of the following on the REACTOR

FEEDWATER SYSTEM; and (b) based

on those predictions, use proccdures

to correct, control, or mitiqate the

consequences of those abnormal

conditions or operations: Reactor

water level control malfunctions.

261000 SGTS

04

01

K3.04 Knowledqe of the effect that a

3.1/3.1

1

loss or malfunction of the STANDBY

GAS TREATMENT SYSTEM will have

on the following: High pressure

coolannt injection system.

K4.01 Knowled e of STANDBY GAS

TREATMENT &STEM design

3.7/3.8

1

feature(s) and/or interlocks which

provide for the followins: Automatic

system initiation. (RO Only)

264000 EDGs

05

06

K4.05 Knowled e of EMERGENCY

3.2/3.5

2

GENERATORS(DIESELUJET) design

feature(s) and/or interlocks which

provide for the following: Laod

shedding and sequencing

KS.06 Knowledge of the op Load

3.4/3.5

shedding and sequencing erational

implications of the followina concepts

as they apply to EMERGENCY

GENERATORS (DIESEL/JET): Load

sequencing.

K/A Category Point Totals:

j3

2

12

15

12

2 2

12 13

13

3

Group Point Total:

1 28

ES-401

BWR RO Examination Outline

Form ES-401-2 (R8, S)

Plant Systems - Tier 2lGroup 2

System # / Name

K1

K2

K3

K4

K5

K6

Al

A2

A3

A4

G

K/A Topic(s)

Imp.

Points

201003 Control Rod and Drive Mechanism

01

09

K3.01 Knowledge of the effect that a

3.2/3.4

2

loss or-malfunction of the CONTROL

ROD AND DRIVE MECHANISM will

have on following: Reactor power. (RO

ONLY)

3.2/3.4

A2.09 Ability to (a) predict the impacts

of the following on the CONTROL ROD

AND DRIVE MECHANISM; and (b)

based on those predictions, use

procedures to correct, control, or

mitigate the consequences of those

abnormal conditions or operations: Low

reactor pressure

201004 RSCS

Does not apply to Browns Ferry.

201006 RWM

2.2.12

G2.2.12 Knowledge of surveillance

3.0/3.4

1

procedures. (RO ONLY)

202001 Recirculation

07

A1.07 Ability to predict and/or monitor

2.7/2.8

1

changes in parameters associated with

operating the RECIRCULATION

SYSTEM controls including:

Recirculation pump speed.

204000 RWCU

06

04

K1.06 Knowledge of the physical

2.8/2.8

2

connections and/or cause- effect

relationships between REACTOR

WATER CLEANUP SYSTEM and the

following: Main condenser

K5.04 Knowledge of the operational

2.7/2.7

implications of the following concepts as

them

applyto REACTOR WATER

CLEANUP SYSTEM: Heat exchanger

operation.

205000 Shutdown Cooling

01

A3.01 Ability to monitor automatic

3.2/3.1

1

operations of the SHUTDOWN

COOLING SYSTEM (RHR SHUTDOWN

COOLING MODE) including: Valve

operation. (RO ONLY)

214000 RPIS

01

K4.01 Knowledge of ROD POSITION

3.0/3.1

INFORMATION SYSTEM design

feature(s) and/or interlocks which

prve for the following: Reed switch

215002 RBM

04

K6.04 Knowledge of the effect that a

2.8/3.0

1

loss or malfunction of the following will

have on the ROD BLOCK MONITOR

SYSTEM: APRM reference channel.

I

_

(RO ONLY)

219000 RHR/LPCI: Torus/Pool Cooling Mode

03

A2.03 Ability to (a) predict the impacts

3.1/3.2

of the following on the RHRJLPCI:

TORUS/SUPPRESSION POOL

COOLING MODE; and (b) based on

those predictions, use procedures to

correct, control, or mitigate the

consequences of those abnormal

conditions or operations: Valve closures

226001 RHRPLPCI: CTMT Spray Mode

230000 RHR/LPCI: Torus/Pool Spray Mode

15

A2.15 Ability to (a) predict the impacts

4.0/4.1

of the following on the RHR/LPCI:

TORUS/SUPPRESSION POOL SPRAY

MODE; and (b) based on those

predictions, use procedures to correct,

control, or mitigate the consequiences of

those abnormal conditions or

operations: Loss of coolant accident.

(RO ONLY)

239001 Main and Reheat Steam

16

K3.16 Knowledge of the effect that a

3.6/3.6

loss or malfunction of the MAIN AND

REHEAT STEAM SYSTEM will have on

the following: Relief/safety valves.

245000 Main Turbine Gen. and Auxiliaries

10

A4.10 Ability to manually operate and/or

2.6/2.6

1

monitor in the control room: Hydrogen

gas pressure.

256000 Reactor Condensate

01

K2.01 Knowledge of electrical power

2.7/2.8

1

supplies to the following: System

pumps.

262001 AC Electrical Distribution

05

A4.05 Ability to manually operate and/or

3.3/3.3

1

monitor in the control room: Voltage,

current, power, frequency and A.C.

buses.

262002 UPS (AC/DC)

Not selected.

263000 DC Electrical Distribution

01

K2.01 Knowledge of electrical poser

3.1/3.4

1

supplies to the following: Major D.C.

loads.

271000 Offgas

02

A3.02 Ability to monitor automatic

2.9/2.8

1

operations of the OFFGAS SYSTEM

including: System flows. (RO ONLY)

272000 Radiation Monitoring

02

K1.02 Knowledge of the physical

3.2/3.5

1

connections andor cause-effect

relationships between the RADIATION

MONITORING SYSTEM and the

following: Offgas system (augmented

offgas).

286000 Fire Protection

Not selected.

290001 Secondary CTMT

290003 Control Room HVAC

Not selected.

300000 Instrument Air

02

K3,02 Knowledge of the effect that a

3.3/3.4

1

loss or malfuntion of the INSTRUMENT

AIR SYSTEM will have on the following:

Systems having pneumatic valves and

controls.

400000 Component Cooling Water

Not selected.

KlA Category Point Totals:

I2 2J

13 11 1

1

1 3

2 J

1 i

Group Point Total:

K 19

ES-401

BWR RO Examination Outline

Form ES-401-2 (Re, Si)

Plant Systems - Tier 2/Group 3

_

System # / Name

K1

K2

K3

K4

K5

K6

Al

A2

A3

A4

G

KIA Topic(s)

Imp.

PTS

215001 Traversing In-core Probe

01

A2.01 Ability to (a) predict the impacts of

2.7/2.9

1

the following on the TRAVERSING IN

CORE PROBE; and (b) based on those

predictions, use procedures to correct,

control, or mitigate the consequences of

those abnormal conditions or operations:

Low reactor water level. (RO ONLY)

233000 Fuel Pool Cooling and Cleanup

02

K2.02 Knowledge of electrical power

2.8/2.9

1

supplies to the following: RHR pumps.

(RO ONLY)

239003 MSIV Leakage Control

Does not apply to Brunswick.

268000 Radwaste

01

AI.01 Ability to predict and/or monitor

2.7/3.1

1

changes in parameters associated with

operating the RADWASTE controls

including: Radiation level.

288000 Plant Ventilation

290002 Reactor Vessel Internals

K/A Category Point Totals:

1

1111[

11l

1 1 I Group Point Total:

4

Plant-Specific Priorities

System I Topic

Recommended Replacement for...

Reason

Point

s

Plant-Specific Priority Total: (limit 10)

= 0.fl-1

f

l ItIF

flnrnknwnln n

hQti.

litie(ie

QFrmF-O

Facility: Brunswick

Date of Exam:

Exam Level: RO

ML030840253

Text

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