Text

August Exam 50-302/2003-301 Draft Written Exam Outlines
	ML032940448
Person / Time
Site:	Crystal River
Issue date:	08/29/2003
From:	; NRC/RGN-II
To:	; Progress Energy Florida
References
	50-302/03-301 50-302/03-301
	Download: ML032940448 (27)
	v • d • e

Draft Submittal

(Pink Paper)

I.

Written Exam Sample out~ines

CRYSTAL RIVER AUGUST

EXAM 50-302/2003-301

AUGUST 25 - 29,2003

ES-401

PWR EXAMINATION OUTLINE (RO)

FORM ES-401-2

11 Facility:

CRYSTAL RIVER UNIT 3

Date of Exam: AUGUST 25,2003

I

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.

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 r l from that specified in the table based on

NRC revisions. The final RO exam must total 75 points and the SRC-only exam must total 25 points.

Select topics from many systems and evolutions: avoid selecting more than two KIA topics from a

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

Systemslevolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the categorykier.

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 SRC-level learning objective.

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.

2.

3.

4.

5.

6.*

7.

8.

9.

For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

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

The random sampling guidance provided in ES-401, Attachment 1, was used to

generate this outline.

Page 1 of 15

F\\2003 NRC Exam\\OUTLINES\\Written\\RO NRC ZK3 Written Exam 0utline.doc

NUREG-1021, DRAFT REV. 9

1 -

1

_.

1 -

1

-

1

-

1

-

1 -

1

-

1

-

1 -

-

Emergency and Abnormal Plant Evolutions - Tier 11Group 1 (Ro)

I

-

IR -

-

4.3 -

3.2 -

3.0 -

3.3 -

2.9 -

2.6

-

2.7

-

3.3

-

4.2 -

3.8

-

3.6

-

4.4

-

EIAPE # I Name I Safety

000007 or EOZEIO Reactor Trip -

T

Stabilization - Recovery / 1

WA Topic(s)

007EA2.02 - Abilitv to determine or interoret the

fol oiing as they apply IO a reactor ir p 'Proper

actions to be laden f tne aLtoma18c safety

fdnctions nave no1 laken pace

000008 Pressurizer Vapor Space

Accident / 3

X

OOBAKI .01 - Knowledge of the operational

implications of the following concepts as they

apply to a Pressurizer Vapor Space Accident:

Thermodynamics and flow characteristics of

open or leaking valves

009EK2.03 - Knowledge of the interrelations

between the small break LOCA and the S/GS.

000009 Small Break LOCA I 3

I

00001 1 Large Break LOCA I 3

I

01 162.4.20 - Knwledge of operational

implications of EOP warnings, cautions, and

notes

I-

000015/17 RCP Malfunctions I 4

015AK2.07 - Know edge of tne intene alions

between Reactor Coolant PJmp Ma fLnCl ons

fLoss of RC Flow) and tne RCP seals.

000022 Loss of Rx Coolant Makeup / 2

022AA2.04-Abilitv to determine and interpret

the following as thky apply to the Loss of

Reactor Coolant Pump Makeup: How long PZR

level can be maintained within limits

---t

000025 Loss of RHR System / 4

025AX2 05 - Know edge of the nterrelallons

DeNveen the -oss of Decay Heat Removal

System and the lo owing Reactor DL. alng

SUmD

~

026AA1.04 - Abilitv to operate and /or monitor

000026 Loss of Component Cooling

Water / 8

the followina as thev aodv to the Loss of

NLclear Sekices / Deday'Heal C osed Cycle

Cool ng CRDM n gh-temperalde alarm syslem

~

000027 Pressurizer Pressure Control

System Malfunction / 3

027AA1 05 - A~ilily to operate and I or mon lor

me following as they apply IO Ihe Pressurizer

Pressdre Control Malhnct ons

Transfer of

heaters to backup Dower supply

000029 ATWS / 1

029EK3.11- Knowledge of the reasons for the

followina resoonses as the apDIv to the ATWS:

lnitiatini emergency boration .

038EA2.08 - Abilitv to determine or interpret the

000038 Steam Gen. Tube Rupture / 3

follow,ng as they a'pp~y to a SGTR. v ade

a ternatnves for plac ng plan1 in safe condil on

wnen condenser s not avai able

EO5EA1 .2 - Ab lily 10 Operate and I or monitor

me followinq as tney apply to the (Excess ve

000040 or E05 Steam Line Rupture -

Excessive Heat Transfer / 4

. . . .

Heat Transfer): Operating behavior

charactenstics of the facility.

~~~

000054 Loss of Main Feedwater I 4

n54AA1~02- Abilihl to ooerate and /or monitor

., -- ~.~~

~

_ _ .

.

tne follow ng as they apply 10 tne Loss of Main

Feeawater (MFW): Manual slart~p of elec1r.c

and steamdriven EFW pumps

NUREG-1021,

DRAFT REV. 9

~

Page 2 of 15

F\\2003 NRC Exam\\OUTLINES\\Written\\RO NRC 2K3 Written Exam 0utline.doc

ES-401

PWR EXAMINATION OUTLINE (RO)

FORM ES-401-2

Emergency and Abnormal Plant Evolutions - Tier 11Group 1 (Ro)

EIAPE # I Name I Safety

Function

000055 Station Blackout / 6 c

000056 Loss of Off-site Power / 6

11 000057 Loss of Vital AC Inst. Bus / 6 I

000058 LOSS of DC Power / 6

000062 Loss of Nuclear Svc Water / 4

000065 Loss of Instrument Air / 8

Il-

I

E04 Inadequate Heat Transfer- Loss of

Secondary Heat Sink / 4

KIA Category Totals:

2

KIA Topic(s)

055EK3.02 - Knowledge of the reasons for the

following responses as the apply to the Station

Blackout: Actions contained in EOP for loss of

offsite and onsite Dower

056G2.1.2 - Knowledge of operator

responsibilities during all modes of plant

oDeration.

058AA2.02 - Aoility to aeterm ne ana interpret

me follow ng as they apply lo the -0% of DC

Power: 125V dc bJs vodage, low alarm

062AK3.02 - Knowledge of the reasons for the

following responses as they apply to the Loss of

Raw Water: The automatic actions

(a ignments) w in n the RWS result*ng from lne

act~at

on of [ne ESFAS

EMEKI .3 - Knowledae of the ooerational

iiipliations of the foiowing cokepts as tney

apply to the (InadeqLate Heal Transfer)

Annunc ators and conditions ind cat ng Signals,

and remedial actions associated with the

(Inadequate Heat Transfer).

Group Point Total:

Page 3 of 15

F\\2003 NRC Exam\\OUTLINES\\Written\\RO NRC 2K3 Written Exam 0utline.doc

NUREG-1021. DRAFT REV. 9

ES-401

PWR EXAMINATION OUTLINE (RO)

FORM ES-401-2

Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (Ro)

E/APE # / Name / Safety

K1

KZ

Function

000003 Dropped Control Rod / 1

000005 InoperablelStuck Control Rod / 1

000024 Emergency Boration / 1

000028 Pressurizer Level Malfunc~on

/ 2

X

000032 Loss of Source Range NI / 7

000033 Loss of intermediate Range NI / 7

000036 (BW/AO8) Fuel Handling Accident /

0

~~

000037 Steam Generator Tube Leak / 3

000051 Loss of Condenser Vacuum / 4

t

000059 Accidental Liquid RadWaste Rel. /

~

000060 Accidental Gaseous Fadwaste Rel.

19

000061 ARM System Alarms / 7

000067 Plant Fire On-site / 8

000068 (BW/AO6) Control Room Evac. / 8

000069 (W/E14) Loss of CTMT Integrity / 5

000074 (W/E06&E07) had. Core Cwling /

Page 4 of 15

K/A Topic(s)

IR

~~~~~~

003AK3.07 - Knowledge of the reaions for

the foilowing responses as they apply to the

Dropped Control Rod: TechSpec limits for T-

3.8

1

ave

028AK2.02 - Knowledge of the interrelations

between the Pressurizer Level Control

Malfunctions and the following: Sensors and

2.6

1

detectors

033AA2.04-Ability to determine and interpret

the following as they apply to the Loss of

intermediate Range Nuclear Instrumentation:

3.2

1

Satisfactoly overlap between sourcerange,

intermediate-range and power-range

instrumentation

037AK3.05 - Knowledae of the reasons for

the following responses as they apply to the

Steam Generator Tube Leak: Actions

monitoring. RCS water inventory balance, S/G

contained in prccedures for radiation

3.7

1

tube failure, and plant shutdown

I

069G2.1.33 -Ability to recognize indications

for system operating parameters which are

specifications.

entry-level conditions for technical

3.4

1

NUREG-1021. DRAFT REV. 9

F\\2003 NRC Exam\\OUTLINES\\Written\\RO NRC 2K3 Written Exam 0udine.doc

ES-401

PWR EXAMINATION OUTLINE (RO)

FORM ES-401-2

Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (Ro)

K/A Topic@)

AOlAA2 2 . Ability to determine and nterpret

me follow ng as they app y to the (Plant

Runback) Adnerence to appropriate

procedures and operation within the

limitations in the facilitys license and

amendments

AWAAl. 1 -Ab lhly to operate and I or monitor

the fol ow ng as they apply to the (Tub ne

Trip). Components, and fLnctions of COntrO

and safety systems, including instrumentation,

signals, interlocks, failure modes, and

automatic and manual features.

A07AK1.2 - Knowledge of the operational

implications of the following concepts as they

apply to the (Flooding): Normal, abnormal

and emergency operating procedures

associated with (Flooding).

E13EQ 1 - Know eage of the interre ations

berween the (EOP RJles) ana the folowlng

Components, and fmctions of control and

safety systems. ncLding instrunentation.

s gna s. nterlocks, failLre moaes, and

automate and manua features

Group Point Total:

I 9/E

Page 5 of 15

F\\2003 NRC Exam\\OUTLlNES\\Written\\RO NRC 2K3 Written Exam Outline.doc

NUREG-1021. DRAFT REV. 9

ES-401

PWR EXAMINATION OUTLINE (RO)

FORM ES-401-2

System # I Name 1 K*

--r

003 Reactor Coolant

Pump

004 Chemical and

Volume Control

005 Residual Heat

Removal

007 Pressurizer

RelieflCluench Tank

008 Component

Cooling Water

Plant Systems - Tier 21Group 1 (Ro)

KIA Topic@)

003K3.05 - 6nowleage of tne

effect that a oss or ma fJnct on

of the RCPs w II have on the

lo ow,ng' ICs

003K6.04 - Knowledge of the

effect of a loss or malfunction of

Reactor Building isolation valves

on RCP operation

004A1.12-Abilityto predict

and/or monitor changes in the

rate of boron concentration

reduction in RCS as a function of

letdown flow while deborating

demineralizer is in service (to

prevent exceeding design limits)

associated with operating the

MUPS controls

00564 08. Knowleage of Decay

Heat System design featJre(s)

analor nter ock(s) wn ch prov ae

for tne following L neup for

pggy-backmodewln hgh-

pressure In.ection (MakeJp

System)

006K4 05 - 6nowledge of ECCS

des gn featJre(s) analor

nterlock(s) which prowde for

aLtostati of dP /.PI

006G2.1.28 - Knowledged the

purpose and function of major

system components and

controls.

007A4.10-Ability to manually

operate andlor monitor in the

control room: Recognition of

leaking PORVIcode safety

008A4.07-Ability to manually

operate and/or monitor in the

control room: Control of

minimum level in the SWS I DCS

surge tank

Page 6 of 15

NUREG-1021,

DRAFT REV. 9

F\\2003 NRC Exam\\OUTLINES\\Written\\RO NRC 2K3 Written Exam 0utline.doc

ES-401

PWR EXAMINATION OUTLINE (RO)

FORM ES-401-2

Plant Systems - Tier 2/Group 1 (Ro)

010 Pressurizer

Pressure Control

012 Reactor

Protection

013 Engineered

Safety Features

Actuation

022 Containment

Cooling -

026 Containment

Spray

Page 7 of 15

WA Topic(s)

)10K5.01 - Knowledge of the

Iperational implications of the

ollowing concepts as the apply

o the PZR PCS: Determination

)f condition of fluid in PZR, using

team tables

)12K1.03 - Knowledge ofthe

)hysical wnnections andlor

ause-effect relationships

letween the RPS and the CRDS.

)13K6.01 - Knowledge of the

?ffect of a loss or malfunction of

SFAS related sensors and

jetectors.

)13K1.13- Knowledgeofthe

)hysical connections andlor

awe effect relationshios

)eween the ESFAS and the

7VAC systems.

122A2.04- Ability to (a) predict

he impacts of the following

nalfunctions or operations on the

CS; and (b) based on those

)redictions. use procedures to

orrect, wntrol. or mitigate the

onsequences of those

nalfunctions or operations: Loss

)f cooling water

326A3.01 - Abilityto monitor

automatic operation of the BSS,

ncluding: Pump starts and

orrect MOV positioning

NUREG-1021,

DRAFT REV. 9

F\\2003 NRC Exam\\OUTLINES\\Written\\RO NRC 2K3 Written Exam 0utline.doc

ES-401

PWR EXAMINATION OUTLINE (RO)

FORM ES-401-2

Plant Systems - Tier 2/Group 1 (R4)

039 Main and Reheat

Steam

056 Condensate

059 Main Feedwater

061

Auxiliary/Emergency

Feedwater

062 AC Electrical

Distribution

063 DC Electrical

Distribution

Page 8 of 15

K/A Topic(s)

039K3.04 - Knowledge of the

effect that a loss or malfunction

of the MRSS will have on the

following: MFW pumps

039A2.05- Ability to (a) predict

the impacts of the following

malfunctions or operations on the

MRSS: and (b) based on

predictions, use procedures to

correct, controi, or mitigate the

consequences of those

malfunctions or operations:

lncreasino steam demand. its

relationstp to increases in

reactor power

056K1.03 - Knowledge of the

physical connections andlor

cause-effect relationships

between the Condensate System

and the following systems: MFW

059A4.10-Ability to manually

operate and monitor in the

control room: ICs

059G2.1.22 -Ability to determine

Mode of Operation.

061K2.01 - Knowleoge of OLS

power supplies lo the following:

EFW system MOVs

062K3.01 - Knowledge of the

effect that a loss or malfunction

of the AC distribution system will

have on the following: Major

system loads

06202.1.33 -Ab ty to recognize

indica1 ons for system operating

parameters wnich are entry-leve

condit ons for tecnntcal

spec ficat ons.

063A3.01- Aoil ty to monitor

aLtomatic operation of the dc

eieclr cal system, ncluding:

Meters. annLnc alors. ala 5.

recorders, and in0:cating lights

NUREG-1021, DRAFT REV. 9

-

IR -

-

2.5

3.3

-

2.6

-

3.9

2.8 -

3.2

-

3.5

-

3.1

-

2.7

-

F\\2003 NRC Exam\\OUTLINES\\Written\\RO NRC 2K3 Written Exam 0utline.doc

~

ES-401

PWR EXAMINATION OUTLINE (RO)

FORM ES-401-2

System # / Name

064 Emergency

Diesel Generator

073 Process

Radiation Monitoring

076 Service Water

078 Instrument Air

103 Containment

WA Category Point

Totals:

Plant Systems - Tier 2/Group 1 (Ro)

WA Topic(s)

064A2.08- Ability to (a) predict

the impacts of the following

malfunctions or operations on the

ED/G system; and (b) based on

those predictions, use

procedures to correct, control, or

mitigate the consequences of

those malfunctions or operations:

Consequences of

openinglclosing breaker between

buses (VARS, out-d-phase.

voltage)

073K5.02 - 6nowleage of the

operat onal mpl callonS as lney

app y IO concepts as they apply

to the PRM svslem: Raoation

intensity chaAges with source

distance

076A2.02Ability to (a) predict

the impacts of the following

malfunctions or operations on the

RWS; and (b) based on those

predictions, use procedures to

correct, control, or mitigate the

consequences of those

malfunctions or operations: RW

header pressure

078K2.01 - Knowledge of bus

power supplies to the following:

Instrument air compressor

103A3.01 -Ability to monitor

automatic operation of the

reactor building system,

including: Reactor Building

isolation

Group Point Total:

Page 9 of 15

F\\2003 NRC Exam\\OUTLINES\\Written\\RO NRC 2K3 Written Exam 0utline.doc

NUREG-1021, DRAFT REV. 9

ES-401

PWR EXAMINATION OUTLINE (RO)

FORM ES-401-2

System # I Name

001 Control Rod

Drive

002 Reactor Coolant

01 1 Pressurizer Leve

Control

014 Rod Position

IndicaBon

015 Nuclear

Instrumentation

016 Non-nuclea!

Instrumentation

017 In-core

Temperature Monitor

027 Containment

iodine Removal

028 Hydrogen

Recornbiner and

Purge Control

Page 10 of 15

,,

X

Plant Systems - Tier 2/Group 2 (Ro)

KIA Topic@)

OOlK5.28 - Knowledge of

boron reactivity worth vs.

boron concentration. (i.e.;

amount of boron needed

(ppm) to change core

reactivity to desired amount).

002K1.09 - Knowledge of the

physical connectons and/or

cause-effect relationships

between the RCS and the

Pressurizer (PZR).

014K4.05 - Knowledge of

RPlS design feature(s) and/or

interlock(s) which provide rod

hold interlocks.

015A1.04-Abiiityto predict

andlor monitor changes in

parameters (to prevent

exceeding design limits)

associated with operating the

NIS controls inciuding:

Quadrant power tilt ratio

016A301 -Ao~llytomonlor

aLtomat c operat on of me

hN S. NncLdlng AJtOmatiC

select on of hNlS nputs to

contro systems

NUREG-1021. DRAFT REV. 9

F\\2003 NRC Exam\\OUTLINES\\Written\\RO NRC 2K3 Written Exam 0utline.doc

ES-401

PWR EXAMINATION OUTLINE (RO)

FORM ES-401-2

System # / Name

029 Containment

Purge

033 Spent Fuel Pool

Cooling

034 Fuel Handling

Equipment

035 Steam Generator

041 Steam

DumpITurbine

Bypass Control

045 Main Turbine

Generator

055 Condenser Air

Removal

068 Liquid Radwaste

071 Waste Gas

Disposal

072 Area Radiation

Monitoring

Page 11 of 15

Plant Systems - Tier 2/Group 2

WA Topic(s) 3

035K4 01 - Know edge of

SIGS design featJre(s) andlor

inierlock(s) wnich prov de for

SIG level wntro.

3.6

041A2.02-Ability to (a)

predict the impacts of the

following malfunctions or

operations on the Turbine

Bypass Valves; and (b) based

on those predictions or

3.6

mitigate the consequences of

those malfunctions or

operations: Steam valve

stuck open

04543.01 - Xnowleage of the

effect that a oss or

rnalfJnct on of me MTIG

I 2.9

system will have on the

071K3.04 - Knowledge of the

effect that a loss or

malfunction of the Waste Gas

Disposal System will have on

the following: Ventilation

system

2.7

NUREG-1021, DRAFT REV. 9

F:\\2003 NRC Exam\\OUTLINES\\Written\\RO NRC 2K3 Written Exam 0utline.doc

ES-401

PWR EXAMINATION OUTLINE (RO)

FORM ES-401-2

086 Fire Protection

IIlIEt

KIA Categoly Point

Totals

Plant Systems - Tier 2/Group 2 (Ro)

Page 12 of 15

F\\2003 NRC Exarn\\OUTLINES\\Written\\RO NRC 2K3 Written Exam 0udine.doc

NUREG-1021.

DRAFT REV. 9

__

~

~~~

ES-401

Generic Knowledge and Abilities Outline (RO)

Form ES-401-3

2.1.4

Facility: Crystal River Unit #3

Date of Exam: August 25,2003

Knowledge of shift staffing requirements.

I

ML032940448

Text

Navigation menu

Search