Text

August Exam 50-302/2003-301 Final Sample Plans/Outlines
	ML032940423
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: ML032940423 (36)
	v • d • e

Final Submittal

CRYSTAL RIVER AUGUST

EXAM 50-30212003-301

AUGUST 25 - 29,2003

FINAL SAMPLE PLANS I OUTLlNtS

ES-301

Administrative Topics Outline

Form ES-301- 1

Facility: Crvstal River Unit 3

Date of Examination: August 25. 2003

ExamLevel RO

Operating Test No.: I

Administrative Topic

(see Note)

Conduct of Operations

Equipment Control

Radiation Control

Emergency Plan

Describe activity to be performed:

Print Reading - Determine criteria for start of AHF-44B during a LOOP.

KIA - G2.1.24 RO 2.8 SRO 3.1

Multiple electrical prints and flow diagrams [New]

Perform a Daily Heat Balance Comparison

KIA - G2.1.23 RO 3.9 SRO 4.0

SP-3 12A [Modified Bank]

Perform an RCS Water Inventory Balance per SP-317

K/A - G2.2.12 RO 3.0 SRO 3.4

SP-317 [Direct]

Complete the State of Florida Notification Message Form and make

required notifications

KIA - G2.4.43 RO 2.8

EM-202 [New, Alternate Path]

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are

retaking only the administrative topics, when 5 are required.

NUREG- 102 I, DraR Rev. 9

FU003 NRC Exam\\OUTLINEWPMs\\NRC

ZK3 RO Only Outline Admin JPMs (301 -I).doc

ES-301

Administrative Topics Outline

Form ES-301-1

Operating Test No.: 1

Describe activity to be performed:

Print Reading - Determine criteria for start of AHF-44B during a LOOP.

KIA - G2.1.24 RO 2.8 SRO 3.1

Multiple electrical prints and flow diagrams [New]

Facility: Crvstal River Unit 3

Exam Level SRO

Date of Examination: Aueust 25. 2003

Administrative Topic

(see Note)

Conduct of Operations

Equipment Control

Perform a Daily Heat Balance Comparison

K/A - G2.1.23 RO 3.9 SRO 4.0

SP-312A [Modified Bank]

After completing heat balance determine required TS actions

WA-G2.1.12 S R 0 4 . 0

~

~~

~

Perform an RCS Water Inventory Balance per SP-317

WA - G2.2.12 RO 3.0 SRO 3.4

SP-317 [Direct]

After completing SP-317 determine required TS actions

WA-G2.1.12 SR04.0

Determine external reporting requirements per CP-151

KIA - (32.3.1 SRO 3.0

CP-151 & NUREG-1022 [New]

Radiation Control

Emergency Plan

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they arf

retaking only the administrative topics, when 5 are required.

Determine Emergency Action Level after Simulator Scenario # 2

K/A -G2.4.41 SRO 4.1

EM-202 [New]

NUREG-1021,

Draft Rev. 9

F:U003 NRC Exam\\OUTL1NESJPMs\\NRC ZK3 SRO Only Outline Admin JPMs (301 -I).doc

ES-301

Control Roomfln-Plant Systems Outline

Form ES-301-2

~~

System / JPM Title

a. CRDS - Transfer control rod to auxiliary power supply

WA- 001A4.03 RO 4.0 SRO 3.7 (OP-502)

b. ESFAS - ES " B HPI Diverse Containment Isolation Test

WA- 013A3.01 RO 3.7 SRO 3.9 (SP-358A)

c. PZR PCS - Perform PORV Exercise Test

K/A - 010A3.01 RO 3.0 SRO 3.2 (SP-379)

d. RHR - Perform a crosstie of DHR flow to the Reactor Vessel

WA - 005A1.02 RO 3.3 SRO 3.4 (OP-404)

e. CSS - Ensure Building Spray actuation

WA - 026A3.01 RO 4.3 SRO 4.5 (EM-225C)

AC - Perform actions for loss of an ES 4160V Bus

f.

WA - 062A2.12 RO 3.2 SRO 3.6 (AP-770)

g. RPS - Place the RPS in Shutdown Bypass.

h. WGDS/PRM - Perform actions for an accidental Waste Gas leak

WA- 060AA2.05 RO 3.7 SRO 4.2 (AP-250)

WA- 012A4.03 RO 3.6 SRO 3.6 (OP-202/507)

SPARE

MU - Restart a MUP Following an RCS Leak Isolation

WA- 002A2.01 RO 4.3 SRO 4.4 (AP-520)

Facility: Crvstal River Unit 3

Exam Level: RO

Date of Examination: Aueust25.2003

Operating Test No.: 1

Control Room System (8 for RO; 7 for SRO.1: 2 or 3 for SRQU)

Type

Safety

Code*

Function

D, S

1

A, D. S

2

L. N,

S

3

L, D, S

4

A, D, S

5

A, M, S

6

L, D. S

7

A. C, N,

9

S

D. S

2

i. AFWEFW - Place EFIC Channel in Tripped condition

N

WA- 061A2.05 RO 3.1 SRO 3.4 (OP-450)

j. CCWS - Fill SW surge tank from the Fire Service system

WA- 008A1.04 RO 3.1 SRO 3.2 (EOP-14, Enclosure 2)

D. R

k. CRD - Manually trip reactor from outside control room

A. D

WA-02EA1.1 RO 4.0 SRO 3.6 (AP-990)

SPARE

FS/OTSG - Transfer excess secondary inventory to FST

D

WA - 037AK3.07 RO 4.2 SRO 4.4 (EOP-14 Enclosure 9)

NUREG- 1021. Draft Rev. 9

4

8

1

2,8

F\\2003 NRC Exam\\OUTLINEWPMs\\NRC 2K3 RO Only Outline SIM-Plant JPMs (301 -2) Rev 1 .doc

ES-301

Control Room/In-Plant Systems Outline

Form ES-301-2

b. ESFAS - ES "B" HPI Diverse Containment Isolation Test

WA- 013A3.01 RO 3.7 SRO 3.9 (SP-358A)

c. PZR PCS - Perform PORV Exercise Test

WA- 010A3.01 RO 3.0 SRO 3.2 (SP-379)

d. RHR - Perform a crosstie of DHR flow to the Reactor Vessel

CSS - Ensure Building Spray actuation

WA- 005A1.02 RO 3.3 SRO 3.4 (OP-404)

e.

WA - 026A3.0 1 RO 4.3 SRO 4.5 (EM-225C)

f. AC - Perform actions for loss of an ES 4 16OV Bus

WA- 062A2.12 RO 3.2 SRO 3.6 (AP-770)

g. RPS - Place the RPS in Shutdown Bypass.

WGDS/PRM - Perform actions for an accidental Waste Gas leak

WA- 060AA2.05 RO 3.7 SRO 4.2 (AP-250)

WA- 012A4.03 RO 3.6 SRO 3.6 (OP-202/507)

h.

SPARE

MU - Restart a MUP Following an RCS Leak Isolation

WA- 002A2.01 RO 4.3 SRO 4.4 (AP-520)

Facility: Crvstal River Unit 3

Exam Level: SROQ

Date of Examination: August 25. 2003

Operating Test No.: 1

Control Room Systems (8 for RO; 7 for SROI; 2 or 3 for SRO-U)

A, D. S

2

L. N, S

3

L, D. S

4

A, D, S

5

A, M. S

6

L, D. S

7

A, C. N.

9

S

D. S

2

System / JPM Title

i. AFW/EFW - Place EFIC Channel in Tripped condition

N

WA- 061A2.05 RO 3.1 SRO 3.4 (OP-450)

j. CCWS - Fill SW surge tank from the Fire Service system

D, R

WA- 008A1.04 RO 3.1 SRO 3.2 (EOP-14, Enclosure 2)

k. CRD - Manually trip reactor from outside control room

A, D

WA- 02EAl.l RO 4.0 SRO 3.6 (AP-990)

SPARE

FS/OTSG - Transfer excess secondary inventory to FST

D

WA- 037AK3.07 RO 4.2 SRO 4.4 (EOP-14 Enclosure 9)

Type

Safety

I Code* I Function

4

8

1

2,8

NUREG-1021,

Draft Rev. 9

F:\\2003 NRC Enam\\OUTLINESUPMs\\NRC 2K3 SRO-I Only Outline SIM-Plant JPMs (301 -2) Rev I.doc

ES-301

Control Roomfln-Plant Systems Outline

Form ES-301-2

~

b. ESFAS - ES "B" HPI Diverse Containment Isolation Test

WA- 013A3.01 RO 3.7 SRO 3.9 (SP-358A)

c. PZR PCS - Perform PORV Exercise Test

WA- 010A3.01 RO 3.0 SRO 3.2 (SP-379)

d. RHR - Perform a crosstie of DHR flow to the Reactor Vessel

WA- 005A1.02 RO 3.3 SRO 3.4 (OP-404)

SPARE

MU - Restart a MUP Following an RCS Leak Isolation

WA- 002A2.01 RO 4.3 SRO 4.4 (AP-520)

Facility: Crvstal River Unit 3

Exam Level: SRO(U)

Operating Test No.: 1

Date of Examination: Aueust 25. 2003

A. D, S

2

L, N, S

3

L, D, S

4

D, S

2

Control Room Systems (8 for RO: 7 for SRC-I; 2 or 3 for SRO-U)

j. CCWS - Fill SW surge tank from the Fire Service system

WA- 008A1.04 RO 3.1 SRO 3.2 (EOP-14, Enclosure 2)

k. CRD - Manually trip reactor from outside control room

WA- 02EAl.l RO 4.0 SRO 3.6 (AP-990)

SPARE

FSlOTSG - Transfer excess secondary inventory to FST

WA - 037AK3.07 RO 4.2 SRO 4.4 (EOP-14 Enclosure 9)

System I JPM Title

D. R

8

A, D

1

D

2. 8

I

Type I

Safety

Code*

Function

NUFEG- 1021, Draft Rev. 9

FD003 NRC Enam\\OUTLINESJPMs\\NRC 2K3 SRO-U Only Outline SlM-Plant JPMs (301 -2) Rev 1 .doc

Appendix D

Scenario Outline

Form ES-D- 1

Event

No.

Malf.

Event

No.

Type*

Description

~

1

2

I (RO) I Turbine header pressure setpoint fails low over three minutes.

//

I

I (SRO)

SROTSdetermination. (TS 3.7.4)

N/A

N (BOP)

Turbine startup in progress. (OP-203)

1

I (SRO)

RM-A6 Gas fails low. SRO TS determination. (TS 3.4.14)

4

5

11

6

I

4

I

C (RO)

I PZR steam space leak, small, 20 gpm. (AP-520)

NIA

R (RO)

Manual power increase.

FW-223/224-TE trend up. Requires startup of FWBP-1B and

(Bop)

shutdown of FWBP-1A. (OP-605)

3

7

8

5

6

C (BOP)

M (ALL)

RCV- 13, PZR spray block valve, fails to close.

PZR steam space leak, large, 160 gpm. (EOP-2, EOP-3) '

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

9

10

NUREG- 1021, Draft Rev. 9

F:Y2003 NRC Exam\\OUTLMES\\Simulator\\Scenario

Outline (D- 1) NRC #1 Rev 1 .doc

MUP- 1 C shaft seizure on ES start signal / MW-73 fails to

open automatically. [CT] (EOP-13, Rule 1)

RCP- 1 D breaker will not open. [CT]

(Bop)

C (RO)

7

8

Appendix D

Scenario Outline

Form ES-D-1

Event

No.

1

Facility: Crystal Unit #3

Scenario No.: 2

n\\r RC)

Op-Test No.: 1.

Malf.

Event

NO.

Type*

Description

N/A

N (BOP)

Perform SP-321, Enclosure 1.

-

_

Examiners:

Operators:

3

4

Initial Conditions: The plant is at 100% power.

C (BOP)

C (SRO)

Gland steam leak / condenser vacuum degradation (OP-607)

SRO ODCM determination for RM-A12.

2

3

C (BOP)

ARF- 1A trips.

Turnover: The following equipment is 00s: DHP-1A (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ); MUP-1A (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ); RWP-I

(24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ); Offsite Power Transformer (7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ). SP-321 is due after turnover is complete. All

other required surveillances have been completed. Substation personnel in switchyard (OPT

repair).

6

7

5

C (BOP)

40 gpm A OTSG tube leak. (EOP-6)

6

Two MSIVs close at 70% power / manual reactor trip [CT]/

tube leak increases to 160 mm (AI-505. EOP-2)

(ALL)

2

I

1

I

I (SRO)

I EF-98-LT fails low. SRO TS determination.

9

8

C (RO)

PORV fails to close. [CT]

R (OAC) 1 RX demand station fails as is / rapid power reduction with

rods and possibly FW in manual. (AP-510)

5

1

4

1

I (OAC)

8

I

7

I

C (RO)

I RCV-14, PZR spray valve, fails to open.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

NUREG- 1 02 1, Draft Rev. 9

F:\\2003 NRC Exam\\OUTLINES\\Simulator\\Scenario

Outline (D- 1) NRC #2.doc

Appendix D

Scenario Outline

Form ES-D-1

2acility: Crvstal Unit #3

Scenario No.: 3

(NRC)

Op-Test No.: 1

!xaminers:

Operators:

nitial Conditions: The plant is at 60% power. Power decrease in progress to perform trouble

,hooting on the B MFWP governor.

rumover: The following equipment is 00s: DHP-1A (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ); MUP-1A (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ); RWP-1

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ). All required surveillances have been completed. Substationpersonnel in switchyard

Unit 5 breaker maintenance).

+

4

/

3

5

1

4

6

1

5

3I

(N)ormal, (R)ea

Event

Type*

N (RO)

I (SRO)

C (BOP)

Event

Descriotion

Continue power decrease to approximately 50% power. (OP-

204)

MS-112-PT fails low. SRO TS determination (TS 3.3.1 1)

B MFWP governor fails as the plant is brought through the

feedwater MBVs. (01-09)

Selected turbine header pressure transmitter fails high over 2

minutes. (OP-501)

~~

SW leak into the RW system. (AP-330)

Turbine remains in manual. Rapid power reduction required

for SW leak. (AP-510)

A OTSG steam leak in containment. (EOP-2, EOP-5)

EFV-56 fails as is. [CT]

B Train RBIC fails to actuate automatically/manually and

MUV-258 fails to close. lCTl

vity, (I)nstrument, (C)omponent, (M)ajor

NUREG- 1021, Draft Rev. 9

F:\\2003 NRC Exam\\OUTLINES\\Simulator\\Scenario

Outline (D- 1) NRC #3.doc

Appendix D

Scenario Outline

Form ES-D-1

Event

Malf.

Event

No.

Type*

1

N/A

N (BOP)

C (SRO)

2

1

Event

Description

Vent CFT-1B. (OP-401)

RWP-2B trips. (01-09) SRO TS determination. (TS 3.8.1)

3 -

4

2

3

Selected A OTSG level transmitter slowly fails high /

SASS module will not transfer. (OP-501)

A ES Bus is lost due to troubleshooting activities associated

with the A EDG breaker. (AP-770) SRO TS

I (Ro)

(SRo)

determination. (TS 3.0.3)

5

6

7

8

9

NJA

R (RO)

Manual power decrease. (AP-510)

C (RO)

R (RO)

required. (AP-545)

RCP- 1D sheared shaft. Manual runback and FW re-ratio

4

5

C (RO)

ASV-27 malfunction. Loss of both MFWPs. (01-09)

6

M (ALL)

Turbine fails to trip. [CT] (EOP-2)

7

C (BOP)

EFP-3 diesel trips after start.

NUREG- 1021, Draft Rev. 9

10

F:\\2003 NRC Exam\\OUTLINES\\Simuiator\\Scenario

Outline (D- 1 ) NRC #4.doc

8

C (BOP)

ASV-5 fails to open. [CT] (EOP-4)

ES-401

PWR EXAMINATION OUTLINE (SRO)

FORM ES-401-2

Facility:

CRYSTAL RIVER UNIT 3

Date of Exam: AUGUST 25,2003

I

3. Generic Knowledge and

Abilities Categories

2

1

2

Note:

1.

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

(Le., 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 - t l 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.

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.

Systemslevolutions within each group are identified on the associated outline.

The shaded areas are not applicable to the categoryltier.

The generic (G) K/As 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. The SRO K/As must also be linked to

10 CFR 55.43 or an SRO-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 SRC-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 K/A statements.

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

generate this outline, with the exception of the 18 Tier 1 and Tier 2 SRO only

WAS. A smart random sampling method was approved for use by the Chief

Examiner.

Page 1 of 11

F\\2M)3 NRC Exam\\OLlTLINES\\Written\\SRO NRC 2K3 Written Exam 0utline.doc

NUREG-1021, DRAFT REV. 9

ES-401

PWR EXAMINATION OUTLINE (SRO)

FORM ES-401-2

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

EIAPE # I Name I Safety

n

Function

000007 or E02/E10 Reactor Trip -

000008 Pressurizer Vapor Space

Accident I 3

000009 Small Break LOCA / 3

I

000015/17 RCP Malfunctions / 4

000022 Loss of Rx Coolant Makeup / 2

X

000025 Loss of RHR System / 4

000026 Loss of Component Cooling

Water / 8

000027 Pressurizer Pressure Control

System Malfunction / 3

000029 ATWS / 1

000038 Steam Gen. Tube Rupture / 3

000040 or E05 Steam Line Rupture -

Excessive Heat Transfer / 4

000054 Loss of Main Feedwater / 4 I

000055 Station Blackout / 6 t

000056 LOSS of Off site Power / 6

Page 2 of 11

G

KIA Topic(s)

009EK3.06 - Knowleoge of tne reasons for the

lo low ng responses, as they apply to the sma

brea6 LOCA: RCS inventoty balance

025AK1.01- Knowledge of the operational

implications of the following COnCePtS as they

apply to Loss of Decay Heat Removal System:

Loss of DH System during all modes of

operation

02602 4 47 - Aoilily to oiagnose and recognize

lrends n an accurate and tmely manner 1.1

zing

me appropriate control room reference material

X

029EA2 09 - Abilily to determine or interpret the

follow ng as tney app,y to a ATWS 0cc.rrence

of a ma n txbinelreactor tr p

038EA2 13 -Ability to determine or nbrpret tne

following as they apply to a SGTR: Magnituoe

of ruptJre

040AK3.2 - Knowledge of the reasons for the

following responses as they apply to the

(Excessive Heat Transfer): Normal, abnormal

and emergency operating procedures

T

associated with (Excessive Heat Transfer).

055G2.4.7 - Knowledge of event based EOP

/------

mitigation strategies.

NUREG-1021, DRAFT REV. 9

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

ES-401

PWR EXAMINATIOP OUT1 IE (SRO)

FORM ES-401-2

Emergency and Abnormal Plant Evolutions - Tier l/Group 1 (SRO)

N

Page 3 of 11

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NRC 2K3 Written Exam 0utline.doc

NUREG-1021, DRAFT REV. 9

ES-401

PWR EXAMINATION OUTLINE (SRO)

FORM ES-401-2

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

000005 InoperableIStuck Control Rod I 1

000059 Accidental Liq

000060 Accidental Gaseous Radwaste Rel.

00074 (W/E06&E07) Inad. Core Cooling I

Page 4 of 11

KIA Topic(s)

IR

005AA2.01 -Ability to determine and interpret

the following as they apply to the Inoperable /

Stuck Control Rod: Stuck or inoperable rod

from in-core and ex-cae NIS. inmre t

061G2.1.14 - Anowledge of syslem slaas

criteria which requ re the nol'tcal'on of plant

074EA2 03 -Ab ry IO determine or interpret

the fo lowing as they apply to a nadequate

Core Coolina Availaoilih, of tub ne bypass

..

valvesfor cooldown

.

I

A

NUREG-1021, DRAFT REV. 9

F\\Z003 NRC Exam\\OUTLINES\\Written\\SRO NRC ZK3 Written Exam 0utline.doc

ES-401

PWR EXAMINATION OUTLINE (SRO)

FORM ES-401-2

Emergency and Abnormal Plant Evolutions - Tier 1IGroup 2 (SRO)

II

E/APE#/NameISafety

K1

K2 K3

A1

A2

Function

BW/A028A03 Loss of NNI-WY / 7

X

1

2

WA Category Point Totals:

KIA Topic(s)

IR

A02AA1 .I

-Ability to operate and I or monitor

the followina as thev amlv to the (Loss of

I

,

.

I

hN-X) Components, and fmct ons of control

and safety systems. Inc A n g insuumeniauon.

signals, interlocq failLre modes, and

aJtomatc ana manua featdies

3.8 -

A05G2.2.20 - Knowledge of the process for

managing troubleshooting activities.

Group Point Total:

Page 5 Of 11

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NRC 2K3 Written Exam 0utline.doc

NUREG-1021, DRAFT REV. 9

ES-401

PWR EXAMINATION OUTLINE (SRO)

FORM ES-401-2

003 Reactor Coolant

004 Chemical and

Volume Control

005 Residual Heat

Removal

006 Emergency Core

Cooling

007 Pressurizer

RelieflQuench Tank

008 Component

Cooling Water

I

010 Pressurizer

012 Reactor

Protection

013 Engineered

Safety Features

Actuation

022 Containment

Cooling

I

Spray

Page6of 11

Plant Systems - Tier 2/Group 1 (SRO)

K

WA Topic(s)

004A2.09-

Ability to (a) predict

the impacts of a high primary

andlor secondary activRy on the

MUPS: and (b) based on those

predictions, use procedures to

correct, control, or mitigate the

consequences of these

malfunctions.

012G2.2.24 - Abilitv to analyze

the affect of ma ntenance '

actw es on L O slatLs

NUREG- 102 1, DRAFT REV. 9

F\\2003 NRC Exam\\OUTLINES\\Written\\SRO

NRC 2K3 Written Exam 0utline.doc

ES-401

PWR EXAMINATION OUTLINE (SRO)

FORM ES-401-2

System#/Name I K1

I

039 Main and Reheat

Steam I

056 Condensate

059 Main Feedwater

061

Auxiliaty/Emergency

Feedwater

062 AC Electrical

Distribution

063 DC Electrical t

Distribution

064 Emergency

Diesel Generator

073 Process

Radiation Mnitoring

076 Service Water

078 Instrument Air I

103 Containment

KIA Category Point

Totals:

Page 7 Of 11

Plant Systems - Tier 2/Group 1 (SRO)

WA Topic(s)

061A2.05-Ab ryto(a)preact

the mpacls of the lo low.ng

ma IJncuons or operations on the

EFW and (b) based on those

predictions, use procedures to

correct, control, or mitigate the

consequences of those

malfunctions or operations:

Automatic control malfunction.

064A1.03 - Ability to predict

and/or monitor changes in

parameters (to prevent

exceeding design limits)

associated with operating the

ED/G system controls including:

Operating voltages, currents, and

temDeratureS

Group Point Total:

NUREG-1021, DRAFT REV. 9

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

ES-401

PWR EXAMINATION OUTLINE (SRO)

FORM ES-401-2

127 Containment

odine Removal

128 Hydrogen

ieccmbiner and

'urge Control

)29 Containment

'urge

)33 Spent Fuel Pool

ooling

134 Fuel Handling

iquipment

135 Steam Generator

141 Steam

)umptTurbine

iypass Control

033G2.3.10 -Ability to

perfon procedures to reduce

3,3 ,

excessive levels of radiation

and guard against personnel

exposure.

Page 8 of 11

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

NUREG-1021, DRAFT REV. 9

ES-401

PWR EXAMINATION OUTLINE (SRO)

FORM ES-401-2

Plant Systems - Tier 2/Group 2 (SRO)

Page 9 of 11

F\\2003 NRC Exarn\\OUTLlNES\\Written\\SRO NRC 2K3 Written Exam 0utline.doc

NUREG-1021, DRAFT REV. 9

~~

-

ES-401

Generic Knowledge and Abilities Outline (SRO)

Form ES-401-3

-

Facility: Crystal River Unit #3

Date of Exam: August 25,2003

Ability to evaluate plant performance and make

operational judgments based on operating

characteristics, reactor behavior, and instrument

interpretation.

I

")'

Page 14 of 15

F\\2003 NRC Exam\\OUTLINES\\Written\\RO NRC 2K3 Written Exam Outline Rev Ldoc

NUREG-1021. DRAFT REV. 9

ES-401

Record of Rejected KIAs

FORM ES-401-4

1 I2

Reason for Rejection

Tier I

Randomly

Grow

Selected WA

028AK2.07

WA= 1.8

01 5AK2.05

I QA = 1.9

1 WA = 2.2

I 003K3.06

I 007A4.05

KIA = 2.4

I

. .

II 211

I 007A4.02

I WA = 2.2

211

056

059A4.02

WA = 2.3

064K6.02

KIA = 2.4

Only 2 RO WAS,

2.5 in whole system - flipped coin.

II 211

I 013K6.03

I WA = 2.4

212

II 211

1 039A2.02

I WA=2.4

035K4.04

035K4.08

071 K3.01

WA = 2.0

071 K3.03

WA = 2.2

Not applicable at CR #3

Not applicable at CR #3 and WA = 1.9

II 211

I 064K6.06

I WA=2.3

It 212

1 002K1.15

1 WA = 2.2

11 Generic I 2.4.36

1 RO WA = 2.0

Page 15 of 15

F\\2W3 NRC Exarn\\OUTLlNES\\Written\\RO NRC 2K3 Written Exam Outline Rev l.doc

NUREG-1021, DRAFT REV. 9

ML032940423

Text

I

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