ML050200017

Examination Outline Submittals for the Kewanee Retake Examination - Nov 2004

ML050200017
Person / Time
Site:	Kewaunee
Issue date:	11/16/2004
From:	Coutu T Nuclear Management Co
To:	NRC/RGN-III
Shared Package
ML050190172	List: ML050190332 ML050190363 ML050200017 ML050200021
References
50-305/04-302 50-305/04-302
Download: ML050200017 (33)

Text

2004 Kewaunee RO Written Retake Exam Rev. 8 OUTLINE SUBMITTAL-I of 3

- Licensee Letter Transmitting Outline to NRC

- ES-201-2 Examination Outline Quality Checklist

- ES-401-4 & -5 PWR Examination Outline (I

00 questions)

- NRC Outline Comments (NONE)

Committed to Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC July 21, 2004 N RC-04-085 10 CFR 55.40 Regional Administrator, Region Ill U.S. Nuclear Regulatory Commission Attn: Mr. Dell McNeil 2443 Warrenville Road, Suite 21 0 Lisle, IL 60532 - 4352 Kewaunee Nuclear Power Plant Docket 50-305 License No. DPR-43 Reactor Operator Written Examination Materials for Mr. Jason F. Crowlev In accordance with the guidelines NUREG 1021, Operating License Examination Standard for Power Reactors Revision 8, Supplement 1, we are providing you with the Reactor Operator written examination materials for the re-examination of Mr. Jason Crowley, scheduled for the week of August 16, 2004. This package contains the 100 -

question written examination, the reference material supporting the distracters, and form ES-401-7.

NUREG 1021 physical security requirements state that the enclosed examination materials shall be withheld from public disclosure until after the examination is complete.

Please direct any questions or comments regarding this material to Mr. David Fitzwater at 920-388-8387.

Thomas Coutu Site Vice President, Kewaunee Nuclear Power Plant Nuclear Management Company, LLC Enclosures (3) cc w/o enclosures:

Senior Resident Inspector, Kewaunee, USNRC N490 Highway 42 Kewaunee, Wisconsin 54216-951 1 Telephone: 920.388.2560

ES-201 Examination Outline Form ES-201-2 Quality Checklist Item Initials Task Description I

1

1.

W R I T

T E

N

a. Verify that the wtline(s) fit(s) the appropriate model per ES-401.

a b'

, ciy J I#-

b. Assess whether the wtline was systematically and randomly prepared in accordance with Section 0.1 of ES-401 and whether all KIA cateqories are appropriately sampled.

c. Assess whether the wtli overemphasizes any systems, evdutiw, or generic topics.

d. Assess whether the jusWcatiom for deselected cw rejected WA statements are appropriate.

J,./

v J w

3.

W I

T

2.

S I

M

4.

G E

N E

R A

L -

./.

a. Using Form ES-301-5, verify that the proposed scenario sels covef the required number of normal evdutians. instrument and component failures. and major transients.

b. Assess Awlher there are enough scenario sets (and spares) to test the projeaed number and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity; emure each appkant can be tested using at lead one new or sgnirintly modiied scenario, that no scenarios are duplicated from the applicants' audit test(s)',

and scenarios will not be repeated over successive days.

c. To the extent possible, assess whether the autliis) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in

'x D.

I

a. Verifythat (1) the outlii(s) contain(s) the required number of control room and in-plant tasks, (2) no more than 30% of the test material is repeated from the fast NRC examination.

(3)' no tasks are duplicated hom the applicants' audii test(s), and (4) nomorethanEO%danyoper atinq test is taken directly from the i i

s exam banks.

b. Verifythat (1) the tasks are distnbuted among the safety lunction groupings as specified in ES-301, (2) one task is conducted in a low-power or shutdown condition, (3) 40% of the tasks require the a p p l i i to implement an alternate path procedure.

(4) one in-plant task tests the appliint's response to an emergency or abnormal condition, and (5) the in-piant walk-throrqqh requires the applicant to enter the RCA.

c. Verify that the requhed administrative topics are covered, with emphasis on performance-based aaivities.

I f

d. oetermine if there are enough different 0 u U i i to test the projected number and mix of Note:

Not applicabie for NRCdeveloped examinations.

1. Independent NRC reviewer initial items in Column t:'

chief examiner concwrence required.

I I

23 of 24 NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 3

3 3

4 13 Note: 1.

2.

3.

4.

5.

6.*

7.

Ensure that at least two topics from every WA category are sampled within each tier (Le., the Tier Totals in each WA category shall not be less than 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 k1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

Select topics from many systems; avoid selecting more than two or three WA topics from a given system unless they relate to plant-specific priorities.

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

The shaded areas are not applicable to the categoryher.

The generic WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.

On the following pages, enter the WA 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. WAS below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in two).

ES-401 E/APE # / Name / Safety Function 000005 Inoperable/Stuck Control Rod / 1 000015117 RCP Malfunctions 14 BW/EOS; CUA13; W/E09&E10 Natural Circ. 14

~~

000024 Emergency Boration / 1 000026 Loss of Component Cooling Water I 8 000027 Pressurizer Pressure Control System Malfunction / 3 000040 (BW/EO5' CUE05. W/E12) Steam Line Rupture - Excessive Heat transfer 14 CUAI 1 ; W/E08 RCS Overcooling - PTS / 4 000051 Loss of Condenser Vacuum I 4 000055 Station Blackout 16 000057 Loss of Vital AC Elec. Inst. Bus / 6 000062 Loss of Nuclear Service Water / 4 000067 Plant Fire On-site / 9 000068 (BW/A06) Control Room Evac. / 8 000069 (W/EI 4) Loss of CTMT Integrity I 5 000074 (W/E06&E07) Inad. Core Cooling / 4 BW/E03 Inadequate Subcooling Margin 14 000076 High Reactor Coolant Activity / 9 I

BW/A02&A03 LOSS of NNI-XN 17 WA Categoty Totals:

0 Emergency anb Actions contained in EOP for PZR PCS malfunction 1 x 1 2.4.6 - Knowledge symptom based EOP mitigation strategies 1

3.1 1

(1 I

I I

I II

~

16 4

3 Group Point Total:

PWR RO Exa Emergency and Abnormal PI WA Topic(s)

Imp.

3.2 3.2 casualty Manually driving rods into position that existed before start of Thermodynamics and flow characteristics of open or leaking valves Adequate core cooling 4.3 Pumps I ESF actuation system in manual 2.614.4 Points 1

1 1

2 WIEI 1 Loss of Emergency Coolant Recirc. 14 W/EO1 & E02 Re-diagnosis & SI Termination 13 000022 Loss of Reactor Coolant Makeup 1 2 03 02 X

Facilitys heat removal systems, including primary coolant, emergenc coolant, the decay heat removal systems, and relations between tt?e proper operation of these systems to the operation of It._ --:r:A..

Desired operating results during abnormal and emergency situations Operating behavior characteristics of the facility 3.7 1

3.6 1

3.4 2.1.32 -.Ability to explain and apply all systems limits and precautions 1

Pump cavitation Manual trip of main turbine Effects of voltage changes on performance Actions contained in EOP for SIG tube leak Radioactive liquid monitor 3.5 1

I I

3.4 1

4.1 1

4.1 1

4.2 1

Automatic actuation I 3.6

[

1 I

I 2.4.48 - Ability to interpret control room indications to verify the actions and directives adct plant and system conditions.

status and operation of s stem and understand how operator Desired operating results during abnormal and emergency situations I

I I

3.5,.

1 3.8 1

Group Point Total:

I 17 WA Category Point Totals:

2 2

2 7

2 2

PWR RO Exai BWIAO7 Flooding 1 8 CE/Al6 Excess RCS Leakage I 2 W/E13 Steam Generator Over-pressure 1 4 02 I I

WA Category Point Totals:

1 0

1 1

0 0

iination Outline Form ES-401-4 Int Evolutions - Tier l/Group 3 Imp.

Points WA Topic(s)

I I

I Principle of cooling by natural convection 3.7 1

Remote manual loaders 2.7 1

1 Normal, abnormal and emergency operating procedures associated with Steam Generator 2.9 I

I

~

Group Point Total:

3

ES-401 A2 A3 S stem # I Name 001 Control Rod Drive A4 G

WA Topic@)

Imp.

Points 03 NIS and RPS I CRDS mode control 4.514.0 2

003 Reactor Coolant Pump 004 Chemical and Volume Control 01 3 Engineered Safety Features Actuation 015 Nuclear Instrumentation 017 In-core Temperature Monitor 022 Containment Cooling 025 Ice Condenser 056 Condensate 03 059 Main Feedwater 061 AuxilialylEmergency Feedwater 068 Liquid Radwaste 07 071 Waste Gas Disposal 02 072 Area Radiation Monitoring Conditions which exist for an abnormal normal shutdown of an RCP shutdown of an RCP in comparison to a 3.7 1

~

~

WA Category Point Totals:

3 I

04 ESFAS & safeguards equipment control I Sensors and detectors 3,612,7 I

I 01 Reactor trip bypasses 12.1.12 - Ability to apply tech specs for a system 3,9,2,9 x

Manuallautomatic transfers of control I 1 Reason for hydrogen cover gas in VCT I 3.2/2.8 1 I

I I

I I

I Natural circulation indications 3.5 1

Automatic containment isolation 12.1.10 Knowledge of conditions and limitations 3.612.7 2

in the facility license 03 Sources of liquid wastes for LRS 2.7 1

monitoring system alarm and actuating 3.2l3.6 2

ARM and PRM systems I Radiation signals x

MFW 12.4.45; Ability to prioritize and interpret the significance of each annunciator or alarm I 2.613.3 1 2

Radiation levels 12.4.31._ Knowledge of use of the response instructions annunciator alarms and indications, and 3.413.3 2

I I

I I SIGs I Auto isolation of MFW I 3.513.2 I 2

I I

I 1

Relationship between A W flow and RCS heat transfer / AFW source tank 1 3.613.9 1 2

I I I I level 1

1 1

4 Group Point Total:

23

Ir I

079 Station Air 086 Fire Protection WA Category Point Totals:

01 Cross-connect with IAS 2.9 1

x alarms and indications, and use of the 3.3 1

2.4.31 - Knowledge of annunciators response instructions.

20 3

1 4

1 1

1 3

1 2

2 1

Group PointTotal:

ES-401 PWR RO Exami Plant Systems -

I I

I I

I I

I A2 A3 A4 r

WA Category Point Totals:

1 1

1 1

1 0

0 Plant-Specifi G

WA Topic(s)

Imp.

Points Reactivity effects of RHR fill water 2.9 1

Loads cooled by CCWS 3.3 1

C 05

~~

Fuel protection from binding and dropping 2.6 1

Reactor power 3.5 1

Electro-hydraulic control 2.6 1

ESF-actuated MOVs 3.1 1

1 2.4.1 1 - Knowledge of abnormal condition orocedures 3.4 I

I I

I I

I 03 1

Phase A and B isolation I 3.5 1

1 0

1 Group Point Total:

8 Plant-Soecific Prioritv Total: (limit 10)

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-5 WA ##

2.1.2 Facility

Kew Topic Imp.

Points 1

Knowledge of operator responsibilities during all modes of plant ooeration 3.0 Category 2.1.3 2.1.32 Conduct of Operations Knowledge of shift turnover practices 3.0 1

Ability to explain and apply all system limits and precautions 3.4 1

Equipment Control Total 3

2.2.12 Knowledge of surveillance procedures 3.0 1

2.2.13 Knowledge of tagging and clearance procedures 3.6 1

2.2.22 Knowledge of limiting conditions for operations and safety limits 3.4 1

Total 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control requirements control, including permissible levels in excess of those authorized 2.6 2.3.4 Knowledge of radiation exposure limits and contamination 2.5 2.3.9 2.5 Knowledge of the process for performing a containment purge Radiation Control 3

1 1

1 Emergency Procedures/

Plan Total 3

2.4.1 Knowledge of EOP entry conditions and immediate actions steps 4.3 1

2.4.8 Knowledge of how the event-based emergency/abnormal 3.0 operating procedures are used in conjunction with the syrnptom-1 based EOPs 2.4.1 1 Knowledge of abnormal condition procedures 3.4 1

1 2.4.1 6 Knowledge of EOP implementation hierarchy and coordination 3.0 with other support procedures

2004 Kewaunee RO Written Retake Exam Rev. 9 OUTLINE SUBMITTAL-2 of 3

- Licensee Letter Transmitting Outline to NRC

- ES-201-2 Examination Outline Quality Checklist

- ES-401-2, & -3 PWR Examination Outline (75 questions)

- NRC Outline Comments (NONE)

Committed to Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC August 13,2004 NRC-04-096 10 CFR 55 Regional Administrator, Region Ill U.S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 21 0 Lisle, IL 60532 - 4352 Kewaunee Nuclear Power Plant Docket 50-305 License No. DPR-43 Re-application for Mr. Jason F. Crowley for Reactor Operator License The NMC is submitting the sample plan for Mr. Crowleys examination per our phone conversation on August 6, 2004.

The sample plan was randomly generated in accordance with NUREG -1021, ES-401 requirements, using the PWR sample plan generating software distributed by the Westinghouse Owners Group. This software meets the requirements of section D.l.b of that section of the examiners standard. We have enclosed the following forms as prescribed by NUREG -1 021 :

ES-201-2 ES-40 1 -2 ES-40 1 -3 ES-40 1 -4 NUREG 1021 physical security requirements state that the enclosed examination materials shall be withheld from public disclosure until after the examination is complete.

Please contact Mr. Wyatt Godes, Operations Training Group Supervisor, at 920-388-8779 for any issues related to this submittal.

Thomas Coutu Site Vice President, Kewaunee Nuclear Power Plant Nuclear Management Company, LLC Enclosures (4) cc w/o enclosures:

Senior Resident inspector, Kewaunee, USNRC N490 Highway 42 0 Kewaunee, Wisconsin 54216-951 1 Telephone: 920.388.2560

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

Kewaunee Nuclear Power Plant Date of Examination: 1 1 /I 512004 Item Task Description

1.

w

a. Verify that the outline(s) fit@) the appropriate model per ES-401.

b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.l of ES-401 and whether all WA categories are appropriately sampled.

I r

b. Facility Reviewer (")

c. NRC Chief Examiner (#)

d. NRC Supervisor Note:

• Not applicable for NRC-developed examinations.

1. Independent NRC reviewer initial items in Column "c;" chief examiner concurrence required.

NUREG-1021, Draft Revision 9 24 of 25

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

My Power Unit Date Of Exam:

06/01/2004 Printed: 08/11/2004 I

I I

RO WA Category Point:

I SRO-Only Points Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (Le., the "Tier Totals" in each WA category shall not be less than two). Refer to Section D. 1.c for additional guidance regarding the 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 *I 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 WA 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 (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the WA 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 columns labeled "K' and "A".

Use duplicate pages for RO and SROanly exams.

8. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form

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

ES-401-3.

1

PWR RO Examination Outline Printed: 08/1 1/2004 Facility:

My Power Unit ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name /Safety Function 3

000009 Small Break LOCA / 3 000008 Pressurizer Vapor Space Accident /

00001 1 Large Break LOCA / 3 00001 1 Large Break LOCA / 3 000022 Loss of Rx Coolant Makeup / 2 000025 Loss of RHR System / 4 000026 Loss of Component Cooling Water /

000027 Pressurizer Pressure Control System 8

Malfunction / 3 000029 ATWS / 1 000040 Steam Line Rupture - Excessive Heat Transfer / 4 000054 Loss of Main Feedwater / 4 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 000057 Loss of Vital AC Inst. Bus / 6 000062 Loss of Nuclear Svc Water / 4 000065 Loss of Instrument Air / 8 W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 W/El 1 Loss of Emergency Coolant Recirc. /

4 WACategory Totals:

K1 K2 K3 A1 A2 G

KATopic Imp.

Points X

AKl.01 - Thermodynamics and flow 3.2 1

X EA2.39 - Adequate core cooling 4.3 1

X EAl.04 - ESF actuation system in 4.4 1

X EK2.02 - Pumps 2.6*

1 X 2.1.32 - Ability to explain and apply all 3.4 1

X AA2.07 - Pump cavitation 3.4 1

X AK3.03 - Guidance actions contained in 4.0 1

X AK3.03 - Actions contained in EOP for 3.7 1

X EA 1.13 - Manual trip of main turbine 4.1 1

X 2.4.6 - Knowledge symptom based EOP 3.1 1

X 2.4.48 - Ability to interpret control 3.5 1

characteristics of open or leaking valves manual system limits and precautions.

EOP for Loss of CC W PZR PCS malfunction mitigation strategies.

room indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.

X EK3.02 - Actions contained in EOP for 4.3 1

loss of offsite and onsite power X

AKl.01 - Principle of cooling by natural 3.7 1

convection X

AA2.18 - The indicator, valve, breaker, 3.1 1

or damper position which will occur on a loss of power water procedures.

operation of isolating certain equipment from instrument air X 2.4.24 - Knowledge of loss of cooling 3.3 1

X AK3.03 - Knowing effects on plant 2.9 1

X EAI.3 - Desired operating results 3.8 1

during abnormal and emergency situations X

EA 1.3 - Desired operating results 3.7 1

during abnormal and emergency situations 2

1 4

4 3

4 Group Point Total:

18 1

AK3.18 - Actions contained in EOP for control room evacuation emergency task AK2.03 - Personnel access hatch and emergency access hatch 4.2 1

2.8*

1 PWR RO Examination Outline Facility:

My Power Unit Printed: 08/1 1/2004 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function KA Topic Imp.

3.6 4.2 Points 1

1 000005 Inoperable/Stuck Control Rod / 1 AK3.02 - Rod insertion limits 000037 Steam Generator Tube Leak / 3 AK3.07 - Actions contained in EOP for S/G tube leak

~~~~

~~

~~~

00005 1 Loss of Condenser Vacuum / 4 AA2.02 - Conditions requiring reactor and/or turbine trip 3.9 I 000068 Control Room Evac. / 8 000069 Loss of CTMT Integrity / 5 W/E03 LOCA Cooldown - Depress. / 4 EK2.2 - Facility's heat removal systems, 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 3.7 1

~~

~

2.4.18 - Knowledge of the specific bases for EOPs.

2*7 I WE08 RCS Overcooling - PTS / 4 W/EI 0 Natural Circ. / 4 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.4 1

W/El3 Steam Generator Over-pressure / 4 EK3.2 - Normal, abnormal and emergency operating procedures associated with Steam Generator Overpressure 2.9 1

Group Point Total:

9 KIA Category Totals:

1

PWR RO Examination Outline Facility:

My Power Unit l7C - A 0 1 Plant Systems - Tier 2 / Group 1 U" - -."1 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 003 Reactor Coolant Pump X

004 Chemical and Volume Control 004 Chemical and Volume Control X

X 005 Residual Heat Removal X

006 Emergency Core Cooling X

008 Component Cooling Water X

006 Emergency Core Cooling X

0 10 Pressurizer Pressure Control 0 12 Reactor Protection X

0 13 Engineered Safety Features Actuation 01 3 Engineered Safety Features Actuation 022 Containment Cooling X

X X

X 022 Containment Cooling 026 Containment Spray X

039 Main and Reheat Steam X

056 Condensate X

056 Condensate 059 Main Feedwater X

059 Main Feedwater X

06 1 AuxiliaryEmergency X

06 1 Auxiliary/Emergency X

Feedwater Feedwater Printed:

O W 1 1/2004 Form ES-401-2 A4 G KATopic Imp. Point A2.02 - Conditions which 3.7 1

exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP K4.04 - Manual/automatic 3.2 1

transfers of control K5.04 - Reason for 2.8 1

hydrogen cover gas in VCT (oxygen scavenge)

K5.03 - Reactivity effects of 2.9*

1 RHR fill water A 1.1 1 - Boron concentration 3.1 1

K1.07 - MFW System 2.9*

1 K I.02 - Loads cooled by 3.3 1

ccws K3.01-RCS 3.8 1

K6.10 - Permissive circuits 3.3 1

K2.0 1 - ESFASIsafeguards 3.6*

1 equipment control K6.01 - Sensors and 2.7*

1 detectors K4.03 - Automatic 3.6*

1 containment isolation conditions and limitations in the facility license.

A 1.O 1 - Containment 3.9 1

pressure Al.03 - Primary system 2.6 1

temperature indications, and required values, during main steam system warm-up K1.03 - MFW 2.6*

1 X 2.4.45 - Ability to prioritize 3.3 1

and interpret the significance of each annunciator or alarm.

K3.03 - S/GS 3.5 1

K4.19 - Automatic 3.2 1

feedwater isolation of MFW A 1.04 - AFW source tank 3.9 1

level K5.01 - Relationship 3.6 1

between AFW flow and RCS heat transfer X 2.1.10 -Knowledge of 2.7 1

1

PWR RO Examination Outline Facility:

My Power Unit ES - 401 Plant Systems - Tier 2 / Group 1 Printed: 08/11/2004 Form ES-401-2 G KATopic Imp.

Point A3.05 - Safety-related 3.5 1

indicators and controls K3.02 - Components using 3.5 1

DC control power K2.03 - Control power 3.2*

1 A2.01 - Erratic or failed power supply K2.08 - ESF-actuated MOVs X 2.4.11 - Knowledge of abnormal condition 1 procedures.

A2.03 - Phase A and B isolation 1 331* 1 1 Group Point Total:

28 31 2

PWR RO Examination Outline Facility:

My Power Unit KA Topic Imp.

Plant Systems - Tier 2 / Group 2 Points Printed: 0811 1/2004 Form ES-401-2 A4.0 1 - Rod selection control K1.02 - Containment radiation monitor K4.01 - Fuel protection from binding and dropping K1.09 - RCS A3.05 - Electrohydraulic control K1.07 - Sources of liquid wastes for LRS A3.03 - Radiation monitoring system alarm and actuating signals A 1.O 1 - Radiation levels A4.01 - Emergency/essentia' S WS Dumtx

• 3.8 I 1

2.6 I 1

3.2*

K4.0 1 - Cross-connect with IAS 2.9 I '

Group Point Total:

10 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Equipment Control 2.2.12 Knowledge of surveillance procedures.

3.O 1

2.2.13 Knowledge of tagging and clearance procedures.

3.6 1

Category Total:

2 Facility:

My Power Unit 1

2.1.2 I Knowledge of operator responsibilities during all modes of dant oDeration.

Printed: 08/11/2004 Form ES-401-3 3.O Generic Category KA KA Topic Imp.

2.1.32 Points Ability to explain and apply all system limits and precautions.

3.4 Conduct of Operations 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

2.5 I 2.1.3 I Knowledge of shift turnover practices.

I 3.0 2.3.9 I

I I

I I

Knowledge of the process for performing a containment purge.

2.5 4

3 2.4. I Knowledge of EOP entry conditions and 4.3 1

immediate action steps.

Radiation Control 1

2.3.1 I Knowledge of 10 CFR: 20 and related facility I

2.6 radiation control reauirements.

q 3

I I

I I

I Emergency ProceduresPlan I 2.4.1 1 I Knowledge of abnormal condition procedures.

I 3.4 1

I I

I Category Total:

2 Generic Total:

10 I

ES-401 Record of Rejected WAS Form ES-401-+)4 Tier I Group 111 Randomly Reason for Rejection Selected WA 065 AA1.01 Plant does not have equipment that would be considered "remote manual loaders" Replaced with randomly selected WA 065 AK3.03 NUREG-1021, Draft Revision 9 28 of 34

2004 Kewaunee RO Written Retake Exam Rev. 9 OUTLINE SUBMITTAL-3 of 3

- ES-201-2 Examination Outline Quality Checklist

- ES-401-2, & -3 PWR Examination Outline (75 questions)

- ES-401-4 Record of Rejected WAS

- NRC Outline Comments (NONE)

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Kewaunee Nuclear Power Plant Item Task Description -

Date of Examination: 1 1 / I 512004 Initials a

b*

c#

1.

a. Verify that the outline(s) fit(s) the appropriate model per ES-401.

are distributed a is conducted in a pecified in ES-301, c NRC Chief Examiner (#)

d. NRC Supemsor Note:

Not applicable for NRC-developed examinations.

1. Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

NUREG-1021, Draft Revision 9 24 of 25

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

Kewaunee Nuclear Power Plant Date Of Exam:

1111 5/2004 Printed: 1011 5/2004

3. Generic Knowledge And Abilities Categories SRO-Only Points Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (Le., the "Tier Totals" in each WA category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the 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 &I 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 WA 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 (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the WA 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 columns labeled "K' and "A".

Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form

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

ES-401-3.

1

PWR RO Examination Outline Facility:

Kewaunee Nuclear Power Plant K1 X

X Printed: 1011 512004 K2 X

2 1

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

X KA Topic AK 1.O 1 - Thermodynamics and flow characteristics of open or leaking valves EA2.39 - Adequate core cooling EAl.04 - ESF actuation system in manual EK2.02 - Pumps 2.1.32 - Ability to explain and apply all system limits and precautions.

X 2.4.48 - Ability to interpret control room indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.

4 3

4 Group Point Total:

18 EIAPE # / Name / Safety Function 000008 Pressurizer Vapor Space Accident I 3

000009 Small Break LOCA 1 3 0000 1 1 Large Break LOCA I 3 0000 1 1 Large Break LOCA I 3 000022 Loss of Rx Coolant Makeup 12 T

000025 Loss of RHR System 1 4 I X I I AA2.07 - Pump cavitation 3.4 I 1

000026 Loss of Component Cooling Water I 8

X 4.0 I AK3.03 - Guidance actions contained in EOP for Loss of CCW X

3.7 I 000027 Pressurizer Pressure Control System Malfunction 13 AK3.03 - Actions contained in EOP for PZR PCS malfunction 000029 ATWS I 1 x I I I EA1.13 - Manual trip of main turbine 4.1 I 1

T 000040 Steam Line Rupture - Excessive Heat Transfer 14 2.4.6 - Knowledge symptom based EOP mitigation strategies.

000054 Loss of Main Feedwater 1 4 3.7 X

~~ I I I EK3.02 - Actions contained in EOP for 000055 Station Blackout 16 I

I I loss of offsite and onsite power 000056 Loss of Off-site Power I 6 i

AK1.O1 - Principle of cooling by natural convection AA2.18 - The indicator, valve, breaker, or damper position which will occur on a loss of power 000057 Loss of Vital AC Inst. Bus 1 6 X -

000062 Loss of Nuclear Svc Water 14 2.4.24 - Knowledge of loss of cooling water procedures.

AK3.03 - Knowing effects on plant operation of isolating certain equipment from instrument air 000065 Loss of Instrument Air I 8

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1 EA1.3 - Desired operating results WE05 Inadequate Heat Transfer - Loss of Secondary Heat Sink I 4 during abnormal and emergency situations WE1 1 Loss of Emergency Coolant Recirc. I 4

EAl.3 - Desired operating results during abnormal and emergency situations 4 -

KIA Category Totals:

1

PWR RO Examination Outline Printed: 10/15/2004 Facility:

Kewaunee Nuclear Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 K3 X

X X

I X

I 4

EIAPE # / Name I Safety Function I K1 A1 A2 X

X 0

2 000005 Inoperable/Stuck Control Rod / 1 I

000037 Steam Generator Tube Leak / 3 00005 1 Loss of Condenser Vacuum / 4 000068 Controi Room Evac. / 8 000069 Loss of CTMT Integrity / 5 WE03 LOCA Cooldown - Depress. / 4 WE08 RCS Overcooling - PTS / 4 W/E 10 Natural Circ. / 4 W/E13 Steam Generator Over-pressure / 4 WA Category Totals:

0 X

AK3.07 - Actions contained in EOP for S/G tube leak EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and i

amendments AA2.02 - Conditions requiring reactor and/or turbine trip AK3.18 - Actions contained in EOP for control room evacuation emergency task

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AK2.03 - Personnel access hatch and r

emergency access hatch EK2.2 - Facility's heat removal systems, 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 2.4.18 - Knowledge of the specific bases for EOPs.

EK3.2 - Normal, abnormal and emergency operating procedures associated with Steam Generator Overpressure Group Poir 1 1

-Imp. I Points

---I-t Total:

9 1

PWR RO Examination Outline Facility:

Kewaunee Nuclear Power Plant Plant Systems - Tier Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 003 Reactor Coolant Pump ES - 401 004 Chemical and Volume Control 004 Chemical and Volume Control X

2 / Group 1

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Printed: 10/15/2004 Form ES-401-2 A4 G KATopic A2.02 - Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP K4.04 - ManuaVautomatic transfers of control K5.04 - Reason for hydrogen cover gas in VCT (oxygen scavenge)

X A4.07 - Boration/dilution K5.03 - Reactivity effects of A 1.1 1 - Boron concentration I

I I K1.02 - Loads cooled by ccws K3.01 - RCS X

X detectors 2.1.10 - Knowledge of conditions and limitations in the facilitv license.

A 1.O 1 - Containment pressure A 1.03 - Primary system temperature indications, and required values, during main steam system warm-up 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.

K1.03 - MFW K3.03 - S/GS K4.19 - Automatic feedwater isolation of MFW

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A1.04 - AFW source tank level K5.01 - Relationship between AFW flow and RCS heat transfer A3.05 - Safety-related indicators and controls 3.5 1

3.2 1

3.9 1

3.6 1

3.5 1

1

PWR RO Examination Outline Facility:

Kewaunee Nuclear Power Plant Sys/Evol ## / Name 063 DC Electrical Distribution ES - 401 K1 I 064 Emergency Diesel Generator I

I 1 073 Process Radiation Monitoring 076 Service Water I 076 Service Water I X 078 Instrument Air 103 Containment l 3 WA Category Totals:

Plant Systems - Tier 2 / Group 1 Printed: 10/15/2004 Form ES-401-2 KA Topic K3.02 - Components using DC control Dower K2.03 - Control power A2.0 1 - Erratic or failed power supply K2.08 - ESF-actuated MOVs K1.05 - ED/G 2.4.1 1 - Knowledge of abnormal condition mocedures.

A2.03 - Phase A and B isolation Imp.

Points

-t; 3.2* I 1 &-

3*5* I Group Point Total:

28 2

PWR RO Examination Outline Facility:

Kewaunee Nuclear Power Plant Sys/Evol# / Name Printed:

10/15/2004 K1 K2 I

0 14 Rod Position Indication K3 0

0 029 Containment Purge 034 Fuel Handling Equipment I

X 035 Steam Generator I X 045 Main Turbine Generator I

068 Liquid Radwaste 07 1 Waste Gas Disposal 072 Area Radiation Monitoring I

075 Circulating Water 079 Station Air K/A Category Totals: -

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

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline 2.1.32 Printed: 10/15/2004 Form ES-401-3 Ability to explain and apply all system limits and 3.4 1

precautions.

Facilitv:

Kewaunee Nuclear Power Plant Generic Categorv Conduct of Operations KA KA Topic Zmp.

Points I

I I

1 2.1.2 I

3.0 I I

Knowledge of operator responsibilities during all modes of plant operation.

2.1.3 Knowledge of shift turnover practices.

3.0 I 1

1 Equipment Control Knowledge of surveillance procedures.

Knowledge of tagging and clearance procedures.

2.2.12 2.2.13 Category Total:

2 Radiation Control Knowledge of 10 CFR: 20 and related facility radiation control reauirements.

2.6 1

2.3.1 2.3.4 2.3.9

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Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

Knowledge of the process for performing a containment purge.

Category Total:

2.5 1

2.5 1

3 2.4.1 t 2.4.1 1 Knowledge of EOP entry conditions and immediate action steps.

Knowledge of abnormal condition procedures.

Emergency ProceduresPlan I

Category Total:

Generic Total:

10 1

ES-401 Record of Rejected WAS Form ES-401-4-04 Tier I Group 111

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Randomly Reason for Rejection Selected WA 076 K1.05 Plant does not have equipment that would be considered "remote manual loaders".

I Replaced with randomly Selected WA 065 AK3.03.

NUREG-1021, Draft Revision 9 28 of 34