ML050200017

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Examination Outline Submittals for the Kewanee Retake Examination - Nov 2004
ML050200017
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 11/16/2004
From: Coutu T
Nuclear Management Co
To:
NRC/RGN-III
Shared Package
ML050190172 List:
References
50-305/04-302 50-305/04-302
Download: ML050200017 (33)
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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 (I00 questions)

- NRC Outline Comments (NONE)

Committed to Kewaunee Nuclear Power Plant Operated by Nuclear Management Company, LLC July 21, 2004 NRC-04-085 10 CFR 55.40 Regional Administrator, Region Ill U.S. Nuclear Regulatory Commission Attn: Mr. Dell McNeil 2443 Warrenville Road, Suite 210 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 54216-9511 Telephone: 920.388.2560

ES-201 Examination Outline Form ES-201-2 Quality Checklist Initials Item Task Description I 1

- a b' , ciy

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

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

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c. Assess whether the w t l i overemphasizes any systems, evdutiw, or generic topics. J ,./ v N d. Assess whether the jusWcatiom for deselected cw rejected WA statements are appropriate. Jw
2. 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. ./.

S I b. Assess Awlher there are enough scenario sets (and spares) to test the projeaed number and M 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 s g n i r i n t l y 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 f

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

I (3)' no tasks are duplicated hom the applicants' audii test(s), and T (4) nomorethanEO%danyoperatinq 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

d. oetermine if there are enough different 0 u U i i to test the projected number and mix of 4.

G E

N E

R A

L I

Note: Not applicabie for NRCdeveloped examinations.

  1. Independent NRC reviewer initial items in Column t:'chief examiner concwrence required. 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 13 3 3 3 4 Note: 1. 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 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 k1 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 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 categoryher.

6.* 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.

7. 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

ES-401 0 Emergency anb E/APE # / Name / Safety Function 000005 Inoperable/Stuck Control Rod / 1 000015117 RCP Malfunctions 14 BW/EOS; CUA13; W/E09&E10 Natural Circ. 1 4

~~

000024 Emergency Boration / 1 000026 Loss of Component Cooling Water I 8 000027 Pressurizer Pressure Control System Actions contained in EOP for PZR PCS malfunction Malfunction/ 3 000040 (BW/EO5' CUE05. W/E12) Steam Line Rupture - Excessive Heat transfer 1 4 1 1 x 2.4.6 - Knowledge symptom based EOP mitigation strategies 1 3.1 1 (1 CUAI 1; W/E08 RCS Overcooling - PTS / 4 000051 Loss of Condenser Vacuum I 4 000055 Station Blackout 1 6 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 Margin1 4 I

000076 High Reactor Coolant Activity / 9 I I I I BW/A02&A03 LOSSof NNI-XN 1 7

~

I WA Categoty Totals: 4 3 Group Point Total: 16

PWR RO Exa Emergency and Abnormal PI WA Topic(s) Imp. Points Manually driving rods into position that existed before start of casualty 3.2 1 Thermodynamics and flow characteristicsof open or leaking valves 3.2 1 Adequate core cooling 4.3 1 Pumps I ESF actuation system in manual 2.614.4 2 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..

WIEI 1 Loss of Emergency Coolant Recirc. 14 03 Desired operating results during abnormal and emergency situations 3.7 1 W/EO1 & E02 Re-diagnosis & SI Termination 1 3 02 Operating behavior characteristicsof the facility 3.6 1 000022 Loss of Reactor Coolant Makeup 1 2 X 2.1.32 -.Ability to explain and apply all systems limits and 3.4 1 precautions Pump cavitation 3.4 1 Manual trip of main turbine 4.1 1 Effects of voltage changes on performance 4.1 1 Actions contained in EOP for SIG tube leak 4.2 1 2.4.48 - Ability to interpret control room indications to verify the status and operation of s stem and understand how operator 3.5,. 1 actions and directives a d c t plant and system conditions.

Desired operating results during abnormal and emergency situations 3.8 1 Radioactive liquid monitor 3.5 1 I I Automatic actuation I I

3.6 [

I 1

I I I

WA Category Point Totals: 2 2 2 7 2 2 Group Point Total: I 17

PWR RO Exai iination Outline Form ES-401-4 Int Evolutions Tier l/Group 3 WA Topic(s) Imp. Points I I I

Principle of cooling by natural convection 3.7 1 Remote manual loaders 2.7 1 BWIAO7 Flooding 1 8 CE/Al6 Excess RCS Leakage I 2 W/E13 Steam Generator Over-pressure 1 4 02 Normal, abnormal and emergency operating procedures associated 2.9 1 with Steam Generator I

I I

I WA Category Point Totals: 1 0 1 1 0 0 Group Point Total: 3

~

ES-401 S stem # I Name A2 A3 A4 G WA Topic@) Imp. Points 001 Control Rod Drive 03 NIS and RPS I CRDS mode control 4.514.0 2 Conditions which exist for an abnormal 003 Reactor Coolant Pump 02 shutdown of an RCP in comparison to a 3.7 1 normal shutdown of an RCP 004 Chemical and Volume Control I I I 1

I Manuallautomatic transfers of control I Reason for hydrogen cover gas in VCT I

I 3.2/2.8 1 I

013 Engineered Safety Features Actuation ESFAS & safeguards equipment control I 3,612,7 Sensors and detectors I I I 015 Nuclear Instrumentation Reactor trip bypasses 12.1.12 - Ability to 3,9,2,9 apply tech specs for a system 017 In-coreTemperature Monitor Natural circulation indications 3.5 1 Automatic containment isolation 12.1.10 022 Containment Cooling x ;Knowledge of conditions and limitations 3.612.7 2 in the facility license 025 Ice Condenser 056 Condensate 03 MFW 12.4.45; Ability to prioritize and interpret the significanceof each annunciator or alarm I 1 2.613.3 2 059 Main Feedwater I I I II SIGs I Auto isolation of MFW II 3.513.2 II 2 061 AuxilialylEmergencyFeedwater 04 I I I I Relationship between A W flow and RCS heat transfer / AFW source tank level 1 3.613.9 1 2 068 Liquid Radwaste 07 Sources of liquid wastes for LRS 2.7 1 ARM and PRM systems I Radiation 071 Waste Gas Disposal 03 monitoring system alarm and actuating 3.2l3.6 2 signals 072 Area Radiation Monitoring 01 x Radiation levels 12.4.31 Knowledge of annunciator alarms and indications, and 3.413.3 2 use of the response instructions

~ ~

1 WA Category Point Totals: 3 1 1 1 4 Group Point Total: 23

Ir I 079 Station Air 01 Cross-connectwith IAS 2.9 1 2.4.31 - Knowledge of annunciators 086 Fire Protection x alarms and indications, and use of the 3.3 1 response instructions.

WA Category Point Totals: 3 1 4 1 1 1 3 1 2 2 1 Group PointTotal: 20

ES-401 PWR RO Exami Plant Systems -

I I I I I I I A2 A3 A4 G WA Topic(s) Imp. Points Reactivity effects of RHR fill water 2.9 1 Loads cooled by CCWS 3.3 1 I I I I I I

~~

Fuel protection from binding and dropping 2.6 1 Reactor power 3.5 1 05 Electro-hydrauliccontrol 2.6 1 ESF-actuated MOVs 3.1 1 2.4.11 - Knowledge of abnormal condition 3.4 1 orocedures r

03 Phase A and B isolation I 3.5 1 WA Category Point Totals: 1 1 1 1 1 0 0 1 1 0 1 Group Point Total: 8 Plant-SpecifiC Plant-Soecific Prioritv Total: (limit 10)

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Kew Category WA ## Topic Imp. Points 2.1.2 Knowledge of operator responsibilities during all modes of plant ooeration 3.0 1 Conduct of Operations 2.1.3 Knowledge of shift turnover practices 3.0 1 2.1.32 Ability to explain and apply all system limits and precautions 3.4 1 Total ' 3 2.2.12 Knowledge of surveillance procedures 3.0 1 Equipment 2.2.13 Knowledge of tagging and clearance procedures 3.6 1 Control 2.2.22 Knowledge of limiting conditions for operations and safety limits 3.4 1 Total 3 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control 2.6 1

requirements Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination 2.5 1

control, including permissible levels in excess of those authorized 2.3.9 Knowledge of the process for performing a containment purge 2.5 1 Total 3 2.4.1 Knowledge of EOP entry conditions and immediate actions steps 4.3 1 Emergency 2.4.8 Knowledge of how the event-based emergency/abnormal 3.0 Procedures/ operating procedures are used in conjunctionwith the syrnptom- 1 based EOPs Plan 2.4.1 1 Knowledge of abnormal condition procedures 3.4 1 2.4.1 6 Knowledge of EOP implementation hierarchy and coordination 3.0 1

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 210 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-401-2 ES-401-3 ES-401-4 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 54216-9511 Telephone: 920.388.2560

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Kewaunee Nuclear Power Plant 512004 Date of Examination: 11/I Item Task Description

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

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

r &

b. Facility Reviewer (")
c. NRC Chief Examiner (#)
d. NRC Supervisor Note:
  • Not applicable for NRC-developed examinations.
  1. IndependentNRC 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 Printed: 08/11/2004 Date Of Exam: 06/01/2004 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 *Ifrom 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 ES-401-3.
9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

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 K1 K2 K3 A1 A2 G KATopic Imp. Points 000008 Pressurizer Vapor Space Accident / X AKl.01 - Thermodynamics and flow 3.2 1 3 characteristics of open or leaking valves 000009 Small Break LOCA / 3 X EA2.39 - Adequate core cooling 4.3 1 00001 1 Large Break LOCA / 3 X EAl.04 - ESF actuation system in 4.4 1 manual 00001 1 Large Break LOCA / 3 X EK2.02 - Pumps 2.6* 1 000022 Loss of Rx Coolant Makeup / 2 X 2.1.32 - Ability to explain and apply all 3.4 1 system limits and precautions.

000025 Loss of RHR System / 4 X AA2.07 - Pump cavitation 3.4 1 000026 Loss of Component Cooling Water / X AK3.03 - Guidance actions contained in 4.0 1 8 EOP for Loss of CCW 000027 Pressurizer Pressure Control System X AK3.03 - Actions contained in EOP for 3.7 1 Malfunction / 3 PZR PCS malfunction 000029 ATWS / 1 X EA 1.13 - Manual trip of main turbine 4.1 1 000040 Steam Line Rupture - Excessive X 2.4.6 - Knowledge symptom based EOP 3.1 1 Heat Transfer / 4 mitigation strategies.

000054 Loss of Main Feedwater / 4 X 2.4.48 - Ability to interpret control 3.5 1 room indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.

000055 Station Blackout / 6 X EK3.02 - Actions contained in EOP for 4.3 1 loss of offsite and onsite power 000056 Loss of Off-site Power / 6 X AKl.01 - Principle of cooling by natural 3.7 1 convection 000057 Loss of Vital AC Inst. Bus / 6 X AA2.18 - The indicator, valve, breaker, 3.1 1 or damper position which will occur on a loss of power 000062 Loss of Nuclear Svc Water / 4 X 2.4.24 - Knowledge of loss of cooling 3.3 1 water procedures.

000065 Loss of Instrument Air / 8 X AK3.03 - Knowing effects on plant 2.9 1 operation of isolating certain equipment from instrument air W/E05 Inadequate Heat Transfer - Loss of X EAI.3 - Desired operating results 3.8 1 Secondary Heat Sink / 4 during abnormal and emergency situations W/El 1 Loss of Emergency Coolant Recirc. / X EA 1.3 - Desired operating results 3.7 1 4 during abnormal and emergency situations WACategory Totals: 2 1 4 4 3 4 Group Point Total: 18 1

PWR RO Examination Outline Printed: 08/1 1/2004 Facility: My Power Unit ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # / Name / Safety Function KA Topic Imp. Points 000005 Inoperable/Stuck Control Rod / 1 AK3.02 - Rod insertion limits 3.6 1 000037 Steam Generator Tube Leak / 3 AK3.07 - Actions contained in EOP for 4.2 1 S/G tube leak

~~~~ ~~ ~~~

00005 1 Loss of Condenser Vacuum / 4 000068 Control Room Evac. / 8 AA2.02 - Conditions requiring reactor and/or turbine trip AK3.18 - Actions contained in EOP for 3.9 4.2 I 1 control room evacuation emergency task 000069 Loss of CTMT Integrity / 5 AK2.03 - Personnel access hatch and 2.8* 1 emergency access hatch W/E03 LOCA Cooldown - Depress. / 4 EK2.2 - Facility's heat removal systems, 3.7 1 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

~~ ~

WE08 RCS Overcooling - PTS / 4 W/EI 0 Natural Circ. / 4 2.4.18 - Knowledge of the specific bases for EOPs.

EA2.2 - Adherence to appropriate 2*7 3.4 I 1 procedures and operation within the limitations in the facility's license and amendments W/El3 Steam Generator Over-pressure / 4 EK3.2 - Normal, abnormal and 2.9 1 emergency operating procedures associated with Steam Generator Overpressure KIA Category Totals: Group Point Total: 9 1

PWR RO Examination Outline Printed: O W 1 1/2004 Facility: My Power Unit l7C - A01 U" - -."1 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Point 003 Reactor Coolant Pump X A2.02 - Conditions which 3.7 1 exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP 004 Chemical and Volume Control X K4.04 - Manual/automatic 3.2 1 transfers of control 004 Chemical and Volume Control X -

K5.04 Reason for 2.8 1 hydrogen cover gas in VCT (oxygen scavenge) 005 Residual Heat Removal X K5.03 - Reactivity effects of 2.9* 1 RHR fill water 006 Emergency Core Cooling X A 1.1 1 - Boron concentration 3.1 1 006 Emergency Core Cooling X -

K1.07 MFW System 2.9* 1 008 Component Cooling Water X K I .02 - Loads cooled by 3.3 1 ccws 0 10 Pressurizer Pressure Control X K3.01- RCS 3.8 1 0 12 Reactor Protection X K6.10 - Permissive circuits 3.3 1 0 13 Engineered Safety Features X K2.0 1 - ESFASIsafeguards 3.6* 1 Actuation equipment control 013 Engineered Safety Features X K6.01 - Sensors and 2.7* 1 Actuation detectors 022 Containment Cooling X K4.03 - Automatic 3.6* 1 containment isolation 022 Containment Cooling X 2.1.10 -Knowledge of 2.7 1 conditions and limitations in the facility license.

026 Containment Spray X A 1 .O 1 - Containment 3.9 1 pressure 039 Main and Reheat Steam X Al.03 - Primary system 2.6 1 temperature indications, and required values, during main steam system warm-up 056 Condensate X K1.03 - MFW 2.6* 1 056 Condensate X 2.4.45 - Ability to prioritize 3.3 1 and interpret the significance of each annunciator or alarm.

059 Main Feedwater X K3.03 - S/GS 3.5 1 059 Main Feedwater X K4.19 - Automatic 3.2 1 feedwater isolation of MFW 06 1 AuxiliaryEmergency X A 1.04 - AFW source tank 3.9 1 Feedwater level 06 1 Auxiliary/Emergency X K5.01 - Relationship 3.6 1 Feedwater between AFW flow and RCS heat transfer 1

PWR RO Examination Outline Printed: 08/11/2004 Facility: My Power Unit ES - 401 Plant Systems - Tier 2 / Group 1 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 1

K2.08 - ESF-actuated 1 11 MOVs X 2.4.11 - Knowledge of abnormal condition procedures.

A2.03 - Phase A and B 331*

isolation 31 Group Point Total: 28 2

PWR RO Examination Outline Printed: 0811 1/2004 Facility: My Power Unit Plant Systems - Tier 2 / Group 2 Form ES-401-2 KA Topic Imp. Points A4.0 1 - Rod selection control K1.02 - Containment radiation monitor K4.01 - Fuel protection from binding and dropping K1.09 - RCS 3.8 I 1 A3.05 - Electrohydraulic control 2.6 I 1 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' 3.2*

S WS Dumtx 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 Printed: 08/11/2004 Facility: My Power Unit Form ES-401-3 4

Generic Category KA

_. KA Topic Imp. Points Conduct of Operations 1 2.1.2 I Knowledge of operator responsibilities during all modes of dant oDeration.

3 .O I 2.1.3 I Knowledge of shift turnover practices. I I

3.0 I

I I I 2.1.32 Ability to explain and apply all system limits and 3.4 precautions.

3 Equipment Control 2.2.12 Knowledge of surveillance procedures. 3 .O 1 2.2.13 Knowledge of tagging and clearance procedures. 3.6 1 q

Category Total: 2 Radiation Control 1 2.3.1 I Knowledge of 10 CFR: 20 and related facility radiation control reauirements.

I 2.6 2.3.4 Knowledge of radiation exposure limits and 2.5 contamination control, including permissible levels in excess of those authorized.

2.3.9 Knowledge of the process for performing a 2.5 3 containment purge.

I I I I I Emergency ProceduresPlan 2.4. I Knowledge of EOP entry conditions and 4.3 1 immediate action steps.

I 2.4.1 1 I I

Knowledge of abnormal condition procedures. I I

3.4 I

1 Category Total: 2 Generic Total: 10 I

ES-401 Record of Rejected WAS Form ES-401-+)4 Tier I Randomly Reason for Rejection Group Selected WA 111 065 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 Date of Examination: 11/ I 512004 Initials Item Task Description -

a b* c#

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

are distributed a pecified in ES-301, is conducted in a 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 Printed: 10115/2004 Date Of Exam: 11115/2004 SRO-Only Points

3. Generic Knowledge And Abilities Categories 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 ES-401-3.
9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

1

PWR RO Examination Outline Printed: 1011512004 Facility: Kewaunee Nuclear Power Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 EIAPE # / Name / Safety Function K1 K2 G KA Topic 000008 Pressurizer Vapor Space Accident I X AK 1.O 1 - Thermodynamics and flow 3 characteristics of open or leaking valves 000009 Small Break LOCA 1 3 EA2.39 - Adequate core cooling 0000 11 Large Break LOCA I 3 EAl.04 - ESF actuation system in manual 0000 11 Large Break LOCA I 3 X EK2.02 - Pumps 000022 Loss of Rx Coolant Makeup 1 2 000025 Loss of RHR System 1 4 X 2.1.32 - Ability to explain and apply all system limits and precautions.

I X I IAA2.07 - Pump cavitation T3.4 I 1 000026 Loss of Component Cooling Water I 8

X AK3.03 - Guidance actions contained in EOP for Loss of CCW 4.0 I 000027 Pressurizer Pressure Control System Malfunction 1 3 X AK3.03 - Actions contained in EOP for PZR PCS malfunction 3.7 II 000029 ATWS I 1 xI I IEA1.13 - Manual trip of main turbine 4.1 1 T

000040 Steam Line Rupture - Excessive 2.4.6 - Knowledge symptom based EOP Heat Transfer 1 4 mitigation strategies.

000054 Loss of Main Feedwater 1 4 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.

000055 Station Blackout 1 6 X I I IEK3.02 - Actions contained in EOP for I I Iloss of offsite and onsite power

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i 000056 Loss of Off-site Power I 6 X AK1.O1 - Principle of cooling by natural 3 .7 convection 000057 Loss of Vital AC Inst. Bus 1 6 AA2.18 - The indicator, valve, breaker, or damper position which will occur on a loss of power 000062 Loss of Nuclear Svc Water 1 4 X 2.4.24 - Knowledge of loss of cooling water procedures.

000065 Loss of Instrument Air I 8 AK3.03 - Knowing effects on plant operation of isolating certain equipment from instrument air 1 EA1.3 - Desired operating results

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WE05 Inadequate Heat Transfer - Loss of Secondary Heat Sink I 4 during abnormal and emergency situations W E 1 1 Loss of Emergency Coolant Recirc. I EAl.3 - Desired operating results 4 during abnormal and emergency situations KIA Category Totals: 2 1 4 4 3 4 Group Point Total: 18 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 EIAPE # / Name I Safety Function I K1 K3 A1 A2 -Imp. I Points 000005 Inoperable/Stuck Control Rod / 1 I X 000037 Steam Generator Tube Leak / 3 X AK3.07 - Actions contained in EOP for S/G tube leak 00005 1 Loss of Condenser Vacuum / 4 X AA2.02 - Conditions requiring reactor and/or turbine trip 000068 Controi Room Evac. / 8 X AK3.18 - Actions contained in EOP for control room evacuation emergency task 000069 Loss of CTMT Integrity / 5 r ~~~

emergency access hatch

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AK2.03 - Personnel access hatch and WE03 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

-I WE08 RCS Overcooling - PTS / 4 X 2.4.18 - Knowledge of the specific bases for EOPs.

W/E 10 Natural Circ. / 4 X EA2.2 - Adherence to appropriate I ' procedures and operation within the limitations in the facility's license and i amendments W/E13 Steam Generator Over-pressure / 4 X EK3.2 - Normal, abnormal and emergency operating procedures I associated with Steam Generator Overpressure WA Category Totals: 0 ' 4 0 2 ' 11 Group Poir t Total: 9 1

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PWR RO Examination Outline Printed: 10/15/2004 Facility: Kewaunee Nuclear Power Plant ES - 401 Plant Systems Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A4 G KATopic 003 Reactor Coolant Pump A2.02 - Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP 004 Chemical and Volume Control X K4.04 - ManuaVautomatic transfers of control 004 Chemical and Volume 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 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 K1.03 - MFW X 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.

K3.03 - S/GS 3.5 1 K4.19 - Automatic 3.2 1

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feedwater isolation of MFW A1.04 - AFW source tank 3.9 1 level K5.01 - Relationship 3.6 1 between AFW flow and RCS heat transfer X A3.05 - Safety-related 3.5 1 indicators and controls 1

PWR RO Examination Outline Printed: 10/15/2004 Facility: Kewaunee Nuclear Power Plant ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol ## / Name 063 DC Electrical Distribution I 064 Emergency Diesel Generator I K1 KA Topic K3.02 - Components using DC control Dower K2.03 - Control power

-t; Imp.

3.2* I Points 1

1 073 Process Radiation Monitoring 076 Service Water I 076 Service Water I

I X A2.0 1 - Erratic or failed power supply K2.08 - ESF-actuated MOVs K1.05 - ED/G 078 Instrument Air 2.4.1 1 - Knowledge of abnormal condition mocedures.

103 Containment A2.03 - Phase A and B isolation 3*5* I WA Category Totals:

l3 Group Point Total: 28 2

PWR RO Examination Outline Printed: 10/15/2004 Facility: Kewaunee Nuclear Power Plant Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Evol# / Name K1 K2 K3 0 14 Rod Position Indication I X 029 Containment Purge 034 Fuel Handling Equipment I

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 0 0 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 10/15/2004 Facilitv: Kewaunee Nuclear Power Plant Form ES-401-3 Generic Categorv -

KA KA Topic Zmp. Points I I I 1 Conduct of Operations 2.1.2 Knowledge of operator responsibilities during all modes of plant operation. I 3.0 I I 2.1.3 Knowledge of shift turnover practices. 3.0 I 1 1 2.1.32 Ability to explain and apply all system limits and 3.4 1 precautions.

Equipment Control 2.2.12 Knowledge of surveillance procedures.

2.2.13 Knowledge of tagging and clearance procedures.

Category Total: 2 Radiation Control 2.3.1 Knowledge of 10 CFR: 20 and related facility 2.6 1 radiation control reauirements.

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2.3.4 Knowledge of radiation exposure limits and 2.5 1 contamination control, including permissible levels in excess of those authorized.

2.3.9 Knowledge of the process for performing a 2.5 1 containment purge.

Category Total: 3 Emergency ProceduresPlan t

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

Knowledge of abnormal condition procedures.

Category Total:

Generic Total: 10 1

ES-401 Record of Rejected WAS Form ES-401-4-04

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Tier I Randomly Reason for Rejection Group Selected WA 111 076 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

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