ML052430747

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Examination Outline Cover Letter and Written Examination Outline Submittal for the Clinton Initial Examination - July 2005
ML052430747
Person / Time
Site: Clinton Constellation icon.png
Issue date: 07/18/2005
From: Setser G
AmerGen Energy Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML052430228 List:
References
50-461/05-301 50-461/05-301
Download: ML052430747 (35)
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Text

EXAMINATION OUTLINE COVER LETTER AND WRITTEN EXAMINATION OUTLINE SUBMITTAL FOR THE CLINTON INITIAL EXAMINATION - JULY 2005

- An ExelonCompany ClintonPower Station R. R. 3, Box 228 Clinton, IL 61727 U-603722 April 7, 2005 Mr. James L. Caldwell Regional Administrator U. S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, Illinois 60532-4352 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461

Subject:

Submittal of Initial License Training Examination Outline

- Enclosed are the examination outlines which Amergen Energy Company (AmerGen), LLC is submitting in support of the Initial License Examination scheduled for the weeks of 7/11/2005 and 7/18/2005 at Clinton Power Station.

This submittal includes the all appropriate Examination Standard forms and outlines in accordance with NUREG-1021, Operator Licensing Examination Standards, Revision 9.

In accordance with NUREG-1021, Section ES-201, Initial Operator Licensing Examination Process, please ensure that these materials are withheld from public disclosure until after the examinations are complete.

Should you have any questions related to this information, please contact Mr. Gary Setser at (217) 937-4122.

Respectfully, William S. lliff Regulatory Assurance Manager Clinton Power Station EET/blf APR 11 2005

U-603722 U.S. Nuclear Regulatory Commission Page 2 of 2

-- Attachments: (Hand delivered to NRC Region 111 Chief Examiner/or Designee)

Examination Security Agreement (Form ES-201-3),

Administrative Topics Outline (Form ES-301-I),

Control Room/ln-Plant Systems Outline (Form ES-301-2),

BWR Examination Outline (Form ES-401-1),

Record of Rejected WAS (Form ES-401-4),

Operational Scenarios Outline (Form ES-D-I),

Examination Outline Quality Checklist (Form ES-201-2), and Transient and Event Checklist (Form ES-301-5).

Outline Methodology for 2004 Clinton Power Station Written NRC Exam Clinton Power Station Suppressed WAS cc: R. S. Bement, V-275 (w/o Attachments)

M. D. McDowell, T-31A (w/o Attachments)

T. J. Shortell, V-922 (w/o Attachments)

A. D. Bailey, V-922 (w/o Attachments)

G. D. Setser, V-922 (w/o Attachments)

INITIAL RO WRITTEN EXAMINATION OUTLINE SUBMITTAL FOR THE CLINTON INITIAL EXAMINATION -JULY 2005

ES-401 BWR Examination Outline Form ES-401-1 Facilitv: Clinton Power Station Printed: 04/07/2005 Date Of Exam: 01/31/2005 RO K/A Category Points I SRO-Only Points Note:

1. Ensure that at least b o topics from every KIA category are sampied within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA cabgory shall not be less than two).
2. The point total for each goup and tier in the proposed outline must match that specified in the table. The find point total for each group and tier may deviate by flfrom 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. Systems/evdutions within each group are identified on the associated outline; systems or evolutions that do not apply at the faality should be deleted and justified; operationally important, sitespecific systems that are not included on the outline should be added. Refer to ES401, Attachment 2, for guidance regarding the elimination of inappmpnate WA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system a-evdubn.
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selecbd. Use the RO and SRO ratings for the Ro and SRO+nly potions. respectively.
6. Select SRO topics for Tiers 1 and 2 from Ihe shaded systems and WA categories 7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Cafalog, but the topics must be relevant to the applicable evolution or system.
8. On the fdlowing pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IRs) 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. Use duplicate pages for RO and SRO-only exams.
9. For Tier 3,s l e d topics from Section 2 of the WA catalog, and enter the KIA numbers, descriptions, I&, and point totals (#)on Form ES4019. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

Note:This formdeviate~mmeNUREG-1021Form ES-401-Iby meadditionoftbeK andA mlumn underthe SROOnly Points This allows samplingaUFuelHandlingSystan KAsasrequiredby Es-401.

BWR RO Examination Outline Printed: 04/07/2005 Facility: Clinton Power Station ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1 I Group 1 (RO I SRO) Form ES-401-1 I WAPE # I Name I Safety Function K1 K2 K3 A1 A2 G KATopic(s) IR #

295001 Partial or Complete Loss of Forced X AKl.01 -Natural circulation 3.5 1 Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC Pwr 16 I I I II I AA2.02 - Reactor power, pressure, and llevel I I I 4.2*

295004 Partial or Complete Loss of DC Pwr X 2.1.14 - Knowledge of system status 2.5 1 16 criteria which require the notification of 295005 Main Turbine Generator Trip I 3 X AAl.01 -Recirculation system: 3.1 1 Plant-Specific 295006 SCRAM I 1 X -

AK2.07 Reactor pressure control 4.0 1 295016 Control Room Abandonment I 7 X 2.1.32 - Ability to explain and apply 3.4 1 system limits and precautions.

295018 Partial or Total Loss ofCCW 1 8 X AA1.03 -Affected systems so as to 3.3 1 isolate damaged portions 295019 Partial or Total Loss of Inshument X AK2.11- Radwaste 2.5 1 Airla

~

295021 Loss ofShutdownCoolingl4 I I IX I I I IAK3.01 -Raising reactorwater level I 3.3 I 1 1 295023 Refueling Acc I 8 X AK2.02 -Fuel pool cooling and cleanup 2.9 1 system 35024 High Drywell Pressure 15 X EK2.05- RPS 3.9 1 295025 High Reactor Pressure 1 3 X -

EK3.09 Low-low set initiation: 3.7 1 Plant-Specific

%J5026SuppressionPoolHighWater 1 1 IX I I 1 (EK3.02- Suppressionpoolcooling I 3.9 I 1 Temp. 1 5  ! 1 295027 High Containment Tempaahuc 1 5 I I EA2.01 -Containment temperature:

Mmk-IU 2.4.4 Abilily to recognize abnormal 3.7 4.0 I

I 295028 High Drywell Temperature 1 5 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

295030 Low Suppression Pool Wtr Lvl15 -

EAl.04 Suppression pool make-up 4.0 I system: Mark-Ill 295031 Reactor Low Water Level I 2 X -

EK1.03 Water level effects on reactor 3.7 1

- power 295037 SCRAM Condition Present and X EA2.02 - Reactor water level 4.1* 1 Reactor Power Above APRM Downscale or unlmownI 1 295038 High Off-Site Release Rate 1 9 X EA2.03 - ?Radiation levels 3.5f 1

.00000 Plant F k On Site / 8 x -

AK1.01 Fire Classifications by type 2.5 1

.T I I I I I I I I I I I 1

BWR RO Examination Outlioe Printed 04/07/2005 Facillty: Clinton Power Station WAPE # I Name I Safety Function WACategoryToWs:

K1 Kf K3 AI A2 G 3 4 3 3 4 I 3 KATOpiC(8) JR Group Point Total:

20 2

BWR RO Examination Outline Printed: 04/07/2005 Facility: Clinton Power Station ES - 401 -

Emergency and Abnormal Plant Evolutions Tier 1/ Group 2 (RO / SRO) Form ES-401-1 AKI.01 - Moishue carryover 2 9 G 8 High Reactor Water Level X 295012 High D w e l l Temperahue I5 X I 295017 High Off-SiteRelease Rate / 9 I I I X Plant-Specific I I I 295022 Loss of CRD Pumps 1 1 I I I AA1.04 -Reactor water cleanup system: 2.5 1 Plant-Specific

/

295029 High Suppression Pool Wtr Lvl/ 5 X 2.1.33-Ability to recognize indications 3.4 1 for system operating parameters which are entry-level conditions for technical specifications.

295032 High Secondary Containment Area EK3.02 -Reactor SCRAM 3.6 1 500000 High CTMT Hydrogen Conc. I 5 EK2.01 -Containment hydrogen 3.1 1 monitoring systems c

1 Group Point Total:

WACategory Totals: 2 1

-1 7 1

215003 IRM X K1.04- Process computer/ 2.5 1 performance monitoring system (SPDS/ERIS/CRIDS/GDS):

Plant-Specific 215004 Source Range Monitor X K6.01 - RPS 3.2 1 X K1.07 - Process computer, 2.6 1 I215005ApRMnpRM performance monitoring system i, 217000 RCIC X K4.06 - Manual initiation 3.5 1 218000 ADS X A3.08 - Reactorpressure 4.2* 1 218000ADS X 2.4.31 -Knowledge of 3.3 1 annunciators alarms and indications, and use of the response instructions.

223002 PCISNuclear Steam X K3.22 -Containment 2.5 1 223002 PCIS/Nuclear Steam

drainage system X 2.4.31 -Knowledge of 3.3 1 Supply Shutoff annunciators alarms and indications, and use of the response instructions.

239002 SRVs X A1.06 - Reactor power 3.7 I 259002 Reactor Water Level X K5.07 - Turbine speed 2.7 1 Conknl control mechanisms:

TDRFP 261000 SGTS X K4.01-Automatic system 3.7 1 initiation 262001 AC Elechical Distribution X AZ.09 - Exceeding voltage 3.1 1 1imitations -

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B W R RO Examination Outline Printed 04/07/2005 Facility: Clinton Power Station ES - 401 Plant Systems -Tier 2 I Group 1 (RO I SRO) Form ES-401-1 I

SydEvol #/.Name 262001 AC Elechical Distrilmtion 262002 U P S (ACDC) 263000 6 C Elechical Distribution 300000 Inshument Air 400000 Component Cooling Water W A Category Totals 2

B W R RO Examination Outline Printed 04/07/2005 F8cWty: Clinton Power Station 1

Generic Knowledge and Abilities Outline (Tier 3)

BWR RO Examination Outline Printed 0410712005 Fleilitv: Clinton Power Station Form ES-401-3 i

IR -#

I Conduct of Operations 2.1.3 Knowledge of shift turnover practices. I 3.0 I 1 I 2.1.17 Ability to make accurate, clear and concise verbal 3.5 1 reports.

2.1.25 Ability to obtain and interpret station reference 2.8 1 materials such as graphs, monographs, and tables I L which contain performance data.

I I Category Total: 3 1 Equipment Control 2.2.2 Ability to manipulate the console controls as 4.0 1 required to operate the facility between shutdown 2.2.28 Knowledge ofnew and spent fuel movement 2.6 1 proCedUreS.

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

2.3.9 Knowledge of the process for performing a containment purge.

Emergency Plan 2.4.7 Knowledge of event based EOP mitigation 3.1 1 strategies.

2.4.24 Knowledge of loss of cooling water procedures. 3.3 1 2.4.48 Ability to interpret control room indications to 3.5 1 verify the status and operation of system, and understand how operator action s and directives affect plant and system conditions.

1

INITIAL SRO WRITTEN EXAMINATION OUTLINE SUBMITTAL FOR THE CLINTON INITIAL EXAMINATION -JULY 2005

ES-401 BWR Examination Outline Form ES-401-1 1 2 3 4 1 2 3 4

3. Generic KnowledgeAnd 0 - 7 Abilities Categories 0 0 0 0 2 2 2 1 Note: ?his form deviates from the NUREG-1021 Form ES-401-1by the additionof the K and A column under the SRO Only Points This allows samplingall Fuel Hmdling System KAs as required by ES-401.

1

' VAPE # I Name I Safety Function K1 K2 K3 A1 A2 G KATopic(s)

X 2.2.25 - Knowledge ofbases in IR 3.7 I

L-295004 Partial or Complete Loss of M3 Pwr 16 technical specifications for limiting conditions for operations and safety limits.

295016 Control Room Abandonment / 7 X 2.4.6 - Knowledge symptom based EOP 4.0 1 mitigation strategies.

295019 Partial or Total Loss of Instrument X AAz.02 - Status of safety-related 3.7 1 Ail/8 instnunent air system loads (see AK2.1-AK2.19) 295021 Loss of Shutdown Cooling I 4 X AA2.01 - Reactor water 3.6 1 heatup/cooldown rate 295025 High Reactor Pressure I3 X EA2.01- Reactor pressure 4.3; 1 295037 SCRAM Condition Present and X 2.1.20 - Ability to execute procedure 4.2 1 Reactor Power Above APRM Downscale or steps.

unlalown I 1 600000 Plant Fire On Site / 8 X AA2.09 - That a failed fire alarm 2.8 1 detector exists WACategoryTotnk 0 0 0 0 4 3 Group Point Total: 7 1

BWR SRO Examination Outline Printed: 04/07/2005 Fadlity: Cliton Power Station

' VAPE # t Name I Safety Funelion K1 K2 K3 A1 A2 X

G KA Topic(s)

AA2.02 - Drywell pressure IR 3.9 ff 1

~ 9 5 0 1 0High Drywell Pressure I5 29501 1 High Containment Temp 1 5 X 2.1.14 -Knowledge of system status 3.3 1 criteria which reauire the notification of I I I I plant personnel. I I 500000 High CTMT Hydmgen Conc. 1 5 I I X EA2.03 -Combustible limits for *ell 3.8 1 I K/ACategoryTotrls:I 0 1 0 1 O l O l Z l 11 Group Point Total: 3 1

BWR SRO Examination Outline Printed: 04/07/2005 Facility: Clinton Power Station

\-

ES - 401 Syflvol # I Name 209002HPcs K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic X 2.4.30 -Knowledge of IR 3.6 1

which events related to system operationststatus should be reported to outside agencies.

X A2.04 - Inadequate system 3.4* 1 211000 SLC flow X 2.2.25 -Knowledge ofbases 3.7 1 215005AeRMnPRh4 in technical specifications for limiting conditions for operations and safety limits.

259002 Reactor Water Level X A2.06 -Loss of controller 3.4 1 Control signal output X A2.03 - Highllow CCW 3.0 1 400000 Component Cooling Water temperature WACategoryTotak 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 1

BWR SRO Examination Outline Printed: 04/07/2005 Facility: Clinton Power Station ES - 401 -

Plant Systems Tier 2 I Group 2 (RO I SRO) Form ES-401-1 ISyalEvol # I Name 202001 Recirculation Cooling Mode based EOP mitigation IUA Category Totals:

1

Generic Knowledge and Abilities Outline (Tier 3)

B W R SRO Examination Outline Printed 04/07/2005 F.eilihr: Cliton Power Station Form ES-401-3 Conduct of Operations 2.1.4 Knowledge of shift stafingrequirements. 3.4 1 I 1 I I I I

2.1.33 Ability to recognize indications for system 4.0 1 operating parameten which are entry-level conditions for technical specifications.

Equipment Control 2.2.23 Abilityto track limiting conditions for operations. 3.8 1 2.2.29 Knowledge of SRO fuel handling responsibilities. 3.8 1 Category Total: 2 Radiation Control 2.3.1 Knowledge of IO CFR 20 and related facility 3.0 1 radiation control requirements.

I 2.3.2 [ Knowledge of facility ALARA program. I 2.9 I I I Catemrv Total: 2 1

~ ~~ ~ ~ ~ ~

i/

Emergency Plan 2.4.22 Knowledge of the bases for prioritizing safety 4.0 1 h c t i o n s during abnormallemergency operations.

1

FINAL RO WRITTEN EXAMINATION OUTLINE SUBMITTAL FOR THE CLINTON INITIAL EXAMINATION -JULY 2005

ES-401 BWR Examination Outline Form ES-401-1 Facilia: Clinton Power Station Printed: 06/20/2005 Date Of Exam: 07/11/2005 L,.

3. Generic Knowledge And Abilities Categories
1. Ensure that at least two topics from every KIA category are sampled within each tier of the RO and SROonlyoutlines (Le., exceptfor one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WAcategory shall not be less than two).

L,

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total f a each goup and tier may deviate by f l t o m 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. Systems/evdutions within each group are identified on the associated outline; systems or evolutions that do not apply at the fadlity should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimiwtion of inappropriate WA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group befae seleding a second topic for any system or evdution.
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.' The generic (G) WASin Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evdution or system.

8. On the following pagas. enter the WA numbers, a brief description of each topic, the topics' importanca ratings (IRs) 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. Use duplicate pages for RO and SRO-only exams.

i

-.- Note:~lhisformdeviatesfrommeNUREG-1021Form ES-401-Iby theadditionoftheKandAcolumnunderthe SROOnly Points This allows sampling all Fuel Handling System KAs as requiredby F.S-401.

1

BWR RO Examination Outline Printed: 0612012005 Facility: Clinton Power Station ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1 I Group 1 (RO I SRO) Form ES-401-1 quire the notification of 295028 High lkywell Temperahue / 5 indications for system operating parameten which are enhy-level 1

BWR RO Examination Outline Printed 06/20/2005 Facility: Clinton Power Station ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1 / Group 1 (RO I SRO) Form ES-401-1 I

WAPE # I Name I Safety Function K l KZ K3 A1 A2 G KATopic(s) IR #

600000 Plant Fire On Site / 8 X AK1.02 - Fire Fighting 2.9 1 WACategoryTotak 3 4 3 3 4 3 Group Point Total: 20 2

B W R RO Examination Outline Printed: 06I2012005 Fadlity: Clinton Power Station ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1 I Group 2 (RO / SRO) Form ES-401-1 WAPE # I Name I Safety Function K1 KZ K3 AI A2 G KATopiNs) IR #

295002 Loss of Main Condenser Vac I 3 X AK2.02 - Main turbine 3.1 1 295008 High Reactor WaW Level I 2 X AKI.01 -Moisture carryover 3.0 1 295017 High Off-Site Release Rate / 9 X AA2.03 - tRadiation levels: 3.1 1 Plant-SDecific I 295022 Loss of CRD Pumps / 1 I I I IXOI AA1.04 - Reactor water cleanup system:

Plant-Specific 295029 High Suppression Pool Wtr Lvl 1 5 X 2.1.33 - Ability to recognize indications 3.4 1 for system operating parameters which are entry-level conditions for technical specifications.

295032 High Secondary Containment Area X EK3.03 - Isolating affected systems 3.8 1 Temuernlure I 5 500000 High CTMT Hydrogen Conc. 1 5 I XI I l l IEK2.01- Containment hydrogen 3.1 1 I I I I Imonitoring systems WACateeorvTotrla: I 1 1 2 1 1 I 11 1 I 1 I Group Point Total: 7 1

B W R RO Examination Outline Printed 06/20/2005 Fadlity: Clinton Power Station 1

B W R RO Examination Outline Printed: 06/20/2005 Facility: Clinton Power Station ES 401 -

PImt Systems Tier 2 I Group 1 (RO I SRO) Form ES-401-1 I I I I K4.01 - Transfer 60m preferred power to alternate power supplies A2.02 - Loss of ventilation during charging I

~ 2 . 0 1- Parallel operation of1 3.5 I 1 emergency generator I A4.01 - Pressure gauges 1 2.6 I 1 K5.01 - Air compressors K6.06 - Heat exchangers and condensers Group Point Total: 26 I 2

B W R RO Examination Outline Printed: 06/20/2005 Facility: Clinton Power Station

Generic Knowledge and Abilities Outline (Tier 3)

B W R RO ExaminationOutline Printed: 06/20/2005 F.eilitv: Clinton Power Station Form EMOl-3 C.tePorv -

KA# -IR  !!

I Conduct of Operatlorn I 2.1.3 I Knowledge of shift turnover practices I 3.0 I 1 I I I I I

I 2.1.25 Ability to obtain and interpret station reference 2.8 1 materials such as graphs, monographs, and tables which contain performance data.

2.1.30 Ability to locate and operate components, 3.9 1 including local controls.

Equipment Control 2.2.2 Ability to manipulate the console controls as 4.0 1 required to operate the facility between shutdown and designated power levels.

2.2.28 Knowledge of new and spent fuel movement 2.6 1 procedures.

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

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

Emergency Plan 2.4.7 Knowledge of event based EOP mitigation 3.1 1 strategies.

2.4.24 Knowledge of loss of cooling water procedures. 3.3 1 2.4.43 Knowledge of emergency communications 2.8 1 systems and techniques.

Generic Total: 10 1

FINAL SRO WRITTEN EXAMINATION OUTLINE SUBMITTAL FOR THE CLINTON INITIAL EXAMINATION -JULY 2005

ES-401 BWR Examination Outline Form ES-401-1 Clinton Power Station Printed: 06/20/2005 Date Of Exam: 01/31/2005 RO K/A Category Points I SRO-Only Points Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each KIA 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 fw each goup and tier may deviate by f l t o m 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. Systems/evdutions within each group are identifiedon the associated outline; systems cf evolutions that do not apply at the faalily should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or ewlution in the group before selecting a second topic for any system w evolution.
5. Absent a plant-specific priority, only those WAShaving an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO+nly portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
7. The generic (G) WAS in Tiers 1 and 2 shall be seleded from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evdution or system.
8. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (IRs) 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. Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics tom Section 2 of the WA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#)on Form ES-401-3. Limit SRO sdections to WAS that are linked to Note:Thk.formdeviatesfmmtheNUREG-1021FormES-401-1by theadditionoftheKandAcolumnunderthe SROOnl)

Points This allows samplingallFue1Handling System Usasrequired by ES-401.

1

BWR SRO Examination Outline Printed: 06/20/2005 Facility: Clinton Power Station ES 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 (RO / SRO) Form ES-401-1 295025 High Reactor Pressure / 3 X W . 0 1 - Reactor pressure 4.3* 1 295037 SCRAM Condition Present and X 2.1.20 - Ability to execute procedure 4.2 1 Reactor Power Above APRM Downscale or steps.

unknown / 1 600000 Plant Fire On Site / 8 X AA2.09 - That a failed fire alarm 2.8 1 detectorexists WACateeor~Totals: 0 0 0 0 4 3 Group Point Total: 7 1

BWR SRO Examination Outline Printed 06/20/2005 Facility: Clinton Power Station ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1I Group 2 @O I SRO) Form ES-401-1 I

~

WAPE # I Name I Safety Function K1 K2 K3 A i A2 G KATopicIs) IR #

7 295010 High Drywell Pressure I 5 X AA2.02 - Drywell pressure 3.9 1 29501 1 High Containment Temp / 5 X 2.1.14 -Knowledge of system status 3.3 1 criteria which require the notification of plant personnel.

500000 High CTMT Hydrogen Conc. I 5 X EA2.03 -Combustible limits for drywell 3.8 1 WACateeorvTotals: 0 0 0 0 2 1 G r o w Point Total: 3 1

BWR SRO Examination Outline Printed: 06/20/2005 Facility: Clinton Power Station ES - 401 SyslEvol # IName K1 KZ K3 K4 K5 K6 A1 A2 A3 A4 G KATopic IR #

. X 2.4.30-Knowledge of 3.6 1 209002 HPCS which events related to system operations/status should be reported to outside agencies.

211000 SLC X A2.04 - Inadequate system 3.4* 1 flow 215005 APRM/LPRM X 2.2.25-Knowledge ofbases 3.7 1 in technical specifications for limiting conditions for operations and safety limits.

259002 Reactor Water Level X A2.06 - Loss of controller 3.4 1 Control signal output 400000 Component Cooling Water X A2.03 - Highflow CCW 3.0 1 temperature WACategoryTotals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 1

BWR SRO Examination Outline Printed: 0612012005 Fadlity: Clinton Power Station 1

Generic Knowledge and Abilities Outline (Tier 3)

BWR SRO Examination Outline Printed: 06/20/2005 F.fllihr: Clinton Power Station Form ES-401-3 Conduct of Operations 2.1.4 Knowledge of shift stafiing requirements. 3.4 1 2.1.33 Ability to recognize indications for system 4.0 1 operating parameters which are entry-level conditions for technical specifications.

I Equipment Control 2.2.23 Ability to track limiting conditions for operations. 3.8 1 2.2.29 Knowledge of SRO fuel handling responsibilities. 3.8 1 Category Total: 2 I Radiation Control 2.3.1 2.3.2 Knowledge of 10 CFR 20 and related facility radiation control requirements.

Knowledge of facility ALARA program.

3.0 2.9 1

1 W

Emergency pI.n 2.4.22 Knowledge of the bases for prioritizing safety 4.0 1 functions during abnomallemergency operations.

Category Total: 1 1

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