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 Exelon Company 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-1 021, 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 fl 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. 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-1021 Form ES-401-I by meadditionoftbeK andA mlumn underthe SROOnly Points This allows samplingaUFuelHandling Systan KAsasrequiredby Es-401.

Printed: 04/07/2005 Form ES-401-1 BWR RO Examination Outline Facility:

Clinton Power Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 (RO I SRO)

I WAPE # I Name I Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 K1 K2 K3 A1 A2 G KATopic(s)

IR X

AKl.01 -Natural circulation 3.5 1

I 4.2* I I

AA2.02 - Reactor power, pressure, and I I I I I I llevel 295003 Partial or Complete Loss of AC Pwr 16 295004 Partial or Complete Loss of DC Pwr 16 X 2.1.14 - Knowledge of system status 2.5 1

criteria which require the notification of 295005 Main Turbine Generator Trip I 3 295006 SCRAM I 1 295016 Control Room Abandonment I 7 X

AAl.01 -Recirculation system:

3.1 1

X AK2.07 - Reactor pressure control 4.0 1

X 2.1.32 - Ability to explain and apply 3.4 1

Plant-Specific system limits and precautions.

295018 Partial or Total Loss ofCCW 18 295019 Partial or Total Loss of Inshument Airla 295021 Loss ofShutdownCoolingl4 I

I I X I I

I IAK3.01 -Raising reactorwater level I 3.3 I 1 1

X X

AA1.03 -Affected systems so as to isolate damaged portions AK2.11-Radwaste

%J5026SuppressionPoolHighWater 1

1 I X I I

1 (EK3.02-Suppressionpoolcooling I

3.9 I 1

3.3 1

2.5 1

Temp. 1 5 1

~

295023 Refueling Acc I 8 35024 High Drywell Pressure 15 295025 High Reactor Pressure 13 I I 295027 High Containment Tempaahuc 1 5 X

AK2.02 -Fuel pool cooling and cleanup 2.9 1

X EK2.05 - RPS 3.9 1

X EK3.09 - Low-low set initiation:

3.7 1

system Plant-Specific EA2.01 -Containment temperature:

2.4.4 - Abilily to recognize abnormal Mmk-IU indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

EAl.04 - Suppression pool make-up system: Mark-Ill EK1.03 - Water level effects on reactor power 3.7 I

4.0 I

4.0 I

3.7 1

295028 High Drywell Temperature 1 5 295030 Low Suppression Pool Wtr Lvl15 295031 Reactor Low Water Level I 2 I

I I

I I

I I

I I

I I

X 1

295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or unlmown I 1 295038 High Off-Site Release Rate 1 9

.00000 Plant F k On Site / 8

.T X

EA2.02 - Reactor water level 4.1*

1 X

EA2.03 - ?Radiation levels 3.5f 1

x AK1.01 - Fire Classifications by type 2.5 1

BWR RO Examination Outlioe Facillty:

Clinton Power Station WAPE # I Name I Safety Function K1 Kf K3 AI A2 G KATOpiC(8)

Printed 04/07/2005 JR WACategoryToWs:

3 4

3 2

3 4 I 3 Group Point Total:

20

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 X

X

' 29G8 High Reactor Water Level 295012 High Dwell Temperahue I5 I I I I 295017 High Off-Site Release Rate / 9 I

I I

295022 Loss of CRD Pumps 1 1 I

I I

295029 High Suppression Pool Wtr Lvl/ 5 /

295032 High Secondary Containment Area 500000 High CTMT Hydrogen Conc. I 5 WACategory Totals:

2 1

1 X

X c

1 -

AKI.01 - Moishue carryover Plant-Specific AA1.04 -Reactor water cleanup system:

2.5 1

2.1.33 -Ability to recognize indications 3.4 1

Plant-Specific for system operating parameters which are entry-level conditions for technical specifications.

EK3.02 -Reactor SCRAM 3.6 1

EK2.01 -Containment hydrogen 3.1 1

monitoring systems Group Point Total:

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

performance monitoring system X

K4.06 - Manual initiation 3.5 1

218000 ADS X

A3.08 - Reactorpressure 4.2*

1 I 215005ApRMnpRM i,

217000 RCIC 218000ADS X 2.4.31 -Knowledge of 3.3 1

annunciators alarms and indications, and use of the response instructions.

drainage system 223002 PCISNuclear Steam X

K3.22 -Containment 2.5 1

223002 PCIS/Nuclear Steam 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:

261000 SGTS X

K4.01 -Automatic system 3.7 1

262001 AC Elechical Distribution X

AZ.09 - Exceeding voltage 3.1 1

TDRFP initiation 1 imitations k

Facility:

Clinton Power Station ES - 401 SydEvol #/.Name 262001 AC Elechical Distrilmtion I

262002 UPS (ACDC) 263000 6C Elechical Distribution 300000 Inshument Air 400000 Component Cooling Water W A Category Totals B W R RO Examination Outline Plant Systems -Tier 2 I Group 1 (RO I SRO)

Printed 04/07/2005 Form ES-401-1 2

BWR RO Examination Outline Printed 04/07/2005 F8cWty:

Clinton Power Station 1

i Conduct of Operations Generic Knowledge and Abilities Outline (Tier 3)

BWR RO Examination Outline Printed 0410712005

2.1.3 Fleilitv

Clinton Power Station Ability to make accurate, clear and concise verbal reports.

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

3.5 1

2.8 1

2.1.17 2.1.25 I

Equipment Control 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown 2.2.28 Knowledge ofnew and spent fuel movement proCedUreS.

I L

4.0 1 -

2.6 1

Form ES-401-3 IR 2.3.4 2.3.9 Knowledge of shift turnover practices.

I 3.0 I 1 I 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.

Emergency Plan 2.4.7 Knowledge of event based EOP mitigation strategies.

2.4.24 Knowledge of loss of cooling water procedures.

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

I I

Category Total:

3 1

3.1 1

3.3 1

3.5 1

Radiation Control I

1

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

ES-401 BWR Examination Outline Form ES-401-1 1

0

3. Generic Knowledge And Abilities Categories 2

3 4

1 2

3 4

0 0

0 2

2 2

1 0 -

7 Note: ?his form deviates from the NUREG-1021 Form ES-401-1 by the addition of the K and A column under the SRO Only Points This allows sampling all Fuel Hmdling System KAs as required by ES-401.

1

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

IR L-295004 Partial or Complete Loss of M3 Pwr 16 295016 Control Room Abandonment / 7 295019 Partial or Total Loss of Instrument Ail/8 295021 Loss of Shutdown Cooling I4 295025 High Reactor Pressure I3 1

X 2.2.25 - Knowledge ofbases in 3.7 I

technical specifications for limiting conditions for operations and safety limits.

mitigation strategies.

instnunent air system loads (see AK2.1-AK2.19) heatup/cooldown rate X 2.4.6 - Knowledge symptom based EOP 4.0 1

X AAz.02 - Status of safety-related 3.7 1

X AA2.01 - Reactor water 3.6 1

X EA2.01 - Reactor pressure 4.3; 1

295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or unlalown I 1 600000 Plant Fire On Site / 8 WACategoryTotnk X 2.1.20 - Ability to execute procedure 4.2 1

steps.

X AA2.09 - That a failed fire alarm 2.8 1

detector exists 0

0 0

0 4

3 Group Point Total:

7

BWR SRO Examination Outline Fadlity:

Cliton Power Station

' VAPE # t Name I Safety Funelion K1 K2 K3 A1 A2 G Printed: 04/07/2005 KA Topic(s)

IR ff

~95010 High Drywell Pressure I5 29501 1 High Containment Temp 1 5 X

AA2.02 - Drywell pressure 3.9 1

X 2.1.14 -Knowledge of system status 3.3 1

criteria which reauire the notification of I

I K/ACategoryTotrls:I 0 1 0 1 O l O l Z l 11 Group Point Total:

3 I I I plant personnel.

I I

1 I I 500000 High CTMT Hydmgen Conc. 1 5 X

1 EA2.03 -Combustible limits for *ell 3.8

BWR SRO Examination Outline Facility:

Clinton Power Station ES - 401 Syflvol # I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic X 2.4.30 -Knowledge of which events related to system operationststatus should be reported to outside agencies.

flow

\\- 209002HPcs X

A2.04 - Inadequate system 211000 SLC 215005AeRMnPRh4 in technical specifications for limiting conditions for operations and safety limits.

X A2.06 -Loss of controller signal output X

A2.03 - Highllow CCW X 2.2.25 -Knowledge ofbases 259002 Reactor Water Level Control 400000 Component Cooling Water temperature Printed: 04/07/2005 IR 3.6 1

3.4*

1 3.7 1

3.4 1

3.0 1

WACategoryTotak 0

0 0

0 0

0 0

3 0

1 0

2 Group Point Total:

5

BWR SRO Examination Outline Printed: 04/07/2005 Facility:

Clinton Power Station ES - 401 I SyalEvol # I Name 202001 Recirculation Cooling Mode IUA Category Totals:

Plant Systems - Tier 2 I Group 2 (RO I SRO)

Form ES-401-1 based EOP mitigation 1

Generic Knowledge and Abilities Outline (Tier 3)

BWR 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 stafing requirements.

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 Radiation 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 2.3.1 I 2.9 I I

I 2.3.2 [ Knowledge of facility ALARA program.

Knowledge of IO CFR 20 and related facility 3.0 1

radiation control requirements.

I Catemrv Total:

2 1

~

~~

~

~

~

Emergency Plan 2.4.22 i/

~

Knowledge of the bases for prioritizing safety 4.0 1

hctions 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).
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 fl tom 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) 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 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.

L, i -.-

Note:~lhisformdeviatesfrommeNUREG-1021 Form ES-401-I by theadditionoftheKandAcolumnunderthe SROOnly Points This allows sampling all Fuel Handling System KAs as required by 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 600000 Plant Fire On Site / 8 WACategoryTotak K l KZ K3 A1 A2 G KATopic(s)

IR X

AK1.02 - Fire Fighting 2.9 1

3 4

3 3

4 3

Group Point Total:

20 2

BWR RO Examination Outline Printed: 06I2012005 Form ES-401-1 Fadlity:

Clinton Power Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 (RO / SRO)

WAPE # I Name I Safety Function 295002 Loss of Main Condenser Vac I 3 295008 High Reactor WaW Level I 2 K1 KZ K3 AI A2 G KATopiNs)

IR X

AK2.02 - Main turbine 3.1 1

X AKI.01 -Moisture carryover 3.0 1

295017 High Off-Site Release Rate / 9 X

AA2.03 - tRadiation levels:

Plant-SDecific AA1.04 - Reactor water cleanup system:

I I I I X O I Plant-Specific I 295022 Loss of CRD Pumps / 1 3.1 1

295029 High Suppression Pool Wtr Lvl 1 5 295032 High Secondary Containment Area Temuernlure I 5 X 2.1.33 - Ability to recognize indications 3.4 1

for system operating parameters which are entry-level conditions for technical specifications.

X EK3.03 - Isolating affected systems 3.8 1

I I I I I monitoring systems WACateeorvTotrla: I 1 1 2 1 1 I 11 1 I 1 I Group Point Total:

7 500000 High CTMT Hydrogen Conc. 1 5 I

XI I

l l

I EK2.01-Containment hydrogen 1

3.1 1

BWR RO Examination Outline Fadlity:

Clinton Power Station Printed 06/20/2005 1

BWR RO Examination Outline Facility:

Clinton Power Station Printed: 06/20/2005 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 K5.0 1 - Air compressors K6.06 - Heat exchangers and condensers Group Point Total:

26 I 2

BWR RO Examination Outline Facility:

Clinton Power Station Printed: 06/20/2005

Generic Knowledge and Abilities Outline (Tier 3)

BWR RO ExaminationOutline Printed: 06/20/2005 F.eilitv: Clinton Power Station Form EMOl-3 C.tePorv KA#

IR 2.1.25 I Conduct of Operatlorn Ability to obtain and interpret station reference 2.8 1

materials such as graphs, monographs, and tables which contain performance data.

I 2.1.3 I Knowledge of shift turnover practices 2.1.30 I 3.0 I 1

Ability to locate and operate components, 3.9 1

including local controls.

I I

I I

I I

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 Equipment Control Knowledge of new and spent fuel movement 2.6 1

procedures.

2.3.4 Knowledge of radiation exposure limits and 2.5 1

contamination control, including permissible levels in excess of those authorized.

Radiation Control I

2.3.9 Knowledge of the process for performing a 2.5 1

containment purge.

2.4.7 2.4.24 2.4.43 Emergency Plan Knowledge of event based EOP mitigation 3.1 1

strategies.

Knowledge of loss of cooling water procedures.

3.3 1

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 tom 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 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 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+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-1021 FormES-401-1 by theadditionoftheKand Acolumnunderthe SROOnl)

Points This allows samplingallFue1 Handling 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 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or unknown / 1 600000 Plant Fire On Site / 8 WACateeor~Totals:

X W. 0 1 - Reactor pressure 4.3*

1 X 2.1.20 - Ability to execute procedure 4.2 1

steps.

X AA2.09 - That a failed fire alarm 2.8 1

0 0

0 0

4 3

Group Point Total:

7 detector exists 1

BWR SRO Examination Outline Printed 06/20/2005 Facility:

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

Form ES-401-1

~

WAPE # I Name I Safety Function I

7 295010 High Drywell Pressure I 5 K1 K2 K3 Ai A2 G KATopicIs)

IR X

AA2.02 - Drywell pressure 3.9 1

29501 1 High Containment Temp / 5 500000 High CTMT Hydrogen Conc. I 5 WACateeorvTotals:

1 X 2.1.14 -Knowledge of system status 3.3 1

criteria which require the notification of plant personnel.

X EA2.03 -Combustible limits for drywell 3.8 1

0 0

0 0

2 1

G r o w Point Total:

3

BWR SRO Examination Outline ES - 401 SyslEvol #I Name K1 KZ K3 K4 K5 K6 A1 A2 A3 A4 G KATopic X 2.4.30 -Knowledge of which events related to system operations/status should be reported to outside agencies.

flow X 2.2.25 -Knowledge ofbases in technical specifications for limiting conditions for operations and safety limits.

A2.06 - Loss of controller 209002 HPCS 211000 SLC X

A2.04 - Inadequate system 215005 APRM/LPRM X

259002 Reactor Water Level Control signal output 400000 Component Cooling Water X

A2.03 - Highflow CCW temperature Printed: 06/20/2005 IR 3.6 1

3.4*

1 3.7 1

3.4 1

3.0 1

Facility:

Clinton Power Station WACategoryTotals:

0 0

0 0

0 0

0 3

0 0

2 Group Point Total:

5 1

BWR SRO Examination Outline Fadlity:

Clinton Power Station Printed: 0612012005 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.

Radiation Control I

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 2.3.1 Knowledge of 10 CFR 20 and related facility 3.0 1

radiation control requirements.

1 2.3.2 Knowledge of facility ALARA program.

2.9 1

W Emergency pI.n 2.4.22 Knowledge of the bases for prioritizing safety 4.0 1

Category Total:

1 functions during abnomallemergency operations.

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