ML11168A108

2010 Clinton Power Station Initial License Examination Outline Submission

ML11168A108
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Site:	Clinton
Issue date:	11/04/2010
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2010 CLINTON POWER STATION INITIAL EXAMINATION OUTLINE SUBMITTAL

• Clinton Power Station 8401 Power Road Clinton , IL 61727 Nuclear U-603966 10CFR55.40 J ul y 2 I 20 1 0 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 supporting the Initial License Examination scheduled

• for the weeks of 11/1/2010 through 11/12/2005 at Clinton Power Station .

This submittal includes all appropriate Examination Standards forms and outlines in accordance with NUREG-1 021 , "Operating licenSing Examination Standards for Power Plants," Revision 9 Supplement 1.

In accordance with NUREG-1 021, 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. Tallion French at (217) 937-3234.

p~~

F. A. Kearney Site Vice President Clinton Power Station EET/bif cc: (w/o attachments)

Chief, NRC Operator Licensing Branch NRC Senior Resident Inspector - Clinton Power Station JUl 1 2 2010

U.S. Nuclear Regulatory Commission U-603966 July 2, 2010

• Page 2 of 2 Attachments: (Hand delivered to NRC Region III Chief Examiner)

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

Administrative Topics Outline (Form ES-301-1) ,

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

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

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

Operational Scenarios Outline (Form ES-O-1) ,

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

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

Outline Methodology for 2010 Clinton Power Station Written NRC Exam

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

• Facility:

Item

~II YJ.fo11 Task Description Date of Examination: .)

l(L l a

IU Initials b* c#

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

W R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all KIA categories are appropriately sampled.

T T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topiCS.

E N d. Assess whether the justifications for deselected or rejected KIA statements are appropriate.

a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number

2. of normal evolutions, instrument and component failures, technical specifications, and major transients.

S I

b. Assess whether there are enough scenario sets (and spares) to test the projected number M

and mix of applicants in accordance with the expected crew composition and rotation schedule U

without compromising exam integrity, and ensure that each applicant can be tested using L at least one new or significantly modified scenario, that no scenarios are duplicated A

from the applicants' audit test(s), and scenarios will not be repeated on subsequent days.

T 0

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative R

and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form 1 (2) task repetition from the last two NRC examinations is within the limits specified on the form T (3) no tasks are duplicated from the applicants' audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form

b. Verify that the administrative outline meets the criteria specified on Form ES-301-1 :

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3i no more than one task is repeated from the last two NRC licensino examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam section.

G

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

E N c. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5.

E R d. Check for duplication and overlap among exam sections.

A e. Check the entire exam for balance of coverage.

L

f. Assess whether the exam fits the appropriate job level (RO or SRO).

a. Author IAwrAi KAJ ~t.1L 7~2m~~s~~

b. Facility Reviewer (*) -;::; ., .. ~!> C tJ.A"{AJtl-l (... ~

c. NRC Chief Examiner (#)

d. NRC Supervisor NOTE: # Independent NRC Reviewer initial items in Column "c"; chief examiner concurrence required.

• Not applicable for NRC-prepared examination outlines .

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

• Facility: Clinton Item Task Description Date of Examination: 11/01 /2010 a

Initials b* c#

W

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

~af- ~ ~

A b. Assess whether the outline was systematically and randomly prepared in accordance with I Section 0 .1 of ES-401 and whether all KIA categories are appropriately sampled . 1~ (( f4-.

T T

E

c. Assess whether the outline over-emphasizes any systems, evolutions, or generiC topics.

~ i- flty..

N d. Assess whether the justifications for deselected or rejected KIA statements are appropriate. 11 ~ ~

a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number 2.

S of normal evolutions, instrument and component failures, technical specifications, and major transients .

/If f-- tw.

I b. Assess whether there are enough scenario sets (and spares) to test the projected number M and mix of applicants in accordance with the expected crew composition and rotation schedule U without compromising exam integrity, and ensure that each applicant can be tested using ()f tHk L

A at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s) , and scenarios will not be repeated on subsequent days.

~

T 0

1f ~

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative A

and quantitative criteria specified on Form ES-301-4 and described in Appendix D. ~

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301 -2:

(1 ) the outline(s) contain(s) the required number of control room and in-plant tasks distributed among the safety functions as specified on the form W

K (2) task repetition from the last two NAC examinations is within the limits specified on the form 1

T (3) no tasks are duplicated from the applicants' audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form 1f ~

(5) the number of alternate path, low-power, emergency, and ACA tasks meet the criteria on the form

b. Verify that the administrative outline meets the criteria specified on Form ES-301-1 :

(1 ) the tasks are distributed among the topics as specified on the form 1{

(2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing. examinations

f. ~

c. Determine if there are enough different outlines to test the projected number and mix f1J'/

4. a.

of IWplicants and ensure that no items are duplicated on subsequent days.

Assess whether plant-specific priorities (including PAA and IPE insights) are covered

1. tM in the appropriate exam section. )f R ~

G E

b. Assess whether the 10 CFA 55.41/43 and 55.45 sampling is appropriate. /[ ( f!.. I~

N c. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. !W tJUt(

E A d. Check for duplication and overlap among exam sections. 1SC/, j) ~

!){ ~

A e. Check the entire exam for balance of coverage.  ;!-/It(

L

f. Assess whether the exam fits the appropriate job leve({AO):>r SAO). /l~ ,l ~

a. Author 1{:ltu" ~ ~~ame 1 Signature ~te / D 9.f:J

b. Facility Aeviewer (*) .ei<'~t\4.~ .(!,~{)(t'-1 / 7!r~R/)P- ..fJ.. ~- U:/'- f ()

IO/~Lto

c. NAC Chief Examiner (#) {"Nll It'IXAlF:.. ( ~~ "7flm.p ,., ~

d. NRC Supervisor /./;Y/), A, Uk"",;, / /",-~ Lo-;7~o

//7 V~ V NOTE: # Independent NAC Aeviewer initial items in Column "c"; chief examiner concurrence required .

• Not applicable for NAC-prepared examination outlines.

ES-201, Page 26 of 28 17¥:J;s 'IS -me:. ~ g.C; - Zol"'~ >U~~. ~ ~T £s- ZP( -Z- wAs ~6t~ ?/(zlra WI:i7+ ~ P.J{h~ ~. %Jf1}L ~ TFJ ~ CU'faAlG,. RP.::.:u~ TAJ 11ft.. <S£(6i1~

of-~ GS-UI-Z.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Clinton Date of Examination : 11 /01/10 Examination Level: RO~ SRO 0 Operating Test Number: 2010301 Administrative Topic Type Describe activity to be performed (See Note) Code*

JPM 412 / Generic 2.1.18/ 3.6 Conduct a panel walkdown Conduct of Operations M,S 3601 JPM 409/ Generic 2.1.4/ 3.3 Perform license Conduct of Operations N,R maintenance check JPM 411 / Generic 2.2 .13/ 4.1 Print reading errors in Equipment Control M,R tagout Radiation Control M,R JPM 410/ Generic 2.3.7/ 3.5 Read survey map Emergency Procedures/Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required .

• Type Codes & Criteria: (C)ontrol room , (S)imulator, or Class(R)oom (D)irect from bank C:s. 3 for ROs ; :s. 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (::: 1)

(P)revious 2 exams (:s. 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Clinton Date of Examination: 11 /01/1 0 Exam Level: RO ~ SRO-I D SRO-U D Operating Test Number: 2010301 Control Room Systems@(8 for RO) ; (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System 1 JPM Title Type Code*

Function

a. 201005 A2 .021 2.8 JPM 413 Control Rod Timing Restoration N,A,S 1

b. 209002 A4.031 3.8JPM 228 Defeat HPCS Level 8 isolation D,C 2

c. 241000 A4.191 3.5 JPM 415 Perform tubine online tests D,S 3

d. 217000 A2 .071 3.1 JPM 221 Start up RCIC tank to tank loss of lube oil D,A,S 4

e. 223002 A4.061 3.6 JPM 217 Verify a Group 8 isolation D,A,S 5

f. 264000 A4.041 3.7 JPM 414 Parallel a diesel N,A,S 6

g. 212000 A4.141 3.8 JPM 227 Reset a scram A,D ,S.L 7

h. 288000 A4.011 3.1 JPM 106 S/U CCP P,D,A,S 9 In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U )

i. 295037 EA 1.05/3 .9 JPM 054 Bypass CRD filters for reactivity control D,E,L,R 1

j. 295024 EA 1.18/3.6 JPM 022 Vent containment to spent fuel pool P,D,E,L,R 5

k. 262002 2.1.301 4.4 JPM 252 Restore UPS 1B D,R 6

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety function s; in-pla nt systems and functi ons may overlap th ose tested in the control room .

• Type Codes Criteria for RO 1 SRO-I 1 SRO-U (A)lternate path 4-61 4-6 1 2-3 (C)ontrol room (D)irect from bank ~9 1 ~8 1 ~4 (E)mergency or abnormal in-plant ~ 1 1 ~1 1 ~ 1 (EN)gineered safety feature / ~ 1 (control room system (L)ow-Power 1 Shutdown ~ 1 1 ~1 1 ~1 (N)ew or (M)odified from bank including 1(A) ~21 ~2 1 ~1 (P)revious 2 exams ~ 3 1 ~3 1 ~ 2 (randomly selected)

(R)CA ~ 11 > 1 1 ~ 1 (S)imulator ES-301, Page 23 of 27

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Clinton Date of Exam : 11 /01/2010 Operating Test Number: 2010301 A E Scenarios P V 1 2 3 Spare P E T M L N CREW CREW CREW CREW 0 I I T POSITION POSITION POSITION POSITION T N A I C

A T S A B S A B S A B S A B L M N Y R T 0 R T 0 R T 0 R T 0 U 0 C P 0 C P 0 C P 0 C P M(*)

T P E R I U RX 3 1 1 1 0 RO jgJ NOR 1 1 1 1 1 1 SRO-I IIC 2, 4 3,5 4,5 4 4 4 2 0

SRO-U MAJ 7,8 7,8,9 7 5 2 2 1 0 TS 0 2 2 RX 2 2 1 1 1 0 RO jgJ NOR 1 1 1 1 1 SRO-I IIC 5,6 4,6 3,6 4 4 4 2 0

SRO-U MAJ 7,8 7,8,9 7 5 2 2 1 D TS 0 2 2 RX 1 1 0 RO D

SRO-I NOR 1 1 1 IIC 4 4 2 0

SRO-U MAJ 2 2 1 0 TS 0 2 2 RX 1 1 0 RO 0 NOR 1 1 1 SRO-I IIC 4 4 2 0

SRO-U MAJ 2 2 1 0 TS 0 2 2 Instructions:

1. Check the afElicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC )"

and "balance-of-plant (BOP)" positions . Instant SROs must serve in both the SRO and the ATC positions ,

including at least two instrument or component (I/G) malfunctions and one major transient, in the ATC position . If an Instant SRO additionatrr serves in the BOP position, one IIC malfunction can be credited toward the two IIC malfunctions required for he ATC position .

Reactivi~ manipulations may be conducted under normal or controlled abnormal conditions (refer to 2.

Section .5.d) but must be sign ificant per Section C.2.a of Appendix D. P Reactivity and normal evolutions may be replaced with additional instrument or component mal unctions on a 1-for-1 basis.

3. Whenever practical , both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

ES-301, Page 26 of 27

ES-401 Written Examination Outline Form ES-401-1 Facility: 09-0 1 NRC Exam Date of Exam:  ;:/ 0/ b ttJ/o RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total I 2 3 4 5 6 I 2 3 4

• I. I 3 3 4 3 3 4 20 7 Emergency

& 2 I 1 I I I 2 7 3 Plant Tier Evolutions 4 4 5 4 4 6 27 \0 Totals I 3 2 2 2 3 2 3 2 2 2 3 26 5 2.

Plant 2 1 I I I I 1 I I 1 I 2 12 3 Systems Tier 4 3 3 3 4 3 4 3 3 3 5 38 8 Totals I 2 3 4 I 2 3 4

3. Generic Knowledge & Abilities 10 7 Categories 2 3 3 2 Note: I. Ensure that at least two topics from every applicable K/ A 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 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. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D. I.b of ES-40 I, for guidance regarding elimination of inappropriate KIA 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 or evolution .

5. Absent a plant specific priority, only those KAs 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 I and 2 from the shaded systems and KIA categories.

7.* The generic (G) KI As in Tiers I and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D. I.b of ES-40 I for the applicable KIA's

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (lR) 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. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note

1. 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3 . Limit SRO selections to KlAs that are linked to IOCFR55.43

ES-401 2 Form ES-401-1 09-01 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function KiA Topic(s)

EK 1.0 I - Knowledge of the operational 295030 Low Suppression Pool implications of the following concepts as X 3.8 Water Level /5 they apply to LOW SUPPRESSION POOL WATER LEVEL: Steam condensati on EK 1.02 - Knowledge of the operational implications of the following concepts as 295024 High Drywell Pressure / 5 X 3.9 they apply to HIGH DR YWELL PRESSURE

Containment bui lding integrity: Mark-III A K 1.03 - Knowledge of the operational implications of the following concepts as 295004 Partial or Total Loss of DC X they apply to PA RTI AL OR COMPLETE 2.9 Pwr/6 LOSS OF D.C. POWER : Electrical bus divisional separation A K2.02 - Knowledge of the interrelations 295023 Refueling Acc Cooling between REFUELI NG ACCIDENTS and the X 2.9 Mode / 8 following: Fuel pool cooling and cleanup system EK2.01 - Knowledge of the interrelations 295026 Suppression Pool High between SUPPRESSION POOL HIGH Water Temp. / 5 X 3.9 WAT ER TEMPERATURE and the following : Suppression pool cooling EK2.04 - Knowledge of the interrelations between HIGH CONTAINMENT 295027 High Containment TEMPERATURE (MARK III X 2.6 Temperature / 5 CONTAINMENT ONLY) and the following: SPDS/ERIS/CRIDS/GDS :

Mark-III AK3.01 - Knowledge of the reasons for 295005 Main Turbine Generator the following responses as they apply to Tri p / 3 X 3.8 MAIN TURBINE GENERATOR TRIP:

Reactor SCRAM AK3.06 - Knowledge of the reasons for 295003 Partial or Complete Loss of the following responses as they apply to AC / 6 X 3.7 PARTIAL OR COMPLETE LOSS OF A.C . POWER : Containment isolation AK3.01 - Knowledge of the reasons for 295006 SCRAM / I X the following responses as they apply to 3.8 SCRAM : Reactor water level response AA 1.02 - Ability to operate and/or monitor the following as they apply to 700000 Generator Voltage and Electric Gri d Disturbances X GENERATOR VOLTAGE AND 3.8 ELECTRIC GRID DISTURBANCES:

Turbine/generator controls.

AA 1.04 - Ability to operate and/or monitor the following as they apply to PARTIAL 29500 I Partial or Complete Loss of OR COMPLETE LOSS OF FORCED Forced Core Flow Circulation / I & X 2.6 CORE FLOW CIRCULATION : Rod 4

control and information system : BWR-5&6 AA 1.02 - Ability to operate and/or monitor the following as they appi"y to PARTIAL 2950 19 Partial or Total Loss of Ins!. Ai r / 8 X OR COMPLETE LOSS OF 3.3 INSTRUMENT AIR : Instrument air system valves: Plant-Specific EA2.03 - Ability to determ ine and/or 295038 High Off-site Release Rate interpret the following as they apply to

/9 X 3.5 HIGH OFF-SITE RELEASE RATE :

Radiation levels 2950 18 Partial or Total Loss of AA2 .01 - Ability to determine and/or CCW /8 X 3.3 interpret the followinll as they apply to

ES-401 2 Form ES-401-1 09-01 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function KIA Topic(s)

PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

Component temperatures EA2.04 - Ability to determine and/or interpret the following as they apply to 295037 SCRAM Conditi ons SCRAM CONDITION PRESENT AND Present and Reactor Power Above X 4.0 REACTOR POWER ABOVE APRM APRM Downscale or Unknown I I DOWNSCALE OR UNKNOWN :

Suppression pool temperature 2.2.25 - Equipment Control: Knowledge 29502 1 Loss of Shutdown Cooling of bases in technical specifications for X 3.2 14 limiting conditions for operations and safety limits.

2.4.11 - Emergency Procedures / Plan:

2950 16 Control Room X Knowledge of abnormal condition 4.0 Abandonment 17 prcedures.

2.2.42 - Equipment Control:: Ability to recognize system parameters that are 295025 High Reactor Pressure 1 3 X 3.9 entry-level conditions for Technical Specifications.

EK3.01 - Knowledge of the reasons for 295028 High Drywell Temperature the following responses as they apply to X 3.6 15 HIGH DRYWELL TEMPERATURE :

Emergency depressurization 2.2.39 - Equipment Control: Knowledge 29503 1 Reactor Low Water Levell of less than one hour technical 2

X 3.9 specification action statements for systems.

KIA Category Totals: 3 3 4 3 3 4 Group Point Total:

I 20

ES-401 3 Form ES-401-1 09-01 NRC Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE # / Name Safety Function KIA Topic(s)

EK 1.0 I - Knowledge of the operational implications of the following concepts as 295036 Secondary Containment X they apply to SECONDARY 2.9 High Sump/Area Water Level / 5 CONTAINMENT HIGH SUMP/AREA WATER LEVEL : Radiation releases EK2.06 - Knowledge of the interrelations between HIGH SECONDARY 295032 High Secondary X CONTAINMENT AREA TEMPERATURE 3.3 Containment Area Temperature / 5 and the following: Area temperature monitoring system EK3.0 I - Knowledge of the reasons for the 295029 High Suppression Pool following responses as they apply to HIGH X 3.5 Water Level / 5 SUPPRESSION POOL WATER LEVEL:

Emergency depressurization AAI.OI - Ability to operate and/or monitor 295022 Loss of CRD Pumps / I X the following as they apply to LOSS OF 3.1 CRD PUMPS: CRD hydraulic system AA2 .01 - Ability to determine and/or 295008 High Reactor Water Level interpret the following as they apply to HIGH X 3.9 12 REACTOR WATER LEVEL : Reactor water level 500000 High CTMT Hydrogen 2.4.6 - Emergency Procedures I Plan:

X 3.7 Conc.15 Knowledge of EOP mitigation strategies.

2.4. 11 - Emergency Procedures I Plan:

295020 Inadvertent Cont. Isolation X Knowledge of abnormal condition 4.0 15 & 7 procedures.

KIA Category Totals: 1 1 1 1 1 2 Group Point Total:

I 7

ES-401 4 Form ES-401-1 09-01 NRC Exam Written Examination Outline

• System # / Name K

1 K

2 K

3 Plant Systems - Tier 2 Group 1 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G Imp. Q#

K 1.05 - Knowledge of the physical connections and/or cause- effect relationships between HIGH 209002 HPCS X 2.8 PRESSURE CORE SPRAY SYSTEM (HPCS) and the following: Standby liquid control system: Plant-Specific K 1.13 - Knowledge of the physical connections and/or cause- effect 2 12000 RPS X relationships between REACTOR 3.5 PROTECTION SYSTEM and the following: Containment pressure K2.01 - Knowledge of electrical 400000 Component Cooling power supplies to the following : 2.9 X

Water CCW pumps K2.02 - Knowledge of electrical 21SOOS APRM I LPRM X power supplies to the following : 2.6 APRM channels K3.03 - Knowledge of the effect that a loss or malfunction of the SOURCE RANGE MONITOR 21SOO4 Source Range Monitor X 3.3 (SRM) SYSTEM will have on following: Rod control and information system : Plant-Specific K3.17 - Knowledge of the effect that a loss or malfunction of the UNINTERRUPTABLE POWER 262002 UPS (ACfDC) X 2.9 SUPPLY (A.C.lD.C.) will have on following: Process monitoring:

Plant-Specific K4.01 - Knowledge of A.C.

ELECTRICAL DISTRIBUTION 26200 I AC Electri cal 3.0 X design feature(s) and/or interlocks Distribution which provide for the following :

Bus lockouts K4.01 - Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM 218000 ADS X design feature(s) and/or interlocks 3.7 which provide for the following :

Prevent inadvertent initiatior of ADS logic KS.01 - Knowledge of the operational implications of the 263000 DC Electrical following concepts as they apply to X 2.6 Distribution D.C. ELECTRICAL DISTRIBUTION : Hydrogen generation during battery charging.

KS.06 - Knowledge of the operational implications of the 264000 EDGs X following concepts as they apply to 3.4 EMERGENCY GENERATORS (DIESEUJET) : Load sequencing K6.03 - Knowledge of the effect that a loss or malfunction of the 239002 SRVs X following will have on the 2.7 RELIEF/SAFETY VALVES : A.C.

power: Plant-Specific

ES-401 4 Form ES-401-1 09-01 NRC Exam Written Examination Outline

• System # / Name K

1 K

2 K

3 Plant Systems - Tier 2 Group 1 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K6.09 - Knowledge of the effect Imp. Q#

that a loss or malfunction of the following will have on the 3.1 26 1000SGTS X STANDBY GAS TREATMENT SYSTEM : Primary containment high pressure: Plant-Specific A 1.10 - Ability to predict and/or monitor changes in parameters associated with operating the 2 11 000 SLC X 3.7 STANDBY LIQUID CONTROL SYSTEM controls including: Lights and alarms A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 205000 Shutdown Cooling X SHUTDOWN COOLING SYSTEM 3.3 (RHR SHUTDOWN COOLING MODE) controls including: Heat exchanaer coolina flow A2.02 - Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and 217000 RCIC ) (b) based on those predictions, use 3.8 procedures to correct, control , or mitigate the consequences of those abnormal conditions or operations: Turbine trios A2.16 - Ability to (a) predict the impacts of the following on the RHA/LPCI : INJECTION MODE (PLANT SPECIFIC) ; and (b) 203000 RHRlLPCI: Injection based on those predictions, use

) 4.4 Mode procedures to correct, control , or mitigate the consequences of those abnormal conditions or operations: Loss of coolant accident A3.01 - Ability to monitor automatic operations of the INTERMEDIATE 215OO3 IRM X RANGE MONITOR (IRM) 3.3 SYSTEM including: Meters and recorders A3.10 - Ability to monitor automatic operations of the REACTOR 259002 Reactor Water Level 3.1 X WATER LEVEL CONTROL Control SYSTEM including: TDRFP lockup: TDRFP A4.01 - Ability to manually operate 300000 Instrument Air X and/or monitor in the control room : 2.6 Pressure gauges A4.03 - Ability to manually operate 20900 1 LPCS X and/or monitor in the control room : 3.7 Injection valves 2.4.49 - Emergency Procedures /

Plan: Ability to perform without 223002 PCISlNuclear Steam reference to procedures those

) 4.6 Supply Shutoff actions that require immediate operation of system components and controls.

ES-401 4 Form ES-40 1-1 09-01 NRC Exam Written Examination Outline

• System # / Name K

1 K

2 K

3 Plant Systems - Tier 2 Group 1 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G Imp. Q#

2.2.36 - Equipment Control: Ability to analyze the effect of maintenance activities, such as 212000 RPS ) 3. 1 degraded power sources, on the status of limiting conditions for operations.

2.1.31 - Conduct of Operations:

Ability to locate control room switches, controls, and indications, 26 1000 SGTS ) 4.6 and to determine that they correctly reflect the desired plant lineup.

K5.06 - Knowledge of the operational implications of the following concepts as they apply to 211000SLC X 3.0 STANDBY LIQUID CONTROL SYSTEM: Tank level measurement A 1.01 - Ability to predict and/or monitor changes in parameters 263000 DC Electrical associated with operating the D.C.

X 2.5 Di stribution ELECTRICAL DISTRIBUTION controls including: Battery charging/discharging rate K1 .06 - Knowledge of the physical connections and/or cause- effect relationships between 218000 ADS X AUTOMATIC 3.9 DEPRESSURIZATION SYSTEM and the following : Safety/relief valves I

r KIA Category Totals: 3 2 2 2 3 2 3 < 2 2 ~ Group Point Total : 26

ES-401 5 Form ES-40 1-1 09-01 NRC Exam Written Examination Outline

• System # / Name K

1 K

2 K

3 Plant Systems - Tier 2 Group 2 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G Imp. Q#

KI.23 - Knowledge of the physical connections and/or cause- effect relationships between 20200 1 Recirculation X RECIRCULATION SYSTEM and 3.4 the following : Average power range monitor flow converters: Plant-Specific K2.02 - Knowledge of electrical 20 1001 CRD Hydraulic X power supplies to the following: 3.6 Scram valve solenoids K3.07 - Knowledge of the effect that a loss or malfunction of the 290002 Reactor Vessellntemals X REACTOR VESSEL INTERNALS 3.1 will have on following: Nuclear boiler instrumentation K4 .01 - Knowledge of SECONDARY CONTAINMENT design feature(s) and/or interlocks 29000 I Secondary CTMT X which provide for the following: 3.5 Personnel access without breaching secondary containment:

Plant-System K5.03 - Knowledge of the operational implications of the 290003 Control Room HV AC X following concepts as they apply 2.6 to CONTROL ROOM HVAC Temperature control K6.05 - Knowledge of the effect that a loss or malfunction of the 286000 Fire Protection X following will have on the FIRE 2.6 PROTECTION SYSTEM Screen wash system : Plant-Specific A 1.01 - Ability to predict and/or monitor changes in parameters associated with operating the 20 1005 RCIS X ROD CONTROL AND 3.2 INFORMATION SYSTEM (RCIS) controls including: First stage shell pressure/turbine load : BWR-6 A2 .06 - Ability to (a) predict the impacts of the following on the REACTOR WATER CLEANUP SYSTEM; and (b) based on those 204000 RWCU ) predictions, use procedures to 2.5 correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C .

failure A3 .09 - Ability to monitor automatic operations of the 272000 Radiation Monitoring X RADIATION MONITORING 3.6 SYSTEM including: Containment isolation indications A4 .04 - Ability to manually operate 233000 Fuel Pool X and/or monitor in the control room : 2.9 Cooling/Clean up Pool level 2.4.20 - Emergency Procedures /

22300 1 Primary CTMT and Plan: Knowledge of operational X 3.8 Aux. implications of EOP warnings, cautions, and notes.

ES-401 5 Form ES-40 1-1 09-01 NRC Exam Written Examination Outline Plant Systems - Tier 2 Group 2 K K K K K K A A A A Imp. Q#

System # / Name G 1 2 3 4 5 6 1 2 3 4 2.4. 1 - Emergency Procedures /

22300 1 Primary CTMT and Plan: Knowledge of EOP entry X 4 .6 Aux.. conditions and immediate action steps.

KIA Category Totals: 1 1 1 1 1 1 1 1 1 1 2 Group Point Total:

I 12

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

• Facility:

Category 09-01 NRC Exam KIA # Topic Date:

IR RO Q#

SRO-Only IR Q#

1. Knowledge of procedures and limitations Conduct 2.1.36 3.0 involved in core alterations.

of Operations Ability to interpret reference materials, such 2.1.25 3.9 as graphs, curves, tables, etc.

Subtotal 2 2.2.12 Knowledge of surveillance procedures. 3.7 2.

Knowledge of limiting conditions for Equipment 2.2.22 4.0 operations and safety limits.

Control Ability to interpret control room indications to verify the status and operation of a system ,

2.2.44 4.2 and understand how operator actions and directives effect plant and system conditions.

Subtotal 3 Knowledge of radiation exposure limits under 2.3.4 3.2

3. normal or emergency conditions.

Radiation 2.3.11 Ability to control radiation releases. 3.8 Control Knowledge of Radialogical Safety Principles pertaining to licensed operator duties, such as 2.3.12 containment entry requirements, fuel handling 3.2 responsibilities, access to locked high-radiation areas, aligning filters, etc.

Subtotal 3 4.

Emergency Procedures /

Plan

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of general guidelines for EOP 2.4.14 3.8 usage.

Knowledge of low power / shutdown implications in accident (e.g., loss of coolant 2.4.9 3.8 accident or loss of residual heat removal) mitigation strategies.

Subtotal 2 Tier 3 Point Total 10

Appendix D Scenario Outline Form ES-D-l

• Facility: Clinton Power Station Examiners: Carl Moore Dell McNeil Scenario No.: One Operating Test No.: 2010301 Operators:

Initial Conditions:

Reactor power is 88%

Turnover:

1. Cross tie H-I busses with I supplying.

Event Malf. No. Event Event No. Type* Description I None BOP-N Cross tie H-I busses with I supplying 2 Override ATC-IIC Clogged filter CB pump 3 None ATC-R Lower reactor power with flow 4 Override ATC-C HCU failure pressure at zero requiring control rod to be driven into 00 5 Override BOP-C Turbine L.O. temperature controller 6 All - A02_01 - BOP-C Loss of seal water to A Circulating water pump 7_TVM 7 ALL-M RCIC unisolable steam line leak 2 areas 8 ALL-C BID 2 SRV's fail to open.

9

• (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor

• Page I of 2

Appendix D Scenario Outline Form ES-D-I Scenario No.: One Operating Test No.: 2010301 Narrative Summary Event # Description

1. Cross tie R-I busses with I supplying

2. Clogged filter CB pump applicant is required to secure the Condensate Booster Pump and start a standby pump.

3. Lower reactor power with flow required per the turnover sheet.

4. RCU failure pressure at zero requiring control rod to be driven into 00 call in from the field operator says there is a leak on the F-111 valve and the RCU.cannot be pressurized until repairs are complete requiring the control rod to be driven in to position 00

5. Turbine L.a. temperature controller fails causing main turbine lube oil temperature to rise requiring the operator to take manual control of main turbine lube oil temperature.

6. Loss of seal water to A Circulating water pump requiring it to be removed from service

7. RCIC un-isolable steam line leak 2 areas requiring a manual initiation of ADS

8. Upon the initiation of ADS 2 SRV's fail to open which requires manual operation to open two more relief valves to complete the blow down EOPS 1,6,3 Critical tasks:

• Blow down when two areas above max safe

• Verify seven relief valves open upon initiation of ADS

• Page 20f2

Appendix D Scenario Outline Form ES-D-l

• Facility: Clinton Power Station Examiners: Carl Moore Dell McNeil Scenario No.: Two Operating Test No.: 2010301 Operators:

Initial Conditions:

Reactor power is 50%

Turnover:

I. MDRFP locked out for maintenance

2. Shift TBCCW pumps for maintenance Event Malf. No. Event Event No. Type* Description 1 None BOP-N Swap TBCCW pumps 2 None ATC-R Raise reactor power with rods 3 BOP-C CCW pump trip YP_XMFfB -

39lX 4 Override ATC-C 'B ' RWCU pump seal plate temperature high 5 ED_EK20_TR BOP-C ERA T Static V AR Compensator trip UE 6 YPRRI5AA ATC-I FWLC level sensor failure 7 ALL-M Loss of stator water cooling causing Generator runback 8 XP_MMFFf_ ALL-M ATWS All Scram functions fail.

B4963 XMFfB5002 9 YP_XMFfB - ALL-M CRD Pump trip A or (B) on the scram 4852(3)

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

• Page 1 of 2

Appendix D Scenario Outline Form ES-D-l Scenario No.: Two Operating Test No.: 2010301 Narrative Summary Event # Description Narrative Summary Event # Description

l. Swap TBCCW pumps

2. Raise reactor power with rods lAW with the REMA

3. CCW pump trip. The 'B' operator will have to start the standby CCW pump in accordance with the ARP.

4. RWCU pump B develops a seal leak requiring its removal from service.

5. ERAT Static V AR Compensator trips. The 'B' RO places control switch to off and remove from service and perform 9082.01 in accordance with the ARP.

6. Feed water level instrument fails high causing the applicant to transfer FWLC to the operating channel.

7. Loss of stator water cooling generator runback manual scram required

8. A TWS all scram functions fail

9. On initiation of the scram the operating CRD pump will trip which will not allow the control rods to be driven in until CRD is restored.

EOPS 1,lA Critical tasks:

• Perform a manual scram at the confirmation of the main generator runback

• Restore CRD to drive control rods to shut down the reactor

• Lower reactor water level to control reactor power by terminating and preventing injection

• Inject SLC

• Page 2 of2

Appendix D Scenario Outline Form ES-D-l

• Facility: Clinton Power Station Examiners: Carl Moore Dell McNeil Scenario No.: Spare Operating Test No.: 2010301 Operators:

Initial Conditions:

Reactor power is 50%

Turnover:

I. Swap EHC pumps Event Malf. No. Event Event No. Type* Description I None BOP-N Shift EHC pumps 2 None ATC-R Raise reactor power with rods 3 ATC-C While with drawing control rod coupling failure (will recouple) 4 BOP-C SRV open (closes upon removal of fuses) 5 YP_XMFTB - BOP-C Spurious HPCS initiation 4102 6 Override ATC-C 'A' TDRFP trouble alarm 7 IT-14 ALL-M Instrument line break 8 IT-IS ALL-C Loss of all indication requiring RPV flooding EOP 2.

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

• Page 1 of 2

Appendix D Scenario Outline Form ES-D-l Scenario No.: Spare Operating Test No.: 2010301 Narrative Summary Event # Description

1. Shift EHC pumps per 3105.02 Main EHC hydraulic power unit.

2. Raise reactor power with rods per the REMA.

3. When with drawing control rod the coupling will fail requiring the operator to re-couple the control rod.

4. SRV will fail open and the SRV will close upon removal of the "B" control power fuses.

5. HPCS will initiate causing reactor power to lower. The "B" operator will have to secure HPCS.

6. 'A' TDRFP experiences a trouble alarm on a thrust bearing wear condition requiring tripping of the 'A' TDRFP. This will require verification that the running 'B' TDRFP is adequately maintaining level. A RR FCV runback will require entry to CPS 4008.01, Abnormal Coolant Flow and CPS 4100.02 Core Stability Control to verify no core instabilities along with entry into CPS 4002.01, Abnormal RPV LevellLoss of Feedwater At Power.

7. Instrument line break in the drywell causing drywell pressure to rise requiring a manual scram

• EOPS 1,1A

8. 4 minutes after the instrument line break there will be a loss of all RPV level instrumentation and RPV will have to be flooded to the Main Steam Lines.

Critical tasks:

• Secure HPCS

• Manual Scram

• Flood vessel to the main steam lines

• Page 2 of2