ML081190707

Updated Checklists - Administered Examination for the Fermi Initial Exam - January 2008

ML081190707
Person / Time
Site:	Fermi
Issue date:	03/25/2008
From:	Hironori Peterson Operations Branch III
To:	Jennifer Davis Detroit Edison
Shared Package
ML080860174	List: ML081190547 ML081190699 ML081190701 ML081190704 ML081190707 ML081200422 ML081200435 ML081200448 ML081200455
References
50-341/08-301
Download: ML081190707 (28)

Text

UPDATED CHECKLISTS - ADMINISTERED EXAMINATION FOR THE FERMI INITIAL EXAM -JANUARY 2008

ES-301 Administrative Topics Outline Form ES-301-1 acility: Fermi 2 ixamination Level: RO [XI SRO 0 Date of Examination: 01/28/2008 Operating Test Number: 2008-1 Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Type Code Describe activity to be performed Perform Thermal Limit Verification (MAPRAT) 293009 Core Thermal Limits GENERIC 2.1.7 -Ability to evaluate plant performance and make operational judgments based on operating characteristics / reactor behavior / and instrument interpretation. RO 4.4 I SRO 4.7 Complete and Communicate a Nuclear Plant Technical Data Form (Alert)

GENERIC 2.4.39 - Knowledge of the ROs responsibilities in emergency plan implementation.

RO 3.91SRO 3.8 Perform 24.202.03, HPCI System Piping Filled And Valve Position Verification 206000 High Pressure Coolant Injection System GENERIC 2.2.12 - Knowledge of surveillance procedures. RO 3.7 I SRO 4.1 Determine Dose Limit Will Be Exceeded and Initiate a Dose Extension.

GENERIC 2.3.4 - Knowledge of radiation exposure limits and contamination control / including permissible levels in excess of those authorized.

RO 3.21SRO 3.7 30TE: 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 8 Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes)

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

(P)revious 2 exams (5 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Administrative ToDics Outline Form ES-301-1

acility: Fermi 2 ixamination Level: RO 0 SRO [XI Date of Examination: 01/28/2008 Operating Test Number: 2008-1 Administrative Topic (See Note)

Conduct of Operations Conduct of ODerations Equipment Control Radiation Control Emergency Plan Describe activity to be performed Perform Thermal Limit Verification (MAPRAT) 293009 Core Thermal Limits GENERIC 2.1.7 -Ability to evaluate plant performance and make operational judgments based on operating characteristics I reactor behavior I and instrument interpretation. RO 4.4 I SRO 4.7 Knowledge of Shift Staffing Requirements GENERIC 2.1.4 - Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

Perform 24.202.03, HPCI System Piping Filled And Valve Position Verification 206000 High Pressure Coolant Injection System GENERIC 2.2.12 - Knowledge of surveillance procedures. RO 3.7 SRO 4.1 Determine Dose Limit and Complete a Dose Extension GENERIC 2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions.

RO 3.21SRO 3.7 RO 3. 3 1 ~ ~ 0 3.8 Perform On-Site Protective Actions and Classification for Security Event (Alert)

GENERIC 2.4.40 - Knowledge of the SROs responsibilities in emergency plan implementation.

RO 2.7 SRO 4.5 UOTE: 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 (0)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes)

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

(P)revious 2 exams (5 1; randomly selected)

ES 301, Page 22 of 27

~

Control Roomlln-Plant Systems Outline Form ES-301-2 ES-301 Facility: Fermi 2 Exam Level: RO SRO-I 0 SRO-U 0 Date of Examination: 1/28/2008 Operating Test Number: 2008-1 Control Room Systems" (E for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title

a. Manually Start the RClC System 217000 Reactor Core Isolation Cooling System A4. Ability to manually operate and/or monitor in the control room:

A4.04 Manually initiated controls RO 3.6 / SRO 3.6

b. Respond to Refuel Floor High Radiation 272000 Radiation Monitoring System AZ. Ability to (a) predict the impacts of the following on the RADIATION MONITORING SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.12 Refuel floor handling accidents/operations RO 3.3 l SRO 4.0

c. Manually Initiate Low Low Set (No Fault) 239002 RelieflSafety Valves A4. Ability to manually operate and/or monitor in the control room:

A4.01 SRV's RO 4.4 / SRO 4.4

3. SOP Run of Core Spray System in Test Mode 209001 Low Pressure Core Spray System A2. Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.06 Inadequate system flow RO 3.2 l SRO 3.2

1. Restore a RWCU Pump After Oil Sample (Plant Hot) With System Leak 223002 Primary Containment Isolation System /Nuclear Steam Supply Shut-Off A2. Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.03 System logic failures RO 3.0 / SRO 3.3

f. Respond to Multiple Rod Drifts and RPS Failure 212000 Reactor Protection System AZ. Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.16 Changing mode switch position RO 4.0 I SRO 4.1 and Failure to Isolate Type Code' D,S P,EN,D,A,S Safety Function 2

4 5

7

g. Manually Initiate Div 1 Emergency Equipment Cooling Water 400000 Component Cooling Water Systems (CCWS)

A4. Ability to manually operate and I or monitor in the control room:

A4.01 CCW indications and control.RO 3.1 I SRO 3.0

h. Shift Operating CRD Pumps 201001 Control Rod Drive Hydraulic System A4. Ability to manually operate andlor monitor in the control room:

A4.01 CRD pumps RO 3.1 I SRO 3.1 N A S D,S In-Plant Systemsa (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

j. Defeat ARI Logic Trips 216000: Nuclear Boiler Instrumentation EA1 Ability to operate andlor monitor the following as they apply to scram condition present and reactor power above aprm downscale or unknown :

EA1.03

k. Place ESF Battery Charger in Service 263000: DC Electrical Distribution Al. Ability to predict andlor monitor changes in parameters associated with operating the D.C. ELECTRICAL DISTRIBUTION controls including:

ARIIRTIATWS: Plant-Specific... RO 4.1 I SRO 4.1 (CFR: 41.5 145.5)

AI.01 Battery charging I discharging rate RO 2.5 I SRO 2.8 0

1 7

6 I. Shift In Service IAS Dryers 300000: Instrument Air System AZ. Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

A2.01 Air dryer and filter malfunctions RO 2.9 I SRO 2.8 All RO and SRO-l control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

'Type Codes Criteria for RO I SRO-l I SRO-U

~~~

(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (S)imulator (R)CA 4-6 I 4-6 I 2-3 e 9 1 5 0 1 5 4

> I / >I 1 2 1

- I - I ) 1 (control room system)

> I 1,I 1 2 1

> 2 1 )2 1 2 1

- 3 15 3 I 5 2 (randomly selected)

> I I 2 1 I 2 1 ES-301, Page 23 of 27

ES-301 Control Roomlln-Plant Svstems Outline Form ES-301-2 Facility: Fermi-2 Exam Level: RO 0 SRO-I SRO-U 0 Date of Examination: 01/28/2008 Operating Test Number: 2008-1 Control Room Systems" (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title

a. Manually Start the RClC System 217000 Reactor Core Isolation Cooling System A4. Ability to manually operate andlor monitor in the control room:

A4.04 Manually initiated controls RO 3.6 / SRO 3.6

b. Respond to Refuel Floor High Radiation 272000 Radiation Monitoring System A2. Ability to (a) predict the impacts of the following on the RADIATION MONITORING SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.12 Refuel floor handling accidents/operations RO 3.3 I SRO 4.0

c. Manually Initiate Low Low Set (No Fault) 239002 ReliefISafety Valves A4. Ability to manually operate andlor monitor in the control room:

A4.01 SRVs RO 4.4 I SRO 4.4

d. SOP Run of Core Spray System in Test Mode 209001 Low Pressure Core Spray System A2. Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.06 Inadequate system flow RO 3.2 I SRO 3.2

e. Restore a RWCU Pump After Oil Sample (Plant Hot) With System Leak 223002 Primary Containment Isolation System /Nuclear Steam Supply A2. Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEMlNUCLEAR STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.03 System logic failures RO 3.0 / SRO 3.3 and Failure to Isolate Shut-Off

f. Respond to Multiple Rod Drifts and RPS Failure 212000 Reactor Protection System A2. Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.16 Changing mode switch Dosition RO 4.0 / SRO 4.1 Type Code' P,EN,D,A.S Safety Function 2

4 5

7

g. Manually Initiate Div 1 Emergency Equipment Cooling Water 400000 Component Cooling Water Systems (CCWS)

A4. Ability to manually operate and I or monitor in the control room:

A4.01 CCW indications and control.RO 3.1 I SRO 3.0 In-Plant Systemsa (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

j. Defeat ARI Logic Trips 216000: Nuclear Boiler Instrumentation EA1 Ability to operate andlor monitor the following as they apply to scram condition present and reactor power above aprm downscale or unknown :

EA1.03 ARIIRTIATWS: Plant-Specific... RO 4.1 I SRO 4.1

k. Place ESF Battery Charger in Service 263000: DC Electrical Distribution A I. Ability to predict andlor monitor changes in parameters associated with operating the D.C. ELECTRICAL DISTRIBUTION controls including:

(CFR: 41.5 145.5)

A1.O1 Battery charging I discharging rate RO 2.5 I SRO 2.8 I. Shift In Service IAS Dryers 300000: Instrument Air System AZ. Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

A2.01 Air dryer and filter malfunctions RO 2.9 I SRO 2.8 7

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 selve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes I

Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 /

4-6 / 2-3 (C)ontrol room (D)irect from bank

< 9 / ( a / 5 4 (E)mergency or abnormal in-plant

> I / >I / > I (EN)gineered safety feature (L)ow-Power / Shutdown

> I / )I / > 1 (N)ew or (M)odified from bank including 1(A)

> 2 /,2 /,I

> I / >I

/ > 1

- / - I 2 1 (control room system)

(P)revious 2 exams jS)imulator

< 3 I 5 3 / 5 2 (randomly selected)

ES-301, Page 23 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Fermi-2 Exam Level: RO 0 SRO-I 0 SRO-U [XI Date of Examination: 01/28/2008 Operating Test Number: 2008-1 Control Room Systems" (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title

a. Manually Start the RClC System 217000 Reactor Core Isolation Cooling System A4. Ability to manually operate and/or monitor in the control room:

A4.04 Manually initiated controls RO 3.6 I SRO 3.6

b. Respond to Refuel Floor High Radiation 272000 Radiation Monitoring System A2. Ability to (a) predict the impacts of the following on the RADIATION MONITORING SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.12 Refuel floor handling accidentsloperations RO 3.3 I SRO 4.0

i. Temporary Removal and Restoration of SDC for 18C Surveillances 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

A4. Ability to manually operate andlor monitor in the A4.01 SDClRHR pumps RO 3.7 I SRO 3.7 A4.03 SDC/RHR discharge valves RO 3.6 / SRO 3.5 A4.05 Minimum flow valves RO 3.2 / SRO 3.2 In-Plant Systems" (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) control room:

j. Defeat ARI Logic Trips 216000: Nuclear Boiler Instrumentation EA1 Ability to operate and/or monitor the following as they apply to scram condition present and reactor power above aprm downscale or unknown :

EA1.03 ARIIRTIATWS: Plant-Specific... RO 4.1 I SRO 4.1

k. Place ESF Battery Charger in Service 263000: DC Electrical Distribution AI. Ability to predict andlor monitor changes in parameters associated with operating the D.C. ELECTRICAL DISTRIBUTION controls including:

(CFR: 41.5 145.5)

AI.01 Battery charging I discharging rate RO 2.5 I SRO 2.8

~~

Type Code' D.S N,EN,A,S Safety Function 2

9 4

7 6

All RO and SRO-I control room (and in-plant) systems must be different and sene different safety functions; all 5 SRO-U systems must sene different safety functions; in-plant systems and functions may overlap those tested in the control room.

Criteria for RO / SRO-I / SRO-U

'Type Codes I

(A)lternate path 4-6 I 4-6 / 2-3 (C)ontrol room (0)irect from bank

< 9 / ( 8 I 5 4 (E)mergency or abnormal in-plant

> I / > I / > I (EN)gineered safety feature

- I - / 2 1 (control room system)

> I / > I /, I (L)ow-Power I Shutdown

> 2 1 > 2 1 2 1 (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams

> I / > I / > 1 (R)CA 1S)imulator

- - 3 I( 3 I 5 2 (randomly selected)

ES-301, Page 23 of 27

ES-301 Transient and Event Checklist Form ES-301-5 acility: Fermi-2 Date of Exam: 1/28/2008 Operating Test Number: 2008-1 A

P P

L I C

A N

T 10 3

4 3

RO-I

RO-U -

!?

?-I Yo-u Y-'

Y Y-I Y-"

10 7

IRO-U -

lnstruc E

l Scenarios V

E N

T T

Y P

E -

RX VOR

/c

\\nAJ rs

~ -

RX NOR

~

IC TS RX NOR

\\rlAJ rs VOR

~

WAJ

~

I/C

~ -

RX

~

I/C WAJ

~

TS ins:

1 CREW POSITION

$E-2 3

l 4

POSITION POSITION POSITION 0

0 I

Check tne a event ly e f8 are not ap licable for RO ap licants. ROs must serve in both tne "at-the-controls (ATC) and.bal%ie-of-lant (B8P)' positions Insfant SROs must serve In DOth the SRO and ATC pos.tions.

including at leasrtwo instrument or component,(l/C) malfunctions and one major transient in the ATC Dosition If an instant SRO additionallv serves in the BOP Dosition. one I IC) malfunction can be credited licant level and enter the operating test number and Form ES-D-1 event numbers for each toward the two (IC) malfunctions required for the ATC position.

Reactivit manipulations may be conducted under normal or controlled abnormal conditions (refer to Section 8.5.d) but must be significant,per Section C.2.a of Appendix D. *) Reactivity and normal evolutions may be replaced with additional instrument or component malhnctions on a 1-for-1 basis.

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

2.

3.

ES-301, Page 26 of 27

ES-301 Transient and Event Checklist Form ES-301-5

-acility: Fermi-2 Date of Exam: 1/28/2008 Operating Test Number: 2008-1 A

P P

L I C

A N

T RO ISI sI"0-l E

E0-I RO 0

E O - '

FU E -

SRO-I SRO-U 0

0 -

lnstruc M

I N

I M

U M(')

01212

1.

Check the aoolicant level and enter the ooeratino test number and Form ES-D-1 event numbers for each event ty e t$ are not ap licable for RO ap Iicahts ROs must Serve in both the at-the-controls (ATC)'

and.baknce-of-Ian1 (BCfP)' positions InsLnt SROs must serve in both tne SRO ana ATC posit ons.

includ ng at leasftwo instrument or component (I/C) malfunctions and one major trans ent, n the ATC posltion fan nstant SRO additionally serves in the BOP osition, one (IC) malfdnction can be cred teo oward tne two (IC) malflrnct ons required for the ATC posil;)on 2

Reactivit manipulations may be conducted under normal or controlled abnormal cond,tions (refer to Section 8.5 d) but must be significant per Section C.2.a of Appendix D

) Reactivity and norma Whenever practical. both instrument and component malfunctions should be included. only those that require verifiable actions that provide insight to the applicanfs w m etence count toward the minimum reouirements SDeCified for the aDDlicant's license level in &e riaht-hand collrmns evolutions may be replaced with additional instrument or component mal r unctions on a 1-for-I basis 3

ES-301, Page 26 of 27

ES-301 Competencies Checklist Form ES-301-6 Date of Examination: 1/28/2008 (1)

(2)

Optional for an SRO-U.

(3)

Only applicable to SROs.

Includes Technical Specification compliance for an RO Operating Test No.: 2008-1 ANTS I

I I

I I

I Instructions:

Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-301, Page 27 of 27

ES-301 Competencies Checklist Form ES-301-6 Date of Examination: 1/28/2008 Operating Test No.: 2008-1 I Notes:

(1)

(2)

Optional for an SRO-U.

(3)

Only applicable to SROs.

Includes Technical Specification compliance for an RO.

Instructions:

Check the applicant's license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-301, Page 27 of 27

ES-401 Written Examination Outline Form ES-401-1

'acility:

Fermi 2007 NRC Exam Date of Exam:

1/21/2008 Tier I.

Emergency Plant Evolutions

2.

Plant Systems qote:

1.

2.

3.

4.

5.

6.

7.'

8.

9.

I

3. Generic Knowledge & Abilities Categories I

I I

I I

I I

I I

I Ensure that at least two topics from every applicable WA category are sampled within each tier ofthe RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not he less than two).

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 i1 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.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should he deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.1.b of ES-401, for guidance regarding elimination of inappropriate W A statements.

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.

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.

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

The generic (G) WAS in Tiers I and 2 shall he selected from Section 2 of the W A Catalog, but the topics must he relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable WA's On the following pages, enter the W A numbers, a brief description of each topic, the topics' impoltance 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 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 #I does not apply).

Use duplicate pages for RO and SRO-only exams.

lor I isr 3. selecl topics irom Section 2 of the K A Catalog. and enter the K.I\\ nuinhcrs. hcription>. IK,. ;and

_p(snl tolals (P) on Form t:S-401-3. l.imit SRO selections WAS that arc_link$j.lo Ill('l:KSS 43

T PP EP ZP I P Ob 6E zx i x ox h i 81 L L

'JL 5 r 0 P 8 E Z E Z E Z E 9 t it 7 t X L tP L t 2 t lN3WNOONVW L'iOOtl lOtllN03 oi Aidde Aaui se sasuodsai fiu1mo11or 8 I IIV

' l S U l J 0 SSOl IVlOLiO IB!lred 610562 l-LOP-S3 WJOA tots3

ES-401 2

recirculation AKI.01 - Knowledge of the operational implications of the following concepts as they apply to REFUELiNG ACCIDENTS :

Radiation exposure hazards 2.1.27. Knowledge of system purpose andlor fundion.

EKI.04 - Knowledge of the operational Form ES-401-1 3,6 48 3.9 49 Outline 1 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 implications of the following concepts as they apply to HIGH REACTOR PRESSURE : Decay heat generation EKI.01 - Knowledge of the operational implicalions of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE : PUmD 3,6 3.0 1 EAPE # I Name Safety Function I K1 I K2 I K3 I A1 I A2 [ G I WA Topic@)

I Imp. I Q#

50 5 1 295023 Refueling Accidents I 8 295024 High Drywell Pressure 1 5 295031 Reactor Low Water Level 1 2 295028 High Drywell Temperature 15 I x I 1

295025 High Reactor Pressure 13 X

295026 Suppression Pool High Water remp. 1 5 600000 Plant Fire On-site I 8 X

700000 Generator Voltage and Electric

rid Disturbances CIA Category Totals

I I

I NPSH I

I I EK2 03 - Knowledge of the interrelations I I 4 2 I 52 between REACTOR LOW I

l l

WATER LEVEL and the following Low I

I I pressure core spray I

I I EA1 01 - Abilitv to operate anolor monitor I the following as they apply to HIGH X

I I I ORYWELL TEMPERATURE Drywell I

I I spray Ma&-1811 I

I 1 EA1 02 - Abilitv to operate andlor monitor I H

2.1.25 -Conduct of Operations: Ability to intemret reference materials. such as 3.9 graphs, curves, tables, etc.

I I

2.1.32 - Conduct of Operations: Ability to I

explain and apply all system limits and precautions.

AK3.04 - Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE: Actions contained in the abnormal Dlocedure for Dlant fire on 2.8 I 57 AA1.03 -Ability to operate andlor monitor the following as they apply to GRID DISTURBANCES: Voltage regulator controls.

Group Point Total:

2017

ES-401 3

Form ES-401-1 Outline 1 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 2 I EAPE # I Name Safety Function I K1 I K2 I K3 I A I I A2 [ G I KIA Topic@)

I Imp. 1 w 1 295008 I ligli Reactor Water 1.cvcl I ?

2YSO.33 High Sccondary Conlainnicnl Area Riidialion I.cvcIs 1 9 295010 High Drywell Pressure I 5

ES-401 K

K K

K K

K A

A A

A G

System # / Name 1

2 3

4 5

6 1

2 3

4 4

Form ES-401-1 Outline 1 Written Examination Outline Plant Systems -Tier 2 Group 1 Imp.

Q#

223002 I'C'ISINaclcar Srciini Supply Shurofl 215Ui13 lllM 203000 RHWLPCI. lnjeclion Mode 205000 Shutdown Cooling 206000 HPCl 209001 LPCS 21 1000 SLC and the following: Condensate sforage and transfer system: PlanlSpecific A1.O1 -Ability to predict and/or monitor changes in parameters associated with operating the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) controls including:

Heat exchanger cooling now A2.04 -Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM ; and (b) based on those predictions, use procedures lo correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C. failures: BWR-2.3.4 K3.03 - Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following: Emergency generators K1.02 - Knowledge of the physical connections andlor cause-effect relationships between STANDBY LIQUID CONTROL SYSTEM and the following: Core plate differential pressure indication

ES-401 K

K K

K K

K A

A A

A G

Imp.

1 2

3 4

5 6

1 2

3 4

System # I Name 4

Form ES-401-1 Outline 1 Written Examination Outline Plant Systems - Tier 2 Group 1 Q#

212000 RPS 215003 IRM 215003 IRM 215004 Source Range Monitor 215005 APRM / LPRM 2 I7000 RClC 218000 ADS 223002 PCISlNuclear Steam

upply Shutoff 239002 SRVs 239002 SRVs 259002 Reactor Water Level

.ontrol 261000 SGTS X

procedures.

K2.01 - Knowledge of electrical power supplies to the following: IRM channelddetectors K4.01 -Knowledge of SOURCE RANGE MONITOR (SRM) SYSTEM design feature@) and/or interlocks which provide for the following: Rod I I I I I withdrawal blocks I K5 04 - Knowledge of the operational implications of the following concepts as they apply to AVERAGE POWER RANGE MONITOWLOCAL POWER RANGE MONITOR SYSTEM : LPRM 2.2.44 - Equipment Control: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives effect plant and monitoring A2 05 -Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM,

and (b) based on those predictions, use Drocedures to correct control or X

mitigate the consequences ofthose abnormal conditions or operations:

loss or malfunction of the STANDBY GAS TREATMENT SYSTEM will have on following: High pressure coolant injection system: Plant-

ES-401 K

K K

K K

K A

A A

A G

1 2

3 4

5 6

1 2

3 4

System # / Name 4

Form ES-401-1 Outline 1 Written Examination Outline Plant Systems - Tier 2 Group 1 Imp.

Q#

261000 SGTS 261000 SGTS 262001 AC Electrical Distribution 262001 AC Electrical Distribution I l l 203000 RHWLPCI Injection 263000 DC Electrical Distribution 263000 DC Electrical Distribution 264000 EDGs ii 300000 lnstmrnent Air

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I l l 300000 Instrument Air 400000 Component Coaling Water KIA Category Totals.

A2 11 -Ability 10 (a) pred.ct the mpacls of the follow4ng on the STANDBY GAS TREATMENT SYSTEM an0 (b) based on those predictions. bse proceaures 10 correct. control. or m t gate the consequences of tnose abnormal conditions or oDeratons H ah containment pressure K5 01. Knowledge of tne operational implications ofthe following concepts as they apply to A.C. ELECTRICAL DISTRIBUTION: Principle involved with paralleling two A.C. sources A1.02 -Ability to predict andlor monitor changes in parameters associated vvlth operating the RHWLPCI: INJECTION MODE (PLANT SPECIFIC) controls including: Reactor pressure A4.01 -Ability to manually operate and/or monitor in the control room:

Major breakers and control power fuses: Plant-Specific 2.4.35. Emergency Procedures 1 Plan:

Knowledge of local auxiliary operator tasks during emergency and the resultan1 operat onal effects K4 06 - Knowleoge of EMERGENCY GENERATORS (OIESEUJET) design featurep) analor nterioc6s w n m provide for the following: Govemoi control K4.03 -Knowledge of (INSTRUMENT AIR SYSTEM) design feature@) and or interlocks which provide for the following: Securing of IAS upon loss of cooling water A3.02 -Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including: Air temperature K2.01 - Knowledge of electrical power supplies to the following: CCW pumps Group Point Total:

32 3 1 39 3 3 -

3 8 26 28 -

2 9 -

29 7

I 2615

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ES-401 System # I Name 5

Form ES-401-1 Outline 1 Written Examination Outline Plant Systems - Tier 2 Group 2 K

K K

K K

K A

A A

A G

Imp.

Q#

1 2

3 4

5 6

1 2

3 4

K2.05 - Knowledge of electrical power supplies to the following: Reactor building ventilation monitors: Plant-Specific 2.2.40 - Equipment Control: Ability to system.

272000 Radialion Monitoring X

288000 Plant Ventilation X

apply technical specifications for a 2.6 37 3.4 38 KIA Category Totals.

1 1

1 1

1 1

2 2

1 1

3 Group Point Total:

I213

ES-401 Generic Knowledge and Abilities Outline (Tier3)

Form ES-401-3 Facility:

Category I.

onduct

)f Operations 3quipment hntrol I.

cadiation h t r o l Outline 1 Date:

I RO SRO-Only IR Q#

IR Q#

WA ?#

Topic 1

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Ability to use procedures to determine the etrects on reactivity of plant changes. such as KCS tenipcrature.

sccondary plant, he1 depletion, etc.

2. I.43 2.1.41 Knowledge of the refueling process.

2.8 2.1.5 such as minimum crew complement, overtime 2.9 Ability to use procedures related to shifl staffing, limitations, etc.

Subtotal Knowledge ofthe process for controlling equipment I Ability to determine 'Technical Specification Mode of I Operation.

I I

3.6 Knowledge of conditions and limitations in the 2.2.38 facility license.

2.2.13 Knowledge of tagging and clearance procedures.

4.1 2.2.40 Abiliw to amlv technical specifications for a svstem.

3.4 Subtotal I

2.3.5 2.3.4 fixed radiation monitors and alarms, portable survey 2.3.13 2.3.15 iuhtotal Knowledge of Radiological Safety Procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

3.4 2.9 1 4.3 I 95 I 4.5 I 96

ES-401 Generic Knowledge and Abilities Outline (Tier3)

Form ES-401-3 Knowledge of operational implications of EOI' Knowledge of the bases for prioritizing emergency operations.

2.4.20 warninss, cautions, and notes.

2.4.23 procedure implementation during cmergcncy 4.3 4.4 Emergency Procedures I Plan

4.

1 2.4.'

2.4.27 2'4'43 99 Knowledge of EOP entry conditions and immediate 4,6 73 action steps.

Knowledge of "fire in the plant" procedures.

3.4 74 Knowledge of emergency communications systems 3,2 75 and techniques.

Subtotal 3

Tier 3 Point Total IO

ES-401 Record of Rejected WAS Form ES-401-4 Tier I Group 1 I1 1 11 1 1 1 1 I1 1 11 1 / I 2 I1 2 I1 21 1 2 11 2 I1 2 12 2 I 2 Randomly Selected WA 295027 I EK2.03 295021 / AK2.06 295028 I EA1.04 295004 12.2.4 295024 I EA2.07 600000 12.2.40 215003 12.4.30 262002 I AI.02 239002 I K5.06 207000 I 2.1.23 207000 I A2.06 239003 I A1.07 239003 12.1.23 I

Reason for Rejection Fermi-2 is equipped with a Mark I Drywell I Torus. Mark 111 Containment is NA. Kept same Statement number. Randomly reselected EPE 29503 1. (29503 1 EK2.03)

Fermi-2 RHR Head Spray is not used.

Kept same APE number. Randomly reselected statement AK2.07 (295021 AK2.07)

Double Jeopardy with 295010 I AA2.06. Both randomly selected topics relate Drywell Temperature and Pressure. Kept same EPE 295028. Randomly reselected statement EAI.01 (295028 EAI.01)

Fermi-? is a Single Unit plant. Multi-unit KA Statcmcnt is NA.

Kept same APE 295004, randomly reselected Statement 2.2.25. (295004 2.2.25)

Fenni-2 is equipped with a Mark I Drywell I Torus. Mark 111 Containment is NA. Kept samc I.~t'E number. Randomly reselected statement EA2.01 (295024 EA2.01)

Plant Fire On Site - Ability to apply 'I'cchnical Spccitications for a System is not relevant. Kept sanie APE. liandomly reselected statement 2.4.41 (600000 2.4.41)

Low Operational Validity. Intermediate Range Monitors have no conditions which require an RO to notify organizations or agencies. Kept same System number. Randomly reselected statement 2.4.31. (215003 2.4.31)

Fermi-2 Unintermptible Power Supplies do not include Motor Generators. Only remaining A1 statement in 262002 has RO Importance below 2.5. Kept same Statement number.

Randomly reselected System 203000. (203000 AI.02)

Double Jeopardy with 239002 I K6.05. Both randomly selected topics involve SRV Tailpipe Vacuum Breaker operation. Kept same System 239002. Randomly reselected statement K5.04 (239002 K5.04)

Fermi-2 is not equipped with 'an Isolation Condcnscr. Kept same Statement number. Randomly reselected System 223002.

(223002 2.1.23)

Fermi-2 is not equipped with an lsolation Condenser. Kept same Staterncnt number. Randomly rcselectcd Systcni 21 8000.

(21 8000 A2.06)

Fermi-2 MSIV-LCS is abandoned in place. Kept same statement number. Randomly reselected System 201 001.

(201001 A1.07)

Ih-mi-2 MSIV-I..CS is abandoned in place. 2.1.23 is previously used on SRO System 223002. Randomly reselected

ES-401 Record of Rejected WAS Form ES-401-4 Randomly Selected WA 21 9000 / 2.4.23 2.3.13 295024 12.1.27 295007 I AK1.02 295022 12.4.18 295036 I EK2.02 2.2.15 295016 / 2.1.30 295030 / EA2.04 295012 / 2.2.39 22.3002 / 2.1.23

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262001 /2.1.19 Reason for Rejection Statement 2.4.23 is not specified in NUREG 1021 (SUPI) ES-401 page 4 of34 as an appropriate Tier 1 or 2 Generic.

Rendomly reselected statement 2.4.1 1. (219000 2.4.1 1)

Double Jeopardy for SRO candidates. wme 'I icr 3 Cicncric selected on RO exam. Randomly resclccted statement 2 3.4 (Generic 2.3.4)

Could not write an appropriate RO Level question regarding High Drywell Pressure - Knowledge of a system purpose or function without Double Jeopardy. Randomly reselected statement 2.2.22. 295024 2.2.22 Double Jeopardy with 295025 EKl.04 Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR PRESSURE : Decay heat generation. Randomly reselected APE 295008. Kept same Statement. 295008 AKI.02 Loss of CRD Pumps has no relation to Knowledge of specific bases for EOPs. Randomly reselected statement 2.4.1 1. Kept same APE. 295022 2.4.1 1 Secondm Containment Hieh Water Level has no association with the Post-Accident Sampling System. Randomly reselected statement EK2.03. Kept same EPE. 295036 EK2.03 Double Jeopardy with Operating Exam JPM. System Lineup is used to verify system status. Randomly reselected statement 2.2.13.

Topic is not unique to SKO duties; KOs arc also required to locate and operate components, including local controls.

Randomly reselected statement 2.4.4. Kept same APE.

2950 16 2.4.4 Drywell/ suppression chamber differential pressure is not relevant to Low Suppression Pool Level at Fermi-2.

Randomly reselected statement EA2.01. Kept samc IPI~1.

295030 EA2.01 High Drywell Temperature has no relation lo Knowledge of less than or equal to one hour 'Technical Specification action statements for systems. Randomly reselected statement 2.2.22. Kept same APE. 295012 3.2.22 Could not write an appropriate LOD 1,OK question for the SRO Level question using this statement. Randomly reselected statement 2.2.36. Kept same System. 223002 2.2.36 Topic is not unique to SRO duties; ROs are also required to use plant computers to evaluate system or component status.

Randomly reselected statement 2.4.8 Kept same System.

262001 2.4.8

ES-401 Tier I Group 21 1 211 1 / 1 111 3

211 212 212 112 Randomly Selected K/A 223001 1 2.1.20 212000 A3.06 295024 12.2.22 295026 / EKl.02 2.2.43 261000 I K3.06 234000 / AI.02 201001 lA1.07 295008 lAA2.02 Record of Rejected WAS Form ES-401-4 Reason for Rejection Could not write an appropriate SRO 1,evel question regarding Priinary Containment and Auxiliaries -- ability to interpret and execute procedure steps. Randomly reselected statcnient 2.2.40. Kept same System. 223001 2.2.42 Double Jeopardy with 295005 AA2.05. Both topics relate Main Turbine Generator Trip / Scram association with Reactor Power. Randomly reselected statement A3.05. Kept same System. 212000 A3.05 Low Operational Validity. At Fermi-2, High Drywell Pressure EOP entry condition is met prior to exceeding High Drywell Pressure LCO. Addressing an LCO vice mitigating accident condition has Low Operational Validity. Randomly reselected Knowledge of the operational implications of the following concepts as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Steam condensation.

Kandomly reselected statement 2.2.38.

Could not write an appropriate KO Lcvel question regarding Primary Containment Oxygen content. Randomly reselected reselected statement AA2.05. Kent same APE. 295008