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

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

ES-301 Administrative Topics Outline Form ES-301-1 acility: Fermi 2 Date of Examination: 01/28/2008 ixamination Level: RO [XI SRO 0 Operating Test Number: 2008-1 Administrative Topic Type Describe activity to be performed (See Note) Code Perform Thermal Limit Verification (MAPRAT) 293009 Core Thermal Limits GENERIC 2.1.7 -Ability to evaluate plant Conduct of Operations 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)

Conduct of Operations 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 Equipment Control 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 Radiation Control limits and contamination control / including permissible levels in excess of those authorized.

RO 3.21SRO 3.7 Emergency Plan 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 1)(r (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 Date of Examination: 01/28/2008 ixamination Level: RO 0 SRO [XI Operating Test Number: 2008-1 Administrative Topic Describe activity to be performed (See Note)

Perform Thermal Limit Verification (MAPRAT) 293009 Core Thermal Limits GENERIC 2.1.7 -Ability to evaluate plant Conduct of Operations 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 Conduct of ODerations as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

RO 3 . 3 1 ~ ~3.8 0 Perform 24.202.03, HPCI System Piping Filled And Valve Position Verification Equipment Control 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 Radiation Control GENERIC 2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions.

RO 3.21SRO 3.7 Perform On-Site Protective Actions and Classification for Security Event (Alert)

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

RO 2.7 SRO 4.5 UOTE: All items (5total) 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 (53 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank 1)(z (P)revious 2 exams (5 1; randomly selected)

ES 301, Page 22 of 27

~ .. _.. .

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

Safety System / JPM Title Type Code' Function

a. Manually Start the RClC System D,S 2 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 P,EN,D,A,S 4 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 5 and Failure to Isolate 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 7 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

g. Manually Initiate Div 1 Emergency Equipment Cooling Water NAS 0 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 D,S 1 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 In-Plant Systemsa (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

j. Defeat ARI Logic Trips 7 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 6 263000: DC Electrical Distribution Al. 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 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 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank -

e91 50 154 (E)mergency or abnormal in-plant > I / >I1 2 1 (EN)gineered safety feature - I - I ) 1 (control room system)

(L)ow-Power I Shutdown >

- I 1 ,I 121 (N)ew or (M)odified from bank including 1(A) -

> 2 1 )2 121 (P)revious 2 exams - 3 15 3 I 5 2 (randomly selected)

(R)CA -

> II 21 I 21 (S)imulator ES-301,Page 23 of 27

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

Safety System I JPM Title Type Code' Function

a. Manually Start the RClC System 2 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 P,EN,D,A.S 4 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 5 and Failure to Isolate 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 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

f. Respond to Multiple Rod Drifts and RPS Failure 7 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

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 7 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 6 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

@ 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 - / - I 2 1 (control room system)

(L)ow-Power / Shutdown -

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

> 2 / ,2 /,I (P)revious 2 exams -

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

> I / >I/ > 1 jS)imulator ES-301, Page 23 of 27

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

~~

Safety System I JPM Title Type Code' Function

a. Manually Start the RClC System D.S 2 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 9 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 N,EN,A,S 4 205000 Shutdown Cooling System (RHR Shutdown Cooling Mode)

A4. Ability to manually operate andlor monitor in the control room:

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)

j. Defeat ARI Logic Trips 7 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 6 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)

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

@ All RO and SRO-Icontrol room (and in-plant) systems must be different and sene differentsafety functions; all 5 SRO-U systems must sene 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 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)

(L)ow-Power I Shutdown - I / > I /,I (N)ew or (M)odified from bank including 1(A) -> 2 1 >2 121 (P)revious 2 exams - 3 I ( 3 I 5 2 (randomly selected)

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

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

L E

N 1 2 3 l 4 I T C CREW A T POSITION POSITION POSITION POSITION N Y T P E

0 0 1 0 RX 3

RO-I VOR 4 /c

RO-U 3 \nAJ

- rs-

~

RX

?! ~

NOR

?-I IC Yo-u ~

WAJ TS 1 0 RX 7 NOR Y-'

IRO-U

~

I/C

\rlAJ

- rs-

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$E- I Y RX VOR Y-I ~

I/C Y-" ~

WAJ TS lnstruc ins:

Check tne a licant level and enter the operating test number and Form ES-D-1 event numbers for each 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. I C.) malfunction can be credited toward the two (IC) malfunctions required for the ATC position.

2. 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.

3. 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 t f e right-hand columns.

ES-301, Page 26 of 27

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

-acility: Fermi-2 A

Date of Exam: 1/28/2008 Operating Test Number: 2008-1 P

P M L I I N C I A M N

T U M(')

RO ISI sI"0-l E

E0-I RO 0

EO-'

FU E

SRO-I 0

SRO-U 0

- 01212 lnstruc

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 f a n 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 r

Section 8.5 d) but must be significant per Section C.2.a of Appendix D ) Reactivity and norma evolutions may be replaced with additional instrument or component mal unctions on a 1-for-I basis 3 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 ES-301, Page 26 of 27

ES-301 Competencies Checklist Form ES-301-6 Date of Examination: 1/28/2008 Operating Test No.: 2008-1 ANTS I I I I I I (1) Includes Technical Specificationcompliance for an RO (2) Optional for an SRO-U.

(3) Only applicable to SROs.

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) Includes Technical Specificationcompliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

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

3. Generic Knowledge & Abilities I

Categories

- I I I I I I I I I I qote: 1. Ensure that at least two topics from every applicable W A 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).

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 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.

3. 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.

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 1 and 2 from the shaded systems and WA categories.

7.' The generic (G) WASin 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

8. 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 #Idoes not apply).

Use duplicate pages for RO and SRO-only exams.

9. l o r 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

8 I IIV T ' l S U l J 0 S S O l IVlOLiO IB!lred 610562 lN3WNOONVW L'iOOtl l O t l l N 0 3 PP 5 r oi Aidde Aaui se sasuodsai fiu1mo11or EP 0P ZP 8E IP ZE Ob ZE 6E ZE zx 9t ix it ox 7t hi XL 81 tP LL Lt

'JL 2t l-LOP-S3 WJOA tots3

ES-401 2 Form ES-401-1 Outline 1 Written Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1 Group 1 1 EAPE # IName Safety Function I K1 I K2 I K3 I A1 I A2 [ G I WA Topic@) I Imp. I Q#

recirculation AKI .01 - Knowledge of the operational 295023 Refueling Accidents I 8 implications of the following concepts as 3,6 48 they apply to REFUELiNG ACCIDENTS :

Radiation exposure hazards 2.1.27. Knowledge of system purpose 295024 High Drywell Pressure 1 5 3.9 49 andlor fundion.

EKI .04 - Knowledge of the operational 295025 High Reactor Pressure 13 IxI 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 3,6 50 295026 Suppression Pool High Water they apply to SUPPRESSION POOL 3.0 51 remp. 15 HIGH WATER TEMPERATURE : PUmD I I I NPSH I I I EK2 03 - Knowledge of the interrelations I 295031 Reactor Low Water Level 1 2 X II l l between REACTOR LOW WATER LEVEL and the following Low I I42 52 I I pressure core spray I I I EA1 01 - Abilitv to operate anolor monitor I 295028 High Drywell Temperature 15 X I I

I I I

the following as they apply to HIGH ORYWELL TEMPERATURE Drywell 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 graphs, curves, tables, etc.

2.1.32 - Conduct of Operations: Ability to explain and apply all system limits and I

I 3.9 I

precautions.

600000 Plant Fire On-site I 8 X 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 700000 Generator Voltage and Electric

rid Disturbances GRID DISTURBANCES

Voltage regulator controls.

CIA Category Totals: 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. 1w 1 295008 Iligli Reactor Water 1.cvcl I ?

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

ES-401 4 Form ES-401-1 Outline 1 Written Examination Outline Plant Systems -Tier 2 Group 1 K K K K K K A A A A G Imp. Q#

System # / Name 1 2 3 4 5 6 1 2 3 4 223002 I'C'ISINaclcar Srciini Supply Shurofl 215Ui13 lllM 203000 RHWLPCI. lnjeclion Mode 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 205000 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 206000 HPCl 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 209001 LPCS PRESSURE CORE SPRAY SYSTEM will have on following: Emergency generators K1.02 - Knowledge of the physical connections andlor cause- effect relationships between STANDBY 211000SLC LIQUID CONTROL SYSTEM and the following: Core plate differential pressure indication

ES-401 4 Form ES-401-1 Outline 1 Written Examination Outline Plant Systems - Tier 2 Group 1 K K K K K K A A A A G Imp.

System # I Name Q#

1 2 3 4 5 6 1 2 3 4 212000 RPS 215003 IRM procedures.

K2.01 - Knowledge of electrical power 215003 IRM X supplies to the following: IRM channelddetectors K4.01 -Knowledge of SOURCE RANGE MONITOR (SRM) SYSTEM 215004 Source Range Monitor 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 215005 APRM / LPRM 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 2 I7000 RClC system, and understand how operator actions and directives effect plant and 218000 ADS 223002 PCISlNuclear Steam

upply Shutoff 239002 SRVs 239002 SRVs monitoring A2 05 -Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM ,

259002 Reactor Water Level and (b) based on those predictions, use

.ontrol X Drocedures to correct control or mitigate the consequences ofthose abnormal conditions or operations:

loss or malfunction of the STANDBY GAS TREATMENT SYSTEM will have 261000 SGTS on following: High pressure coolant injection system: Plant-

ES-401 4 Form ES-401-1 Outline 1 Written Examination Outline Plant Systems Tier 2 Group 1 K K K K K K A A A A G System # / Name Imp. Q#

1 2 3 4 5 6 1 2 3 4 A2 11 -Ability 10 (a) pred.ct the mpacls of the follow4ngon the STANDBY GAS TREATMENT SYSTEM an0 (b) based on those predictions. bse proceaures 10 261000 SGTS 32 correct. control. or m t gate the consequences of tnose abnormal conditions or oDeratons H ah "

containment pressure -

K5 01 .Knowledge of tne operational 262001 AC Electrical Distribution Ill 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 associatedvvlth 31 203000 RHWLPCI Injection operating the RHWLPCI: INJECTION 39 MODE (PLANT SPECIFIC) controls including: Reactor pressure -

A4.01 -Ability to manually operate 263000 DC Electrical and/or monitor in the control room:

33 Distribution Major breakers and control power fuses: Plant-Specific -

2.4.35. Emergency Procedures 1 Plan:

263000 DC Electrical Knowledge of local auxiliary operator 38 Distribution tasks during emergency and the resultan1operat onal effects -

K4 06 - Knowleoge of EMERGENCY GENERATORS (OIESEUJET) design i i 264000 EDGs featurep) analor nterioc6s w n m 26 provide for the following: Govemoi control -

K4.03 -Knowledge of (INSTRUMENT AIR SYSTEM) design feature@)and or 300000 lnstmrnent Air interlocks which provide for the 28 following: Securing of IAS upon loss of

~

cooling water -

Ill A3.02 -Ability to monitor automatic 300000 Instrument Air operations of the INSTRUMENT AIR 29 SYSTEM including: Air temperature -

400000 Component Coaling K2.01 - Knowledge of electrical power 29 Water supplies to the following: CCW pumps 7

KIA Category Totals. Group Point Total: I 2615

sainieiaduai uaisAs I I aiesuapuo3 loiaeaa 0 0 0 9 s ~

SldN OOOPlZ KIM8 OOOPOZ s3m ZOOlOZ E

ES-401 5 Form ES-401-1 Outline 1 Written Examination Outline Plant Systems - Tier 2 Group 2 System # I Name 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 272000 Radialion Monitoring X 2.6 37 building ventilation monitors: Plant-Specific 2.2.40 Equipment Control: Ability to 288000 Plant Ventilation X apply technical specifications for a 3.4 38 system.

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: Outline 1 Date: I RO SRO-Only Category W A ?# Topic IR

~~~ Q# IR Q#

Ability to use procedures to determine the etrects on 1

2. I .43 reactivity of plant changes. such as KCS tenipcrature.

sccondary plant, h e 1 depletion, etc.

I.

onduct 2.1.41 Knowledge o f the refueling process. 2.8

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

Subtotal Knowledge o f t h e process for controlling equipment 1 4.3 I 95 I Ability to determine 'Technical Specification Mode of I Operation. I 4.5 I 96 I I 3quipment Knowledge of conditions and limitations in the hntrol 2.2.38 3.6 facility license.

2.2.13 Knowledge of tagging and clearance procedures. 4.1 2.2.40 Abiliw to a m l v technical specifications for a svstem. 3.4 I

Subtotal 2.3.5 fixed radiation monitors and alarms, portable survey 2.3.4 Knowledge o f Radiological Safety Procedures I. pertaining to licensed operator duties, such as cadiation response to radiation monitor alarms, containment 2.3.13 3.4 htrol entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc.

Knowledge of radiation monitoring systems, such as 2.3.15 fixed radiation monitors and alarms, portable survey 2.9 instruments, personnel monitoring equipment, etc.

iuhtotal

ES-401 Generic Knowledge and Abilities Outline (Tier3) Form ES-401-3 Knowledge of operational implications of EOI' 4.3 99 2.4.20 warninss, cautions, and notes.

Knowledge of the bases for prioritizing emergency 2.4.23 procedure implementation during cmergcncy 4.4 operations.

4. 1 Emergency Procedures I Knowledge of EOP entry conditions and immediate 4,6 73 2.4.'

Plan action steps.

2.4.27 Knowledge of "fire in the plant" procedures. 3.4 74 Knowledge of emergency communications systems 3,2 75 2'4'43 and techniques.

Subtotal 3 Tier 3 Point Total IO

ES-401 Record of Rejected W A S Form ES-401-4 Randomly Selected Tier I Group WA Reason for Rejection I

Fermi-2 is equipped with a Mark I Drywell I Torus. Mark 111 1 I1 295027 I EK2.03 Containment is NA. Kept same Statement number. Randomly reselected EPE 29503 1. (29503 1 EK2.03)

Fermi-2 RHR Head Spray is not used.

1 11 295021 / AK2.06 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 1 11 295028 I EA1.04 same EPE 295028. Randomly reselected statement EAI.01 (295028 EAI.01)

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

1 I1 295004 12.2.4 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 1 11 295024 I EA2.07 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 1 / I 600000 12.2.40 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 2 I1 215003 12.4.30 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 2 I1 262002 I AI .02 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 21 1 239002 I K5.06 same System 239002. Randomly reselected statement K5.04 (239002 K5.04)

Fermi-2 is not equipped with 'an Isolation Condcnscr. Kept 2 11 207000 I 2.1.23 same Statement number. Randomly reselected System 223002.

(223002 2.1.23)

Fermi-2 is not equipped with an lsolation Condenser. Kept 2 I1 207000 I A2.06 same Staterncnt number. Randomly rcselectcd Systcni 21 8000.

(218000 A2.06)

Fermi-2 MSIV-LCS is abandoned in place. Kept same 2 12 239003 I A1.07 statement number. Randomly reselected System 201 001.

(201001 A1.07)

Ih-mi-2 MSIV-I..CS is abandoned in place. 2.1.23 is 2 I2 239003 12.1.23 previously used on SRO System 223002. Randomly reselected

ES-401 Record of Rejected W A S Form ES-401-4 Randomly Selected Reason for Rejection WA Statement 2.4.23 is not specified in NUREG 1021 (SUPI) ES-21 9000 / 2.4.23 401 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 2.3.13 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 295024 12.1.27 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 295007 I AK1.02 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 295022 12.4.18 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 295036 I EK2.02 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 2.2.15 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.

295016 / 2.1.30 Randomly reselected statement 2.4.4. Kept same APE.

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

295030 / EA2.04 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 295012 / 2.2.39 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 22.3002 / 2.1.23 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.

262001 /2.1.19 Randomly reselected statement 2.4.8 Kept same System.

262001 2.4.8

ES-401 Record of Rejected W A S Form ES-401-4 Randomly Selected Tier I Group K/A Reason for Rejection Could not write an appropriate SRO 1,evel question regarding Priinary Containment and Auxiliaries -- ability to interpret and 21 1 223001 1 2.1.20 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 211 212000 A3.06 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 1/1 295024 12.2.22 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 111 295026 / EKl.02 HIGH WATER TEMPERATURE: Steam condensation.

3 2.2.43 Kandomly reselected statement 2.2.38.

Could not write an appropriate KO Lcvel question regarding 211 261000 I K3.06 Primary Containment Oxygen content. Randomly reselected 212 234000 / AI .02 212 201001 lA1.07 112 295008 lAA2.02 reselected statement AA2.05. Kent same APE. 295008