NRC-02-0091, Outline Submittal for the Fermi Initial Examination - March 2003

Outline Submittal for the Fermi Initial Examination - March 2003

ML030970397
Person / Time
Site:	Fermi
Issue date:	03/10/2003
From:	Bollinger S Detroit Edison
To:	Office of Nuclear Reactor Regulation
References
50-341/03-301, D-1, ES-201-2, ES-301-1, ES-301-2, ES-301-5, ES-301-6, ES-401-1, ES-401-2, NRC-02-0091 50-341/03-301
Download: ML030970397 (40)

Text

OUTLINE SUBMITTAL FOR THE FERMI INITIAL EXAMINATION - MARCH 2003

Outline Submittal (do not write in this package)

Contains the following:

Outline Submittal Letter ES-201-2 Examination Outline Quality Checklist ES-301-1 Administrative Topics Outline (RO)

ES-301-1 Administrative Topics Outline (SRO)

ES-301-2 Control Room and Facility Walk-Through Test Outline (RO/SRO(l))

ES-301-2 Control Room and Facility Walk-Through Test Outline (SRO(U))

ES-301-5 Transient and Event Checklist ES-301-6 Competencies Checklist D-1 Dynamic Simulator Scenario Outline for 2 scenarios ES-401-1 BWR SRO Examination Outline ES-401-2 BWR RO Examination Outline NO NRC COMMENTS TO THE FERMI OUTLINE SUBMITTAL.

William T. O'Connor, Jr.

Vice President, lNuclea r Generation Fermi 2 6400 North Dixie Hwyi., Newport, Mlichizgan 48160 Tel: 734-586-5201 Fax: 734-586-4172 DTE Energy December 10, 2002 NRC-02-0091 Mr. Dell McNeil U. S. Nuclear Regulatory Commission Region III 801 Warrenville Road Lisle, Illinois 60532-4351

Reference:

NRC Correspondence from Roger D. Lanksbury to William O'Connor, Jr., dated November 25, 2002

Subject:

Administration of Licensing Examinations The attached Examination Outline is provided per Reference in support of the licensing examinations at the Fermi 2 Nuclear Power Plant the weeks of March 10, 2003 and March 17, 2003.

The outline optimizes efficiency and the mix of Reactor Operator (RO) and Senior Reactor Operator (SRO) applicants.

Additionally, find attached Form ES-201-1, "Examination Outline Quality Assurance Checklist," with the facility portion completed.

To maintain examination security and integrity, the examination outlines shall be withheld from public disclosure until after the examinations are complete.

Should you have any questions regarding any aspect of the licensing examinations, please contact Steve Bollinger at (734) 586-4105, or Tim Barrett at (734) 586-4147.

Sincerely, W<t

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

refml

2.

Date of Examination:

3IiI2o00o3 Item Task Description a

b c#

1.

a. Verify that the outline(s) fit(s) the appropriate model per ES-401.

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b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled. '

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

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d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. S U f

2.

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

normal evolutions, instrument and component failures, and major transients.

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

mix of applicants in accordance with the expected crewbcomposition and rotation schedule without compromising exam integrity; ensure each applicant can be tested using at least one new or 4

significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s)*,

and scenarios will not be repeated over successive days.

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

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

3.

a. Verify that:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks, I

W (2) no more than 30% of the test material is repeated from the last NRC examination,

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(3)* no tasks are duplicated from the applicants' audit test(s), and ell T

(4) no more than 80% of any operating test is taken directly from the licensee's exam banks.

b. Verify that:

(1) the tasks are distributed among the safety function groupings as specified in ES-301 (2) one task is conducted in a low-power or shutdown condition, (3) 40% of the tasks require the applicant to implement an alternate path procedure, tell (4) one in-plant task tests the applicant's response to an emergency or abnormal condition, and (5) the in-plant walk-through requires the applicant to enter the RCA.

c. Verify that the required administrative topics are covered, with emphasis on performance-A based activities.

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d. Determine if there are enough different outlines to test the projected number and mix of

,4 applicants and ensure that no items are duplicated on successive days.

4.

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the g4D appropriate exam section.

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

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c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.

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d. Check for duplication and overlap among exam sections.

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e. Check the entire exam for balance of coverage.

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

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Printed m is' re bea 6 (jep Dat e2j la. Author gCaErd -ff

b. Facility Reviewer(*)

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c. NRCChiefExaminer(#)

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d. NRC Supervisor 4f/Ai Note:

Not applicable for NRC-developed examinations.

1. Independent NRC reviewer initial items in Column 'c;" chief examiner concurrence required.

23 of 24 NUREG-1021, Revision 8, Supplement 1

ES-301 Administrative Topics Outline Form ES-301-1 (R8, S1)

Facility:

Fermi 2 Date of Examination:

3/10/2003 Examination Level (circle one):

I SRO Operating Test Number:

2003-301 Administrative Describe method of evaluation:

Topic/Subject 1.' ONE Administrative JPM, OR Description

2. TWO Administrative Questions A.1 Obtain and verify a copy of a procedure Procedure Use JPM - K/A2.1.21 Ability to obtain and verify controlled procedure copy.

RO 3.1 SRO 3.2 Interpret Use a mechanical drawing to isolate a leak.

Drawings JPM - K/A 2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.

Ro 2.8 SRO 3.1 A.2 Surveillance Review a completed surveillance that has an error Test JPM - K/A 2.2.12, Knowledge of surveillance procedures RO 3.0 SRO 3.4 A.3 Calculate stay time and determine a dose extension is needed.

Radiation Work Permit JPM - K/A 2.3.4, Knowledge of radiation exposure limits and contamination control / including permissible levels in excess of those authorized.

RO 2.5 A.4 Emergency Perform actions as Emergency communicator during declaration Coin -

of a General Emergency munications JPM - K/A 2.4.43, Knowledge of emergency communications systems and techniques RO 2.8

ES-301 Administrative Topics Outline Form ES-301-1 (R8, S1)

Facility:

Fermi 2 Date of Examination:

3/10/2003 Examination Level (circle one): RO /I Operating Test Number:

2003-301 Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A.1 Obtain and verify a copy of a procedure Procedure Use JPM - K/A2.1.21 Ability to obtain and verify controlled procedure copy.

RO 3.1 SRO 3.2 Interpret Use a mechanical drawing to isolate a leak.

Drawings JPM - K/A 2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.

Ro 2.8 SRO 3.1 A.2 Surveillance Review a completed surveillance that has an error.

Test JPM - K/A 2.2.12, Knowledge of surveillance procedures RO 3.0 SRO 3.4 A.3 Determine dose limit will be exceeded and complete a dose Radiation Work extension.

Permit JPM - K/A 2.3.4, Knowledge of radiation exposure limits and contamination control / including permissible levels in excess of those authorized.

SRO 3.1 A.4 Emergency Determine Emergency Classification and PARS Action Levels JPM - K/A 2.4.41, Knowledge of the emergency action levels and PARS thresholds and classifications.

SRO 4.1

ES-301 Control Room Systems Form ES-301-2 (R8, Si) and Facility Walk-Through Test Outline Facility:

Fermi 2 Date of Examination:

3/10/2003 Exam Level (circle one):

FTQ4

/ SRO(U)

Operating Test No.:

2003-301 B.1 Control Room Systems System / JPM Title Type Code*

Safety Function

a.

Feeding Reactor vessel with SBFW during Reactor vessel Low Level 2

295031 - Reactor Low Water Level EAl. Ability to operate and/or monitor the following as they apply to M/AIS reactor low water level (CFR: 41.7 / 45.6): EA1.08 Alternate injection systems 3.8/3.9

b.

Open MSIVs following isolation 239001 - K2 - Knowledge of electrical power supplies to the following: OFR: 41.7) K2.01 - Main steam D/L/S 3

isolation valve solenoids 3.2/3.3, A4 - Ability to manually operate and/or monitor in the control room:qFR:

41.7 145.5 to 45.8), A3.01 - Isolation of main steam system

c.

Perform manual scram functional test 212000 Reactor Protection System - K4. Knowledge of REACTOR PROTECTION SYSTEM design feature(s) and/or interlocks which provide for the following PFR: 41.7): K4.05 - Functional testing of the system while maintaining power operation 3.4/3.q Al. Ability to predict and/or monitor changes in parameters associated with operating the REACTOR PROTECTION SYSTEM controls including (CFR: 41.5/ 45.5): Al.11 - System status lights and alarms 3.4/3.3; A2. Ability to (a) predict the impacts of N/S 4

the following on the REACTOR PROTECTIONSYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR: 41.5 /45.6): A2.03 - Surveillance testing 3.3/3.5, A2.19 - Partial system activation (half-SCRAM) 3.8/3.9; A4. Ability to manually operate and/or monitor in the control room OFR: 41.7/45.5 to 45.8): A4.02 -

Perform system functional test(s) 3.6/3.7, A4.07 -System status lights and alarms 4.0*/3.9*, A4.14 - Reset system following system activation 3.8/3.8

d.

Drywell vent IAW 29.ESP.07 5

EPE: 295024 High Drywell Pressure - EK3 - Knowledge of the reasons for the following responses as they apply to high drywell pressure (CFR: 41.5 / 45.6): EK3.07 Drywell venting 3.5/4.0 EAl - Ability to operate M/A/S and/or monitor the following as they apply to highdrywell pressure (CFR: 41.7/45.6): EAl.14 -Drywell ventilation system 3.4/3.5 EA2 - Ability to determine and/or interpret the following as they apply to high drywell pressure (CFR: 41.10 / 43.5 / 45.13): EA2.01 Drywell pressure4.2/4.4

e.

Start individual CTG1 1 Unit from Control Room 226001 A.C. Electrical Distribution K1 - Knowledge of the physical connections and/or cause effect relationships between A.C. electrical distribution and the following PFR: 41.2 to 41.9/45.7 to 45.8): K1.06 D/S 6

Altemate shutdown system 3.6/3.9, A4 - Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8): A4.05 Voltage, current, power, and frequency onA.C. buses 3.3/3.3

f.

Switch RBCCW pumps 400000 Component Cooling Water System (CCWS) K3 - Knowledge of the effect that a loss or malfunction D/S 8

of the CCWS will have on the following (OFR: 41.7145.6): K3.01, Loads cooled by CCWS 2.9/3.3

g.

CCHVAC shift with fan failure 290003 Control Room HVAC, K3 - Knowledge of the effect that a loss or malfunction of the control room HVAC will have on following (CFR: 41.7/45.6): K3.04 Control room pressure 2.8/2.9, A2 -Ability to (a) predict the impacts of the following on the CONTROL ROOM HVAC; and (b) based on those predictions, use M/A/S 9

procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR: 41.5 / 45.6): A2.03 Initiation/reconfiguration failure 3.4/3.6, A4 - Ability to manually operate and/or monitor in the control room (CFR: 41.7/45.5 to 45.8): A4.01 Initiate/reset system 3.2/3.2 B.2 Facility Walk-Through

a.

Switch CRD FCV 201001 Control Rod Drive Hydraulic System, Ki - Knowledge of the physical connections and/or cause effect relationships between control rod drive hydraulic system and the following ~FR: 41.2 to 41.9/45.7 to 45.8): K1.09, Plant air systems 3.1/3.2,A1 - Ability to predict and/or monitor changes in parameters associated with operating the control rod drive hydraulic SYSTEM controls including tFR: 41.5 / 45.5):

M/A/R 1

A1.09, CRD drive water flow. 2.9/2.8, A2 - Ability to (a) predict the impacts of the following on the control rod drive hydraulic system ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations OFR: 41.5 / 45.6): A2.07, Flow control valve failure3.2/3.1

b.

Defeat RPS trips per ESP EPE: 295037 - SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown, EK2

- Knowledge of the interrelations between scram condition present and reactor power aboveaprm downscale or unknown and the following (CFR: 41.7/ 45.8): EK2.01, RPS 4.2*/4.3*, EK3 - Knowledge of the reasons for the following responses as they apply to scram condition present and reactor power above D/L 7

aprm downscale or unknown (CFR: 41.5/ 45.6): EK3.07, Various altemate methods of control rod insertion 4.2/4.3*, EAl - Ability to operate and/or monitor the following as they apply to scram condition present and reactor power above aprm downscale or unknown (CFR: 41.7 / 45.6): EA1.01 Reactor Protection System 4.6*/4.6*

c.

Shutdown the diesel fire pump 286000 Fire Protection System - K4. Knowledge of fire protection system design feature(s) and/or interlocks which provide for the following (OFR: 41.7) (CFR: 41.5 / 45.3) (CFR: 41.7/ 45.7) (CFR: 41.5 / 45.5)

(CFR: 41.5 145.6) (CFR: 41.7145.7) (CFR: 41.7 / 45.5 to 45.8), K4.05 Fire protection capability during loss of off-N 8

site power 3.7/3.8 K5 - Knowledge of the operational implications of the following concepts as they apply to fire protection system (CFR: 41.5/45.3):, K5.05 Diesel operations 3.0/3.1, A4 - Ability to manually operate and/or monitor in the control room (FR: 41.7/45.5 to 45.8): A4.06 Fire diesel 3.4/3.4

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

ES-301 Control Room Systems Form ES-301-2 (R8, S1) and Facility Walk-Through Test Outline Facility:

Fermi 2 Date of Examination:

3/10/2003 Exam Level (circle one): RO / SRO(I) /I% i Operating Test No.:

2003-301 B.1 Control Room Systems System / JPM Title Type Code*

Safety Function

b.

Open MSIVs following isolation 239001 - K2 - Knowledge of electrical power supplies to the following: OFR: 41.7) K2.01 - Main steam D/L/S 3

isolation valve solenoids 3.2/3.3, A4 -Ability to manually operate and/or monitor in the control room:qFR:

41.7/45.5 to 45.8), A3.01 - Isolation of main steam system

g.

CCHVAC shift with fan failure 290003 Control Room HVAC, K3 - Knowledge of the effect that a loss or malfunction of the control room HVAC will have on following (CFR: 41.7 /45.6): K3.04 Control room pressure 2.8/2.9, A2 - Ability to (a) predict the impacts of the following on the control room HVAC; and (b) based on those predictions, use M/A/S 9

procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR: 41.5 / 45.6): A2.03 hitiation/reconfiguration failure 3.4/3.6, A4 - Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8): A4.01 Initiate/reset system 3.2/3.2 B.2 Facility Walk-Through

a.

Switch CRD FCV 201001 Control Rod Drive Hydraulic System, K1 - Knowledge of the physical connections and/or cause effect relationships between control rod drive hydraulic system and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): K1.09, Plant air systems 3.1/3.2A1 - Ability to predict and/or monitor changes in parameters associated with operating the control rod drive hydraulic system controls including (CFR: 41.5 / 45.5):

M/A/R 1

A1.09, CRD drive water flow. 2.9/2.8, A2 -Ability to (a) predict the impacts of the following on the control rod drive hydraulic system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR: 41.5 / 45.6): A2.07, Flow control valve failure 3.2/3.1

b.

Defeat RPS trips per ESP EPE: 295037 - SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown, EK2

- Knowledge of the interrelations between scram condition present and reactor power aboveprm downscale or unknown and the following (CFR: 41.7 / 45.8): EK2.01, RPS 4.2*/4.3*, EK3 - Knowledge of the reasons for the following responses as they apply to scram condition present and reactor power above D/L 7

aprm downscale or unknown (CFR: 41.5 / 45.6): EK3.07, Various alternate methods of control rod insertion 4.2/4.3*, EA1 - Ability to operate and/or monitor the following as they apply to scram condition present and reactor power aboveaprm downscale or unknown (CFR: 41.7 / 45.6): EA1.01 Reactor Protection System 4.6*/4.6*

c. Shutdown the diesel fire pump 286000 Fire Protection System - K4. Knowledge of fire protection system design feature(s) and/or interlocks which provide for the following (CFR: 41.7) (CFR: 41.5 / 45.3) (CFR: 41.7 / 45.7) (CFR: 41.5/

45.5) (CFR: 41.5 / 45.6) (CFR: 41.7 /45.7) (CFR: 41.7 145.5 to 45.8), K4.05 Fre protection capability N

8 during loss of off-site power 3.7/3.8 K5 - Knowledge of the operational implications of the following concepts as they apply to fire protection system (CFR: 41.5 / 45.3):, K5.05 Diesel operations 3.0/3.1, A4 -

Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8): A4.06 Fire diesel 3.4/3.4

• Type Codes: (D)irect from bank, (Mpodified from bank, (N)ew, (A)Iternate path, (C)ontrol room, (Spmulator, (L)ow-Power, (R)CA

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

ES-30 1 Transient and Event Checklist Form ES-301-5 (R8, Sl)

OPERATING TEST NO.: 2003-301 Todd Horton Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

Normal 1

RO Instrument /

4 Component Major 1

Reactivity 1

Normal 0

As RO Instrument /

2 Component Major 1

SRO-I Reactivity 0

Normal 1

As SRO Instrument /

2 Component Major 1

Reactivity 0

Normal 1

1(#1)

SRO-U Instrument 2

4 Component

(#2,3,5,7)

Major 1

1(#6)

Instructions:

Author:

NRC Reviewe (1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2)

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(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 requirement.

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NUREG-1021, Revision 8, Supplement 1

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Sl)

ES-3D 1 Transient and Event Checklist Form ES-301-5 (R8, Si)

OPERATING TEST NO.: 2003-301 Chuck Kharrl Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

Normal 1

RO Instrument /

4 Component Major 1

Reactivity 1

Normal 0

As RO Instrument!

2 Component Major 1

SRO-=

Reactivity 0

Normal 1

As SRO Instrument!

2 Component Major 1

Reactivity 0

Normal 1

1(#1)

SRO-U Instrument 2

4 Component

(#2,3,5,7)

Major 1

1(#6)

Instructions:

Author:

NRC Reviewe (1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2)

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(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 requirement.

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NUREG-1021, Revision 8, Supplement 1

ES-30 1 Transient and Event Checklist Form ES-301-5 (R8, Sl)

OPERATING TEST NO.: 2003-301 Joe Simone Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

Normal 1

RO Instrument 4

Component Major 1

Reactivity 1

Normal 0

As RO Instrument 2

Component Major 1

SRO-I Reactivity 0

Normal 1

As SRO Instrument 2 2 Component Major 1

Reactivity 0

Normal 1

1(#1)

_ =

=

SRO-U Instrument 2

4 Component

(#2,3,5,7)

Major 1

1(#6)

=

=

Instructions:

Author:

NRC Reviewei (1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2)

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(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 requirement.

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NUREG-1021, Revision 8, Supplement 1

ES-30 1 Transient and Event Checklist Form ES-301-5 (R8, Sl)

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

OPERATING TEST NO.: 2003-301 Jeff Yeager Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

Normal 1

RO Instrument 4

Component Major 1

Reactivity 1

1(#2)

Normal 0

As RO Instrument 2

2 Component

(#5,8)

Major 1

1(#6)

SRO-I Reactivity 0

Normal 1

1(#1)

As SRO Instrument /

24 Component

(#2,3,5,7)

Major 1

1 (#6)

Reactivity 0

Normal 1

SRO-U Instrument 2

Component Major 1

Instructions:

Author:

NRC Reviewe (1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2)

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(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 requirement.

or:

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I NUREG-1021, Revision 8, Supplement 1

ES-30 1 Transient and Event Checklist Form ES-301-5 (R8, S1 )

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

OPERATING TEST NO.: 2003-301 Jeff Clements Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

11 )

Normal 1

1(1 RO Instrument 4

2 2

Component

(#2,3)

(#4, 5)

Major 1

(#6) 1 (#6)

Reactivity 1

Normal 0

As RO Instrument /

2 Component Major 1

SRO-=

Reactivity 0

Normal 1

As SRO Instrument!

2 Component Major 1

l Reactivity 0

Normal 1

SRO-U Instrument I2 Component l

Major 1

Instructions:

Author:

NRC Reviewe (1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2)

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(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 requirement.

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NUREG-1021, Revision 8, Supplement 1

I ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

ES-30 1 Transient and Event Checklist Form ES-301-5 (R8, S1)

OPERATING TEST NO.: 2003-301 Andy Nighswander Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

1 (#1)

Normal 1

1 RO Instrument /

2 2

Component

(#2,3)

(#4, 5)

Major 1

1 (#6) 1 (#6)

Reactivity 1

Normal 0

As RO Instrument!

2 Component Major 1

SRO-=

Reactivity 0

Normal 1

As SRO Instrument 2

Component Major 1

Reactivity 0

Normal 1

SRO-U Instrument!

2 Component Major 1

Instructions:

Author:

NRC Reviewei (1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2)

Reactivity manipulations may be conducted under normal or controlled abnorma] conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(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 requirement.

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I NUREG-1021, Revision 8, Supplement 1

ES-301 Transient and Event Checklist Form ES-30 1-5 (R8, Sl1)

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

OPERATING TEST NO.: 2003-301 Craig Rice Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

1 (#2)

Normal 1

1 (#4)

RO Instrument 4

2 2

Component

(#5,7)

(#5,8)

Major 1

1 (#6) 1(#6)

Reactivity 1

Normal 0

=

=

As RO Instrument /

2 Component Major 1

SRO-I Reactivity 0

Normal 1

As SRO Instrument /

2 Component Major 1

l Reactivity 0

Normal 1

SRO-U Instrument!

2 Component Major 1

Instructions:

Author:

NRC Reviewe (1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2)

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(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 requirement.

Sr:

I NUREG-1021, Revision 8, Supplement 1

ES-30 1 Transient and Event Checklist Form ES-301-5 (R8, S1 )

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

OPERATING TEST NO.: 2003-301 Eric Sorg Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

1 (#2)

Normal 1

1 (#4)

RO Instrument

/

4 2

2 Component

(#5,7)

(#5,8 Major 1

1 (#6) 1 (#6)

Reactivity 1

Normal 0

As RO Instrument /2 Component Major 1

SRO-I Reactivity 0

Normal 1

As SRO Instrument I 2

Component Major 1

Reactivity 0

Normal 1

SRO-U Instrument!

2 Component Major 1

Instructions:

Author:

NRC Reviewei (1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2)

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(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 requirement.

r:

hl,'L(~L.)4-,,6 e?///

I I

/

NUREG-1021, Revision 8, Supplement 1

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

OPERATING TEST NO.: 2003-301 Brian Teifer Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

1 (#2)

Normal 1

1 (#4)

RO Instrument 4

2 2

Component

(#5,7)

(#5,8)

Major 1

(#6) 1 (#6)

Reactivity 1

Normal 0

As RO Instrument 2

Component Major 1

SRO-1 Reactivity 0

Normal 1

As SRO Instrument 2

Component Major 1

Reactivity 0

Normal 1

SRO-U Instrument I 2

Component Major 1

Instructions:

Author:

NRC Reviewei (1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2)

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(3)

Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant'scompetence count toward the minimum requirement.

I

-)-- - --

7 NUREG-1021, Revision 8, Supplement 1

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Sl)

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

OPERATING TEST NO.: 2003-301 Scott Bahnsen Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

Normal 1

RO Instrument /

4 Component Major 1

Reactivity 1

1 (#1)

Normal 0

As RO Instrument /

2 2

Component

(#2, 3)

Major 1

1 (#6)

SRO-I Reactivity 0

Normal 1

1(#2)

As SRO Instrument 2

2 Component

(#4, 5)

Major 1

1(#6)

=

Reactivity 0

Normal 1

SRO-U Instrument!

2 Component Major 1

Instructions:

(1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2)

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(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 requirement.

Author:

NRC Reviewer:

f Cci

/ k 4

/<iiY NUREG-1021, Revision 8, Supplement 1

ES-30 1 Transient and Event Checklist Form ES-301-5 (R8, Sl)

ES-301 Transient and Event Checklist Form ES-301-5 (R8, Si)

OPERATING TEST NO.: 2003-301 Mike Himebauch Applicant Evolution Minimum Scenario Number Type Type Number 1

2 3

4 Reactivity 1

Normal 1

RO Instrument!

4 Component Major 1

Reactivity 1

1 (#1)

Normal 0

As RO Instrument 2

2 Component

(#2, 3)

Major 1

1 (#6)

SRO-I Reactivity 0

Normal 1

1(#2)

As SRO Instrument /2 2

Component

(#4, 5)

Major 1

1(#6)

Reactivity 0

Normal 1

SRO-U Instrument!

2 Component Major 1

Instructions:

Author:

NRC Reviewei (1)

Enter the operating test number and Form ES-D-1 event numbers for each evolution type.

(2)

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.4.d) but must be significant per Section C.2.a of Appendix D.

(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 requirement.

r:

NUREG-1021, Revision 8, Supplement 1

ES-301 Competencies Checklist Form ES-301-6 (R8, Si)

Applicant #1 Applicant #2 Applicant #3 RO/SRO-I/SRO-U RO/SRO-I/SRO-U RO/SRO-I/SRO-U Horton Kharrl Simone Competencies SCENARIO SCENARIO SCENARIO 1

2 3

4 1

2 3

4 1

2 3

4 Understand and Interpret 25,6 53 5,6 Annunciators and Alarms 2,3 2,3 2,3 Diagnose Events 5,6 5,6 5,6 and Conditions Understand Plant 2,5 2,5 2,5 and System Response Comply With and 5,6 5,6 5,6 Use Procedures (1)

Operate Control N/A N/A N/A Boards (2)

Communicate and 1-7 1-7 1-7 Interact With the Crew 1-6 1-6 1-6 Demonstrate Supervisory Ability (3)

Comply With and 2,5 2,5 2,5 Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Circle 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.

Author:

NRC Reviewer:

ES-301 Competencies Checklist Form ES-301-6 (R8, Si)

Applicant #1 Applicant #2 Applicant #3 RO/SRO -I/SRO-U RO/SRO-I/SRO-U RO/SRO-I/SRO-U Bahnsen Himebauch Yeager Competencies SCENARIO SCENARIO SCENARIO 1

2 3

4 1

2 3

4 1

2 3

4 Understand and Interpret 523 3, 4 53,4 23 5, 64 Annunciators and Alarms 2,3 3, 4 2,3 3, 4 2,3 5, 6 Diagnose Events 5,

5, 6 5

5, 6 5,6 8

and Conditions Understand Plant 2,6 4, 5 2,5 4, 5 2,56 2, 4 and System Response 6

6 6

8 CmlWihad1, 2

3,4

1.

2 3,4 2,3 2, 5 Comply With and 3, 6 5,6 3, 6 5,6 5,6 6, 8 Use Procedures (1) 1, 2

N/A 1, 2 N/A N/A 2, 5 Operate Control 3, 6 3, 6 6, 8 Boards (2) 1, 2

1-8 1-7 1-8 1-7 1-6 Communicate and 3, 6 1

Interact With the Crew 8

Demonstrate Supervisory NA 1-6 NA 1-6 1-6 NA Ability (3)

Comply With and NA 4

NA 4

2,5 NA Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Circle 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.

Author:

1C tN S An

/

Ag a

NRC Reviewer:

ES-301 Competencies Checklist Form ES-301-6 (R8, S1)

Applicant #1 Applicant #2 Applicant #3 RO/S RO-l/SRO-U RO/S RO-I/SRO-U RO/S RO-l/SRO-U Clements Nighswander Rice Competencies SCENARIOO SCENARIO SCENARIO 1

2 3

4 1

2 3

4 1

2 3

4 Understand and Interpret 5263 l5,6 5,46 5,6 53,6 Annunciators and Alarms Diagnose Events 2,3 3,4l 2,3 3,4 5,6 5, 6 Digoe5 5, 6 5, 6 7

8 and Conditions 7

5 7

UnesadPat2,6 1, 4 2,5 1, 4 4,5 2, 4 Understand Plant 5, 6 6

5, 6 6

5, 6 and System Response 7

7 8

1, 2 1, 4 1, 2 1, 4 4, 5 2, 5 Comply With and 3, 6 5,6 3, 6 5,6 6

6, 8 Use Procedures (1)

Cnrl1, 2

1, 4 1, 2 1, 4 4, 5 2, 5 Operate Control 3, 6 5, 6 3, 6 5, 6 6

6, 8 Boards (2)

Cmuiaead1, 2

1, 3 1, 2 1, 3 2, 4 1-6 Communicate and 3, 6 4, 5 3, 6 4, 5 5, 6 8

Interact With the Crew 6

6 7

Demonstrate Supervisory NA NA NA NA NA NA Ability (3)

Comply With and NA NA NA NA NA NA Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Circle 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.

Author:

/2S$~

v NRC Reviewer:

1

ES-301 Competencies Checklist Form ES-301-6 (R8, Si)

Applicant #4 Applicant #5 Applicant RO/SRO-I/SRO-U RO/SRO-l/SRO-U

/SRO-l/SRO-U Sorg Teifer Competencies SCENARIO SCENARIO SCENARIO 1

2 3

4 1

2 3

4 1

2 3

4 5,6 3, 4 5,6 3, 4 Understand and Interpret 7

5, 6 7

5' 6 Annunciators and Alarms 5,6 5, 6 5,6 5, 6 Diagnose Events 7

8 7

8 and Conditions Understand Plant 465 24 465

526, and System Response 8

8 4, 5 2,5 4, 5 2, 5 Comply With and 6

6, 8 6

6, 8 Use Procedures (1)

Operate Control 54 2, 5 4,

2, 5 5 6 6, 8 5 6 6, 8 Boards (2) 2,4 2,4 1-6 Communicate and 5, 6 1-6 5, 6 8

Interact With the Crew 7

7 Demonstrate Supervisory NA NA NA NA Ability (3)

Comply With and NA NA NA NA Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions:

Circle 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.

Author:

K

/

NRC Reviewer:

Appendix D Scenario Outline Form ES-D-1 Facility:

Fermi 2 Scenari() No.

1 Op-Test No: 2003-301 Operators:

Examiners:

Initial Conditions: IC-14, MOL 65% Reactor Power NOTE: The Pre-job Briefing for 24.206.01 is to be conducted by the crew prior to entering the simulator. (suggested time 30 minutes prior to beginning the scenario)

Event Malf. No.

Event Event No.

Type*

Description 1

N/A R(RO)

Withdraw Control Rods to the target rod pattern.

N (SRO) 2 VO 1300 I(RO)

APRM Channel 1 Failure (130%)

3 MF 142 C(RO)

Control Rod 06-31 Uncoupled 4

N/A N(BOP)

Perform 24.206.01 section 5.1

1. 5 MF 3656 C(BOP)

Pressure Regulator Failure N001A( 100)

MF 3657 Pressure Regulator Failure NOO1 B(1100)

@ 6 MF 14 M

Main Steam Line C Rupture in the Drywell (3%)

7 VO 177 C

Div 1 (2) RHR DW Spray Otbd Iso Vlv, Fail as is at 0%

VO 178

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor The inservice pressure regulator will be failed upscale.

Simulator software support will be requested to provide a MSL B break inside the Drywell.

NUREG 1021, Rev.8, Supplement 1

Appendix D Scenario Outline Form ES-D-1 Facility: _

Examiners:

FERMI 2 Scenario No.

2 Operators: _

Op-Test No: 2003-301 Initial Conditions: IC-11, BOL 25%, Reactor Power Division 2 RPS supplied by Alternate Transformer and B CRD pump in service.

NOTE: The Pre-job Briefing for 23.107 Section 5.6 is to be conducted by the crew prior to entering the simulator. (suggested time 30 minutes prior to beginning the scenario)

Event No.

Malf. No.

Event Event Description T y pe

• 1 N/A N(BOP)

Transfer feedwater from the SULC valve to single element control 2

N/A R(RO)

Raise power with Control Rod withdrawal N(SRO) 3 MF 2469 All Seismic Event alarm 4

MF 1442 l(BOP)

RCIC spurious initiation 5

MF C(AII)

Trip of 65 E Bus 6

MF 0068 M(AII)

Recirc "B" Loop Rupture (5% break)

MF 2469 Seismic Event alarm 7

MF 1432 C(AII)

HPCI Turbine Exhaust Check Valve Failure E41-F049 8

MF 3595 I(RO)

Total Scram Failure RF 2315 Division 1 ARI Level 2 Isolation Defeat RF2316 Division 2 ARI Level 2 Isolation Defeat RF 2317 Division 1 ARI Pressure Isolation Defeat RF 2318 Division 2 ARI Pressure Isolation Defeat 9

VO 211 C

SULC Valve fail as-is (0%)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG 1021, Rev.8, Supplement 1

ES-40 1 BWR SRO Examination Outline Form ES-401-1 (R8. S1 )

ES-40 1 BWR SRO Examination Outline Form ES-401-1 (R8. S1

Facility:

Fermi 2 Date of Exam:

3/13/2003 Exam Level: SRO K/A Category Points Point Tier Group K jK K

K K

K A

A A

A Total 1

2 3

4 5

6 1

2 3

4 Gl 1.1 3

4 6 10E E

4 5

X 4

26 1.

Emergency &

2 4

2 6

2 Anormal Plant Evolutions Tier 1

1 2

2 3

1 1

2 4

3 2

2l 23

2.

2 2

0 1

1 1

0 0

1 1

4 2

13 Systems 3

1 0

0 0

0 1

0 0

1 0

1 4

Tier Totals 4

2 3

4 2

2 2

5 5

6 5

40 Cat 1 Cat 2 Cat 3 Cat 4

3. Generic Knowledge and Abilities 5

4 4

4 1 7 Note:

1.

Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A 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

+/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

3.

Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4.

Systems/evolutions within each group are identified on the associated outline.

5.

The shaded areas are not applicable to the category/tier.

6.*

The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

ER SRO Examination OutlineForm ES-401-1 (R8, Si)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function l K1 lK2 l K3 l Al l A2 G

K/A Topic(s) l Imp.

l Points 295003 Partial or Complete Loss of AC Pwr /6 04 Operational implications of electrical bus divisional separation.

3.2 1

295006 SCRAM /1 01 Knowledge of the interrelations between SCRAM and RPS 4.4 1

02 Determine / interpret control rod position 4.4 1

295007 High Reactor Pressure / 3 04 Knowledge of safety/relief valve operation:

4.1 1

295009 Low Reactor Water Level /2 02 Operate / monitor steam flow/feed flow mismatch 3.7 1

295010 High Drywell Pressure / 5 02 Knowledge of increased drywell cooling 3.4 1

06 Determine / interpret drywell temperature 3.6 1

295013 High Suppression Pool Temp. /5 02 Operate / monitor systems that add heat to the suppression pool 3.9 1

295014 Inadvertent Reactivity Addition / 1 03 Interrelations between Fuel temperature 3.4 1

02 Determine / interpret Reactor period 3.9 1

295015 Incomplete SCRAM / 1 02 Operational implications of cooldown effects on reactor power 4.1 1

01 Bypassing rod insertion blocks 3.7 1

295016 Control Room Abandonment / 7 01 Interrelations between Remote shutdown panel 4.5 1

X 2.4.16 Knowledge of EOP implementation hierarchy and coordination 4.0 1

with other support procedures.

295017 High Off-site Release Rate / 9 X

2.3.11 Ability to control radiation releases.

3.2 1

295023 Refueling Accidents Cooling Mode / 8 03 Inadvertent criticality 4.0 1

295024 High Drywell Pressure /5 20 Operate / monitor standby gas treatment/FRVS:

3.6 1

X 2.2.22 Knowledge of limiting conditions for operations and safety limits.

4.1 1

295025 High Reactor Pressure / 3 05 Knowledge of RCIC operation 3.7 1

02 Operate / monitor Reactor/turbine pressure regulating system 3.8 1

295026 Suppression Pool High Water Temp. / 5 05 Knowledge of Reactor SCRAM 4.1 1

295030 Low Suppression Pool Water Level / 5 X

2.2.25 Knowledge of bases in technical specifications for limiting 3.7 1

conditions for operations and safety limits.

295031 Reactor Low Water Level / 2 16 Interrelations between reactor water level control 4.1 1

295037 SCRAM Condition Present and Power 04 Operate / monitor SBLC 4.5 1

Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 02 Knowledge of System isolations 4.2 1

500000 High Containment Hydrogen Conc. / 5 01 Determine / interpret hydrogen monitoring system availability 3.5 1

K/A Category Totals:

3 4 16 I 4 J5 4

1 Group Point Total:

26

ES-401 oVVR SRO Examination OutlineForm ES-401-1 (R8, SI)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 2

[ E/APE # Name / Safety Function K1 K2 K3 Al A2

[G

[K/A Topic(s)

I Imp.

I Points 295001 Partial or Complete Loss of Forced Core 05 Operate / monitor recirculation flow control system 3.3 1

Flow Circulation / 1 & 4 295002 Loss of Main Condenser Vacuum / 3 04 Operational implications of increased offgas flow 3.3 1

295004 Partial or Total Loss of DC Pwr / 6 01 Operational implications of load shedding:

3.1 1

295005 Main Turbine Generator Trip / 3 01 Operational implications of Pressure effects on reactor power 4.1 1

295008 High Reactor Water Level / 2 01 Knowledge of the operational implications of moisture carryover 3.2 1

295012 High Drywell Temperature / 5 01 Interrelations between drywell ventilation 3.5 1

295018 Partial or Total Loss of CCW / 8 Not Randomly Selected 295019 Partial or Total Loss of Inst. Air / 8 02 Knowledge of standby air compressor operation 3.4 1

295020 Inadvertent Cont. Isolation / 5 & 7 04 Operational implications of bottom head thermal stratification 2.8 1

295021 Loss of Shutdown Cooling /4 X

2.1.2 Knowledge of operator responsibilities during all modes of plant 4.0 1

operation.

295022 Loss of CRD Pumps / 1 01 Knowledge of Reactor SCRAM 3.9 1

295028 High Drywell Temperature / 5 02 Know of reasons for the response as apply to RPV flooding 3.8 1

295029 High Suppression Pool Water Level /5 01 Interrelations between emergency depressurization 3.9 1

295032 High Secondary Containment Area Not Randomly Selected Temperature / 5 295033 High Secondary Containment Area 02 Interrelations between reactor SCRAM 3.6 1

Radiation Levels / 9 295034 Secondary Containment Ventilation High 03 Operate / monitor secondary containment ventilation 3.9 1

Radiation / 9 295035 Secondary Containment High Differential X

2.1.11 Knowledge of less than one hour technical specification action 3.8 1

Pressure / 5 statements for systems.

295036 Secondary Containment High Sump/Area 01 Interrelations between secondary containment equipment and floor drain 3.2 1

Water Level / 5 system 600000 Plant Fire On Site / 8 16 Determine / interpret vital equipment and control systems to be 3.5 1

maintained and operated during a fire K/A Category Point Totals:

4 2

1 6 1 2 1

1 2 1 Group Point Total:

[

17

ES-401 BV~r SRO Examination OutlineForm ES-401-1 (R8, Si)

Plant Systems - Tier 2/Group 1 System #/Name K1 K2 K3 K4 K5 IK6 AlA2 A3 A4 G

K/A Topic(s)

Imp Points 202002 Recirculation Flow Control 07 Predict and / or monitor changes in 3.1 1

recirculation loop flow 203000 RHR/LPCI: Injection Mode X

2.2.23 Ability to track limiting conditions for 3.8 1

operations.

206000 HPCI 05 Oper. implications of turbine speed control:

3.3 1

209001 LPCS 04 Knowledge of loss of D.C. power 2.9 1

211000 SLC 08 Knowledge of system initiation upon 4.2 1

operation of SBLC control switch 212000 RPS 04 Monitor auto operations of bypass SCRAM 3.9 1

instrument volume high level SCRAM signal 215004 Source Range Monitor 01 Knowledge of pwr to SRM chan./detectors 2.8 1

215005 APRM / LPRM 06 Predict impacts of recirc. flow chan. upscale 3.5 1

216000 Nuclear Boiler Instrumentation 14 Predict impacts of Recirculation flow:

2.9 1

217000 RCIC 02 Predict and / or monitor RCIC pressure 3.3 1

03 Monitor auto operations of System pressure 3.6 1

218000 ADS X

2.1.28 Knowledge of the purpose and 3.3 1

function of major system components and

___controls.

223001 Primary CTMT and Auxiliaries 17 Knowledge of phys. conn. and / or cause 3.1 1

effect relationship between RBHVAC:

223002 PCIS/Nuclear Steam Supply Shutoff 01 Predict impacts of A.C. elect dist. failures 3.5 1

03 Monitor auto ops of reset system isolations.

3.5 1

226001 RHR/LPCI: CTMT Spray Mode 02 Monitor auto operations of System pressure 2.8 1

239002 SRVs 01 Knowledge of loss of Reactor press. control 4.0 1

241000 Reactor/Turbine Pressure Regulator 19 Knowledge of steam bypass valve control 3.7 1

259002 Reactor Water Level Control 02 Knowledge of power to feedwater coolant 3.5 1

_injection (FWCI) initiation logic FWCI/HPCI 261000 SGTS 04 Knowledge of loss HPCI system:

3.1 1

262001 AC Electrical Distribution 03 Monitor auto operations of Load shedding 3.5 1

264000 EDGs 01 Knowledge of Emerg generator trips (normal) 3.7 1

290001 Secondary CTMT 04 Predict impacts of high airborne radiation 3.7 1

K/A Category Point Totals:

[1

[2 2

l 3

[ 1 [ 1 [ 2

[ 4 [ 3

[2

[2 [ Group PointTotal:

l 23

ES-401 BWR SRO Examination OutlineForm ES-401-1 (R8, SI)

Plant Systems - Tier 2/Group 2

(

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

K/A Topic(s)

Imp.

l oints 201001 CRD Hydraulic Not Randomly Selected 201002 RMCS Not Randomly Selected 201006 RWM X

2.1.11 Knowledge of less than one hour 3.8 1

technical specification action statements for

__systems.

202001 Recirculation 22 Predict impacts of loss of CCW 3.2 1

204000 RWCU 05 Knowledge of Double valve isolation from 3.1 1

reactor 205000 Shutdown Cooling Not Randomly Selected 214000 RPIS 01 Know. of effect of loss / malfunction of RWM:

3.2 1

215002 RBM 04 Knowledge of the phys. conn. and /or cause 3.1 1

effect relationship with recirculation system:

215003 IRM 04 Monitor auto ops of control rod block status 3.5 1

219000 RHR/LPCI: Torus/Pool Cooling Mode 06 Monitor auto ops of valve logic reset after 3.7 1

auto initiate of LPCI/RHR in inject mode 230000 RHR/LPCI: Torus/Pool Spray Mode Not Randomly Selected 234000 Fuel Handling Equipment X

2.1.28 Knowledge of purpose and function of 3.3 1

major system components and controls.

239003 MSIV Leakage Control Not Randomly Selected 245000 Main Turbine Gen. and Auxiliaries 08 Manually operate turbine oil pressure 2.7 1

259001 Reactor Feedwater 01 Manually operate or monitor system flow 3.5 1

262002 UPS (AC/DC)

Not Randomly Selected 263000 DC Electrical Distribution Not Randomly Selected 271000 Offgas Not Randomly Selected 272000 Radiation Monitoring Not Randomly Selected 286000 Fire Protection 05 Operational implications of diesel operations 3.1 1

290003 Control Room HVAC Not Randomly Selected 300000 Instrument Air 04 Knowledge of the phys. conn. and /or cause 2.9 1

effect relation cooling water to compressor 400000 Component Cooling Water 01 Man. Operate / monitor CCW indic. / control 3.0 1

K/A Category Point Totals:

2 0

1 1 l1 0

0 1

1 4

2 Group Point Total:

13

(a

(

(

ES-401 BWR SRO Examination OutlineForm ES-401-1 (R8, Si)

Plant Systems - Tier 2/Group 3 System # / Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G

I K/A Topic(s)

Imp.

Poits 201003 Control Rod and Drive Mechanism Not Randomly Selected 215001 Traversing In-core Probe 10 Phys. conn. or cause effect relation of 2.8 1

area radiation monitoring system:

233000 Fuel Pool Cooling and Cleanup Not Randomly Selected 239001 Main and Reheat Steam 10 Knowledge of effect of a loss / malf. of 3.7 1

ADS/low low set:

256000 Reactor Condensate X

2.1.30 Ability to locate and operate 3.4 1

components / including local controls.

268000 Radwaste Not Randomly Selected 288000 Plant Ventilation 01 Monitor auto opers of Isol. / init. signals 3.8 1

290002 Reactor Vessel Internals Not Randomly Selected K/A Category Point Totals:

1 0

0 0

0 1

0 0

1 0

1 Group Point Total:

4 Plant-Specific Priorities System /Topic Recommended Replacement for...

Reason Points 4

4 4

t

+

t 4

4 4

4

-I.

t i

4 4

I i ____________________

I _________________________

I ______

Plant-Specific Priority Total (limit 10):

I NUREG-1021, Revision 8, Supplement 1

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

Form ES-401-5 (R8, S1 )

Facility: Fermi 2 Date of Exam: 3/10/03 Exam Level: SRO Category K/A #

Topic Imp.

Points 2.1.3 Knowledge of shift turnover practices.

3.4 1

2.1.7 Ability to evaluate plant performance and make 4.4 1

operational judgments based on operating characteristics /

reactor behavior / and instrument interpretation.

Conduct of 2.1.10 Knowledge of conditions and limitations in the facility 3.9 1

Operations license.

2.1.22 Ability to determine Mode of Operation.

3.3 1

2.1.29 Knowledge of how to conduct and verify valve lineups.

3.3 1

Total 5

2.2.22 Knowledge of limiting conditions for operations and safety 4.1 1

limits.

2.2.13 Knowledge of tagging and clearance procedures.

3.8 1

2.2.29 Knowledge of SRO fuel handling responsibilities.

3.8 1

Equipment 2.2.30 Knowledge of RO duties in the control room during fuel 3.3 1

Control handling such as alarms from fuel handling area /

communication with fuel storage facility / systems operated from the control room in support of fueling operations / and supporting Total 4

2.3.1 Knowledge of 10 CFR: 20 and related facility radiation 3.0 1

control requirements.

2.3.2 Knowledge of facility ALARA program.

2.9 1

Radiation 2.3.4 Knowledge of radiation exposure limits and contamination 3.1 1

Control control / including 2.3.7 Knowledge of the process for preparing a radiation work 3.3 1

permit.

Total 4

2.4.2 Knowledge of system set points / interlocks and 4.1 1

automatic actions associated with EOP entry conditions.

Emergency 2.4.11 Knowledge of abnormal condition procedures.

3.6 1

Procedures/

2.4.16 Knowledge of EOP implementation hierarchy and 4.0 1

Plan coordination with other support procedures.

2.4.46 Ability to verify that the alarms are consistent with the 3.6 1

plant conditions.

Total II 4

Tier 3 Point Total (RO/SRO) l 17 NUREG-1021, Revision 8, Supplement 1

ES-40 1 BWR RO Examination Outline Form ES-401-2 (R8, Sl)

ES-40 1 BWR RO Examination Outline Form ES-401-2 (R8, Si)

Facility: Fermi 2 Date of Exam:

3/10/03 Exam Level:

RO K/A Category Points Point Tier Group K I K K

K K

K A

A I A l A Total 1 l2 l3 l4 l5 l6 l 1 l2 l 3 l4 lG' 1

X 1

4

<g2 l4 1

13 Emrgnc 2&

2-3 1

1 Emergency & 242811111 f1gg11 Abnormal Plant 3

1 1

0 0

l 2

4 Evolutions Tier vuosTotals 6

4 12 5 *-.: Xs5 4

36 1

2 3

3 3

1 2

3 3

3 3

2 28

2.

2 3

1 1

1 2

1 0

3 2

3 2

19 Sysntem 3

1 0

0 1

0 0

0 0

1 0

1 4

Tier Totals 6

4 4

5 3

3 3

6 6

6 5

51 Cat 1 Cat 2 Cat 3 Cat 4

3. Generic Knowledge and Abilities 3

4 13 3

3 3

4 1 13 !

Note:

1.

Ensure that at least two topics from every K/A category are sampled within each tier (i.e.,

the 'Tier Totals" in each K/A 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 +/-1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

3.

Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4.

Systems/evolutions within each group are identified on the associated outline.

5.

The shaded areas are not applicable to the category/tier.

6.*

The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities.

Enter the tier totals for each category in the table above.

0

,VVR RO Examination OutlineForm ES-401-2 (R8, SI)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G

K/A Topic(s) l Imp.

Points 295005 Main Turbine Generator Trip / 3 01 Operational implications of pressure effects on reactor power 4.0 1

295006 SCRAM / 1 02 Determine / interpret control rod position 4.4 1

295007 High Reactor Pressure / 3 04 Knowledge of safety/relief valve operation:

4.0 1

295009 Low Reactor Water Level / 2 02 Operate / monitor steam flow/feed flow mismatch 3.6 1

295010 High Drywell Pressure / 5 02 Knowledge of increased drywell cooling 3.0 1

295014 Inadvertent Reactivity Addition / 1 02 Determine / interpret Reactor period 3.9 1

295015 Incomplete SCRAM / 1 01 Bypassing rod insertion blocks 3.4 1

295024 High Drywell Pressure /5 X

2.2.22 Knowledge of limiting conditions for operations and safety limits.

3.4 1

295025 High Reactor Pressure /3 05 Knowledge of RCIC operation 3.6 1

02 Operate / monitor Reactor/turbine pressure regulating system 3.8 1

295031 Reactor Low Water Level / 2 16 Interrelations between reactor water level control 4.1 1

295037 SCRAM Condition Present and Power 04 Operate / monitor SBLC 4.5 1

Above APRM Downscale or Unknown / 1 500000 High Containment Hydrogen Conc. / 5 01 Determine / interpret hydrogen monitoring system availability 3.1 1

lK/A Category Totals:

1 1

4 2

4 1

Group Point Total:

=

13

lES-401 \\

VR RO Examination OutlineForm ES-401-2 (R8, Si)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # Name / Safety Function KlI K2 I K3 Al A2 G

K/A Topic(s)

Imp.

Points 295001 Partial or Complete Loss of Forced Core 05 Operate / monitor recirculation flow control system 3.3 1

Flow Circulation / 1 & 4 295002 Loss of Main Condenser Vacuum / 3 04 Operational implications of increased offgas flow 3.0 1

295003 Partial or Complete Loss of AC Pwr / 6 04 Operational implications of electrical bus divisional separation.

3.1 1

295004 Partial or Total Loss of DC Pwr / 6 01 Operational implications of load shedding:

2.6 1

295008 High Reactor Water Level /2 01 Knowledge of the operational implications of moisture carryover 3.0 1

295012 High Drywell Temperature / 5 01 Interrelations between drywell ventilation 3.4 1

295013 High Suppression Pool Temp. / 5 02 Operate / monitor systems that add heat to the suppression pool 3.9 1

295016 Control Room Abandonment / 7 01 Interrelations between Remote shutdown panel 4.4 1

295017 High Off-site Release Rate / 9 Not Randomly Selected 295018 Partial or Complete Loss of CCW / 8 Not Randomly Selected 295019 Partial or Total Loss of Inst. Air / 8 02 Knowledge of standby air compressor operation 3.5 1

295020 Inadvertent Cont. Isolation / 5 & 7 04 Operational implications of bottom head thermal stratification 2.5 1

295022 Loss of CRD Pumps / 1 01 Knowledge of Reactor SCRAM 3.7 1

295026 Suppression Pool High Water Temp. / 5 05 Knowledge of Reactor SCRAM 3.9 1

295028 High Drywell Temperature / 5 02 Know of reasons for the response as apply to RPV flooding 3.5 1

295029 High Suppression Pool Water Level /5 01 Interrelations between emergency depressurization 3.5 1

295030 Low Suppression Pool Water Level /5 X

2.2.25 Knowledge of bases in technical specifications for limiting 2.5 1

conditions for operations and safety limits.

295033 High Secondary Containment Area 02 Interrelations between reactor SCRAM 3.5 1

Radiation Levels / 9 295034 Secondary Containment Ventilation High 03 Operate / monitor secondary containment ventilation 4.0 1

Radiation / 9 295038 High Off-site Release Rate / 9 02 Knowledge of System isolations 4.2 1

600000 Plant Fire On Site / 8 16 Determine / interpret vital equipment and control systems to be 3.0 1

maintained and operated during a fire K/A Category Point Totals:

l 4 l 2 l 8 l 3 l 1 l 1 l Group Point Total:

[

19

(

(

ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, Si)

Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE # Name / Safety Function K1 K2 K3 A1 A2 G

K/A Topic(s)

[Imp. [ Points 295021 Loss of Shutdown Cooling /4 X

2.1.2 Knowledge of operator responsibilities during all modes of plant 3.0 1

operation.

295023 Refueling Accidents Cooling Mode /8 03 Inadvertent criticality 3.7 1

295032 High Secondary Containment Area Not Randomly Selected Temperature / 5 295035 Secondary Containment High Differential X

2.1.7 Ability to evaluate plant performance and make operational 37 1

Pressure / 5 judgments based on operating characteristics / reactor behavior / and instrument interpretation.

295036 Secondary Containment High Sump/Area 01 Interrelations between secondary containment equipment and floor drain 3.1 1

Water Level / 5 system K/A Category Point Totals:

1 l1 0

0 l0 2

lGroup Point Total:

[

4

ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, Si)

Plant Systems - Tier 2/Group 1 System # Name Kl K2 K3 K4 K5 K6 Al 1 A2 A3 A4 G

K/A Topic(s)

Imp.

Points 201001 CRD Hydraulic 05 Knowledge of a loss of A.C. power.

3.3 1

201002 RMCS 01 Predict / monitor changes in CRD drive flow 2.8 1

202002 Recirculation Flow Control 07 Predict / monitor changes in recirc. loop flow 3.1 1

203000 RHR/LPCI: Injection Mode 01 Knowledge of power supply to pumps 3.5 1

X 2.2.23 Ability to track LCO's.

2.6 1

206000 HPCI 05 Ops. implications of turbine speed control:

3.3 1

209001 LPCS 04 Know. of loss of D.C. power 2.8 1

211000 SLC 01 Phys. conn. / cause eff of CS line brk det 3.0 1

212000 RPS 04 Auto ops of byp SCRAM inst vol SCRAM sig.

3.9 1

05 Monitor auto ops of SCRAM inst vol. lvI 3.9 1

215003 IRM 04 Monitor auto ops of control rod block status 3.5 1

215004 Source Range Monitor 01 Know. of elect. pwr. Supp. to SRM chan/det 2.6 1

215005 APRM / LPRM 06 Predict impacts of recirc. flow chan. upscale 3.4 1

216000 Nuclear Boiler Instrumentation 12 Loss / malf. of react water IvI contl sys 3.7 1

14 Predict impacts of Recirculation flow:

2.9 1

217000 RCIC 02 Predict / monitor RCIC pressure 3.3 1

03 Monitor auto operations of System pressure 3.7 1

218000 ADS X

2.1.28 Know. of purp.& func. of comp.& cont.

3.2 1

223001 Primary CTMT and Auxiliaries 17 Phys. conn. / cause eff between RBHVAC:

3.1 1

223002 PCIS/Nuclear Steam Supply Shutoff 01 Predict impacts of A.C. elect. Dist. failures 3.2 1

03 Monitor auto ops of reset system isolations.

3.6 1

239002 SRVs 01 Know. of loss of Reactor pressure control 3.9 1

241000 Reactor/Turbine Pressure Regulator 19 Know. of steam bypass valve control 3.6 1

259001 Reactor Feedwater 05 Know. of RFP protection 2.7 1

01 Manually operate or monitor system flow 3.6 1

259002 Reactor Water Level Control 02 Elect. Pwr. Supp. to initiate logic FWCI/HPCI 3.5 1

261000 SGTS 04 Know. of loss HPCI system:

3.1 1

264000 EDGs 01 Know. of Emerg. Generator trips (normal) 3.5 1

K/A Category Point Totals:

2 3

3 3

1 12 3

I3 1 3 3

12 l Group Point Total:

l 28

(

(

(

ES-401 BWR RO Examination OutlineForm ES-401-2 (R8, Si)

Plant Systems - Tier 2/Group 2 System # / Name lKi K2 I K3 I K4 lK5 K6 Al A2 A3 A4 G

K/A Topic(s) l Imp. [ Points 201003 Control Rod and Drive Mechanism 02 Predict impact of uncoupled rod 3.7 1

201006 RWM X

2.1.32 Ability to explain and apply system 3.4 1

_limits and precautions.

202001 Recirculation 22 Predict impacts of loss of CCW 3.1 1

204000 RWCU 05 Know of dbl valve isolation from reactor 3.0 1

205000 Shutdown Cooling 02 Know of power to motor operated valves 2.5 1

214000 RPIS 01 Know of loss or malfunction of RWM:

3.0 1

215002 RBM 04 Know of physical connection and /or cause 3.1 1

effect relationship with recirculation system:

219000 RHR/LPCI: Torus/Pool Cooling Mode 06 Monitor auto ops of valve logic reset auto 3.9 1

initiation of LPCI/RHR in injection mode 226001 RHR/LPCI: CTMT Spray Mode 02 Monitor auto operations of System pressure 2.8 1

230000 RHR/LPCI: Torus/Pool Spray Mode Not randomly selected 239001 Main and Reheat Steam 10 Effect of loss / malf of ADS/low low set:

3.6 1

245000 Main Turbine Gen. and Auxiliaries 08 Manually operate turbine oil pressure 2.7 1

256000 Reactor Condensate X

2.1.30 Ability to locate and operate 3.9 1

components / including local controls.

262001 AC Electrical Distribution 03 Monitor auto operations of Load shedding 3.4 1

262002 UPS (AC/DC)

Not randomly selected 263000 DC Electrical Distribution 02 Know of phys conn / loss or malf. or cause 3.2 1

effect relation battery charger / battery 271000 Offgas Not randomly selected 272000 Radiation Monitoring Not randomly selected 286000 Fire Protection 05 Operational implications of diesel operations 3.0 1

290001 Secondary CTMT 04 Predict impacts of high airborne radiation 3.4 1

290003 Control Room HVAC 02 Ops impl of differential pressure control 2.8 1

300000 Instrument Air 04 Know of phys conn / cause effect relation 2.8 1

Cooling water to compressor 400000 Component Cooling Water 01 Man oper or monitor CCW indications and 3.1 1

1control K/A Category Point Totals:

3 l 1 T 1 l 1

] 2 1

l 0 3

l 2 l3 l2 Group Point Total:

l 19

ES-401 B... RO Examination OutlineForm ES-401-2 (R8, Si)

Plant Systems - Tier 2/Group 3 System #/Name lK1 K2TK3 K4 K5 K6 A1 A2 A3 A4l G

K/A Topic(s) lImp.

Points 215001 Traversing In-core Probe 10 Physical connection or cause effect 2.6 1

relationship of area radiation monitoring system:

233000 Fuel Pool Cooling and Cleanup Not Randomly Selected 234000 Fuel Handling Equipment X

2.1.28 Knowledge of the purpose and 3.2 1

function of major system components and controls.

239003 MSIV Leakage Control Not Randomly Selected 268000 Radwaste Not Randomly Selected 288000 Plant Ventilation 01 Monitor automatic operations of 3.8 1

Isolation/initiation signals 290002 Reactor Vessel Internals 03 Knowledge of core orificing 3.2 1

K/A Category Point Totals:

l1 0

0 l 1 l 0 0

0 10 1

0 1 1 l Group Point Total:

l 4

Plant-Specific Priorities System / Topic Recommended Replacement for...

l Reason

]

Points

+

4

_ __I

-r i

4

+

4 J

Iri

+

I I

l l4

+

I_

__I_

Iri l

4 l

Plant-Specific Priority Total: (limit 10)

NUREG-1021, Revision 8, Supplement 1

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

Form ES-40 1-5 (R8, S1 )

ES-40 1 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-5 (R8, Si)

Facility: Fermi 2 Date of Exam:

3/10/03 Exam Level: RO Category K/A #

Topic Imp.

Points 2.1.3 Knowledge of shift turnover practices.

3.4 1

Conduct of 2.1.22 Ability to determine Mode of Operation.

3.3 1

Operations 2.1.29 Knowledge of how to conduct and verify valve lineups.

3.3 1

Total 3

2.2.22 Knowledge of limiting conditions for operations and safety 4.1 1

I_

limits.

2.2.13 Knowledge of tagging and clearance procedures.

3.8 1

Equipment 2.2.30 Knowledge of RO duties in the control room during fuel 3.3 1

Control handling such as alarms from fuel handling area /

communication with fuel storage facility / systems operated from the control room in support of fueling operations I and supporting Total 3

2.3.1 Knowledge of 10 CFR: 20 and related facility radiation 3.0 1

control requirements.

Radiation 2.3.2 Knowledge of facility ALARA program.

2.9 1

Control 2.3.4 Knowledge of radiation exposure limits and contamination 3.1 1

control I including Total 3

2.4.2 Knowledge of system set points / interlocks and 4.1 1

automatic actions associated with EOP entry conditions.

Emergency 2.4.11 Knowledge of abnormal condition procedures.

3.6 1

Procedures!

2.4.16 Knowledge of EOP implementation hierarchy and 4.0 1

Plan coordination with other support procedures.

2.4.46 Ability to verify that the alarms are consistent with the 3.6 1

plant conditions.

Total 4

Tier 3 Point Total (ROISRO) l 13 j

NUREG-1021, Revision 8, Supplement 1