ML13319A890

2013 Fermi Power Plant Initial License Examination Outline Submittal

ML13319A890
Person / Time
Site:	Fermi
Issue date:	09/09/2013
From:	Moore C NRC/RGN-III/DRS/OLB
To:	Detroit Edison, Co
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Text

2013 FERMI POWER PLANT INITIAL LICENSE EXAMINATION OUTLINE SUBMITTAL

Fermi 2 6400 :'lorth Dixie Hwy Newport. l\11 48166

• 'DTEEnergy*

10 CFR 55.40 June 25, 2013*

NRC-13-0037 Mr. Hironori Peterson Chief, Operations Branch Division of Reactor Safety Region III .

U. S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, Illinois 60532-4352

Reference:

Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

Subject:

Fermi 2 Initial License Operator Examination Outline Enclosed please find the proposed examination outline for the upcoming Fermi 2 Initial License Examination that is scheduled for the week of September 9, 2013:

• Examination O~tline Quality Checklist (Form ES-201-2)

• Photocopies ofExamination Security Agreements (Form ES-201-3)

• RO Administrative Topics Outline (Form ES-301-1)

• SRO Administrative Topics Outline (Form ES-301-1)

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

• SRO Instant Control Room/In-Plant Systems Outline (Form ES-301-2)

• SRO Upgrade Control Room/In-Plant Systems Outline (Form ES-301-2)

• Transient ~nd Event Checklist (Form ES-301-5)

• Scenario Outlines (Form ES-D-1)

• RO BWR Examination Outline (Form ES-401-1)

• SRO BWR Examination Outline (Form ES-401-1)

• Generic Knowledge and Abilities Outline (K/As) (Form ES-401-3)

• Record of Rejected K/As (Form ES-401-4)

JUN 2::6 2013

USNRC NRC-13-0037.

Page2 The examination outline was developed using the appropriate guidance contained in NUREG-1021, Revision 9, Supplement 1. These materials shall be withheld from public disclosure ~til after the examinations are complete.

We look forward to working with you and your examination team during the examination development and administration process. If you have any questions or comments regarding the contents of the items listed above please contact Mr. David G. Coseo, General Supervisor, Operations Training at (734) 586-4055.

Sincerely, Zackary W. Rad Manager- Nuclear Licensing Enclosures cc: [w/o Enclosures]

NRC Project Manager Reactor Projects Chief, Branch 5, Region III NRC Resident Office Document Control Desk, Washington D C

USNRC NRC-13-0037 Page 3 bee: [w/o Enclosures]

M.S. C8fagher W. A. Colonnello J. T. Conner J. W. Davis J. K. Ford J. H. Plona Z. W.Rad K. C. Scott G. A. St:cobel Electronic Licensing Library (ELL) (200 TAC) [w/o Enclosures]

Information Management (140 NOC) [w/o Enclosures]

NSRG Administrator (210 NOC) [w/o Enclosures]

NRR Chron File [w/o Enclosures]

C. Aldri~ge-Nunn [w/o Enclosures]

T. J. Barrett [w/o Enclosures]

D. G. Coseo [w/o Enclosures]

R. J. Salmon [w/o Enclosures]

• ES-201 Facility:

Item Examination Outline Quality Checklist Date of Examination:

Task Description Form ES-201-2 Initials a b* c#

1.

w

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

~ 1-- ?lflt PR ~ ~

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

T T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. ~ t?r ~

E N d. Assess whether the justifications for deselected or rejected KJA statements are appropriate. aj ty a..t

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

~ t#f of normal evolutions, instrument and component failures, technical specifications, s

I and major transients. ~

M b. Assess whether there are enough scenario sets (and spares) to test the projected number u and mix of applicants in accordance with the expected crew composition and rotation schedule

~

L without compromising exam integrity, and ensure that each applicant can be tested using II.J'\

at least one new or significantly modified scenario, that no scenarios are duplicated A

T from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days. h' 0

~ ~ ~

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

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

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

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

T

12) task repetition from the last two NRC examinations is within the limits specified on the form

-(3) no tasks are duplicated from the applicants' audit test(s) 1)b l} ~

..--(4) the number of new or modified tasks meets or exceeds the minimums specified on the form

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

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

~~

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

"'(2) at least one task is new or significantly modified

..{3) no more than one task is repeated from the last two NRC licensing examinations i

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

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. 11 8- ~

E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. 'g) 11- C/11(

N E

c. Ensure that KJA importance ratings (except for plant-specific priorities) are at least 2.5. 1]1};_ ~ ~.

R d. Check for duplication and overlap among exam sections. )38 Jr ~

A L e. Check the entire exam for balance of coverage. 11> It' ~

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

~~ . arne/Signature Date

.~ -&; I.hARJ?t:: TT

~~

a. Author Timothy J. Barrett ...

b. Facility Reviewer(*) David G. Coseo ~

c. NRC Chief Examiner (#) Carl Moore ~-7~ .

d. NRC Supervisor Pw ~.t c;.,e.. fttltw i (5_..,-"'- I /l~f.A/

-FOr HP

• Note: # Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.

• Not applicable for NRC-prepared examination outlines

• ES-301 Facility: Fermi 2 Examination Level: RO 0 SRO Administrative Topics Outline D

Form ES-301-1 Date of Examination: 09/09/13 Operating Test Number: 2013-301 Administrative Topic Type Describe activity to be performed (see Note) Code*

Demonstrate the Operability of AC Sources per 24.000.01, Att. 28b.

S,D Conduct of Operations

[KIA 2.1.29] 802-4101-421 r2 Perform Torus Water Average Temperature Calculation R,M Conduct of Operations [KIA 295026 EA2.01] 802-3006-401 rO Using plant drawings, identify Isolation Boundaries for a Clearance to Replace a Pump Impeller.

S,R, Equipment Control D,P

[KIA 2.2.13] (NRC ILO 201 0) 802-4101-441 r1 N/A Radiation Control Request Emergency Offsite Services for the Control S,R,D Room per EP-290.

Emergency Procedures/Plan

[KIA 2.4.43] 831-0001-402r3 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

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

ES-301, Page 22 of 27

• ES-301 Facility: Fermi 2 Examination Level: ROD SRO Administrative Topics Outline 0

Form ES-301-1 Date of Examination: 09/09/13 Operating Test Number: 2013-301 Administrative Topic Type Describe activity to be performed (see Note) Code*

Perform a CRS Short-Term Relief per MOP07.

S,D Conduct of Operations [KIA 2.1.3] 802-4101-419r4 Perform Torus Water Average Temperature Calculation R,M Conduct of Operations [KIA 295026 EA2.01] 802-3006-401 rO Identify less than required AC Electrical Distribution Systems Operable, and perform remedial action.

S,R,D Equipment Control

[KIA 2.2.36] 802-4101-1 02r0 Calculate Stay Time and Determine if Extension is R,D Required Radiation Control

[KIA 2.3.4] 802-41 01-413r3 Activate ECOS per EP-290, Enclosure E.

S,R Emergency Procedures/Plan D,P [KIA 2.4.43] (NRC ILO 2010) 802-41 01-443r0 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

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

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

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

ES-301, Page 22 of 27

• ES-301 Facility: Fermi 2 Exam Level: RO 0 SR0-1 Control Room/In-Plant Systems Outline D SRO-U D Date of Examination:

Operating Test No.:

Form ES-301-2 09/09/13 2013-301 Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function Conduct Control Rod Coupling Integrity Test

a. [KIA 201003 A2.02] A,E,M,S SF-1 315-011 0-407r0 b Transfer Feedwater control from Long Cycle Cleanup to Startup Level Control

• [KIA 259001 A4.05] (NRC ILO 2010) 315-0107-002r1 D,L,P,S SF-2 Control Reactor Pressure from the Remote Shutdown Panel A,D,E,S SF-3 C. [KIA 295016 AA1.08] 802-2001-211 r5 d RCIC Recovery following Manual Trip

• [KIA 217000 A4.02] 315-0043-005r2 D,L,S SF-4 Manually Isolate HPCI System

e. [KIA 295032 EA 1.05] 315-0139-005r1 A,D,E,EN,S SF-5 Loss of 64C with EDG-12 Failure

f. [KIA 262001 A2.04] 315-0158-402r3 D,E,S SF-6 Control Rod Drift with RPS Failure

g. [KIA212000A2.16] 802-21 04-212r4 A,D,E,S SF-7 h Switch Off Gas Recombiner Chains

. [KIA 271000 A4.09] 315-0135-002r0 A,N,S SF-9 In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

Transfer UPS from Normal to Alternate Power Supply using Static Transfer Switch

i. [KIA 262002 A2.01] (NRC ILO 2010) 315-0262-003r1 A,D,P,R SF-6 Defeat RBCCW/EECW to Drywell Isolations

j. [KIA 295024 EA 1.07] 802-3006-321 r3 D,E,L,R SF-8 Startup Fuel Pool Ventilation Exhaust Radiation Monitor

k. [KIA 272000 A1.01] 315-0150-001 r3 D,R SF-9

@ All RO and SR0-1 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 SR0-11 SRO-U (A)Iternate path 4-6 I 4-6 12-3 (C)ontrol room (D)irect from bank ~91~81~4 (E)mergency or abnormal in-plant ~11~11~1 (EN)gineered safety feature - I - I ~1 (control room system)

(L)ow-Power I Shutdown ~11~11~1 (N)ew or {M)odified from bank including 1(A) ~21~21~1 (P)revious 2 exams ~ 31 ~ 31 ~ 2 (randomly selected)

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

• ES-301 Facility: Fermi 2 Exam Level: RO D SR0-1 Control Room/In-Plant Systems Outline 0 SRO-U D Date of Examination:

Operating Test No.:

Form ES-301-2 09/09/13 2013-301 Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function Conduct Control Rod Coupling Integrity Test

a. [KIA 201003 A2.02] A,E,M,S. SF-1 315-0110-407r0 b Transfer Feedwater control from Long Cycle Cleanup to Startup Level Control

• [KIA 259001 A4.05] (NRC ILO 2010) 315-0107-002r1 D,L,P,S SF-2 Control Reactor Pressure from the Remote Shutdown Panel C. [KIA295016AA1.08] A,D,E,S SF-3 802-2001-211 r5 d RCIC Recovery following Manual Trip

• [KIA 217000 A4.04] 315-0043-005r2 D,L,S SF-4 Manually Isolate HPCI System

e. [KIA 295032 EA 1.05] 315-0139-005r1 A,D,E,EN,S SF-5 Loss of 64C with EDG-12 Failure

f. [KIA 262001 A2.04] 315-0 158-402r3 D,E,S SF-6 N/A g.

Switch Off Gas Recombiner Chains

h. [KIA 271000 A4.09] 315-0135-002r0 A,N,S SF-9 In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

Transfer UPS from Normal to Alternate Power Supply using Static Transfer Switch

i. [KIA 262002 A2.01] (NRC ILO 2010) 315-0262-003r1 A,D,P,R SF-6 Defeat RBCCW/EECW to Drywell Isolations

j. [KIA 295024 EA1.07] 802-3006-321 r3 D,E,L,R SF-8 Startup Fuel Pool Ventilation Exhaust Radiation Monitor

k. [KIA 272000 A1.01] 315-0150-001 r3 D,R SF-9

@ All RO and SR0-1 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 SR0-11 SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank -;.91-;.81-;.4 (E)mergency or abnormal in-plant ~11~11~1 (EN)gineered safety feature - I - I ~1 (control room system)

(L)ow-Power I Shutdown ~11~11~1 (N)ew or (M)odified from bank including 1(A) ~21~21~1 (P)revious 2 exams -;. 3 I -;. 3 I -;. 2 (randomly selected)

(R)CA ~11~1h1 (S)imulator ES-301, Page 23 of 27

• ES-301 Facility: Fermi 2 Exam Level: ROD SR0-1 D Control Room/In-Plant Systems Outline SRO-U 0 Date of Examination:

Operating Test No.:

Form ES-301-2 09/09/13 2013-301 Control Room Systems@ (8 for RO); (7 for SR0-1); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function N/A a.

N/A b.

N/A c.

RCIC Recovery following Manual Trip

d. [KIA 217000 A4.02] 315-0043-005r2 D,L,S SF-4 Manually Isolate HPCI System

e. [KIA 295032 EA 1.05] 315-0139-005r1 A,D,E,EN,S SF-5 N/A f.

N/A g.

Switch Off Gas Recombiner Chains

h. [KIA 271000 A4.09] 315-0135-002r0 A,N,S SF-9 In-Plant Systems@ (3 for RO); (3 for SR0-1); (3 or 2 for SRO-U)

Transfer UPS from Normal to Alternate Power Supply using Static Transfer Switch

i. [KIA 262002 A2.01] (NRC ILO 2010) 315-0262-003r1 A,D,P,R SF-6 Defeat RBCCW/EECW to Drywell Isolations

j. [KIA 295024 EA1.07] 802-3006-321 r3 D,E,L,R SF-8 N/A k.

@ All RO and SR0-1 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 SR0-11 SRO-U (A)Iternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :s;9l:s;8l:s;4 (E)mergency or abnormal in-plant  :<:11:<:11:<:1 (EN)gineered safety feature - I - I :<: 1 (control room system)

(L)ow-Power I Shutdown  :<:11:<:11:<:1 (N)ew or (M)odified from bank including 1(A)  :<:21:<:21:<:1 (P)revious 2 exams :s; 3 I :s; 3 I :s; 2 (randomly selected)

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

• ES-301 Facility: Fermi-2 A

p p

L E

v E

N 1 Transient and Event Checklist 2

Date of Exam: 9/9/13 Scenarios 3 4 Form ES-301-5 Operating Test Number: 2013-1 T

0 M

I I T T N c CREW POSITION CREW POSITION CREW POSITION CREW POSITION A I A T L M N y T p s A 8 s A 8 s A 8 s A 8 u R T 0 R T 0 R T 0 R T 0 M(*)

E c c c 0 p 0 c p 0 p 0 p R I u RO RX 2 1 1 1 0

~

SR0-1 NOR 0 1 1 1 D 1/C 4,6,8,11 2,3,9 7 4 4 2 SRO-U D MAJ 7,9 4,6,8 5 2 2 1 TS 0 0 2 2 RO RX 0 1 1 0 D NOR SR0-1 7 1 1 1 1

~ 1/C 1,3,7,9 1,2,3,5,9 9 4 4 2 SRO-U D MAJ 5,6 4,6,8 5 2 2 1 TS 1,3 2 0 2 2 RO RX 0 1 1 0 D NOR SR0-1 3 4 7 3 1 1 1

~ 1/C 1,6,8,10 1,2,3,7,9 1,3,5 12 4 4 2 SRO-U D MAJ 7,9 5,6 4,6,8 7 2 2 1 TS 1,3 2 0 2 2 RO RX 2 1 1 1 0 D NOR SR0-1 3 4 2 1 1 1 D 1/C 1468 2,3,9 9 4 4 2 SRO-U 10,11

~ MAJ 7,9 5,6 4 2 2 1 TS 4,6 2 0 2 2 Instructions:

1. Check the afglicant level and enter the operating test number and Form ES-D-1 event numbers for each event tyFae; are not a'tftlicable for RO apfclicants. ROs must serve in both the "at-the-controls (ATC)"

and "ba ance-of-flant (B P)" positions. Ins ant SROs must serve in both the SRO and ATC positions, including at leas two instrument or component (1/C) malfunctions and one major transient, in the ATC rcosition. If an instant SRO additionally serves in the BOP ~osition, one (1/C) malfunction can be credited oward the two (IC) malfunctions requ1red for the ATC posi ion.

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

Section .5.d) but must be significant per Section C.2.a of Appendix D. p Reactivity and normal evolutions may be replaced w1th additional instrument or component mal unctions on a 1-for-1 basis.

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

• ES-301, Page 26 of 27

• ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: Fermi 2 Date of Exam: 9/9/2013 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G" Total 1 2 3 4 5 6 1 2 3 4 "

1. 1 3 4 3 3 3 4 20 3 4 7 Emergency &

Abnormal 2 1 1 1 N/A 2 1 N/A 1 7 1 2 3 Plant Evolutions Tier Totals 4 5 4 5 4 5 27 4 6 10 1 2 2 2 3 3 2 3 3 2 2 2 26 3 2 5 2.

Plant 2 1 1 2 1 1 1 1 1 1 1 1 12 0 2 1 3 Systems Tier Totals 3 3 4 4 4 3 4 4 3 3 3 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 2 3 3 2 2 2 1 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals" in each KIA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

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

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those KIAs 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 KIA categories.

7.* The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KIAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

ES-40 1, Page 17 of 34

ES-401 2 Form ES-401-1

• EIAPE #I Name I Safety Function 1 Partial or Complete Loss of Forced K K 2

K 3

BWR Examination Outline Emergency and Abnormal Plant Evolutions- Tier 1/Group 1 (RO)

A KIA Topic(s) to interpret reference materials, such as graphs, curves, Form ES-401-IR 3.9 Flow Circulation /1 & 4 etc.

0 Partial or Complete Loss of AC /6 of battery discharge rate on capacity 2.7 1

0 Partial or Total Loss of DC Pwr /6 3.1 1

0 Main Turbine Generator Trip /3 3.2 4

0 4.1 7

Control Room Abandonment /7 4.1 Knowledge of the purpose and function of major system 8 Partial or Total Loss of CCW /8 and controls.

4.1 0

9 Partial or Total Loss of lnst. Air /8 2.8 8

0 1 Loss of Shutdown Cooling I 4 Feeding and bleeding reactor vessel 3.3 2

• Refueling Ace I 8 High Drywell Pressure I 5 High Reactor Pressure /3 0

3 pool level without reference to procedures those actions immediate operation of system components and 3.3 3.8 4.6 Suppression Pool High Water 0 3.0

/5 1 High Containment Temperature I 5 0 0

High Drywell Temperature I 5 3.6 4

0 Low Suppression Pool Wtr Lvl/ 5 3.4 2

Reactor Low Water Level/ 2 4.6 SCRAM Condition Present and Knowledge of annunciator alarms, indications, or response Power Above APRM Downscale or procedures.

4.2

/1 0

High Off-site Release Rate /9 Protection of the general public 4.2 2

0 Plant Fire On Site I 8 2.6 1

• Generator Voltage and Electric Grid

/6 3

2 4

0 3 3 3.1 20

ES-401 Form ES-401-1 3

BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions- Tier 11Group 2 (RO) lr-------------------------~~K~~~~-A~ ~~----------~~~~--------~~--~--~~

KIA Topic(s) IR #

1 0

Loss of Main Condenser Vac 13 3.6 3

High Reactor Pressure I 3 0 3.5 0

Low Reactor Water Levell2 3.1 3

of the operational implications of EOP warnings.

0 High Drywell Pressure I 5 notes.

3.8 11 High Containment Temp I 5 0 12 High Drywell Temperature /5 0 3 High Suppression Pool Temp. /5 0 0

Inadvertent Reactivity Addition 11 3.7 2

• Incomplete SCRAM /1 7 High Off-site Release Rate I 9 Inadvertent Cont. Isolation /5 & 7 0

0 0

Loss of CRD Pumps /1 0 High Suppression Pool Wtr Lvl/ 5 0 High Secondary Containment Area 0

re 15 High Secondary Containment Area 3.8 Levels 19 0

Secondary Containment High 3.8 IIDiifferen,ti::~l Pressure I 5 Secondary Containment High 0

Water Level/ 5 0

• Category Totals: Group Point Total:

ES-401, Page 19 of 34 7

ES-401 4 Form ES-401-1

• IES-401 lr-----------------------r-~~.-,--r-.~~~--

System # I Name 203000 RHRILPCI: Injection Mode

'\ '\ '\ '\

~E~- ~

BWR Examination Outline Plant Systems - Tier 2/Group 1 (RO)

---~~--~---------------,----.---~1 cooling methods KIA Topic(s)

Form ES-401-IR 3.5 1

205000 Shutdown Cooling Cornoo11ent cooling water systems 3.2 1 206000 HPCI High drywall pressure: BWR-2, 3, 4 4.0 1 J

It-~-*~,**.~~....-----~.-

_ ..~, ,!_s.,o._la-tio_.n_J_.~m_.e...;.rg_e_ncy_....;.)_...*,._?'*::_'<-+ '-+"-+I;-+,;:li-+.-+--+:1-+l;..r...**.,~--~---** ***f*ii:!, . ., . o,i :io . ,.. ... !ij,:.:i*

1209001 LPCS ~ ~~ I ~Pump power; Reactor pressure 3; 3.7 2

[:~'::,' Specfficisolation ; Explosive valves indicating lights: Plant- 3.8; 1211000 SLC 2 3.8 0 3.3; 1212000 RPS Specific logic arrangements ; Reactor power 2 2 4.3 1215003 IRM i to interpret and execute procedure steps. 4.6 1 Reactor protection system 3.6 1 2.6; channels; Core now effects on APRM trip setpoints 2 3.6 Reactor water level 3.7 1 logic control 3.8 1 1vv,,gi,,, ,, instrumentation; Valve closures 3; 3.7 2

's::lllndiicatE!d vs. actual steam flow: Plant-Specific 3.1 1 of controller signal output 3.3 1 Valve operation 3.0 1

)

: All breakers and disconnects (including available switcl1 3.4 1 t£z vard): Plant-Specific l'> il to determine operability and/or availability of safety 3.6 1 ruwrli~i'l*f,.r*ellated equipment ri;

f A.C. electrical distribution 3.3 1 4.1 1 to other air systems 3.0 1 HigMow CCW temperature 2.9 1

• KIA Category Totals: 2223323~2 ES-401, Page 20 of 34 Group Point Total:

0 26

ES-401-1 5 Form ES-401-1

• IES-401

!System #l Name

'201001 CRD Hydraulic 201002 RMCS

' ' ' K K BWR Examination Outline

~

I Plant Systems - Tier 2/~()lp 2 (ROl

<<" ~' 0 KIATop;o(o)

Form ES-401-1 IR #

0 0

201003 Control Rod and Drive Mechanism  ; ~ ,~j IControl rod position 3.7 1 201004 RSCS  ?~$ 0 201005 RCIS

0

~01006 RWM

~02001 Recirculation 1202002 Recirculation Flow Control

~

~

~~

--1

~-

ii+~;,

• <;; manual control system

  P-Spec(Not-BWR6) cooling: Plant-Specific 3.2 2.7 0

1 1

1204000 RWCU 1214000 RPIS

~

~~

1iiJc

• ~"ri- Valve closures 2.7 3.0 1

1 1215001 Traversing In-core Probe

~;: 0 1215002 RBM 0 216000 Nuclear Boiler lnst.

~ Recorders 3.3 1

~~9d0e00 RHR/LPCI: Torus/Pool Cooling 0

223001 Primary CTMT and Aux. 'flJ 0

• 226001 RHRILPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup

~s;~

!i

!!tl! ,.~J; l2ll ~{~~

=

Knowledge of system purpose and/or function . 3.9 1 0

0 1!{ ;1JR~ It: .. ',, 1- ~}-

F __,

/~

234000 Fuel Handling Equipment 0 1239001 Main and Reheat Steam 1239003 MSIV Leakage Control

~ If 3.7 1 0

==

~' 1:1

~41 000 Reactor/Turbine Pressure ""llu'""v' 0

~

~* * !r 1245000 Main Turbine Gen. I Aux. *YHQ,~I  : Plant-Specific 2.7 1 1256000 Reactor Condensate ~1;] 0 1259001 Reactor Feedwater

! '~

0 1268000 Radwaste s 0 1271 000 Offgas

~ l:i Hydrogen gas concentration 3.2 1 1272000 Radiation Monitoring ]\ 0 286000 Fire Protection

~ o:;;i~ ~il:i Pumps 2.9 1 288000 Plant Ventilation

~ ~~ 0 t- *-

290001 Secondary CTMT 0 r-290003 Control Room HVAC 0

• ~

290002 Reactor Vessel Internals Recirculation system 3.1 1

~-,f~  ;~~l 0 KIA Category Totals: 1 1 2 1 1 1 1 r* 1 1 [~; Group Point Total: 12 ES-401, Page 22 of 34

ES-401 2 Form ES-401-1

• EIAPE #I Name I Safety Function 1 Partial or Complete Loss of Forced Flow Circulation 11 & 4 K K 2

K 3

BWR Examination Outline Emergency and Abnormal Plant Evolutions- Tier 11Group 1 (SRO)

A KIA Topic(s)

Form ES-401 IR #

0 Partial or Complete Loss of AC 16 Cause of partial or complete loss of A. C. power 3.7 to recognize system parameters that are entry-Partial or Total Loss of DC Pwr 16 4.6 for Technical Specifications.

Main Turbine Generator Trip 13 2.7 0

Control Room Abandonment 17 0 Knowledge of the bases in Technical Specifications for 8 Partial or Total Loss of CCW 18 4.2 conditions for operations and safety limits.

9 Partial or Total Loss of lnst. Air 18 0 1 Loss of Shutdown Cooling I 4 0

• Refueling Ace I 8 High Drywell Pressure I 5 High Reactor Pressure 13 to perform specific system and integrated plant during all modes of plant operation.

4.4 0

0 Suppression Pool High Water Suppression pool water temperature 4.2 15 High Containment Temperature 15 0 High Drywell Temperature 15 0 Low Suppression Pool Wtr Lvl/ 5 0 Knowledge of abnormal condition procedures. 4.2 0

0 Plant Fire On Site I 8 0

• Generator Voltage and Electric Grid 16 0 0 0 0 0

7

ES-401 3 Form ES-401-1

• 1 ~----------------------------------------T~K~~~-K-r-A-112!~5(102 EIAPE #I Name I Safety Function Loss of Main Condenser Vac I 3 1 3 BWR Examination Outline Emergency and Abnormal Plant Evolutions- Tier 11Group 2 (SRO) 1

~------------------~~---~---------------~----r---~ 1 KIA Topic{s)

Form ES-401 IR #

0 High Reactor Pressure I 3 0 0

0 0 High Drywell Pressure I 5 0 11 High Containment Temp 15 0 High Drywell Temperature 15 0 3 High Suppression Pool Temp. 15 Knowledge of the specific bases for EOPs. 4.0 14 Inadvertent Reactivity Addition 11 0

• Incomplete SCRAM 11 High Off-site Release Rate I 9 4.3 0

0 Loss of CRD Pumps 11 0 0

II2!~5Cl32 High Secondary Containment Area 0

15 u..::~oli.J.J High Secondary Containment Area 0

IIR;adi;aticm Levels 19 plant performance and make operational on operating characteristics, reactor behavior, 4.7 interpretation.

0 0

0

• Category Totals: 0 0 0 ES-401, Page 19 of 34 3

ES-401 4 Form ES-401-1

,ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 1 (SRO)

'J~

System # I Name ~ '\ :" :" <~ ! ~ E KIA Topic(s) IR #

203000 RHRILPCI: Injection 0 205000 Shutdown Cooling Mode 0

~j r.

uouuu HPCI r:tr 0 r-1207000 Isolation (Emergency)

I~

1'-'"""'w""w' I 0

=

1209001 LPCS 0 HPCS i~ 0 1211000 SLC

~i~' 0 i-

!212000 RPS 0 I2150031RM 0

~~~

Knowledge of less than or equal to one hour Technical 215004 Source Range Monitor Specification action statements for systems.

4.5 1 215005 APRM I LPRM .:;

t 0

• 217000 RCIC 218000ADS 223002 PCISINuclear Steam Supply Shutoff

~;jJ Loss of lube oil Ability to explain and apply system limits and precautions.

3.1 4.0 1

1 0

r-239002 SRVs SRV 3.2 1

• ~* '" Reactor Water Level Control 0 1261000 SGTS

~ air system failure 2.6 1 1262001 AC Electrical Distribution ~~;: 0

'*t;~

l?,:;?nn? UPS (ACIDC)

'+) 0 DC Electrical Distribution 0 l?,:;<~.nnn EDGs

~~ 0 1-Instrument Air 0 l<~.nnnnn Component Cooling Water 0

• IKJA Category Totals: 0 0 0 0 0

~

! =

0 ES-401, Page 20 of 34 Group Point Total:

0 5

ES-401 5 Form ES-401-1 IES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)

!System # I Name

~01001 CRD Hydraulic

~01002 RMCS

~ ~ ~ ~

1\ e~

~~

':,'~\

~ rs;

~

t-2;:

KIA Topic(s) IR #

0 0

1201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS

• ~-i ;jj 0 0

0 201006 RWM 0 202001 Recirculation 202002 Recirculation Flow Control

! lc, pump speed mismatch between loops: Plant-3.2 0

1

~04000 RWCU

,*,; 0 1214000 RPIS ~;j~ {:;'* 0

~15001 Traversing In-core Probe

.J1 *))~ 0

~15002 RBM

~ l~~ 0

~16000 Nuclear Boiler Ins!.

1219000 RHRILPCI: Torus/Pool Cooling 1M ode i 0 0

223001 Primary CTMT and Aux. tJ 0 226001 RHR/LPCI: CTMT Spray Mode  ;'\2) ~. 0 230000 RHR/LPCI: Torus/Pool Spray Mode

~  ;~~1 0 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment 239001 Main and Reheat Steam

• ** I I ~*t *

~e:f!;

p;::

~

0 0

0 239003 MSIV Leakage Control ~~5;: ~ 0

~41000 Reactor/Turbine Pressure Regulator 1,;~ 0

[A'~*:I 1245000 Main Turbine Gen. I Aux. 0

~56000 Reactor Condensate r*;w Low hotwell level 3.2 1 1259001 Reactor Feedwater  !} =i~~~ _,._

• <v v~"' y u *~ o<a<uo 4.4 1 1268000 Radwaste

<:t fil f**

0 1271000 Offgas 0 I,*

~72000 Radiation Monitoring bt; 0

~86000 Fire Protection

~ c: 0 1288000 Plant Ventilation 0 290001 Secondary CTMT (!(;j II 0 290003 Control Room HVAC .*:!; 0

• 1290002 Reactor Vessellntemals IE Totals: 0 0 0 0 0 0 0 c:,

0 ES-401, Page 21 of 34 o~Group 0

0 3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:Fermi 2 Date of Exam:9/9/2013 KU ~KU-Unly Category KIA# Topic IB_ # lH #

Knowledge of criteria or conditions that require plant-wide announcements, such as pump 2.1 14 starts, reactor trips, mode changes, etc.

3.1 1 2.1 19 Ability to use plant computers to evaluate system or component status. 3.9 1

1. 2.1 39 Knowledge of conservative decision making practices. 4.3 1 Conduct of 2.1 05 lAbility use procedures related to shift staffing, such as minimum crew complement, 3.9 1

!overtime limitations, etc.

0(.Jt:r citiun::s I Subtotal 2 2.2 14 Knowledge of the process for controlling equipment configuration or status. 3.9 1 2.2 06 *~ ovmvv"v of the process for making changes to procedures. 3.0 1 2.2 20 ""' of the process for managing troubleshooting activities. 4.5 1 12.

Equipment 3.8 1 2.2 38 I -o* of conditions and limitations in the facility license.

!Control

• Subtotal 2.3 11 2.3 05 Ability to control radiation releases.

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

3.8 2.9 1

1 2

Ability to comply with radiation work permit requirements during normal or abnormal

3. 2.3 07 conditions. 3.5 1 R;

2.3 04 ..l:ll. of radiation exposure limits under normal or emergency conditions. 3.7 1 Control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, 2.3 14 or emergency conditions or activities.

3.8 1

!Subtotal 2 IKnOWie<lge Of cUP ""~'v'"C'"auvol nlerarcny ana NOV"oauvol Wltn otner support 2.4 16 I procedures i abnormal operating procedures, 3.5 1 land severe accident

• ouidelines.

2.4 25 Knowledge of fire protection procedures. 3.3 1

4. 2.4 14 Knowledge of general guidelines for EOP usage. 3.8 1 Emergency Procedures 2.4 44 Knowledge of emergency plan protective action recommendations. 4.4 1

'Plan

• • [ier ~nt TQ§I_

!Subtotal ES-401, Page 27 of 34 1

7

Appendix D Scenario Outline Form ES-D-1

• Facility:

Examiners:

Fermi 2 C. Moore D. McNeil C. Phillips Scenario No.

Operators:

1 Op-Test No: 2013-1 Initial Conditions: IC-20, MOL, 100% Rx. Power Turnover: The Qlant has been OQerating at 100 % Reactor Qower for the last 205 days. #2 GSW is OOS for motor reQlacement. ExQected return to service is two weeks. "B" CRD PumQ is OOS for oil reQlacement on gear reducer. Return to service is exQected tomorrow.

Event Malf. No. Event Event No. Type* Description 1 NGADN302 C(BOP) #2 TCV Unitized Actuator Failure (Oil Leak)- 4D2 1C002TVSP C(SRO) 2 R(ATC) Reduce Reactor Power< 93% to lock down #2 TCV R(SRO)

N(BOP) Lock Down #2 TCV- 23.109, Main Turbine 3

N(SRO)

C11MF1106 C(ATC) CR 58-39 Individual SCRAM from half scram during 4

1. 2TCV lockdown and blown fuse. Disarm CR due to badly C(SRO) damaged fuse clip.

CRS enter TS 3.1.3, Control rod operability- one rod inop and inserted.

C93RF0001 NA Earthquake - AOP 20.000.01 - AOP Actions 5

C97MF1087 6 E51MF0010 C(All) RCIC Steam Leak. Auto Isolation Fails. Manual isolation Successful. EOP 29.100.01 Sheet 5 (CT 1)

EOPRF0024 CRS enter TS 3.5.3, RCIC EOPRF0025 N20MF0023 M(All) Loss ofFeedwater-AOP 20107.01-Mode Switch to SID 7

EOP 29.100.01 Sheet 1 - RPV Control N20MF0024 N20MF0025 E41MF0011 C(All) Loss of High Pressure Feed Sources- Lower RPV pressure 8

to feed with HFP.

N21MF0011 Inhibit ADS (CT -2)

N21MF0038

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, 38 of 39

Appendix D Scenario Outline Form ES-D-1

• Facility:

Examiners: C. Moore D. McNeil B. Palagi Fermi 2 Scenario No.

Operators:

1 Op-Test No: 2013-1 Initial Conditions: IC-20, MOL, 100% Rx. Power Event Malf. No. Event Event No. Type* Description 9 B31MF0066 M(All) Leak in drywell- EOP 29.100.01 Sheet 2- Primary Containment Control Emergency Depressurization EOP 29.100.01 Sheet 3-(CT-3) 10 E21RF0005 C(BOP) Auto Start Failure- Div. 1 Core Spray C(SRO) 11 E11MF0016 C(ATC) Containment Spray Valve Failure E1150-F016A C(SRO) Spray Drywell (CT 4)

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

• Appendix D, 38 of 39

Appendix D Scenario Outline Form ES-D-1

• Facility:

Examiners: C. Moore Fermi 2 D. McNeil C. Phillips Scenario No.

Operators:

2 Op-Test No: 2013-2 Initial Conditions: IC-15 (55% Power)

Turnover: Reactor gower is 55%. A giant startug is in grogress following a glanned shutdown for regairs to Main Transformer 2A. The startug is currently on hold, awaiting chemistry results on heater drains. CW Pumg #5 is OOS for motor reglacement Event Malf. No. Event Event No. Type* Description C102Cll P C(ATC) Trip of A CRD Pump (B CRD Fails) AOP 20.106.01 -restart 1

S- N001A- S C(SRO) ACRD.

TFCLOSE C11MF1117 TS 3.1.5 2 TEAJSPECI C(BOP) High Vibration/High Amps #6 Drywell Cooling Fan- 8D45 FIC F78875 C(SRO) - Shutdown Fan 3TFF

• B21MF0025 C(All) C SRV Open- AOP 20.000.02 - SRV closes when fuses 3

pulled TS 3.4.3 4 N(BOP) Torus Cooling- 23.205 N(SRO)

NMRDFU M(All) Loss of Steam Jet Air Ejectors/Loss of Vacuum- AOP 5

llCC 20.125.01 Mode Switch to Shutdown 6 C11MF0001 M(All) ATWS- EOP 29.100.01 Sheet 1 and 1A Inhibit ADS (CT 1)

C71MF0006 Terminate and Prevent (CT 2)

C41MF0003 C(ATC) SLC Pumps Trip 7

C41MF0004 C(SRO) 29.ESP.02- Alternate Boron Injection 8 EOPRF0007 NA Insert Control Rods (CT 3) thru 29.ESP.10 EOPRF0014 29.ESP.11 9 B21MF0102 C(All) Spurious MSIV Closure F SRV fails Open- EOP 29.100.01Sheet 2- High Torus B21MF0028 Temp

• (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Appendix D, 38 of 39