Text

2012 Quad Cities Nuclear Power Station Initial License Examination Outline Submittal
	ML12201A259
Person / Time
Site:	Quad Cities
Issue date:	04/23/2012
From:	Palagi B; NRC/RGN-III/DRS/OLB
To:	; Exelon Generation Co
References
	Download: ML12201A259 (40)
	v • d • e

2012 QUAD CITIES POWER PLANT INITIAL LICENSE EXAMINATION OUTLINE SUBMITTAL

Exe on.

Exelon Generatioll Com pany, LLC www exeloncorp.com Nuclear Quad Cities Nuclear Pow r Station 22710 206th Avenue North Cordova, IL 61242-9740 SVP-12-012 February 2, 2012 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4352 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Submittal of Initial Operator Licensing Examination Outlines Enclosed are the examination outlines that support the Initial License Examination scheduled for the weeks of April 23, 2012 and April 30, 2012 at Quad Cities Nuclear Power Station.

This submittal includes all appropriate examination standard forms and outlines in accordance with NUREG-1 021, "Operator Licensing Examination Standards for Power Reactors," Revision 9 (Supplement 1),

In accordance with NUREG-1 021, Revision 9 (Supplement 1), Section ES-201, "Initial Operator Licensing Examination Process," please ensure that these materials are withheld from public disclosure until after the examinations are complete.

Should you have any questions concerning this letter, please contact Mr. Wally J. Beck, Regulatory Assurance Manager, at (309)-227-2800. For questions concerning examination outlines, please contact Christopher J. Burkhart at (309)-227-4057, Respectfully,

~<--~

Tim Hanley Site Vice President Quad Cities Nuclear Power Station FEa 3 2012

February 2, 2012 U. S. Nuclear Regulatory Commission Page 2

Enclosures:

(Overnight delivery to Bruce Palagi, Chief Examiner, NRC Region III)

Examination Outline Quality Checklist - Form ES-201-2 Photocopies of Examination Security Agreement - Form ES-201-3 Administrative Topics Outline (RO) - Form ES-301-1 Administrative Topics Outline (SRO) - Form ES-301-1 Control Roomlln-Plant Systems Outline (RO) - Form ES-301-2 Control Roomlln-Plant Systems Outline (SRO) - Form ES-301-2 Transient and Event Checklist (4) - Form ES-301-5 Scenario Outlines (4) - Forms ES-D-1 BWR Examination Outline (RO & SRO) - Forms ES-401-1 and ES-401-3 Record of Rejected KJAs - Form ES-401-4 Statement detailing method of Written Exam Outline generation cc:

Chief, Operations Branch - NRC Region III (w/o enclosures)

NRC Senior Resident Inspector - Quad Cities Nuclear Power Station (w/o enclosures)

ES*201 Examination Security Agreement Form ES*201*3

~2-

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of ~~P as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not een authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthennore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2.

Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of

. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as speCifically noted below and authorized by the NRC.

. PRINTED NAME

. SIGNA~TURE JOB TITL~ / RESPONSIBILITY (1

DATE SIGNATURE (2)

DATE NOTE

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13.___________

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NOTES:

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ES.201 Examination Security Agreement Form ES*201*3

?q..5~ I

1.

Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of o't/zYU)lZas of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2.

Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of

. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1)

DATE SIGNATURE (2)

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ES-201 Examination Outl ine Quality Checklist Form ES-201-2 Facility: Quad Cities Date of Examination: 0412312012 Initials Item Task Description a

b*

c#

1.

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

b fI I a.

W R

b. Assess whether the outline was systematically and randomly prepared in accordance with

~- 6 ~f>

I Section 0.1 of ES-401 and whether all KiA categories are appropriately sampled.

T fI,,A) (KJ T

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

E N

d. Assess whether the justifications for deselected or rejected KiA statements are appropriate.

rs J) fjJ

2.

a.

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

,6 tt of normal evolutions, instrument and component failures, technical specifications, f;

S and major tranSients.

I I

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 0 Pf L

without compromising exam,integrity, and ensure that each applicant can be tested using A

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

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

0 To the extent possible, assess whether the outline(s) conform(s) with the qualitative b ~P" R

I c.

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

Cf

3.

a. Verify that the systems walk-through outline meets the criteria specif'ied on Form ES-301-2:

q (1, ) the outline(s) contain(s) the required number oJ control room and in-plant tasks 6

W distributed among the safety functions as specified on the form

~fJ

/

(2) task repetition from the last two NRC examinations is within the limits specified on the form T

(3) no tasks are duplicated from the applicants' audit test(s)

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

on the form.

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

~ ~ Sf (1 ) the tasks are distributed among the topics as specified on the form I

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

~ lap

c.

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

~

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

4.

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered q.-J 6 eP in the appropriate exam sections.

G 4 Ib ~

E

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

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

if Ib tr E

c.

R

d. Check for duplication and overlap among exam sections.

17 1,It) eP A

~ (1) ep L

e. Check the entire exam for balance of coverage.

f.

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

~ /r; fP pr i nt~signature Date

a. Author Christooher Burkhart

.".. ~ -

If

b. Facility Reviewer (*)

Terrv Gallentine

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c. NRC Chief Examiner (#)

Brllce Palaai

(~;:..

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12

d. NRC Supervisor

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2

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I v...~~1 Note:

Independent NRC reviewer initial items in Column "c H

chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Quad Cities Date of Examination: April 23, 2012 Examination Level: RO [8l SRO D Operating Test Number: ILT 10-1 Administrative Topic Type Describe activity to be performed (See Note)

Code*

Perform One-Rod-Out Interlock Surveillance KIA: 2.1,44 Rating: 3,9 Knowledge of RO duties in the control room during fuel Conduct of D,P,S handling such as responding to alarms from the fuel Operations handling area, communications with the fuel storage facility, systems operated from the control room in support of fueling operations, and supportina instrumentation Perform Electrical Distribution Surveillance KIA: 2.1,31 Rating 4.6 I Conduct of D,S Ability to locate control room switches, controls, and Operations indications, and to determine that they correctly reflect the desired plant lineup

I-Print Reading Exercise KIA: 2.2.41 Rating 3,5 Equipment Control N,S Ability to obtain and interpret station electrical, and mechanical drawings.

I I

Select Personnel for Radiation Work KIA 2.3,4 Rating 3.2 D,R Knowledge of radiation exposure limits under normal or emergency conditions Radiation Control Emergency N/A NlA ProceduresIPian NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Type Codes &Criteria:

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

(N)ew or (M)odified from bank (?, 1)

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

I ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Quad Cities Date of Examination: April 23. 2012 Examination Level: RO 0 SRO ~

Operating Test Number: ILT 10-1 Administrative Topic Type Describe activity to be performed Code*

(See Note)

Review a Fire Impairment Permit Requiring Compensatory Actions Conduct of DPR KA: 2.1.25 Rating: SRO 4.2 Operations Ability to interpret reference materials such as graphs, curves, tables, etc.

Reactivation of SRO License KIA 2.1.4 Rating SRO 3.8 Conduct of Knowledge of individual license operator responsibilities DR Operations I related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 1 OCFR 55, etc.

Review an Electrical Distr'ibution Surveillance Equipment Control DR KIA: 2.2.40 Rating SRO 4.7 Ability to apply Technical Specifications for a system Identify ODCM Compensatory Measures for Inoperable Rad Monitor KIA: 2.3.15 Rating SRO 3.1 Radiation Control NR Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Classify an Event and Determine Protective Action Recommendations (PARs)

Emergency OS KIA: 2.4.44 Rating:SRO 4.4 Procedures/Plan Knowledge of emergency plan protective action recommendations NOTE: All' items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

Type Codes & Criteria:

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

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

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

ES 301, Page 22 of 27

I ES-301 Control RoomJIn-Plant Systems Outline Form ES-301-2 System / JPM Title

a. Scram Condition Present and Reactor Power Above APRM Downscale or Unknown 295037 EA 1.01 4.6/4.6 Insert Control Rods by De-Energizing the Scram Solenoids

b. Low Pressure Core Spray 209001 A 1.02 3.213.4 Return B Core Spray to Standby After Test

c. Main and Reheat Steam system 239001 A4.01 4.214.0 Perform the MSIV closure Timing Test

d. RCIC 217000 A4.03 3.4/3.3 Shutdown the RCIC System

e. Primary Containment System and Auxiliaries 223001 A2.04, 3.7/3.8 Vent Containment Irrespective of Release Rates with APCV

f. A.C. Electrical Distribution 262001 A4.04 3.6/3.7 Energize Bus 13-1 via the Crosstie with the 1/2 EDG failure

g. Component Cooling Water 400000 Generic 2.1.32 3.8/4.0 Start-Up RHRSW System With Reduced Pump Capacity

h. Plant Ventilation Systems 288000 A4.01 3.1/2.9 Unisolate and Start the Reactor Building Ventilation System In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Condensate Systeml Reactor Low Water Level 295031 EA 1.11 4.1/4.1 Inject Water Into the RPV using the Condensate System Crosstie

j. RPS 212000 A2.02 3.7/3.9 Transfer Power from Reserve Power to (RPS) MG Set

k. Emergency Generators 264000 2.1.30 4.4/4.0 Place the Unit 1 DGCWP on Alternate Feed Facility: Quad Cities Date of Examination: April 23, 2012 Exam Level: RO ~ SRO-I 0 SRO-U 0 Operating Test Number: ILT 10-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may Type Code*

DLS Safety Function 1

NAS OS DAS DALS MAS DAS DPS 2

3 4

5 6

8 9

DPER DR DER 2

7 6

overlap those tested in the control room.

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

(P)revious 2 exams (R)CA (S)imulator i

Criteria for RO / SRO-I / SRO-U 4-6 1 4-6 / 2-3

~9/ ~8 / ~ 4

~ 1 1

~1 / ~ 1

- /

/ ~ 1 (control room system)

~ 1 1

~1 / ~ 1

~2/ ~2 / ~ 1

~3/ ~3 / ~ 2 (random Iy selected)

~ 1 /

~1 / ~ 1 I

I

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Quad Cities Date of Examination: April 23. 2012 Exam Level: RO 0 SRO-I [8J SRO-U 0 Operating Test Number: ILT 10-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U. including 1 ESF)

I System / JPM Title Type Code*

Safety Function

a. Scram Condition Present and Reactor Power Above APRM Downscale or Unknown 295037 EA1.01 4.6/4.6 Insert Control Rods by De-Energizing the Scram Solenoids DLS 1

b. Low Pressure Core Spray 209001 A1.02 3.2/3.4 Return B Core Spray to Standby After Test NAS 2

c. Main and Reheat Steam system 239001 A4.01 4.2/4.0 Perform the MSIV closure Timing Test DS 3

d. RCIC 217000 A4.03 3.4/3.3 Shutdown the RCIC System DAS 4

I f. A.C. Electrical Distribution 262001 A4.04 3.6/3.7 Energize Bus 13-1 via the Crosstie with the 1/2 EDG failure MAS 6

I

g. Component Cooling Water 400000 Generic 2.1.32 3.8/4.0 Start-Up RHRSW System With Reduced Pump Capacity DAS 8

h. Plant Ventilation Systems 288000 A4.01 3.1/2.9 Unisolate and Start the Reactor Building Ventilation System DPS 9

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Condensate System/ Reactor Low Water Level 295031 EA 1.11 4.1/4.1 Inject Water Into the RPV using the Condensate System Crosstie DPER 2

j. RPS 212000 A2.02 3.7/3.9 Transfer Power from Reserve Power to (RPS) MG Set DR I

7

k. Emergency Generators 264000 2.1.30 4.4/4.0 Place the Unit 1 DGCWP on Alternate Feed DER 6

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

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

(P)revious 2 exams (R)CA (S)im ulator 4-6/ 4-6 / 2-3

$.9/ $.8 / $. 4

~ 1 /

~1 / ~ 1

- /

/ ~ 1 (control room system)

~ 1 /

~1 / ~ 1

~2/ ~2 / ~ 1

$. 3 /

$.3 / $. 2 (randomly selected)

~ 1 /

~1 / ~ 1 I

ES-301 Transient and Event Checklist Form ES-301-5 CREWb 2012 NRC Exam Crew 0 Facility: Quad Cities Date of Exam: 04/23/12 Operating Test Number: IL T 10-1 A

E Scenarios P

V 1

2 3

4 T

M P

E L

N CR~

CREW CREW CREW 0

I I

T POS ON POSITION POSITION POSITION T

N C

A I

A T

S A

B S

A 8

S A

8 S

A 8

L M

R T

0 R

T 0

R T

0 R

T 0

U N

Y 0

C P

0 C

P 0

C P

0 C

P M(*)

T P

SRO SRO RO SRO SRO RO SRO RO SRO E

A I

U 7

8 4

8 7

4 7

4 8

RO RX 5

1 1

1814 NOR 1

1 2

1 SRO-I IIC 3

34 26 5

4 0

SRO-U MAJ 6

6 7

3 2

0 TS 0

0 RO RX 2

5 5

3 1

0 NOR 1

SRO-I 1

2 1

1817 IIC 348 27 246 8

4 SRO-U MAJ

_6 6

7 3

2 0

TS 45 I

36 4

2 RX 2

5 2

1 RO 0

NOR 1

1 2

1 SRO-I 234 1818 IIC 48 7

4 7

4 SRO-U MAJ 6

6 7

3 2

0 TS 135 3 1 2

I'nstructions:

1.

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

and Aba ance-of-plant (8 P)" positions. Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC fc0sition. If an Instant SRO additionally serves in the 80P position, one IIC malfunction can be credited oward the two IIC malfunctions required for the ATC position.

2.

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

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

3.

Whenever practical, both instrument and component malfunctions should be included; only those that reqUire verifiable actions that provide insight to the applicant's com~etence count toward the mimmum requirements specified for the applicant's license level in t. e right-hand columns.

ES-301, Page 26 of 27

ES-301 Transient and Event Checklist Form ES-301-5 CREWC 2012 NRC Exam Crew C Facility: Quad Cities pate of Exam: 04/23/12 Operating Test Number: IL T 10-1 A

P P

L I

C A

N T

E V

E N

T T

Y P

E Scenarios 1

2 3

4 CREW POSITION T

0 T

A L

M I

N I

M U

M(*)

CREW POSITION CREW POSmON CREW POSIT,ION S

R 0

SRO 5

A T

C SRO 6

B 0

P RO 3

S R

0 SRO 6

A T

C SRO 5

I B

0 P

RO 3

S R

0 SRO 5

A T

C RO 3

B 0

P SRO 6

S R

0 A

T C

B 0

P R

I U

RO 1813 SRO-I 0

SRO-U 0

RX 5

1 1

NOR 1

I 1 2

1 IIC 5

i j

3 27 4

4 MAJ 6

I 6

I 6 3

2 TS 0

0 RO 0

SRO-I 1815 SRO-U 0

RX 3

2 5

3 1

NOR 1

1 2

1 IIC 245 I

48 234 7

9 4

MAJ 6

6 6

3 2

TS 2

1 35 4

2 RO 0

SRO-I 1816 SRO-U 0

RX 3

2 2

1 NOR 1

1 2

1 IIC 24 348 34 7

4 MAJ 6

6 6

3 2

TS 45

. 2 2

Instructions:

I

1.

Check the afglicant level and enter the operating test number and Form ES-O-1 event numbers for each event tYFae; are not a~licable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "ba ance-ofrlant (B P)" positions. Instant SROs must serve in both the SRO and the ATC positions, including at leas two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one IIC malfunction can be credited toward the two IIC malfunctions required for the ATC position.

2.

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

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

3.

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

ES-301, Page 26 of 27

ES-301 Transient and Event Checklist Form ES-301-5 CREwe CrewB Facility: Quad Cities Date of Exam: 04/23112 Operating Test Number: I L T 10-1 Scenarios A

E P

V 1

2 4

3 T

M P

E I

10 CREW CREW CREW CREW L

N I

T N

POSITION POSITION POSITION POSITION I

T I

A C

L M

S A

B A

B S

A B

S S

A B

A T

R R

R U

T T

T 0

0 R

T 0

0 Y

N p.:

I T

P I

M(*)

P 0

C P

P C

0 0

C 0

C SRO SRO RO SRO RO I

SRO SRO RO SRO R

U E

3 4

2 2

4 4

3 2

3 RX 1

1 5

RO 1

1 1

NOR 2

~2 SRO-I 4

I/C 5

3 26 I

4 0

2 SRO-U MAJ 6

7 6

3 0

0

, TS 0

1 RX 3

2 5

3 RO I

0 1

1 1

NOR 2

SRO-I 4

245 246 I/C 48 8

1813 I

2 SRO-U 7

MAJ 6

6 3

0 I

I 2

TS 2

36 I 3 RX 1

3 2

2 I

RO 0

1 1

NOR 1

2 SRO-I IIC 4

24 4

348 6

1814 I

2 SRO-U 7

MAJ 6

6 3

0 2

TS 45 2

Instructions:

1.

Check the af~licant level and enter the operating test number and Form ES-D-1 event numbers for each event tYFae; are not a~licable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "ba ance-of-rlant (B P)" positions. Instant SROs must serve in both the SRO and the ATC positions, including at leas two instrument or component (I/C) malfunctions and one major transient, in the ATC fc0sition. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited oward the two I/C malfunctions required for the ATC position.

2.

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

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

3 Whenever practical, both instrument and component malfunctions should be included; only those 1

that require verifiable actions that provide insight to the applicant's com~etence count toward the minrmum requirements specified for the applicant's license level in t e right-hand columns.

ES-301, Page 26 of 27

ES-301 Transient and Event Checklist Form ES-301-5 CREW A 2012 NRC Exam Crew A Facility: Quad Cities Date of Exam: 04/23/12 Operating Test Number: ILT 10-1 A

E Scenarios P

V 1

2 3

4 T

M P

E L

N CAEW CREW CAEW CAEW 0

I I

T POSITION POSmON POSITION POSITION T

N C

I A

T S

A B

S A

B S

I A

B S

A B

L M

N Y

R T

0 R

T 0

R T

0 I R T

0 U

T P

0 C

P 0

C P

0 C

P I 0 C

P M(*)

E SRO SRO RO SRO SRO RO SRO RO S~O I

R I

U 1

2 1

1 1

1 RX I

5 1 1 1

AO

,1811 NOR 1

1 2

1

'SRO-I IIC 5

34 26 5

4 0

SAO-U MAJ I

6 6

7 3

2 D

TS 0

0 AO AX 3

5 5

3 1

0 SRO-I NOR 1

I 1

2 1

1811 IIC 245 27 246 8

4 SAO-U MAJ 6

6 7

3 2

D TS 2

36 3

2 AX 3

5 2

1 AO D

NOA 1

1 2

1 SAO-I 234 1812 IIC 24 7

4 7

4 SAO-U MAJ 6

6 0

7 3

2 TS 135 3

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~licable for RO applicants. AOs must serve in both the "at-the-controls (ATC)"

and Mba ance-of-rlant (B P)" positions. Instant SAOs must serve in both the SAO and the ATC positions, including at leas two instrument or component (IIC) malfunctions and one major transient, in the ATC position. If an Instant SAO additionally serves in the BOP position, one IIC malfunction can be credited toward the two IIC malfunctions required for the ATC position.

I Reactivi~ manipulations may be conducted under norma'i or controlled abnormal conditions (refer to

2.

Section

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

3.

Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's com~etence count toward the minimum requirements specified for the applicant's license level in t e right-hand columns.

ES-301, Page 26 of 27

E5-401 BWR Examination Outline FORM ES-401-1 Facility Name: Quad Cities Date of Exam: 04/23/2012 RO KIA Category Points SRO-Only Points Tier Group I K K K

K I K K A A A A G G*

4 '1

. ~.6 i 2

3 Total A2 Total 1

2 3

4

1.

1 3

3 3

4 3

4 20 4

3 7

Emergency &

Abnormal 2

1 1

1 N/A 2

1 N/A 1

7 1

2 3

Plant Evolutions Tier Totals 4 4

4 6

4 5

27 5

5 10 1

3 2

2 2

3 2

2 2

3 26 2

3 5

2.

I Plant I

I 1

2 1

1 1

2 1

12 0

2 3

Systems Tier Totals 4 3

4 3

3 3

4 3

3 4

4 38 4

4 8

3. Generic Knowledge and Abilities 1

2 3

4 1

2 3

4 I

10 7

Categories 2

3 2

3 1

2 2

2 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 (Le., 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 KlAs 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) KlAs in TIers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topiCS I

must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.

B.

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; il 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 KlAs that are linked to 10 CFR 55.43.

ES-401, Page 16 of 33

ES-401 2

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

ElAPE # / Name / Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

~95001 Partial or Complete Loss of Forced 0

Reactor power response 3.7 1

Core Flow Circulation / 1 & 4 2

0

~95003 Partial or Complete Loss of AC / 6 4

System lineups 3.5 1

~95004 Partial; or Total Loss of DC Pwr / 6 01. Ability to perfonn specific system and integrated plant procedures 4.3 1

23 during all modes of plant operation.

~95005 Main Turbine Generator Trip / 3 0

Reactor power 3.8 1

5

~95006 SCRAM / 1 0

Reactor pressure control 4.0 1

7

~95016 Control Room Abandonment / 7 0

Reactor water level 4.0 1

6 295018 Partial or Total Loss of CCW / 8

02. Knowledge of the design. procedural. and operational differences 3.8 1

~ between units.

295019 Partial or Total Loss of Inst. Air /8 0

eackup air supply 3.5 I

1 1

295021 Loss of Shutdown Cooling / 4 0

Maximizing reactor water cleanup flow 3.3 1

4 295023 Refueling Acc / 8

04. Ability to diagnose and recognize trends In an accurate and timely 4.2 1

47 manner utilizing the appropriate control room reference material.

295024 High Drywell Pressure / 5

04. Knowledge of annunciator alanns. indications. or response 4.2 1

31 procedures.

195025 High Reactor Pressure / 3 0

Pressure effects on reactor power 3.9 1

1 295026 Suppression Pool High Water Temp.

0 Steam condensation 3.5 1

5 2

~ HIgh ContIdhmentTemperature /5

~ 3Contahnei\\i Id~ to QJIII CIItea 9

0 I

295028 High Drywell Temperature / 5 3

Drywell cooling system 3.9 1

295030 Low Suppression Pool Wtr Lvi / 5 0

RelC operation: Plant-Specific 3.6 1

3 I

~9503 1 1 Reactor Low Water Level / 2 0

Reactor core isolation cooling: Plant-Specific 4.0 1

4

~95037 SCRAM Condition Present and 0

Reactor Power Above APRM Downscale or 4

Suppression pool temperature 4.0 1

Unknown /1

~95038 High Oft-site Release Rate / 9 0

Protection of the general public 4.2 1

2

~OOOO Plant Fire On Site / 8 0

Plant and control room ventilation systems 3.0 I

1 5

1700000 Generator Voltage and Electric Grid 0

Breakers, relays 3.1 I

1 I

Disturbances / 6 2

3 3

I 3 4

3 i Group Point Total:

20 I

ES-401, Page 17 of 33

3 Form ES-401-1

/=S-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier lIGroup 2 (RO)

ElAPE # / Name / Safety Function K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

295002 Loss of Main Condenser Vac / 3 0

Offgas system Ilow 2.8 1

4.

295007 High Reactor Pressure / 3 0

295008 High Reactor Water Level / 2 0

c.

295009 Low Reactor Water Level / 2 0

I 295010 High Drywall Pressure / 5 0

.-... HIGh COntaInment Temp /&

Mlltt3 ~natlpllbblllO Q.a CIII-s I'

0 295012 High Drywell Temperature / 5 0

295013 High Supp~ession Pool T~mp. / 5 0

~95014lnadvertent Reactivity Addition /1 0

~95015 Incomplete SCRAM / 1 0

CRD mechanism 3.3 1

7 I

~95017 High Off-site Release Rate / 9 0

I ~95020 Inadvertent Cont. Isolation / 5 & 7 0

Reactor pressure response 4.1 1

4 I

~95022 Loss of CRD Pumps / 1 0

~95029 High Suppression Pool Wtr Lvi / 5 0

I

~95032 High Secondary Containment Area Iremperature /5 I

0

~95033 High Secondary Containment Area 0

Radiation Levels / 9

~95034 Secondary Containment Ventilation I

0 Secondary containment ventilation 4.0 1

High Radiation / 9 3

295035 Secondary Containment High 0

Secondary containment integrity 3.9 1

I Differential Pressure / 5 1

295036 Secondary Containment High

04. Ability to recognize abnormal indications for system operating Sump/Area Water Level / 5 04 parameters that are entry*level condnions for emergency and 4.5 1

abnormal operating procedures.

500000 High CTMT Hydrogen Conc. / 5 0

Primary containment hydrogen instrumentation 3.4 1

1 I

KIA Category Totals:

1 1

1 2

1 1 Group Point Total:

7 ES-401, Page 18 of 33

ES-4011 4

Form ES-401-1 ES-401 BWR Examination Outline Fonn ES-401-1 Plant Systems - Tier 21Group 1 (RO)

System # I Name K K K K K K A A A A G KIA Topic(s)

IR 1 2 3

4 5

6 1 2: 3 4

0 0

Automatic depressurization logic; Adequate pump net I 4.2; 203000 RHRlLPCI: Injection Mode 3

6 positive suction head (inte~ock suction valve open): Plant 3.5 2

Specific 205000 Shutdown Cooling 0

Pump motors 3.1 1

1 206000 HPCI '

0 Reactor pressure: BWR-2. 3, 4 3.8 1

3

~ 18CIIaIIon~)

tfA. S)tIefttnotu-..ItQuld CII.a 0\\

rw-~-

209001 LPCS 0

4 Heat removal (transfer) mechanisms 2.8 1

~HPC8

~A,~ IIIIt ~ IIIa.tc...

.ct 211000 SLC 0

Inadequate system flow 3.1 1

4 212000 RPS 1

5 SCRAM air header pressure 3.8 1

0

01.

HM channels/detectors ; Ability to evaluate plant 2.5; 2150031RM pe~onnance and make operationat iudgments based on 2

1 Q-7 operating characteristics. reactor behavior, and instrument 4.4 215004 Source Range Monitor 0

RPS 3.2 1

1 215005 APRM I LPRM 1

6 Aow converter/comparator network: Plant-Specific 3.3 1

217000 RCIC 0

04. lights and alarms ; Knowledge of the operational 3.5; 2

6 120 imptications of EOP wamings, cautions, and notes.

3.8 218000 ADS 0

ADS valve tait pipe temperature 3.5 1

I 6

223002 PCIS/Nuclear Steam Supply 0

System Indicating lights and alarms 3.5 1

Shutoff 1

, ~39002 SRVs 0

Vacuum breaker operation 2.7 1

6 I

0

~59002 Reactor Water Level Control I

1 Reactor water level 3.8 1

I

~61000 SGTS 0

High train moisture content 2.5 1

4

~62001 AC Electrical Distribution 0

0 D.C. power; Bus voltage 3.1 ;

2 1 3 2.9

~62002 UPS (AC/OC) 0 Transfer from altamative source to preferred source 2.8 1

1

~63000 DC Electrical Distribution I

0 Meters, dials, recorders. alarms, and indicating lights 3.2 1

1

~64000 EDGs 0

A.C. electrical dist~bu tion 3.9 1

2 I

300000 Instrument Air 01. Knowledge of the purpose and function of major system 4.1 1

28 components and controls.

I rwOOOO Component Cooling Water 0

Loads cooled by CCWS 2.9 1

1 217000) SSMP 0

Altemate supplies of water 3.6 1

7 KIA Category Totals:

3 2

2 2 13 I

2 2 2

3 Group Point Total:

26 ES-401, Page 19 of 33

ES-401-1 5

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 2 (RO)

System # I Name K K K K K K

A A A

A G KJA Topic(s)

IR 1

2 3

4 5

6 1 2 3

4 201001 CRD Hydraulic 0

201002 RMCS 0

Controt rod block actuation 3.2 1

1 201003 Control Rod and Drive Mechanism 0

~1004RSCB

~A. ~ notutIbrId IIa.tCIIII 0

~OO5RC18 N1A,.~ not.....,IIIOU1de...

0 201006RWM 0

Rod position indication: P-Spec(Not-BWR6) 2.9 1

3 202001 Recirculation 0

202002 Recirculation Flow Control 0

Recirculation system flow 3.3 1

8

, 204000 RWCU Knowtedge of system set points. intertocks and automatic 4.5 1

actions associated "';th EOP entry conditions.

214000 RPIS 0

CRDM 3.0 1

3 215001 Traversing In-core Probe 0

215002 RBM 0

216000 Nucicar Boiler Inst.

0

-~-

219000 RHRlLPCI: Torus/Pool Cooling Mode 0

223001 Primary CTMT and Aux.

1 Temperature measuremenl 2.7 1 1

1 226001 RHRlLPCI: CTMT Spray Mode I

0 230000 RHRlLPCI: Torus/Pool Spray Mode 0

233000 Fuel Pool Cooling/Cleanup 0

234000 Fuel Handling Equipment 0

239001 Main and Reheat Steam Steam line break 4.1 1

1 23800SMSIV ~ConWI

!fA........ 1IOI...0UId <*III t, 0 241000 ReactorfTurbine Pressure Regulator 1

Main turbine speed 2.7 1

3

~45000 Main Turbine Gen. I Aux.

0 Turbine controt 3.1 1

9

~56000 Reactor Condensate I

0 I

~59001 Reactor Feedwater 0

I

~6BOOO Radwaste 0

~71oo0 Olfgas I

0 1272000 Radiation Mon~oring 0

286000 Fire Protection 0

Are detection system: Plant-Specific 2.5 1

3

~88000 Plant Ventilation I

I 0

~90001 Secondary CTMT 0

I Off-site radioactive release rates 4.0 1

1 1290003 Control Room HVAC 0

tnitiate/reset system 3.2 1

I 1

~90002 Reactor Vessel Internals 0

0

~A Category Totals:

1 1

1 2

1 Group Point Total:

12 ES-401, Page 20 of 33

ES-401 2

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)

ElAPE # I Name I Safety Function K

K I ~ I A

A Q

KIA Topic(s)

I IR 1

2 1

2 1295001 Partial or Complete Loss of Forced I

0 Core Flow Circulation 11 & 4 I

I

~95003 Partial or Complete Loss of AC 16 0

I

~95004 Partial or Total Loss of DC Pwr 16 I

0 I

1295005 Main Turbine Generator Trip 13

01. Ability to interpret and execute procedure steps.

4.6 1

I 20

~95006 SCRAM 11 0

~95016 Control Room Abandonment I 7 I

0 1295018 Partial or Total Loss of CCW 18

02. Abitity to determine operability and/or availability of 4.6 1

87 safety related equipment.

295019 Partial or Total Loss of Inst. Air I 8 0

1295021 Loss of Shutdown Cooling I 4 0

Reactor water level 3.6 1

S 295023 Refueling Acc I 8 0

295024 High Drywell Pressure I 5 0

295025 High Reactor Pressure I 3 I

0 I

295026 Suppression Pool High Water Temp.

C)4,.

Knowtedge of the specific bases for EOPs.

4.0 1

5 1It

~ HIgh Contak1menttempendUre./5 F'

Mllk3COO...... nat.....toa-tc..

10 C)i

~..

295028 High Drywell Temperature 15 0

f95030 Low Suppression Pool Wtr LviI 5 0

Suppression pool level 4.2 1

I 1

I

~95031 Reactor Low Water Level 12 0

~5037 SCRAM Condition Present 0

~nd Reactor Power Above APRM 6

Reactor pressure 4.1 1

Downscale or Unknown 11

~95038 High Off-site Release Rate I 9 0

I

~0000 Plant Fire On Site I 8 0

Damper position 2.9 1

2 1700000 Generator Voltage and Electric Grid 0

Disturbances I 6 KIA Category Totals:

0 0

4 a Group Point Total:

7=

ES-401, Page 17 of 33

ES-401 3

Form ES-401-1 f S-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)

ElAPE # / Name / Safety Function K

I K

K A

A G

KIA Topic(s)

IR 1

2 3

1 2

~95002 Loss of Main Condenser Vac / 3 0

~95007 High Reactor Pressure / 3 0

~95008 High Reactor Water Level / 2 0

~95009 Low Reactor Water Level / 2 0

~95010 High Drywell Pressure / 5 0

~11 High COntaInment Tamp /8 MIlt! 3Ccn11rwnint naI.....IDQlldQlel 0:

295012 High Drywell Temperature / 5 02 Knowledge of lim~ing cond~ions for operations and safety limits.

4.7 1

22 295013 High Suppression Pool Temp. / 5 0

~95014 Inadvertent Reactivity Addition / 1 0

~95015 Incomplete SCRAM / 1 0

I 295017 High Off-site Release Rate / 9 I

I 0

295020 Inadvertent Cont. Isolation / 5 &7 0

295022 Loss of CRD Pumps / 1

04. Knowledge of abnonnal cond~ion procedures.

4.2 1

11 295029 High Suppression Pool Wtr Lvi / 5 0

295032 High Secondary Containment Area I

0 Temperature / 5 295033 High Secondary Containment Area I

0 Cause of high area radiation 4.2 1

Radiation Levels / 9 3

295034 Secondary Containment Ventilation I

I 0

High Radiation / 9

~95035 Secondary Containment High 0

Differential Pressure / 5

~95036 Secondary Containment High 0

Sump/Area Water Level / 5

~OOOOO High CTMT Hydrogen Conc. / 5 0

KIA Category Totals:

0 0

1 2 Group Point Total:

3 ES-401, Page 18 of 33

ES-401 4

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

System # I Name K

1 K

2 K

3 K

4 K

5 K

6

A A 1 2 A

3 A

4 G KIA Topic(s)

IR 203000 RHRlLPCI: Injection 205000 Shutdown Cooling Mode I

I I

0 0

206000 HPCI

!!O7000 I8oIa1ion (Emergency}

~-

209001 LPCS I

k',

04 4$

I'fA. ___ nac tIIII:zI4IIQIId CIIIII Ability to prioritize and interpret the significance of each annunciator or alarm.

4.3 0 I 0

~=

1

~HPCS 211000 SLC 212000 RPS 2150031RM 215004 Source Range Monitor 215005 APRM I LPRM 217000 RCIC 1218000 ADS 1223002 PCIS/Nuclear Steam Supply

~hutoff 1239002 SRVs 1259002 Reactor Water Level Control 1261000 SGTS 1262001 AC Electrical Distribution 262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs i300oo0 Instrument Air 400000 Component Cooling Water 217000) SSMP I

I I

0 4

0 8

04 30 Ot.

oe WA.~IIIIt"""IIQ111fClllae SCRAM trip sign~s Reactor high pressure

~nOwle<lge 01 events relateo to system operation/status ma must be reported to intemal organizations or external agencies. such as the State. the NRC. or the transmission

""'Am "",,,,,n, Knowledge 01 EOP mitigation strategies.

3.9 4.3 4.1 I

4.7 0,'

0 0

1 0

0 I

0 1

1 0

0 0

1 0

0 KIA Category Totals:

0 0

I 0 2 0 0

3 Group Point Total:

5 ES-401, Page 19 of 33

ES-401 5

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 2 (SRO)

System # I Name K

K K

K A

A A

A G KIA Topic(s) 1 2

3 4

5 6

1 2 3

4

~01001 CRD Hydraulic I

~01002 RMCS 201003 Control Rod and Drive Mechanism

~OO4fI8CS

~~notulbld.~QIa 1ao'005 RCI8 fA &,IIImnat......ClIIdCllile

~01006 RWM I

~02001 Recirculation 202002 Recirculation Flow Control I

04000 RWCU 14000 RPIS I

15001 Traversing In-core Probe

~15002 RBM

02. Ability to apply Technical Specilicalions lor a system.

.40

~ 16000 Nuclear Boiler Inst.

I 0

Remrence leg flashing 19000 RHRlLPCI: ToruS/Pool Cooling Mode

~3001 Primary CTMT and Aux.

226001 RHRlLPCI: CTMT Spray Mode

~30000 RHRlLPCI: Torus/Pool Spray Mode

~330oo Fuel Pool Cooling/Cleanup 0

Valve closures 5

234000 Fuel Handling Equipment 239001 Main and Reheat Steam 239003 MSIV Leakage Control

~41 000 ReactorlTurbine Pressure Regulator

~45ooo Main Turbine Gen. I Aux.

~56000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas I

272000 Radiation Monitoring 286000 Fire Protection I

I 288000 Plant Ventilation 290001 Secondary CTMT

. 290003 Control Room HVAC I

1290002 Reactor Vessel Internals I

KIA Category Totals:

0 0

0 2

0 0

1 Group Point Total:

IR 0

0 0

~O

[I >~

0 0

I 0

0 4.7 1

3.5 1

0 0

2.5 1

0 0

0 I

0 0

0 3

ES-401, Page 20 of 33

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

Form ES-401-3 Fa~ility Name:Quad Cities Date of Exam :04/23/2012 Category KJA#

Topic RO

_SRO-Only IR IR 2.1. 01 Knowledge 01 conduct of operations requirements.

3.8 1

2.1. 39

l<' of oonservative decision making practices.

3.6 1

1.

2.'. 41 Knowledge 01 the refueling process.

3.7 1

Conduct of 2.1.

r..

VJ..ICI C1UVII~

2.1.

SubtotC&

1 2.2.43 Knowledge 01 the process used to track inoperable alarms.

3.0 1

2.2.38 Know1edge 01 conditions and limitations in the facility license.

3.6 1

2.

2.2. 42 lAbility to recognize system parameters that are entry*level oonditions for Technical 3.9 1

Em ent 12.2. 23 ' lAbility to track Technical Specification limiting oonditions for operatlens.

4.6 1

Control 12.2. 25 IKnowl~ge..oIthe bases in Technical Specifications for limiting conditions for operations 4.2 land~fety limits.

1 12.2.

. ISubtotal 2

12.3. 11 lAbility to control radiation releases.

3.8 1

101 I

I Safety pnnaples pertaining to licensed operator duties, suen as I

2.3. 12 lradiation areas. alinninn filters. ~tc.

I responSibilities, access to locked high*

3.2 1

13.

2.3.04 01 radiation exposure limits under normal or emergency conditions.

3.7 1

'IRadi.

,01

-~.

I salety

pertaining to licensed operalor dulles, suen 2.3. 13 las response.

fuel handling 3.8 1

IComrol

~"""<<. tnlnr""ri

~'A~'.Unn;nn flit,,,. Atr 2.3.

2.3.

1~llhtnt;:!1 2

'OIt:UPI.

,nlerarcny and ~'U'Q~' witn orner support 2.4. 16 I:'=~;= acddent,

i

,,,,'~u,c', abnormal operating procedures, 3.5 1

t nuidelines.

2.4. 27 I _~. 01 "fire in the planr procedures..

3.4 1

14.

tasks performed outside the main oontrol room during an emergency 2.4, 34 and the resultant operational effects.

4.2 1

I IEmergency

'..... rocedures 12.4. 08 of how abnormal operating procedures are used in oonjunction with EOPs.

4.5 1

II Plan 2.4. 46 Ability to verify that the alarms are oonsistent with the plant conditions.

4.2 1

12.4.

ISubtotal 2

Tier 3 Point Total I

ES-401, Page 26 of 33

ES-401 Tier /

Group T1/G1 I

T1/G1 T1/G1 T1/G1 T1/G1 T1/G2 T1/G2 T1/G2 T1/G2 Record of Rejected K1As (RO)

Form ES-401-4 2012 NRC EXAM as of 02101/12 Randomly Reason for Rejection Selected KJA TIER 1 Group 1 2950232.4.11 Generic KA 2.4.11 was also selected in SRO T1 G2. Randomly Became selected 2.4.47 from the field of un-used System Generic KAs.

295023 2.4.47 295028 A 1.01 HighOW Temp A1.01 is ability to monitor/operate OW Sprays. Any Became question on this topic would conflict with several scenario events.

295028 A 1.03 Randomly selected A 1.03 295024 2.1.07 A question on 2.1.07 would overlap with operating exam. Randomly Became selected 2.4.31 from the field of un-used System Generic KAs.

2950242.4.31 295030 K3.07 NPSH considerations (K3.07) for ECCS pumps at QC are based on Became Torus water temp and pump flow, not Torus level. Randomly 295030 K3.03 selected an alternate K.3 topic Became TIER 1 Group 2 295012 K2.01 I

Became 295015 K2.07 Unable tQ write an operationally valid question about OW Ventilation. The only other K2 topic is DW Cooling (K2.02), which would conflict with the KA Topic for 295028, OW Hi Temp Emergency. From the field of unused T1G2 evolutions, randomly selected 295015. Selected from K2 again in order to maintain Outline balance. Randomly selected 1K2.11, Instrument Air, but that topic would be over-sampled (See RO T1 G1 and RO& SRO T2G 1)

Randomly selected K2.10, SPOS, but were unable to write an operationally valid question on that topic. Randomly selected K2.05, RWM, but a question on that topic would conflict with the RWM question in RO T2G2. Randomly selected K2.08, neutron monitoring, but a question on that topic would conflict with previously developed SRO T3 question 2.4.46. Randomly selected K2.07.

295036 2.4.01. Unable to meet 2na part of KIA statement since there are no Became immediate operator actions for QGA 300 on Reactor Building water 2950362.4.04 level. Randomly selected 2.4.04 from the field of un-used System Generic KAs.

500000 EA11.07 Unable to write an operationally valid question about N2 Purge Became during an H2 accident condition. Randomly selected an alternate 500000 EA1.01 A.1 topic Became ES-401, Page 27 of 33

Form IES-401-4 Reason for Rejection Selected KIA I

203000 2.4.06 ' Outline T2G1 had 4 generics but only 1 K4 and Tier Total had 5 Became Generics but only 2 K4s. To achieve better balance, from the field 203000 K4.06 of T1 G1 Systems with a Generic KA, randomly selected 203000 and replaced the Generic KA with a randomly selected K4 Topic.

215005 2.2.25 System 215005 was oversampled (selected twice in RO T2G1 and Became once in SRO T2G1). Randomly deselected the Generic KA.

217000 2.4.21 Randomly selected System 217000 and a 2.4.21 trom the field of un-used System Generic KAs.

217000 2.4.21 Unable to write a psYe.-hometrically sound question on this topic.

Became From tfle field of un-used System Generic KlAs, randornly selected 217000 2.4.20 2.4.20.

300000 K3.02 I System 300000 was oversampled (selected twice in RO T2G1 and Became once in SRO T2G 1). Randomly deselected the K3. Randomly 203000 K3.03 selected System 203000 and a K3.03.

ES-401 Record of Rejected KlAs (RO) 2012 NRC EXAM Tier 2 Group 1 Tier/

Randomly Group T2/G1 I

T2/G1 T2IG1 209002 K4.01 209002 (HPCS) was used as a place-holder for SSMP during the T2/G1 Became I

initial random selection process. Replaced HPCS with SSMP.

SSMP I K4.01 did not apply to SSMP so randomly selected a new K4 from (217000) K4.07 I the RCIC tOJ:)ics.

3000002.4.50 2.4.50 would be about a loss of air transient and would conflict with T2/G1 Became the question for 295019 in Tier 1. From the field of un-used System I

I I

300000 2.1.28 Generic KlAs, randomly selected 2.1.28 209001 K5.01 Unable to write~ ~s~chornet(i~all;i sound question on this topic.

T2/G1 Became (Indications of pump cavitation) Randomly selected an alternate K5 209001 K5.04 topic.

212000 K1.07 Topic K1.07 (Low-Low Set Logic) is not applicable to RPS at Quad T2/G1 Became Cities. Randomly selected an alternate K1 topic.

212000 K1.15 218000 A4.07 A question on A4.07 would overlap with operating exam. Randomly T2/G1 Became se:lected an allternate A4 topic.

218000 A4.06 I 239002K5.03 A question on K5.03 would overlap with operating exam. Randomly T2/G1 Became selected an a'lternate K.5 topic.

239002 K5.06 215004 K6.04 ",L!l;!able to lll!Iite a gs~g;bCg:H~t[icall~ sOImd question about SRM T2/G1 Became "detectors failure". Randomly selected K6.02, but this topic is too 215004 K6.01 similar to a previously developed IRM question. Randomly selected K6.05, but were unable to write a psychometrically sound question about SRM trip unit failure". Randomly selected K6.03, but importance rating, was < 2.5 and it is not facility identified important item. Randomly selected K6.01 ES-401, Page 27 of 33

ES-401 Record of Rejected KlAs (RO)

Form ES-401-4 2012 NRC EXAM Tier 2 Group 1 (Conti'nued)

Tier /

Group Randomly Selected K/A Reason for Rejection T2/G1 ; 215003 2.4.06 Became 215003 2.1.07 No EOP mitigation strategies related to lAMs. Randomly selected 2.1.30 but IRMs have no in-plant components to operate and control room operations would conflict with a previously developed SRM question. Randomly selected 2.1.27 but could not write a discriminatory question on system purpose. Randomly selected 2.2.22 but there are no <1 hr Tech Spec and no Safety Limits associated with lAMs. From the field of un-used System Generic KlAs, randomly selected 2.1.07.

T2/G1 262001 K6.03 Became 262001 K6.01

~Unable to write a question that did not conflict with previously developed questions on the topic of generator Trip. Randomly selected an alternate K6 topic.

T2/G1 223002 A1.03 Became 223002 A 1.01 Unable to write an operationally valid question for PCIS related to SPDS. Randomly selected an alternate A.1 topic.

T2/G1 Became Tier 2 Group 2 Tier /

Group Randomly Selected K/A Reason for Rejection T2/G2 202002 A4.06 Became 202002 A4.08 A4.06 addresses "Scoop Tube power", a topic that is no longer applicable to QC. Randomly sel'ected an alternate A4.

T2/G2 201006 K6.01 Became 201006 K6.03 KIA K6.01 is loss of RWM Power supply. Power comes from Plant Process Computer at Quad Cities. Could not write an operationally valid question. Randomly selected an alternate K6 topic.

T2/G2 2040002.4.49 Became 2040002.4.02 Topic 2.4.49 is not app'licable to RWCU at Quad Cities. (Immediate operator actions without reference to procedures) From the field of un-used System Generic KlAs, randomly selected 2.4.02.

T2/G2 234000 A2.02 Became 239001 A2.11 No Question could ba.develooed to match the A.2 KIA statement for this system. The A.2 statement measures the ROs' ability to use procedures to mitigate the failures. However, Quad Cities Fuel Handling procedures do not address a "loss of Refuel Bridge air" failure. T,he same problem exists for the other two A.2 topics. In order to maintain outline balance, from the field of unused T2G2 systems, randomly selected 239001 and selected frQm A2-again.

T2/G2 Became T2/G2 Became ES-401, Page 27 of 33

ES-401 Record of Rejected KlAs (RO)

Form ES-401-4 2012 NRC SRO Tier /

Randomly Reason for Rejection Group Selected KIA SRO TIER 1 Group 1 295030 A2.04 1lPable to write a g,SYchometrically sound question on this topic.

T1 Became (OW to Torus DP reiafERrfo Low Torus Level) Randomly selected an G1 295030 A2.01 alternate A2 topic.

2950182.1.19 2.1.19 (Using pilant computers) was not applicable to Abnormal T1 Became Event 295018. From the field of un-used System Generic KlAs, G1 295018 2.2.37 randomly selected 2.2.37 295026 A2.02 I

A2.02 was repeated from the Cert Exam and 3 other questions were T1 Became related to Low Torus Level. Randomly selected an alternate A2 G1 295026 A2.01 topic.

I 295026 A2.01 I Unable to write an SRO level question on A.2 topics for High Torus Became Water Temperature. Randomly reselected Evolution 295037 and 295037 A2.06 an alternate A.2 topic.

295021 A2.07 Unable to write a esychometricall~ sound question on this topic.

T1 I

Became I (Reactor recirculation) Randomly selected an alternate A2 topic.

G1 295021 A2.03 700000 2.2.36 A question on 2.2.36 would overlap with operating exam. From the T1 Became field of un-used System Generic KlAs, randomly selected 2.4.41 G1 700000 2.4.41 700000 2.4.41 Ullah!e to write. an SRO level question on Grid Instability without Became overlapping previously developed questions. Randomly selected 295026 2.4.18 Evo'lution 295026 and, from the field of un-used Generic KlAs, an alternate generic topic T1 Became G1 SRO TIER 1 Group 2 Evolution 295012 was being over-sampled (also selected in RO 295012 A2.03 T1 T2G2) Randomly reselected Evolution 295033 and an alternate A2.

Became G2 295033 A2.03 2950102.4.46 12.4.46 was being over-sampled (also selected in Tier 3). Randomly T1 reselected 2.2.44 from the field of un-used Generic KlAs.

Became G2 2950102.2.44 295010 2.2.44 Unable to write a question that did not conflict with previously T1 Became developed queStions on the topic of High Drywell pressure.

G2 295012 2.2.22 Randomly reselected Evolution 295012 and, from the f.ield of un used Generic KlAs, an alternate generic topic T1 Became G2 ES-401, Page 27 of 33

ES-401 Record of Rejected KlAs (RO)

Form ES-401-4 2012 NRC SRO P age 2 SRO TIER 2 Group 1 Tier I Randomly Reason for Rejection Group Selected KIA 259002 2.4.49 2.4.49 was being over-sampled (selected in RO T2G2 and T3 and T2 Became in SRO T2G2).

Randomly reselected 2.4.30 from the field of un-I G1 used Generic KlAs.

262001 2.2.22 [ System 262001 was being over-sampled (se'lected twice in RO 259002 2.4.30 T2 Became T2G1 and once in SRO T2G1).

Randomly reselected system G1, 209001 and topic 2.4.45 from the field of un-used Generic KlAs.

209001 2.4.45 209002 A2.14 209002 (HPGS) was used as a place-holder for SSMP during the T2 initial random selection process. Replaced HPGS with SSMP.

Became G1 A2.14 did not apply to SSMP so randomly selected a new A2 from SSMP the RGIG topics.

, (217000) A2.05 (SSMP) 217000 A question on A2.05 would overlap with operating exam. Randomly A2.05 selected an alternate A2 topic.

Became (SSMP) 217000 A2.13 I

(SSMP) 217000 Unable to write an SRO level guestion on A.2 topics for the Safe A2.13

=Shutdown Makeup PUmp. Randomly selected an alternate T2G 1 Became I system. Randomly selected a new A2 topic.

206000 A2.09 I 206000 A2.09 Unable to write a question HPGI that would not conflict with Became previously developed questions on other EGGS systems or suction T2 G1 T2 G1 T2 G1 T2 G2 239002 A2.06 sources. Randomly selected an alternate T2G1 system. Randomly selected a new A2 topic.

300000 2.4.41 2.4.41, concerns EAL thresholds for loss of air but there are none.

Became From the field of un-used System Generic KlAs, randomly selected 3000002.4.35 2.4.35 3000002.4.35 l...unable to write an SRO leyel' question because KIA 2.4.35 asks Became about Equipmen1 Operator actions. Randomly reselected an 300000 2.4.06 alternate topic from the field of un-used Generic KlAs.

215005 A2.01 A question on A2.01 would overlap with operating exam. Randornly Became selected an alternate A2 topic.

215005 A2.04 Became SRO TIER 2 Group 2

' 215002 2.4.18 System GeneriC Topic 2.4.18 (Specific EOP Bases) does not apply Became I to RWM. From the field of un-used System Generic KlAs, randomly 215002 2.4.20 selected 2.2.40 Became ES-401, Page 27 of 33 I

I ES-401 Record of Rejected KlAs (RO)

Form ES-401-4 SRO Tier 3 T3 2.1.32 2.11.32 was previously used for a RO/SRO Systems JPM. From the Became unused 2.1 Generic KlAs with 10 CFR 55.43.b links, randomly 2.1'.36 selected 2.1.36 2.1.36 Became 2.1.41 2.2.07 T3 Became 2.2.23 2.2.05 T3 Became 2.2.37 2.2.37 Became 2.2.42 I

2.2.42 Became I

I 2.2.39 2.2.39 Became 2.2.25 2.3.06 T3 Became I

2.3.04 2.1.36, procedures and limitations involved in core alterations, conflicts with an SRO Admin JPM. From the unused 2.1 Generic KlAs with 10 CFR 55.43.b link~, randomly selected 2.1.41 2.2.07 (Process for conducting special or infrequent tests) is not operationally valid at ac. From the unused 2.2 Generic KlAs with 10 CFR 55.43.b links, randomly selected 2.2.23

, 2.2.05 (Process for making design or operating changes) is not I operationally valid at ac. Such authority would require an additional qualification. From the unused 2.2 Generic KlAs with 10 CFR 55.43.b links, randomly selected 2.2.37.

l,Jnable to develo~ a guestion at the SRO level for 22.37. From the unused 2.2 Generic KlAs with 10 CFR 55.43.b links, randomly Iselected 2.2.42 1 Unable to develop a~question at the SRO levelJor 2.2.42, From the unused 2.2 Generic KlAs with 10 CFR 55.43.b lin'ks, randomly selected 2.2.39.

,Unable to aevelo~ a question at the SRO level for 2.2.~ From the unused 2.2 Generic KlAs with 10 CFR 55.43.b links, randomly selected 2.2.25 2.3.06 was previously used for a JPM on the SRO Cert Exam. From the unused 2.3 Generic KlAs with 10 CFR 55.43.b links, randomly selected 2.3.04.

T3 T3 I

I ES-401, Page 27 of 33 I

E5-401 Random-Iy Group Tier /

Selected K/A 2.1.03 T3 Became 2.1.39 I

2.2.01 T3 Became I

2.2.39 2.2.39 Became 2.2.42 2.3.07 T3 Became 2.3.11 2.4.49 T3 Became 2.4.27 I

I T3 T3 Record of Rejected KlAs (RO)

Form ES-401-4 TIE'R 3 RO Tier 3 Reason for Rejection 2.1.03 was previously selected and used on the Cert Exam. From the unused 2.1 Generic KlAs, randomly selected 2.1.39.

2.2.01 was previously selected and used on the Cert Exam. From the unused 2.2 Generic KlAs, randomly selected 2.2.39.

2.2.39 was previously selected and used on the Cert Exam. Also, unable to develop a Generic question without being a Systems question. From the unused 2.2 Generic KlAs, randomly selected 2.2.42 2.3.07 was previously selected and used on the Cert Exam. From

the unused 2.3 Generic KlAs, randomly selected 2.3.11.

I II 2.4.49 was selected 3 times and was being over-sampled (also I selected in RO T2G2 and in SRO T2G 1). Randomly reselected 2.4.27 from the field of un-used Generic KlAs.

ES-401, Page 27 of 33

Quad Cities 2012 Initial License Written Exam Description of Random Selection Process per ES-401 D.1.b The Quad Cities Initial License Written Exam is scheduled for administration in April of 2012.

The Written Exam Outline was systematically and randomly developed using a random generation tool from Western Technical Services as agreed to by the Chief Examiner during a phone conversation on 1'0/17/201'1. Future adjustments to the outline will use numbered poker chips to follow the process described in ES-401 Attachment 1.

As allowed by ES-401 Attachment 1, the evolutions and systems that were not applicable to Quad Cities were deleted. All remaining KIA Statements that have at least a 2.5 Importance Ratings were included in the selection field.

The Safe Shutdown Makeup Pump (SSMP) is an important system at Quad Cities. It was added to the list of systems in Tier 2 Group 1 using the KIA statements from RCIC (217000). This convention was established in the NRC-prepared Licensing Exam in 2007 and used again on the facility-prepared 2009 and 2011 exams. This adjustment was approved by the Chief Examiner during a phone conversation on 10/17/2011. Due to limitations with the random generation tool, HPCS (not a Quad Cities system) was used as a place-keeper for SSMP until the K1-6, A1-4, or Generic was selected, after which the sub-topic was reselected.

An "Originall Random Outline" was developed by this process. ES-401-4 "Record of Rejected KlAs" documents all revisions used to produce the Written Exam Outlines on ES-401-1 and ES-401-3 as submitted.

Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2012 NRC Scenario 1 Op-Test No.: ILT 10-1 Examiners:

Operators:

Initial Conditions:

A Startup is in progress at 7% Power in RUN (After a forced outage for a Recirc pump seal repair)

Turnover:

Establish Drywell inerting. Continue the startup by withdrawing control rods to open the Turbine Bypass Valves further.

Event No.

Malf. No.

Event Type*

Event Description 1

None BOP N

Establish the, Drywell Inerting lineup per QCOP 1600-20 I

2 dihs10700ap4md 4 (Override)

NM08E ATC I

Multiple APRM Failures. APRM 4 fails inoperable. Later, APRM 5 Fails slowly Downscale TS (QCOA 0700-03) 3 None ATC R

Withdraw control rods to achieve 2-4 Turbine I

Bypass Valves open 4

RD02R4211 ATC C

Recoverable Stuck Rod / Raise CRD Drive Pressure (QCOA 0300-02) 5 MC15R (Remote Function)

BOP I

Loss of SJAE Steam (Recoverable)

(QCOA 5400-04) 6 ED02 ED03D ED04K DG03B Crew M

Station Blackout is entered. The SBO diesel will be used to reenergize Bus 14-1.

(QCOA 6100-04) 7 RR10A HP08 RCOl Crew M

The transient initiates a small LOCA in the Drywell; QGA 100 and 200 are performed.

RCIC trips, the SSMP must be manually initiated, and local action is necessary to make HPCI available. When essential bus power is restored, the challenges to the Primary containment will be addressed.

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

Scenario 1

SUMMARY

Initial conditions:

o The plant is operating at 7% power just after the Mode Switch was taken to RUN. (After a forced outage for a Recirc pump seal repair)

Event 1: The BOP establishes the Drywell Inerting lineup per QCOP 1600-20.

Event 2: Multiple APRM Failures. Part 1: APRM 4 fails inoperable, resulting in a Y2 Scram and Rod Block. Since no other Channel B APRMs are out of service, APRM 4 can be bypassed and the Y2 Scram reset. (Note: This event continues after the stuck rod is resolved in Event 4.)

Event 3: The crew resumes control rod withdrawal to achieve 2 to 4 Turbine Bypass Valves opened per QCGP 1-1 Step F.6.kk.

Event 4: During rod withdrawal, one rod will not move from position 08. When the ATC raises CRD drive water pressure, the rod can be withdrawn. Drive water pressure should then be returned to normal.

Event 2, Part 2: APRM 5 will fail downscale over a 1-minute period. The failure will result in a Rod Block and downscale alarms. The SRO must address Tech Specs 3.3.1.1, RPS Instrumentation, for a second APRM inoperable on RPS Channel B and address TRM 3.3.a for Rod Block Instrumentation. If directed, the ATC will manually insert a B RPS Y2 Scram.

Event 5: Loss of SJAE steam results in the North Condenser Suction valves closing. (Condenser vacuum remains stable at low power) The BOP and SRO work through QCAN 901-7 A-14, QCOA 3300-02 and QCOA 5400-04 to identify the loss of steam to the in service SJAE. Bypassing the steam supply PCV will be successful. The BOP win reopen the SJAE Suction Valves.

Event 6: A Loss of Offsite Power occurs. Bus 13-1 locks out and the U1 Diesel cannot be started. When Bus 14-1 to Bus 24-1 crosstie fails, Station Blackout is entered. The SBO diesel must be used to reenergize Bus 14-1, which may be used to backfeed Bus 1'4 and Bus 19.

Event 7: The transient initiates a small LOCA in the Drywell; QGA 100 and 200 are performed. The crew will attempt to manually initiate RCIC but it will trip on a mechanical overspeed fault that cannot be reset. Local action is necessary to make HPCI: available. The crew will start the SSMP to maintain RPV Water level. When essential bus power is restored, the challenges to the Primary containment will be addressed.

Approximate Run Time: 1.5 Hours CRITICAL TASKS:

Critical task #1: Given a shutdown reactor with a LOCA in progress, restore and maintain RPV water level with avatlable high-pressure systems lAW with QGA 100 before RPV water level,reaches TAF.

Critical task #2: When Torus pressure exceeds 5 psig, INITIATE drywell sprays while in the safe region of the drywell spray initiation limit (DSIL). (BWROG PC-5.1 INIT DW SPRAY)

(Conditional Critical Task) If RPV water level lowers to less than -59 inches, inhibit ADS in accordance with QGA 100.

Appendix 0 Scenario Outline Form ES-O-1 Facility: Quad Cities Scenario No.: 2012 NRC Scenario 2 Op-Test No.: ILT 10-1 Examiners:

Operators:

Initial Conditions:

The plant is operating at 100% power.

The 1 A EHC Pump is out of Service.

1B Service Water Pump is out of service.

Turnover: QCIS 0600-01, Unit 1 Reactor Pressure 0 to 1200 psig Indication Calibration, is in progress.

Event Malf. No.

No.

1 None 2

None 3

SW02A I RD04 4

S None 6

PCOS

'RR03A RD13A 7

TCOSB SL01 8

(N)ormal, (R)eactivity, Event Event Type*

Description BOP

QCIS 0600-01 performed from the DFWLC OWS N

ATC Lower power with Rods and Recirc for Load R

Following BOP Service Water Pump degradation C

(QCOA-3900-01 )

ATC Hod 0 rift Out TS C

(QCOA-0300-11 )

SRO Torus Water Level PAM Instrument inoperable TS TS Crew A RBCCW leak in the drywell requires a manual M

scram (QCOA-3700-06). After RPS has been

~ tripped, approximately Y2 of the control rods remain withdrawn. (Hydraulic A TWS)

Crew QGA 101 Level/Power Control. Turbine Bypass M

valves become unavailable, requiring manual RPV Pressure control with Relief Valves ATC Malfunction after Major: Failure of 1 sl SBLC Pump to C

start (I)nstrument, (C)omponent, (M)ajor

Scenario 2

SUMMARY

Initial Conditions:

o The plant is operating at 100% power.

o The 1A EHC Pump is out of service.

o The 1 B Service Water pump is out of service.

Event 1: The BOP performs QCIS 0600-01 from the DFWLC OWS and returns FWLC to 3-Element.

Event 2: SRO and ATC insert control rods and lower Recirc Pump Speed and Reactor Power for load Following.

Event 3: The 1A Service Water Pump capacity will degrade to the pOint that the low pressure alarm is received in the Control Room. Reports from the Equipment Operator confirm a problem with the pump. The BOP will start the Y2 or the 2A Service Water Pump and secure the 1A pump.

Event 4: Control Rod B-6 drifts out from position 00. The ATC and SRO respond per QCANs and QCOA 300-11. The rod should be inserted and 'scrammed. The SRO should address Tech Specs TS 3.1.3, Condition C, for an inoperable control rod.

Declares control rod B-6 inoperable and enters which is 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months to fully insert and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to disarm.

Event 5: The IMD Supervisor calls the US to report that an unqualified replacement part was recently used for the Torus level Transmitter for Control Room Narrow Range indications. The SRO will address Technical Specifications for an inoperable Post Accident Monitoring (PAM) instrument.

Event 6: A RBCCW leak in the Drywell requires the crew to manually scram the reactor per QCOA 3700-06. After RPS has been tripped, approximately Y2 of the control rods remain withdrawn. (Hydraulic ATWS)

Event 7: The crew terminates and prevents injection per QGA 101 (Level/Power Control). During this period, the running EHC pump trips which closes the Turbine Bypass valves. The crew must manually control RPV Pressure with Relief Valves.

Torus Cooling may be placed in service.

Event 8: When SBlC is initiated for the ATWS, the 1st pump selected will fail to start.

The ATC will recognize this malfunction and start the other SBlC Pump.

Scenario ends when actions are being taken to shutdown the reactor and RPV water level is being controlled in the specified band.

Approximate Run Time: 1.5 Hours CRITICAL TASKS:

Critical Task #1 With a reactor scram required and the reactor not shutdown, TAKE ACTION TO REDUCE POWER by injecting boron (prior to exceeding 110°F torus temperature) and/or inserting control rods, to prevent exceeding primary containment design limits. (BWROG RPV-6.1 ATWS PWRllVL SID REACTOR)

Critical task #2: During at A lWS with conditions met to perform powerllevel control, TERMINATE AND PREVENT INJECTION, with the exception of boron, CRD and RCIC into the RPV until conditions are met to re-establish injection.

Critical task #3: When conditions are met to re-establish injection, use available injection systems to MAINTAIN RPV water level above the Minimum Steam Cooling RPV Water level (-166").

(Conditional Critical Task) If RPV water level lowers to less than -59 inches, inhibit ADS in accordance with QGA 100 or QGA 101.

Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2012 NRC Scenario 3 Op-Test No.: ILT 10-1 Examiners:

Operators:

Initial Conditions:

The plant is operating at 75% power.

Turnover: Perform the SSMP POV Test.

IIEvent Malt. No.

No.

1 LOHS1*290181" (Override) 2 RD07 I

3 HP10 4

SW12A 5

ED038 6

RR10A ED03A 7

RC04 8

HP01 Event Event I

Description T~pe*

Perform the SSMP POV Test (QCOS 2900-03) TS N

ATC BOP CRD Pump Trip C

(QCOA 0300-01)

BOP Inadvertent HPCI Initiation TS I

(QCOA 2300-01 )

BOP I The running TBCCW pump begins to fail C

JQCOA 3800-03)

ATC Loss of Bus 12, Respond to ~oss of B Recirc Pump TS (QCOA 6500-02 & QCOA 0202-04) Insert R

control rods to exit Instability Region 2 Crew Large Line Break LOCA. When the plant trips, Bus M

11 trips and the remaining Feed Pumps will be lost.

ATC I RCIC Auto Initiation fails, requiring manual RCIC C

initiation Crew HPCI trips and Alternate Level Control per QGA 100 M

second leg actions are taken. The crew Emergency Depressurizes per QGA 500-1 at T AF and restores RPV level with Low-Rressure systems.

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

Scenario 3

SUMMARY

Initial Conditions:

o The plant is operating at 75% power.

Event 1: The BOP performs SSMP Power Operated Valve Test per acos 2900-03.

The 1-2901-08 valve stroke time exceeds its 1ST limit requiring the SRO to reference TS 3.7.9 Condition A, enter a 14-Day LCO to restore operability.

Event 2: The A CRD Pump trips. The ATC Operator and US respond per aCOA 0300-01 to start the B CRD Pump and open its discharge valve.

Event 3: The BOP responds to an inadvertent HPCI Initiation per aCOA 2300-01.

When HPCI has been trip-latched to prevent restart, the SRO should reference TS 3.5.1 Condition G.

Event 4: The running TBCCW pump begins to fail. The BOP and SRO respond to low pressure in the TBCCW header per the aCAN and aCOA 3800-03 to stabilize the system.

Event 5: The BOP responds to a loss of Bus 12 per aCOA 6500-02. The ATC/BOP respond to loss of B Recirc Pump per aCOA 0202-04. The ATC and SRO insert control rods to exit I nstability Region 2.

Event 6: A LOCA inside the Drywell begins. The crew enters and performs QGA 100 and 200. Bus 11 and the :remaining Feed Pumps are lost when the UAT trips.

Operators will control containment parameters without further challenge.

Event 7: RCIC auto initiation and the Iinitiation Pushbutton will fail. The ATC must manually initiate RCIC per the QCOP 1300-02 Hard Card for RPV water level control.

Event 8: HPCI fails and the remaining high-pressure systems will not be able to maintain RPV Water level' above Top of Active Fuel. The crew will perform Emergency Depressurization and then restore RPV Water Level with available low pressure systems.

Approximate Run Time: 1.5 Hour CRITICAL TASKS:

Critical task #1 : Given the plant with the inability to maintain level above -59 inches, INHIBIT ADS, to prevent an uncontrolled depressurization lAW QGA 100.

Critical task #2: When Torus pressure exceeds 5 pSig, INITIATE drywell sprays while in the safe region of the drywell spray initiation limit (DSIL). (BWROG PC-5.1 INIT OW SPRAY)

Critical task #3: Given the plant with an inability to maintain RPV water Level above -142 inches with an injection source lined-up and running, initiate an emergency depressurization before RPV water level drops to -166 inches in accordance with QGA 100 and QGA 500-1.

Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2012 NRC Scenario 4 Op-Test No.: ILT 10-1 Examiners:

Operators:

Initial Conditions:

The plant is operating at 80% power. Holding power for QNE verification of thermal limits.

The 1 C Circ Water Pump is out of service.

Turnover: Perform the Acoustic Monitor Test for SRVs 3A, 3B, and 3C.

Event No.

Malt. No.

Event Type*

Event Description 1

None BOP N

Perform Acoustic Monitor Test I

2 FW18C FW19C ATC C

Respond to a Condensate/Cond Booster Pump degraded capacity 3

RM05A SRO TS Drywell Radiation Monitor Fails Upscale TS 4

AIPIC1874011 BOP C

DW N2 pressure control fails upscale (QCOA 0201-01) 5 MC01B ATC R

Loss of a Circ Pump I Emergency Power Reduction for Condenser Backpressure (QCOA 4400-04)

I 6

ED10 ED11 ATC C

I Respond to Loss of ESS Bus TS (QOA 6800-03) 7 CR01 HP12 HP13 Crew M

Fuel failure. QCOA 1700-4 will require the crew to close the MSIVs. An unisolable leak in the HPCI room requires the crew to enter QGA 300 and 100.

8 CR02 Crew M

When the Torus Area also exceeds Max Safe Temperature or Radiation, the crew will Emergency Depressurize_per QGA 500-1.

(N)ormal, (R)eactivity.

(I)nstrument, (C)omponent, (M)ajor

Scenario 4

SUMMARY

Initial Conditions:

o The plant is operating at 80% power. Holding power for QNE verification of thermal limits.

o 1 C Circ Water Pump out of service for coupling repair.

Event 1: The BOP performs a partial Acoustic monitor test, QCOS 0203-01 for SRVs 3A, 3B, and 3C.

Event 2: The ATC responds to degraded capacity of a Condensate/Condensate Booster pump by shifting to the standby pump.

Event 3: Operators respond to an unexpected 112 Group 2 Isolation and determine that the A Drywell Rad Monitor has failed (upscale). The SRO enters Technical Specifications (PCI) 3.3.6.1 Condition A and (PAM) 3.3.3.1 Condition A.

Event 4: Drywell N2 controller fails, causing the makeup valve to open fully. The BOP can take manual control of the valve and close it to stabilize Drywe" pressure.

Without operator action, Drywe" pressure will continue to rise and eventually exceed the Drywe" High Pressure alarm setpoint.

Event 5: The BOP responds to Loss of a Circ Pump (1 Pump operation) per QCOA 4400-04. The ATC and SRO perform Emergency Power Reduction for loss of a Circ Pump per QCOA 4400-04. Reducing Reactor power to within the capacity of one Circ Water Pump stabilizes condenser vacuum.

Event 6: ESS UPS failure. The crew wi" respond per QOA 6800-03. Equipment Operator actions can restore the bus. The BOP will restore the SJAE lineup. The ATC wi" reset the lockup of a Feed Reg Valve and reset the partial Group 1 Isolation. The SRO should reference Technical Specifications 3.5.1 Conditions G & I and 3.5.3 Conditions A & B for HPCI and RCIC Inoperable.

Event 7: A fuel element failure begins. The crew wi" respond to High Offgas radiation per QCOA 1700-04. When SJAE Rad levels cannot be maintained less than High High alarm, the crew wi" isolate Oftgas, Scram, and close the MSIVs/Drains. A leak in the HPCI room then begins that requires the crew to enter QGA 300. The crew wi" attempt to isolate the leak, but the leak cannot be isolated.

Event 8: When the Torus Area also exceeds Max Safe Radiation level, the crew will Emergency Depressurize the RPV.

Approximate Run Time: 1.5 Hours CRITICAL TASKS:

Critical Task #1: The Crew will take action to isolate the RPV and reduce the release of radioactivity by manually clOSing the MSIV's, Main Steam drains and verifying the Offgas System is isolated as required.

Critical task #2: Given an operating reactor plant with a primary system discharging into the reactor building and the discharge cannot be isolated, INITIATE an emergency depressurization when two or more areas exceed the maximum safe operating levels of the same parameter (radiation, temperature, or water level).

ML12201A259

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