ML120250287

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2011 Quad Cities Nuclear Power Station Initial Examination Outline Submittal
ML120250287
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 06/06/2011
From: Bielby M
NRC/RGN-III/DRS/OLB
To:
Exelon Generation Co, Exelon Nuclear
Shared Package
ML11167A119 List:
References
Download: ML120250287 (31)
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Text

2011 QUAD CITIES NUCLEAR POWER STATION INITIAL EXAMINATION OUTLINE SUBMITTAL

Exelon Generation Company, LLC Qu,ld Cities Nuclear Powel Station wvvw,exelo!1corp,(om Nuclear 22710206'" Avenue North Cordova,!L 61242,-9740 SVP-11-013 February 21 , 2011 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 May 31, 2011 through June 13, 2011 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 Raymond J. Venci at (309)-227-4033.

R~

William R. Gideon Site Vice President Quad Cities Nuclear Power Station FEB 2 2 2011

February 21, 2011 U. S. Nuclear Regulatory Commission Page 2

Enclosures:

(Overnight delivery to Carl Moore, 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 Room/In-Plant Systems Outline (RO) - Form ES-301-2 Control Room/In-Plant Systems Outline (SRO) - Form ES-301-2 Transient and Event Checklist (6) - 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 KlAs - 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 Outline Quality Checklist Form ES-201-2 Dale of Examination: £;(;/ I, &/-<¢I Initials Item Task Description a b* c#

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

W R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section 0.1 of ES-401 and whether all KIA categories are appropriately sampled.

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

T E

d. Assess whether the justifications for deselected or rejected KIA statements are appropriate, N
2. a. Using Form e5-301-5. verify that the proposed scenario sets cover the required number of normal evolutions. instrument and component failures. technical specifications.

S and major transients.

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 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 testIs). and that scenarios will not be repeated on subsequent days.

o c. To the extent possible. assess whether the outline(s) conform(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 1 (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 testIs)

(4) the number of new or modified task!! meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power. emergency. and RCA I.a:iil1§ meet the criteria on the form.

b. Verify that the administrative outline meets the criteria specified on Form e5-301-1:

(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 re~eated from the last two NRC licensinlLexaminations

c. Determine if there are enough different outlines to test the projected number and mix of apj)licants and ensure that no items are duplicated on subsequent da~.
4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

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

e N c. Ensure that KIA importance ratings (except for plant-speclflc priorities) are at least 2.5.

E

d. Check for duplication and overlap among exam sections.

R A e, Check the entire exam for balance of coverage.

L

f. Assess whether the exam fils the appropriate job level (RO or SRO).
a. Author
b. Facility Reviewer (*)
c. NRC Chief Examiner (#)
d. NRC Supervisor Note: # Independent NRC reviewer initial items in Column *c"; chief examiner concurrence required.

I

  • Not applicable for NRC-prepared examination outlines T

ES-201, Page 26 of 28

ES-301

- - - -Form ES*301*1 Facility: Quad Cities Dale of Examination: May 31, 2011 Examination Level: RO 18l SRO 0 Operating Test Number; 09-01 Administrative Topic Type Describe activity to be performed (See Note) Code*

Perform One-Rod-Out Interlock Surveillance KIA: 2.1.44 Rating: 3.9/3.8 Knowledge of RO duties in the control room during fuel Conduct of Operations N,S handling such as responding to alarms from the fuel handling area, communications with the fuel storage facility, systems operated from the control room in support r-------~----~

of fueling oQerations, and SUEE0rting instrumentation Evaluate License Maintenance Requirements KIA: 2.1.4 Rating: 3.3/3.8 Conduct of Operations D,P,R Knowledge of individual license operator responsibilities related to shift staffing, such as medical requirements, "no-solo"operation, maintenance of active license status, etc.

Review Quarterly SBLC Pump Flow Rate Test Equipment Control N,R KIA: 2.2.12 Rating: 3.7/4.1 Knowledge of surveillance procedures Disable NUMAC ARM channel KIA: 2.3.5 Rating: 2.9/2.9 Radiation Control N,R Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Emergency Procedures/Plan N/A N/A 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 e. 1)

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

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Quad Cities Date of Examination: May 31,2011 Examination Level: RO 0 SRO [8] Operating Test Number: 09-01 Administrative Topic Type Describe activity to be performed (See Note) Code" Review a Fire Impairment Permit Requiring Compensatory Actions Conduct of Operations D,S KA: 2.1.25 Rating: 3.9/4.2 Ability to interpret reference materials such as graphs, curves, tables, etc.

Use Procedures Related to shift staffing Conduct of Operations D,P,R KIA: 2.1.5 Rating: 2.9/3.9 Ability to us procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

Verify Reactor Mode Change Requirements Equipment Control D,S,R KA: 2.2.12 Rating: 3.7/4.1 Knowledge of Surveillance Procedures Verify Liquid Radwaste River Discharge Permit Radiation Control D,R KA: 2.3.6 Rating: 2.0/3.8 Ability to approve release permits Classify a Security Event Emergency Procedures/Plan N,S KA: 2.4.41 Rating: 2.9/4.6 Knowledge of emergency action level thresholds and classifications.

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 e 1)

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

ES 301, Page 22 of 27

ES-301 Control Room/In-Plant Systems Outline Form ES-301*2 Facility: Quad Cities Date of Examination: 05/31/2011 Exam level: RO 0 SRO-I 181 SRO-U 0 Operating Test Number: IlT 09-1

. Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System 1JPM Title Type Code*

Function

a. SBlC, 211000 A4.06 3.9/3.9 A,D,S 1 Initiate Standby_Liquid Control with RWCU Failure to Isolate
b. RCIC 217000 A4.04 3.6/3.6 A,D,S 2 Manual Initiation of RCIC
c. ReactorlTurbine Pressure Regulating System 241000 A 4.15 3.2/3.2 N,S 3 Adjust Turbine/Generator System load Set
d. Shutdown Cooling System 205000 A2.06 3.4/3.5 A,D,l,S 4 Place Shutdown Cooling in Operation with Spurious Group II
e. A.C. Electrical Distribution 262001 A4.01 3.4/3.7 A,N,l,S 6 Energize 480 VAC Bus 15 With a Failure of the Normal Feed
f. RPS. 212000 2.1.23 4.3/4.4 N, L, S 7 Bypass "A" Channel of the Reactor Mode Switch to Shutdown Scram I g. RHRlLPCI Torus Cooling Mode 219000 A4.01 3.8/3.7 D,S 5 Shutdown Torus Cooling 11 h. N/A lIn-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Emergency Generators 264000 A2.08 3.3/3.7 A, D. E, R 6 Locally_Startu~ a Diesel Generator With a Failure of the Vent Fan to Start

, j. Reactor Low Water Level 295031 EA1.11 4.1/4.1 D,E,R 2 Inject Water Into the RPV using the Condensate System Crosstie

k. Fire Protection System 286000 K1.01 2.7/2.8 D,E,R 8 Align Fire Protection Water to SSMP Room Cooler

@ 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 1 SRO-II SRO-U (A)lternate path 4-6 I 4-6 (C)ontrol room (D)irect from bank ~91 ~8 I ~4 (E)mergency or abnormal in-plant ~1 1 ~1 1 ~ 1 (EN)gineered safety feature - 1 - I ~ 1 (control room system (L)ow-Power I Shutdown ~1I ~1 1 ~ 1 (N)ew or (M)odified from bank including 1(A) ~21 ~2 I ~ 1 (P)revious 2 exams ~31 ~3 I ~ 2 (randomly selected)

(R)CA ~ 1 1 ~1 I ~1 (S)imulator

ES-301 Transient and Event Checklist Form ES-301-5 CREW A Facility: Quad Cities Date of Exam: 05/31/11 Operating Test Number: ILT 09-1 A E Scenarios P V  !

1 2 3 4 T M P E L N CREW CREW CREW CREW 0 I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T 0 R T 0 R T 0 R T 0 U T P 0 C P 0 C P 0 C P 0 C P M(*)

E R I U RX 5 1 1 RO 1811 NOR 1 1 1 SRO-I IIC 5 1 48 4 4 D

SRO-U MAJ 6 6 6 3 2 D 0 TS 0 RX 2 1 1 RO D NOR 12 15 4 1 SRO-I 34 23 I/C 35 9 4 1811 5 48 SRO-U 2 MAJ 6 6 6 3 D

TS 45 4 3 2

! 1 RX 2 1 RO D NOR 1 2 1 2 i 1

SRO-I 13 34  ; 4 I/C 23 7 1812 5 SRO-U MAJ 6 6 6 3 2 D

TS 14 2 .;

2 Instructions:

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 "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

~osition. 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.

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 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 verifiab e actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

ES-301, Page 26 of 27

ES-301 Transient and Event Checklist Form ES-301-5 CREwe Facility: Quad Cities Date of Exam: 05/31/11 Operating Test Number: ILT 09-1 A E Scenarios P V 1 2 3 4 P E T M L N CREW CREW CREW CREW 0 I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T 0 R T 0 R T 0 R T 0 U T P 0 C P 0 C P 0 C P 0 C P M(*)

E R I U RO RX 5 1 1 ,

[8]2 NOR 1 1 2 1 SRO-I 4 I/C 5 46 48 5 0 ~

SRO-U MAJ 6 9 6 3 2 0

TS 0 0 RX 7 1 , 1 RO 0 NOR 12 f 15 4 1 SRO-I 34 23 "

IIC 38 9 4

[8]3 5 48 SRO-U , 2 MAJ 6 9 6 3 0

TS 45 4 3 2 RX 2 1 1 RO 0 NOR 17 1 3 1 l SRO-I 34

[8]4 I/C 34 23 8 4 68 SRO-U 9 6 3 2 MAJ 6 I; 0

TS 25 2 2 Instructions:

1. Check the afg'icant level and enter the operating test number and Form ES-D-1 event numbers for each event tYPae; are not affllicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "ba ance-of-plant (B 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

~osition. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited oward the two IIC malfunctions required for the ATC position.

2. Reactivi~ manipulations ma¥ 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. P Reactivity 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 level in the right-hand columns.

ES-301, Page 26 of 27

ES-301 Transient and Event Checklist Form ES-301-5 CREWC Facility: Quad Cities Date of Exam: 05/31/11 Operating Test Number: ILT 09-1 A E Scenarios P V 1 2 3 4 P E T M L N CREW CREW CREW CREW 0 I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M N Y R T 0 R T 0 R T 0 R T 0 U T P 0 C P 0 C P 0 C P 0 C P M(*)

E R I U RX 7 1 1 RO

[gI3 NOR 1 1 1 SRO-I I/C 5 38 1 4 4 0

SRO-U MAJ 6 9 6 3 2 0 0 TS 0 RX 2 1 1 RO D NOR 12 17 4 1 SRO-I ,

34 34 4

[gIS I/C 35 9 5 68 SRO-U 3 2 MAJ 6 9 6 D

TS 45 25 4 2 RX 2 1 1 RO D NOR 1 2 2 1 SRO-I 13

[gI6 IIC 34 46 7 4 5

SRO-U MAJ 6 9 6 3 2 D

TS 14 2 2 Instructions:

1. Check the "glicant 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 "ba ance-of-plant (B 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 position. If an Instant SRO additionally serves in the BOP position, one IIC malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivi~ manipulations ma¥ 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. P Reactivity 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 verifiab(e actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

ES-301, Page 26 of 27

ES-301 Transient and Event Checklist Form ES-301-5 CREW 0 Facility: Quad Cities Date of Exam: 05/31/11 Operating Test Number: ILT 09-1 A E Scenarios P V 1 2 3 4 P E T M L N CREW CAEW CAEW CAEW 0 I I T POSITION POSITION POSITION POSITION T N C A I A T S A B S A B S A B S A B L M R T 0 A T 0 A T 0 A T 0 U N Y 0 C P 0 C P 0 C P 0 C p T P M(*)

E R I U RX 5 1 1 AO

~4 NOR 1 1 1 SRO-I I/C I 46 1 48 5 4 0

SRO-U MAJ 9 6 6 3 2 0

TS 0 0 AX 2 1 1 RO 0 NOR 17 15 4 ~

1 SAO-I 34 23 IIC I 35 10 4

~7  ;

68 48 SRO-U 6 2 MAJ 9 6 3 0

TS 25 4 3 2 AX 7 1 1 RO 0 NOR 2 1 2 \

1 SAO-I 13 IIC 38 23 7 4

~8 5 SRO-U 2 MAJ 9 6 6 3 0

TS 14 2 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. AOs must serve in both the "at-the-controls (ATC)"

and "ba 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 (I/C) malfunctions and one major transient, in the ATC

~osition. If an Instant SRO additionally serves in the BOP position, one IIC malfunction can be credited oward the two IIC malfunctions required for the ATC position.

2. Aeactivi~ 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. P Reactivity 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 level in the right-hand columns.

ES-301, Page 26 of 27

ES-301 Transient and Event Checklist Form ES-301-5 CREWE Facility: Quad Cities Date of Exam: 05/31/11 Operating Test Number: ILT 09-1 A E Scenarios

{ ,:. , ..

P V 1 2 <3 4 P E T M L N CREW CREW CREW , CREW 0 I I T POSITION POSITION i P OSITION POSITION T N C A I A T S A B S A B S A B -.S A B L M N Y R T 0 R T 0 R T b R T 0 U T P 0 C P 0 C P '0 C P 0 C P M(*)

E R I U RX 2 1 1 RO

~5 NOR 1 1 1 SRO-I 4 IIC 34 46 4 0

SRO-U MAJ 6 9 2 2 010 "

TS 0 0 RX 7 1 1 RO 0 NOR 12 2 1 SRO-I 34

, i IIC 38 5 4

~9 5 SRO-U 6 2 MAJ 9 2 0

TS 45 2 2 w

S RX U

R NOR 0

G I/G A MAJ T

E TS i i

Instructions:

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

and "ba ance-of-f'ant (8 P)" positions. Instant SROs must serve in both the SRO and the ATC positions, including at leas two instrument or component (IIC) malfunctions and one major transient, in the ATC

~osition. 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 .

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 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 mimmum requirements specified for the applicant's license level in the right-hand columns.

ES-301 , Page 26 of 27

ES-301 Transient and Event Checklist Form ES-301-5 CREWF Facility: Quad Cities Date of Exam: 05/31/11 Operating Test Number: ILT 09-1 A E Scenarios P V 1 2 3 4 T M P

L E

N C~EW CREW

,, CREW CREW 0 I I T POSITION POSITION POSITION POSITION T N C A I A T 's A B S A B S A B S A B L M N Y R T 0 'R T -0 R T 0 R T 0 U T P 0 C P 0 C P 0 C P 0 C P M(*)

E R I U RX 2 1 1 RO

~6 NOR 1 1 1 SRO-I IIC 35 23 4 4 0

SRO-U MAJ 6 6 2 2 010 TS 0 0 RX 5 1 1 RO 0 NOR , 2 1 1 SRO-I 13 I/C 48 5 4

~10 5 SRO-U 2 MAJ 6 6 2 0 ,

TS ~ 14 2 2 S RX U

R NOR 0

G I/C ,

A MAJ ,

T E TS ,

Instructions:

1. Check the 19licant level and enter the operating test number and Form ES-D-1 event numbers for each event tyrce; are not a~licable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "ba ance-of-plant (B 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

~osition. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited oward the two IIC malfunctions required for the ATC position.

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 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 level in the right-hand columns.

ES-301, Page 26 of 27

ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: Quad Cities Date of Exam: 05/31/2011 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 4 3 3 3 20 3 4 7 Emergency &

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

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

3. Generic Knowledge and Abilities 10 7 Categories 2 3 3 2 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the AO and SAO-only outlines (i.e., except for one category in Tier 3 of the SAO-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 NAC revisions . The final AO exam must total 75 pOints and the SAO-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. Aefer 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 (IA) of 2.5 or higher shall be selected.

Use the AO and SAO ratings for the AO 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 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) lor 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 KlAs that are linked to 10 CFA 55.43.

ES-401, Page 16 of 33

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

KKK A A G 2 3 2 KIA Topic(s) IR #

Partial or Complete Loss of Forced o Nuclear boiler inslf\Jmenlation system 3.1 Flow Circulation 11 & 4 7 Partial or Complete Loss of AC I 6 o Manual and auto bus transfer 3.3 Partial or Total Loss of DC Pwr 16 o 3.1 Main Turbine Generator Trip I 3 o Pressure effects on reactor power 4.0 3 .8 6 Control Room Abandonment 17 o 3.3 6

18 Partial or Total Loss of CCW 18 o 3.3 9 Partial or Total Loss of Ins!. Air 18 o air system supply: Plant-Specific 3.3 1 Loss of Shutdown Cooling I 4 o '1RIHRlshutdOlNn cooling 3.6 3

Refueling Acc I 8 o associated with fuel handling equipment 3.4 2

High Drywell Pressure 15 ISllpplre,,'ion poOl spray: Plant-Specific 3.8 3

High Reactor Pressure I 3 o 4.4 5

r to interpret control room indications to verify the status and Suppression Pool High Water Temp.

of a system, and understand how operator actions and 4 .2 affect plant and system conditions.

3.4 Low SuppreSSion Pool Wtr LviI 5 o 3.5 5

o depressurization system actuation 3.9 SCRAM Condition Present and 3.8 o of the general public 4.2 2

U4', '~;no'e(jgeof how abnormal operating procedures are used in IGOlnIU"GIKm wilh EOPs.

3.8 outside the generator capability curve 3 .5 3 4 4 3 20 ES-401, Page 17 of 33

ES-401 3 Form ES-401-1 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

KKK A A G ElAPE 1# / Name / Safety Function 2 3 2 KIA Topic(s) IR 1#

,,'),u,rrn') Loss of Main Condenser Vac / 3 o IC<>nde"ser vacuum/absolute pressure 2.9 1

High Reactor Pressure / 3 o 112!~S()08 High Reactor Water Level / 2 o 112!35C)09 Low Reactor Water Level / 2 o 2.7 4

3.2 3.4 13 High Suppression Pool Temp. / 5 o 2.9 4

14 Inadvertent Reactivity Addition / 1 0 Incomplete SCRAM / 1 0 17 High Off-site Release Rate /9 0 01 . of the purpose and functioo of major sys tem Il2g'S0:W Inadvertent Cont. Isolation / S & 7 4.1 28 and controls.

1129'50:~2 Loss of CRD Pumps / 1 0 pressure 3.S 1

1I2g'50:~9 High Suppression Pool Wtr Lvi / S 0 112!~5()32 High Secondary Containment Area 0

/S 112!~5()33 High Secondary Containment Area IIR"rli"tir,n Levels / 9 0 IIL"'-"'" Secondary Containment Ventilation 0 Radiation / 9 112!~5()3S Secondary Containment High 0

IIniff",r"rlti~1 Pressure / 5 112!~5()36 Secondary Containment High

,n",I.Q,ro," Water Level /5 0 IISCIOO()O High CTMT Hydrogen Conc. / S 0 Category Totals : 2 Point Total: 7 ES-401 , Page 18 of 33

ES-401 4 Form ES-401-1 Form ES-401 IR #

RHRlLPCI : Injection Mode 3.5 2.6 4.0 air systems: Plant-Speciflc; Over pressure protection 2 of EOP mitigation strategies. 3.7 3.6 2.8; 5004 Source Range Monitor delector position; Meters and recorders 2 3.2 3.2 I pool level 3.3 operation; RHRlLPCI system pressure: Plant 3.8; 2

3.9 PCIS/Nuclear Steam Supply 3.5 3.1 Reactor Water Level Control 3.8 oxygen content: Mark-I&II; Ventilation 3; 2.7 2 1 AC Electrical Distribution I Un'intelTUDlllOle power supply 3.1 UPS (AC/DC) 4.2 DC Electrical Distribution 3.0 starting of compressor and emergency 3.0 2.9 Component Cooling Water 2.8 (Use 217000 for selection) 2.8 26 ES-401, Page 19 of 33

ES-401-1 5 Form ES-401-1 Form ES-40 1-1 IR #

2.9 o

cooling water systems 3.1 0

measurement 2.6 switch localions 3.0 0

0 0

RHRlLPCI: Torus/Pool Cooling i pool temperature controt 3.9 Primary CTMT and Aux. 0 RHRlLPCI: CTMT Spray Mode 0 2.8 Fuel Pool Cooling/Cleanup cootlng water systems: Plant*Speciflc 2.7 Fuel Handling Equipment 0 Main T urbina Gen. / Aux. 2.9 0

0 0

0 0

3.2 3.3 3.1 0

0 0

ES-401, Page 20 of 33

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

KKK A A G KIA Topic(s) IR #

23 2 Partial or Complete Loss of Forced Flow Circulation / 1 & 4 o

Partial or Complete Loss of AC / 6 o Partial or Total Loss of DC Pwr / 6 4.7 Main Turbine Generator Trip / 3 o o Whether a reactor SCRAM has occurred 4 .6 o

Control Room Abandonment / 7 o Partial or Total Loss of CCW / 8 o Partial or Total Loss of Ins!. Air /8 o to determine operability and/or availability of Loss of Shutdown Cooling /4 4.6 related equipment.

Ability to prioritize and interpret the sign~icance of each Refueling Acc / 8 4.3

'"n'nI"",,""nror alarm.

High Drywell Pressure / 5 o High Reac10r Pressure / 3 o Suppression Pool High Water Temp.

4.0 o

Low Suppression Pool Wtr Lvi / 5 o o core cooling 4 .8 4

o Reactor pressure 4.1 6

o o

o 000 o 4 Group Point Total: 7 ES-401, Page 17 of 33

ES-401 3 Form ES-401-1 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)

KKK A A G ElAPE # / Name / Safety Function 2 3 2 KIA Topic(s) IR #

1129150()2 Loss of Main Condenser Vac / 3 o High Reactor Pressure / 3 o 1129150()8 High Reactor Water Level / 2 o 1129150()9 Low Reactor Water Level / 2 o o High Drywell Pressure / 5 o 2 High Drywell Temperature / 5 0 3 High Suppression Pool Temp. /5 0 4 Inadvertent Reactivity Addition / 1 0 period 3.9 2

5 Incomplete SCRAM / 1 0 7 High Off-site Release Rate / 9 0 Inadvertent Cont. Isolation /5& 7 0 Loss of CRD Pumps / 1 0 High Suppression Pool Wtr Lvi / 5 0 High Secondary Containment Area 0

perature / 5 High Secondary Containment Area 04. of the emergency action level thresholds and 4.6 Levels /9 41 Secondary Containment Ventilation 0

Radiation / 9 0 containment pressure: Plant-Specific 3.9 1

0 0

Category Totals: 0 0 0 0 2 1 Group Point Total: 3 ES-401, Page 18 of 33

ES-401 4 Form ES-401-1 BWR Examination Outline Form ES-401-1 KJA Topic(s) IR #

RHRlLPCI: Injection o Shutdown Cooling Mode o 4.0 o

o o

15004 Source Range Monitor o 15005 APRM / LPRM o o

o PCIS/Nuclear Steam Supply o

4 .3 the operalional impllcallons 01 EOP wamlngs.

Reactor Water Level Control 4.3 o

AC Electrical Distribution o the eHect of maintenance activities , such UPS (AC/DC) power sources. on the slatus 01limiting 4 .2 DC Electrical Distribution o o

o Component Cooling Water o (Use 217000 for selection) o Category TotalS: Point Total: 5 ES-401, Page 19 of 33

ES-401 5 Form ES-401-1 BWR Examination Outline Form ES-401-1 KIA Topic(s) IR #

o o

I room indk:atlons to verify the status of a system, and understand how operator 4.4 aHect plant and syst em conditions.

0 0

0 0

Traversing In-core Probe 0 0

flow: Design-Spec ifiC 2.9 AHA/LPCI: Torus/Pool Cooling Mode 0 that the alarms are consistent with the plant Primary CTMT and Aux. 4.2 AHA/LPCI: CTMT Spray Mode 0 AHR/lPCI : Torus/Pool Spray Mode 0 0

0 o

o o

o o

o o

o o

o o

o ES-401, Page 20 of 33

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 IFacility Name:Quad Cities Date of Exam:9~1/2011 RO SRO-Onlv Category KIA # Topic IR # IR #

!Knowledge of administrative requirements for temporary management directives , such as 2.1. 15 Istanding orders. night orders. operations memos, etc. 2.7 1 2.1. 41 Knowledge of the refueling process. 2.8 1

1. 12.1 . 40 Knowledge of refueling administrative requirements . 3.9 1 Conduct of

,2.1. 20 lAbility to interpret and execute procedure steps. 4.6 1 IOI-'t::1 cuiu" 2.1.

2.1.

,Sub~1 ~

jAbility to analyze the effect of maintenance ac1ivities, such as degraded power sources, 2.2. 36 lon' status of limiting conditions lor operations. 3.1 1 2.2. 37 lAbility to determine operability andlor availability of safety related equipment. 3.6 1 2.2. 40 ,Ability to apply Technical Specifications for a system. 4.7 1 12.

IEquipment 2.2. 14 I of Ihe process for controlling equipment configuration or status. 4.3 1 IControl 2.2.

2.2.

~tlhtnt;:!1

~ ~

IAbili~, use radiation monitoring systems. such as fixed radiation monitors and alarms.

2.3. 05 portable survey instruments, personnel monitoring equipment , etc. 2.9 1

'0 'of radiological safety principles pertaining to licensed operator duties, such as 2.3. 12 ,~, requirements, fuel handling responsibilities, access to locked high* 3.2 1 radiation areas, aligning filters, etc.

'Ability with radiation work. pennit requ irements during normal or abnormal

13. 12.3. 07 "'i'"

3.5 1 IRadiation 12.3. 11 Ability to control radiation releases. 4.3 1 IControl 12.3.

12.3.

Subto@1 3 1 12.4. 14 of general guidelines for EOP usage. 3.8 1 2.4. 11 of abnormal condition procedures. 4.0 1 AbWty i abnormal indications for system operating parameters that are entry

14. 2.4. 04 ,level conditions for emergency and abnormal operating procedures. 4.5 1 IEmergency In, res 2.4. 29 I of the emergency plan. 4.4 1 II Plan 2.4. 25 of fire protection procedures. 3.7 1 2.4.

iSubtotal 3 2 ITier 3 Point Total 10 7 ES-401, Page 26 of 33

Quad Cities 2011 NRC EXAM Scenario 1 Appendix D Scenario Outline Form ES-D-l Facility: Quad Cities Scenario No.: 2011 NRC Scenario 1 Op*Test No.: ILT 09-1 Examiners: Operators:

Initial Conditions:

The plant is operating at 9% power with a startup in progress. The Mode Switch is in RUN.

APRM 4 is out of service and bypassed for repair.

1C RFP is out of service.

Turnover: Continue the Reactor startup per QCGP 1-1.

Event Malf. No. Event Event No. Type* Description 1 None BOP Establish the Dryweilinerting lineup per QCOP N 1600-20 2 None ATC Withdraw control rods to achieve 2-4 Turbine R Bypass Valves open 3 RD02R2627 ATC Stuck rod I raise CRD Drive Pressure C

4 NM08 ATC APRM 5 failS inoperable, but RPS fails to trip TS RP02B&D I 5 RC11 BOP RCIC Leak wlo auto isolation. Crew performs RC13 C QCOA 0201 and QGA 300 to manually isolate the leak. TS 6 RR11A Crew LOCA, restore RPV Water level and respond to M elevated containment pressure and temperature 7 FW04B Crew Loss Feedwater (Degradation of 1B RFP and loss of ED03A M 1A RFP due to loss of Bus 11). Use HPCI to restore and maintain RPV water level.

  • (N)ormal. (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 5 BOP Normal: El Malfunction(s) after EOP (1-2): E7 ATC Reactivity (1 per set): E2 Abnormal Events (2-4): E3, 4, 5 BOP I/C (4 per set): E5 Major Transient(s) IE-Plan entry (1-2): E6 ATC I/C (4 per set): E3& 4 EOPs (1-2): QGA 100/200 and 300 SRO-II/C (4 per set inc 2 as ATC): E3, 4, 5 EOP Contingencies (0-2): None SRO Tech Spec (2 per set): E4& 5 Critical Tasks (2-3): 3 ALL Maior Transients (2 Der set) E6

=

-2

Quad Cities 2011 NRC EXAM Scenario 1

SUMMARY

  • Initial Conditions:

o The plant is operating at 9% power just after the Mode Switch was taken to RUN.

o APRM 4 is out of service and bypassed for repair.

o The 1C Feed Pump is Out-of Service.

  • Event 1: The BOP establishes the Dryweliinerting lineup per QCOP 1600-20.
  • Event 3: During rod withdrawal, one rod will not move from position 00. When the ATC raises CRD drive water pressure, the rod can be withdrawn normally. Drive water pressure should then be returned to normal.
  • Event 5: A steam leak in the RCIC Room results in RCIC Steam Line high DP and High area Temperature alarms, but RCIC fails to isolate as designed. A report from the Reactor Building confirms a steam leak. The BOP will manually isolate the RCIC Steam Lines and the Crew will perform the QCOA 0201-05, Primary System Leaks (Slow Leaks) Outside Primary Containment, and QGA 300. The SRO will address Technical Specifications for inoperable RCIC and inoperable PCIV valves/instrumentation.
  • Event 6: A LOCA inside the Drywell results in a reactor scram and entry into QGA 100 and 200. The crew restores RPV Water Level and controls Drywell Pressure and Temperature with Containment Sprays.
  • Event 7: A loss of Bus 11 deenergizes the 1A RFP. The 1B RFP degrades and cannot maintain RPV Level. Manual initiation of HPCI is necessary for high-pressure injection to restore RPV water Level.
  • Approximate Run Time: 1.5 Hours CRITICAL TASKS:

Critical Task #1: Given a reactor plant with a reactor building area radiation alarm or temperature alarm, isolate all discharges into the area.

Critical Task #2: Given a shutdown reactor with a LOCA in progress, restore and maintain RPV water level with available high pressure systems lAW with QGA 100.

Critical task #3: 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)

-3

.' Quad Cities 2011 NRC EXAM Scenario 2 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2011 NRC Scenario 2 Op-Test No.: ILT 09-1 Examiners: Operators:

Initial Conditions:

The plant is operating at 100% power.

HPCI maintenance complete. Working to restore and test, then exit 14-Day LCO and ATR.

Drywell Spray Valve 23A is inoperable, Day 2 of a 7 -Day LCO.

Turnover: Restore HPCI to its standby lineup. Post Maintenance Surveillance later in shift.

Event Malt. No. Event Event No. Type* Descri ption 1 None BOP Re-pressurize HPCI Steam Lines and restore HPCI N to standby lineup 2 AN09121G12 SRO Toxic Gas Monitor Inoperablity. TS TS (Optional for Surrogate) 3 AIFC103401B ATC CRD FCV Fails High causing a control rod to drift IN.

RD03R C 4 AIPIC1874011 BOP Drywell N2 controller failure C

5 None SRO Torus Water Level PAM Instrument Inoperability TS TS (Optional for Surrogate) 6 DIHS156041A BOP Gland Exhauster trip/start standby LOHS156041A4 C 7 MC08 ATC Emergency Power Reduction of Loss of Main MC15R R Condenser vacuum (Recoverable) 8 RP02 ATC Drywell pressure starts to rise slowly. Manual and RP03 C auto Scram logics fail. ARI Initiation is necessary 9 MS04C Crew LOCA; A Steam line leak in the Drywell results in a M reactor scram and entry into QGA 100 and 200 10 DIHS 11001 S 17B Crew Div 2 Drywell Spray valves fail to open, Emergency M Depressurization per QGA 500-1 when PSP exceeded

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attributes: ES-301-5 Quantitative attributes:

Total Malfunctions (5-8): 8 BOP Normal: E1 Malfunction(s) after EOP (1-2): E10 ATC Reactivity (1 per set): E7 Abnormal Events (2-4): E3, 4,7 BOP I/C (4 per set): E4 It 6 Major Transient(s) IE-Plan entry (1-2): E9 ATC I/C (4 per set): E3 It 8 EOPs (1-2): QGA 2001100 SRO-II/C (4 per set inc 2 as ATC): E3, 4, 6, 8 EOP Contingencies (0-2): E10 SRO Tech Spec (2 per set): E2 It 5 Critical Tasks (2-3): 2 ALL Maior Transients (2 Der set) E9

- 'L

Quad Cities 2011 NRC EXAM Scenario 2

SUMMARY

  • Initial Conditions:

o The plant is operating at 100% power.

o HPCI maintenance complete. Restore HPCI to its standby lineup.

o Drywell Spray Valve MO 1-1001-23A is inoperable, on Day 2 of a 7-Day TLCO.

  • Event 1: The BOP re-pressurizes the HPCI Steam Lines and restores HPCI to its standby lineup per QCOP 2300-01 Step F.5.
  • Event 2: (Optional for Surrogate) The BOP responds to Annunciator 912-1 G-12 CONTROL ROOM STANDBY HVAC SYS. MAJOR TRBL and determines that the Toxic Gas Monitor is inoperable. The SRO refers to Technical Requirements Manual TLCO 3.3.e, Cond A and QCOS 5750-06. If the signal from the faulty monitor is inhibited within 40 minutes, TS 3.7.4 Condition A for inoperable CREV system will not apply.
  • Event 3: The CRD Flow Controller Auto output will fail upscale, which raises Drive Pressure and Cooling Flow. This causes a single control rod to drift INWARD to position 12. The ATC must fully insert the rod per the QCAN and QCOA for Rod Drift. The ATC may also restore CRD parameters to normal by taking the controller to MANUAL per the QCOA for a failed CRD Flow Control valve.
  • 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 Drywell pressure. Without operator action, Drywell pressure will continue to rise and eventually exceed the Drywell High Pressure alarm setpoint.
  • Event 5: (Optional for Surrogate) The IMD Supervisor calls the US to report that an unqualified replacement part was recently used 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: The running Gland Seal Exhauster will trip. The BOP will start the standby Exhauster and adjust Gland Exhaust pressure.
  • Event 7: An air leak will result in lowering Main Condenser Vacuum. The crew performs QOA 3300-02 and Emergency Power Reduction. Prompt action by Equipment Operators to re-fill a loop seal line will stabilize Main Condenser Vacuum.
  • Event 8: Drywell Pressure starts to rise when a LOCA is initiated. The Manual Scram Pushbuttons, the Mode Switch to SHUTDOWN, and Drywell Pressure >2.5 psig will fail to trip RPS. The ATC must perform Alternate Rod Insertion procedures, most likely ARI initiation, to successfully insert all control rods. QCGP 2-3 actions for the Scram Discharge Volume, SRMs and IRMs are different will be different with the failure of RPS to trip.
  • Event 9: A LOCA inside the Drywell results in a reactor scram and entry into QGA 100 and 200. The crew restores RPV Water Level and attempts to control Drywell Pressure and Temperature with Containment Sprays.
  • Event 10: When Division 2 Containment Spray valves cannot be opened, the crew must Blowdown in order to avoid exceeding Pressure Suppression Pressure (PSP).

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.

Critical task #2: When Drywall temperature CANNOT be maintained < 280 F OR Torus pressure CANNOT be maintained < the Pressure Suppression Pressure Limit, (PSP).

INITIATE an Emergency Depressurization.

-3

Quad Cities 2011 NRC EXAM Scenario 3 Appendix D Scenario Outline Form E5-D-1 Facility: Quad Qities Scenario No.: 2011 NRC Scenario 3 Op-Test No.: ILT 09-1 Examiners: Operators:

Initial Conditions:

The plant is operating at 100% power.

Drywell Spray Valve 23A is inoperable.

FWLC Transmitter LT 1-646A is out of service for repair.

TurnovE r: Shift EHC Pum::>s and perform Core Spray MonthlY Test.

Event Malf. No. Event Event No. Type* DescrIPtion 1 CS06 BOP Core Spray Monthly with Min Flow Valve failure TS C

2 DIHS13401A ATC Emergency Power Reductions for loss of FW DIHS13403 R Heating 3 DIHS10202320 ATC Runback Pushbutton and Master Recirc Controller AOFC102622 C Failure during downpower requires manual operation of individual Recirc Controllers 4 SER0698 SRO Target Rock Relief bellows failure TS TS S RR1SA ATC A 2 nd FWLC Transmitter fails which shifts Reg valves RR1SB C to manual operation during power operation and QGA 100 and 300 actions.

6 CR01 Crew Fuel failure due to loss of FW Heating begins.

HP12 & 13 M 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.

7 CR02 Crew When the Torus Area also exceeds Max Safe M Temperature or Radiation, the crew will Emergency Depressurize per QGA SOO-1

. (N)ormal. (R)eactivity * (I)nstrument, (C)omponent. (M)ajor ES-3Q1-4 QuantitS!tive anributes: ES-301-S Quantitative attributes:

Total Malfunctions (S-8): 7 BOP Normal: None Malfunction(s) after EOP (1-2): E6 ATC Reactivity (1 per set): E2 Abnormal Events (2-4): E1, 3 & 5 BOP IIC (4 per set): E1 Major Transient(s) IE-Plan entry (1-2): E6 ATC IIC (4 per set): E3 & 5 EOPs (1-2): QGA 300, QGA 100 SRO-II/C (4 per set inc 2 as ATC): E1, 3 & 5 EOP Contingencies (0-2): E7 SRO Tech Spec (2 per set): E1 & 4 Critical Tasks (2-3): 3 ALL Maior Transients (2 oer set) E6

- 2

Quad Cities 2011 NRC EXAM Scenario 3

SUMMARY

  • Initial Conditions:

o The plant is operating at 100 power.

o Drywell Spray Valve 23A is inoperable.

  • Event 1: The BOP performs QCOS 1400-01, Quarterly Core Spray System Flow Rate Test

("A" Pump only). When the Minimum Flow valve fails to auto close, the BOP will stop the Core Spray Pump and secure the system. The SRO will address Tech Specs for one Core Spray System inoperable, 3.5.1 Condition B.

  • Event 2: The 1A Feedwater Heater level switch fails, resulting in the isolation of a Feedwater Heater String. The Crew responds per QCOA 3500-01, "Feedwater Temperature Reduction with the Main Turbine Online". The crew performs QCOA 0400-01, "Reactivity Addition", by performing an Emergency Power Reduction. When the level switch is restored, the reactivity addition is terminated after closure of the LP Heater String Bypass Valve.
  • Event 3: During Emergency Power Reduction, neither the Runback Pushbutton nor the Master Recirc Controller will respond. The ATC must diagnose this problem and take manual control of individual Recirc Controllers.
  • Event 5: When a second FWLC transmitter fails, the reg valves shift to manual. The ATC must control level manually during power operations, a scram, and QGA 100 and 300 performance.
  • Event 6: Due to the loss of FW Heating, a fuel element failure begins. The crew will respond to High Offgas radiation per QCOA 1700-04. When SJAE Rad levels cannot be maintained

< High-High alarm, the crew will isolate Offgas, Scram, and close the MSIVs/Drains. A leak in the HPCI room then begins that requires the crew to enter QGA 300. The crew will attempt to isolate the leak, but the leak cannot be isolated.

  • Event 7: 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: Given an operating reactor plant and a loss of Feedwater heating, perform actions to control reactor power and reelose the MO 1-3403, LP HTR STRING BYP VLV, to terminate the reactivity addition.

Critical Task #2: 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 #3: 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).

-3

Quad Cities 2011 NRC EXAM Scenario 4 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: 2011 NRC Scenario 4 Op-Test No.: ILT 09-1 Examiners: Operators:

Initial Condition§:

The plant is operating at 75% power.

The 1A EHC Pump is out of Service.

1B Service Water Pump is out of service.

Drywell Spray Valve 23A is inoperable.

Turnover: Swap Condensate pumps Event Malf. No. Event Event No. Type* Description 1 None BOP Start the 1A Condensate pump and secure the 1B N Condensate pump 2 ED01C BOP SWitchyard Breaker 4-6 Trip and restoration C

3 SW02A BOP Service Water Pump degradation C

4 SER0382 ATC 1A Recirc High Vibration Alarm, Seal Leak, RR06A C Shutdown and isolate Recirc Pump. 18 RR07A 5 None ATC Insert Cram Rods for loss of 1A Recirc Pump R

6 RR03A Crew 1B Recirc Pump trips IManual scram. After RPS has RD13A M been tripped, approximately Y2 of the control rods remain withdrawn. (Hydraulic ATWSJ 7 TC05B Crew QGA 101 LevellPower Control. Turbine Bypass M valves become unavailable, requiring manual RPV Pressure control with Relief Valves 8 DIHS11130301 ATC Malfunction after Major: Failure of 1sl SBLC Pump to C start

. (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor ES-301-4 Quantitative attrib!,!tes: ES-~01-~ QUgntit§tive gttributes:

Total Malfunctions (5-8): 6 BOP Normal: E1 Malfunction(s) after EOP (1-2): E7&8 ATC Reactivity (1 per set): E5 Abnormal Events (2-4): E2, 3, & 4 BOP I/C (4 per set): E2 & 3 Major Transient(s) IE-Plan entry (1-2): E6 ATC IIC (4 per set): E4 & 8 EOPs (1-2): QGA 100 SRO-II/C (4 per set inc 2 as ATC): E2,3,4,&8 EOP Contingencies (0-2): E7 SRO Tech Spec (2 per set): E4 Critical Tasks (2-3): 3 ALL Maior Transients (2 oer set) E6

- 2

-, Quad Cities 2011 NRC EXAM Scenario 4

SUMMARY

  • Initial Conditions:

o The plant is operating at 75% power.

o The 1A EHC Pump is out of service.

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

o Drywell Spray Valve 23A is inoperable.

  • Event 1: The BOP starts the 1A Condensate pump and secures the 1B Condensate pump.
  • Event 2: GCB 4-6 is inadvertently tripped open during a Switchyard breaker inspection. The problem is resolved and the US directs the BOP to reclose GCB 4-6 per QCOP 6400-0B.
  • 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 should start the Y2 or the 2A Service Water Pump and secure the 1A pump.
  • Event 4: 1A Recirc Pump Seals fail due to pump vibration. Drywell pressure begins to rise.

The ATC must shutdown the Pump and isolate it. The SRO must address Technical Specifications for Single Loop Operation.

  • Event 6: The 1B Recirc Pump trips. When the second Recirc pump trips, the ATC must manually scram the reactor. Only 1/2 of the withdrawn control rods insert. The crew performs the actions of QGA 100 and 101 for a 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.

  • Event B: When SBLC is initiated for the A TWS, 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 ATWS 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 RPVwater level above the Minimum Steam Cooling RPVWater Level (-166").

-3

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