ML100710109

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2009 Quad Cities Nuclear Power Station Initial Examination Outline Submittal
ML100710109
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 11/30/2009
From:
NRC/RGN-III
To:
Exelon Generation Co
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Download: ML100710109 (22)
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Text

2009 QUAD CITIES NUCLEAR POWER STATION INITIAL EXAMINATION OUTLINE SUBMITTAL

wwwexeloncOTp corn Ex~llln C,c'lleiatlOi" (llillflan)', lee Nuclear Quad Cltle, G~neratllig Station 22710 2u6th Avenue North (ordov;l, Il 61242 SVP-09-051 September 8, 2009 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 November 30, 2009 and December 7, 2009 at Quad Cities Nuclear Power Station.

This submittal includes all appropriate examination standard forms and outlines in accordance with NUREG-1021, "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)-227-4009.

Respectfully Timothy

(

J. Tulon Site Vice President Quad Cities Nuclear Power Station

September 8, 2009 U. S. Nuclear Regulatory Commission Page 2

Enclosures:

(Overnight delivery to Raymond K. Walton, Chief Examiner, NRC Region III)

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 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 Scenario Outlines (4) - Forms ES-D-1 Completed Checklists:

Examination Outline Quality Checklist - Form ES-201-2 Transient and Event Checklist - Form ES-301-5 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 Facility:

(/tl/lb t./icJ' Date of Examination: ///SojbtJ?

Initials Item Task Description a b* c#

1.

W

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

n~ t/ ~

~ V ~

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 T

E

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

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

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~~)

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

S of normal evolutions, instrument and component failures, technical specifications, and major transients.

'1N t...

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

~v.\;J M and mix of applicants in accordance with the expected crew composition and rotation schedule U without compromising exam integrity, and ensure that each applicant can be tested using L L I~

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

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

T 0

R c.

a.

To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

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

rW c.. ~

3.

~~

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

/

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 on the form DtJ

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

(1 ) the tasks are distributed among the topics as specified on the form c.,.. ~~

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

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 subseauent davs. r C {<j{\J
4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam section. D,L G ~~\Al G

E

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. I (., ~vJ N c. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. 1 C- jQV-.vJ E

R d. Check for duplication and overlap among exam sections. I L R\(.w A e. Check the entire exam for balance of coverage. (l ,... L ~\J L

f. Assess whether the exam fits the appropriate job level (RO or SRO) . ,V c... RUw
a. Author

..31Ii//!JIAI.'Ii j i/r..'!Wl,pri~,/t>(aJne./ Signat~7 ~ .

. : n , . . WA. 9JJj~e9

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b. Facility Reviewer (*)  :¥. '1"&,1/ I'L.I:I/ ....--, Qhl OCt k,w1l\Dr-c\ V. \J.,.1lr",.,'1 ~ ~ \, \. (JiJ.'.,-.. 9/1, ,109 1F
c. NRC Chief Examiner (#)
d. NRC Supervisor ) / ;lIhOJ1". P.' /(...-/. ~-....'C :-y - ////iJtJ"1. v

/ ..../ v '-' ."

NOTE: # Independent NRC Reviewer initial items in Column "c"; chief examiner concurrence required.

  • Not applicable for NRC-prepared examination outlines.

ES-201, Page 26 of 28

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  • ES-301 Facility: Quad Cities Examination Level: RO ~ SRO Administrative Topics Outline D

Form ES-301-1 Date of Examination: 11/30/09 Operating Test Number: ILT 08-1 Administrative Topic Type Describe activity to be performed (See Note) Code*

Perform APRM Flow Biased High Flux (Heat Balance)

Calibration Test (Partial for step H.4)

Conduct of Operations D,S KIA 2.1.43 4.1/4.3 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

Operate the Plant Process Computer Conduct of Operations N,S KIA 2.1.19 3.9/3.8 Ability to use plant computers to evaluate system or component status.

Review a Worker Tagout for 2nd Approval Equipment Control D,R KIA 2.2.13 4.1/4.3 Knowledge of tagging and clearance procedures.

Perform Whole Body Frisk KIA 2.3.5 2.9/2.9 Ability to use radiation monitoring Radiation Control N,R 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 (~ 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 Exam ination: 11/30/09 Examination Level: RO 0 SRO ~ Operating Test Number: ILT 08-1 Administrative Topic Type Describe activity to be performed (See Note) Code*

Review QOS 0005-S01 for Start of Daily Refueling Activities Conduct of Operations N,R KIA 2.1.36 SRO 4.1 Knowledge of procedures and lim itations involved in core alterations Use Procedures Related to Shift Staffing Conduct of Operations N,R KIA 2.1.5 SRO 3.9 Ability to use procedures related to shift staffing, such as minimum crew compliment, overtime limitations, etc..

Determine On Line Risk KIA 2.2.17 SRO 3.8 Knowledge of the process for Equipment Control N,R managing maintenance activities during power operations, such as risk assessments, work prioritization and coordination with transmission syStem operator.

Perform Whole Body Frisk KIA 2.3.5 2.9/2.9 Ability to use radiation monitoring Radiation Control N,R systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Classify Event and Determine Protective Action Recommendations (PARS)

Emergency Procedures/Plan D,S KIA 2.4.44 SRO 4.4 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 (s 3 for ROs; S 4 for SROs & RO retakes)

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

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

  • ES 301, Page 22 of 27

ES-301 Control RoomJIn-Plant Systems Outline Form ES-301-2

  • Facility: Quad Cities Exam Level: RO ~ SRO-I 0 SRO-U 0 Date of Examination: 11/30/09 Operating Test Number: ILT 08-1 Control Room SystemsO (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function

a. Reactor Recirculation, 202001 A4.01 3.7/3.7 D,S 1 Startup Reactor Recirculation Pump to Exit SLO
b. RWCU, 204000 A4.03 3.2/3.1 N, L, S 2 RWCU System Coolant Reiection
c. Main Steam, 239001 A4.01 4.2/4.0 D,L,S 3 Pressurize the Main Steam Lines
d. RCIC, 217000 A4.07 3.9/3.8 Control Reactor Pressure With RCIC A, M, L,S 4
e. PCIS/NSSS 223002 A4.03 3.6/3.5 D,L,S 5 Bypass All Group 1 isolation siQnals
f. AC Electrical, 262001 A4.01 3.4/3.7 Energize Bus 14-1 with Cross-tie A,D,S 6 Failure and subsequent SBO Startup
g. RPS, 212000 A4.02 3.6/3.7 Complete A Manual Scram Functional Test A,M,S 7
h. Plant Ventilation, 288000 A4.01 3.1/2.9 N,S 9 Unisolate and Start The Reactor BldQ Ventilation System C

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

i. Scram Condition Present and Reactor Power Above APRM Downscale or D,E,L,R 1 Unknown: CRD Hydraulic System 295037 EA1.05 3.9/4.0 Depressurize the Scram Air Header
j. Emergency Generators 264000 2.1.23 4.3/4.4 A,D,E,R 6 Perform an Emergency Diesel Shutdown Following a Failure of the Enaine Driven Cooling Water Pump
k. Fire Protection System, 286000 2.1.30 4.4/4.0 0 8 Locally Startup the 1/2A Fire Diesel

@ 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 4-6/ 4-6 / 2-3 (C)ontrol room (D)irect from bank ~9/ ~8 / ~ 4 (E)mergency or abnormal in-plant ~1 / ~1 / ~1 (EN)gineered safety feature - / - / ~ 1 (control room system (L)ow-Power / Shutdown ~1 I ~1 / ~1 (N)ew or (M)odified from bank including 1(A) ~2/ ~2 / ~1
    • (P)revious 2 exams (R)CA (S)imulator ES-301, Page 23 of 27

~31

~1 /

~3 / ~ 2 (randomly selected)

~1 I ~1

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2

  • Facility: Quad Cities Exam Level: RO D SRO-I ~ SRO-U D Date of Examination: 11/30/09 Operating Test Number: ILT 08-1 Control Room SystemsO (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System 1 JPM Title Type Code*

Function a.

b. RWCU, 204000 A4.033.2/3.1 N,L,S 2 RWCU System Coolant Reiection
c. Main Steam, 239001 A4.01 4.2/4.0 D, L, S 3 Pressurize the Main Steam Lines
d. RCIC, 217000 A4.07 3.9/3.8 Control Reactor Pressure With RCIC A, M, L,S 4
e. PCIS/NSSS 223002 A4.03 3.6/3.5 D, L, S 5 Bypass All Group 1 isolation signals
f. AC Electrical, 262001 A4.01 3.4/3.7 Energize Bus 14-1 with Cross-tie A,D,S 6 Failure and subsequent SBO Startup
g. RPS, 212000 A4.02 3.6/3.7 Complete A Manual Scram Functional Test A,M,S 7
h. Plant Ventilation, 288000 A4.01 3.1/2.9 N,S 9 Unisolate and Start The Reactor Blda Ventilation System
  • In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Scram Condition Present and Reactor Power Above APRM Downscale or Unknown: CRD Hydraulic System 295037 EA1.05 3.9/4.0 Depressurize the Scram Air Header
j. Emergency Generators 264000 2.1.23 4.3/4.4 D,E,L,R A,D,E,R 1

6 Perform an Emergency Diesel Shutdown Following a Failure of the Enaine Driven Coolina Water Pump

k. Fire Protection System, 2860002.1.304.4/4.0 D 8 Locally Startup the 1/2A Fire Diesel

@ 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-I 1 SRO-U (A)lternate path 4-61 4-6 1 2-3 (C)ontrol room (D)irect from bank ~91 ~8 1 ~4 (E)mergency or abnormal in-plant ~1 1 ~1 1 ~1 (EN)gineered safety feature - 1 - 1 ~ 1 (control room system (L)ow-Power 1 Shutdown ~11 ~1 1 ~1 (N)ew or (M)odified from bank including 1(A) ~21 ~2 1 ~1 (P)revious 2 exams ~31 ~3 1 ~ 2 (randomly selected)
  • (R)CA (S)imulator ES-301, Page 23 of 27

~ 1 1 ~1 1 ~ 1

  • ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: Quad Cities Date of Exam: 11/30109 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 4 4 3 3 3 3 20 3 4 7 Emergency &

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

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

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 3 2 3 2 2 2 1 Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRQ-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 must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KlAs.

8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRo-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

ES-401, Page 17 of 34

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

K K K A A IR ElAPE # / Name / Safety Function G KIA Topic(s) #

1 2 3 1 2

~95001 Partial or Complete Loss of Forced 0 Thermal limits 3.6 1

~ore Flow Circulation I 1 & 4 3 0

1295003 Partial or Complete Loss of AC 16 Station batteries 3.2 1 1

0

~95004 Partial or Total Loss of DC Pwr 16 Reactor SCRAM: Plant-Specific 3.1 1 3

0

~95005 Main Turbine Generator Trip / 3 Main generator controls 2.7 1 4

0

~95006 SCRAM I 1 Reactor water level 4.0 1 3

01.

~95016 Control Room Abandonment I 7 Ability to interpret and execute procedure steps. 4.6 1 20 0

~95018 Partial or Total Loss of CCW 18 Effects on component/system operations 3.5 1 1

0 1295019 Partial or Total Loss of Ins!. Air I 8 Component cooling water 2.9 1 2

0

~95021 Loss of Shutdown Cooling / 4 Raising reactor water level 3.3 1 1

  • ~95023 Refueling Acc I 8 Q95024 High Drywell Pressure I 5 295025 High Reactor Pressure / 3 0

6 0

2 04.

01 Neutron monitoring Drywell temperature Knowledge of EOP entry condillons and immediate action steps.

3.3 3.9 4.6 1

1 1

295026 Suppression Pool High Water 0 Steam condensation 3.5 1 Temp./5 2

~95027 High Containment Temperature 15 Mark 3 Containment nol app!icablelo Quad dlie. 0 0

295028 High Drywell Temperature / 5 Drywell spray: Mark-I&II 3.7 1 1

0 295030 Low Suppression Pool Wtr LviI 5 Pump NPSH 3.5 1 2

0 295031 Reactor Low Water Levell 2 Low pressure coolant injection (RHR) 4.2 1 5

295037 SCRAM Condition Present and 0

Reactor Power Above APRM Downscale or Maintaining heal sinks external to the containment 3.8 1 6

Unknown /1 0

1295038 High Oft-site Release Rate I 9 Meteorological instrumentation 3.0 1 2

0 1600000 Plant Fire On Site I 8 Fire alarm 2.8 1 3

700000 Generator Voltage and Electric Grid 04. Knowledge of how abnormal operating procedures are used In conjunction with EOPs.

3.8 1 Disturbances / 6 08 KIA Category Totals: 4 4 3 3 3 3 Group Point Total: 20

ES-401 3 Form ES-401-1

1 K

2 K

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

A 1

A 2

G KiA Topic(s)

Form ES-401-1 IR 0

1295007 High Reactor Pressure / 3 0 0

1295008 High Reactor Water Level / 2 Feedwater system 3.5 1 8

0 295009 Low Reactor Water Levell 2 Steam flow/feedflow mismatch 3.6 1 2

1295010 High Drywell Pressure I 5 0

~95011 High Containment Temp / 5 Matk 3 CclnIeInlllllllt not _IClIIlle to Quad Chles 0 1295012 High Drywell Tem perature / 5 0

01. Ability to locate and operate components. induding local 1295013 High Suppression Pool Temp./5 4.4 1 30 c:onlrols 1295014 Inadvertent Reactivity Addition / 1 0
  • 1295015 Incomplete SCRAM 11 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 0

2 Protection of Ihe general public 3.8 0

1 0

0 295022 Loss of CRD Pumps / 1 Reactor water level 2.5 1 4

295029 High Suppression Pool Wtr Lvi / 5 0 295032 High Secondary Containment Area 0 Emergency/normal depressurization 3.5 1 Temperature / 5 1 1295033 High Secondary Containment Area 0 Area radiation monitoring system 3.9 1 Radiation Levels / 9 1 1295034 Secondary Containment Ventilation 0

High Radiation I 9

~95035 Secondary Containment High 0

Differential Pressure / 5 1295036 Secondary Containment High 0

Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. /5 0

  • KiA Category Totals: 1 1 1 2 1 1 Group Point Total:

ES-401, Page 19 of 34 7

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A #.

iSystem # / Name G KIA Topic(s) IR 1 2 3 4 5 6 1 2 3 4 0

b03000 RHRlLPCI: Injection Mode Emergency generator' 3.7 1 3

0

~05000 Shutdown Cooling SOC/RHR pumplsyslem discharge pressure 2.8 1 9

0 1 1206000 HPCI Inadequate system 1I0w: BWR*2. 3. 4 3.3 6

1207000 Isolation (Emergency)

HlA, Sy$~ not utJIized at Quad Cltillll 0

!condenser 0

1209001 LPCS Syslem pressure 3.5 1 3

~9002 HPCS NlA. Syslem not utIlzed at Quad C1II8t 0 0

~11000 SLC Explosive valves firing circuit status 4.1 1 3

0 04. Provide manual SCRAM signal(s) : Abilily to verify that the 4.6; 1212000 RPS alarms are consistenl with the planl condilions.

2 1 46 4.2 0 0 3.6; 12150031RM Reactor manual canlrol ; lAM inop condition 2 2 2 3.5

01. Ability to perform speciric system and inlegrated plant b15004 Source Range Monitor procedures during all modes of plant operation.

4.3 1 23 0

2.6 1 215005 APRM / LPRM APRM channels 2

0 217000 RCIC Prevenl over lilling reactor vessel 3.3 1 2

0 218000 ADS ADS logic operation 3.8 1 1

223002 PCIS/Nuclear Steam Supply 0 Conlainmenl inslrumentation 3.0 1 Shutoff 5 0

?39002 SRVs Reaelor pressure 3.8 1 4

0 1259002 Reactor Water Level Control Loss of controller signal oulput 3.3 1 6

0 1261000 SGTS System flow 3.2 1 1

0 All breakers and disconnects (including available slNilch 1262001 AC Electrical Distribution 3.4 1 1 yard): Planl-Specific D.C eleclrical power: Knowledge of local auxiliary operalor 0 04. 2.8; 1262002 UPS (AC/DC) lasks during an emergency and the resultant operational 2 2 35 effects. 3.8 0

1263000 DC Electrical Distribution Bauery charger and oauery 3.2 1 2

0 0 A.C electrical distribution; Indicating lights. meters, and 3.9; 1264000 EDGs recorders 2

2 3 3.4 0

1300000 Instrument Air Systems having pneumatic valves and controls 3.3 1 2

0 1400000 Component Cooling Water Automatic start of standby pump 3.4 1 1

0 (217000) SSMP Flow Indication 3.1 1 2

.T.

2 1 2 2 2 3 2 3 3 3 3 Group Point Total: 26 ES-401, Page 20 of 34

~------- - - -

ES-401-1 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 21Group 2 (RO)

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

1 2 3 4 5 6 1 2 3 4 0

1201001 CRD Hydraulic Component cooling water systems: Plant-Specific 2.8 1 6

1201002 RMCS 0 1201003 Control Rod and Drive Mechanism 0 201004 RSCS lIlIA. SysIam not utilized al Quad CIties 0 201005 ACIS NlA, Sy$lem not utilized al Quad CllIes 0 0

1201006 RWM Aeaclor manual conlrol system: P~Spec(Not*BWA6) 3.2 1 1

~02001 Recirculation 0 0

1202002 Recirculation Flow Control Reactor/turbine pressure regulation system 2.9 1 4

0 1204000 RWCU Reactor waler temperature 2.8 1 5

1214000 RPIS 0 1215001 Traversing In-core Probe 0 1215002 RBM 0 1216000 Nuclear Boiler Insl 0

~19000 RHR/LPCI: Torus/Pool Cooling 0 Pump motor cooling: Plant-Specific 2.7 1 1M0de 6 1223001 Primary CTMT and Aux. 0

  • 1226001 RHA/LPCI: CTMT Spray Mode 1230000 RHA/LPCI: Torus/Pool Spray Mode 1233000 Fuel Pool Cooling/Cleanup 1234000 Fuel Handling Equipment 0

Air operated MSIV's 2.8 0

0 0

0 1

1239001 Main and Reheat Steam 6

1239003 MSIV Leakage Control NlA, Sy$lem not utilized al Quad CIIies 0 0

1241000 ReactorlTurbine Pressure Regulator COI"K1enservacuum 3.4 1 5

1245000 Main Turbine Gen. / Aux. 0 0

1256000 Reactor Condensate System waler quanry 2.7 1 8

0 1 1259001 Reactor Feedwater Loss of condensate pump(s) 3.6 3

1268000 Radwaste 0 12710000ffgas 0 0

1272000 Radiation Monitoring Main steamline radiation monitors 2.5 1 1

1286000 Fire Protection 0 1288000 Plant Ventilation 0 0

1290001 Secondary CTMT Reactor building area temperatures: Plant-Specific 3.3 1 2

1290003 Control Room HVAC 0

04. Knowledge of EOP mltigallon slralegies. 3.7 1 1290002 Reactor Vessel Internals 06 0

~A Category Totals: 1 1 2 1 1 1 1 1 1 1 1 Group Point Total: 12 ES-401, Page 22 of 34

ES-401 2 Form ES-401-1

  • ES-401 E/APE # / Name / Safety Function 1295001 Partial or Complete Loss of Forced

!core Flow Circulation / 1 & 4 K

1 K

2 K

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

A 1

A 2

G 04.

04 KIA Topic(s)

Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

Form ES-401-1 IR 4.7 1

295003 Partial or Complete Loss of AC / 6 0 Ability to evaluate plant performance and make

01. operational judgments based on operating 1295004 Partial or Total Loss of DC Pwr / 6 4.7 1 07 characteristics, reactor behavior, and instrument interoretation.

1295005 Main Turbine Generator Trip / 3 0 295006 SCRAM / 1 0 0 Suppression chamber pressure 3.4 1

295016 Control Room Abandonment / 7 7

04.

295018 Partial or Total Loss of CCW / 8 Knowledge of abnormal condition procedures, 4.2 1 11 1295019 Partial or Total Loss of Inst. Air / 8 0 1295021 Loss of Shutdown Cooling / 4 0

  • 1295023 Refueling Acc / 8 295024 High Drywell Pressure / 5 295025 High Reactor Pressure / 3 0

0 0

1295026 Suppression Pool High Water Temp, 0

5 1295027 High Containment Temperature /5 Mark 3 Containment not applicable to Quad Cities 0 0 4,2 1295028 High Drywell Temperature / 5 Drywell pressure 1 4

1295030 Low Suppression Pool Wtr Lvi / 5 0 1295031 Reactor Low Water Level / 2 0 1295037 SCRAM Condition Presenl land Reactor Power Above APRM 0 Downscale or Unknown / 1 0

295038 High Off-site Release Rate / 9 Off-site 4.3 1 1

Knowledge of events related to system operation/status

04. that must be reported to internal organizations or 4,1 1600000 Plant Fire On Site / 8 1 30 external agencies, such as the State, the NRC, or the transmissiQn svstem ooerator.

700000 Generator Voltage and Electric Grid 0

Disturbances / 6 0 0 0 0 3 4 Group Point Total: 7

ES-401 3 Form ES-401-1

1 K

2 K

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

A 1

A 2

G KIA Topic(s)

Form ES-401-1 IR 0

295007 High Reactor Pressure I 3 0

295008 High Reactor Water Levell 2 0 295009 Low Reactor Water Levell 2 0 295010 High Drywell Pressure I 5 0

~95011 High Containment Temp /5 Mer1< 3 Containment nol applicable to Quad Ciliee a 295012 High Drywell Temperature 15 0

.295013 High Suppression Pool Temp./5 0 0 1 295014 Inadvertent Reactivity Addition 11 Reactor power 4.2 1

  • 295015 Incomplete SCRAM 11 295017 High Off-site Release Rate I 9 295020 Inadvertent Cont. Isolation 15 & 7 0

0 0

295022 Loss of CRD Pumps 11 0

04. Ability to verily system alarm selpoints and operate contrors 295029 High Suppression Pool Wtr Lvii 5 4.0 1 50 identified in the alarm response manual.

295032 High Secondary Containment Area 0

Temperature 15 295033 High Secondary Containment Area 0

Radiation Levels / 9 295034 Secondary Containment Ventilation 0

High Radiation I 9 1295035 Secondary Containment High 0

Differential Pressure I 5 1295036 Secondary Containment High 0

!sumpiArea Water Level/5 0

~OOOOO High CTMT Hydrogen Conc. I 5 Hydrogen monitoring system availability 35 1 1

KIA Category Totals: 0 0 0 0 2 1 Group Point Total: 3 ES-401, Page 19 of 34

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (SRO)

K K K K K K A A A A System # / Name G KIA Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 203000 RHA/LPCI: Injection 0 205000 Shutdown Cooling Mode 0 Ability 10 recognize abnormal ind)eations for system 04.

206000 HPCI operating parameters thai are enlry-Ievel conditions lor 4.7 1 04 emergency and abnormal operating procedures.

207000 Isolation (Emergency)

NtA. Syslem not utilized 81 Quad Cities 0 Condenser 209001 LPCS 0 209002 HPCS NtA. System not utilized at Quad ClUes 0 211000 SLC 0 1212000 RPS 0 12150031RM 0 1215004 Source Range Monitor 0 1215005 APRM / LPRM 0 01-1217000 RCIC Ability to explain and apply system limits and precautions 4.0 1 32 1218000 ADS 0 1 Loss or air supply 10 ADS valves: Plant-Specific 3.6 3

223002 PC IS/Nuclear Steam Supply 0

Shutoff 239002 SRVs 0 259002 Reactor Water Level Control 0 261000 SGTS 0 262001 AC Electrical Distribution 0 Types or loads thai, if deenergized, would degrade or hinde plant operation 4.2 1 4

262002 UPS (AC/DC) 0 1263000 DC Electrical Distribution 0 1264000 EDGs 0

~00000 Instrument Air

04. Ability 10 prioritize and interpret the significance of each annunciator or alarm.

4.3 1 45 1400000 Component Cooling Water 0

  • KIA Category Totals: 0 0 0 0 0 0 0 2 0 0 3 Group Point Total:

ES-401, Page 20 of 34 0

5

ES-401 5 Form ES-401-1

~01OO2 RMCS K K K K K K 1 2 3 4 5 6 A

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

A 2

A 3

A 4

G KIA Topic(s)

Form ES-401-1 IR #

a a

~01 003 Control Rod and Drive Mechanism a 201004RSCS N/A, System not ulII29d at Quad Olles 0 201005 RCIS NlA. Systam not ullllzad at Quad ClIiaS 0 201006 RWM a 0

02001 Recirculation Inadvertent recirculation flow decrease 3.8 1 6

~02oo2 Recirculation Flow Control a 1204000 RWCU a

~14oo0 RPIS a 1215001 Traversing In-core Probe a 1215002 RBM a 1216000 Nuclear Boiler Insl. a

~19OO0 RHR/LPCI: Torus/Pool Cooling Mode a 1223001 Primary CTMT and Aux. a

  • 1226001 RHR/LPCI: CTMT Spray Mode

~3OOOO RHR/LPCI: Torus/PoOl Spray Mode

~33ooo Fuel Pool Cooling/Cleanup 1234000 Fuel Handling Equipment 1239001 Main and Reheat Steam a

a a

a a

~39003 MSIV Leakage Control NlA. System not uWIzed at Quad ClIiaS 0 1241000 ReactorfTurbine Pressure RegUlator a 1245000 Main Turbine Gen. / Aux. a

~56000 Reactor Condensate a 1:>59001 Reactor Feedwater a

268000 Radwaste 0
>71000 Offgas 0
272000 Radiation Monitoring 0 0

286000 Fire Protection Fire protection diesellrips 3.3 1 5

288000 Plant Ventilation a

>90001 Secondary CTMT a Ability to interpret control room indications to verHy the status 02.

290003 Control Room HVAC and operation af a system, and understand how operator 4,4 1 44 .fictions and directives affecl plant and system conditions 90002 Reactor Vessel Internais 0 0

KIA Category Totals: a a a a a a 0 2 a a 1 Group Point Total: 3 ES-401, Page 21 of 34

ES-401 Generic Knowledge and Abilities Outline JTier 3~ Form ES-401-3

  • IFacility Name:

Category K/A#

Date of Exam:

2.1. 04 Topic Knowledge of individual licensed operator responsibilities related to shift stalling, such as medical requirements, "ncrs~o" operation, maintenance of active license status, 10CFR55. etc, IR 3.3 RO 1

SRO -OnIV IR #

I 2.1. 18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. 3.6 1

1. 2.1. 25 Ability to interpret reference materials, such as graphs, curves, lables, etc. 4.2 1 Conduct of 2.1. 34 Knowledge of primary and secondary plant chemistry limits. 3.5 1 Operations 2.1.

2.1.

Subtotal 2 2 Ability to determine the expeeled plant configuration using design and configuration 2.2. 15 control documentation, such as drawings, line-ups, tag*outs, etc. 3.9 1 Knowledge of the bases in Technical Specifications for limiting conditions for operations 2.2. 25 and safety limits 3.2 1

2. 2.2. 37 Ability to determine operability and/or availability of safety related equipment. 3.6 1 Equipment 2.2. 14 Knowledge 01 the process lor conlroliing equipment configuration or slalus, 4.3 1 Control 2.2. 38 Knowledge 01 conditions and limitations in the facility license. 4.5 1
  • 2.2.

Subtotal 2.3. 11 2.3. 13 Ability to control radiation releases.

Knowledge or radiologIcal safety procedures pertaining to licensed operator dulles, such ns response to radiation monitor alarms, containment entry requirements, luel handling r.onnnojhiIlU_ .,.,..,0. In I""".... hlnh.""fl.Hnn ArA.O "Innlnn lill."" ..t~

3.8 3.4 3

1 1

2

3. 2.3. 04 Knowledge of radiation exposure limits under normal or emergency conditions. 3.7 1 Radiation Knowledge 01 radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3. 15 portable survey instruments, personnel monitoring equipment, etc. 3.1 1 Control 2.3.

2.3.

Subtotal 2 2 2.4. 32 Knowledge of operator response to ioss 01 ali annunciators. 3.6 1 Knowledge of the bases for prioritizing emergency procedure implementalion during 2.4. 23 emergency operations, 3.4 1

4. 2.4. 42 Knowledge of emergency response facilities. 2.6 1 Emergency Knowleoge of Eul" implementatIon hierarChy ano coordinaUon With other support Procedures 2.4. 16 procedures or guideiines such as, operating procedures, abnormal operating procedures, 4.4 1

, Plan n.< ... ....,..; ... ""'nt"'" " ,.. ............... "l..l ......

2.4.

2.4.

  • Subtotal Tier 3 Point Total ES-401, Page 27 of 34 3

10 1

7

Quad Cities NRC EXAM Scenario 1 Appendix D Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: NRC Scenario 1 Op-Test No.: ILT 08-1 Examiners: Operators:

Initial Conditions:

100% power Turnover: Perform QCOS 1400-01, "Quarterly Core Spray System Flow Rate Test", for the 1A Core Spray Pump.

Event Malt. No. Event Event No. Type* Description 1 None BOP QCOS 1400-01, Quarterly Core Spray System Flow N Rate Test ("A" Pump only) 2 RD04R ATC/SRO Control rod drift out (TS)

I/C 3 None ATC "B" RFP steam leak resulting in Emergency Power R Reduction to.s.... 9.8 Mlb/hr Feedwater flow.

4 None BOP/SRO T-12 Oil leak Itransfer Aux power to T-11 (TS)

I/C 5 DIFC106401811 ATC FRV master controller failure (High)

RAISE IIC 6 RR11A Crew LOOP/LOCA (A Recirc Pump Discharge Line Break)

M 7 DG04A BOP EDG-1 auto start failure IC 8 HP01 Crew Malfunction after EOP entry: HPCI Trip M

9 None Crew Contingencies: Slowdown at TAF and Restore M 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 SOP Normal: E1 Malfunction(s) after EOP (1-2): E7, E8 ATC Reactivity (1 per set): E3 Abnormal Events (2-4): E2, E5 SOP IIC (4 I set): E4 & E7 Major Transient(s) IE-Plan entry (1-2): E6 ATC IIC (4 I set): E2 & E5 EOPs (1-2): 100/200 SRO-II/C (4 I set inc 2 as ATC): E2,E4,E5,E7 EOP Contingencies (0-2): 500-1 SRO Tech Spec (2 per set): E2 & E4 Critical Tasks (2-3): 4 ALL Maior Transients (2 oer set): 1 Quad Cities NRC EXAM Scenario 2 Appendix 0 Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: NRC Scenario 2 Op-Test No.: ILT 08-1 Examiners: Operators:

Initial Conditions:

85 % power Turnover: Reverse Main Condenser Flow per QCOP 4400-09, then return to rated power by increasing core flow in accordance with QCGP 3-1 and the REMA.

Event Malf. No. Event Event No. Tvpe* Description 1 None BOP Reverse Main Condenser flow N

2 E001C BOP GCB 4-6 trip / reclose IC 3 RM05A SRO OW Rad Mon fails upscale (TS)

TS 4 FW08A ATC FRV Lockup IC HPCI Steam leak / failure to isolate (TS) 5 HP15 BOP/SRO IC 6 MC08 ATC Main Condenser Vacuum leak / Emergency Power R Reduction, (attempt to maintain Main Condenser backpressure < 6.5 in Hg.)

7 R013A Crew Manual Scram / ATWS (Hydraulic)

M 51 8 OlHS11130301 ATC Malfunction after Major: Start failure of 1 SBLC IC Pump 9 MC08 Crew Complete Loss of Main Condenser Vacuum M

10 None Crew Contingencies: Power Level Control QGA 101 M

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

Total Malfunctions (5-8): _7 BOP Normal: E1 Malfunction(s) after EOP (1-2): E8 ATC Reactivity (1 per set): E6 Abnormal Events (2-4): E2, E4, E5, E6 BOP I/C (4 per set): E2 & E5 Major Transient(s) IE-Plan entry (1-2): E7 ATC I/C (4 per set): E4 & E8 EOPs (1-2): 100, SRO-I I/C (4/set & 2 as ATC):E2, E4, E5, E8 EOP Contingencies (0-2): 101 ATWS SRO Tech Spec (2 per set): E3 & E5 Critical Tasks (2-3): 5 ALL Major Transients (2 per set) E7 Quad Cities NRC EXAM Scenario 3 Appendix 0 Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: NRC Scenario 3 Op-Test No.: ILT 08-1 Examiners: Operators:

Initial Conditions:

20% Power, MO 1-1001-26B, INBD OW SPRAY ISOL VLV out of service for Iimitorque replacement.

Turnover:

Perform QCOS 1000-09 RHR Power Operated Valve Test then continue the startup per step 2 of the REMA and QCGP 1-1.

Event Malf. No. Event Event No. Type* Description 1 None BOP Perform QCOS 1000-09 RHR Power Operated N Valve Test (Partial) 2 None ATC Normal power up Recirc R

3 DIFC10262222 ATC Recirc Pump run up/Master Controller fails high RAISE IC 4 NM08F/RP02BI ATC/SRO APRM upscale w no Y2 scram (TS)

  • 5 6

RP02D AD01D SW12A IC BOP/SRO IC BOP IC Spurious ERV actuation (TS)

Degraded TBCCW pump, Start STBY 7 MS05A Crew Steam Line break inside Containment M

8 None Crew Contingencies: Blowdown M

9 MS16A, MS16B Crew Malfunction after EOP: Tailpipe rupture MS16C M 10 None Crew Venting to stay under PCPL M

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

Total Malfunctions (5-8): _6 BOP Normal: E1 Malfunction(s) after EOP (1-2): E9 ATC Reactivity (1 per set): E2 Abnormal Events (2-4): E3, E4, E5 BOP I/C (4 per set): E5, E6 Major Transient(s) IE-Plan entry (1-2): E7 ATC I/C (4 per set): E3, E4 EOPs (1-2): QGA 100 & 200 SRO-II/C (4 Iset inc 2 as ATC): E3,E4,ES,E6 EOP Contingencies (0-2): QGA 500-1 SRO Tech Spec (2 per set): E4, E5 Critical Tasks (2-3): 3 _ ALL Maior Transients (2 oer set) E7 Quad Cities NRC EXAM Scenario 4 Appendix 0 Scenario Outline Form ES-D-1 Facility: Quad Cities Scenario No.: NRC Scenario 4 Op-Test No.: ILT 08-1 Examiners: Operators:

Initial Conditions:

100% Power Turnover: Continue to maintain full load per QCGP 3-1 and the REMA.

Event Malf. No. Event Event No. Tvpe* Description 1 RD07A ATC CRD Pump trip IC 2 RD03R ATC Rod drift in one notch after CRD Pump Restart IC 3 DIHS13401A ATC Emergency Power Reduction for loss of FW Heater String DIHS13403 R due to 1A1 Heater Level Switch failure, (maintain Reactor Power < 105% and Flow Control Line < 100%)

4 RP04A1RD05R Crew A RPS Trip w 5 rod scram /Manual Scram / Fuel damage CR01 M 5 RD14A Crew Malfunction After EOP: SDV Rupture M

6 DIHS10590303 Crew Scram Reset Switch failure M

7 None Crew Contingency: Slowdown due to 2 areas> Max Safe M Rads

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

Total Malfunctions (5-8): _7 SOP Normal: None Malfunction(s) after EOP (1-2): E5, 6 ATC Reactivity (1 per set): E3 Abnormal Events (2-4): E1, E2, E3 SOP I/C (4 per set): None Major Transient(s) IE-Plan entry (1-2): E4 ATC I/C (4 per set): E1, E2 EOPs (1-2): QGA 300 & 100 SRO-II/C (4 /set inc 2 as ATC): E1, E2 EOP Contingencies (0-2): QGA 500-1 SRO Tech Spec (2 per set): None Critical Tasks (2-3): 2 ~

ALL Maior Transients (2 oer set): E4

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