ML12361A100

Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 1 of 10

ML12361A100
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Site:	Quad Cities
Issue date:	10/31/2012
From:	Delaney M Stevenson & Associates
To:	Office of Nuclear Reactor Regulation
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SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 50.54(f) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC for the QUAD CITIES GENERATING STATION UNIT 1 22710 2 0 6 TH AVENUE NORTH, CORDOVA, ILLINOIS 61242 Renewed Facility Operating License No. DPR-29 NRC Docket No. 50-254 Correspondence No.: RS-12-169 Exeton Exelon Generation Company, LLC (Exelon)PO Box 805398 Chicago, IL 60680-5398 Prepared by: Stevenson

& Associates 1661 Feehanville Drive, Suite 150 Mount'Prospect, IL 60056 Report Number: 12Q0108.40-R-001, Rev.. 3 (Printed Name Preparer:

Marlene Delaney Reviewer:

Tony Perez Approver:

Tony Perez rm Leader: Walter Djordjevic Signature t/J-A(--Peer Review Tea Date 10/31/2012 10/31/2012 10/31/2012 10131/2012 ill /4zI-.Lead Responsible Engineer: Branch Manager: Senior Manager Design Engineering:

ýSUL~I/iAgl Corporate Acceptance:

it S. Clrle.ddide,ý'F -,I V.

I I I Document Title: SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 50.54(f) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC for the QUAD CITIES GENERATING STATION UNIT I I Document Type: Report Report Number: 12Q0108.40-R-001 Project Name: NTTF R2.3 Seismic Walkdowns for Exelon -Quad Cities Job No.: 12Q0108.40 Client: ' Exeton This document has been prepared in accordance with the S&A Quality Assurance Program Manual, Revision 17 and project requirements:

Initial Issue (Rev. 0)Date: 10/19/2012 P re pa red by : M a rle ne D e la ney A ( _ _ _ _ _ _ _ _Date: 10/19/2012 Reviewed by: Tony Perez ,Approved by:Date: 10/19/2012 Approved by: Tony Perez,' _------_______-__

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Contents L ist o f T a b le s ......................................................................................................

.. iii Executive Sum mary ...............................................................................................

iv I Introduction

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1-1 1 .1 P u rp o s e ...................................................................................................................

1 -1 1.2 Background

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1-1 1.3 Plant Overview ........................................................................................................

1-1 1 .4 A p p ro a c h ..................................................................................................................

1 -2 1 .5 C o n c lu s io n ..............................................................................................................

1-2 2 Seism ic Licensing Basis ...............................................................................................

2-1 2.1 Overview .................................................................................................................

2-1 2.2 Safe Shutdown Earthquake (SSE) ..........................................................................

2-1 2.3 Design of Seism ic Category I SSCs ........................................................................

2-1 3 Personnel Qualifications

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3-1 3.1 Overview ...................................................................................................

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3-1 3.2 W alkdown Personnel

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3-1 3.3 Additional Personnel

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3-2 4 Selection of SSCs ......................................................................................................

4-1 4 .1 O v e rv ie w .................................................................................................................

4 -1 4.2 SW EL Development

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4-1 4.2.1 SWEL 1 -Sample of Required Items for the Five Safety Functions

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4-1 4.2.2 SW EL 2 -Spent Fuel Pool Related Items .....................................................

4-3 4.2.3 SW EL 2 -Conclusion

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4-4 5 Seism ic W alkdowns and Area W alk-Bys.................................................................

5-1 5 .1 O v e rv ie w .................................................................................................................

5 -1 5.2 Seismic W alkdowns ................................................................................................

5-1 5.2.1 Adverse Anchorage Conditions

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5-2 5.2.2 Configuration Verification

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5-2 5.2.3 Adverse Seism ic Spatial Interactions

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5-3 5.2.4 Other Adverse Seism ic Conditions

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5-4 5.2.5 Issues Identification during Seismic W alkdowns ...........................................

5-4 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 5 .3 A re a W a lk-B ys ........................................................................................................

5-4 5.3.1 Issue Identification during Area Walk-bys ......................................................

5-6 5.4 Supplemental Information on Electrical Cabinet Inspections

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5-6 6 Licensing Basis Evaluations

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6-1 7 IPEEE Vulnerabilities Resolution Report ....................................................................

7-1 8 Peer Review ..........................................................................................................

8-9 R eferences

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9-1 Appendices A Project Personnel Resumes and SWE Certificates

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A-B Equipment Lists ...............................................

B-I C Seismic Walkdown Checklists (SWCs) .................................................................

C-1 D Area Walk-By Checklists (AWCs) ........ , ...........................................

D-1 E Plan for Future Seismic Walkdown of Inaccessible Equipment

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E-1 F Peer Review Report ................................................................................................

F-1 G IPEEE Vulnerability Status ............................

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G-1 ii Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 List of Tables Table 3-1. Personnel R oles ....................................................................................

3-1 Table 5-1. Anchorage Configuration Confirmation

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5-3 Table 5-2. Issues Identified during Seismic Walkdowns

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5-8 Table 5-3. Issues Identified during Area Walk-Bys .....................................................

5-10 Table B-la. Base List Ia -Items Exclusive to Unit 1 .....................................................

B-3 Table B-lb.' Base List lb -Items Common to Units 1 and 2 ......................

B-15 T a ble B -2 .S W E L I ......................

r .......................................................................

B -18 Table C-1. Summary of Seismic Walkdown Checklists

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C-2 Table D-1. Summary of Area Walk-By Checklists

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D-2 Table E-1. Seismic Walkdown Inaccessible Items .........................

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E-2 Table E-2. Deferred Internal Cabinet Inspection

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E-3 Table G-1. IPEEE Vulnerability Status .......................................................................

G-2 iii Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Executive Summary The purpose of this report is to provide information as requested by the Nuclear Regulatory Commission (NRC) in its March 12, 2012 letter issued to all power reactor licensees and holders of construction permits in active or deferred status. (Ref. 5) In particular, this report provides information requested to address Enclosure 3, Recommendation 2.3: Seismic, of the March 12, 2012 letter. (Ref. 5)Following the accident at the Fukushima Dai-ichi nuclear power plant resulting from the March 11, 2011, Great Tohoku EarthquIake and subsequent tsunami, the NRC established the Near Term Task Force (NTTF) in response to Commission direction.

The NTTF issued a report -Recommendations for Enhancing Reactor Safety in the 2 1 st Century: The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident -that made a series of recommendations, some of which were to be acted upon "without unnecessary delay." (Ref. 6) On March 12, 2012, the NRC issued a letter to all power reactor licensees in accordance with 10CFR50.54(f).

The 50.54(f) letter requests information to assure that certain NTTF recommendations are addressed by all U.S. nuclear power plants. (Ref. 5) The 50.54(f) letter requires, in part, all U.S. nuclear power plants to perform seismic walkdowns to identify and address, degraded, non-conforming or unanalyzed conditions and to verify the current plant' configuration is within the current seismic licensing basis. This report documents the seismic walkdowns performed at Quad Cities Generating Station Unit I in response, in part, to the 50.54(f)letter issued by the NRC.The Nuclear Energy Institute (NEI), supported by industry personnel, cooperated with the NRC to prepare guidance for conducting seismic walkdowns as required in the 50.54(f) letter,, Enclosure 3, Recommendation 2.3: Seismic. (Ref. 5) The guidelines and procedures prepared by NEI and endorsed by the NRC were published through the Electric Power Research Institute (EPRI) as EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012; henceforth, referred to as the "EPRI guidance document." (Ref. 1) Exelon/Quad Cities'has utilized this NRC endorsed guidance as the basis for the seismic walkdowns and this report. (Ref. 1)The EPRI guidance document was used to perform the engineering walkdowns and evaluations described in this report. In 'accordance with the EPRI guidance document, the following topics are addressed in the subsequent sections of this report." Seismic Licensing Basis" Personnel Qualifications

• Selection of Systems, Structures, and Components (SSC)* Seismic Walkdowns and Area Walk-Bys* Seismic Licensing Basis Evaluations

• IPEEE Vulnerabilities Resolution Report" Peer Review iv Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Seismic Licensing Basis The Seismic Licensing Basis is briefly described in Section 2 of this report. The safe shutdown earthquake for the Quad Cities Generating Station site is 0.24g horizontal ground acceleration and 0.16g vertical ground acceleration. (Ref. 2 section 3.7)Personnel Qualifications Personnel qualifications are discussed in Section 3 of this report. The personnel who performed the key activities required to fulfill the objectives and requirements of the 50.54(f) letter are qualified and trained as required in the EPRI guidance document.(Ref. 1) These personnel are responsible for:* Selecting the SSCs that should be placed on the Seismic Walkdown Equipment List (SWEL),* Performing the Seismic Walkdowns and Area Walk-Bys," Performing the seismic licensing basis evaluations, as applicable," Identifying the list of plant-specific vulnerabilities identified during the IPEEE program and describing the actions taken to eliminate or reduce them,* Performing the peer reviews Selection of SSCs Selection of SSCs is discussed in Section 4 of this report. The process used to select the items that were included in the overall Seismic Walkdown Equipment List (SWEL) is described in detail in the EPRI guidance document, Section 3: Selection of SSCs. (Ref.1) The SWEL is comprised of two groups of items, which are described at a high level in the following subsections.

Sample of Required Items for the Five Safety Functions

-SWEL 1 Screen #1 narrowed the scope of SSCs in the plant to those that are designed to Seismic Category I requirements because they have a seismic licensing basis.Screen #2 narrowed the scope of SSCs by selecting only those that do not regularly undergo inspections to confirm that their configuration continues to be consistent with the plant licensing basis.Screen #3 narrowed the scope of SSCs included on SWEL I as only those associated with maintaining the five safety functions.

These five safety functions include the four safe shutdown functions (reactor reactivity control, reactor coolant pressure control, reactor coolant inventory control, and decay heat removal, which includes the Ultimate Heat Sink), plus the containment functions.

Screen #4 was a process intended to result in a SWEL 1 that sufficiently represented the broader population of plant equipment and systems needed to meet the objectives of the 50.54(f) letter. The following five sample attributes were used: e A variety of types of systems 9 Major new or replacement equipment* A variety of types of equipment e A variety of environments v

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment enhanced due to vulnerabilities identified during the IPEEE program Spent Fuel Pool Related Items -SWEL 2 Screen #1 and Screen #2 were used to narrow the scope of spent fuel pool related SSCs to those that have a seismic licensing basis and those that are appropriate for an equipment walkdown process. Screen #3 was a process intended to result in SWEL 2 that sufficiently represents the broader population of spent fuel pool Seismic Category I equipment and systems to meet the objectives of the 50.54(f) letter, and included the following sample selection attributes: " A variety of types of systems" Major new or replacement equipment" A variety of types of equipment* A variety of environments Screen #4 identified items of the spent fuel pool that could potentially cause a rapid drain-down of the pool, even if such items are not Seismic Category I. Rapid drain-down is defined as lowering of the water level to the top of the fuel assemblies within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the earthquake.

Any items identified as having the potential for rapidly draining the spent fuel pool were to be added to SWEL 2.For Quad Cities Unit 1, the SWEL is comprised of:* SWEL 1 resulted with 104 items for walkdown.* SWEL 2 resulted with no items for walkdown." There are no SSCs associated with spent fuel pool rapid drain-down to be included on SWEL 2.Seismic Walkdowns and Area Walk-Bys Section 5, Appendix C, and Appendix D of this report documents the equipment Seismic Walkdowns and the Area Walk-Bys.

The online seismic walkdowns for Quad Cities Unit 1 were performed during the week of August 20, 2012. During the majority of the walkdown activities, the walkdown team consisted of two (2) Seismic Walkdown Engineers (SWEs), the station Lead Responsible Engineer (LRE) or designee, and a station Equipment Operator.The seismic walkdowns focused on the seismic adequacy of the items on the SWEL.The walkdowns focused on the following:

.Adverse anchorage conditions

• Adverse seismic spatial interactions

• Other adverse seismic conditions (e.g., degradation, configuration, etc.,)Area Walk-Bys were conducted in each area of the plant that contained an item on the SWEL (generally within 35 feet of the SWEL component).

The Area Walk-By was performed to identify potentially adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL item. The key examination factors that were considered in the Area Walk-Bys included the following:

vi Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169* Anchorage conditions (if visible without opening equipment)

• Significantly degraded equipment in the area 0 Potential seismic interaction

• A visual assessment (from the floor) of cable/conduit raceways and HVAC ducting (e.g., condition of supports or fill conditions of cable trays)* Potential adverse interactions that could cause flooding/spray and fire in the area* Other housekeeping items, including temporary installations The seismic walkdown team inspected 94 of the 104 components on the SWEL (comprised of SWEL 1 and SWEL 2). Walkdowns for 10 components were deferred due to accessibility issues such as being located in containment or energized equipment.

The 10 remaining Unit I items will be walked down during a unit outage or another time when the equipment is accessible, as appropriate.

Anchorage verification was required for a minimum of 28 components. (Ref. 1) A total of 37 anchorage configurations were confirmed to be installed in accordance with the station documentation.

Following the completion of the online seismic'walkdowns, the industry was made aware that the NRC staff had clarified a position on opening electrical cabinets to inspect for other adverse seismic conditions.

Supplemental inspections of 18 electrical cabinets are planned and will be completed, as required, during a unit outage or another time when the equipment becomes accessible.

The list of electrical cabinets along with the milestone completion schedule is provided in Table E-2.During the seismic walkdowns at Quad Cities Unit I twenty (20) Issue Reports (IRs), with one repeated, were issued for conditions such as open S-hooks and seismic housekeeping issues. Seismic housekeeping conditions were found to be the most common. After evaluation through the CAP, it was determined that none of the conditions identified in the IRs were adverse seismic conditions.

Seismic Licensing Basis Evaluations The EPRI. guidance document, Section 5: Seismic Licensing Basis Evaluation provides a detailed process to perform and document seismic licensing basis evaluations of SSCs identified when potentially adverse seismic conditions are identified.

The process provides a means to identify, evaluate and document how the identified potentially adverse seismic condition meets a station's seismic licensing basis without entering the condition into a station's Corrective Action Program (CAP). In lieu of this process, Exelon/Quad Cities utilized the existing processes and procedures (Site CAP Expectations) to identify, evaluate and document conditions identified during the Seismic Walkdowns.

In accordance with Exelon/Quad Cities processes and procedures, all questionable conditions identified by the SWEs during the walkdowns were entered into the station CAP to be further evaluated and addressed as required.

The SWEs provided input to support the identification and evaluation (including seismic licensing basis evaluations, as required) of the potentially adverse seismic conditions entered into the CAP. The station corrective action program is a more robust process than that provided in the EPRI guidance document; in part, ensuring each condition is properly evaluated for conformance with design and licensing bases and corrected as required.vii Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Conditions identified during the walkdowns were documented on the SWCs, AWCs, and entered into the CAP.. Tables 5-2 and 5-3 in the report provide the IR, a summary of the condition, and the action completion status.IPEEE Vulnerabilities.IPEEE vulnerabilities are addressed in Section 7 of this report. No vulnerabilities were identified as a result of the effort that addressed the Individual Plant Examination of External Events (IPEEE). (Ref. 3) However, plant improvements were identified in section 7 of Reference

3. Table G-1 provides the list of plant improvements, the IPEEE proposed resolution, the actual resolution and resolution date. All IPEEE improvement actions are complete.Peer Reviews A peer review team consisting of at least two individuals was assembled and peer reviews were performed in accordance with Section 6: Peer Reviews of the EPRI guidance document.

The Peer Review process included the following activities:

• Review of the selection of SSCs included on the SWEL 0 Review of a sample of the checklists prepared for the Seismic Walkdowns and Area Walk-Bys* Review of licensing basis evaluations, as applicable

• Review of the decisions for entering the potentially adverse conditions into the CAP process" Review of the submittal report* Provided a summary report of the peer review process in the submittal report Section 8 of this report contains a summary of the Peer Review. The Peer Review determined that the objectives and requirements of the 50.54(f) letter are met. Further, it was concluded by the peer reviews that the efforts completed and documented within this report are in accordance with the EPRI guidance document.Summary In summary, seismic walkdowns have been completed at the Quad Cities Generating Station Unit 1 in accordance with the NRC endorsed walkdown methodology.

All.potentially degraded, nonconforming, or unanalyzed conditions identified as a result of the seismic walkdowns have been entered into the corrective action program.Evaluations of the identified conditions are complete and documented within the CAP.These evaluations determined the Seismic Walkdowns resulted with no adverse anchorage conditions, no adverse seismic spatial interactions, and no other adverse seismic conditions associated with the items on the SWEL. Similarly, the Area Walk-Bys resulted with no adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL item(s).The Seismic Walkdowns identified several minor issues predominantly pertaining to seismic housekeeping.

Other than these minor issues, the Seismic Walkdowns identified no degraded, nonconforming,A or unanalyzed conditions that required either immediate or follow-on action(s).

No planned or newly identified protection or mitigation features have resulted from the efforts to address the 50.54(f) letter.viii Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Follow-on activities required to complete the efforts to address Enclosure 3 of the 50.54(f) letter include inspection of 10 items deferred due to inaccessibility along with supplemental inspections of 18 electrical cabinets.

Area Walk-Bys will be complete, as required, during these follow-on activities.

ix Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 I Introduction

1.1 PURPOSE

The purpose of this report is to provide information as requested by the Nuclear Regulatory Commission (NRC) in its March 12, 2012 letter issued to all power reactor licensees and holders of construction permits in active or deferred status. (Ref. 5) In particular, this report provides information requested to address Enclosure 3, Recommendation 2.3: Seismic, of the March 12, 2012 letter. (Ref. 5)

1.2 BACKGROUND

Following the accident at the Fukushima Dai-ichi nuclear power plant resulting from the March 11, 2011, Great Tohoku Earthquake and subsequent tsunami, the NRC established the Near Term Task Force (NTTF) in response to Commission direction.

The NTTF issued a report -Recommendations for.Enhancing Reactor Safety in the 21s, Century: The Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident -that made a series of recommendations, some of which were to be acted upon "without unnecessary delay." (Ref. 6) On March 12, 2012, the NRC issued a letter to all power reactor licensees in accordance with 10CFR50.54(f).

The 50.54(f) letter requests information to assure that certain NTTF recommendations are addressed by all U.S. nuclear power plants. (Ref. 5) The 50.54(f) letter requires, in part, all U.S. nuclear power plants to perform seismic walkdowns to identify and address degraded, non-conforming or unanalyzed conditions and to verify the current plant configuration is within the current seismic licensing basis. This report documents the seismic walkdowns performed at Quad Cities Generating Station Unit 1 in response, in part, to the 50.54(f)letter issued by the NRC.The Nuclear Energy Institute (NEI), supported by industry personnel, cooperated with the NRC to prepare guidance for conducting seismic walkdowns as required in the 50.54(f) letter, Enclosure 3, Recommendation 2.3: Seismic. (Ref. 5) The guidelines and procedures prepared by NEI and endorsed by the NRC were published through the Electric Power Research Institute (EPRI) as EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near- Term Task Force Recommendation 2.3: Seismic, dated June 2012; henceforth, referred to as the "EPRI guidance document." (Ref. 1) Exelon/Quad Cities has utilized this NRC endorsed guidance as the basis for the seismic walkdowns and this report. (Ref. 1)1.3 PLANT OVERVIEW Quad Cities Generating Station consists of two operating boiling water reactor (BWR)generating units. The site is located in Rock Island County, Illinois, in parts of sections 7, 8, 17, 18, 19 and 20, Township; 20 North, Range; 2 East. It is on the east bank of the Mississippi River opposite the mouth of the Wapsipinicon River, and about three (3)miles north of Cordova, Illinois.

The site is about 20 miles northeast of the Quad Cities (Davenport, Iowa; Rock Island, Moline, and East Moline, Illinois). (Ref. 2 section 2.1.1)1-1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Both units have Mark I containments, are rated for 2957 MWt power (RENEWED FACILITY OPERATING LICENSE NO. DPR-29 (Unit 1) and DPR-30 (Unit 2)), and were originally designed and built by GE as prime contractor for Commonwealth Edison Company. The commercial service dates for Quad Cities Units 1 and 2 were February 18, 1973 and March 10, 1973 respectively. (Ref. 2 section 1.1.1)1.4 APPROACH The EPRI Seismic Walkdown Guidance is used for the Quad Cities Generating Station Unit 1 engineering walkdowns and evaluations described in this report. (Ref. 1) In accordance with Reference 1, the following topics are addressed in the subsequent sections of this report:* Seismic Licensing Basis* Personnel Qualifications

• Selection of SSCs* Seismic Walkdowns and Area Walk-Bys* Licensing Basis Evaluations

• IPEEE Vulnerabilities Resolution Report* Peer Review

1.5 CONCLUSION

Seismic walkdowns have been completed at the Quad Cities Generating Station Unit 1 in accordance with the NRC-endorsed walkdown methodology.

All potentially degraded, nonconforming, or unanalyzed conditions identified as a result of the seismic walkdowns have been entered into the corrective action program.Evaluations of the identified conditions are complete and documented within the CAP.These evaluations determined the Seismic Walkdowns resulted with no adverse anchorage conditions, no adverse seismic spatial interactions, and no other adverse seismic conditions associated with the items on the SWEL. Similarly, the Area Walk-Bys resulted with no adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL item(s).The Seismic Walkdowns identified several minor issues predominantly pertaining to seismic housekeeping.

Other than these minor issues, the Seismic Walkdowns identified no degraded, nonconforming, or unanalyzed conditions that required either immediate or follow-on action(s).

No planned or newly identified protection or mitigation features have resulted from the efforts to address the 50.54(f) letter.Follow-on activities required to complete the efforts to address Enclosure 3 of the 50.54(f) letter include inspection of 10 items deferred due to inaccessibility along with supplemental inspections of 18 electrical cabinets.

Area Walk-Bys will be complete, as required, during these follow-on activities.

1-2 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 2 Seismic Licensing Basis 2.1 OVERVIEW This section of the report summarizes the seismic licensing basis for the Quad Cities Generating Station Unit I and Unit 2. The safe shutdown earthquake and a summary of the codes, standards, and methods used in the design of Seismic Category I SSCs are presented.

This section does not establish or change the seismic licensing basis of the facility and is intended to provide a fundamental understanding of the seismic licensing basis of the facility.2.2 SAFE SHUTDOWN EARTHQUAKE (SSE)The safe shutdown earthquake for the Quad Cities Generating Station site is 0.24g horizontal ground acceleration and 0.16g vertical ground acceleration. (Ref. 2 section 3.7)2.3 DESIGN OF SEISMIC CATEGORY I SSCs The input motions used to create the seismic design of Quad Cities are based on the Housner Ground Response Spectrum (GRS) and the south 80 degrees east (S80E)component of the 1957 San Francisco Golden Gate Park earthquake.

The Quad Cities drywell was evaluated using the results of the Dresden drywell analysis, which used the north-south component earthquake record of El Centro of May 18, 1940, normalized to 0. 1Og for Operating Basis Earthquake (OBE (0.2g for Safe Shutdown Earthquake (SSE)). For the seismic analysis of the Seismic Class I structures and development of In-Structure Response Spectra (ISRS), the Housner GRS was used. (Ref. 2 section 3.7)The Golden Gate earthquake time history was used to verify that when using the time-history method, the maximum OBE loadings did not occur in the valleys of the unsmoothed (Golden Gate) spectrum.

The Quad Cities OBE is defined in the horizontal direction by the Housner GRS scaled to 0.12g peak ground acceleration (PGA) and the ISRS developed from the Golden Gate earthquake time history scaled to 0.12g. In addition, the OBE in the vertical direction is constant for all periods with a resulting PGA value of 0.08g. The Quad Cities SSE is defined by multiplying the OBE accelerations by a factor of 2, resulting in horizontal and vertical directions GRS PGA values of 0.24g and 0.16g respectively. (Ref. 2 section 3.7)The response spectrum method was used to calculate the buildings' responses.

For the Reactor Building, the SSE damping values used were 2% damping for steel and 5%damping for concrete.

For the Turbine Building, an SSE damping value of 5% was used.The peaks of the time history-derived spectra were broadened by 15%. (Ref. 2 section 3.7).The governing codes for the design of the structures were American Concrete Institute's ACI-318-63 for reinforced concrete, and American Institute of Steel Construction (AISC)Steel Construction Manual, 6th Edition for steel, and American Society of Mechanical 2-1 Quad Cities Generating Station Unit 1 12Q0108:40-R-001 Rev. 3 Correspondence No.: RS-12-169 Engineers (ASME) Boiler & Pressure Vessel Code,Section III 1965 for the containment.(Ref. 2 section 3.7)A full description of the Safe Shutdown Earthquake along with the codes, standards, and methods used in the design of the Seismic Class I (Category I) SSCs for meeting the seismic licensing basis requirements is provided in the following Quad Cities Generating Station UFSAR sections:* 3.7 Seismic Design* 3.8 Design of Category I Structures

• 3.9 Mechanical Systems and Components

• 3.10 Seismic Qualification of Seismic Category I Instrumentation and Electrical Equipment These UFSAR sections should be referred to for a detailed understanding of the seismic licensing basis.2-2 Quad Cities Generating Station Unit I 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 3 Personnel Qualifications

3.1 OVERVIEW

This section of the report identifies the personnel that participated in the NTTF 2.3 Seismic Walkdown efforts. A description of the responsibilities of each Seismic Walkdown participant's role(s) is provided in Section 2 of the EPRI Seismic Walkdown Guidance. (Ref. 1) Resumes provided in Appendix A provide detail on each person's qualifications for his or her role.3.2 WALKDOWN PERSONNEL Table 3-1 below summarizes the names and corresponding roles of personnel who participated in the NTTF 2.3 Seismic Walkdown effort.Table 3-1. Personnel Roles Equipment Plant Seism Licensing IPEEE Peer Name Selection BasisWalkdown Lisi Engineer Operations Engineer Reviewer Reviewer Reviewer (SWE) Reviewer A. Perez X K. Hull X T.K. Ram X1 J. Griffith X X D. Carter X X M. Wodarcyk X X J. Kim (Exelon) X X X K. Hall (Exelon) X T. Bacon X W. Djordjevic x2 T. Fuhs (Exelon) X Notes: 1. Peer Review Team member for SWEL review only.2. ' Peer Review Team Leader.3-1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 3.3 ADDITIONAL PERSONNEL In addition to the S&A personnel listed above, Exelon Plant Operations, Tony Fuhs, reviewed the SWEL. Tony Fuhs is the Operation Support Manager at Quad Cities Station, a formerly licensed SRO that has worked at the Quad Cities'for almost 30 years and is familiar with all aspects of the station operating procedures.

Various station personnel also provided support to the SWEL preparer in identifying major equipment or system modifications, equipment and systems located in different environments, and equipment and systems that would be accessible for inspection during the plant walkdowns, in accordance with Reference 1.3-2 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 4 Selection of SSCs 4.1 OVERVIEW This section of the report describes the process used to select structures, systems, and components, (SSCs) that were included in the Seismic Walkdown Equipment List (SWEL). The actual equipment lists.that were developed in this process are found in Appendix B and are as follows:* Table B-la. Base List la -Items Exclusive to Unit 1 Table B-lb. Base List lb -Items Common to Units 1 and 2* Table B-2. SWEL 1 4.2 SWEL DEVELOPMENT The selection of SSCs process described in EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012, was utilized to develop the SWEL for Quad Cities Generating Station Unit 1. (Ref. 1)The SWEL is comprised of two groups of items:* SWEL I is a sample of items to safely shut down the reactor and maintain containment integrity" SWEL 2 is a list of spent fuel pool related items 4.2.1 SWEL 1 -Sample of Required Items for the Five Safety Functions The process for selecting a sample of SSCs for shutting down the reactor and maintaining containment integrity began with the composite Seismic Individual Plant Examination for External Events (IPEEE) Success Path Equipment List (SPEL). (Ref. 3)The IPEEE SPEL was then subjected to the following four screens to identify the items to be included on the first Seismic Walkdown Equipment List (SWEL 1): 1. Screen #1 -Seismic Category I As described in Reference 1, only items that have a defined seismic licensing basis are to be included in SWEL 1. Each item on the IPEEE SPEL was reviewed to determine if it had a defined seismic licensing basis. All items identified as Class I, as defined in Quad Cities UFSAR Chapter 3, were identified as having a defined seismic licensing basis. (Ref. 2) Electrical.

enclosures containing Class I electrical devices were identified as Class I.'ý Class I determination was made through a review of current design and licensing basis documentation.

4-1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 2. Screen #2- Equipment or Systems This screen narrowed the scope of items to include only those that do not regularly undergo inspections to confirm that their configuration is consistent with the plant licensing basis. This screen further reduced the IPEEE SPEL of any Class I Structures, Containment Penetrations, Class I Piping Systems, cable/conduit raceways and HVAC ductwork.3. Screen #3 -Support for the Five Safety Functions This screen narrowed the scope of items included on the SWEL 1 to only those associated with maintaining the following five safety functions:

A. Reactor Reactivity Control (RRC)B. Reactor Coolant Pressure Control (RCPC)C. Reactor Coolant -Inventory Control (RCIC)D. Decay Heat Removal (DHR)E. Containment Function (CF)The first four functions are associated with bringing the reactor to a safe shutdown condition.

The fifth function is associated with maintaining containment integrity.

As described in Reference 3, the safety function for each item on the IPEEE SPEL was identified.

It is noted that items on SWEL 1 with a specific safety function(s) are considered frontline systems. Items with a safety function of 'Auxiliary

&Support', 'Electrical Systems', or 'Racks & Panels' may be a frontline or support system. Items with a safety function of 'Auxiliary

& Support', 'Electrical Systems', or 'Racks & Panels' support at least one of the five safety functions however, the specific safety function(s) is not indicated as identification of the specific safety function(s) supported is not required by Reference 1.The resultant equipment list after Screen #3 is defined in the EPRI guidance document as Base List 1 and is included in Appendix B. (Ref. 1)4. Screen #4- Sample Considerations This screen is intended to result in a SWEL 1 that sufficiently represents a broad population of plant Seismic Category I equipment and systems to meet the objectives of the NRC 50.54(f) letter. The following attributes were considered in the selection process for items included on SWEL 1: A. A Variety of Types of Systems The system is identified for each item on SWEL 1. The equipment included on SWEL 1 is a representative sample of several systems that perform one or multiple safety functions.

Further, the systems represented include both frontline and support systems as listed in Reference 1 Appendix E: Systems to Support Safety Function(s).

B. Major New and Replacement Equipment The equipment on SWEL 1 includes several items that have been modified or replaced over the past several years. Each item on SWEL 1 that is new or replaced is identified.

4-2 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 C. A Variety of Types of Equipment The equipment class is identified for each item on SWEL 1. The equipment included on SWEL 1 is a representative sample from each of the classes of equipment listed in Reference 1 Appendix B: Classes of Equipment.

Where appropriate, at least one piece of equipment from each class was included on SWEL 1.Screening

1. 1, #2, and #3 resulted in no equipment in the following classes:* (13) -Motor Generators

• (19) -Temperature Sensors D. A Variety of Environments The location for each item is identified on SWEL 1. The equipment included on SWEL 1 is a representative sample from a variety of environments (locations) in the station.E. Equipment Enhanced Due to Vulnerabilities Identified During the IPEEE Program The equipment on SWEL 1 includes several items that were enhanced as a result of the IPEEE program. Each item on SWEL 1 that was enhanced as a result of the IPEEE program is identified.

F. Contribution to Risk In selecting items for SWEL 1 that met the attributes above, some items with similar attributes were selected based on their higher risk-significance.

To determine the relative risk-significance, the Risk Achievement Worth (RAW)and Fussell-Vesely importance for a Loss of Off-Site Power (LOOP) scenario from the internal plant PRA were used. Additionally, the list of risk-significant components for the LOOP PRA were compared with the draft SWEL 1 to confirm that a reasonable sample of risk-significant components (relevant for a seismic event) were included on SWEL 1. (Ref. 7)4.2.2 SWEL 2 -Spent Fuel Pool Related Items ii!The process for selecting a sample of SSCs associated with the spent fuel pool (SFP)began with a review of the station design and licensing basis documentation for the SFP and the interconnecting SFP cooling system. (Ref. 2 section 9.1 and Refs. 8, 9, 10, 11, &12) The following four screens narrowed the scope of SSCs to be included on the second Seismic Walkdown Equipment List (SWEL 2): 1. Screen #1 -Seismic Category I Only those items identified as Seismic Category I (having defined seismic licensing basis) are to be included on SWEL 2 with exception to the SFP structure.

As described in Reference 1, the adequacy of the SFP structure is assessed by analysis as a Seismic Category 1 (Class I) structure.

Therefore, the SFP structure is assumed to be seismically adequate for the purposes of this program and is not included in the scope of items included on SWEL 2.The review of design and licensing basis documentation for the SFP revealed no Class I equipment for Quad Cities Generating Station Unit 1. (Ref. 2 section 9.1 and Refs. 8, 9, 10, 11, & 12)4-3 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Screen #1 resulted with no items added to SWEL 2. Therefore, Screens #2 and #3 below were not performed.

However, Screens #2 and #3 are provided for completeness as they are part of the equipment selection process.2. Screen #2 -Equipment or Systems This screen was to consider only those items associated with the SFP that were appropriate for an equipment walkdown process. This screen was not performed as Screen #1 resulted with no items added to SWEL 2.3. Screen #3 -Sample Considerations This screen represents a process that was intended to result in a SWEL 2 that sufficiently represents a broad population of SFP Seismic Category 1 (Class I)equipment and systems to meet the objectives ofthe NRC 50.54(f) letter. (Ref. 1)The following attributes were to be considered in'the development of SWEL 2: A.. A variety of types of systems B. Major new and replacement equipment C. A variety of types of equipment D. A variety of environments This screen was not performed as Screen #1 resulted with no items added to SWEL 2.4. Screen #4- Rapid Drain-Down This screen identifies items that could allow the spent fuel pool to drain rapidly.Consistent with Reference 1, the scope of items included in this screen is limited to the hydraulic lines connected to the SFP and the equipment connected to those lines. For the purposes of this program it is assumed the SFP gates are installed and the SFP cooling system-is in its normal alignment for power operations.

The SFP gates are passive devices that are integral to the SFP. As such, they are considered capable of withstanding a design basis earthquake without failure and do not allow for a rapid drain-down of the SFP.The SSCs identified in this screen are not limited to Seismic Category I (having defined seismic licensing basis) items, but are limited to those items that could allow rapid drain-down of the SFP. Rapid drain-down is defined as lowering the water level to the top of the fuel assemblies within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the earthquake.

An assessment of the Quad Cities Generating Station Unit 1 spent fuel pools and their cooling systems was performed and found no SFP penetrations below 10 feet above the top of the fuel assemblies. (Ref. 2 section 9.1, and Refs. 8, 9, 10, 11, &12) As such, and consistent with Reference 1, there is no potential for rapid drain-down and no items were added to SWEL 2.4.2.3 SWEL 2- Conclusion No items were identified to be included in the scope of SWEL 2 for Quad Cities Generating Station Unit 1.4-4 Quad Cities Generating Station Unit I 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 5 Seismic Walkdowns and Area Walk-Bys 5.1 OVERVIEW Seismic Walkdowns and Area Walk-Bys were conducted by two (2) person teams of trained Seismic Walkdown Engineers (SWEs), in accordance with the EPRI guidance document during the week of August 20, 2012. The Seismic Walkdowns and Area Walk-Bys are discussed in more detail in the following sub-sections.

Consistent with the EPRI guidance document, Section 4: Seismic Walkdowns and Area Walk-Bys, the SWEs used their engineering judgment, based on their experience and training, to identify potentially adverse seismic conditions.

Where needed, the engineers were provided the latitude to rely upon new or existing analyses to inform their judgment.The SWEs conducted the Seismic Walkdowns and Area Walk-Bys together as a team.During the evaluations, the SWEs actively discussed their observations and judgments with each other. The results of the Seismic Walkdowns and Area Walk-Bys reported herein are based on the comprehensive agreement of the SWEs.5.2 SEISMIC WALKDOWNS The Seismic Walkdowns focused on the seismic adequacy of the items on the SWEL as provided in Appendix B of this report. It is noted, as discussed in Section 4 above, there were no items included on SWEL 2 for Quad Cities Unit 1. The Seismic Walkdowns also evaluated the potential for nearby SSCs to cause adverse seismic interactions with the SWEL items. The Seismic Walkdowns focused on the following adverse seismic conditions associated with the subject item of equipment: " Adverse anchorage conditions" Adverse seismic spatial interactions" Other adverse seismic conditions The results of the Seismic Walkdowns have been documented on the Seismic Walkdown Checklist (SWC) provided in the EPRI guidance document, Appendix C.Seismic Walkdowns were performed and a SWC completed for 94 of the 104 items identified on the Quad Cities Unit 1 SWEL. The completed SWCs are provided in Appendix C of this report. Additionally, photos have been included with most SWCs to provide a visual record of the item along with any comments noted on the SWC.Drawings and other plant records are cited in some of the SWCs, but are not included with the SWCs because they are readily retrievable documents through the station's document management system. Information on anchorage that was obtained from the previously performed Seismic Qualification Utility Group (SQUG) walkdowns are included in the SWCs since this information, in part, was used for the anchorage verification.

5-1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Seismic Walkdowns are deferred for the remaining 10 items to a unit outage or appropriate time when the equipment is accessible.

These items could not be walked down during the 180-day period following the issuance of the 10CFR50.54(f) letter due to their being inaccessible.

Inaccessibility of this equipment was either based on the location of the equipment (environment that posed personnel safety concerns while the unit is operating) or due to the electrical safety hazards posed while the equipment is operating.

Appendix E of this report identifies the inaccessible equipment along with the plan for future Seismic Walkdowns.

The following subsections describe the approach followed by the SWEs to identify potentially adverse anchorage conditions, adverse seismic interactions, and other adverse seismic conditions during the Seismic Walkdowns.

5.2.1 Adverse

Anchorage Conditions Guidance for identifying anchorage that could be degraded, non-conforming, or unanalyzed relied on visual inspections of the anchorage and verification of anchorage configuration.

Details for these two types of evaluations are provided in the following two subsections.

The evaluation of potentially adverse anchorage conditions described in this subsection applies to the anchorage connections that attach the identified item of equipment to the civil structure on which it is mounted. For example, the welded connections that secure the base of a Motor Control Center (MCC) to the steel embedment in the concrete floor would be evaluated in this subsection.

Evaluation of the connections that secure components within the MCC is covered later in the subsection "Other Adverse Seismic Conditions." Visual Inspections The purpose of the visual inspections was to identify whether any of the following potentially adverse anchorage conditions were present:* Bent, broken, missing, or loose hardware" Corrosion that is more than mild surface oxidation* Visible cracks in the concrete near the anchors" Other potentially adverse seismic conditions Based on the results of the visual inspection, the SWEs judged whether the anchorage was potentially degraded, non-conforming, or unanalyzed.

The results of the visual inspection were documented on the SWC, as appropriate.

If there was clearly no evidence of degraded, nonconforming, or unanalyzed conditions, then it was indicated on the checklist and a licensing basis evaluation was not necessary.

However, if it was not possible to judge whether the anchorage is degraded, nonconforming, or unanalyzed, then the condition was entered into the Corrective Action Program as a potentially adverse seismic condition.

5.2.2 Configuration

Verification In addition to the visual inspections of the anchorage as described above, the configuration of the installed anchorage was verified to be consistent with existing plant documentation for at least 50% of the items on the SWEL.5-2 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Line-mounted equipment (e.g., valves mounted on pipelines without separate anchorage) was not evaluated for anchorage adequacy and was not counted in establishing the 50% sample size.Examples of documentation that was considered to verify that the anchorage installation configurations are consistent with the plant documentation include the following:

• Design drawings* Seismic qualification reports of analyses or shake table tests* IPEEE or USI A-46 program documentation, as applicable The Table C-1 of Appendix C indicates the anchorage verification status for components as follows: N/A: components that are line-mounted and/or are not directly anchored (with separate anchorage) to the civil structure and therefore do not count in the anchorage confirmation total Y: components that are anchored to the civil structure which were confirmed to be consistent with design drawings and/or other plant documentation N: components that are anchored to the civil structure for which anchorage drawings were not identified and/or retrieved See Table 5-1 below for the accounting of the 50% anchorage configuration confirmations, and the individual SWC forms in Appendix C for the specific drawings used for each anchorage verification confirmation.

Table 5-1. Anchorage Configuration Confirmation No. of SWEL N/A Items Required to SWEL Items Confirm? Items Confirmed (A) (B) (A-B)I2 Total 104 48 28 37 5.2.3 Adverse Seismic Spatial Interactions An adverse seismic spatial interaction is the physical interaction between the SWEL item and a nearby SSC caused by relative motion between the two during an earthquake.

An inspection was performed in the area adjacent to and surrounding the SWEL item to identify any seismic interaction conditions that could adversely affect the capability.of that SWEL item to perform its intended safety-related functions.

The three types of seismic spatial interaction effects that were considered are:* Proximity* Failure and falling of SSCs (Seismic II over I)* Flexibility of attached lines and cables 5-3 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Detailed guidance for evaluating each of these types of seismic spatial interactions is described in the EPRI guidance document, Appendix D: Seismic Spatial Interaction.

The Seismic Walkdown Engineers exercised their judgment to identify seismic interaction hazards. Section 5.2.5 provides a summary of issues identified during the Seismic Walkdowns.

5.2.4 Other

Adverse Seismic Conditions In addition to adverse anchorage conditions and adverse seismic interactions, described above, other potentially adverse seismic conditions that could challenge the seismic adequacy of a SWEL item could have been present. Examples of the types of conditions that could pose potentially adverse seismic conditions include the following:

• Degraded conditions

• Loose or missing fasteners that secure internal or external components to equipment" Large, heavy components mounted on a cabinet that are not typically included by the original equipment manufacturer

• Cabinet doors or panels that are not latched or fastened" Other adverse conditions Any identified other adverse seismic conditions are documented on the items' SWC, as applicable.

5.2.5 Issues

Identification during Seismic Walkdowns Table 5-2 provides a summary of issues identified during the equipment Seismic Walkdowns.

The equipment Seismic Walkdowns resulted with a total of eight (8)concerns identified and each of these was entered into the station's CAP. All of the identified concerns were assessed and it was concluded that the condition would not prevent the associated equipment from performing its safety-related function(s).

None of the conditions identified by the SWEs during the equipment Seismic Walkdowns were concluded to be adverse seismic conditions.

5.3 AREA WALK-BYS The purpose of the Area Walk-Bys is to identify potentially adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL items. Vicinity is generally defined as the room containing the SWEL item. If the room is very large (e.g., Turbine Hall), then the vicinity is identified based on judgment, e.g., on the order of about 35 feet from the SWEL item. This vicinity is described on the Area Walk-By Checklist (AWC), shown in Appendix D of this report. A total of 26 AWCs were completed for Quad Cities Unit 1. It is noted that additional AWCs will be completed, as required, as deferred and supplemental inspections are completed.

The key examination factors that were considered during Area Walk-Bys include the following:

• Anchorage conditions (if visible without opening equipment)

• Significantly degraded equipment in the area 5-4 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169* A visual assessment (from the floor) of cable/conduit raceways and HVAC ducting (e.g., condition of supports or fill conditions of cable trays)" Potentially adverse seismic interactions including those that could cause flooding, spray, and fires in the area* Other housekeeping items that could cause adverse seismic interaction (including temporary installations and equipment storage)* Scaffold construction was inspected to meet Exelon Procedure NES-MS-04.1, Seismic Prequalified Scaffolds" Seismic housekeeping was examined to meet station procedure MA-QC-716-026-1001, Seismic Housekeeping The Area Walk-Bys are intended to identify adverse seismic conditions that are readily identified by visual inspection, without necessarily stopping to open cabinets or taking an extended look. Therefore, the Area Walk-By took significantly less time than it took to conduct the Seismic Walkdowns described above for a SWEL item. If a potentially adverse seismic condition was identified during the Area Walk-By, then additional time was taken, as necessary, to evaluate adequately whether there was an adverse condition and to document any findings.The results of the Area Walk-Bys are documented on the AWCs included in Appendix D of this report. A separate AWC was filled out for each area inspected.

A single AWC was completed for areas where more than one SWEL item was located.Additional details for evaluating the potential for adverse seismic interactions that could cause flooding, spray, or fire in the area are provided in the following two subsections.

Seismically-Induced Flooding/Spray Interactions Seismically-induced flooding/spray interactions are the effect of possible ruptures of vessels or piping systems that could spray, flood or cascade water into the area where SWEL items are located. This type of seismic interaction was considered during the IPEEE program. Those prior evaluations were considered, as applicable, as information for the Area Walk-Bys.One area of particular concern to the industry is threaded fire protection piping with long unsupported spans. If adequate seismic supports are present or there are isolation valves near the tanks or charging sources, flooding may not be a concern. Numerous failures have been observed in past earthquakes resulting from sprinkler head impact.Less frequent but commonly observed failures have occurred due to flexible headers and stiff branch pipes, non-ductile mechanical couplings, seismic anchor motion and failed supports.Examples where seismically-induced flooding/spray interactions could occur include the following:

• Fire protection piping with inadequate clearance around fusible-link sprinkler heads* Non-ductile mechanical and threaded piping couplings can fail and lead to flooding or spray of equipment* Long, unsupported spans of threaded fire protection piping" Flexible headers with stiffly supported branch lines 5-5 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169* Non-Seismic Category I tanks The SWEs exercised their judgment to identify only those seismically-induced interactions that could lead to flooding or spray.Seismically-Induced Fire Interactions Seismically-induced fire interactions can occur when equipment or systems containing hazardous/flammable material fail or rupture. This type of seismic interaction was considered during the IPEEE program. Those prior evaluations were considered, as applicable, as information for the Area Walk-Bys.Examples where seismically-induced fire interactions could occur include the following:

• Hazardous/flammable material stored in inadequately anchored drums, inadequately anchored shelves, or unlocked cabinets* Natural gas lines and their attachment to equipment or buildings* Bottles containing acetylene or similar flammable chemicals" Hydrogen lines and bottles Another example where seismically-induced fire interaction could occur is when there is relative motion between a high voltage item of equipment (e.g., 4160 volt transformer) and an adjacent support structure when they have different foundations.

This relative motion can cause high voltage busbars, which pass between the two, to short out against the grounded bus duct surrounding the busbars and cause a fire.The Seismic Walkdown Engineers exercised their judgment to identify only those seismically-induced interactions that could lead to fires.5.3.1 Issue Identification during Area Walk-bys Table 5-3 provides a summary of issues identified during the Area Walk-bys.

Thirteen (13) issues were identified during the Area Walk-Bys and entered into the station CAP.No potentially adverse seismic conditions were identified that resulted in a seismic licensing basis evaluation.

No seismically-induced flooding or spray interactions were identified during the Area Walk-Bys.

No seismically-induced fire interactions were identified during the Area Walk-Bys.5.4 SUPPLEMENTAL INFORMATION ON ELECTRICAL CABINET INSPECTIONS Following the completion of the online seismic walkdowns, the industry was made aware that the NRC had clarified a position on opening electrical cabinets to inspect for adverse seismic conditions.

The purpose for opening these cabinets is to inspect for evidence of:* internal components not being adequately secured,* whether fasteners securing adjacent cabinets together are in place, and* other adverse seismic conditions.

Appendix E of this report includes Table E-2 which identifies components in the specified equipment classes that would be considered as electrical cabinets: 5-6 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 1. Motor Control Centers and Wall-Mounted Contactors

2. Low Voltage Switchgear and Breaker Panels 3. Medium Voltage, Metal-Clad Switchgear

4. Transformers

14. Distribution Panels and Automatic Transfer Switches 16. Battery Chargers and Inverters 20. Instrumentation and Control Panels Table E-2 indicates internal accessibility of each cabinet. Cabinets that have been identified as requiring these supplemental internal inspections are those with doors or panels with latches or thumbscrews and can be readily opened during normal maintenance activities.

Also provided for each cabinet is a proposed milestone schedule for performing these internal inspections and the associated station tracking record (IR number).Components identified on Table E-2 may also be identified on Table E-1 as items whose walkdowns have been deferred to an outage.The Seismic Walkdown Checklists (SWC) for the components identified in Table E-2 that can be opened for internal inspections will be revised at the time of the supplemental walkdown to indicate the results of these internal inspections.

5-7 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Table 5-2. Issues Identified during Seismic Walkdowns Action Actions Item ID Description of Issue Request Complete I I)Yes/No (See ID (IR) Notes 1 & 2)During the Seismic Walkdowns it was identified that there is a 1/4 inch clearance between the U1 P1 1-4641-44 and the EDG Skid. There is a possibility that during a seismic event, the gauge could displace and contact the EDG skid. Due to the minimal weight of the gauge, the seismic displacement and inertia gained will be minimal. As such, 1-4699-226 the gauge impact with the skid will not cause significant 1403063 Yes damage to the gauge. Any damage to the gauge would be limited to minor surface damage. The gauge would not break apart, nor would it become unconnected from the air line. Therefore there is no concern that the equipment would be affected during a seismic event.Loose nuts on threaded rods holding down light pack 1-8300-1 *above charger. Still with full thread engagement.

Light 1403065 Yes packs will not fall and impact equipment.

1 panel bolt missing on left side of panel, 3 panel bolts loose on right side of panel. Right side has locations for 16 bolts; 13 bolts acceptable.

Left side has locations for 1-2251-113 11 bolts; 10 bolts acceptable.

Number of properly-1403068 No installed bolts is judged, adequate to ensure panel is able to perform its design function.During the Seismic Walkdowns it was identified that there are 3 screws missing and 1 screw loose on the 25OVDC Charger. Two screws are missing on the right side. One screw is missing on the left side and one screw is loose on the left side. There are 40 screws on each side of this 1-8350 charger holding the panel piece in place. Based on 1403079 No Engineering Judgment the remaining 38 of 40 screws per side are more than adequate to maintain the connection of the panel during a seismic event, thus preventing any adverse impact to the charger.Two gas cylinders near the 1-8801 Valve on RB 623 are each restrained by a single chain that is not tight.1-8801A-AO Adequate distance to safety-related components exists, 1403593 Yes so there is no seismic interaction concern.5-8 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Action Actions Item ID Description of Issue Request Complete ID(R Yes/No (See ID(IR) Notes 1 & 2)Instrument Air Lines connected to the 1-8801A, 8801 B, 8801C, 8802A, 8802B & 8802C valves are in contact with rigid insulation covering adjacent piping. Reference UFSAR 6.2.5.1, Oxygen content in primary containment is monitored by an oxygen analyzer at various locations within the containment to ensure the containment is maintained at the desired oxygen content below 4% by 1-8801A-AO volume during normal operation.

During a seismic event, 1403596 Yes there is a possibility that the solenoid could move out of phase with the adjacent pipe. If the two items move out of phase, they could contact each other and the Instrument Air line may be damaged. A drawing review shows that the valves fail closed upon loss of air. Therefore, there is no immediate seismic concern.During Fukushima seismic walkdowns, it was discovered that the angle brackets providing vertical support for the 1-0302-18 and 1-0302-19A lines are installed but not providing any support for the lines. There is a gap 1-0302-19A between the top of the brackets and the bottom of the 1403597 Yes lines. These are located at UL1 RB 595, Col line 17-18 and L. No excessive deflection or distortion noted and nearby adjacent supports are in good condition.

Therefore, there is no immediate seismic concern.During the seismic walkdowns, a number of slightly open S-hooks and incorrectly-oriented beam clamps supporting light fixtures were found. The S-hook openings do not warrant concern since mitigating robust items limit the 1-7800- pendulum action of the light fixtures during a seismic 18195 event. Low vertical acceleration values and the minimal weight of the light fixtures are judged to provide significant margin against the beam clamps being dislodged during a seismic event.Notes: 1) "Yes" indicates that any corrective actions resulting from the issue are complete 2) "No" indicates that any corrective actions resulting from the issue are NOT complete.

Actions are tracked by the IR number in the station Corrective Action Program.5-9 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Table 5-3. Issues Identified during Area Walk-Bys Actions Action Complete Item ID Description of Issue Request Complee ID IR) Yes/No (See ID(IR) Notes 1 & 2)Several light fixtures supported by open S-hooks. Fixtures have long (approx. 4 feet) chains, minimizing ability of AWC-Ul-18 fixtures to fall from hook. Clearance between fixtures and 1402669 No conduits above (approx. 3 inches) is small, which minimizes pendulum motion of fixtures.During the Seismic Walkdowns it was identified that the light fixture between switchgear 18 and switchgear 19 has one unclosed S Hook. The other S Hook is closed.Because one of the two S Hooks is closed, there is reasonable assurance that the light fixture will not fall AWC-Ul-20 during a seismic event. Should the one open S Hook 1403072 No become unhooked during a seismic event, there is sufficient clearance such that the switchgear will not be impacted.

Additionally, there are no other components in the line of fire which would be adversely affected due to impact from the light fixture. Therefore there is no seismic concern regarding this unclosed S Hook.Ten of over 100 screws loose or missing at back side of Bus 1 BI. Loose/missing screws spread over 4 different AWC-U1-2 locations along bus. Sufficient remaining engaged 1403074 No fasteners to maintain panel connection per engineering judgment.Panel 2251-12 missing 2 panel assembly screws. Due to AWC-U1-9 abundance of remaining fasteners present, panel judged 1403076 No to be acceptable.

Light fixture above 1-1001-1 D valve with open S-hooks.Valve is robust and would not be affected by light fixture AWC-U1-6 impact. Fixture above 1 D RHRSW pump with open S- 1403082 Yes hook. Hardwired power cable prevents light fixture from falling.During the Seismic Walkdowns it was identified that one of two bolts connecting HCUs together is missing. The two AWC-U1-17 HCUs are the 1-0305-127-3051 and the 1-0305-107-3035.

1403391 No Remaining bolt is judged sufficient to prevent adverse seismic interaction between HCUs.5-10 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Actions Action Complete Item ID Description of Issue Request Yes/No (See ID (IR) Notes 1 & 2)During the Seismic Walkdowns it was identified that a conduit support located in the cable spreading room is missing anchor bolts. The location of this support is approximately 20 ft north of the south wall and 15 ft west AWC-Ul-13 of the east wall. This conduit support is a stanchion which 1403393 No holds a 2 inch and a 3 inch conduit approximately 18 inches off of the floor. Adjacent conduit supports are in good condition and are judged adequate to prevent damage to cables in conduit during a seismic event.It was identified that the bottom of the concrete slab above EL 623' (i.e., the bottom of the EL 647' slab) in the vicinity of column lines L, 14-15 is spalling.

Currently, there is some minor concrete debris on the EL 623' slab below the spalled area. In addition, there is a piece of concrete in the spalled area that is cracked through. This piece of AWC-Ul-14 concrete is being held in place by a conduit that is 1404147 No attached to the bottom of the slab and, therefore, there is no immediate concern that any additional concrete debris will fall. The spalled concrete slab is considered acceptable with deficiencies as defined in Procedure ER-AA-450 (Structures Monitoring) and the structural adequacy of the spalled slab is not compromised.

During the seismic walkdowns,'a number of slightly open S-hooks and incorrectly-oriented beam clamps supporting light fixtures were found. The S-hook openings do not AWC-UI-10 warrant concern since mitigating robust items limit the AWC-Ul-16 pendulum action of the light fixtures during a seismic 1404697 No AWC-UI1-17 event. Low vertical acceleration values and the minimal weight of the light fixtures are judged to provide significant margin against the beam clamps being dislodged during a seismic event.Emergency light pack 42E (1-7900-42E) is missing the right side mounting fasteners.

These mounting fasteners hold the light pack to the wall mounted tray. This is not a seismic concern because the left side is securely AWC-Ul-15 fastened.

It should be noted that there is a lip on the wall 1405892 No so rotation cannot occur. There is also a considerable distance from any safety related component, so if the light pack were to fall out of the wall-mounted tray, no damage would occur.5-11 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Actions Action Complete Item ID Description of Issue Request Yes/No (See ID(IR) Notes 1 & 2)For the conduit that feeds valve 1-2301-6-MO, the first conduit support away from the valve is missing the conduit clamp. The conduit span from the valve to the next adequate conduit support (located at the manual operator junction box) is relatively short. Thus, by engineering judgment, sufficient design margin remains for the conduit to perform its design function during a seismic event.The flexible portion of the same conduit at valve 1-2301-6-MO has a split in one side. Although this is not a seismic concern, the insulation on the cabling within the conduit in AWC-Ul-24 conjunction with the results of recent surveillance testing 1404153 No for valve 1-2301-6-MO provides reasonable assurance that the valve remains fully operable.One of the four bolts that mount the manual operator box for valve 1-2301-3-MO to the supporting Unistrut members is missing. By engineering judgment, the three remaining mounting bolts are adequate to support the manual operator box during a seismic event since the manual operator box weight is small and the seismic accelerations at El. 554 ft. in the Reactor Building are relatively low.During the Unit 1 seismic walkdowns, 15 housekeeping issues were found throughout the plant. Per procedure Ue MA-QC-716-026-1 001, staged materials near safety- 1405922 No related equipment must adhere to the listed requirements.

See IR for specific instances.

No measures in place to prevent trolleys on top of Switchgears 18, 19, and 29 from impacting trolley rail end AWC-Ul-20 stops during seismic event, thereby introducing vibration 1419584 No into Switchgears 18, 19, and 29. Trolley movement and impact is judged to be minimal due to cyclic motion of seismic event and relatively small weight of trolley.Notes: 1) "Yes" indicates that any corrective actions resulting from the issue are complete 2) "No" indicates that any corrective actions resulting from the issue are NOT complete.

Actions are tracked by the IR number in the station Corrective Action Program.5-12 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 6 Licensing Basis Evaluations The EPRI guidance document, Section 5: Seismic Licensing Basis Evaluation provides a detailed process to perform and document seismic licensing basis evaluations of SSCs identified when potentially adverse seismic conditions are identified.

The process provides a means to identify, evaluate and document how the identified potentially adverse seismic condition meets a station's seismic licensing basis without entering the condition into a station's Corrective Action Program (CAP). In lieu of this process, Exelon/Quad Cities utilized the existing.

processes and procedures (Site CAP Expectations) to identify, evaluate and document conditions identified during the Seismic Walkdowns.

In accordance with Exelon/Quad Cities processes and procedures, all questionable conditions identified by the SWEs during the walkdowns were entered into the station CAP to be further evaluated and addressed as required.

The SWEs provided input to support the identification and evaluation (including seismic licensing basis evaluations, as required) of the potentially adverse seismic conditions entered into the CAP. The station corrective action program is a more robust process~than that provided in the EPRI guidance document; in part, ensuring each condition is properly evaluated for conformance with design and licensing ibases and corrected as required.Conditions identified during the walkdowns were documented on the SWCs, AWCs, and entered into the CAP. Tables 5-2 and 5-3 in the report provide the IR, a summary of the condition, and the action completion status.6-1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 7 IPEEE Vulnerabilities Resolution Report Per the Individual Plant Examination of External Events (IPEEE) Submittal for Quad Cities and the Staff Evaluation Report of IPEEE submittal of Quad Cities Nuclear Power Station, Units 1 and 2 dated April 26, 2001, an explicit definition of vulnerability was not provided and no vulnerabilities with respect to potential severe accidents related to external events were identified. (Ref. 3 & 4) However, plant improvements and previously identified SQUG outliers were identified in Sections 3 and 7 of Reference 3.Table G-1, in Appendix G, lists the plant improvements, the IPEEE/SQUG proposed resolution, the actual resolution and resolution date. All IPEEE improvement actions are complete.7-1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 8 Peer Review A peer review team consisting of at least two individuals was assembled and peer reviews were performed in accordance with Section 6: Peer Reviews of the EPRI guidance document.

The Peer Review process included the following activities: " Review of the selection of SSCs included on the SWEL* Review of a sample of the checklists prepared for the Seismic Walkdowns and Area Walk-Bys" Review of Licensing basis evaluations, as applicable

• Review of the decisions for entering the potentially adverse conditions into the CAP process* Review of the submittal report* Provide a summary report of the peer review process in the submittal report The peer reviews were performed independently from this report and the summary Peer Review Report is provided in Appendix F of this report.8-1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 9 References Reference drawings related to SWEL items are provided in the Seismic Walkdown Checklists and if applicable, in the Area-Walkdown Checklists.

1. EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012.2. Quad Cities Nuclear Power Station Updated Final Safety Analysis Report (UFSAR), Revision 11, October 2011 3. CornEd Letter from R.M. Krich to U.S. Nuclear Regulatory Commission, dated July 29, 1999,

Subject:

Updated Individual Plant Examination of External Events Report 4. Staff Evaluation Report of Individual Plant Examination of External Events (IPEEE)submittal of Quad Cities Nuclear Power Station, Units 1 and 2 dated April 26, 2001 5. NRC (E Leeds and M Johnson) Letter to All Power Reactor Licensees et al.,"Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," Enclosure 2.3,"Recommendation 2.3: Seismic," dated March 12, 2012 6. "Recommendations for Enhancing Reactor Safety in the 2 1 st Century: The Near-term Task Force Review of Insights from the Fukushima Dai-ichi Accident," ADAMS Accession No. ML11186107, July 12, 2011 7. Internal RM document QC-MISC-12, Rev. 0, Quad Cities Risk Importance Listing to Support Development of the Seismic Walkdown Equipment List (SWEL)8. Drawing M-38, Rev. AP, Diagram of Fuel Pool Cooling Piping 9. Drawing M-45, Rev. W, Diagram of Fuel Pool Filter Demineralizer Piping 10. Drawing B-262, Rev. S, Reactor Building Pool Liner Bottom Plan 11. Drawing B-263, Rev. L, Reactor Building Pool Sections & Details 12. Drawing B-264, Rev. M, Reactor Building Pool Sections & Details 9-1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 A Project Personnel Resumes and SWE Certificates Resumes and certificates (where applicable) for the following people are found in Appendix A: A. Perez, Equipment Selection Engineer .........................................................

A-2 K. Hull, Equipm ent Selection Engineer ............................................................

A-6 J. Griffith, SWE, Licensing Basis Reviewer ........................................................

A-9 D. Carter, SWE, Licensing Basis Reviewer ......................................................

A-13 M. Wodarcyk, SWE, Licensing Basis Reviewer ..................................................

A-16 J. Kim, SWE, Licensing Basis Reviewer, IPEEE Reviewer ................................

A-18 K .H a ll, S W E .........................................................................................................

A -2 1 T. Ram, SWEL Peer Reviewer ....................................

A-24 W. Djordjevic, Peer Review Team Leader ........................................................

A-26 T. Bacon, Peer Reviewer ........................................

A-30 A-1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Stevenson

& Associates Antonio J. Perez, P.E.

SUMMARY

Mr. Perez has over 15 years of experience in project management, project engineering, equipment design, and mechanical systems layout for nuclear and industrial facilities.

EDUCATION B.S. -Mechanical Engineering Michigan Technological University, Houghton, MI Magna cum Laude LICENSES Professional Engineer, Wisconsin:

September 2002 Minnesota:

December 2010 PROFESSIONAL EXPERIENCE Stevenson

& Associates, Green Bay, WI General Manager October 2010 -Present" Responsible for interfacing with clients with a focus on continuously improving relationships.

• Responsible for managing staff resources to meet or exceed clients' needs.* Responsible for recruiting and hiring staff necessary to meet resource requirements while effectively increasing capacity.* Responsible for providing Engineering Consultation services to clients.Project Manager March 2007 -October 2010" Performing Project Management tasks including development of project plans, identification of resource needs, estimating.task durations, developing project schedules, and monitoring budgets." Lead design team efforts at the Kewaunee Power Station on multiple projects that include two separate Auxiliary Feedwater flow control modifications, Auxiliary Feedwater flow monitoring instrumentation modifications, and Auxiliary Building roof modifications.

• Supported the Calculation Reconstitution and Improvement Project at the Prairie Island Nuclear Generating Plant by mapping calculations associated with the RHR system.Dominion Energy Kewaunee (formerly Nuclear Management Company 2001 -2005)Kewaunee Power Station, Kewaunee, WI Shift Technical Advisor (trainee)

January 2006 -March 2007* Trainee in a Senior Reactor Operator Certificate training program.Page 1 of 3 A-2 Quad Cities Generating Station Unit I 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Stevenson

& Associates Antonio J. Perez, P.E.Engineering Supervisor

-ME/CE/SE Design May 2004 -January 2006* Supervised a staff of 12 to 15 engineers (mechanical, civil, and structural design) who were charged with developing design changes, maintaining design and licensing basis documentation and supporting maintenance.

• Integrated the civil/structural engineering group and the mechanical engineering group into a cohesive unit that resulted in gained efficiency and a net reduction of one full time equivalent engineer.* Substantially increased the quality of engineering products developed and published by the ME/CE/SE Design Engineering group through coaching and feedback as a result of increased supervisory oversight of engineering products.* Developed a work management system for the group that provided a means for prioritizing activities, estimating the level of effort, and scheduling of activities.

This system allowed for an increased understanding of workload and became an invaluable tool for prioritizing work and managing resources.

• Increased communications within the group by holding daily 15 minute meetings where station messages were delivered and where the group's resources were assessed and redirected as necessary to meet commitments.

This resulted in an increase, in morale and an increase in commitments met.* Increased communications with other departments by establishing a central point of contact for the group and by assuring that the ME/CE/SE Design Engineering group was represented at Planning and Scheduling meetings.Motor Operated Valve Engineer June 2001 -May 2004* Established a project plan and led the implementation effort that re-organized the Motor-Operated Valve Program at KPS. This effort consisted of developing a Program Manual, developing controlled calculations, performing Design Basis Reviews, and compiling and/or establishing plant positions on known industry issues.The result of this effort was a reduction of full time equivalent engineers, from 3 to 1, required to maintain the Program.* Performed and reviewed MOV safety related calculations including Minimum Required Stem Thrust, Weak Link Analysis, and Available Margin." Assisted in MOV testing by providing engineering support to maintenance personnel.

DISTRIBUTION PLANNING, INC., Grandville, MI Systems Mechanical Engineer 2000 -2001 9 Integrated mechanical systems and designed equipment for material handling systems.0 Procured equipment and coordinated delivery schedules with vendors., Page 2 of 3 A-3 Quad Cities Generating Station Unit 1 12Q0108,40-R-001 Rev. 3 Correspondence No.: RS-12-169 Stevenson

& Associates Antonio J. Perez, P.E.SMS SANDMOLD SYSTEMS, INC., Newaygo, MI Project Engineer/Manager 1998 -2000* Led multi-discipline project design teams for several projects that ranged in size from a few thousand dollars up to $2.2 million.* Coordinated efforts with engineering, manufacturing, and installation groups to establish and maintain project schedules that met or exceeded the client's expectations.

• Procured equipment and coordinated delivery schedules with vendors.* Acted as the company's liaison with clients to work through issues that arose during projects.

Provided project status updates to clients and management.

• Designed equipment such as sand storage bins -up.to 540-ton live load capacity, bucket elevators, belt conveyors, screw conveyors, and mixers. Most of this equipment was for handling of bulk solids (foundry sand).* Analyzed and designed structural support members for various types of equipment such as vibratory conveyors, mixers, and conveyors.

Designed access structures such as stair towers, service platforms and catwalks.* Calculated foundation loads and point loads of equipment support points.LIFT-TECH INTERNATIONAL, Muskegon, MI Project Engineer 1997-1998 0 Performed engineering analyses, wrote critiques, and recommended design modifications of structural members for the purpose of upgrading bridge cranes and hoists.* Implemented engineering design changes to enhance product development.

Page 3 of 3 A-4 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 A-5 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 KIM L. HULL BACKGROUND

SUMMARY

Accomplished Lead Engineer/

Project Manager with significant experience in commercial nuclear power industry.

Demonstrated ability to lead and contribute on cross-functional project teams. Possess strong analytical, problem resolution, collaboration, and communication skills when interacting with diverse audiences including regulatory inspectors, internal inspectors, management, and employees.

Respected trainer with ability to develop and present information and measure effectiveness through evaluation techniques.

Strengths include: Project Management Design Modifications Plant Operational Support Procurement Management/Leadership Regulatory Compliance Training/Coaching Auditing Inspections KEY ACCOMPLISHMENTS

• Served as KNPP Lead Engineer/

Project Supervisor for approximately 125 plant design changes.* Experienced in all aspects of nuclear power plant modification packages including development of calculations, design, engineering, and procurement specifications." Thorough understanding of configuration control, management, and preparation of 10CFR50.59 analyses.* Participated in several regulatory and industry audits, including CDBI and INPO assessments." Experienced as a Technical Specialist performing NUPIC Audits." Well-developed communication skills for preparing technical presentations including lesson plans, project reports, and meetings in support of regulatory activities and inspections.

• Qualified Shift Technical Advisor for KNPP Operations Group (1980s).PROFESSIONAL EXPERIENCE STEVENSON

& ASSOCIATES

-Project Manager 2010 -Current National consulting engineering firm specializing in civil, structural and mechanical engineering for power, industrial and advanced technology facilities.

Project Manager" Development of plant specific Seismic Walkdown Equipment Lists for multiple Units in response to NRC 50.54(f) requirements regarding Recommendation 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," Enclosure 2.3, "Recommendation 2.3: Seismic."" Onsite at Kewaunee Power Station Consultant support to resolve Q-list Open Items* On-site at Kewaunee Power Station Consultant support for Auxiliary Feedwater Flow Control Modification including preparation and review of design documentation.

WISCONSIN PUBLIC SERVICE RESOURCES

/ Nuclear Management Company DOMINION ENERGY -Kewaunee, WI 1982 to 2010 Senior Instructor (Maintenance)

(2009 -2010)* Developed lesson plans and taught Basic Systems and Continuing Training Topics for Engineering and Technical Support training program.Engineer Ill/Principal Engineer (2004 -2009)" Responsible for modifications and emergent issues including Steam Exclusion Boundaries, Fuel Transfer Carriage, Frazil Ice development on the KPS Circulating Water Intake, and NRC 96-06 Two Phase flow." Member of Dominion Fleet Calculation Quality Review Team and Mentor for Calculation training.* Outage nightshift Lead Mechanical Design Engineer/Back-up Supervisor.

• KPS Engineering representative on the Independent Review Team developed to address CDBI A-6 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 inspection findings.

Assigned to review all calculations, modification packages, l0CFR 50.59 screenings, evaluations, and procurement packages.* Technical Instructor for Administrative Process training for new engineers.

Mechanical Design Supervisor (2002 -2004)" Supervised nine engineers, analysts, and technicians assigned to the KNPP Mechanical Design Group." Provided Mechanical Design Oversight for all vendor activities impacting KNPP Mechanical Design Bases.* Provided support for emergent plant issues, NRC Inspections, and Physical Change Packages.* Subject Matter Expert Instructor for 1 OCFR 50.59 process training for new engineers.

Principal Engineer (Analytical Group SGR Project) (1998 -2002)* Contract Manager for Steam Generator Replacement (SGR)." Responsible for coordination of SGE design, fabrication and installation contracts.

• Provided outage schedule development, coordination, and work process integration between Bechtel and KNPP.* Coordinated contractor mobilization, badging, and plant specific training.* Technical Specialist for Quality Assurance audits of vendors.* SGR Shift Manager for night shift* Responsible Engineer for SGR related Physical Change Packages." Responsible for SGR budget development up to 1998." Prepared, reviewed, and awarded Bechtel Installation contract." Participated in review and award of Ansaldo Fabrication contract.* Served on team to review and award Westinghouse Design contract.* Selected to work at Arkansas Nuclear One for their steam generator installation.

Senior Engineer (Analytical Group) (1994-1998)

• Responsible Engineer for Physical Change Packages.* Member KNPP Engineering Reorganization Team.* Recognized Technical Expert for KNPP systems.Senior Project Supervisor (1992-1994)

• Provided project management and engineering services for KNPP DCR packages." Supervisor of KNPP NPM Project Attendants responsible for modification package organization and close out.Nuclear Services Supervisor (1991-1992)" Supervised initial Steam Generator replacement project effort." Provided specification development for services and major plant components.

Prior to 1992 -Held engineering positions from Associate Engineer to Nuclear Design Engineering Supervisor.

EDUCATION Masters Program Coursework

-Mechanical Engineering; Michigan State University

-E. Lansing, MI B.S. -Mechanical Engineering

-Michigan State University

-E. Lansing, MI B.A. -Biology -Albion College -Albion, MI A-7 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 A-8 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 STEVENSON

& ASSOCIATES JAMES D. GRIFFITH QUALIFICATIONS Knowledgeable professional with over 23 years of diverse experience in structural engineering.

Thorough, results-oriented problem solver with excellent communication skills. Works well independently or as part of a team. Highly skilled in all project phases from design through construction and specializes in field problem resolution.

PROFESSIONAL EXPERIENCE Proiect Engineer (Stevenson

& Associates, 2000 to present)Responsible for all aspects of civil structural design. Also provides interface between clients, vendors, constructors and Stevenson

& Associates.

Decommissioning Design Engineer (ComEd, 1998 to 2000)Responsible for structural design work during conversion from generating to storage facility.

Gathered design information during conceptual field walkdowns and prepared design calculations and drawings.Provided field support during construction.

• Designed all component supports and concrete foundations for various new indoor equipment." Managed construction during installation of new roof-mounted HVAC system." Designed structural steel support framing and access gallery for new outdoor cooling towers.Maintenance Engineer (ComEd, 1995 to 1998)Responsible for the design of structural repairs to station equipment and facilities.

Interfaced with maintenance and construction personnel and performed evaluations of rigging, lead shielding, and scaffolding.

Investigated and developed solutions for structural problems in the field and provided field support during installation of modifications." Designed and supervised field installation of heavy-duty rigging apparatus for replacement of large overhead crane motor.* Performed conceptual design and supervised field construction of 60 foot high scaffold work platform for valve replacement.

• Prepared and reviewed calculations to justify structural acceptability of station equipment during successful completion of Seismic Qualification Utility Group (SQUG) evaluation program.* Acted as engineering liaison to other station departments (Maintenance, Operations, Radiation Protection, etc) to resolve emergent problems regarding:

• Rigging for lifting various plant equipment* Placement and support of temporary lead shielding* Storage of equipment in safety related seismic areas of the plant* Structural repairs and improvements to plant buildings and equipment Structural Engineer (Sargent and Lundy, 1983 to 1995)Responsible for design of structural modifications to various components of power generating facilities.

Prepared and reviewed design calculations and drawings* Designed numerous modifications toexisting structural steel framing members and end connections.

1 A-9 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169" Supported field installation of modifications and provided solutions to problems encountered in the field." Designed and monitored field installation of new access galleries for various pieces of equipment.

EDUCATION B.S., Civil and Environmental Engineering, University of Wisconsin, Madison, Wisconsin Continuing Education"Concrete Evaluation and Repair Seminar", Portland Cement Association, Skokie, Illinois, 1996"STAAD III Program Training", Sargent and Lundy Engineers, Chicago, Illinois, 1995"Piping Design, Analysis and AUTOPIPE Training" Vectra Technologies, Inc., Zion, Illinois, 1995"SQUG Walkdown Screening and Seismic Evaluation Training Course", Seismic Qualification Utility Group through ComEd, Downers Grove, Illinois, 1994 PROFESSIONAL REGISTRATIONS Licensed Professional Engineer in State of Wisconsin 2 A-10 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 A-11 Quad Cities Generating Station Unit I 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 S&4 A-12 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Stevenson

& Associates DAVID N. CARTER PROFESSIONAL EXPERIENCE April, 1998-Present Wisconsin Electric, Point Beach Nuclear Plant (On loan from Stevenson

&Associates)

Point Beach Nuclear Plant is located in Wisconsin between Milwaukee and Green Bay on Lake Michigan.Worked as Seismic Qualification Engineer responsible for performing seismic evaluations of plant equipment as well as providing input to procurement documents and reviewing seismic qualification reports for new plant equipment.

Also worked as Design Engineer preparing and managing various plant modifications.

Modifications included reinforcement of RWST anchorage, new HELB barriers and vent paths, new firewall, platform and foundation modifications.

The modification preparations included preparing design change documents, 50.59 safety evaluations and calculations as well as assisting in resolution of installation problems.December, 1997-April, 1998 Stevenson

& Associates Stevenson

& Associates is a consulting engineering firm. Work includes design and analysis of building structures and components.

April, 1995-December, 1997 CornEd, Zion Station Zion Station is a nuclear power plant that is owned and operated by ComEd, an electric utility serving northern Illinois.

Member of design engineering group as a Senior Structural Engineer.

Work included the scoping, cost estimating, design and preparation of design documents for various plant modifications.

Prepared 50.59 safety evaluations for various plant modifications.

Member of the Zion Seismic Review Team that implemented the SQUG program. Performed SQUG walkdowns and assessments.

Proposed and implemented upgrades to SQUG outliers.

Attended and completed the SQUG SCE Training.April, 1984-April, 1995 Sargent & Lundy Engineers Sargent & Lundy is a consulting engineering firm that specializes in the design and modification of power plants. Work included the design and analysis of building structures and support components on fossil and nuclear power plants. Assignment highlights include the following:

• Member of modification design project team at Zion Station." Member of Zion project team in Sargent and Lundy Chicago office for approximately two years.Worked on various modifications for Zion Station as a Senior Engineer in the Structural Engineering Division.

Design activities included preparation, review or approval of design calculations, design documents such as engineering change notices and design criteria documents.

Supervised up to four other engineers.

• Member of a design team working on the design of two new nuclear units located in Korea (Yonggwang 3&4). The design was done in the offices of Korea Power Engineering Corporation located in Seoul, Korea. Responsibilities included the design of the structural steel for the turbine building.

The assignment involved working with and providing guidance for engineers from the Korean engineering company. The work also involved the preparation of design procedures, procurement specifications, and design calculations as well as the review of design drawings and shop drawings.

The length of this assignment was approximately four years.1 A-13 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169" Member of a group of engineers that worked on a weld evaluation program at Watts Bar Nuclear Power Station. The assignment included the evaluation of various weld discrepancies on structural steel connections and component supports.

This assignment lasted one year." Member of various project teams which worked on the design of modifications for fossil and nuclear power plants. Projects include Dresden, Quad Cities, Byron, Braidwood Stations (Commonwealth Edison Co.), and Parish Station (Houston Lighting and Power). Work included the assessment of masonry walls, design of component supports, design of hot air ducts, evaluation of structural steel framing for final loads and preparation of study and design reports. Responsibilities also included the preparation and review of design documents, letters, supervising other engineers, and meeting with clients.September, 1980-March 1984 American Bridge Division -United States Steel Corp.American Bridge was a consulting engineering firm whose main client was U.S. Steel. They specialized in the design and modification of steel mill buildings.

Assignments included the following:

• Design of various modifications to blast furnaces.* Member of group of engineers whose function was to inspect existing mill buildings, prepare a report of findings and recommend repairs. Included in this assignment was the preparation of design drawings showing the recommended repairs. This assignment lasted approximately one year.* Loaned to Sargent and Lundy Engineers to assist in the design of component supports and the final load evaluation on Byron Nuclear Power Station. This assignment totaled approximately 16 months.EDUCATION Syracuse University, L. C. Smith College of Engineering; Bachelor of Science Degree in Civil Engineering.

Graduated Cum Laude.PROFESSIONAL AFFILIATIONS Licensed Professional Engineer in State of Minnesota Licensed Structural Engineer in State of Illinois Licensed Professional Engineer in State of Wisconsin 2 A-14 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 W1 F, ýA,ý'N '. ffi%ý ý'fNx-. 'R NY-t Au", MIE Certificate of Completion Dave Carter Successfully Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns__"____ __ -___ __ _ /)Date: 06/26/12 Bruce M. LIFy- instructor NTTF 2.3 Seismic Walkdown Course..........!17 S 0 0 -GtOZ .A-15 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 MICHAEL WODARCYK EMPLOYMENT Stevenson

& Associates, Glenview, Illinois Staff Engineer June 2011 -present Analysis and design of nuclear power plant structures and other assorted structures.

On-site engineering at plants during outage maintenance periods.ESCA Consultants, Urbana, Illinois Design Engineer September 2010 -June 2011* Structural design and hydraulic modeling of bridges for the Illinois Department of Transportation, Canadian National Railway, BNSF Railway, and others. Inspection of the production of precast structural elements for CN.Evans, Mechwart Hambleton, & Tilton, Columbus, Ohio Intern May 2007 -August 2007, May 2008 -August 2008* Assisted in the design and drafting of site, stormwater, and utility plans for various projects using AutoCAD, including the headquarters tower and garage for Grange Insurance in downtown Columbus.D.E. Huddleston General Contractors, Columbus, Ohio Laborer May 2006 -August 2006* Constructed footing foundations and performed other miscellaneous tasks for two elementary schools under construction in the Columbus City Schools district.EDUCATION University of Illinois, Urbana-Champaign Master of Science, Civil Engineering Structural Engineering Concentration GPA: 3.66 (of 4.0)University of Notre Dame Bachelor of Science, Civil Engineering GPA: 3.47 (of 4.0)Urbana-Champaign, Illinois August 2010 Notre Dame, Indiana May 2009" Undergraduate Research, January 2009 -August 2009 Studied the effects that different structural systems have on the harmonic damping of a high-rise structure.

Modeled a case study high-rise building using SAP2000." Big Beam Contest, August 2008 -February 2009 Led a team of four students that designed, built, and tested Notre Dame's entry for the Precast/Prestressed Concrete Institute's Big Beam reinforced-concrete beam contest, with all design considerations based upon ACI 318-08 and PCI 6th ed. codes and specifications.

This design won 2nd place in the contest's Zone 4 (Midwest).

CERTIFICATIONS ORGANIZATIONS Engineer-in-Training First Aid American Concrete Institute American Society of Civil Engineers April 2009 August 2008 A-16 Quad Cities Generating Station Unit 1 1200108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 A-17 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 00 Exeton.Julie A. Kim EXPERIENCE

SUMMARY

2011-present Exelon Generation Julie joined Exelon in 2011. During that year, she worked on projects specific to power plants. Previously, she worked on the design height control valves. She also studied computation fluid dynamics (CFD) during college. Examples of her experience are: ACCOMPLISHMENT

SUMMARY

Product Launch Worked on a two person team to design, a height control valve that was later tested, released and sold. Also worked with mirror components that were designed for vibration.

Project Lead the Way An organization that mentors high school kids to design an airplane.Technical aspects of the project included structural mechanics, and the use of FEA and CFD software.

The team won the state competition and made it to the semi-finals at National Competition.

Seismic Walkdowns Organizing SWEL, providing plant drawing, performing plant walkdowns, interfaces with various departments, scheduling dose, writing and tracking issue reports.Combustible Loading Verified all materials are accounted for at the time of calculation.

Tracked and outlined all changes in fire severity in any fire zone.Zinc Injection Modifications Completed design change package for both units for zinc injection skid to change the flow control valve internals.

Interfaced with vendor and various departments to complete the reviews.ASME Presentation Presented co-authored independent research paper to ASME on CFD. The paper analyzed methods of the aerodynamics of pickup trucks.A-18 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 A Exeton.EDUCATION Muskegon Community College, Associates in Arts and Science, 2008 Grand Valley State University, B.S. Mechanical Engineering, 2011 QUALIFICATIONS AND TRAINING EPRI Seismic Walkdown Engineer (SWE) training, 2012 MEMBERSHIPS Member, American Society of Mechanical Engineers (ASME)A-19 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169~I~2 LECTRC POWER RESEARCH I NSTITUTE Certificate of Completion Julie Kim Training on Near Term Task Force Recommendation 2.3-Plant Seismic Walkdowns June 27, 2012 Date.0 4~44 4 Aýa Robert K. Kassawara EPRI Manager, Structural Reliability

& Integrity A-20 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 SExeton.Kevin B. Hall, P.E.EXPERIENCE

SUMMARY

2012-present Exelon Generation, Cordova, IL Kevin joined Exelon in April 2012 as a design engineer.2001-2012 Stanley Consultants, Muscatine, IA Kevin began his professional career at Stanley Consultants in Muscatine, IA. His experience includes the structural design of many different types of structures, including buildings in high wind and seismic regions, flood control structures, water and wastewater treatment facilities, and various commercial, industrial and military installations located all over the world.ACCOMPLISHMENT

SUMMARY

Professional Engineer Earned a professional engineering license in the state of Iowa. License number 17771.Engineer of Record Engineer of Record for many flood control structures around New Orleans following hurricane Katrina and the rebuilding effort. Also served as Engineer of Record for various military projects located all over the world.Seismic Walkdowns Performed plant walkdowns while interfacing with various departments.

A-21 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 , Exelon.EDUCATION Bradley University, Peoria, IL -Bachelor of Science in Civil Engineering, May 2001 QUALIFICATIONS AND TRAINING Professional Engineer in the Branch of Structural Engineering, Iowa Engineering and land Surveying Board, License 17771 EPRI Seismic Walkdown Engineer (SWE) training, 2012 A-22 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ,( 2 1 Upt OE Certificate of Completion Kevin Hall Training on Near Term Task Force Recommendation 2.3-Plant Seismic Walkdowns June 27, 2012 Date Robert K. Kassawara EPRI Manager, Structural Reliability

& Integrity A-23 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Tribhawan Ram EDUCATION:

B.S. -Electrical Engineering, Punjab University, India, 1972 M.S. -Electrical Engineering, University of Cincinnati, 1977 M.S. -Nuclear Engineering, University of Cincinnati, 1982 M.B.A. -Bowling Green State University, 1996 PROFESSIONAL REGISTRATION:

State of Ohio PROFESSIONAL HISTORY: Stevenson

& Associates, Inc., Senior Engineer, 2011 -present Public Service Electric & Gas Co., Senior Plant Systems Engineer, Hancock Bridge, NJ, 2007 -2011 Entergy Corporation, Plymouth, Massachusetts, Senior Design Engineer, 2002-2007 Various Companies, Contract Consulting Project Engineer, 1996 -2002 Public Service Electric & Gas Co., Senior Staff Engineer, Hancock Bridge, NJ, 1983-1990 Toledo Edison Co., Toledo, Ohio, Senior Assistant Engineer, Associate Engineer, 1978-1983 PROFESSIONAL EXPERIENCE:

• Electrical and Controls Design Engineering

• Plant Systems Engineering 0 Transformer and Relay(s) Spec Developer* Plant Modification Engineering

• Systems and Component Test Engineering

• Factory Testing Witness 0 6 Month BWR Systems Engineering Training* ETAP Trained* Arc Flash IEEE 1584 Trained Mr. Ram has over 28 years of electrical project, design and systems engineering experience in US nuclear plants. As part of the Seismic Margin Analysis (SMA) team, in 2012, Mr. Ram is leading the electrical engineering EPRI methodology effort to perform Post-Fukushima relay list development and evaluation to support Safe Shutdown Equipment List (SSEL), including relay functional screening and chatter analysis, for Taiwan nuclear plants (both PWR and BWR). In this effort, he is preparing the final reports including recommendations to replace any bad actor relays. Mr. Ram is preparing proposals to replace these bad actors including modification package development for field replacement of these relays. He has prepared proposals to lead similar forthcoming relay evaluation efforts for several Westinghouse plants in the USA. Mr. Ram has either prepared or peer reviewed the Seismic Walkdown Equipment Lists (SWEL 1 &2) for several Exelon Plants.A-24 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 As a senior plant systems engineer, Mr. Ram has: 1. Developed several test plans for modification packages for the replacement of low and medium voltage circuit breakers (ABB K-Line to Square D Masterpact; GE Magneblast to Wyle Siemens) and for the replacement of the entire Pressurizer Heater Bus switchgear;

2. Personally been involved in execution of these test plans during refueling outages;3. Witnessed factory testing of Pressurizer Heater Bus Switchgear;

4. Interfaced with NRC in their biennial Component Design Basis Inspections (CDBI); Interfaced with INPO in their biennial evaluations;

5. Developed and executed Performance Centered Maintenance (PCM) strategies for Motor Control Centers (MCCs) and low and medium voltage circuit breakers and switchgear; 6.Developed and executed margin improvement strategies for pressurizer heater busses, for twin units, through obtaining funds and then equipment replacement;

7. Developed refueling outage scoping for low and medium voltage circuit breakers and MCCs through working with outage group, maintenance, operations, and work MGMT; 8. Resolved breaker grease hardening issue for ABB K-Line breakers, over a two year period, through working with maintenance and work MGMT in implementing accelerated overhauls with better grease; 9. Trained operations and engineering personnel in the Engaging People and Behavior Change process, as part of a case study team and; 10.Resolved day to day operations and maintenance issues with systems of responsibility (low and medium voltage systems)Mr. Ram has regularly participated in the EPRI annual circuit breaker user group conferences; at the 2011 meeting, he made a presentation on circuit breaker as found testing vis-a-vis protection of equipment, cables, and containment penetrations, and selective coordination preservation.

As a Senior Design Engineer, Mr. Ram has: 1. Developed specifications and procured 345/4.16/4.16 kV and 23/4.16/4.16 kV transformers (ranging up to $1.25 million);

2. Prepared a modification package to install the 23 kV/4.16 kV/4.16 kV transformer, including leading the project team to get this transformer successfully installed, tested, and placed in service; 3. Developed ETAP scenarios and performed load flow studies to successfully support the 2006 INPO evaluation;

4. Performed arc flash calculations per IEEE 1584 methodology for 4 kV, 480V Load Centers, and MCCs, enabling a justification of reduced arc flash rated clothing, thereby allowing conversion of OUTAGE PMs into ONLINE PMs and; 5. Performed single point system vulnerability analysis.As a Consulting Lead Project Engineer, Mr. Ram was heavily involved in resolution of the USI A-46 for several plants. He performed an extensive review of dozens of control circuits for relay chattering issues. To replace bad relay actors, Mr. Ram developed and/or supervised the development of many modification packages including:

selection of replacement relays (both protective and auxiliary);

preparation of relay testing specification with civil engineering input; working with and visiting seismic testing facilities for relay qualification and; developing pre and post installation, instructions including test procedures.

He worked closely with teams consisting of maintenance, operations, and work MGMT during the development and implementation of these projects.

Besides the A-46 issue, Mr. Ram first developed and then was personally involved in the implementation of modification packages consisting of Cable, Conduit, Circuit Breaker and motor starter (contactor) replacements.

The following provides a list of USI A-46 resolution projects: Northeast Utilities

-Millstone Station Consumers Power Co. -Palisades Nuclear Station Boston Edison Co. -Pilgrim Nuclear Power Station Commonwealth Edison Company- Dresden Station, Quad Cities Station Tribhawan Ram Page 2 A-25 Quad Cities Generating Station Unit 1 12QO108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Walter Djordjevic EDUCATION:

B.S. -Civil Engineering, University of Wisconsin at Madison, 1974 M.S. -Structural Engineering, Massachusetts Institute of Technology, 1976 PROFESSIONAL REGISTRATION:

State of California, State of Wisconsin, Commonwealth of Massachusetts, State of Michigan, State of Arizona, State of Missouri PROFESSIONAL HISTORY: Stevenson

& Associates, Inc., President 1996 -present; Vice President and General Manager of the Boston area office, 1983 -1995 URS/John A. Blume & Associates, Engineers, Boston, Massachusetts, General Manager, 1980 -1983;San Francisco, California, Supervisory Engineer, 1979 -1980 Impell Corporation, San Francisco, California, Senior Engineer, 1976 -1979 Stone & Webster Engineering Corporation, Boston, Massachusetts, Engineer, 1974 -1976 PROFESSIONAL EXPERIENCE: " Structural Engineering

• Structural Dynamics* Seismic Engineering

• Construction

• Vibration Engineering

• Expert Witness* Committee Chairman Mr. Djordjevic founded the Stevenson

& Associates Boston area office in 1983 and serves as President and General Manager. Mr. Djordjevic is expert in the field of structural engineering

-more specifically, in the areas of structural vulnerabilities to the effects of seismic and other extreme loading phenomena.

As a structural dynamicist, Mr. Djordjevic also heads the Vibration Engineering Consultants corporate subsidiary of Stevenson

& Associates for which he has overseen numerous designs of vibration sensitive microelectronics facilities for such clients as IBM, Intel, Motorola and Toshiba. He has personally been involved in such projects as resolvi ng vibration problems due to construction activities for the Central Artery Project (Big Dig) in Boston for which he was retained by Massport.

Finally, Mr.Djordjevic has been personally retained as an Expert Witness a number of times relating to cases involving construction, structural and mechanical issues.He has performed over a thousand hours of onsite seismic and other natural phenomena (including tornados, hurricanes, fire, and flooding) inspection walkdowns to assess structural soundness and vulnerabilities.

He has inspected microelectronics fabrication facilities, power facilities, and hazardous material government and military reservations.

He is one of the most experienced seismic walkdown A-26 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 inspection screening and verification engineers having personally participated in seismic walkdowns at over 50 U.S. nuclear units.In recent years, he has concentrated on screening inspection walkdowns and assessments for resolution of the USI A-46 and seismic IPEEE issues, on numerous facilities.

The following provides a partial list of recent projects: American Electric Power -D.C. Cook Station Boston Edison Co. -Pilgrim Nuclear Power Station (SPRA)Commonwealth Edison Company- Braidwood Station PM, Byron Stationp M , Dresden Stationp M , Quad Cities StationPM Consumers Power Co. -Palisades Nuclear StationPM Entergy -Arkansas Nuclear One Florida Power & Light -Turkey Point Station New York Power Authority

-James A. Fitzpatrick Nuclear Power Plant Niagara Mohawk Power Corporation

-Nine Mile Point Station PM Northern States Power Co. -Monticello Nuclear Generating Plant Northern States Power Co. -Prairie Island Nuclear Generating Plant Omaha Public Power District -Fort Calhoun Station (SPRA)Public Service Electric & Gas -Salem Nuclear Station Rochester Gas & Electric -R.E. Ginna Station Wisconsin Electric -Point Beach Nuclear StationPM (SPRA)Wisconsin Public Service -Kewaunee Nuclear Power PlantPM (SPRA)PM Indicates projects where Mr. Djordjevic served as Project Manager Hanford Reservation Savannah River Plant Reservation Rocky Flats Reservation Tooele US Army Depot Anniston US Army Reservation Umatilla US Army Reservation Newport US Army Reservation Aberdeen US Army Reservation He is a member of the IEEE 344 Standards Committee, Chairman of the ASCE Working Group for Seismic Evaluation of Electrical Raceways, and Chairman of the IES Committee for Microelectronics Cleanroom Vibrations Representative projects include overseeing the SEP shake-table testing of electrical raceways, in-situ testing of control panels and instrumentation racks at various nuclear facilities, equipment anchorage walkdowns and evaluations at various nuclear facilities.

He is the principal author of the CERTIVALVE software package to evaluate nuclear service valves, and contributing author in the development of the ANCHOR and EDASP software packages commercially distributed by S&A.Mr. Djordjevic is expert in the area of seismic fr agility analysis and dynamic qualification of electrical and mechanical equipment.

He has participated in and managed over twenty major projects involving the evaluation and qualification of vibration sensitive equipment and seismic hardening of equipment.

As demonstrated by his committee work and publications, Mr. Djordjevic has participated in and contributed steadily to the development of equipment qualification and vibration hardening methodology.

Walter Djordjevic Page 2 A-27 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 PROFESSIONAL GROUPS Member, Institute of Electrical and Electronics Engineers, Nuclear Power Engineering Committee Working Group SC 2.5 (IEEE-344)

Chairman, American Society of Civil Engineers Nuclear Structures and Materials Committee, Working Group for the Analysis and Design of Electrical Cable Support Systems Member, American Society of Mechanical Engineers Operation, Application, and Components Committee on Valves, Working Group SC-5 Chairman.

Institute of Environmental Sciences, Working Group foe Standardization of Reporting and Measuring Cleanroom Vibrations PARTIAL LIST OF PUBLICATIONS 1979 ASME PVP Conference, San Francisco, California, "Multi-Degree-of-Freedom Analysis of Power Actuated Valves", Paper No. 79-PVP-106.

1983 ASME PVP Conference, Portland, Oregon, "A Computer Code for Seismic Qualification of Nuclear Service Valves", Paper No. 83-PVP-81.

1983 ASME PVP Conference, Portland, Oregon, "Qualification of Electrical and Mechanical Equipment at Rocky Flats Reservation Using Prototype Analysis".

1984 ANS Conference, "Qualification of Class 1E Devices Using In-Situ Testing and Analysis." 1986 Testing of Lithography Components for Vibration Publishing Sensitivity, Microelectronics, Cahners 1990 Nuclear Power Plant Piping and Equipment Confer ence, "Development of Generic Amplification Factors for Benchboard and Relay Cabinet Assemblies", Paper No. 106, Structures and Components Symposium, held by North Carolina State University 1991 Electric Power Research Institute, "Development of In-Cabinet Response Spectra for Benchboards and Vertical Panels," EPRI Report NP-7146 Walter Djordjevic Page 3 A-28 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Certificate of Completion Walter Djordjevic Successfullij Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Bruce M. Lor4f- Instructor NTTF 2.3 Seismic Walkdown Course Date: 06/26/12 A-29 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 275 Mishawuin Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 Fax (781) 933-4428 w ivev.ýcsa.

corn Stevenson

& Associates Engineering Solutions for Nuclear Power Todd A Bacon Education 1976- 1980 University of Illinois -Urbana-Champaign Bachelor of Science -Civil Engineering Registration

/ Certification Professional Engineer:

California License No. C-0336104 (Civil), Georgia License. No. 015562, Ohio License No. E-57497 Professional History 2012 -Present Stevenson

& Associates, Charlotte, North Carolina, Senior Consultant and General Manager, Charlotte, NC Office 1980-2012 AREVA Inc., Charlotte, NC, Engineering Manager Professional Experience Mr. Bacon has thirty years of experience in the design and modification of mechanical and structural systems. His responsibilities as an Engineering Manager have included work from the conceptual design through to the installation support phases of projects.

Mr. Bacon has served as Project Engineer and Project Manager for numerous work scope efforts, including coordination of personnel in multiple locations.

The efforts have also included significant client and/or regulatory interface, as required.

These activities have also included responsibility for budgets, schedules and the technical accuracy of work performed.

In addition, he has extensive experience in proposal and report development, as well as personnel training activities.

Mr. Bacon has thirty years of experience in the design and modification of mechanical and structural systems. His responsibilities as an Engineering Manager have included work from the conceptual design through to the installation support phases of projects.

Mr. Bacon has served as Project Engineer and Project Manager for numerous work scope efforts, including coordination of personnel in multiple locations.

The efforts have also included significant client and/or regulatory interface, as required.

These activities have also included responsibility for budgets, schedules and the technical accuracy of work performed.

In addition, he has extensive experience in proposal and report development, as well as personnel training activities.

Mr. Bacon's work has involved extensive use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, including various piping system related committees.

These have included the design group for the HDPE buried pipe group of Section III, and the Flaw Analysis group of Section XI.Other Code experience includes the American Institute of Steel Construction (AISC), American Concrete BOSTON*CLEVELAND eCHICAGO PMINNEA POLISPHOENIX A-30 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 275 Mishawum Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 Fax (781) 933-4428 wwwv.vecsa.com.

Stevenson

& Associates Engineering Solutions for Nuclear Power Institute (ACI), and ASME (ANSI) B3 1.1 and B31.3 codes. He serves on the AREVA College of Experts in the areas of structural and dynamic analysis and is also fluent in using numerous piping and finite element computer programs, as well as in typical frame analysis programs.Engineering Manager, Civil and Layout Department AREVA NP Inc.Mr. Bacon served as an Engineering Manager in the Civil and Layout Department in Charlotte, North Carolina.

In this role he was responsible for the efforts involving work on the 3D model for an AREVA US EPR plant being designed for the Calvert Cliffs site in Maryland.

His areas of responsibility also included the balance of plant piping system design efforts for the plant. In this role, he was involved with interfaces with numerous groups utilizing the 3D model information, as well as consortium partner Bechtel Power, and AREVA offices throughout the US and Europe who served as subcontractors for various portions of the overall project scope of work. This included coordinating the efforts of approximately fifty individuals for these efforts involving technical resolution of issues, manpower planning, personnel issues, and development of the group.In addition to the managerial responsibilities, he was a member of the AREVA College of Experts in the area of mechanics and fluid mechanics.

This group was comprised of approximately one percent of the company worldwide which served as the technical leaders for the company, sharing best practices and knowledge throughout the global organization.

In addition to the New Plants activities in the US, Mr. Bacon supported efforts involving current activities for the International Thermonuclear Experimental Reactor (ITER) effort in which AREVA had the responsibility for the Cooling System involving the piping system evaluations and development of Technical Guides and impact to the building resulting from the piping system.He previously served as an Engineering Manager in the Structural and Engineering Mechanics Group, working on projects involving operating plants. As a Project Engineer and Manager, he helds responsibility for leading project teams in technical areas, as well as in budget and schedule item tracking functions.

Examples of typical projects include the following:

Mixed Oxide (MOX) Fuel Fabrication Facility, Savannah River Site -Conducted third party review of overall project identifying ways to achieve efficiencies and improve production rates for the building design and construction effort. This resulted in numerous recommendations for the site to improve production in the areas of scheduling, group interfacing (engineering disciplines, construction, etc.), procedural development as well as improvements through procedural revisions.

This also included performing as the lead engineer on projects for the facility involving development of procedures for field routing of small bore piping systems, as well as conduit runs.ECCS Debris Blockage Issue, Tokyo Electric Power Company (TEPCO) -Established contact and led proposal efforts to obtain contracts for ECCS suction strainer replacements for first plant performing this BOSTON&CLEVELAND

• CHICAGOoMINNEAPOLIS&PHOENIX A-31 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 275 Mishawum Road, Suite 200, Woburn, MA 01801 ATel (781) 932-9580 Fax (781) 933-4428 wWm.vecsa.CoM Stevenson

& Associates Engineering Solutions for Nuclear Power scope in Japan. Subsequently won contracts for two additional TEPCO units as well, resulting in $ 8M in revenue for AREVA. This work involved extensive interface and oversight of the strainer hardware vendor during the design, fabrication and construction phases of the projects.ASME BPVC Work, Various Facilities

-Served in positions of increasing responsibility performing and reviewing ASME Boiler and Pressure Vessel Code work in the Structural and Engineering Mechanics Group. Work included Class 1 analyses of flued heads, mechanical'equipment evaluations and numerous piping system analyses.ECCS Debris Blockage Issue, involving numerous US BWR clients -Served in various roles including Project Engineer, Project Manager, and Technical Consultant.

Had a significant amount of involvement with this issue including involvement with the BWR Owner's Group for this issue spanning numerous years.GL 96-06 Operability and Design Basis Resolution, Oconee Nuclear Station, Duke Power -Served as the Project Engineer for the Operability Evaluation for the Oconee Nuclear Station in an effort to show all three units operable under the additional-loadings resulting from the USNRC Generic Letter. This assessment included evaluation of the LPSW system, including piping, supports, equipment nozzles, as well as structural platforms and associated components.

In addition, operability guidelines were developed for Oconee during this effort.Reactor Cavity Drain Line Modifications, Palisades Nuclear Power Plant, Consumers Power -Project Manager for the Reactor Cavity Drain Line modifications and letdown piping support modifications at the Palisades Plant. Work scopes included both engineering functions and the generation of modification package paperwork.

NRC Bulletin 79-14 Large-Bore Piping Project Evaluation, D. C. Cook Nuclear Power Plant, Indiana/Michigan Power -Work included serving as Project Engineer to evaluate the adequacy of D.C.Cook's NRC Bulletin 79-14 Large-Bore Piping Project. The work scope involved supervising a project team performing piping and piping support evaluations.

Conclusions drawn from this studyhave enabled the client to realize significant cost savings during recent maintenance outages through discrepancy trending and margin assessment studies.Reactor Pressure Vessel Bottom Head Drain Line Unplugging Project, Dresden Nuclear Generating Station Units 2 & 3, Commonwealth Edison. Included serving as Project Engineer responsible for unplugging reactor pressure vessel bottom head drain lines for Dresden Units 2 and 3. This project was successfully completed within schedule and budget constraints, and also was part of the Unit 2 critical path outage work.HPCI System Sparger Modification, Quad Cities Nuclear Generating Station, ComEd -Served as the Structural and Engineering Mechanics Project Engineer and Manager for Quad Cities Unit 1 and 2 high pressure coolant injection (HPCI) system modification, which resulted in the addition of a sparger assembly inside the torus. The project also included the addition of platforms to provide accessibility for personnel performing maintenance activities at both units.Hardened Wetwell Vent Project Third Party Reviews, Dresden and Quad Cities Nuclear Generating BOSTON.CLEVELAND

• CHICAGOeMINNEAPOL!S*PH OEN!IX A-32 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 275 Mishawum Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 Fax (781) 933-4428 www. vecsa.com Stevenson

& Associates Engineering Solutions for Nuclear Power Stations, CornEd -Led the third party reviews of the hardened wetwell vent projects for the Dresden and Quad Cities stations.

These projects involved the evaluation of existing, as well as new, piping and auxiliary steel. Design codes used for the mechanical work included ASME Section III, Subsections NC, ND, NE and NF, as well as AISC and Uniform Building Code (UBC) standards for the structural evaluations.

Structural Projects, Various Facilities

-Past projects have included extensive structural experience, such as the Hope Creek Nuclear Generating Station's drywell inner water seal plate analysis, and also Mark I piping and pipe support evaluations.

Previous work also included extensive experience working on various mechanical and structural design projects.Licensing and Special Projects, Comanche Peak Steam Electric Station, TUElectric

-Involved in licensing and special studies projects for the Comanche Peak Station.SSFIAudit Responses, CornEd -Participated in responding to concerns raised during safety system functional inspection (SSFI) audits.Project Summary Reports and Operability Guidelines, ComEd and AEPSC -Wrote numerous project summary reports and operability guidelines for Commonwealth Edison (CoinEd) and American Electric Power Company (AEPC).Piping, Piping Support and HVAC Modifications, Various Facilities

-Served as Project Engineer for piping, piping support and HVAC modification work for various nuclear plants, including Dresden Units 2 and 3, Quad Cities Units 1 and 2, D. C. Cook Units I and 2, and Duane Arnold. Project Engineer responsibilities included coordinating schedule and budget issues, as well as addressing technical questions as they arose.Control Rod Drive Frame Analysis, Browns Ferry Nuclear Power Plant, Tennessee Valley Authority (TVA) -Involved in the analysis of the control rod drive frames for the Browns Ferry Plant.BOSTON eCL EVELA ND eCHICAGO @MINNEA POIS *PHOENIX A-33 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Certificate of Completion Todd Bacon Successfullyj Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Bruce M.LEf1y -Instructor NTTF 2.3 Seismic Walkdown Course Date: 06/26/12 A-34 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-1 2-169 B Equipment Lists Appendix B contains the equipment lists that were developed during SWEL development.

Note that because no SWEL 2 or Rapid Drain-Down items existed for Quad Cities Generating Station Unit 1, there is no Base List 2, SWEL 2, or Rapid Drain-Down Equipment List.The following contents are found in Appendix B: SW EL Approval Signature Page ......................................................................

B-2 Table B-ia. Base List 1 a -Items Exclusive to Unit 1 ............................................

B-3 Table B-lb. Base List lb -Items Common to Units 1 and 2 .................................

B-15 T able B -2 .S W E L 1 .....................................................................................

B -18 B-1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Stevenson

& Associates Seismic Walkdown Interim Report, Revision 0 In Response to NTTF Recommendation 2.3: Seismic Quad Cities Generating Station Unit 1 Tony Perez 7/27/2012 Equipment Selection Preparer date Kim L. Hull ' 7/27/2012 Equipment Selection Reviewer date Station Opqfations Staff MeAer --Refer to Attachment 3 for synopsis of Station Operations role and responsibility.

B-2 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Table B-la. Base List la -Items Exclusive to Unit I ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION VLV, PNEUMATIC MAIN STEAM 1-0203-0001AH25 INBOARD ISOLATION VALVE RX RB 592 H-15 VLV, PNEUMATIC MAIN STEAM 1-0203-0001BH25 INBOARD ISOLATION VALVE RX RB 592 H-15 VLV, PNEUMATIC MAIN STEAM 1-0203-0001CH25 INBOARD ISOLATION VALVE RX RB 592 H-16 VLV, PNEUMATIC MAIN STEAM 1-0203-0001DH25 INBOARD ISOLATION VALVE RX RB 592 H-16 VLV, PNEUMATIC MAIN STEAM 1-0203-0002AH25 OUTBOARD ISOLATION VALVE RX RB 591 G-15 VLV, PNEUMATIC MAIN STEAM 1-0203-0002BH25 OUTBOARD ISOLATION VALVE RX RB 591 G-15 VLV, PNEUMATIC MAIN STMAIN STEAM OUTBOARD ISOLATION 1-0203-0002CH25 VALVE RX RB 591 G-16 VLV, PNEUMATIC MAIN STEAM 1-0203-0002DH25 OUTBOARD ISOLATION VALVE RX RB 591 G-16 1-0203-1A VALVE, MSIV INBOARD RX RB 592 H-15 1-0203-1A-1 SOV, FOR MSIV RX RB 592 H-15 1-0203-1A-2 SOV, FOR MSIV RX RB 592 H-15 1-0203-1AA AIR ACCUMULATOR TANK RX RB 592 DRY 1-0203-1B VALVE, MSIV INBOARD RX RB .592 H-15 1-0203-1 B-1 SOV, FOR MSIV RX RB 592 H-15 1-0203-1 B-2 SOV, FOR MSIV RX RB 592 H-15 1-0203-1 BA AIR ACCUMULATOR TANK RX RB 592 DRY 1-0203-1C VALVE, MSIV INBOARD RX RB 592 H-16 1-0203-1 C-1 SOV, FOR MSIV RX RB 592 H-16 1-0203-1 C-2 SOV, FOR MSIV RX RB 592 H-16 1-0203-1 CA AIR ACCUMULATOR TANK RX RB 592 DRY 1-0203-1D VALVE, MSIV INBOARD RX RB 592 H-16 1-0203-1D-1 SOV, FOR MSIV RX RB 592 H-16 1-0203-1 D-2 SOV, FOR MSIV RX RB 592 H-16 1-0203-1DA AIR ACCUMULATOR TANK RX RB 592 DRY 1-0203-2A VALVE, MSIV OUTBOARD RX RB 592 G-15 1-0203-2A-1 SOV, FOR MSIV RX RB 592 G-15 1-0203-2A-2 SOV, FOR MSIV RX RB 592 G-15 1-0203-2AA AIR ACCUMULATOR TANK RX RB 592 DRY 1-0203-2B VALVE, MSIV OUTBOARD RX RB 592 G-15 1-0203-2B-1 SOV, FOR MSIV RX RB 592 G-15 1-0203-2B-2 SOV, FOR MSIV RX RB 592 G-15 1-0203-2BA AIR ACCUMULATOR TANK RX RB 592 DRY 1-0203-2C VALVE, MSIV OUTBOARD RX RB 592 G-16 1-0203-2C-1 SOy, FOR MSIV RX RB 592 G-16 1-0203-2C-2 SOV, FOR MSIV RX RB 592 G-16 1-0203-2CA AIR ACCUMULATOR TANK RX RB 592 DRY 1-0203-2D VALVE, MSIV OUTBOARD RX RB 592 G-16 Table B-Ia Page 1 of 12 B-3 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION 1-0203-2D-1 SOV, FOR MSIV RX RB 592 G-16 1-0203-2D-2 SOV, FOR MSIV RX RB 592 G-16 1-0203-2DA AIR ACCUMULATOR TANK RX RB 592 DRY 1-0203-3A VALVE, ERV RX RB 614 K-15 1-0203-3B VALVE, ERV RX RB 614 K-15 1-0203-3C VALVE, ERV RX RB 614 J-1 7 1-0203-3D VALVE, ERV RX RB 614 J-16 1-0203-3E VALVE, ERV RX RB 614 K-15 1-0203-4A VALVE, SRV RX RB 614 J-15 1-0203-4B VALVE, SRV RX RB 614 J-15 1-0203-4C VALVE, SRV RX RB 614 J-17 1-0203-4D VALVE, SRV RX RB 614 J-16 1-0203-4E VALVE, SRV RX RB 614 J-15 1-0203-4F VALVE, SRV RX RB 614 J-15 1-0203-4G VALVE, SRV RX RB 614 J-17 1-0203-4H VALVE, SRV RX RB 614 J-16 VALVE, PNUEMATIC 1B RECIRC 1-0220-44 LOOP SMPL UPSTREAM SV RX RB 623 K-17 VALVE, PNUEMATIC 1B RECIRC 1-0220-45 LOOP SMPL DOWNSTREAM SV RX RB 624 K-18 1-0302-19A SOV, B/U SCRAM CRP RB 595 L-17 1-0302-19B SOV, B/U SCRAM CRP RB 595 L-17 SOV, SDV VNT & DRN 1A 1-0302-20A SCRAM PILOT SO CRP RB 595 L-17 SOV, SDV VNT & DRN 1B 1-0302-20B SCRAM PILOT SO CRP RB 595 L-17 VALVE, NO. BNK SDV VNT 0302-21A ASSY -1A SDV INBD VENT VLV CRP RB 595 L-13 ASSY -1A SDV OUTBD VENT 1-0302-21 B VLV CRP RB 595 L-13 VALVE, SO. BNK SDV VNT -1 B 1-0302-21C SDV INBD VENT VLV CRP RB 595 L-18 VALVE, SO. BNK SDV VNT- lB 1-0302-21D SDV OUTBD VENT VLV CRP RB 595 L-12 VALVE, NO. BNK SDV DRN -1A 1-0302-22A SDV INBD DRN VLV CRP RB 595 H-14 VALVE, NO. BNK SDV DRN -1A 1-0302-22B SDV OTBD DRN VLV CRP RB 595 H-14 VALVE, SO. BNK SDV DRN -1B 1-0302-22C SDV INBD DRN VLV CRP RB 595 H-14 VALVE, SO. BNK SDV DRN -1 B 1-0302-22D SDV OUTBD DRN VLV CRP RB 595 J-18 ACCUMULATOR (26-31 G-8 1-0305-125-26-31 (South)) CRD RB 595 ACCUMULATOR (30-03 H-1 1-0305-125-30-03 (South)) CRD RB 595 ACCUMULATOR (34-03 J-1 1-0305-125-34-03 (North)) CRD RB 595 Table B-la Page 2 of 12 B-4 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION ACCUMULATOR (34-35 J-9 1-0305-125-34-35 (North)) CRD RB 595 -CRD SCRAM Inlet Valve (26-31 G-1-0305-126-26-31 8 (South)) CRD RB 595 -CRD SCRAM Inlet Valve (30-03 1-0305-126-30-03 H-1 (South)) CRD RB 595 -CRD SCRAM Inlet Valve (34-03 J-1-0305-126-34-03 1 (North)) CRD RB 595 -CRD SCRAM Inlet Valve (34-35 J-1-0305-126-34-35 9 (North)) CRD RB 595 -CRD SCRAM Outlet Valve (26-31 1-0305-127-26-31 G-8 (South)) CRD RB 595 -CRD SCRAM Outlet Valve (30-1-0305-127-30-03 03 H-1 (South)) CRD RB 595 -CRD SCRAM Outlet Valve (34-03 1-0305-127-34-03 J-1 (North)) CRD RB 595 -CRD SCRAM Outlet Valve (34-1-0305-127-34-35 35 J-9 (North)) CRD RB 595 0305-26-31 HCU -(26-31 G-8 (South)) CRD RB 595 0305-30-03 HCU -(30-03 H-1 (South)) CRD RB 595 0305-34-03 HCU -(34-03 J-1 (North)) CRD RB 595 0305-34-35 HCU -(34-35 J-9 (North)) CRD RB 595 -VALVE, RELIEF -1A RHR PMP 1-1001-125A SUCT HDR RV RH RB 554 M-13 VALVE, RELIEF -1C RHR PMP 1-1001-125C SUCT HDR RV RH RB 554 M-17 HEAT EXCHANGER, 1A RHR 1-1001-145A PUMP RH RB 554 M-13 HEAT EXCHANGER, 1B RHR 1-1001-145B PUMP RH RB 554 M-13 HEAT EXCHANGER, 1C RHR 1-1001-145C PUMP RH RB 554 M-18 HEAT EXCHANGER, 1D RHR 1-1001-145D PUMP RH RB 554 M-18 VALVE, RELIEF -1A RHR HX 1-1001-165A TUBE SIDE RV RH RB 554 M-13 VALVE, RELIEF -1B RHR HX 1-1001-165B TUBE SIDE RV RH RB 580 M-18 VALVE, RELIEF -AA RHR HX 1-1001-166A SHELL SIDE RV RH RB 554 M-13 VALVE, RELIEF -1B RHR HX 1-1001-166B SHELL SIDE RV RH RB 554 M-18 VALVE, HX 3A BYPASS -1A 1-1001-16A RHR HX BYP VLV RH RB 554 M-13 VALVE, HX 3B BYPASS -1B.1-1001-16B RHR HX BYP VLV RH RB 554 M-18 VALVE, LOOP A MIN FLOW- 1A 1-1001-18A RHR LOOP MIN FLOW VLV RH RB 554 L-14 Table B-la Page 3 of 12 B-5 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION VALVE, LOOP B MIN FLOW- 1B 1-1001-18B RHR LOOP MIN FLOW VLV RH RB 554 L-17 VALVE, LOOP A CROSS TIE -1A RHR LOOP X-TIE TO 1B RHR 1-1001-19A LOOP SV RH RB 580 M-14 VALVE, LOOP B CROSS TIE -1B RHR LOOP X-TIE TO 1A RHR 1-1001-19B LOOP SV RH RB 580 M-18 VALVE, RELIEF -1A LPCI LOOP 1-1001-22A RV RH RB 554 L-13 VALVE, RELIEF -1B LPCI LOOP 1-1001-22B RV RH RB 554 L-18 VLV, ISOLATION

-1A CONTAINMENT SPRAY LOOP 1-1001-23A UPSTREAM SV RH RB 595 VLV, ISOLATION

-1B CONTAINMENT SPRAY LOOP 1-1001-23B UPSTREAM SV RH RB 623 VLV, ISOLATION

-1A CONTAINMENT SPRAY LOOP 1-1001-26A DOWNSTREAM SV 'RH RB 595 VLV, ISOLATION

-1B CONTAINMENT SPRAY LOOP 1-1001-26B DOWNSTREAM SV RH RB 623 VALVE, LOOP A OUTBRD -1A 1-1001-28A LPCI LOOP UPSTREAM SV RH RB 554 J-13 VALVE, LOOP B OUTBRD -1B 1-1001-28B LPCI LOOP UPSTREAM SV RH RB 554 K-18 VALVE, LOOP A INBRD -1A LPCI LOOP DWNSTRM VALVE 1-1001-29A GATE MOTOR OPERATED RH RB 554 J-14 VALVE, LOOP B INBRD 1001-29B INBOARD LPCI INJECTION MOV RH RB 554 K-17 VALVE, TORUS CLG -1A 1-1001-34A TORUS SPRAY/CLG SV RH RB 554 L-13 VALVE, TORUS CLG.- 1B 1-1001-34B TORUS SPRAY/CLG SV RH RB 554 L-18 VALVE, TORUS CLG -1A 1-1001-36A TORUS CLG SV RH RB 554 L-14 VALVE, TORUS CLG -1B 1-1001-36B TORUS CLG SV RH RB 554. L-17 VLV, ISOLATION

-1A TORUS 1-1001-37A SPRAY SV RH RB 554 VLV, ISOLATION

-lB TORUS 1-1001-37B SPRAY SV RH RB 554 VALVE, RELIEF -U-1 HEAD 1-1001-59 SPRAY HDR RV RH RB 591 G-16 Table B-Ia Page 4 of 12 B-6 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION VALVE, HX DISCH -RHR SERV 1-1001-5A WTR FROM 1A RHR HX FCV RH RB 554 M-13 VALVE, HX DISCH -RHR SERV 1-1001-5B WTR FROM 1B RHR HX FCV RH RB 554 M-18 1A RHR SERVICE WATER MAIN 1-1001-65A PUMP RH TB 547 C-17 1C RHR SERVICE WATER MAIN 1-1001-65C PUMP RH TB 547 C-19 VALVE, CHECK, TESTABLE -A RHR LOOP TESTABLE CHECK 1-1001-68A VLV RH RB 579 K-15 VALVE, CHECK, TESTABLE -B LOOP RHR TESTABLE CHECK 1-1001-68B VLV RH RB 579 K-17 1-1 002A PUMP, 1A -RHR PUMP RH RB 554 M-13 1-1 002A-ROB HX, PMP SEAL COOLING RH RB 554 M-13 1-1002B-ROB HX, PMP SEAL COOLING RH RB 554 M-13 1-1 002C PUMP, 1C -RHR PUMP RH RB 554 M-17 1-1 002C-ROB HX, PMP SEAL COOLING RH RB 554 M-18 1-1002D-ROB HX, PMP SEAL COOLING RH RB 554 M-18 1-1003A HX, 1A RHR RH RB 554 M-13 1-1003B HX, 1B RHR RH RB 554 M-14 1-1006A SEPARATOR, CYCLONE RH RB 554 M-13 1-1006C SEPARATOR, CYCLONE RH RB 554 M-18 VALVE -*PMP SUCT ISOL VLV 1-1201-2 (HW) RT RB 623 K-17 VALVE -RECIRC PMP SUCT 1-1201-5 ISOL VLV RT RB 623 K-18 VLV, ISOLATION -RCIC STEAM 1-1301-16-MO SUPPLY ISOL VLV RI RB 592 H-15 VLV, ISOLATION

-*U1 MAIN STM TO RCIC DOWNSTREAM 1-1301-17-MO SV (HW) RI RB 591 G-16 VALVE, BUTTERFLY ISO, FC -SOLENOID UI B TORUS 1-1601-21 VACUUM BKR PC RB 554 AZ315 VLV, 18", +3', DRYWELL VENT 1601-23-AO U-1 DWVENT VLV PC RB 647 L-16 CONTAINMENT RX BLDG EXH -ASSY -U-1 CNMT RX BLDG EXH 1-1601-24-AO VENT VLV PC RB 647 L-16 VALVE, ISOLATION

-N2 PURGE 1-1601-55 TO U-1 CNMT SV PC RB 554 AZ310 ASSY -U-1 DW TORUS XTIE 1-1601-56 VLV PC RB 554 AZ280 Table B-Ia Page 5 of 12 B-7 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION VLV, 1", +1', N2 MAKEUP TO CONTAINMENT

-U-1 N2 MU FROM TO CNMT 1-1601-57-MO DOWNSTREAM SV PC RB 595 J-18 VLV, 1", +1', N2 MAKEUP TO 1-1601-58-AO TORUS PC RB 595 J-18 VLV, 1", +1', N2 MAKEUP TO 1-1601-59-AO DRYWELL PC RB 595 J-18 VLV, 2", +2', U-1 DW VENT 1-1601-62-AO VALVE BYPASS PC RB 647 L-16 VLV, 6", +6'; U-1 CNTMNT SBGT 1-1601-63-AO VENT PC RB 647 L-16 VALVE, PNUEMATIC

-U-1 DW FLR DRN SUMP PMP 1-2001-3 UPSTREAM DSCH VLV RW RB 554 AZI80 VALVE, PNUEMATIC

-U-1 DW FLR DRN SUMP PMP 1-2001-4 DOWNSTREAM DSCH VLV PC RB 554 AZ180 U-1 HPCI PMP UPSTREAM 1-2301-10-MO TEST VLV HP RB 554 1-2301-14-MO U-1 HPCI PMP MIN FLOW VLV HP RB 554 U-1 HPCI STM LINE TO DRN 1-2301-28-AO POT DRN VLV HP RB 554 U-1 HPCI STM LINE TO CONDENSER UPSTREAM DRN 1-2301-29-AO VLV HP RB 554 U-1 HPCI STM LINE DRN LINE 1-2301-31-AO STM TRAP BYP VLV HP RB 554 U-1 HPCI DRN POT TO GL SEAL 1-2301-32-SO CONDENSER SO HP RB 554 U-1 HPCI PMP DOWNSTREAM 1-2301-35-MO TORUS SUCT VLV HP RB 554 U-1 HPCI PMP UPSTREAM 1-2301-36-MO TORUS SUCT VLV HP RB 554 1-2301-3-MO UI HPCI TURB INLET VLV (HW) HP RB 554 VALVE, ISOLATION

-HPCI MAIN 1-2301-4 STEAM SUPPLY HP RB 592 AZ095 1-2301-46-PCV U-1 HPCI CLG WTR PCV HP' RB 554 1-2301-48-MO VLV HP RB 554 U-1 HPCI CLG WTR PMP TEST 1-2301-49-MO VLV HP RB 554 HPCI/ HPCI Turbine Cooling 1-2301-57 Water Pump HP RB 554*U1 MAIN STM TO HPCI 1-2301-5-MO DOWNSTREAM SV (HW) HP RB 554 1-2301-6-MO U-1 HPCI PMP CCST SUCT VLV HP RB 554 VALVE, CHECK -U1 HPCI 1-2301-7 TESTABLE CHECK VALVE HP RB 591 G-16 Table B-Ia Page 6 of 12 B-8 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION 1-2301-9-MO U-1 HPCI PMP DSCH VLV HP RB 554 1-2302 HPCI/ HPCI Pump HP RB 554 1-2303 TURBINE HPCI HP RB 554 1-2304 PUMP U- HPCI CONDENSATE HP RB 554 1-2305 CONDENSER GLAND SEAL HP RB 554 1-2306 EXHAUSTER GLAND HP RB 554 1-2308 UNIT 1 HPCI AUX OIL PUMP HP RB 554 DRY 1-2310 COOLER U-1 HPCI OIL HP RB 554 1-2317-HO U-1 HPCI TURB SV HP RB 554 HOTWELL U-1 HPCI GLAND 1-2319 SEAL CNDSR HP RB 554 1-2321-HO U-1 HPCI TURB CV HP RB 554 HPCI TURBINE CONSOLE INSTRUMENTATION

-*HPCI TURBINE STOP VALVE 1-2341-11-PS TRIPPED (PS11) ISOL HP RB 554 DRY HPCI TURBINE CONSOLE INSTRUMENTATION

-U-1 HPCI HYDRAULIC OIL PI 1-2341-1 1-2341-1-PS SHUTOFF VLV HP RB 554 DRY CONDENSER COND PMP DSCH 1-2399-15-PCV PCV HP RB 554 TURB EXH VACU BKR AC PCI 1-2399-40 VLV HP RB 554 G-14 TURB EXH VACU BKR DC PCI 1-2399-41 VLV HP RB 554 G-14 125 VDC BATT 1 BATTERY, 125V 125 VDC TB 628 G-24 125 VDC BUS 1 BUS 1, 125 VDC BATTERY 125 VDC TB 615 G-24 125 VDC BUS 1A BUS 1A, 125 VDC BATTERY 125 VDC TB 615 H-24 125 VDC BUS 1A-' BUS 1A-1, 125 VDC BATTERY 125 VDC TB 615 H-24 125VDCBUSlB BUS,TBRES1B 125VDC TB 615 H-24 125 VDC BUS 1B-1 BUS, TB RES 1B-1 125 VDC TB 615 H-24 PUMP, DG COOLING -UI DIESEL GENERATOR COOLING 1-3903 WATER PUMP DGW TB 547 C-21 VLV, ISOLATION, 1A TBCCW HX 1-3903A DISCHARGE DGW TB 611 C-16 TANK, AIR RECEIVER -RECEIVER GAS (IDNS 1-4600A PRESSURE VESSEL) SA DG 595 G-23 TANK, AIR RECEIVER -RECEIVER GAS (IDNS 1-4600B PRESSURE VESSEL) SA DG 595 G-23 TANK, AIR RECEIVER -RECEIVER GAS (IDNS 1-4600C PRESSURE VESSEL) SA DG 595 G-23 Table B-Ia Page 7 of 12 B-9 Quad Cities Generating Station Unit 1 12QO108;40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION TANK, AIR RECEIVER -RECEIVER GAS (IDNS 1-4600D PRESSURE VESSEL) SA DG 595 G-23 1-4604 DRYER, AIR SA DG 595 G-23 1-4605 TANK, BLOWDOWN SA DG, 595 G-23 1-4614 LUBRICATOR, AIR LINE SA DG 595 G-23 SWITCH, PRESS. -*U1 DG PS 1-1-4641-42A 4641-42A SHUTOFF VLV SA DG 595 G-23 SWITCH, PRESS. -*U-1 DG PS 1I 1-4641-42B 4641-42B SHUTOFF VLV SA DG 595 G-23 VALVE, AIR START RELAY -AIR LINE TO U-1 DG AIR START 1-4699-226 MOTOR AO SA DG 595 G-23 VALVE, RELIEF -DG 1A AIR 1-4699-306A RCVR TK RELIEF VLV SA DG 595 G-23 VALVE, RELIEF -DG 1B AIR 1-4699-306B RCVR TK RELIEF VLV SA DG 595 G-23 VALVE, RELIEF -DG 1C AIR 1-4699-306C RCVR TK RELIEF VLV SA DG 595 G-23 VALVE, RELIEF -DG 1D AIR 1-4699-306D RCVR TK RELIEF VLV SA DG 595 G-23 SOV, START AIR -AIR LINE TO 1-4699-310 DG 1 AIR START MOTOR SO SA DG 595 G-23 1-4720-PCV DRYWELL AIR INTAKE VALVE IA RB 595 J-14 VLV, 1", +1', DRYWELL PNEUMATIC

-VALVE SOLENOID TO DW 1-4721-PCV DOWNSTREAM INLET VLV IA RB 595 J-14 1-5201 TANK, FUEL OIL DO 0 595 -VALVE, RELIEF -DIESEL GENERATOR FUEL OIL TRANSFER PUMP DISCHARGE 1-5201-RV RELIEF VALVE DO DG 595 G-23 SOV, DAYTANK FILL -DG 1 DAY TK FILL LINE FROM TRANSFER 1-5201-SOV PMP INLET SO DO DG 595 G-23 1-5202 TANK, FUEL OIL DAY DO DG 595 G-23 1-5203 PUMP, FUEL OIL TRANSF DO DG 595 G-23 1-5206 FILTER, FUEL OIL DO DG 595 G-23 1-5207 STRAINER, FUEL OIL DO DG 595 G-23 1-5208 PUMP, FUEL PRIME DO DG 595 G-23 1-5209 PUMP, ENG DRVN FUEL DO DG 595 G-23 FAN, ROOM VENTILAT -DG 1-5727 ROOM VENT FAN VD DG 595 G-23 COOLER, CUBICLE -1A RHRSW 1-5745A PMP-CUBICAL COOLER VD TB 547 C-18 Table B-la Page 8 of 12 B-1 0 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION COOLER, CUBICLE -HEAT EXCHANGER CONTACT STEAM-1-5745C LIQUID VD TB 547 C-20 COOLER, CUBICLE -FAN RHR EMERGENCY AIR HANDLING 1-5746A UNIT 1A VD RB 580 N-14 COOLER, CUBICLE -COOLER 1-5746B 1B RHR ROOM VD RB 580 M-18 COOLER, CUBICLE -UI HPCi 1-5747 ROOM EMERGENCY COOLER VD TB 554 G-14 COOLER, CUBICLE -1A 1-5748A CS/RCIC PMP RM COOLER VD RB 560 G-18 COOLER, CUBICLE -1B CS PMP 1-5748B RM COOLER VD RB 560 M-13 COOLER, CUBICLE -1DG CW 1-5749 PMP CUB COOLER VD TB 547 C-22 DAMPER -,DG ROOM VENTILATION DAMPER 1-5772-89 CONTROL VD DG 595 G-23 1-6601 DG, UNIT 1 DG DG 595 G-23 1-6650 PUMP, ENG DRVN SCAVEN DG DG .595 G-23 PUMP, PUMP DG ENGINE DRIVEN MAIN LUBE + PISTON 1-6651 CLG DG DG 595 G-23 1-6654 HX, DG LUBE OIL DG DG 595 G-23 1-6655 FILTER, LUBE OIL DG DG 595 G-23 1-6661A HX, DG COOLING DG DG 595 G-23 1-6661B HX, DG COOLING DG DG 595 G-23 1-6662 TANK, EXPANSION DG DG 595 G-23 VALVE, TEMP REG -U-1 DG'!1-6663 CLG WTR TEMP REG VLV DG DG 595 G-23 1-6664 HEATER, IMMERSION DG DG 595 G-23 1-6665 MANIFOLD, ENG CLG DG DG 595 G-23 1-6666A PUMP, ENG DRVN CLG DG DG 595 G-23 1-6666B PUMP, ENG DRVN CLG DG DG 595 G-23 1-6667 SILENCER, EXHAUST DG TB 639 G-24 1-6668 FILTER, INTAKE AIR DG TB 615 G-23 1-6703-13 SWGR 13 4160VAC TB 615 G-22 1-6704-14 SWGR14 4160VAC TB 615 H-22 1-6705-13-1 SWGR 13-1 4160VAC TB 639 H-14 1-6706-14-1 SWGR 14-1 4160VAC TB 639 H-16 1-7100 TRANSFORMER 18 4160V-480V 4160VAC RB 647 H-13 1-7100-18 SWGR 18 480VAC RB 647 H-13 1-7200-19 SWGR 19 480VAC RB 647 H-15 1-7800-18195 MCC -MCC 18/19-5 480VAC RB 595 N-17 1-7800-18-1A MCC -MCC 18-1A 480 VAC RB 623 M-17 MCC DIST PANEL -MCC 18-1A-1-7800-181A1 1 PNL 1 120/208 RB 623 N-16 Table B-la Page 9 of 12 B-1 1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION 1-7800-18-1B MCC -MCC 18-1B 480 VAC RB 623 N-17 177800-18-2 MCC -MCC 18-2 480 VAC TB 615 G-22 1-7800-18-4 MCC -MCC 18-4 480VAC TB 615 E-24 1-7800-19-1 MCC -MCC 19-1 480 VAC RB 623 M-17 1-7800-19-2 MCC -MCC 19-2 480 VAC TB 615 G-23 1-7800-19-3 MCC 19-3 TB 615 G-13 1-7800-19-4 MCC -MCC 19-4 480 VAC RB 623 N-18'1-7800-19-6 MCC 19-6 RB 623 M-17 1-8300-1 CHRGR #1, 125V DC TB 615 G-24 1-8300-1A CHRGR #1A, 125V DC TB 615 G-24 1-8350 CHRGR #1, 250V DC TB 615 G-24 CONTAINMENT 1G DW COOLER UPSTREAM AIR SMPL 1-8801A-AO VLV DAP RB 623 L-14 VALVE, PNUEMATIC

-U-1 CONTAINMENT IE DW COOLER 1-8801B-AO UPSTREAM AIR SMPL VLV DAP RB 623 L-14 VALVE, PNUEMATIC

-U-1 CONTAINMENT HEAD VENT AIR 1-8801C-AO SMPL VENT DAP RB 623 L-14 VALVE, PNUEMATIC

-U-1 CONTAINMENT TORUS 1-8801D-AO UPSTREAM AIR SMPL VLV DAP RB 554 AZ180 CONTAINMENT 1G DW COOLER DOWNSTREAM AIR 1-8802A-AO SMPL VLV DAP RB 623 L-14 VALVE, PNUEMATIC

-U-1 CONTAINMENT 1E DW COOLER 1-8802B-AO DOWNSTREAM AIR SMPL VLV DAP RB 623 L-14 VALVE, PNUEMATIC

-U-1 CONTAINMENT HEAD VENT AIR 1-8802C-AO SMPL VLV DAP RB 623 L-14 VALVE, PNUEMATIC

-U-1 CONTAINMENT TORUS 1-8802D-AO DOWNSTREAM AIR SMPL VLV DAP RB 554 AZ180 VALVE, PNUEMATIC

-U-1 CONTAINMENT AIR SMPL 1-8803 UPSTREAM RETURN VLV DAP RB 554 H-17 VALVE, PNUEMATIC

-U-1 CONTAINMENT AIR SMPL 1-8804 DOWNSTREAM RETURN VLV DAP RB 554 H-17 2201-29A INSTR RACK 2201-29A RM RB 554 2201-29B INSTR RACK 2201-29B RM RB 554 2201-32 RACK, AUTO BLOWDOWN RM RB 623 K-14 2201-5 RACK RM RB 623 K-14 2201-59A RACK RM RB 554 M-14 2201-59B RACK RM RB 554 M-18 2201-6 RACK RM RB 623 L-16 Table B-Ia Page 10 of 12 B-1 2 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION 2201-7 RACK RM RB 595 J-14 2201-70B RACK, ATWS INVERTER B RM SB 595 G-25 2201-73A RACK RM SB 609 G-26 2201-73B RACK RM SB 609 G-26 2201-75 RACK RM RB 554 M-18 2201-8 RACK, AUTO BLOWDOWN RM RB 595 K-17 2212-125 CONTROL RM DG 595 N-13 2212-127 RACK RM DG 595 N-13 2212-32 Wall mounted Panel DG RM DG 595 N-13 2212-45 RACK RM DG 595 N-13 2212-46 RACK, 1/2 DG EXCITER RM DG 595 N-13 2212-50 RACK, 1/2 DG AUX CONTROL RM DG 595 N-13 RACK, U-1 DG RELAY &2251-10 METERING RM DG 595 F-23 2251-100 XFER RM TB 547 C-19 2251-113 RACK, DG ENGINE CONTROL RM DG 595 G-23 2251-12 RACK, DG EXCITER RM DG 595 G-23 2251-86 RACK RM TB 639 H-14 2251-87 RACK RM TB 639 H-16 2251-97 RACK, DG AUX FD TRANSFER RM DG 595 G-23 RACK, DG CWP FEED 2251-98 TRANSFER RM DG 595 G-23 250 VDC BATT 1 BATTERY, 250V 250 VDC TB 628 G-24 250VDC MCC 1 MCC 250 VDC TB 615 G-25 250VDC MCC 1A MCC 250 VDC RB 623 L-19 250VDC MCC 1 B MCC 250 VDC RB 623 N-18 901-3 PANEL PM SB 623 -901-32 PANEL PM SB 595 G-26 901-33 PANEL PM SB 595 H-26 901-36 PANEL PM SB 623 -901-39 PANEL PM SB 595 G-25 901-46 PANEL PM SB 595 G-26 901-47 PANEL PM SB 595 G-26 901-48 PANEL PM SB 595 H-26 901-5 PANEL PM SB 623 -901-50 PANEL PM SB 595 G-27 901-61 PNL, CONTROL PM SB 609 CSR 901-62 PNL, CONTROL PM SB 609 CSR 901-8 PANEL PM SB 623 902-2 PANEL PM SB 623 902-3 PANEL PM SB 623 -902-32 PANEL PM SB 595 F-26 902-33 PANEL PM SB 595 E-26 902-36 PANEL PM SB 623 -902-39 PANEL PM SB 595 E-26 902-46 PANEL PM SB 595 F-26 902-47 PANEL PM SB 595 E-26 902-48 PANEL PM SB 595 E-26 Table B-la Page 11 of 12 B-1 3 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION 902-5 PANEL PM SB 623 902-50 PANEL PM SB 595 F-27 902-61 PNL, CONTROL PM SB 609 CSR 902-62 PNL, CONTROL PM SB- 609 CSR 902-8 PANEL PM SB 623 912-8 PANEL PM SB 623 MCC 18-1A-1 MCC 208 VAC RB 623 N-16 MCC 18-3 MCC 480VAC RB 623 N-15 MCC 19-1-1 MCC 208 VAC RB 623 N-18 MCC 19-1-1 PNL MCC DIST PANEL 208 VAC RB 623 N-18 SWGR 19 TRANSF TRANSFORMER 19 480VAC RB 647 H-15 SWGR 29 TR SWGR 29 480VAC RB 647 H-13 SWGR 31 SWGR 31 4160VAC TB 595 H-11 Table B-Ia Page 12 of 12 B-1 4 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Table B-lb. Base List lb -Items Common to Units 1 and 2 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION UO DIESEL GENERATOR 1/2-3903 COOLING WATER PUMP DGW TB 547 D-21 RECEIVER GAS (IDNS PRESSURE 1/2-4600A VESSEL) SA DG 595 N-13 RECEIVER GAS (IDNS PRESSURE 1/2-4600B VESSEL) SA DG 595 N-13 RECEIVER GAS (IDNS PRESSURE 1/2-4600C VESSEL) SA DG *' 595 N-13 RECEIVER GAS (IDNS PRESSURE 1/2-4600D VESSEL) SA DG 595 N-13 1/2-4604 DRYER, AIR SA DG 595 N-13 1/2-4605 TANK, BLOWDOWN SA DG 595 N-13 1/2-4614 LUBRICATOR, AIR LINE SA DG 595 N-13 VALVE, AIR START RELAY DG 1/2 1/2-4699-226 AIR START AO SA DG 595 N-13 VALVE, RELIEF DG 1/2A AIR RCVR 1/2-4699-306A TK RELIEF VLV " SA DG 595 N-13 VALVE, RELIEFDG 1/2A AIR RCVR 1/2-4699-306B TK RELIEF VLV SA DG 595 N-13 VALVE, RELIEF DG 1/2A AIR RCVR 1/2-4699-306C TK RELIEF VLV SA DG 595 N-13 VALVE, RELIEF DG 1/2A AIR RCVR 1/2-4699-306D TK RELIEF VLV SA DG 595 N-13 SOV, START AIR DG 1/2 AIR 1/2-4699-310 START SO SA DG 595 N-13 TANK, FUEL OIL EDG FUEL OIL:!1/2-5201 STORAGE TANK DO 0 595 VALVE, RELIEF DIESEL GENERATOR FUEL OIL TRANSFER PUMP DISCHARGE 1/2-5201-RV RELIEF VALVE DO DG 595 N-13 SOV, DAYTANK FILL DG 1/2 FUEL OIL DAY TK FILL LINE FROM 1/2-5201-SOV TRANSFER PMP INLET SO DO DG 595 N-13 1/2-5202 TANK, FUEL OIL DAY DO DG 595 N-13 1/2-5203 FEDG FUEL OIL TRANSFER PUMP DO DG 595 N-13 1/2-5206 FILTER, FUEL OIL DO DG 595 N-13 1/2-5207 STRAINER, FUEL OIL DO DG 595 N-13 1/2-5208 PUMP, FUEL PRIME DO' DG 595 N-13 1/2-5209 PUMP, ENG DRVN FUEL DO DG 595 N-13 FAN, ROOM VENTILAT EDG 1/2-5727 ROOM VENT FAN (LARGE FAN)" VP DG 595 N-13 VALVE CR HVAC TRN 'B' RCU 1/2-5741-319A RHRSW SPLY SV VP TB 615 E-23 Table B-lb Page 1 of 3 B-1 5 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION SOV, PILOT -VALVE CR HVAC 1/2-5741-319A TRN 'B' RCU RHRSWSPLY SV VP TB 615 E-23 SOV SOLENOID AD 1/2-574 1-1/2-5741-326 326A,B,C,D,E ISOL DMPRS VP SB 623 G-27 DAMPER +DAMPER CR HVAC 1/2-5741-326E RTN AIR DUCT ISOL VP SB 623 G-26 SOV SOLENOID CR HVAC TRAIN 1/2-5741-330

'B' AHU ISOL DAMPERS VP TB 615 E-24 DAMPER CR HVAC TRAIN 'B' RTN 1/2-5741-330A AIR DUCT ISOL VP TB 615 E-24 DAMPER CR HVAC TRAIN 'B'1/2-5741-330B SPLY AIR DUCT ISOL VP TB 615 E-24 VALVE, FLOW CONTRL FLOW CONTROL VALVE TO B CONTROL 1/2-5741-333 ROOM HVAC RCU VP TB 615 E-24 VALVE, CONTROL, 1-3/8" CONTROL RM TRAIN B HVAC 1/2-5741-341A THERMAL EXPANSION VALVE VP TB 615 E-24 VALVE, CONTROL, 1-3/8" CONTROL RM TRAIN B HVAC 1/2-5741-341B THERMAL EXPANSION VALVE VP TB 615 E-24 VALVE, CONTROL, 1-3/8" CONTROL RM TRAIN B HVAC 1/2-5741-341C THERMAL EXPANSION VALVE VP TB 615 E-24 VALVE, CONTROL, 1-3/8" CONTROL RM TRAIN B HVAC 1/2-5741-341D THERMAL EXPANSION VALVE VP TB 615 E-24 COOLER, CUBICLE 1/2 DG CW 1/2-5749 PMP CUB COOLER VP TB 547 D-21 1/2-5799 COOLER, CUBICLE VP TB 595 G-11 1/2-6601 DG, UNIT 1/2 DG DG 595 N-13 1/2-6650 PUMP, ENG DRVN SCAVEN DG DG 595 N-13 PUMP, ASSY -PUMP DG ENGINE 1/2-6651 DRIVEN MAIN + PISTON CLG DG DG 595 N-13 1/2-6654 HX, DG LUBE OIL DG DG 595 N-13 1/2-6655 FILTER, LUBE OIL DG DG 595 N-13 1/2-6661A HX, DG COOLING DG DG 595 N-13 1/2-6661B HX, DG COOLING DG DG 595 N-13 1/2-6662 TANK, EXPANSION DG DG 595 N-13 1/2-6663 VALVE, TEMP REG DG DG 595 N-13 1/2-6664 HEATER, IMMERSION DG DG 595 N-13 1/2-6665 MANIFOLD, ENG CLG DG DG 595 N-13 1/2-6666A PUMP, ENG DRVN CLG DG DG 595 N-13 1/2-6666B PUMP, ENG DRVN CLG DG DG 595 N-13 1/2-6667 SILENCER, EXHAUST DG DG 615 N-12 1/2-6668 FILTER, INTAKE AIR DG DG 615 N-12 1/2-8350 CHRGR #1/2, 250V DC TB 615 G-24 Table B-I b Page 2 of 3 B-16 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 ID DESCRIPT SYSTEM BUILDING ELEVATION LOCATION AHU FAN MISC/CONTROL RM.1/2-9400-100 AHU/NUS MOD VC TB 615 E-24 UNIT REFRIGERATION CONDENSER UNIT COMPRESSOR 1/2-9400-102 CRANKCASE HEATER VC TB 615 E-24 2212-125 RACK, 1/2 DG ENGINE CONTROL RM DG 595 N-13 2212-127 RACK RM DG 595 N-13 2212-32 Wall mounted Panel DG RM DG 595 N-13 2212-45 RACK RM DG 595 N-13 2212-46 RACK, 1/2 DG EXCITER RM DG 595 N-13 2212-50 RACK, 1/2 DG AUX CONTROL RM DG 595 N-13 912-8 PANEL PM SB 623 Table B-I b Page 3 of 3 B-1 7 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Table B-2. SWEL 1 Item SSEGSeismic New or IPEEE Walkdown Number ID DESCRIPT SYSTEM CLASS BUILDING ELEVATION LOCATION Licensing Function)

Replaced Enhancement Deferred To Comments Basis? F t(s) Equip? ? Outage?1 1-0305-26-31 HCU -(26-31 G-8 (South)) CRD (00) Other RB 595 Y RRC Y 2 1-0305-30-03 HCU -(30-03 H-1 (South)) CRD (00) Other RB 595 Y RRC Y 3 1-0305-34-03 HCU -(34-03 J-1 (North)) CRD (00) Other RB 595 Y RRC Y 4 1-0305-34-35 HCU -(34-35 J-9 (North)) CRD (00) Other RB 595 Y RRC Y Auxiliary

&5 1-4604 DRYER, AIR SA (00) Other DG 595 G-23 Support Y Electrical 6 1-7800-18195 MCC -MCC 18/19-5 480VAC (01) Motor Control Centers RB 595 N-17 Systems Electrical 1-7800-18-1B MCC -MCC 18-1B 480 VAC (01) Motor Control Centers -RB 623 N-17 Systems Y EC 24257 Y Electrical 8 1-7800-18-2 MCC -MCC 18-2 480 VAC (01) Motor Control Centers TB 615 G-22 Systems Y Electrical 9 1-7800-19-1 MCC -MCC 19-1 480 VAC (01) Motor Control Centers RB 623 M-17 Systems Y EC 24258 6Y Electrical 10 25OVDC MCC 1 MCC 250 VDC (01) Motor Control Centers TB 615 G-25 Systems Electrical 11 250VDC MCC 1A MCC 250 VDC (01) Motor Control Centers RB 623 L-19 Y Systems Y _EC 242261 (02) Low Voltage Y Electrical 12 1-7100-18 SWGR 18 480VAC Switchgear RB 647 H-13 Systems Y (03) Medium Voltage Y Electrical Y 13 1-6705-13-1 SWGR 13-1 4160VAC Switchgear TB 639 H-14 Systems Y EC 24279 Y Electrical 14 1-7100 TRANSFORMER 18 4160V-480V 4160VAC (04) Transformers RB 647 H-13 Systems Y 1A RHR SERVICE WATER MAIN 15 1001-65A PUMP RH (05) Horizontal Pumps TB 547 C-17 Y RCIC/DHR 16 1-2302 HPCI/ HPCI Pump HP (05) Horizontal Pumps RB 554 Y RCIC PRA: F-V=8.66e-03 17 1-2304 PUMP U- HPCI CONDENSATE HP (05) Horizontal Pumps RB 554 Y RCIC 18 1-2308 UNIT 1 HPCI AUX OIL PUMP HP (05) Horizontal Pumps RB 554 DRY Y RCIC PUMP, DG COOLING -U1 DIESEL GENERATOR COOLING WATER Y Auxiliary

& PRA: F-V=8.60e-02; 19 1-3903 PUMP DGW (05) Horizontal Pumps TB 547 C-21 Support RAW=8.28 Y Auxiliary

& PRA: F-V=1.95e-02; 20 1-5203 PUMP, FUEL OIL TRANSF DO (05) Horizontal Pumps DG 595 G-23 Y Support RAW=7.92 21 1-1002C PUMP, 1C -RHR PUMP RH (06) Vertical Pumps RB 554 M-17 Y RCIC/DHR PRA: F-V=2.82e-02 VLV, PNEUMATIC MAIN STEAM Y y.22 1-0203-0001AH25 INBOARD ISOLATION VALVE RX (07) Fluid-Operated Valves RB 592 H-15 RCPC/CF Y R 23 1-0203-3A VALVE, ERV RX (07) Fluid-Operated Valves RB 614 K-15 RCPC/CF 24.1-204 VLVRVR (07) Fluid-Operated Valves RB 614 J-15 Y CCC VALVE, PNUEMATIC 1B RECIRC Y 25 1-0220-45 LOOP SMPL DOWNSTREAM SV RX (07) Fluid-Operated Valves RB 624 K-18 RCPC/CF Y Table B-2 Page 1 of 5 B3-18 Quad Cites Generabng Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Seismic New or IPEEE Walkdown Itm ID DESCRIPT SYSTEM CLASS BUILDING ELEVATION LOCATION Licensing Replaced Enhancement Deferred To Comments Number 3-?Function(s)

SBasis? Equip? ? Outage?VALVE, NO. BNK SDV VNT -ASSY y 26 1-0302-21A 1A SDV INBD VENT VLV CRP (07) Fluid-Operated Valves RB 595 L-13 RRC VALVE, NO. BNK SDV DRN -1A y 27 1-0302-22A SDV INBD DRN VLV CRP (07) Fluid-Operated Valves RB 595 H-14 RRC CRD SCRAM Inlet Valve (26-31 G-8 28 1-0305-126-26-31 (South)) CRD (07) Fluid-Operated Valves RB 595 Y RRC Y CRD SCRAM Inlet Valve (30-03 H-1 y 29 1-0305-126-30-03 (South)) CRD (07) Fluid-Operated Valves RB 595 RRC Y CRD SCRAM Inlet Valve (34-03 J-1 y 30 1-0305-126-34-03 (North)) CRD (07) Fluid-Operated Valves RB 595 RRC Y CRD SCRAM Inlet Valve (34-35 J-9 y 31 1-0305-126-34-35 (North)) CRD (07) Fluid-Operated Valves RB 595 RRC Y CRD SCRAM Outlet Valve (26-31 G-32 1-0305-127-26-31 8 (South)) CRD (07) Fluid-Operated Valves RB 595 -RRC Y CRD SCRAM Outlet Valve (30-03 y 33 1-0305-127-30-03 H-1 (South)) CRD (07) Fluid-Operated Valves RB 595 RRC Y CRD SCRAM Outlet Valve (34-03 J- y 34 1-0305-127-34-03 1 (North)) CRD (07) Fluid-Operated Valves RB 595 RRC Y CRD SCRAM Outlet Valve (34-35 J- y 35 1-0305-127-34-35 9 (North)) CRD (07) Fluid-Operated Valves RB 595 RRC Y VALVE, RELIEF -1 B RHR HX TUBE .y 36_ 1-1001-165B SIDE RV RH (07) Fluid-Operated Valves RB 580 M-18 RCIC/DHR .... ..VALVE, RELIEF -1B RHR HX y 37 1-1001-166B SHELL SIDE RV RH (07) Fluid-Operated Valves RB 554 M-18 RCIC/DHR VALVE, RELIEF -1A LPCI LOOP y 38 1-1001-22A RV RH 1(07) Fluid-Operated Valves RB 554 L-13 RCIC/DHR VALVE, BUTTERFLY ISO, FC -SOLENOID Ul B TORUS VACUUM Y 39 1-1601-21 BKR PC (07) Fluid-Operated Valves RB 554 AZ315 CF VLV, 18", +3', DRYWELL VENT -U- Y 40 1-1601-23-AO 1 DWVENT VLV PC (07) Fluid-Operated Valves RB 647 L-16 CF VLV, 18", +5', U-1 CONTAINMENT RX BLDG EXH -ASSY -U-1 CNMT Y 41 1-1601-24-AO RX BLDG EXH VENT VLV PC (07) Fluid-Operated Valves RB 647 L-16 CF VALVE, PNUEMATIC

-U-1 DW FLR DRN SUMP PMP UPSTREAM Y 42 1-2001-3 -DSCH VLV RW (07) Fluid-Operated Vaives RB -554 AZ180 CF .U-1 HPCI STM LINE TO CONDENSER UPSTREAM DRN Y 43 1-2301-29-AO VLV HP (07) Fluid-Operated Valves RB 554 RCIC U-1 HPCI STM LINE DRN LINE y 44 1-2301-31-AO STM TRAP BYP VLV HP (07) Fluid-Operated Valves RB 554 RCIC U-1 HPCI GL SEAL CONDENSER Y 45 1-2399-15-PCV COND PMP DSCH PCV HP (07) Fluid-Operated Valves RB 554 RCIC Table B-2 Page 2 of 5 B- 19 Quad Cities Generating Station Unit 1 12Q0108.40-R-O01 Rev. 3 Correspondence No.: RS-12-169 seismic New or .IPEEE Walkdown Item ID DESCRIPT SYSTEM CLASS BUILDING ELEVATION LOCATION Licensing ft Replaced Enhancement Deferred To Comments Number Basis? uncion(s)

Equip? ? Outage?VALVE, AIR START RELAY -AIR LINE TO U-1 DG AIR START Y Auxiliary

&46 1-4699-226 MOTOR AO SA (07) Fluid-Operated Valves DG 595 G-23 Support VALVE, PNUEMATIC

-U-1 CONTAINMENT 1G DW COOLER Y 47 1-8801A-AO UPSTREAM AIR SMPL VLV DAP (07) Fluid-Operated Valves RB 623 L-14 _ CF (08) Motor-Operated and y 48 1-0203-iA-1 SOV, FOR MSIV RX Solenoid-Operated Valves RB 592 H-15 RCPC/CF (08) Motor-Operated and y 49 1-0302-19A SOV, B/U SCRAM CRP Solenoid-Operated Valves RB 595 L-17 RRC SOV, SDV VNT & DRN 1A SCRAM (08) Motor-Operated and Y 50 1-0302-20A PILOT SO CRP Solenoid-Operated Valves RB 595 L-17 RRC VALVE, HX 3B BYPASS -1 B RHR (08) Motor-Operated and y 51 1-1001-16B HX BYP VLV RH Solenoid-Operated Valves RB 554 M-18 _ RCIC/DHR VALVE, LOOP A INBRD -1A LPCI LOOP DWNSTRM VALVE GATE (08) Motor-Operated and Y 52 1-1001-29A MOTOR OPERATED RH Solenoid-Operated Valves RB 554 J-14 RCIC/DHR VALVE, TORUS CLG -1A TORUS (08) Motor-Operated and Y 53 1-1001-34A SPRAY/CLG SV RH Solenoid-Operated Valves RB 554 L-13 RCIC/DHR VALVE -*PMP SUCT ISOL VLV (08) Motor-Operated and Y y 54 1-1201-2 (HW) RT Solenoid-Operated Valves RB 623 K-17 CF VALVE -RECIRC PMP SUCT ISOL (08) Motor-Operated and Y y 55 1-1201-5 VLV RT Solenoid-Operated Valves RB 623 K-18 CF VLV, ISOLATION -RCIC STEAM (08) Motor-Operated and Y y 56 1-1301-16-MO SUPPLY ISOL VLV RI Solenoid-Operated Valves RB 592 H-15 RCIC/DHR VLV, ISOLATION

-*U1 MAIN STM (08) Motor-Operated and Y Y 57 1-1301-17-MO TO RCIC DOWNSTREAM SV (HW) RI Solenoid-Operated Valves RB 591 G-16 RCIC/DHR VLV, 1", +1', N2 MAKEUP TO y CONTAINMENT

-U-1 N2 MU FROM (08) Motor-Operated and 58 1-1601-57-MO TO CNMT DOWNSTREAM SV PC Solenoid-Operated Valves RB 595 J-18 CF-(08) Motor-Operated and y 59 1-2301-14-MO U-1 HPCI PMP MIN FLOW VLV HP Solenoid-Operated Valves RB 554 RCIC U-1 HPCI PMP DOWNSTREAM (08) Motor-Operated and y 60 1-2301-35-MO TORUS SUCT VLV HP Solenoid-Operated Valves RB 554 Y RCIC 1 (08) Motor-Operated and Y 61 1-2301-3-MO U1 HPCI TURB INLET VLV (HW) HP Solenoid-Operated Valves RB 554 RCIC U-1 HPCI CLG WTR PMP TEST (08) Motor-Operated and Y 62 1-2301-49-MO VLV HP Solenoid-Operated Valves RB 554 RCIC (08) Motor-Operated and y 63 1-2301-6-MO U-1 HPCI PMP CCST SUCT VLV HP Solenoid-Operated Valves RB 554 RCIC (08) Motor-Operated and Y 64 1-2301-9-MO U-1 HPCI PMP DSCH VLV HP Solenoid-Operated Valves RB 554 RCIC FAN, ROOM VENTILAT -DG Y Auxiliary

& PRA: F-V=5.09e-02; 65 1-5727 ROOM VENT FAN VD (09) Fans DG 595 G-23 Support Y _RAW=8.36 Table B-2 Page 3 of 5 B-20 Quad Cities Generating Station Unit 1 12Q0108.40-R-O01 Rev. 3 Correspondenre No.: RS-12-169 Seismic Safety New or IPEEE Walkdown Item ID DESCRIPT SYSTEM CLASS BUILDING ELEVATION LOCATION Licensing Funcion(s)

Replaced Enhancement Deferred To Comments Number Basis? FEquip? ? Outage?COOLER, CUBICLE -1A RHRSW y Auxiliary

&66 1-5745A PMP CUBICAL COOLER VD (10) Air Handlers TB 547 C-18 Support Y COOLER, CUBICLE -Ul HPCI y Auxiliary

& y 67 1-5747 ROOM EMERGENCY COOLER VD (10) Air Handlers TB 554 G-14 Support Y EC 24119 COOLER, CUBICLE -1A CS/RCIC Y Auxiliary

& Y 68 1-5748A PMP RM COOLER VD (10) Air Handlers RB 560 G-18 Support Y EC 24243 COOLER, CUBICLE -1DG CW PMP Y Auxiliary

&69 1-5749 CUB COOLER VD (10) Air Handlers TB 547 C-22 Sppr Y UNIT REFRIGERATION CONDENSER UNIT COMPRESSOR Auxiliary

&70 1/2-9400-102 CRANKCASE HEATER VC (11) Chillers TB 615 E-24 Support TANK, AIR RECEIVER -RECEIVER Y Auxiliary

&71 1-4600A GAS (IDNS PRESSURE VESSEL) SA (12) Air Compressors DG 595 G-23 Support Y Racks &72 901-61 PNL, CONTROL PM (14) Distribution Panels SB 609 CSR _ Panels I Y Racks &73 901-62 PNL, CONTROL PM (14) Distribution Panels SB 609 CSR Panels Y Electrical 74 125 VDC BATT 1 BATTERY, 125V 125 VDC (15) Batteries on Racks TB 628 G-24 Systems Y.Electrical Y 75 250 VDC BATT 1 BATTERY, 250V 250 VDC (15) Batteries.on Racks TB 628 G-24 Systems Y (16) Battery Chargers and Y Electrical 76 1-8300-1 CHRGR #1, 125V DC Inverters TB 615 G-24 Systems Y (16) Battery Chargers and Y Electrical 77 1-8350 CHRGR #1, 250V DC Inverters TB 615 G-24 Systems Y EC 24446 Y Auxiliary

& y PRA: F-V=3.22e-01; 78 1-6601 DG, UNIT 1 DG (17) Engine-Generators DG 595 G-23 Support RAW=8.51 SWITCH, PRESS. -*U1 DG PS 1- y Auxiliary

&79 1-4641-42A 4641-42A SHUTOFF VLV SA (18) Instruments on Racks DG 595 G-23 _ Support Y Racks &80 2201-29A INSTR RACK 2201-29A RM (18) Instruments on Racks RB 554 Panels Racks &81 2201-32 RACK, AUTO BLOWDOWN RM (18) Instruments on Racks RB 623 K-14 Y Panels yY EC 24114-Y Racks &Y 82 2201-59A RACK RM (18) Instruments on Racks RB 554 M-14 Panels Y Racks &83 2201-7 RACK RM (18) Instruments on Racks RB 595 J-14 Panels Y Racks &84 2201-73A RACK RM (18) Instruments on Racks SB 609 G-26 Panels Y Racks &85 2201-8 RACK, AUTO BLOWDOWN RM (18) Instruments on Racks RB 595 K-17 Panels RACK, U-I DG RELAY & Y Racks &86 2251-10 METERING RM (18) Instruments on Racks DG 595 F-23 _ Panels Table B-2 Page 4 of 5 B-21 Quad Cities Generating Station Unit 1 12QO108.40-R-O01 Rev. 3 Correspondence No.: RS-12-169 Seismic New or IPEEE Walkdown Item Safety Number ID DESCRIPT SYSTEM CLASS BUILDING ELEVATION LOCATION Licensing Function(s)

Replaced Enhancement Deferred To Comments Basis? (s) Equip? ? Outage?Racks &87 2251-113 RACK, DG ENGINE CONTROL RM (18) Instruments on Racks DG 595 G-23 _ Panels Racks &88 2251-86 RACK RM (18) Instruments on Racks TB 639 H-14 _ Panels Racks &89 2251-87 RACK RM (18) Instruments on Racks TB 639 H-16 Panels (20) Instrumentation and Control Panels and Y Racks &90 901-3 PANEL PM Cabinets SB 623 Panels (20) Instrumentation and Control Panels and Y Racks &91 901-33 PANEL PM Cabinets SB 595 H-26 Panels Y (20) Instrumentation and Control Panels and Y Racks &92 901-39 PANEL PM Cabinets SB 595 G-25 Panels Y (20) Instrumentation and Control Panels and Y Racks &93 901-5 PANEL PM Cabinets SB 623 Panels SCRAM WATER ACCUMULATOR (21) Tanks and Heat 94 1-0305-125-26-31 (26-31 G-8 (South)) CRD Exchangers RB 595 -RRC Y SCRAM WATER ACCUMULATOR (21) Tanks and Heat y 95 1-0305-125-30-03 (30-03 H-1 (South)) CRD Exchangers RB 595 RRC Y SCRAM WATER ACCUMULATOR (21) Tanks and Heat y 96 1-0305-125-34-03 (34-03 J-1 (North)) CRD Exchangers RB 595 RRC Y SCRAM WATER ACCUMULATOR (21) Tanks and Heat y 97 1-0305-125-34-35 (34-35 J-9 (North)) CRD Exchangers RB 595 RRC Y HEAT EXCHANGER, 1C RHR (21) Tanks and Heat y 98 1-1001-145C PUMP RH Exchangers RB 554 M-18 RCIC/DHR (21) Tanks and Heat 99 1-1003B HX, 1B RHR RH Exchangers RB 554 M-14 RCIC/DHR Y (21) Tanks and Heat y 100 1-2310 COOLER U-1 HPCI OIL HP Exchangers RB 554 RCIC (21) Tanks and Heat y Auxiliary

&101 1-4605 TANK, BLOWDOWN SA Exchangers DG 595 G-23 Support 102 -522 TNK, UELOILDAY O 121)Tank an Het Y Auxiliary

&(21) Tanks and Heat 102 1-5202 TANK, FUEL OIL DAY DO Exchangers DG 595 G-23 ____Support

_________

____(21) Tanks and Heat y Auxiliary

&103 1-6654 HX, DG LUBE OIL DG Exchangers DG 595 G-23 Support (21) Tanks and Heat y Auxiliary

&104 1-6661A HX, DG COOLING DG Exchangers

-DG 595 G-23 SupportI Table B-2 Page 5 of 5 B3-22 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 C Seismic Walkdown Checklists (SWCs)Table C-1 provides a description of each item, anchorage verification confirmation, a list of Area Walk-By Checklists associated with each item, comments, and page numbers of each Seismic Walkdown Checklist.

C-1 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Table C-1. Summary of Seismic Walkdown Checklists Anchorage AREA ID DESCRIPTION Configuration COMMENTS PAGE Verified WALK-BY UNIT REFRIGERATION 1/2-9400-102 CONDENSER UNIT COMPRESSOR CRANKCASE HEATER 1-0203- VLV, PNEUMATIC MAIN STEAM N/A Outage 0001AH25 INBOARD ISOLATION VALVE 1-0203-1 A-1 SOV, FOR MSIV N/A Outage 1-0203-3A VALVE, ERV N/A Outage 1-0203-4A VALVE, SRV N/A Outage 1-0220-45 VALVE, PNUEMATIC 1B RECIRC N/A Outage LOOP SMPL DOWNSTREAM SV 1-0302-19A SOV, B/U SCRAM N/A 17 C -11 1-0302-20A SOV, SDV VNT & DRN 1A SCRAM N/A 17 C-17 1-0302-20A PILOT SO N/A 17 C_17 1-0302-21A VALVE, NO. BNK SDV VNT-ASSY N/A 16 C- 22 1A SDV INBD VENT VLV 1-0302-22A VALVE, NO. BNK SDV DRN -1A N/A 15 C -26 SDV INBD DRN VLV 1-0305-125-SCRAM WATER ACCUMULATOR 26-31 (26-31 G-8 (South))1-0305-125-SCRAM WATER ACCUMULATOR N/A 17 C -40 30-03 (30-03 H-1 (South))1-0305-125-SCRAM WATER ACCUMULATOR N/A 16 C -45 34-03 (34-03 J-1 (North))1-0305-125-SCRAM WATER ACCUMULATOR 34-35 (34-35 J-9 (North)) N/A 16 C -50 1-0305-126-CRD SCRAM Inlet Valve (26-31 G-8 N/A 17 C -55 26-31 (South))1-0305-126-CRD SCRAM Inlet Valve (30-03 H-1 N/A 17 C -57 30-03 (South))1-0305-126-CRD SCRAM Inlet Valve (34-03 J-1 N/A 16 C -59 34-03 (North))1-0305-126-CRD SCRAM Inlet Valve (34-35 J-9 N/A 16 C -61 34-35 (North))1-0305-127-CRD SCRAM Outlet Valve (26-31 G- N/A 17 C -63 26-31 8 (South))1-0305-127-CRD SCRAM Outlet Valve (30-03 N/A 17 C -65 30-03 H-1 (South))1-0305-127-CRD SCRAM Outlet Valve (34-03 J- N/A 16 C -67 34-03 1 (North))1-0305-127-CRD SCRAM Outlet Valve (34-35 J. N/A 16 C-69 34-35 9 (North)) I 1-0305-26-31 HCU -(26-31 G-8 (South)) Y 17 C -71 1-0305-30-03 HCU -(30-03 H-1 (South)) Y 17 C -80 Table C-1 Page 1 of 4 C-2 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Anchorage AREA C ID DESCRIPTION Configuration WALK-BYCOMMENTS PAGE Verified 1-0305-34-03 HCU -(34-03 J-1 (North)) Y 16 C -85 1-0305-34-35 HCU -(34-35 J-9 (North)) Y 16 C -90 1-1001-145C HEAT EXCHANGER, 1C RHR N 26 C-95 PUMP N 26_C_-_95 1-1001-165B VALVE, RELIEF- 1B RHR HX N/A 25 C- 102 TUBE SIDE RV 1-1001-166B VALVE, RELIEF -1B RHR HX N/A 26 C -108 SHELL SIDE RV 1-1001-16B VALVE, HX 3B BYPASS -1B RHR N/A 26 C -112 HX BYP VLV 1-1001-22A VALVE, RELIEF -1A LPCI LOOP N/A 15 C -118 RV VALVE, LOOP A INBRD -1A LPCI 1-1001-29A LOOP DWNSTRM VALVE GATE N/A 15 C -122 MOTOR OPERATED 1-1001-34A VALVE, TORUS CLG -1A TORUS N/A 15 C -126 SPRAY/CLG SV 1A RHR SERVICE WATER MAIN 1-1001-65A PUPY 22 C- 130 PUMP 1-1002C PUMP, 1C -RHR PUMP Y 26 C -135 1-1003B HX, 1B RHR Y 25 C -138 1-1201-2 VALVE -*PMP SUCT ISOL VLV N/A Outage (HW)VALVE -RECIRC PMP SUCT ISOL 1-1201-5 VLV N/A Outage 1-1301 VLV, ISOLATION -RCIC STEAM N/A Outage MO SUPPLY ISOL VLV 1-1301 VLV, ISOLATION

-*U1 MAIN STM MO TO RCIC DOWNSTREAM SV (HW) N/A Outage VALVE, BUTTERFLY ISO, FC 1601-21 SOLENOID UI B TORUS VACUUM N/A 7 C -142 BKR 1-1601 VLV, 18", +3', DRYWELL VENT -U- N/A 5 C -146 AO 1 DW VENT VLV 1-1601 VLV, 18", +5', U-1 CONTAINMENT RX BLDG EXH -ASSY -U-1 CNMT N/A 5 C -150 RX BLDG EXH VENT VLV VLV, 1", +1', N2 MAKEUP TO 1-1601 CONTAINMENT

-U-1 N2 MU MO FROM TO CNMT DOWNSTREAM SV VALVE, PNUEMATIC

-U-1 DW FLR 1-2001-3 DRN SUMP PMP UPSTREAM N/A 15 C -160 DSCH VLV Table C-1 Page 2 of 4 C-3 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Anchorage AREA ID DESCRIPTION Configuration WALK-BY COMMENTS PAGE Verified 1-2301 U-1 HPCI PMP MIN FLOWVLV N/A 24 C -164 MOC 1-2301 U-1 HPCI STM LINE TO CONDENSER UPSTREAM DRN N/A 24 C -168 VLV 1-2301 U-1 HPCI STM LINE DRN LINE AO STM TRAP BYP VLV 1-2301 U-1 HPCI PMP DOWNSTREAM N/A 24 C -130 MO TORUS SUCT VLV 1-2301-3-MO U1 HPCI TURB INLET VLV (HW) N/A 24 C -184 1-2301 U-1 HPCI CLG WTR PMP TEST N/A 24 C -188 MO VLV 1-2301-6-MO U-1 HPCI PMP CCST SUCTVLV N/A 24 C -192 1-2301-9-MO U-1 HPCI PMP DSCH VLV N/A 24 C -197 1-2302 HPCI/ HPCI Pump Y 24 C -202 1-2304 PUMP U- HPCI CONDENSATE N 24 C -207 1-2308 UNIT 1 HPCI AUX OIL PUMP N 24 C -212 1-2310 COOLER U-1 HPCI OIL N 24 C -216 1-2399 U-1 HPCI GL SEAL CONDENSER N/A 24 C -220 PCV COND PMP DSCH PCV 25 VDC BATTERY, 125V Y 3 C -225 BATT 1 _ _ _ _ _ _ _ _PUMP, DG COOLING -U1 DIESEL 1-3903 GENERATOR COOLING WATER Y 6 C -230 PUMP 1-4600A TANK, AIR RECEIVER -RECEIVER N 9 C -235 GAS (IDNS PRESSURE VESSEL)1-4604 DRYER, AIR N/A 9 C -239 1-4605 TANK, BLOWDOWN Y 9 C -242 1-4641-42A SWITCH, PRESS. -*U1 DG PS 1- N 9 C -247 4641-42A SHUTOFF VLV VALVE, AIR START RELAY -AIR 1-4699-226 LINE TO U-1 DG AIR START N/A 9 C -251 MOTOR AO 1-5202 TANK, FUEL OIL DAY Y 8 C -256 1-5203 PUMP, FUEL OIL TRANSF Y 9 C -261 1-5727 FAN, ROOM VENTILAT -DG Y 9 C -266 1-5727 __ ROOM VENT FAN __9_C__26 1-5745A COOLER, CUBICLE -1A RHRSW N 22 C -271 PMP CUBICAL COOLER 1-5747 COOLER, CUBICLE -U1 HPCI Y 24 C -276 ROOM EMERGENCY COOLER 1-5748A COOLER, CUBICLE -1A CS/RCIC Y 11 C -282 PMP RM COOLER I Table C-1 Page 3 of 4 C-4 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No,: RS-12-169 Anchorage AREA ID DESCRIPTION Configuration WALK-BY COMMENTS PAGE Verified 1-5749 COOLER, CUBICLE -1DG CW N 6 C -285 PMP CUB COOLER 1-6601 DG, UNIT 1 Y 9 C -291 1-6654 HX, DG LUBE OIL N 9 C -298 1-6661A HX, DG COOLING N 9 C -302 1-6705-13-1 SWGR 13-1 N 20 (1) C- 307 1-7100 TRANSFORMER 18 4160V-480V N 20 C -313 1-7100-18 SWGR 18 Y 20 C- 320 1-7800-18195 MCC -MCC 18/19-5 N 10 C -329 1-7800-18-1B MCC -MCC 18-1B N 23 C -334 1-7800-18-2 MCC -MCC 18-2 N 1 C -338 1-7800-19-1 MCC -MCC 19-1 N 23 C -343 1-8300-1 CHRGR #1,125V Y 2 C -346 1-8350 CHRGR #1, 250V Y 2 C -354 VALVE, PNUEMATIC

-U-1 1-8801A-AO CONTAINMENT 1G DW COOLER N/A 14 C -358 UPSTREAM AIR SMPL VLV 2201-29A INSTR RACK 2201-29A Y 24 C -366 2201-32 RACK, AUTO BLOWDOWN N 14 C -372 2201-59A RACK Y 12 C -379 2201-7 RACK Y 16 C- 384 2201-73A RACK Y 13 C -390 2201-8 RACK, AUTO BLOWDOWN Y 17 C -395 2251-10 RACK, U-1 DG RELAY & Y 9 C -401 METERING 2251-113 RACK, DG ENGINE CONTROL N 9 C -405 2251-86 RACK Y 20 C -412 2251-87 RACK Y 21 C -417 250 VDC BATTERY, 250V Y 3 C --422 BATT I1_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _25OVDC MCC Y 2C -428 MCC 1 250 VDC MCC MCC N 23 C -434 MCC 1A 901-3 PANEL Y 19 C -439 901-33 PANEL Y 18 C -442 901-39 PANEL Y 18 C -449 901-5 PANEL Y 19 C -456 901-61 PNL, CONTROL Y 13 C -459 901-62 PNL, CONTROL Y 13 C -463 Comments: (1) Anchorage Deferred to Outage Table C-1 Page 4 of 4 C-5 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 1 of 5 Status: FYII N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1/2-9400-102 Equipment Class: (11) Chillers UNIT REFRIGERATION CONDENSER UNIT COMPRESSOR CRANKCASE Equipment

==

Description:==

HEATER Project: Quad Cities 1 SWEL Location (Bldg, Elev, Room/Area):

TB, 615.00 ft, ALL Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is anchorage configuration verification required (i.e., is the item one of the 50%of SWEL items requiring such verification)?

Yes 2. Is the anchorage free of bent, broken, missing or loose hardware?Yes 3. Is the anchorage free of corrosion that is more than mild surface oxidation?

Yes 4. Is the anchorage free of visible cracks in the concrete near the anchors?Yes 5. Is the anchorage configuration consistent with plant documentation? (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

Yes Yes C-6 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 2 of 5 Status: T N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1/2-9400-102 Equipment Class: (11) Chillers UNIT REFRIGERATION CONDENSER UNIT COMPRESSOR CRANKCASE Equipment

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Description:==

HEATER Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes Yes 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?Yes 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yes Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Comments SEWS Anchorage Notes: Chiller mounted on steel skid (no vibration isolators) by eight -3/4" concrete expansion anchors.Seismic Walkdown Team: D. Carter & J. Griffith -8/20/2012 Evaluated by:

David Carter Date: 10/4/2012 James Griffith 10/4/2012 C-7 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 3 of 5 Status: EYII N U Seismic Walkdown Checklist (SWC)Equipment ID No.: Equipment Class: Eaui~ment Descrip~tion:

1/2-9400-102 (11) Chillers UNIT REFRIGERATION CONDENSER UNIT COMPRESSOR CRANKCASE HEATER Photos o-zu-i z uuao unies -i uo t4)%7-C-8 Quad Cities Generating Station Unit I 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 4 of 5 Status: ELI N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1/2-9400-102 Equipment Class: (11) Chillers UNIT REFRIGERATION CONDENSER UNIT COMPRESSOR CRANKCASE 8-20-12 Quad Cities 106 5 8-20-12 Quad Cities 108 (7)C-9 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 5 of 5 Status: ET N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1/2-9400-102 Equipment Class: (11) Chillers UNIT REFRIGERATION CONDENSER UNIT COMPRESSOR CRANKCASE C-10 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 1 of 6 Status: FYii N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1-0302-19A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Eauioment Descriotion:

SOV. B/U SCRAM Project: Quad Cities 1 SWEL Location (Bldg, Elev, Room/Area):

RB, 595.00 ft, ALL Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is anchorage configuration verification required (i.e., is the. item one of the 50%of SWEL items requiring such verification)?

No 2. Is the anchorage free of bent, broken, missing or loose hardware?Not Applicable

3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation? (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Not Applicable Not Applicable Not Applicable

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

Yes Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes C-11 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 2 of 6 Status: r-II N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1-0302-19A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

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Description:==

SOV, B/U SCRAM 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes 10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Valve in contact with support bracket. Pipe from valve is attached to same bracket approximately 16 inches away. No differential movement expected.Judged to be acceptable.

The angle brackets providing vertical support for the 1-0302-18 and 1-0302-19A lines are installed but not providing any support for the lines. There is a gap between the top of the brackets and the bottom of the lines. There is currently no excessive deflection, distortion or any other signs of inadequate support. The adjacent connections/supports were examined and are in good condition.

While this condition is considered deficient due to the bracket not being installed tight under the lines, there is no concern that the lines will fail during a seismic event.Identified in IR 1403597.Comments Seismic Walkdown Team: D. Carter & J. Griffith -8/22/2012 See South CRD Bank area walk-by for further notes.C-12 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 3 of 6 Status: Y-] N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1-0302-19A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Eauioment Descriotion:

SOV. B/U SCRAM Evaluated by: Q)AJ(4-k David Carter Date: 10/4/2012-'V" JamesGriffith 10/4/2012 C-1 3 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 4 of 6 Status: [Y] N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1-0302-19A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves C-14 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 5 of 6 Status: F N U Seismic Walkdown Checklist (SWC)Equipment ID No.: Equipment Class: inmx~nf flgerrinfia~n-1-0302-19A (8) Motor-Operated and Solenoid-Operated Valves C-15 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 6 of 6 Status: F N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1-0302-19A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves C-16 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 1 of 5 Status: N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1-0302-20A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

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Description:==

SOV, SDV VNT & DRN 1A SCRAM PILOT SO Project: Quad Cities 1 SWEL Location (Bldg, Elev, Room/Area):

RB, 595.00 ft, ALL Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL, The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is anchorage configuration verification required (i.e., is the item one of the 50%of SWEL items requiring such verification)?

No 2. Is the anchorage free of bent, broken, missing or loose hardware?Not Applicable

3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation? (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Not Applicable Not Applicable Not Applicable

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

Yes Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes C-17 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 2 of 5 Status: F N U Seismic Walkdown Checklist (SWC)Equipment ID. No.: 1-0302-20A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

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Description:==

SOV, SDV VNT & DRN 1A SCRAM PILOT SO 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

Yes 9. Do attached lines have adequate flexibility to avoid damage?Yes 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yes Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Comments Seismic Walkdown Team: D. Carter & J. Griffith -8/22/2012 See South CRD Bank area walk-by for further notes.Evaluated by: J 2 David Carter Date: 10/4/2012 James Griffith 10/4/2012 C-1 8 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 3 of 5 Status: FYII N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1-0302-20A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

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Description:==

SOV, SDV VNT & DRN 1A SCRAM PILOT SO 01 C-19 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 4 of 5 Status: FYi N U Seismic Walkdown Checklist (SWC)Equipment ID No.: Equipment Class: 1-0302-20A (8) Motor-Operated and Solenoid-Operated Valves C-20 Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 5 of 5 Status: YI1 N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 1-0302-20A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves II~1 0'C-21