ML12341A166

Enclosure 2, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Byron Station, Unit 2, Report No: 12Q0108.20-R-002, Revision 1

ML12341A166
Person / Time
Site:	Byron
Issue date:	11/07/2012
From:	Delaney M Stevenson & Associates
To:	Office of Nuclear Reactor Regulation, Exelon Generation Co
References
RS-12-161 12Q0108.20-R-002, Rev 1
Download: ML12341A166 (210)

Text

U.S. Nuclear Regulatory Commission 180-Day Response to 50.54(f) Letter NTTF Recommendation 2.3: Seismic November 27, 2012 Page 5 Enclosure 2 Seismic Walkdown Report In Response To The 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Byron Station, Unit 2 Report Number: 1200108.20-R-002, Revision 1 (587 pages)

SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 50.54(f) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC for the BYRON GENERATING STATION UNIT 2 4450 NORTH GERMAN CHURCH ROAD, BYRON, ILLINOIS 61010-9794 Facility Operating License No. NPF-66 NRC Docket No. STN 50-455 Correspondence No.: RS-12-161-~ Exeton.Exe Coeneration Company. LLC (Ex )PO Box 605398 Chicago, IL 60680-5398 Prepared by:.Stevenson

& Associates 1661 Feeminvlle Drive, Suite 150 Mount Prospect IL 60056 Report Number. 12Q0108.2D-R-002, Rev. I Prepoar Madam Delay Reviewer Tony Perez Approver Tony Perez Peer Review Team Leader Walter Djordjovc Lead ReaponlbIe EngIn V l l Corporate Accep~mne:

~ s z.11/7/20121117/2012f" 1117/2012.poa 0 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 BYRON GENERATING STATION UNIT 2 Document Type: Report Report Number: 12Q0108.20-R-002 Project Name: NTTF R2.3 Seismic Walkdowns for Exelon -Byron Job No.: 12Q0108.20 Client: ' Exelon This document has been prepared in accordance with the S&A Quality Assurance Pro-gram Manual, Revision 17 and project requirements:

Rev. 0 A( I Date: 10/31/2012 Prepared by: Marlene Delaney Reviewed by: Tony Perez Date: 10/31/2012Date: 10/31/2012 Approved by: Tony Perez Revision Record: Revision Prepared by/ Reviewed by/ Approved by/ Description of Revision No. Date Date Date 1 Marlene Tony Perez Tony Perez Replaced Table G-1 and vii Delaney -11/7/2012 11/7/2012 11/7/2012 DOCUMENT CONTRACT NO.APPROVAL SHEET 12Q0108 Stevenson

& Associates Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Contents L is t o f T a b le s ........ ............................................

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iii Executive Summary ...............................................................................................

iv 1 Introduction

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

1 -1 1 .2 B a c kg ro u n d .............................................................................................................

1 -1 1 .3 P la n t O v e rv ie w .............................................................................

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1 -1" 1.4 Approach .........................................................................................

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

.. ...1 -2 2 Seismic Licensing Basis .................................................................................

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

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

2-1 2.3 Design of Seismic Category I SSCs ........................................................................

2-1 3 Personnel Qualifications

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3-1 3 .1 O v e rv ie w ..................................................................................................................

3 -1 3.2 W alkdown Personnel

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3-1 3.2.1 Stevenson

& Associates Personnel

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3-2 3.2.2 Additional Personnel

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

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4-1 4.1 Overview .................................................................

4-1 42 WE Deeomn........

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4-1 4.2 SW EL Development

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4-1 4.2.1 SWEL I -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 5 Seismic Walkdowns and Area Walk-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 V isua l Inspectio ns ..........................................................................................

5 -2 5.2.3 Configuration Verification

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5-3 5.2.4 Adverse Seismic Spatial Interactions

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5-4 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 5.2.5 Other Adverse Seismic Conditions

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5-4 5.2.6 Conditions Identified during Seismic Walkdowns

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5-4 5 .3 A re a W a lk-B ys .........................................

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5 -5 5.3.1 Seismically-Induced Flooding/Spray Interactions

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5-6 5.3.2 Seismically-Induced Fire Interactions

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5-7 5.3.3 Conditions Identified during Area Walk-bys..................................................

5-7 5.4 Supplemental Information on electrical cabinet internal inspections

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5-7 6 Licensing Basis Evaluations

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

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

8-1 9 References

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9-1 Appendices A Project Personnel Resumes and SWE Certificates

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A-1 B Equipment Lists .........................................................................................................

B-1 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-I G IPEEE Vulnerability Status ......................................................................................

G-1 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 List of Tables Table 2-1. List of Codes, Standards, and Specifications

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2-3 T able 3-1.. P ersonnel R oles ....................................................................................

3-1 Table 5-1. Anchorage Configuration Confirmation

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

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

5-9 Table B-I. BaseList 1 ...........................................

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B-3 Table B-2. Base List2 .................................

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B-41 Table B-3. SWEL 1 ......................................................................

B-43 T a ble B -4 .S W E L 2 ...........................................

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B -4 8 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. Inaccessible and Deferred Equipment List ........................

...... E-2 Table E-2. Supplemental Cabinet Internal Inspection List ..............................................

E-3 Table G -1. IPEEE V ulnerability Status .......................................................................

G -2 iii Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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. 8) In particular, this report provides information requested to address Enclosure 3, Recommendation 2.3: Seismic, of the March 12, 2012 letter. (Ref. 8)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 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. 10) 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. 8) 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 Byron Generating Station Unit 2 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. 8) 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/Byron 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 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Seismic Licensing Basis The Seismic Licensing Basis is briefly described in Section 2 of this report. The maximum horizontal and vertical ground accelerations at the foundation level are 20% of gravity for the safe shutdown earthquake (SSE). (Ref. 2, section 3.7.1.1)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 1 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: " A variety of types of systems* Major new or replacement equipment* A variety of types of equipment" A variety of environments v

Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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 Byron Unit 2, the SWEL is comprised of:* SWEL 1 resulted with 102 items for walkdown.* SWEL 2 resulted with 23 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 Byron Unit 2 were performed during the weeks of August 6 and August 20, 2012. During the majority of the walkdown activities, the walkdown team consisted of two (2) Seismic Walkdown Engineers (SWE), the station Lead Responsible Engineer (LRE), a station Equipment Operator, and a station Operations person.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 special 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 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161* Anchorage conditions (if visible without opening equipment)

• Significantly degraded equipment in the area* 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 walked down 108 of the 125 components on the SWEL.Walkdowns for 17 components were deferred due to accessibility issues such as being located in containment or energized equipment.

For Byron Unit 2, anchorage verification was required for minimum of 35 components to meet the 50% verification requirements of the EPRI guidance document. (Ref. 1) A total of 40 anchorage configurations were confirmed to be installed in accordance with the station documentation.

The 17 remaining Unit 2 items will be walked down during a unit outage or another time when the equipment is accessible, as appropriate.

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 42 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 Byron Unit 2 fifteen (15) Issue Reports (IRs) were issued for conditions such as open fluorescent light fixture S-hooks and grout pad cracks. Open fluorescent light fixture S-hook conditions were found to be the most common. After evaluation through the Corrective Action Program (CAP), it was determined that none of the conditions identified in the IRs were adverse seismic conditions.

Through the efforts of the seismic walkdowns and development of this report, IR 1431416 was initiated to share lessons learned with various workgroups across the station. In particular, the IR was issued to create an action to tailgate lessons learned with Electrical Maintenance, Electrical Maintenance Work Planning, and the Maintenance Contractor.

The focal point of the lessons learned is in regards to open fluorescent light fixture S-hooks. The expected S-hook configuration is that they are closed sufficiently to prevent the support chain links from passing though the S-hook up to metal-to-metal contact.Seismic Licensinq 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 CAP. In lieu of this process, Exelon/Byron utilized the existing processes and procedures (Site CAP Expectations) to identify, evaluate and document conditions identified during the Seismic Walkdowns.

vii Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 In accordance with Exelon/Byron 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 CAP 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.Conditions identified during the walkdowns were documented on the SWCs, AWCs, and entered into the CAP. For those conditions that required it, seismic licensing basis evaluations were completed and documented within the IR. 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 and Appendix G 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 plant improvements and associated 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* 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 performed at the Byron Generating Station Unit 2 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 CAP.Evaluations of the identified conditions are complete and documented within the CAP.These evaluations determined the Seismic Walkdowns resulted with no adverse viii Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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 conditions predominantly pertaining to cracks in grout pads and open fluorescent light fixture S-hooks. Other than these minor conditions, the Seismic Walkdowns identified no degraded, nonconforming, or unanalyzed conditions that required either immediate or follow-on action. 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 17 items deferred due to inaccessibility along with supplemental inspections of 42 electrical cabinets.

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

ix Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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. 8) In particular, this report provides information requested to address Enclosure 3, Recommendation 2.3: Seismic, of the March 12, 2012 letter. (Ref. 8)

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 21st 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. 10) On March 12, 2012, the NRC issued a letter to all power reactor licensees in accordance with 1OCFR50.54(f).

The 50.54(f)letter requests information to assure that certain NTTF recommendations are addressed by all U.S. nuclear power plants. (Ref. 8) 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 Byron Generating Station Unit 2 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. 8) 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/Byron has utilized this NRC endorsed guidance as the basis for the seismic walkdowns and this report. (Ref. 1)1.3 PLANT OVERVIEW The Byron Station nuclear power plant consists of two nearly identical generating units, and two pressurized water reactors (PWR) Nuclear Steam Supply System (NSSS) and turbine-generators furnished by Westinghouse Electric Corporation (Westinghouse).(Ref. 2 section 1.1)1-1 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 The Byron Station Units 1 and 2 are rated at a Licensed power level of 3586.6 MWt.(Operating License; Unit 1 License No. NPF-37 and Unit 2 License No. NPF-66)The reactor containments are of post-tensioned concrete construction with a carbon steel liner. Sufficient free volume is provided to contain the energy released in a major accident without need for "pressure suppression" devices. Sargent & Lundy was responsible for containment design. (Ref. 2 section 1.1)Byron Station is located in north central Illinois, near the town of Byron and near the Rock River. Cooling for the plant is provided by two natural draft cooling towers for nonessential service water cooling, and by mechanical draft cooling towers for essential cooling water. The fuel loading dates for the two units were November 1984 and November 1986 for Units 1 and 2, respectively.

The corresponding dates for commercial operation were September 1985 and August 1987. (Ref. 2 section 1.1)1.4 APPROACH The EPRI guidance document is used for the Byron Unit 2 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 Byron Generating Station Unit 2 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 (CAP).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 conditions predominantly pertaining to cracks in grout pads and open fluorescent light fixture S-hooks. Other than these minor conditions, the Seismic Walkdowns identified no degraded, nonconforming, or unanalyzed conditions that required either immediate or follow-on action. No planned or newly identified protection or mitigation features have resulted from the efforts to address the 50.54(f) letter.1-2 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Follow-on activities required to complete the efforts to address Enclosure 3 of the 50.54(f) letter include inspection of 17 items deferred due to inaccessibility along with supplemental inspections of 42 electrical cabinets.

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

1-3 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 2 Seismic Licensing Basis 2.1 OVERVIEW This section of the report summarizes the seismic licensing basis for the Byron Generating Station Unit 1 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 maximum horizontal and vertical ground accelerations at the foundation level are 20% of gravity for the safe shutdown earthquake (SSE). (Ref. 2, section 3.7.1.1)2.3 DESIGN OF SEISMIC CATEGORY I SSCs A full description of the Safe Shutdown Earthquake along with the codes, standards, and methods used in the design of the Seismic Category I SSCs for meeting the seismic licensing basis requirements is provided in the following Byron Station UFSAR sections:* 3.2 Classification of Structures, Components, and Systems* 3.7 Seismic Design 0 Attachment 3.7A -Reevaluation and Validation of the Byron/Braidwood Seismic Design Basis* 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

3.2 Classification

of Structures, Components, and Systems These UFSAR sections should be referred to for a detailed understanding of the seismic licensing basis.Summary of Seismic Design The UFSAR is a jointly reviewed document and thus is referenced as Byron/Braidwood UFSAR.The site response spectra, which are defined at the ground surface, are given in UFSAR Subsection 2.5.2 and are shown in UFSAR Figures 2.5-40 and 2.5-41 for the Byron site.Foundation level response spectra and time histories were generated by a deconvolution procedure described in UFSAR Subsection 3.7.1.2. The maximum horizontal and vertical ground accelerations at the foundation level are 20% of gravity for the safe 2-1 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 shutdown earthquake (SSE) and 9% of gravity for operating basis earthquake (OBE).The comparisons between the free field seismic design motion applied at the surface and the corresponding foundation (rock) spectra for 2%, 3%, 4%, 5%, and 7% damping ratios are shown in UFSAR Figures 3.7-1 through 3.7-20 for the Byron site.During the review of the FSAR for an Operating License, the Byron/Braidwood seismic design was reevaluated using the Regulatory Guide 1.60 spectra without the application of a deconvolution analysis.

UFSAR Attachment 3.7A contains the specific NRC questions/responses on seismic design. These questions and responses document the historical evolution of certain aspects of the Byron/Braidwood seismic design. UFSAR Attachment 3.7A also provides the details and results of this reevaluation.

The UFSAR concluded that the present seismic design of Byron/Braidwood is conservative.

Based on the reevaluation described in UFSAR Attachment 3.7A, the Byron/Braidwood seismic design basis is acceptable and will therefore be used for all future seismic evaluations.

Seismic Class I structures are designed for seismic forces calculated from the aforementioned spectra using a response spectrum method of analysis.

The directional, combination rule uses three components of earthquake motions (two horizontal directions with vertical direction) combined by the square-root-sum-of-the-squares (SRSS) method. For evaluation of Seismic Class I components, In Structure Response Spectra (ISRS) are used. For horizontal directions, ISRS are generated using an input acceleration time history at the base (foundation) of mathematical models that represent the plant structures.

To determine the foundation (rock) level motion, the soil rock profile above the foundation was modeled as a one-dimensional continuous shear layer system. The ground surface spectra consistent time histories were applied at the ground surface and the foundation level motion was obtained using the SHAKE program. For all of the structures founded on rock, the foundation level motion was used directly to excite the fixed base model.Summary of Codes and Standards The information presented below has been extracted from section 3.8 of Reference 2.This section summarizes the codes, specifications, standards of practice, and other accepted industry guidelines which are adopted to the extent applicable, in the design and construction of the following:

• Containment

-the applicable codes, standards, and specifications for the containment are 1 through 23 in Table 2-1 below.* Containment Internal Structures

-all of the items listed in Table 2-1 below are applicable for the containment internal structures.

• Safety-Related Structures Outside of Containment

-all of the items listed in Table 2-1 below are applicable, with the exception of Items 17 and 18.* Foundations for Seismic Category I Structures

-the applicable codes, standards, and specifications are 1 through 14 and 19 through 23 in Table 2-1 below.2-2 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Table 2-1. List of Standards, Codes, and Specifications UFSAR Table 3.8-2 -List of Standards, Codes, and Specifications Specification Specification or Reference Standard Title-Number Designation 1 ACI 318-71, 77, 83 Building Code Requirements for Reinforced Concrete 2 ACI 301 Specifications for Structural Concrete for Buildings 3 ACI 347 Recommended Practice for Concrete Formwork ANSI A145.1 4 ACI 305 Recommended Practice for Hot Weather Concreting ANSI A170.1 5 ACI 211.1 Recommended Practice for Selecting Proportions for Normal Weight Concrete 6 ACI 304 Recommended Practice for Measuring, Mixing, Transporting, and placing concrete 7 ACl 315 Manual of Standard Practice for Detailing Reinforced Concrete Structures 8 ACI 306 Recommended Practice for Cold Weather, Concreting 9 ACI 309 Recommended Practice for Consolidation of Concrete 10 ACI 308 Recommended Practice for Curing Concrete 11 ACl 214 Recommended Practice for Evaluation of-ANSI A146.I Compression Test Results of Field 12 ACI 311 Recommended Practice for Concrete Inspection 13 ACI 304 Preplaced Aggregate Concrete for Structural and Mass Concrete 14 Report by ACI Placing Concrete by Pumping Method Committee 304 15 AISC-69,78 Specification for the Design, Fabrication, and Erection of Structural Steel for Building 16 AWS D1.1 Structural Welding Code 17 ASME Boiler & Pressure Vessel Code, Section III ASME-1971, S73 Division 1, Subsection NE ASME-1974, S75 Division 1, Subsection NF ASME-1973 Division 2, Proposed Standard Code for Concrete Reactor Vessels and Containments Issued for Trial Use and Comments ASME-1 980 Division 2, CC 6000 ASME-1992 1992 Addenda, Division 1, Section XI, Subsection IWL, IWE 18 American Public Test Methods Sulphides in Water, Standard Methods Health Assoc. for the Examination of Water and Waste Water (APHA)19 ASTM Annual Books of ASTM Standards 20 CRSI Manual of Standard Practice I MSP-1 I 2-3 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UFSAR Table 3.8-2 -List of Standards, Codes, and Specifications Specification Specification or Reference Standard Title Number Designation 21 ANSI N45.2.5 Proposed Supplementary Q.A. Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel During Construction Phase of Nuclear Power Plants 22 CRD Chief of Research and Development Standards, Department of the Army, Handbook for Concrete and Cement Volume I and II, Corps of Engineers U.S.Army 23 ACI-349-76, 85 Code Requirements for Nuclear Safety Related Concrete Structures 24 AISI Specification for design of cold-formed steel structural members Seismic qualification of Seismic Category I instrumentation and electrical equipment is in accordance with IEEE 344-1971 or IEEE 344-1975, IEEE Recommended Practices of Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations.(Ref. 2 section 3.10)2-4 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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 guidance.

document.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 Seismic Licensing Naeeient Plant Walkdown Basis IPEEE Peer Name Selection ReieerReiee Engineer Operations Engineer Review Reviewer Reviewer (SWE) Reviewer A. Perez X K. Hull X T.K. Ram X1 M. Delaney X X P. Gazda X T. Bacon X W. Djordjevic X2 D. Shaw (Exelon X Contractor)

D. Karimi (Exelon) X X Notes: 1. Peer Review Team member for SWEL review only.2. Peer Review Team Leader.3-1 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 3.2.1 Stevenson

& Associates Personnel The following provides a synopsis of each individual's background and experiences.

Antonio Perez, P.E.: Mr. Perez is a Senior Engineer III and serves as the General Manager of the S&A Hudson, WI office. He earned his Bachelor of Science degree in Mechanical Engineering at Michigan Technological University and is a licensed Professional Engineer in the states of Wisconsin and Minnesota.

Mr. Perez has over 15 years of experience in project management, project engineering, equipment design, and mechanical systems design and has served in the nuclear power industry for over 11 years. He has extensive experience in Program and Design Engineering and has held positions such as MOV Engineer, Responsible Design Engineer, Design Engineering Supervisor and STA Trainee in the nuclear power industry.

Throughout his years serving in the nuclear power industry,, Mr. Perez has gained knowledge of plant operations, documentation, and SSCs necessary to capably select a broad distribution of SSCs for the SWEL. In addition, his experiences have provided him with knowledge of IPEEE and USI A-46 programs.

Mr. Perez has successfully completed the Near-Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Training Course.Kim Hull: Mr. Hull is a Senior Engineer III in the S&A Hudson, WI office. He earned his Master of Science degree in Mechanical Engineering at Michigan State University.

Mr.Hull has over 30 years of experience in the nuclear power industry and has held positions such as Shift Technical Advisor, Principal Engineer, Senior Instructor, and Mechanical Design Supervisor.

He has an extensive background in all aspects of nuclear power plant modifications with a thorough understanding of configuration control/management along with design and licensing basis of nuclear power plants.Throughout his years serving in the nuclear power industry, Mr. Hull has gained knowledge of plant operations, documentation, and SSCs necessary to capably select a broad distribution of SSCs for the SWEL. In addition, his experiences have provided him with knowledge of IPEEE and USI A-46 programs.

Mr. Hull has successfully completed the Near-Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Training Course.Tribhawan K. Ram, P.E.: Mr. Ram is a Senior Engineer III in the S&A Phoenix, AZ Office. He has over 28 year experience in the nuclear power industry with expertise in plant systems and design engineering.

Currently, Mr. Ram is leading the electrical engineering effort in support of Post-Fukushima Seismic Margin Analysis (SMA) for two Taiwan nuclear stations (PWR and BWR). This effort, in support of the plant Safe Shutdown Equipment List (SSEL), consists of relay list development, relay screening (using GERS, SQURTS or other available testing data), and relay chatter analysis.

Mr.Ram was involved in resolving USI A-46 relay outliers for several plants (Dresden, Quad Cities, Millstone, Palisades, and Pilgrim).

He evaluated dozens of control circuits for relay chattering issues. To replace outliers, Mr. Ram developed and/or supervised the development of modification packages including:

replacement relay selection; relay testing specification preparation; and seismic testing facility visits for relay qualification.

As a systems manager, Mr. Ram conducted periodic system walkdowns to discover and then pursue resolutions for any design, maintenance or operational issues with equipment.

He has developed test plans for circuit breaker and other electrical equipment replacement, including involvement in test plan execution during refueling outages. Mr. Ram has interfaced, with NRC in their biennial Component Design Basis 3-2 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Inspections (CDBI), and with INPO in their biennial evaluations.

Throughout his years serving in the nuclear power industry, Mr. Ram has gained knowledge of plant operations, documentation, and SSCs necessary to capably select a broad distribution of SSCs for the SWEL. In addition, his experiences have provided him with knowledge of IPEEE and USI A-46 programs.

Mr. Ram has MS degrees in Nuclear and Electrical Engineering from the University of Cincinnati, and an MBA from Bowling Green State University.

He is a licensed Professional Engineer (electrical) in Ohio. Mr. Ram has completed a six month training course in BWR systems.Marlene Delaney, P.E., S.E.: Ms. Delaney is a Senior Engineer III in the S&A Chicago, IL Office. She has a Bachelor of Science degree in civil engineering and has more than 30 years of experience in the nuclear power plant industry.

She is a licensed Structural Engineer in the State of Illinois and has a licensed Professional Engineer in several states. She is a SQUG Qualified Seismic Capability Engineer (SCE) and has completed the NTTF Recommendation

2.3 Training

Course (SWE). In addition to her involvement in design and analysis of structures, systems, and components at nuclear power plants, she has performed SQUG walkdowns at various nuclear power plants.Phil Gazda, P.E., S.E.: Mr. Gazda is a Senior Consultant and serves as the Vice President of S&A as well as the Office Manager of the S&A Chicago, IL Office. He is an advanced degree structural engineering graduate and has more than 35 years of experience in the nuclear power plant industry.

He is a licensed Structural Engineer in the State of Illinois and has a licensed Professional Engineer in several states. He is a SQUG Qualified Seismic Capability Engineer (SCE) and has completed the NTTF Recommendation

2.3 Training

Course (SWE). In addition to his involvement in design and analysis of structures, systems, and components at nuclear power plants, he has been involved in SQUG and IPEEE walkdowns and assessments at ten nuclear plants and led the ComEd team performing the SQUG program at Zion Station. Mr. Gazda has also been the moderator for three SQUG qualification training classes provided for utility engineers.

In addition, Mr. Gazda was the Project Manager for the seismic assessment of HVAC ducts at another utility based on EPRI document Seismic Evaluation Guidelines for HVAC Duct and Damper Systems Revision to 1007896.Jim Griffith, P.E. Mr. Griffith is a Senior Engineer III in the S&A Chicago Office. He has a, Bachelor of Science degree in civil engineering and has more than 25 years of experience in the nuclear power plant industry.

He is a licensed Professional Engineer in the State of Wisconsin.

He is a SQUG Qualified Seismic Capability Engineer (SCE)and has completed the NTTF Recommendation

2.3 Training

Course (SWE). In addition to his involvement in design and analysis of structures, systems, and components at nuclear power plants, Mr. Griffith has many years of experience working at numerous nuclear power plants in support of construction, design, outage, and walkdown activities including SQUG walkdowns.

Todd Bacon: Mr. Bacon is a Senior Consultant in the S&A Boston, MA office. He has over 30 years of experience in evaluations of nuclear systems, structures and components, with specialization in the dynamic analysis and design of piping systems, structures and equipment for seismic, other dynamic, fluid, and wind loads. He has managed various ASME Code related tasks for numerous US and international utilities.

Mr. Bacon has been involved with the dynamic analyses of systems associated with the Main Steam and other NSSS systems, as well as many other plant systems. In addition, Mr. Bacon has led the analysis and subsequent regulatory response for a number of issues including GL 96-03 and masonry block wall assessments related to IEB 80-11.3-3 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 He is a licensed Professional Engineer (civil) in the states of California, Ohio, and Georgia. Mr. Bacon has successfully completed the Near-Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Training Course.Walter Diordievic, P.E. Mr. Djordjevic is a Senior Consultant and serves as President of S&A with specialization in the dynamic analysis and design of structures and equipment for seismic, blast, fluid, and wind loads. He has managed and led seismic walkdowns and fragility analyses of structures and components for use in probabilistic risk assessments.

Mr. Djordjevic has 37 years of seismic experience serving the nuclear industry.

Mr. Djordjevic performed and managed more than 20 USI A-46 and IPEEE projects in response to the requirements of Generic Letters 87-02 and 88-20. Mr.Djordjevic has a Master of Science in Structural Engineering from the Massachusetts Institute of Technology.

He has received industry training as a Seismic Capability Engineer (EPRI SQUG training), EPRI IPEEE Add-on, Seismic Fragility and Seismic Walkdown Engineer (SWE).3.2.2 Additional Personnel Exelon plant Operations contract support staff member Mr. David Shaw reviewed the SWEL. Mr. Shaw was an operator on shift at the Byron Station for 28 years and held many positions from entry level Non Licensed Operator up to a licensed Senior Reactor Operator (SRO) in the Control Room. He is familiar with all aspects of the station operating procedures.

Mr. Shaw provided the Operations' review of the SWEL development and final acceptance in accordance with the EPRI guidance document.(Ref. 1) 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.Exelon Engineering staff member Mr. Davood Karimi performed the IPEEE Vulnerabilities Review based, in part, on the Byron IPEEE submittal along with subsequent correspondence and station records. (Ref. 3) Mr. Karami is a civil/structural/mechanical engineer in the Exelon Engineering Department.

He has worked at Byron since the beginning of 2012 and was in a similar position at Limerick Station for four (4) years. He has completed the NTTF Recommendation

2.3 Training

Course (SWE). He has been a lead engineer and representative for several modifications, is a structural monitoring inspector, and is the structural/seismic representative for the Fukushima Project at Byron.3-4 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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-I. Base List 1* Table B-2. Base List 2* Table B-3. SWEL 1 o Table B-4. SWEL 2 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 list for Byron Generating Station Unit 2. (Ref. 1)The SWEL is comprised of two groups of items:* SWEL 1 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)At the request of Byron personnel, the Diesel Driven Essential Service Water Make-Up Pumps and representative supporting Seismic Category I components located in the River Screen House were added to the SPEL. The resulting amended 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 amended IPEEE SPEL was reviewed to determine if it had a defined seismic licensing basis. All items identified as Safety Category I, as defined in Byron UFSAR Chapter 3, were identified as having a defined seismic licensing basis. Electrical enclosures containing Class 1 E devices were identified as Safety Category I. Safety Category I and Class 1 E 4-1 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 determination was made through a review of current design and licensing basis documentation.

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 amended IPEEE SPEL of any Safety Category I Structures, Containment Penetrations, Safety Category 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 Appendix E of Reference 1, 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 designation of 'Support System HVAC', 'Support System AC Power', 'Support System DC Power', 'Engineered Safety Features Actuation System' (ESFAS) or'Cooling Water' may be a frontline or support system. Items with a safety function designation of 'Support System HVAC' (SSHVAC), 'Support System AC Power'(SSAC), 'Support System DC Power' (SSDC), 'Engineered Safety Features Actuation System' (ESFAS) or 'Cooling Water' (UHS) 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) 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 1 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).

4-2 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 B. Major new and replacement equipment The equipment included 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.

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 I Appendix B: Classes of Equipment.

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

1. 1, #2, and #3 resulted in no equipment in the following classes:* (12) Air Compressors

• (13) Motor Generators.

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 included 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. 11)4.2.2 SWEL 2 -Spent Fuel Pool Related Items 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. 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 1 Only those items identified as Seismic Category 1 (Safety Category I) 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 I structure.

Therefore, the SFP structure is assumed to be 4-3 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 seismically adequate for the purposes of this program and is not included in the scope of items included on SWEL 2.Per the Byron UFSAR Chapters 3 and 9, portions of the SFP SSCs are classified as Safety Category I and are screened into the SWEL 2 list. These Safety Category I SSCs include; the Spent Fuel Pit Heat Exchanger, Spent Fuel Pit Pump, Refueling Water Purification Pump OA, associated instrumentation, piping and manual/check valves. Note, these pump's motors are Safety Category II, even though the Refueling Water Purification Pump OA has an ESF power source. There are no Motor, Air or Fluid operated valves in the Safety Category I SSC flow paths.2. Screen #2 -Equipment or Systems This screen considers only those items associated with the SFP that are appropriate for an equipment walkdown process.3. Screen #3 -Sample Considerations This screen represents a process that is intended to result in a SWEL 2 that sufficiently represents a broad population of SFP Seismic Category 1 equipment and systems to meet the objectives of the NRC 50.54(f) letter. The following attributes were considered in the development of SWEL 2: A. A variety of types of systems The system is identified for each item on SWEL 2. The equipment included on SWEL 2 is a representative sample of the systems associated with the SFP and its cooling system.The SFP pump, Refueling Water Purification Pump OA, and SFP heat exchanger are included in the SWEL2 list. A representative sample of instrumentation, manual valves, and check valves are also included.B. Major new and replacement equipment The equipment included on SWEL 2 includes items that have been modified or replaced over the past several years. No such equipment has been identified.

C. A variety of types of equipment The equipment class is identified for each item on SWEL 2. The equipment included on SWEL 2 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 is included on SWEL 2.The classes/types of equipment include; (5) Horizontal Pumps, (21) Tanks and Heat Exchangers, (18) Instrument Racks, and (0) Other. The manual and check valves are included in the "(0) Other" class.D. A variety of environments The location for each item is identified on SWEL 2. The equipment included on SWEL 2 is a representative sample from a variety of environments (locations) for equipment associated with the SFP and its cooling system. All items are in the Auxiliary Building or Fuel Handling Building.4-4 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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 1 (Safety Category I) items, but is limited to those items that could allow rapid drain-down of the SFP. 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.

Excerpts from the Byron UFSAR 9.1.3.2 System Description document the design features which preclude rapid drain down of the Spent Fuel Pit.The Safety Category I spent fuel pool cooling system shown in Drawing M-63 consists of two complete cooling trains. The spent fuel pool cooling system (piping, pumps, valves, and heat exchangers) is Safety Category I, Quality Group C. The 3-inch piping from the refueling water storage tanks to the refueling water purification pump, the pump, and its associated piping and valves are Safety Category I, Quality Group C. A 2-inch Safety Category I, Quality Group C line from the discharge of the refueling water purification pump to the spent fuel pool is permanently installed.

This is the Category I water makeup circuit. The backup Safety Category I makeup system consists of piping and hoses from the Safety Category I fire protection system. The primary water makeup system non-Category I takes water from both primary water storage tanks and routes the water through the spent fuel pool water filter and then to the return header as indicated in Drawing M-63. In addition, primary water may be added to the spent fuel pool via a fire hose connection in the fuel handling building.

In summary, there are three sources of makeup water available, a primary unborated non-Category I source, a borated Safety Category I source, and an unborated fire protection Safety Category I water system. (Ref. 4, 5, and 6)The spent fuel pool system piping arrangement precludes siphoning after any failure by containing a 1/2-inch diameter hole four inches below the water level. Ten feet above the active fuel corresponds to an elevation of 410'-0". Both the cooling and skimmer systems meet this requirement.

No piping in the pool extends below the 410'-0" elevation except the spent fuel pool cooling system discharge pipe. This pipe contains an anti-siphon hole near the surface of the spent fuel pool. Therefore, piping connections to the SPF explicitly contain anti-siphon features which preclude a rapid drain down of the SFP.Excerpts from the Byron UFSAR Section 9.1.3-3 Safety Evaluation discuss SFP Dewatering incidents.

Incident C discussed is a sluice/transfer gate failure with the transfer canal empty, an open/empty transfer tube and an empty refueling cavity. In this incident, the spent fuel pool water level would be lowered approximately 22 feet 10 inches to the bottom sill of the sluice/transfer gate. This leaves at least 2 feet 6 inches of water as shielding over the active portion of the spent fuel in storage.4-5 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 This incident is not considered a rapid drain down transient.

The gate is a structural element, seismically designed as part of the SFP structural analysis, and is a passive barrier with no active components.

There is no rapid drain down consideration included in the Byron Unit 2 SWEL 2 list.4-6 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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, in accordance with the EPRI guidance document during the weeks of August 6 and August 20, 2012. It is noted that during the walkdowns the SWEs were generally accompanied by Operations and Engineering staff.The Seismic Walkdowns and Area Walk-Bys are discussed in more detail in the following 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 1 and SWEL 2 as provided in Appendix B of this report. 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 108 of the 125 items identified on the Byron Unit 2 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.It is noted that Question 6 on the SWCs is answered Y (yes) for all components unless a specific anchorage issue is identified.

This is pointed out because for certain 5-1 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 components Question 6 does not apply. However, the checkbox N/A (not applicable) is not provided as an option to address Question 6.Seismic Walkdowns are deferred for the remaining 17 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 I0CFR50.54(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." 5.2.2 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 CAP as a potentially adverse seismic condition.

5-2 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 5.2.3 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.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 If plant documentation showing the characteristics of the anchorage for a particular item of equipment could not be located, then that item was evaluated further.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 1 102 35 34 38 2 23 21 1 2 Totals 125 56 35 40(1)Notes: 1) Three (3) anchorage confirmations are for deferred items that will be performed as outlined in Appendix E.5-3 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 5.2.4 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 as follows: " Proximity" Failure and falling of SSCs (Seismic II over I)* Flexibility of attached lines and cables 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 5.2.6 provides a summary of issues identified during the Seismic Walkdowns.

5.2.5 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.

5.2.6 Conditions

Identified during Seismic Walkdowns Table 5-2 provides a summary of conditions identified during the equipment Seismic Walkdowns.

The equipment Seismic Walkdowns resulted with a total of seven (7)conditions 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.

The bases of the panels located in the Auxiliary Electric Equipment Rooms (AEER) are covered by a plastic cove molding. This molding prevents the visual inspection of the base weld anchorage detail for each panel. These panels were included on the SWEL 5-4 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 because they were identified as IPEEE enhancements in that the panels were not connected together and in a seismic event could result in contact between the panels.The panels are also important components for functionality in a seismic event. The inspections by the SWEs did verify that the cabinets have been bolted to adjacent panels in response to the IPEEE enhancements.

The welds at the base can be seen through the molding as "bumps" in the material at most locations.

It is assumed that these are the connection welds since the spacing of the bumps closely approximates the detail as specified on Drawing 6E-0-3391 C Revision BE. The seismic walkdown team could not determine if there were any cracks in the welds however the panels are non-vibratory and therefore, cracking of the welds is unlikely.

The seismic walkdown team could not determine if there was any corrosion of the weld however the AEER is a very dry environment so corrosion is unlikely.

Note that for 2 cabinets, the welds at the front of the panel could be'visually inspected since the molding was not present due to a panel ventilation grate. The welds for these 2 cabinets met the drawing requirements with no corrosion and no cracking.

Based on these observations, it is adjudged acceptable to not remove the cove molding to perform an inspection of the anchorage detail. The panels impacted are: 2PA01J -2PA14J, 2PA27J, 2PA28J, 2PA33J, 2PA34J, 2PA51J, and 2PA52J.There are instances in which small/hairline cracks in concrete have been identified on the SWCs as a note and/or with a photograph.

These small/hairline cracks are not of structural/seismic consequence due to their small size.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 38 Area Walk-Bys were performed for Byron Unit 2.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* 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., Seismic Prequalified Scaffolds* Seismic housekeeping was examined to meet station procedure T&RM MA-BY-716-026-1001, Seismic Housekeeping 5-5 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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.Inspections of masonry walls were performed during the Area Walk-Bys.

Masonry walls were identified as seismic either by their placards and/or construction details such as block wall columns. Based on the IPEEE SER, all block walls in seismic areas are built to seismic standards. (Ref. 7)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.

5.3.1 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* Non-Seismic Category I tanks The SWEs exercised their judgment to identify only those seismically-induced interactions that could lead to flooding or spray.5-6 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 5.3.2 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.5.3.3 Conditions Identified during Area Walk-bys Table 5-3 at the end of this section provides a summary of the conditions identified during the Area Walk-Bys.

Eight (8) conditions 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.Through the efforts of the seismic walkdowns and development of this report, IR 1431416 was initiated to share lessons learned with various workgroups across the station. In particular, the IR was issued to create an action to tailgate lessons learned with Electrical Maintenance, Electrical Maintenance Work Planning, and the Maintenance Contractor.

The focal point of the lessons learned is in regards to open fluorescent light fixture S-hooks. The expected S-hook configuration is that they are closed sufficiently to prevent the support chain links from passing though the S-hook up to metal-to-metal contact.It is noted that open fluorescent light fixture S-hooks identified during the Area Walk-Bys were deemed acceptable because they were found only slightly or partially open. In the configuration they were found, it is unlikely that the chain and S-hook could become disengaged.

5.4 SUPPLEMENTAL

INFORMATION ON ELECTRICAL CABINET INTERNAL INSPECTIONS 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 5-7 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 other 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: 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 Components that are identified on Table E-1 (inaccessible and deferred components) are not listed on Table E-2 to avoid redundancy.

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 number (IR number).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.

5-8 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Table 5-2. Conditions Identified during Seismic Walkdowns Action Actions Item ID Description of Issue Request Complete ID (IR) Yes/No(1,2)

OWO01CA CRACKS IN GROUT PAD 1402729 Yes 2VA01SA CRACKS IN GROUT PAD 1399420 Yes 2DC02E FLUORESCENT LIGHTING FIXTURE: OPEN S-HOOKS 1399385 No 2PM05J SCREWS STRIPPED ON BACK OF PANEL 1397684 No 2DC01E FLUORESCENT LIGHTING FIXTURE: OPEN S-HOOKS 1399383 No 2PM06J THUMB SCREW LOOSE 1397697 ' Yes 2VA02SA GROUT PAD NOT INSTALLED AS SHOWN ON DRAWING 1422972 No M-1219 SHEET 3 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 CAP.5-9 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Table 5-3. Conditions Identified during Area Walk-Bys Action Actions Item ID Description of Issue Request Complete ID (IR) Yes/No(1'2)GENERAL FLUORESCENT LIGHTING FIXTURE: 1399405 No OPEN S-HOOKS Area Walk-by 17 ESWCT El 377 (2AP93E) FLUORESCENT

/Area Walk-by 21, ESWCT El 860, South Elec LIGHTING FIXTURE: 1398127 No Room (U2 Bus 232) OPEN S-HOOKS Area Walk-by 49, Aux El 346 U2 open area 0FIT-GW001 DOES NOT HAVE NUTS ON 1399436 Yes SCREWS Area Walk-by 07 Aux El 451 AEER Unit 2 FLUORESCENT LIGHTING FIXTURE: 1397693 No OPEN S-HOOKS Area Walk-by 07 Aux El 451 AEER Unit 2 DENTED LIGHT PAN 1397700 No AREA WALK-BY 01 UNIT 1 AND 2 CONTROL Main Control Room Panel ROOM fasteners require repairs 1399490 No Area Walk-by 65, Area 7 curved wall at Leak at valve 2RY8028 1403160 Yes penetrations Area Walk-by 2, U2 MEER Room Re-install duct tape on 1397702 Yes 2VE06S ductwork.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 CAP.5-10 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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 CAP. In lieu of this process, Exelon/Byron utilized the existing processes and procedures (Site CAP Expectations) to identify, evaluate and document conditions identified during the Seismic Walkdowns.

In accordance with Exelon/Byron 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 CAP 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.Conditions identified during the walkdowns were documented on the SWCs, AWCs, and entered into the CAP. For those conditions that required, seismic licensing basis evaluations were completed and documented within the IR. Tables 5-2 and 5-3 in the report provide the IR, a summary of the condition, and the action completion status.6-1 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 7 IPEEE Vulnerabilities Resolution Report Per the Individual Plant Examination of External Events (IPEEE) Submittal Report and the Staff Evaluation Report of Individual Plant Examination of External Events (IPEEE)submittal of Byron Station, Units I and 2 dated May 30, 2001, an explicit definition of vulnerability was not provided and no vulnerabilities with respect to potential severe accidents related to external events were not identified in the IPEEE submittal. (Ref. 3 and 7) However, plant improvements were identified in Sections 3 and 7 of Reference 3.Table G-1 in Appendix G lists the plant improvements, the IPEEE proposed resolution, the actual resolution and resolution date. No open items exist as a result of the seismic portion of the IPEEE program.7-1 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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* Observation of seismic walkdown on August 6, 2012 by Peer Review Team Leader, Mr. Walter Djordjevic

• 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 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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. Byron/Braidwood Nuclear Stations Updated Final Safety Analysis Report (UFSAR), Revision 13 3. ComEd letter from K. L. Graesser to Office of Nuclear Reactor Regulation, dated December 23, 1996,

Subject:

Transmittal of Byron Station Individual Plant Examination of External Events Submittal Report 4. Byron Station Drawing M-63, Sheet 1A, Rev. BH, Diagram of Fuel Pool Cooling and Clean-up 5. Byron Station Drawing M-63, Sheet 1 B, Rev. BB, Diagram of Fuel Pool Cooling and Clean-up 6. Byron Station Drawing M-63, Sheet 1C, Rev. AV, Diagram of Fuel Pool Cooling and Clean-up 7. Staff Evaluation Report of Individual Plant Examination of External Events (IPEEE)submittal of Byron Station, Units 1 and 2 dated May 30, 2001 8. 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 9. Not used 10. "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 11. BY-MISC-01 9 Rev. 0, "Byron Risk Importance Listings to Support Development of Seismic Walkdown Equipment List (SWEL)." 9-1 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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, Equipment Selection Engineer ...........................................................

A-6 M. Delaney, SWE, Licensing Basis Reviewer ...................................................

A-9 P. Gazda, SWE, Licensing Basis Reviewer .....................................................

A-13 T. Ram, SWEL Peer Reviewer ...................................................................

A-18 W. Djordjevic, Peer Review Team Leader .....................................................

A-20 T .Bacon, Peer R eview er ..........................................................................

A -24 D. Karimi (Exelon), Licensing Basis Reviewer, IPEEE Reviewer .........................

A-29 A-1 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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 Stev Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 enson & 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* Integrated mechanical systems and designed equipment for material handling systems.* Procured equipment and coordinated delivery schedules with vendors.Page 2 of 3 A-3 Stev Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 enson & 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" 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 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 A-5 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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 1OCFR50.59 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 IllI/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 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161.inspection findings.

Assigned to review all calculations, modification packages, 10CFR 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 I 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 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 A-8 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Stevenson

& Associates MARLENE M. DELANEY PROFESSIONAL EXPERIENCE March 1998 -Present Stevenson

& Associates Project Engineer Stevenson

& Associates is a structural/mechanical engineering firm.Job tasks as a Project Engineer include performing engineering and project engineering activities on a broad scope of projects.

Typical engineering activities include: " Seismic equipment qualification and anchorage design.* Component and support evaluations including modifications and new designs.* Analysis and modification design for cable tray systems." SQUG/IPEEE evaluations and walkdowns." Reinforced concrete analysis.* Structural steel framing assessments.

• Detail fabrication drawings for steel modifications." Interface with clients on all aspects of projects.January 1981 -February 1998 Sargent & Lundy Engineers Senior Engineer, Engineer Sargent & Lundy is an engineering firm that consults primarily to the power industry.Job tasks as a Senior Engineer included: " Performing project engineering and project management duties for numerous plant modification projects.

Responsibilities included overall project scheduling, technical supervision, and budget control." Interfaced with clients, contractors on various projects." Prepared conceptual design report and cost estimates for rehabilitation of hazardous waste handling facility and canal water treatment facility owned by Argonne National Laboratories." Field engineer at LaSalle County Nuclear Station, Enrico Fermi Atomic Power plant and Zion Nuclear Station.* Supervised and coordinated analysis of structural framing and designed modifications to such structures.

• Evaluated and designed modifications for railroad bridges.* Detailed fabrication drawings.Page 1 of 2 A-9 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 EDUCATION University of Wisconsin

-Milwaukee, Bachelor of Science in Civil Engineering, Graduated with Honors.PROFESSIONAL REGISTRATIONS Licensed Professional Engineer in the State of Wisconsin Licensed Structural Engineer in the State of Illinois Licensed Professional Engineer in the State of Illinois Page 2 of 2 A-1 0 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 A-11 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 A-12 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 STEVENSON

& ASSOCIATES PHILIP A. GAZDA PROFICIENCIES 0 0 0 0 0-0 0 0 0 Civil engineering Structural analysis and design Structural dynamics Plant betterment Specifications Project management Excellent communication, presentation and organizational skills Proven ability to function as part of a team SQUG and IPEEE assessments Strong commitment to customer service and long term relationships EXPERIENCE 1997 -Present Stevenson

& Associates 1995-1997 ComEd General Manager, Stevenson

& Associates

-Chicago Responsible for the day to day operation of the S&A Chicago office.Manages the engineering efforts of the Chicago office and coordinates the efforts with other S&A offices.He is a SQUG Qualified Seismic Capability Engineer.

He been involved in SQUG and IPEEE walkdowns and assessments at ten nuclear plants and led the ComEd team performing the SQUG program at Zion Station. Mr. Gazda has also been the moderator for three SQUG qualification training classes provided for utility engineers.

In addition, Mr. Gazda was the Project Manager for the seismic assessment of HVAC ducts at another utility based on EPRI document Seismic Evaluation Guidelines for HVAC Duct and Damper Systems Revision to 1007896.Head -Maintenance Engineering Department.

Zion Nuclear Power Station Managed and coordinated the activities of thirty-five Mechanical, Electrical, Structural and Program Engineers who supported the operation and maintenance of the Zion Nuclear Power Station.Support activities included engineering trouble shooting and evaluations to repair degraded electrical, mechanical and structural components/systems.

Oversaw engineering programs such as In Service Inspection, Vibration Testing, Thermographic Investigations and the Evaluation and repair of piping systems for the effects of Flow Accelerated Corrosion.

Performed administrative duties related to the management of the Maintenance Engineering Department.

Conducted and managed the Zion SQUG and IPEEE programs.1986 -1995, Associate and Senior Project Engineer Managed, coordinated and was responsible for the activities of the structural team engaged in the analysis and design of the structural 1973- 1995 Sargent & Lundy A-13 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 and civil portions of power plants and other miscellaneous structures.

Had ultimate responsibility and ownership for the quality of the structural team and the product produced by the team. The team included hydrologists, geologists, soils engineers, architects, designers and structural engineers depending on the expertise required for each project. Responsible for coordinating the structural work with that of the Mechanical and Electrical disciplines on the project team. Established the technical approach and design criteria for the work, set schedules, and authorized drawings for construction.

1983 -1986, Project Engineer The responsibilities are essentially the same as those described for the Senior Project Engineer (see above). Reported to the Senior Project Engineer.1979 -1983, Supervising Design Engineer Supervised the team generating engineering analyses, calculations, sketches, designs and drawings for steel and concrete structures, foundations, and electrical and mechanical component supports.Reported to Project Engineer.1978 -1979, Supervising Structural Engineering Specialist Supervised the team that performed the structural analysis and design of specialized power plant structures such as containments, fuel pools, base mats, and drywells.

Reported to Project Engineer.1973 -1978, Senior Structural Engineering Specialist (1976 -1978)Structural Engineering Specialist (1973 -1976)Performed the analysis and design of power plant structures.

This work included dynamic analysis for seismic and hydrodynamic loads, finite element analysis, and reinforced concrete and steel design for structures and foundations.

Extensively involved in the analysis, design and construction of the heavy reinforced concrete structures for Illinois Power's Clinton Station. Reported to Project Engineer.1972 -1973 Research Assistant University of Illinois Performed research at the University of Illinois for the U.S.Department of Transportation tunnel liner support system project.A-14 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 EDUCATION* University of Illinois at Urbana, IL.M.S. Civil Engineering" University of Illinois at Urbana, IL.B.S. Civil Engineering REGISTRATIONS 0 0 0 0 0 Licensed Structural Engineer -Illinois Licensed Professional Engineer -Wisconsin Licensed Professional Engineer-Texas Licensed Professional Engineer -Nebraska Licensed Professional Engineer -Minnesota MEMBERSHIPS

&AFFILIATIONS PUBLICATIONS" American Concrete Institute" American Society of Civil Engineers* Structural Engineers Association of Illinois* University of Illinois Civil Engineering Alumni Association Board of Directors, 1992 -2000 University of Illinois Civil Engineering Student Mentor Program, 1993 -present* "Using Advanced Computer Technology to Consolidate Project Information" (co-author), American Power Conference, Chicago, Illinois, April, 1993* "Structural Considerations in Steam Generator Replacement" (co-author), American Power Conference, Chicago, Illinois, April 1991* "Nuclear Plant License Renewal -Structural Issues" (co-author), American Power Conference, Chicago, Illinois, April 1991" "Modifications at Operating Nuclear Power Plants" (co-author), American Society of Civil Engineers Convention, Denver, Colorado, April 1985* "Engineering of Structural Modifications for Operating Nuclear Power Plants" (co-author), Seventh International Conference on Structural Mechanics in Reactor Technology, Chicago, Illinois, August 1983 A-15 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161... .... .... ...fl9 9--xad 9t.Iui 9 9j-lxr -9xI- L- J Certificate of Completion Phil Gazda Successfully Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Bruce M.'Lrry -Instructor NTTF 2.3 Seismic Walkdown Course Date: 06/26/12 t 6 6 4'6 V V V V V V V V V V V V V V V V A-16 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 A-17 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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 a Transformer and Relay(s) Spec Developer* Plant Modification Engineering

• Systems and Component Test Engineering

• Factory Testing Witness* 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-18 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-1 2-161 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-19 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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-20 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. I Correspondence No.: RS-12-161 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-21 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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-1 06.1983 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 1 E Devices Using In-Situ Testing and Analysis." 1986 Testing of Lithography Components for Vibration Sensitivity, Microelectronics, Cahners Publishing 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-22 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 a -1 V nasa a a V V* a a taa Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 WýCertificate of Completion Walter Djordjevic Successfullij Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns lie, ((ý/ ODq)Date: 06/26/12 Bruce M. Lorf- Instructor NTTF 2.3 Seismic Walkdown Course N i a 0 ap I V V V V V V V V V V V V V V V A-23 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 S275 Mishawum Road, Suite 200. Woburn, MA 01801 Tel (781) 932-9580 Fax (781) 933-4428 www. vecsa.CoIn 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 II, and the Flaw Analysis group of Section XI.Other Code experience includes the American Institute of Steel Construction (AISC), American Concrete BOSTON oCLEVELAND sCHICA GO eMINNEA POLIS ePHOENIX A-24 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 275 A4ishawum Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 Fax (781) 933-4428 www. veesa. coin 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 PCLEVELAND

@CHICA GO *MINNEAPOLIS

• PHOENIX A-25 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 275 .Mishawum Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 FPax. (781) 933-4428 www. vecsa.cofl 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 I 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 study have 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 eCLE VELA ND PCHICAGOe MINNEAPOLIS

• PHOENIX A-26 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 275 Mishawwn Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 Tay (781) 933-4428 wwW. vevCa. coin 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, TU Electric -Involved in licensing and special studies projects for the Comanche Peak Station.SSFIAudit Responses, CoinEd -Participated in responding to concerns raised during safety system functional inspection (SSFI) audits.Project Summary Reports and Operability Guidelines, CornEd and AEPSC -Wrote numerous project summary reports and operability guidelines for Commonwealth Edison (ComEd) 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 1 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 *CLEVELAND

@CHICAGO *MINNEAPOLIS

• PHOENIX A-27 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Certificate of Completion Todd Bacon Successfulli)

Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Bruce M.L0'fy -Instructor NTTF 2.3 Seismic Walkdown Course Date: 06/26/12 A-28 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 DAVOOD KARIMI PROFESSIONAL EXPERIENCE Exelon Nuclear Corp, Byron, IL CIVIL/STRUCTURAL/MECHANICAL ENGINEER January, 2012 -Present S 0 S S 0 Structural/Seismic Engineer representative for Fukushima Project.EPRI Seismic Walkdown Engineer (SWE) training, 2012 Lead Responsible Engineer for River Screen House Air Compressor Modification.

Structural monitoring program inspector of all nuclear power plant Al and A2 structures.

Scaffolding qualification expert.Exelon Nuclear Corp, Limerick, PA CIVIL/STRUCTURAL/MECHANICAL ENGINEER January, 2008 -December, 2011* Lead Responsible Engineer for MUR-PU Implementation Project at LGS.* Lead Responsible Engineer for Replacement of all GE-BETZ Chemical Treatment Systems with new NALCO Chemical Treatment Systems." Mechanical Engineer representative for replacing Reactor Recirc Motor Generator Sets with Adjustable Speed Drives." Lead Responsible Engineer for design and application of chemical skid project.* Structural monitoring program inspector of all nuclear power plant Al and A2 structures.

• License renewal document reviewer for station civil/structural documents.

PROFESSIONAL DEVELOPMENT Education BS in Civil Engineering, December 2007 -University of Illinois at Chicago FE/EIT Engineer, 2008 Activities ASCE Member, Society of Hispanic Professional Engineers (SHPE), North American Young Generation in Nuclear (NA-YGN)A-29 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 I 111lIC POWto Certificate of Completion Davood Karimi Training on Near Term Task Force Recommendation 2.3-Plant Seismic Walkdowns June 27, 2012 ft0 M -se K. KmAUMM Stuc"Wa Rtulobut a ktqd^A-30 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 B Equipment Lists Appendix B contains the equipment lists that were developed during SWEL development.

The following contents are found in Appendix B: SWEL Approval Signature Page .....................................................................

B-2 T a ble B -I, B a se List 1 ...................................................................................

B -3 T a ble B -2 , B ase List 2 .................................................................................

B -4 1 T a ble B -3 , S W E L 1 .....................................................................................

B -4 3 T a ble B -4 , S W E L 2 .....................................................................................

B -4 9 B-1 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. I Correspondence No.: RS-12-161 SA Stevenson

& Associates.Seismic Walkdown Interim Report, Revision 0 In Response to NTTF Recommendation 2.3: Seismic Byron Generating Station Unit 2 Kim L. Hull Equipment Selection Preparer Tony Perez Equipment Selection Reviewer 7,[1 -e% -David Shaw Station Operio'ns Staff Member Refer to Attachrfent 3 for synopsis of Station Operations role and responsibility.

07/31/2012 date 07/31/2012 date date B-2 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Table B-1. Base List 1 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 0 0WVW01PA ASSY -PUMP DEEP WELL M-83 M-3 GL Out 400 401 OUTSIDE 0 0VWW01PB ASSY -PUMP DEEP WELL M-83 M-3 GL Out 400 401 OUTSIDE 0 OCC01P ASSY -U-0 CC PP Aux 364 364 15-21/L-Q GENERAL AREA 0 '0PM01J PANEL CONT MCB GEN SERV 0-3378 MCR Aux 451 451 MAIN CONTROL RM U-1 & U-2 0 OPM02J ANNUNCIATOR RSH CONTROL PANEL Aux 451 451 MAIN CONTROL RM U-1 & U-2 0 0VC15J MCR U-1 HVAC START PNL Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OCC01E CC PP 0 BRKR Aux 383 383 15-21/N-Q GENERAL AREA 0 OSX02AA OA SXCT BASIN ESWCT 868 ESWCT 0 OSX02AB OB SXCT BASIN ESWCT 868 ESWCT 0 OWWO19A ASSY -AOV 0B DEEP WELL PP O0WW1PB ESWCT 860 ESWCT TO OA SXCT LCV 0 OWW01 9B ASSY -AOV OA DEEP WELL PP OWWO1PA ESWCT 860 ESWCT TO OB SXCT LCV 0 0WO01CA OA MCR CHLR Aux 383 383 CHILLED WTR RMS (8-10/L-P) 0 OWO01CB OB MCR CHLR Aux 383 383 CHILLED WTR RMS (8-10/L-P) 0 OWO01PA ASSY -OA MCR WO PP Aux 383 383 CHILLED WTR RMS (8-10/L-P) 0 OWO01 PB ASSY -OB MCR WO PP Aux 383 383 CHILLED WTR RMS (8-10/L-P)

O 0W0144A GA MCR WO M/U PRV Aux 383 3 S0WO0144B GB MCR WO M/U PRV Aux 383 3 0 0WO14MA SEPARATOR AIR M-118 Aux 383 383 CHILLED WTR RMS (8-10/L-P) 0 OWO14MB SEPARATOR AIR M-1 18 Aux 383 383 CHILLED WTR RMS (8-10/L-P) 0 OVC01AA GA MCR CHLD WTR CLG COILS & CAB Aux 451 451 U-1 HVAC EQUIP RM (10-11 /L-Q)0 OVC01AB GB MCR CHLD WTR CLG COILS & CAB Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC01CA ASSY -GA MCR HVAC SUP FAN Aux 451 451 U-1 HVAC EQUIP RM (10-11 /L-Q)0 0VC01CB ASSY -GB MCR HVAC SUP FAN Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC01FA GA MCR HVAC SUP FLTRS Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 0VC01FB GB MCR HVAC SUP FLTRS Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 GVC01JA MCR HVAC GA LOC CONT PNL Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC01JB MCR HVAC GB LOC CONT PNL Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC01SA GA MCR HVAC M/U AIR FLTR UNIT Aux 463 463 HVAC GENERAL ARA (11-15/L-Q) 0 OVC01SB OB MCR HVAC M/U AIR FLTR UNIT Aux 463 463 HVAC GENERAL ARA (21-25/L-Q) 0 OVC01YA DAMPER ISO FC 38WX34H Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC01YB DAMPER ISO FC 38WX34H Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q)

Table B-1 Page 1 of 38 B-3 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 0 0VC02CA ASSY -OA MCR HVAC RTRN FAN Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC02CB ASSY -0B MCR HVAC RTRN FAN Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC02FA OA MCR HVAC RECIRC CHAR ADSORB Aux 451 451 U-1 HVAC EQUIP RM (10-1 1/L-Q)0 OVC02FB 0B MCR HVAC RECIRC CHAR ADSORB Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC03CA ASSY -OA MCR M/U AIR FLTR UNIT Aux 463 463 HVAC GENERAL ARA (111-15/L-Q)

____ ___OVC01SA FAN _ _ _ _ _ _ _ _ _ _ _ _0 0VC03CB ASSY -0B MCR M/U AIR FLTR UNIT FAN Aux 463 463 HVAC GENERAL ARA (21-25/L-Q) 0 0VC05YA DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 0VC05YB DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 0VC05YC DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 0VC05YD DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 0VC06YA DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC06YB DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC06YC DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC06YD DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC08Y DAMPER MOD FO 18WX28H Aux 463 463 HVAC GENERAL ARA (21-25/L-Q) 0 OVC09Y DAMPER ISO FO BF-201N Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 451 U-2 AUX ELECTRIC EQUIP RM (23-0 OVC16J MCR U-2 HVAC START PNL Aux 463 451M-23 1 25/M-Q)0 OVC17YA DAMPER ISO FC 38WX34H Aux 451 451 U-1 HVAC EQUIP RM (10-1 1/L-Q)0 OVC17YB DAMPER ISO FC 38WX34H Aux 451 451 U-1 HVAC EQUIP RM (10-1 1/L-Q)0 OVC21YA DAMPER ISO/MOD FO BF-54 Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC21YB DAMPER ISO/MOD FO BF-54 Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC21YC DAMPER ISO/MOD FO BF-54 Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC21YD DAMPER ISO/MOD FO BF-54 Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC22YA DAMPER ISO/MOD FO BF-54 Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC22YB DAMPER ISO/MOD FO BF-54 Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC22YC DAMPER ISO/MOD FO BF-54 Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC22YD DAMPER ISO/MOD FO BF-54 Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC24Y DAMPER MOD FO 18WX28H Aux 463 463 HVAC GENERAL ARA (11-15/L-Q) 0 OVC25Y DAMPER ISO/MOD FO BF-20 Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OSX007 ASSY -MOV U-0 CC HX OCC01A SX OUTLET Aux 346 +12 (EOP VLV)0 __0SX007___

ISOL VLV Ax3 +1(OVL 00 OSX03CA ASSY -OA SXCT FAN ESWCT 909 ESWCT 0 IOSX03CB ASSY -OB SXCT FAN ESWCT 909 ESWCT Table B-1 Page 2 of 38 B-4 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 0 OSX03CC ASSY- 0C SXCT FAN ESWCT 909 ESWCT 0 OSX03CD ASSY -OD SXCT FAN ESWCT 909 ESWCT 0 OSX03CE ASSY -OE SXCT FAN ESWCT 909 ESWCT 0 OSX03CF ASSY -OF SXCT FAN ESWCT 909 ESWCT 0 OSX03CG ASSY -OG SXCT FAN ESWCT 909 ESWCT 0 OSX03CH ASSY -OH SXCT FAN ESWCT 909 ESWCT 0 0SX146 ASSY -MOV U-0 CC HX TO U-I SX RTRN Aux 346 346 15-23/N-Q GENERAL AREA HDR ISOL VLV 0 0SX147 ASSY- MOV U-0 CC HX TO U-2 SX RTRN Aux 346 346 15-23/N-Q GENERAL AREA HDR ISOL VLV 0 OSX157A ASSY -MOV OA SX M/U PP TO OA SXCT ESWCT 872 +04 N CNR-VLV RM BASIN ISOL VLV ASSY -MOV 08 SX M/U PP TO 08 SXCT 00 0SX157B ESWCT 872 +04 S CNR VLV RM BASIN ISOL VLV 00 0SX158A ASSY -MOV OA SX M/U PP TO OA SXCT ESWCT 872 +04 N CNR VLV RM BASIN ISOL VLV 00 OSX158B ASSY -MOV 08 SX M/U PP TO 08 SXCT ESWCT 872 +04 S CNR VLV RM BASIN ISOL VLV 00 0SX162A ASSY -MOV OA SXCT TO BASIN BYP VLV ESWCT 872 +01 OA VLV RM, (EOP VLV)0 0SX162B ASSY -MOV OB SXCT T-O BASIN BYP VLV ESWCT 872 +01 0B VLV RM, (EOP VLV)0 0SX162C ASSY -MOV OA SXCT T-O BASIN BYP VLV ESWCT 872 +01 OA VLV RM, (EOP VLV)0 0SX162D ASSY -MOV OB SXCT T-O BASIN BYP VLV ESWCT 872 +01 OB VLV RM, (EOP VLV)0 0SX163A SXCT OA RISER VLV OA L/S HTR, ESWCT 874 ESWCT 0 0SX163B SXCT OA RISER VLV OB L/S HTR ESWCT 874 ESWCT 0 OSX163C SXCT OA RISER VLV 0C L/S HTR ESWCT 874 ESWCT 0 0SX163D SXCT OA RISER VLV 0D L/S HTR ESWCT 874 ESWCT 0 0SX163E SXCT 0B RISER VLV OE L/S HTR ESWCT 874 ESWCT 0 0SX163F SXCT 0B RISER VLV OF US HTR ESWCT 874 ESWCT 0 0SX163G SXCT 0B RISER VLV OG US HTR ESWCT 874 ESWCT 0 0SX163H SXCT 0B RISER VLV OH US HTR ESWCT 874 ESWCT 0 OCC01A U-0 CC HX Aux 364 364 15-21/L-Q GENERAL AREA 0 OTE-0675 CC HEAT EXCHANGER 0 DISCH 100 OHM Aux 364 364 15-21/L-Q GENERAL AREA PLATINUM RTD OA MCR CLG COIL OVC01AA WO INLET HDR 2J?0WO029A DRN VLV Aux 1 451 _1_1 Table B-1 Page 3 of 38 B-5 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION o GW0029B 0B MCR CLG COIL OVC01AB WO INLET HDR Aux 451 1 DRN VLV ._ _GA MCR WO AIR SEP 0WO14MA DRN HOSE o 0WO111A CNISLLVAux 383 2 CONNI80L VLV o OW0111B G0B MCR WO AIR SEP 0WO14MB DRN HOSE Aux 383 2 CONN ISOL VLV o 0W02142A GA MCR WO STANDPIPE 0WO20MA DEMIN Aux 383 5 WTR QUICK FILL ISOL VLV GB MCR WO STANDPIPE 0WO20MB DEMIN WTR QUICK FILL ISOL VLV A 0 0WO205A GA MCR CHLR WTR M/U CHK VLV Aux 383 3 0 0WO205B 0B MCR CHLR WTR M/U CHK VLV Aux 383 3 0 OVC02Y DAMPER ISO/MOD FC BF-54 Aux 451 0 OVC033Y DAMPER ISO FC 84WX34H Aux 451 0 0VC03Y DAMPER ISO FO 54WX46H Aux 451 0 OVC094Y DAMPER ISO FO 20WX46H Aux 463 0 OVC095Y DAMPER ISO FO 40WX20H Aux 463 0 OVC104Y DAMPER ISO FO 36WX24H Aux 463 8 0 OVC133Y DAMPER ISO FO 36WX24H Aux 463 0 0VC140Y DAMPER ISO FO 36WX24H Aux 463 0 OVC172Y DAMPER ISO FC 84WX34H Aux 451 0 OVC175Y DAMPER ISO FO 42WX20H Aux 463 0 OVC182Y DAMPER ISO FO 20WX48H Aux 463 0 OVC18Y DAMPER ISO/MOD FC BF-54 Aux 451 0 0VCl9Y DAMPER ISO FO 54WX46H Aux 451 0 OVC217Y DAMPER ISO FO 22WX38H Aux 463 0 OVC312Y DAMPER ISO FC 22WX22H Aux 451 0 OVC313Y DAMPER ISO FC 16WX30H Aux 451 0 OVC51Y DAMPER ISO FC 38WX34H Aux 451 0 0SX028A OA SX M/U PP OSX02PA DSCH CHK VLV RSH 686 2 0 0SX028B 0B SX M/U PP OSX02PB DSCH CHK VLV RSH 686 2 o OSX063A ASSY -MOV0GA MCR CHLR CNDSR SX Aux 383 +10 (EOPVLV)SX INLET VLV Ix8 +0EPL GO 05X063B ASSY -MOV 0B MCR CHLR CNDSR SX Aux 383 +10 (EOP VLV)00SX0 INLETVLV Ax8 +0EPL Table B-1 Page 4 of 38 B-6 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION ASSY -HMOV OA MCR CHLR CNDSR SX 00 0SX064A Aux 383 8________OUTLET TCV_____o OSX064B ASSY -HMOV 0B MCR CHLR CNDSR SX Aux 383 8 OUTLET TCV SX TO RESID CHLORINE ANAL OCF03J ISOL 0 0OSX167A VAux 346 +6 4' S OF Q1ll___ ___ __VLV_ _ _ _ _0 OSX167B SX TO RESID CHLORINE ANAL OCF04J ISOL Aux 346 +9 8'W OF Q I _ VLV 0 0SX169A SX M/U HDR OA VAC RLF VLV Out 400 BTWN RSH & PLANT 0 OSX169B SX M/U HDR OB VAC RLF VLV Out 400 BTWN RSH &-PLANT 0 OSX169C SX M/U HDR OC VAC RLF VLV Out 400 BTWN RSH & PLANT 0 OSX169D SX M/U HDR OD VAC RILF VLV Out 400 BTWN RSH & PLANT 0 0SX169E SX M/U HDR OE VAC RLF VLV Out 400 BTWN RSH & PLANT 0 OSX169F SX M/U HDR OF VAC RLF VLV Out 400 BTWN RSH & PLANT SX TO AUX BLDG FP RING HDR XTIE ISOL 0 0SX174 Aux 346 10 VLV (EOP VLV)0 OSX172 SX TO AUX BLDG FP RING HDR XTIE ISOL Aux 383 2 VLV (EOP VLV)0 OSX02PB DIESEL DRIVEN SX MAKE-UP PUMP RSH 686'6" 686'6" 2C 0 ODO08TB OB SX Pp 2000 GALLON DIESEL OIL RSH 702 702 1C7_STORAGE TANK 0 OSX02JA OA SX M/U PP OA Control Cabinet RSH 702' 702' 06 BA 2 2PA28J CAB RELAY AUX SAFEGUARD TRN B 0- Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-3373B AB2 25/M-Q)451 U-2 DIV 21 MISC ELEC EQUIP RM 2 2DC03E 125V DC BATT CHGR 211 Aux 451 (26-28/L-M) 451 U-2 DIV 22 MISC ELEC EQUIP RM 2 2DC04E 125V DC BATT CHGR 212 Aux 451 456-2D2M-EI (26-28/M-Q) 451 U-2 DIV 21 MISC ELEC EQUIP RM 2 2DC05E 125V DC ESF DISTR CENTSR BUS 211 Aux 451 456-2D2L-EI (26-28/L-M) 451 U-2 DIV 22 MISC ELEC EQUIP RM 2 2DC06E 125V DC ESF DISTR CENTER BUS 212 Aux 451 456-2D2M-EI (26-28/M-Q) 2 2RC8001D Loop D RC Hot Leg Stop Valve Cont 401 El. 401 IMB 2 2RC8002D Loop D RC Cold Leg Stop Valve Cont 401 El. 401 IMB Table B-1 Page 5 of 38 B-7 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2TE-0674 CC HEAT EXCHANGER 2 DISCH TEMP 100 Aux 364 364 15-21/L-Q GENERAL AREA OHM PLAT RTD 2 2PM01J PANEL CONT MAIN BOARD GEN/AUX PWR 0 Aux 451 451 MAIN CONTROL RM U-1 & U-2 3378 MCR 2 2PM04J PANEL CONT MAIN BOARD FEEDWATER 0- Aux 451 451 MAIN CONTROL RM U-1 & U-2 3378 MCR 2 2PM05J PANEL CONT MAIN BOARD RX/CV 0-3378 Aux 451 451 MAIN CONTROL RM U-1 & U-2 MCR 2 2PM06J PANEL CONT MAIN BOARD ENE SAFETY 0- Aux 451 451 MAIN CONTROL RM U-1 & U-2 3378 MCR PANEL INST NUCLEAR W-RACK 1-4 0-3378 2 2PM07J PAE Aux 451 451 MAIN CONTROL RM U-1 & U-2____ MCR 2 2PM11J PANEL ISOLATION CONTAINMENT 0-3378 Aux 451 451 MAIN CONTROL RM U-1 & U-2 MCR 2 2PM12J CONSOLE INST MISC 0-3378 MCR Aux 451 451 MAIN CONTROL RM U-1 & U-2 451 U-2 DIV 22 MISC ELEC EQUIP RM.2 21P06E INVERTER INST BUS 212 2-3371 AB2 Aux 451 456-2D2M-E P (26-28/M-Q) 451 U-2 DIV 22 MISC ELEC EQUIP RM 2 21P08E INVERTER INST BUS 214 2--371 AB2 Aux 451 456-2D2M-EI (28-28/M-Q) 2 21P03E TRANSFORMER REG INSTRUMENT BUS Aux 451 213, 426 GENERAL AREA -AREA 2 & 3 (10-2 2AP32E ASSY -480VAUX BLDG ESF MCC 232X5 Aux 426 26 EA R23 21/L-Q)2 2DG01SB AIR COMPRESSOR PACKAGE 2B Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2CV8152 ASSY -AOV U-2 LTDWN HDR ISOL VLV Aux 374 383 U-2 AREA 7 CURVED WALL AREA (EOP VLV)2 2CV1 12E ASSY -MOV RWST TO U-2 CHG PPS SUCT Aux 364 364 U-2 AREA 7 CURVED WALL AREA ISOL VLV 451 U-2 DIV 22 MISC ELEC EQUIP RM 2 2RD05E REACTOR TRIP SWITCHGEAR Aux 451 456-2D2M-EI I (26-28/M-Q)

~451 U-2 DIV 21 MISC ELEC EQUIP RM 2 21P05E INVERTER INST BUS 211 2-3371 AB2 Aux 451 456-2D2L-EI I I (26-28/L-M) 2 2AP27E ASSY -480V AUX BLDG ESF MCC 232X2 Aux 426 426 AREA 7 CURVED WALL AREA 2 2AP92E ASSY -480V SXCT MCC 232Z1, SOUTH ESWCT 874 ESWCT ELEC RM Table B-1 Page 6 of 38 B-8 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2AP93E ASSY -MCC 231Z1 ESW COOLING TOWER ESWCT 874 ESWCT 2 2AP98E 480V ESF SXCT UNIT SUBSTA 232Z, SOUTH ESWCT 874 ESWCT ELEC RM 2 2AP99E ASSY -480V ESF SXCT UNIT SUBSTA 231Z, ESWCT 874 ESWCT NORTH ELEC RM 2 2PA4OJ PANEL ISOLATION CONTAINMENT 0-3378 451 MCR PANEL ISOLATION CONTAINMENT 0-3378 2 2PA39J MC451 MCR 2 1 PA 40J PANEL ISOLATION CONTAINMENT 0-3378 451 MCR 2 1 PA39J iPANEL ISOLATION CONTAINMENT 0-3378 451 MCR PANEL ISOLATION CONTAINMENT 0-3378 2 1MPA 9J _ _ _ 451 2 2PA01J CAB PROC I+C RACK PROT CH 1 0-3373B Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-AB2 25/M-Q)CAB PROC I+C RACK PROT CH 2 0-3373B 451 U-2 AUX ELECTRIC EQUIP RM (23-2 2PA02J AB2 Aux 451 25/M-Q)ICAB PROC I+C RACK PROT CH 3 0-3373B 451 U-2 AUX ELECTRIC EQUIP RM (23-2 2PA03J AB2 Aux 451 25/M-Q)2 2PA04J CAB PROC I+C RACK PROT CH 4 0-3373B Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-AB2 25/M-Q)2 2PA06J CAB PROC I+C RACK CONT GRP 2 0-3373B Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-AB2 25/M-Q)2 2PA07J CAB PROC I+C RACK CONT GRP 3 0-3373B Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-AB2 25/M-Q)2 2PA08J CAB PROC I+C RACK CONT GRP 4 0-3373B Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-AB2 25/M-Q)CAB PROT SYST SOL ST RX/ESF TRN A 0- 451 U-2 AUX ELECTRIC EQUIP RM (23-2 2PA09J 3373B AB2 Aux 451 25/M-Q)Table B-1 Page 7 of 38 B-9 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2PA10J CAB PROT SYST SOL ST RX/ESF TRN B 0- Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-3373B AB2 25/M-Q)2 2PA1 1J CAB TEST SAFEGUARD TRN A 0-3373B AB33 Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-1__ _ _ _ _ _ _ __ _ _ _ _____ 25/M-Q)451 U-2 AUX ELECTRIC EQUIP RM (23-2 2PA12J CAB TEST SAFEGUARD TRN B 0-3373B AB2 Aux 451 451M-2E 25/M-Q)451 U-2 AUX ELECTRIC EQUIP RM (23-2 2PA13J CAB ESF SEQ/ACT TRN A 0-3373B AB2 Aux 451 451M-2E 25/M-Q)2 2PA14J CAB ESF SEQ/ACT TRN B 0-3373B AB2 Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-25/M-Q)J CAB RELAY AUX SAFEGUARD TRN A 0- 451 U-2 AUX ELECTRIC EQUIP RM (23-25/M-Q)J 3373B AB2 25/M-Q)451 U-2 AUX ELECTRIC EQUIP RM (23-2 2PA33J CAB CONT SYSTEM ESF 21 0-3373B AB2 Aux 451 5MQ 2 2PA34J CAB CONT SYSTEM ESF 22 0-3373B AB2 Aux 451 45U2AXELCRCQIPM(3-

____ ____ ____ __ _ ____ ___25/M-Q) 2 2PA51J CAB HJTC RX VESSEL LEVEL CH A 0-3373B Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-AB2 25/M-Q)2 2AP25E ASSY -480V AUX BLDG ESF MCC 231X2 Aux 414 414 CURVED WALL AREA -AREA 7 2 21P04E TRANSFORMER REG INSTRUMENT BUS Aux 451 214 2 2CV8160 Isolation Valve Cont 377 15 2 2AP24E ASSY -480V AUX BLDG ESF MCC 232X3 Aux 383 383 15-21/N-Q GENERAL AREA 2 2FT-AF01 1 AUX FW TO SG 2A FLOW XMTTR Aux 364 364 21-26/L-Q GENERAL AREA 2 2FT-AF012 AUX FWTO SG 2A FLOW XMTTR Aux 364 364 21-26/L-Q GENERAL AREA 2 2FT-AF013 AUX FW TO SG 2B FLOW XMTTR Aux 364 364 21-26/L-Q GENERAL AREA 2 2FT-AF014 AUX FWTO SG 2B FLOW XMTTR Aux 364 364 21-26/L-Q GENERAL AREA 2 2FT-AF015 AUX FW TO SG 2C FLOW XMTTR Aux 364 364 21-26/L-Q GENERAL AREA 2 2FT-AF016 AUX FWTO SG 2C FLOWXMTTR Aux 364 364 21-26/L-Q GENERAL AREA 2 2FT-AF017 AUX FWTO SG 2D FLOWXMTTR Aux 364 364 21-26/L-Q GENERAL AREA 2 2FT-AF018 AUX FW TO SG 2D FLOW XMTTR Aux 364 364 21-26/L-Q GENERAL AREA 2 2AP11E 480V ESF UNIT SUBSTA 231X XFMR Aux 426 426 ESF SWGR RM -DIV 21 2 2AP13E 480V ESF UNIT SUBSTA 232X XFMR Aux 426 426 ESF SWGR RM -DIV 21 2 2AP06E ASSY -4160V ESF SWGR 242 Aux 426 426 ESF SWGR RM -DIV 22 2 2AP10E ASSY -480V ESF SWGR 231X Aux 426 426 ESF SWGR RM -DIV 21 Table B-1 Page 8 of 38 B-1 0 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2AP12E ASSY -480V ESF SWGR 232X Aux 426 426 ESF SWGR RM -DIV 21 2 2AB02T- Recycle Monitor Tank(s)FLOOD _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _2 2WO006A ASSY -MOV 2A & 2C RCFC WO INLET HDR Aux 374 401 AREA 7 CURVED WALL AREA OUTSIDE ISOL VLV 2 2WO006B ASSY -MOV 2B & 2D RCFC CLG COILS WO Aux 401 401 AREA 7 CURVED WALL AREA INLET HDR OUTSIDE CN 2 2W0020A ASSY -MOV 2A & 2C RCFC WO OUTLET Aux 374 401 AREA 7 CURVED WALL AREA HDR OUTSIDE ISOL VLV ______________

2 2WO020B ASSY -MOV 2B & 2D RCFC WO OUTLET Aux 401 401 AREA 7 CURVED WALL AREA HDR OUTSIDE ISOL VLV 2 2W0056A ASSY -MOV 2A & 2C RCFC WO OUTLET Cont 401 +05 (EOP VLV)HDR INSIDE ISOL VLV ASSY -MOV 2B & 2D RCFC WO OUTLET 02 2WO056B HDR INSIDE ISOL VLV Cont 401 +05 (EOPVLV)02 2VX01C ASSY -FAN VENT ESF SWGR 22 HVAC M- Aux 426 426 ESF SWGR RM -DIV 22 116 M-1285-3 AB2 2 2VX01J ESF SWGR RM DIV 21 VENT LOC CONT PNL Aux 426 426 ESF SWGR RM -DIV 21 2 2VX02J ESF SWGR RM DIV 22 VENT LOC CONT PNL Aux 426 426 ESF SWGR RM -DIV 22 2 2VX04C ASSY -FAN VENT ESF 21 HVAC M-1 16 M- Aux 439 426 ESF SWGR RM -DIV 21 1285-4 LCSR+08 2 2VX05C ASSY -FAN VENT BUS 231Z HVAC M-1 19 M- ESWCT 888 ESWCT 1288 SXCT 2 2VX05J OA SXCT SUBSTA BUS 231Z HVAC LOC ESWCT 874 ESWCT CONT PNL 2 2VXO6C ASSY -FAN VENT BUS 232Z HVAC M-119 M- ESWCT 888 ESWCT 1288 SXCT 2 2VXO6J OB SXCT SUBSTA BUS 232Z HVAC LOC ESWCT 874 ESWCT CONT PNL 2 2VX07J ESF SWGR RM DIV 22 HVAC DMPR START Aux 426 426 ESF SWGR RM -DIV 22 PNL 2 2VX08J ESF SWGR RM DIV 21 HVAC DMPR START Aux 426 426 ESF SWGR RM -DIV 21_PNL I I _I Table B-1 Page 9 of 38 B-11 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2VX98J OA SXCT DIV 21 HVAC DMPR START PNL ESWCT 874 ESWCT 2 2VX99J 0B SXCT DIV 22 HVAC DMPR START PNL ESWCT 874 ESWCT 2 2VP01AA RCFC 2A ESW COILS Cont 377 U2 Containment 2 2VP01AB RCFC 2B ESW COILS Cont 377 2 2VP01AC RCFC 2C ESW COILS Cont 377 2 2VP01AD RCFC 2D ESW COILS Cont 377 2 2VP01CA PRIM. CNMT VENT SYSTEM RCFC FAN, Cont 377 U2 Containment MOTOR 2 2VP01CB PRIM. CNMT VENT SYSTEM RCFC FAN, Cont 377 U2 RO MOTOR 2 2VP01CC PRIM. CNMT VENT SYSTEM RCFC FAN, Cont 377 U2 Containment MOTOR 2 2VP01CD PRIM. CNMT VENT SYSTEM RCFC FAN, Cont 377 U2 Containment MOTOR ASSY -U-2 MISC ELEC EQUIP RM VENT 451 U-2 DIV 22 MISC ELEC EQUIP RM 2 2VE01C FAN, BATT RM ROOF Aux 463 (26-28/M-Q)

U-2 MISC ELEC EQUIP RM VENT LOC CONT 451 U-2 DIV 22 MISC ELEC EQUIP RM PNL (26-28/M-Q) 2 2VE01Y DAMPER MOD FO 30WX72H Aux 451 2 2VE02C ASSY -BATT RM 212 EXH FAN, ROOF Aux 463 451 U-2 DIV 22 BATTERY RM 212 (28-_ _28.3/P-Q) 451 U-2 DIV21 BATT-IERY RM 211 (28-2 2VE03C ASSY -BATT RM 211 EXH FAN, ROOF Aux 463 U-21 28.3/L-M)ASSY -U-2 MISC ELEC EQUIP RM DIV 21 451 U-2 DIV 21 MISC ELEC EQUIP RM EXH FAN (26-28/L-M) 2 2VE04J U-2 MISC ELEC EQUIP RM DMPR START Aux 451 451 U-2 NON-ESF SWGR RM (28.3-30/L-PNL Q)ASSY -U-2 MISC ELEC EQUIP RM DIV 22 451 U-2 DIV 22 MISC ELEC EQUIP RM 2 2VEO5C EXH FAN Aux 451 (26-28/M-Q) 2 2VD01CA ASSY -2A DG RM VENT FAN Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2VD01CB ASSY -2B DG RM VENT FAN Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2VD01JA 2A DG RM VENT LOC CONT PNL Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2VD01JB 2B DG RM VENT CONT PNL Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2VD02YA DAMPER MOD FC 53WX52H Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2VD02YB DAMPER MOD FC 53WX52H Aux 401 401 2B DG RM (28.3-30/L-Q)

Table B-1 Page 10 of 38 B-1 2 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2VD04J 2A DG RM HVAC DMPR START PNL Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2VD05J 2B DG RM HVAC DMPR START PNL Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2VD08YA DAMPER FIRE SLV-55WX59H 401 2 2VD08YB DAMPER FIRE SLV-55WX59H 401 2 2VD10YA DAMPER MOD FC 53WX52H Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2VD10YB DAMPER MOD FC 53WX52H Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2VD22YA DAMPER FIRE SLV-55WX59H 401 2 2VD22YB DAMPER FIRE SLV-55WX59H 401 2 2VA01SA SX PP AREA 2A CUB CLR Aux 330 330 13-18/L-S SX PUMP RM 2 2VA01SB SX PP CUB AREA 2B CUB CLR Aux 330 330 18-23/L-S SX PUMP RM 2 2VA02SA 2A RH PP CUB CLR Aux 343 346 21-25/U-V A RH PUMP RM -U-2 2 2VA02SB 2B RH PP CUB CLR Aux 343 346 2B RH PUMP RM (23/X)2 2VA04SA 2A SI PP CUB CLR Aux 364 364 2A SI PUMP RM (20/Q)2 2VA04SB 2B SI PP CUB CLR Aux 364 364 2B SI PUMP RM (23/Y)2 2VA05S U-2 CV PD PP CUB CLR Aux 364 2 2VA06SA 2A CV PP CUB CLR Aux 364 364 2A CV PUMP RM (19-21/U)2 2VA06SB 2B CV PP CUB CLR Aux 379 364 2B CV PUMP RM (21/Y)2 2VA08S 2B DSL DRV AF PP CUB CLR Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2VA08CB ASSY -2B DSL DRVAF PP CUB CLR 2VA08S Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2B FAN_______________

2 2VA01J 2A SX PP CUB CLR LOC CONT PNL Aux 330 330 13-18/L-S SX PUMP RM 2 2VA02J 2B SX PP CUB CLR LOC CONT PNL Aux 330 330 18-23/L-S SX PUMP RM 2 2VA03J 2A RH PP CUB CLR LOC CONT PNL Aux 343 346 21-25/U-VA RH PUMP RM -U-2 2 2VA04J 2B RH PP CUB CLR LOC CONT PNL Aux 343 346 2B RH PUMP RM (23/X)2 2VA10J 2A CV PP CUB CLR LOC CONT PNL Aux 364 364 2A CV PUMP RM (19-21/U)2 2VA11J 2B CV PP CUB CLR LOC CONT PNL Aux 364 364 2B CV PUMP RM (21/Y)2 2SX001A ASSY -MOV 2A SX PP 2SX01 PA SUCT ISOL Aux 346 + (EOP VLV), IN PIT VLV Aux_346_+_(EOPVLV),_INPIT 2 2SX001B ASSY -MOV 2B SX PP 2SX01 PB SUCT ISOL Aux 346 + (EOP VLV), IN PIT VLV Aux_346_+_(EOPVLV),_INPIT 2 2SX01AA 2A SX PP 2SX01PA OIL CLR Aux 330 330 13-18/L-S SX PUMP RM 2 2SX01AB 2B SX PP 2SX01PB OIL CLR Aux 330 330 18-23/L-S SX PUMP RM 2 2SX01FA 2A SX PP DSCH STRN Aux 330 330 13-18/L-S SX PUMP RM 2 2SX01FB 2B SX PP DSCH STRN Aux 330 330 18-23/L-S SX PUMP RM 2 2SX01K 2B AF PP ENG CLSD CYCLE HX Aux 383 383 U-2 AFW PUMP RM (18-21/L-N)

Table B-1 Page 11 of 38 B-1 3 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2SX01PA ASSY -2A SX PP Aux 330 330 13-18/L-S SX PUMP RM 2 2SX01 PA-C 2A SX PP AUX LUBE OIL PP Aux 330 330 13-18/L-S SX PUMP RM 2 2SX01PA-M 2A SX PP MTR Aux 330 330 13-18/L-S SX PUMP RM 2 2SX01PB ASSY -2B SX PP Aux 330 330 18-23/L-S SX PUMP RM 2 2SX01 PB-C 2B SX PPAUX LUBE OIL PP Aux 330 330 18-23/L-S SX PUMP RM 2 2SX01PB-M 2B SX PP MOTOR AB2 Aux 330 330 18-23/L-S SX PUMP RM 2 2SX02K 2B AF PP RHT ANGLE LUBE OIL CLR Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2SX101A SOy 2A MTR DRV AF PP OIL CLR 2AF01AA Aux 383 383 U-2 AFW PUMP RM (18-21/L-N)

SS VV XSX OUTLET VLV 2 2SX169A ASSY -AOV 2A DG JW HX SX OUTLET VLV Aux 401 401 2A DG RM (26-28.3/L-Q)(EOP VLV)ASSY -AOV 2B DG JW HX SX OUTLET VLV 2 2SX169B (EOP VLV) Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2SX173 ASSY -AOV 2B DSL DRV AF PP CLG WTR Aux 383 383 U-2 AFW PUMP RM (18-21/L-N)

SUP VLV (EOP VLV) .ASSY -AOV 2B AF PP HX'S SX RTRN VLV 2 2SX178 (EOP VLV) Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2SXl 12A ASSY -AOV 2A CNMT CHLR 2WO01 CA SX Aux 401 401 AREA 7 CHILLED WTR PUMP RM (21 SUP VLV 26/Q-V)2 2SXl 12B ASSY -AOV 2B CNMT CHLR 2WO01CB SX Aux 401 401 AREA 7 CHILLED WTR PUMP RM (21 SUP VLV 26/Q-V)2 2SX1 14A ASSY -AOV 2A CNMT CHLR 2WO01 CA SX Aux 401 401 AREA 7 CHILLED WTR PUMP RM (21 RTRN VLV 26/Q-V)ASSY.- AOV 2B CNMT CHLR 2WO01CB SX 401 AREA 7 CHILLED WT"R PUMP RM (21 2 2SXII4B RTRN VLV Aux 401 26/Q-V)2 2SX147A AOV 2A CNMT CHLR SX BYP VLV Aux 401 7 2 2SX147B AOV 2B CNMT CHLR SX BYP VLV Aux 401 9 2 2FT-SI050 Loop 2 SI Pump Coolant Injection Cont 2 2FT-SI051 Loop 3 SI Pump Coolant Injection Cont 2 2LS-940A Containment Sump 2A Level Switch Cont 377 El. 377 R126 2 2LS-941A Containment Sump 2A Level Switch Cont 377 El. 377 R128 2 2LT-0930 RWST LVL D/P XMTTR Aux 379 379 U-2 RWST TUNNEL 2 2LT-0931 RWST LEVEL D/P XMTTR Aux 379 379 U-2 RWST TUNNEL 2 2LT-0932 RWST LEVEL D/P XMTTR Aux 379 379 U-2 RWST TUNNEL 2 2LT-0933 RWST LEVEL D/P XMTTR Aux 379 379 U-2 RWST TUNNEL Table B-1 Page 12 of 38 B-14 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2PT-0935 Containment Pressure Cont 454 El. 454 R025 2 2PT-0936 Containment Pressure Cont 454 El. 454 R026 2 2Sl01T U-2 RWST, W OF FHB Out 400 401 FH OUTSIDE 2 2SI05TA SUMP CNMT RECIRC M-136-4 M-2195 BOT Cont 377 367 RX2 2 2SI05TB SUMP CNMT RECIRC M-136-4 M-2195 BOT Cont 377 367 RX2 2 2S18801A ASSY -MOV U-2 CV PPS TO CL 2A ISOL VLV Aux 374 383 U-2 AREA 7 CURVED WALL AREA 2 2SI8801 B ASSY -MOV U-2 CV PPS TO CL 2B ISOL VLV Aux 374 383 U-2 AREA 7 CURVED WALL AREA 2 2SI881 1A ASSY -MOV 2A CNMT RECIRO SUMP Aux 364 364 U-2 AREA 7 CURVED WALL AREA OUTLET ISOL VLV 2 2SI8811 B ASSY -MOV 21 CNMT RECIRC SUMP Aux 364 364 U-2 AREA 7 CURVED WALL AREA OUTLET ISOL VLV 2 2SI8812A ASSY -MOV 2A RH PP RWST SUCT ISOL Aux 343 346 2A CS PUMP RM (23/)2SI8812A__

VLV Aux 343 346_2ACSPUMPRM_(23/V) 2 2SI8812B ASSY -MOV 2B RH PP RWST SUCT ISOL Aux 343 346 2B RH PUMP RM (23/X)2S18812B__

VLV Aux 343_346_2BRHPUMPRM_(23/X) 2 2LT-0459 PZR LEVEL D/P XMTTR Cont 377 2 2LT-0460 PZR LEVEL D/P XMTTR Cont 377 6 2 2LT-0461 PZR LEVEL DP XMTTR Cont 377 2 2RY01S U-2 PZR Cont 410 2 2RY01T U-2 PZR RLFTK Cont 377 2A PORV ACCUM 2RY32MA TO PORV 22RY030A Cont 451 6 2RY455A RLF VLV 2 2RY030B 2B PORV ACCUM 2RY32MB TO PORV Cant 451 6 2RY456 RLF VLV 2 2RY32MA 2A PORV ACCUM, OUTSIDE PZR WALL Cont 453 2 2RY32MB 2B PORV ACCUM, OUTSIDE PZR WALL Cont 453 2 2RY455A ASSY -AOV U-2 PZR PORV (EOP VLV) Cont 461 1 2 2RY455B ASSY -AOV 2D PZR LOOP SPRAY VLV (EOP Cont 390 1 VLV) III_ _ _ _2 2RY455C ASSY -AOV 2C PZR LOOP SPRAY VLV (EOP Cont 390 1 VLV) I I II Table B-1 Page 13 of 38 B-15 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2RY456 ASSY -AOV U-2 PZR PORV (EOP VLV) Cont 456 1 2 2RY8000A ASSY -MOV 2A PZR RLF ISOL VLV Cont 461 +01 (EOP VLV)02 2RY8000B ASSY -MOV 2B PZR RLF ISOL VLV Cont 451 +01 (EOP VLV)02 2RY8010A 2A PZR RLF VLV Cont 451 2 2 2RY8010B 2B PZR RLF VLV Cont 451 2 2 2RY801OC 2C PZR RLFVLV Cont 451 2 2 2RY8028 ASSY -AOV U-2 PRT PW SUP OUTSIDE Aux 374 364 U-2 AREA 7 CURVED WALL AREA CNMT ISOL VLV (EOP VLV)2 21Y-0606 RH HX #2A OUT I/P TRANSDUCER Aux 364 364 17-19/Q-W GENERAL AREA -AREA 6 2 21Y-0607 RH HX #2B OUT I/P TRANSDUCER Aux 364 364 17-19/Q-W GENERAL AREA -AREA 6 2 2RHOlPA ASSY -2A RH PP Aux 343 346 21-25/U-V A RH PUMP RM -U-2 2 2RHO1 PA-A COOLER SEAL RHR PUMP M-137 RXB2 Aux 343 346 21-25/U-V A RH PUMP RM -U-2 2 12RH01PB ASSY -2B RH PP Aux 343 346 2B RH PUMP RM (23/X)2 2RH01PB-A COOLER SEAL RHR PUMP M-137 RXB2 Aux 343 346 2B RH PUMP RM (23/X)2 2RH02AA 2A RH HX Aux 357 364 2A RHR HT EXCH RM (20/S)2 2RH02AB 2B RH HX Aux 357 364 2B RHR HT EXCH RM (20/W)2 2RH61 0 ASSY -MOV 2A RH PP 2RH01 PA RECIRC Aux 357 364 2A RHR HT EXCH RM (20/S)VLV Aux 3 32 HHEHM0 2 2RH611 i ASSY -MOV 2B RH PP 2RH01 PB RECIRC Aux 357 364 2B RHR HT EXCH RM (201W)VLV A36B HE R2 ASSY -MOV 2A RH PP SUCT FROM 2A HL 2 12RH8701A DWST ISOL VLV Cont 377 +02 (EOP VLV)02 2RH8701 B ASSY -MOV 2A RH PP SUCT FROM 2A HL Cant 377 +08 (EOP VLV)UPST ISOL VLV ASSY -MOV 213 RH PP SUCT FROM 2C HL 02 2RH8702A DWST ISOL VLV Cont 377 +02 (EOP VLV)02 2RH8702B ASSY -MOV 2B RH PP SUCT FROM 2C HL Cant 377 +09 (EOP VLV)UPST ISOL VLV 02 2RH8716A ASSY -MOV 2A RH HX 2RH02AA OUTLET Aux 364 364 U-2 AREA 7 CURVED WALL AREA ISOL VLV'2 2RH8716B ASSY -MOV 213 RH HX 2RH02AB OUTLET Aux 364 364 U-2 AREA 7 CURVED WALL IAREA__ _ __ _ _ISOL VLV I_ __I_Table B-1 Page 14 of 38 B-16 Byron Generating Station Unit 2 12QO108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION'RHR PUMP 2A RETURN TEMP RTD 100 OHM 2 2TE-0604 Aux 374 364 U-2 AREA 7 CURVED WALL AREA PLATINUM 2 2TE-0605 RHR PUMP 2B RETURN TEMP RTD 100 OHM Aux 364 364 U-2 AREA 7 CURVED WALL AREA PLATINUM 2 2RF026 AOV U-2 RF PPS DSCH HDR INSIDE CNMT Cont 377 13 ISOL VLV 2 2RF027 AOV U-2 RF PPS DSCH HDR OUTSIDE Aux 374 364 U-2 AREA 7 CURVED WALL AREA CNMT ISOL VLV 2 2RE9170 AOV U-2 RCDT PPS DSCH HDR OUTSIDE Aux 401 401 AREA 7 CURVED WALL AREA CNMT ISOL VLV 2 2PT-0403 Loop A RC Hot Leg Wide Range Pressure Cont 387 El. 387 R122 (2PL75J)Transmitter 2 2PT-0405 Loop C RC Hot Leg Wide Range Pressure Cont 387 El. 387 R131 (2PL66J)2PT-0405_

Transmitter 22PT-0406 Loop A RC Hot Leg Wide Range Pressure 12PT_04 Transmitter Cont 377 El. 377 R028 2PL75J 2 2PT-0407 Loop C RC Hot Leg Wide Range Pressure Cont 377 El. 377 R031 2PL66J Transmitter 2 2RC01BA Steam Generator 2A Cont 390 2 2RC01BB Steam Generator 2B Cont 390 2 2RCO11BC Steam Generator 2C Cont 390 2 2RC01 BD Steam Generator 2D Cont 390 2 2RC01PA Reactor Coolant Pump Cont 390 U2 Containment 2 2RC01PB Reactor Coolant Pump Cont 390 U2 Containment 2 2RC01PC Reactor Coolant Pump Cont 390 U2 Containment 2 2RC01PD Reactor Coolant Pump Cont 390 U2 Containment 2 2RC01 R Reactor Vessel (Internals)

Cont 400 2 2RC8001A Loop A RC Hot Leg Stop Valve Cont 401 El. 401 IMB 2 2RC8001B Loop B RC Hot Leg Stop Valve Cont 401 El. 401 IMB 2 2RC8001C Loop C RC Hot Leg Stop Valve Cont 401 El. 401 IMB 2 2RC8002A Loop A RC Cold Leg Stop Valve Cont 401 El. 401 IMB 2 2RC8002B Loop B RC Cold Leg Stop Valve Cont 401 El. 401 IMB 2 2RC8002C Loop C RC Cold Leg Stop Valve Cont 401 El. 401 IMB 2 2TE-RC022A RC WIDE RANGE LP 2A TEMP Cont 390 4 2 2TE-RC022B RC WIDE RANGE LP 2A TEMP Cont 390 4 Table B-1 Page 15 of 38 B-17 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2TE-RC023A RC WIDE RANGE LP 2B TEMP Cont 390 3 2 2TE-RC023B RC WIDE RANGE LP 2B TEMP Cont 390 3 2 2TE-RC024A RC WIDE RANGE LP 2C TEMP Cont 390 4 2 2TE-RC024B RC WIDE RANGE LP 2C TEMP Cont 390 4 2 2TE-RC025A RC WIDE RANGE LP 2D TEMP Cont 390 3 2 2TE-RC025B RC WIDE RANGE LP 2D TEMP Cont 390 4 2 2PT-0455 Pressurizer Pressure Transmitter Cont 377 El. 377 R042 2PL50J 2 2PT-0456 Pressurizer Pressure Transmitter Cont 383 El. 383 R038 2 2PT-0457 Pressurizer Pressure Transmitter Cont 377 El. 377 R026 2PL52J 2 2PT-0458 Pressurizer Pressure Transmitter Cont 377 El. 377 R028 2PL75J 383 U-2 REMOTE SHUTDOWN RM /2 2PL04J RSD DIV 21 CONT PNL Aux 383 AREA (26-28/L-M) 383 U-2 REMOTE SHUTDOWN RM /2 2PL05J RSD DIV 22 CONT PNL Aux 383 AREA (26-28/L-M) 383 U-2 REMOTE SHUTDOWN RM /2 2PL06J PANEL Aux 383 AE 2-8LM AREA (26-28/L-M) 2 2PL07J 2A DG 2DG01 KA LOC CONT PNL Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2PL08J 2B DG 2DG01KB LOC CONT PNL Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2PL10J U-2 PEN AREA FIRE HAZARDS PANEL Aux 426 426 AREA 7 CURVED WALL AREA 2 2PL50J RX2 CNMT LOC INST PNL Cont 377 2 2PL52J RX2 CNMT LOC INST PNL Cont 377 2 2PL56J RX2 CNMT LOC INST PNL Cont 412 2 2PL57J RX2 CNMT LOC INST PNL Cont 412 2 2PL66J RX2 CNMT LOC INST PNL Cont 377 2 2PL67J RX2 CNMT LOC INST PNL Cont 377 2 2PL69J RX2 CNMT LOC INST PNL Cont 401 2 2PL71J RX2 CNMT LOC INST PNL Cont 412 2 2PL72J RX2 CNMT LOC INST PNL Cont 412 2 2PL75J RX2 CNMT LOC INST PNL Cont 377 2 2PL84JB LOC INST PNL Aux 364 364 21-26/L-Q GENERAL AREA 2 2PL86J LOC INST PNL Aux 364 364 17-19/Q-W GENERAL AREA -AREA 6 2 2PL97J LOC INST PNL Aux 364 364 17-19/Q-W GENERAL AREA -AREA 6 2 2PL77JC 2B SAFETY VLV RM LOC INST PNL Aux 377 377 U-2 MSIV RM B/C Table B-1 Page 16 of 38 B-1 8 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2PL79JB 2A SAFETY VLV RM LOC INST PNL Aux 377 377 U-2 MSIV RM ND 2 2PL84JA LOC INST PNL Aux 364 364 21-26/L-Q GENERAL AREA 2 2PA52J CAB HJTC RX VESSEL LEVEL CH B 0-3373B Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-2 AB2 25/M-Q)2 2NRl 1 E Post Accident Neutron Detector Cont 385 El. 385 270 deg 2 2NRl 3E Post Accident Neutron Detector Cont 385 El. 385 90 deg 2 NE-31 Source Range Neutron Detector Cont 385 El. 385 0 deg 2 NE-32 Source Range Neutron Detector Cont 385 El. 385 180 deg 2 2MS001A ASSY -HOV 2A S/G MS ISOL VLV Aux 377 377 U-2 MSIV RM A/D 2 2MS001 B ASSY -HOV 2B S/G MS ISOL VLV Aux 377 377 U-2 MSIV RM B/C 2 2MS001C ASSY -HOV 2C S/G MS ISOL VLV Aux 377 377 U-2 MSIV RM B/C 2 2MS001 D ASSY -HOV 2D S/G MS ISOL VLV Aux 377 377 U-2 MSIV RM A/D 2 2MS013A 2A S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM A/D 2 2MS013B 2B S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM B/C 2 12MS013C 2C S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM B/C 2 2MS013D 2D S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM A/D 2 2MS014A 2A S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM A/D 2 2MS014B 2B S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM B/C 2 12MS014C 2C S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM B/C 2 2MS014D 2D S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM A/D 2 12MS015A 2A S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM A/D 2 2MS015B 2B S/G MS OUTLET HDR ATMOS RLF VLV Aux 401. 401 U-2 MSIV RM B/C 2 2MS015C 2C S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM B/C 2 2MS015D 2D S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM A/D 2 2MS016A 2A S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM A/D 2 2MS016B 2B S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM B/C 2 2MS016C 2C S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM B/C 2 2MS016D 2D S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM A/D 2 2MS017A 2A S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM A/D 2 2MS017B 2B S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM B/C 2 2MS017C 2C S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM B/C 2 2MS017D 2D S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-2 MSIV RM A/D 2 2MS018A ASSY -HOV 2A S/G MS PORV Aux 401 401 U-2 MSIV RM A/D 2 2MS018B ASSY -HOV 2B S/G MS PORV Aux 401 401 U-2 MSIV RM B/C 2 2MS018C ASSY -HOV 2C S/G MS PORV Aux 401 401 U-2 MSIV RM B/C Table B-1 Page 17 of 38 B-1 9 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2MS018D ASSY -HOV 2D S/G MS PORV Aux 401 401 U-2 MSIV RM A/D TRANSFORMER REG INSTRUMENT BUS 2 21P01E Aux 451 211 451 U-2 AUX ELECTRIC EQUIP RM (23-2 21P01J PANEL DIST INSTRUMENT BUS 211 120VAC Aux 451 451M-23 1 25/M-Q)2 21P02E TRANSFORMER REG INSTRUMENT BUS Aux 451 212 2 21P02J PANEL DIST INSTRUMENT BUS 212 120VAC Aux 451 451 U-2 AUX ELECTRIC EQUIP RM (23-______________________________25/M-Q) 451 U-2 AUX ELECTRIC EQUIP RM (23-2 21P03J PANEL DIST INSTRUMENT BUS 213 120VAC Aux 451 451M-23 1 25/M-Q)451 U-2 AUX ELECTRIC EQUIP RM (23-2 21P04J PANEL DIST INSTRUMENT BUS 214 120VAC Aux 451 451M-2E 25/M-Q)451 U-2 DIV 21 MISC ELEC EQUIP RM 2 21P07E INVERTER INST BUS 213 2-3371 AB2 Aux 451 456-2D2L-EI (26-28/L-M) 2 2LT-0501 SG LOOP 2A W-RNG LEVEL D/P XMTTR Cont 377 2 2LT-0502 SG LOOP 2B W-RNG LEVEL D/P XMTTR Cont 377 2 2LT-0503 SG LOOP 2C W-RNG LEVEL D/P XMTTR Cont 377 2 2LT-0504 SG LOOP 2D W-RNG LEVEL D/P XMTTR Cont 377 2 2PT-0514 SG LOOP 2A STM PRESS XMTTR Aux 377 377 U-2 MSIV RM A/D 2 2PT-0516 SG LOOP 2A STM PRESS XMTTR Aux 377 377 U-2 MSIV RM ND 2 2PT-0524 SG LOOP 2B STM PRESS XMTTR Aux 377 377 U-2 MSIV RM B/C 2 2PT-0525 SG LOOP 2B STM PRESS XMTTR Aux 377 377 U-2 MSIV RM B/C 2 2PT-0526 SG LOOP 2B STM PRESS XMTTR Aux 377 377 U-2 MSIV RM B/C 2 2PT-0534 SG LOOP 2C STM PRESS XMTTR Aux 377 377 U-2 MSIV RM B/C 2 2PT-0535 SG LOOP 2C STM PRESS XMTTR Aux 377 377 U-2 MSIV RM B/C 2 2PT-0536 SG LOOP 2C STM PRESS XMTTR Aux 377 377 U-2 MSIV RM B/C 2 2PT-0544 SG LOOP 2D STM PRESS XMTTR Aux 377 377 U-2 MSIV RM A/D 2 2PT-0545 SG LOOP 2D STM PRESS XMTTR Aux 377 377 U-2 MSIV RM A/D 2 2PT-0546 SG LOOP 2D STM PRESS XMTTR Aux 377 377 U-2 MSIV RM A/D 2 2PT-0515 SG LOOP 2A STM PRESS XMTTR Aux 377 377 U-2 MSIV RM A/D 2 2FW009A HOV 2A S/G FW ISOL VLV Aux 377 377 U-2 MSIV RM A/D 2 2FW009B HOV 2B S/G FW ISOL VLV Aux 377 377 U-2 MSIV RM B/C 2 2FW009C HOV 2C S/G FW ISOL VLV Aux 377 377 U-2 MSIV RM B/C 2 2FW009D HOV 2D S/G FW ISOL VLV Aux 377 377 U-2 MSIV RM A/D Table B-1 Page 18 of 38 B-20 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION m AOV 2A S/G FW TEMPERING LINE DWST 2 2FW035A Aux 377 377 U-2 MSIV RM A/D ISOL VLV (EOP VLV)AOV 213 S/G FW TEMPERING LINE DWST 2 2FW035B AOV 2B S/G Aux 377 377 U-2 MSIV RM B/C_ ISOL VLV (EOP VLV)2 2FW035C AOV 2C S/G FW TEMPERING LINE DWST Aux 377 377 U-2 MSIV RM B/C ISOL VLV (EOP VLV)2 2FW035D AOV 2D S/G FW TEMPERING LINE DWST Aux 377 377 U-2 MSIV RM A/D ISOL VLV (EOP VLV)SG LOOP 2A LEVEL DIP XMTTR W/FILLED 2 2LT-0517 LGCont 401 LEG 2 2LT-0518 SG LOOP 2A LEVEL DIP XMTTR W/FILLED Cont 412 LEG 2 12LT-051 SG LOOP 2A LEVEL DIP XMTTR W/FILLED Cont 412 LEG 2 2LT-0527 SG LOOP 2B LVL D/P XMTTR W/FILLED LEG Cont 377 m2 2LT-0528 SG LOOP 213 LEVEL DIP XMTTR W/FILLED Cont 412 LEG 2 2L-T-0529 SG LOOP 2C LEVEL D/P XMTTR W/FILLED Cont 377_________LEG_____

2 2LT-0537 SG LOOP 2C LEVEL D/P XMTTR W/FILLED Cont 412 LEG SG LOOP 2C LEVEL D/P XMTTR W/FILLED 2 2LT-0537 Cont 412 LEG 2 2LT-0 .539 SG LOOP 2C LEVEL D/P XMTTR W/FILLED Cont 41 LEG 2 2LT-0547 SG LOOP 2D LEVEL DIP XMTTR W/FILLED Cn 0 2 2LT-0548 SG LOOP 2D LVL D/P XMTTR W/FILLED LEG Cont 412 2 2LT-0ý549 SG LOOP 2D LEVEL D/P XMTTR W/FILLED Cont 412 LEG 2 2LT-0556 SG LOOP 2A LVL D/P XMTTR W/FILLED LEG Cont 412 Table B-1 Page 19 of 38 B-21 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION SG LOOP 2B LEVEL D/P XMTTR W/FILLED 2 2LT-0557 Cont 412 LEG 2 2LT-0558 SG LOOP 2C LEVEL D/P XMTTR W/FILLED Cont 412 LEG 2 2LT-0559 SG LOOP 2D LEVEL D/P XMTTR W/FILLED Cont 412 LEG 2 2FP010 AOV RX2 CNMT FP SUP ISOL VLV (EOP Aux 374 364 U-2 AREA 7 CURVED WALL AREA VLV)2 2DO01PA ASSY -2A DG 2A FO XFER PP Aux 373 383 U-2 DIESEL OIL TANK RM A 2 2DO01PB ASSY -2B DG 2B FO XFER PP Aux 373 383 U-2 DIESEL OIL TANK RM B 2 2DO01PC ASSY -2A DG 2C FO XFER PP Aux 373 383 U-2 DIESEL OIL TANK RM A 2 2DO01PD ASSY -2B DG 2D FO XFER PP Aux 373 383 U-2 DIESEL OIL TANK RM B 2 2DO01TA 2A DO STO TK, 50,000 GAL Aux 373 383 U-2 DIESEL OIL TANK RM A 2 2DOO1TB 2B DO STO TK, 50,000 GAL Aux 373 383 U-2 DIESEL OIL TANK RM B 2 2DO02TA 2A DG FO DAY TK, 500 GAL Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2DO02TB 2B DG FO DAY TK, 500 GAL Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2DO10T U-2 DODAY TK, 500 GAL Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2DO12MA EXHAUST SILENCER Aux 4 477 ROOF OF 2A & 2B DG RMS (26-30/L-I Q)2 2DO12MB EXHAUST SILENCER Aux 4 477 ROOF OF 2A & 2B DG RMS (26-30/L-I Q)2 2DG01EA GENERATOR EMERGENCY DIESEL Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2DG01EB GENERATOR EMERGENCY DIESEL Aux 401 401 2B DG RM (28.3-30/L-Q)

ASSY -ENGINE DIESEL GENERATOR M-130-2 2DG01KA 1A AB2 Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2DG01KB ASSY -ENGINE DIESEL GENERATOR M-130- Aux 401 401 2B DG RM (28.3-30/L-Q) 2_ 2 1 1BAB2 2 2DG01SA AIR COMPRESSOR PACKAGE 2A Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2DG18MA INTAKE SILENCER Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2DG18MB INTAKE SILENCER Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2DG19MA FILTER AIR INTAKE 2DG01KA M-152-17 Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2DG19MB FILTER AIR INTAKE 2DG01KB M-152-17 Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2DG04EB RELAY BOX 2DG01 KB SYNCRO-CHECK Aux 426 426 ESF SWGR RM -DIV 22 2DG214 AB2 I_ II Table B-1 Page 20 of 38 B-22 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2DG04EA RELAY BOX 2DG01KA SYNCRO-CHECK Aux 426 426 ESF SWGR RM -DIV 21 2DG212 AB2 451 U-2 DIV 21 BATTERY RM 211 (28-2 2DC01E 125V DC BAT-211 Aux 451 8/LM 1 28.3/L-M)451 U-2 DIV 22 BATTERY RM 212 (28-2 2DC02E 125V DC BATT-1212 Aux 451 283PQ 28.3/P-Q)451 U-2 DIV 21 MISC ELEC EQUIP RM 2 2DC10J 125V DC FUSE PNL ESF 21 Aux 451 456-2D2L-MI (26-28/L-M) 451 U-2 DIV 22 MISC ELEC EQUIP RM 2 2DC11J 125V DC FUSE PNL ESF 22 Aux 451 456-2D2M-EI T 1 3(2 -2a/M-Q)2 2CV01FA 2A CV SEAL WTR INJ FLTR Aux 391 383 GENERAL AREA (12-15/N-Q) 2 2CV01FB 2B CV SEAL WTR INJ FLTR Aux 391 383 GENERAL AREA (12-15/N-Q) 2 2CV01PA ASSY -2A CV CENT CHXG PP Aux 364 364 2A CV PUMP RM (19-21/U)2 2CV01 PA-A 2A CV CENT CHG PP AUX LUBE OIL PP Aux 364 364 2A CV PUMP RM (19-21/U)2 2CV01PB ASSY -2B CV CENT CHG PP Aux 364 364 2B CV PUMP RM (21/Y)2 2CV01 PB-A 2B CV CENT CHG PP AUX LUBE OIL PP Aux 364 364 2B CV PUMP RM (21/Y)383 U-2 SEAL WTR HT EXCH RM (19-2 2CV02A U-2 CV SEAL WTR HX Aux 383 21/U)21/U)2 2CV02F U-2 CV SEAL WTR FLTR Aux 391 383 GENERAL AREA (12-15/N-Q) 2 2CV02SA 2A CV CENT CHG PP GEAR CLR Aux 364 364 2A CV PUMP RM (19-21/U)2 2CV02SB 2B CV CENT CHG PP GEAR CLR Aux 364 364 2B CV PUMP RM (21N)2 2CV03SA 2A CV CENT CHG PP LUBE OIL CLR Aux 364 364 2A CV PUMP RM (19-21/U)2 2CV03SB 2B CV CENT CHG PP LUBE OIL CLR Aux 364 364 2B CV PUMP RM (21K)ASSY -MOV U-2 VCT OUTLET UPST ISOL 426 AREA 6 GENERAL AREA U-1/2 VCT 2 20CVI112B VVAux 426 TN M VLV TANK RMS ASSY -MOV U-2 VCT OUTLET DWST ISOL 426 AREA 6 GENERAL AREA U-1/2 VCT 2 2CV112C VVAux 426 TN M VLV TANK RMS 2 2CV112D ASSY -MOV RWST TO U-2 CHG PPS SUCT Aux 364 364 U-2 AREA 7 CURVED WALL AREA ISOL VLV 2 2CV459 Regeneration Heat Exchanger Isolation AOV Cont 412 El. 414 R028 2 2CV460 Regeneration Heat Exchanger Isolation AOV Cont 387 El. 387 R128 2 2CV81 00 ASSY -MOV U-2 RC PPS SEAL LO HDR Aux 374 383 U-2 AREA 7 CURVED WALL AREA OUTSIDE CNMT ISOL VLV ASSY -MOV U-2 CV CHG PPS DSCH HDR 2 2CV8105 DWST ISOL VLV Aux 374 364 U-2 AREA 7 CURVED WALL AREA Table B-1 Page 21 of 38 B-23 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2CV8106 ASSY -MOV U-2 CV CHG PPS DSCH HDR Aux 374 364 U-2 AREA 7 CURVED WALL AREA UPST ISOL VLV 2 2CV81 10 ASSY -MOV 2B CV PP MINIFLOW ISOL VLV Aux 364 364 U-2 AREA 7 CURVED WALL AREA 2 2CV81 11 ASSY -MOV 2A CV PP MINIFLOW ISOL VLV Aux 364 364 U-2 AREA 7 CURVED WALL AREA 2 2CV8112 Isolation Valve Cont 377 2 2CV8114 SOV 2A CV PP ESF MINIFLOW ISOL VLV Aux 364 364 U-2 AREA 7 CURVED WALL AREA (EOP VLV)2 2CV8116 SOV 2B CV PP ESF MINIFLOW ISOL VLV Aux 364 364 U-2 AREA 7 CURVED WALL AREA (EOP VLV)2 2CV8804A ASSY -MOV 2A RH HX TO U-2 CV PPS SUCT Aux 364 364 U-2 AREA 7 CURVED WALL AREA.HDR ISOL VLV 2 2FT-0121 CHARGING LINE D/P CELL FLOW XMTTR Aux 364 364 17-19/Q-W GENERAL AREA -AREA 6 383 EEA RA-AE 1-9Q 2 2FT-0132 LETDOWN FLOW TRANSMITTER Aux 383 383 GENERAL AREA-AREA6 (17-19/Q-383 GENERAL AREA -AREA 6 (17-19/Q-2 2FT-0139 LOOP FILL HEADER FLOW TRANSMITTER Aux 383 3A 2 2CV02P-C COOLER OIL PD PUMP FLUID DRIVE M-139- Aux 364 364 PD PUMP RM -U-2 (20/U)2 AB32 383 U-2 LETDOWN HT EXCH RM (19-2 2CV04AA 2A CV LTDWN HX Aux 383 1UV 383 U-2 LETDOWN HT EXCH RM (19-2 2CV04AB 2B CV LTDWN HX Aux 383 21/U-V)2A CS PP 2CS01PA SPRAY NOZL HDR CHK 2 2CS008A _ ___Cont 377 35 2 2CS008B 2B CS PP 2CS01PB SPRAY NOZL HDR CHK Cont 377 28 VLV 2 2CO01J C02 FP AREA 2S2 LOC CONT CAB Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2C002J CAB CONT LOC FP AREA 2S4 2-3434 Aux 401 401 2A DG RM (26-28.3/L-Q) 2_ 2CO02J 2CO070 TB2 Aux_401_401_2ADGRM_(26-28.3/L-Q) 2 2CO03J C02 FP AREA 2S1 LOC CONT CAB Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2CO04J C02 FP AREA 2S3 LOC CONT CAB Aux 401 401 2B DG RM (28.3-30/L-Q) 2 2CO17JA 2A DG RM FIRE DMPR CONT PNL Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2CO17JB 2B DG RM FIRE DMPR CONT PNL Aux 401 401 2B DG RM (28.3-30/L-Q)

Table B-1 Page 22 of 38 B-24 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2CO19JA U-2 LCSR & CBL TNL FIRE DMPR CONT PNL Aux 401 401 2A DG RM (26-28.3/L-Q) 2 2CO19JB U-2 LCSR FIRE DMPR CONT PNL Aux 465 463 HVAC GENERAL ARA (15-21/L-Q) 426 GENERAL AREA -AREA 2 & 3 (10-2 2CO20J U-2 UCSR FIRE DMPR CONT PNL Aux 426 26 EA R 23 21/L-Q)2 2CC01A U-2 CC HX Aux 364 364 15-21/L-Q GENERAL AREA 2 2CC01PA ASSY -2A CC PP Aux 364 364 15-21/L-Q GENERAL AREA 2 2CC01P13 ASSY -213 CC PP Aux 364 364 15-21/L-Q GENERAL AREA 426 GENERAL AREA -AREA 2 & 3 (10-2 2CC01T U-2 CC SURGE TK Aux 426 21/L-Q)2 2CC053 AOV U-2 PEN CLG SUP FCV Cont 377 +19 2HS-CCO70 2 2CC9437B ASSY -AOV U-2 EXC LTDWN HX CO RTRN Aux 374 383 U-2 AREA 7 CURVED WALL AREA VLV (EOP VLV)2 2CC9518 Isolation Valve Cont 2 2CC9534 Isolation Valve Cont 2 2FT-0688 RESID HX 2B CCW OUTLET FLW D/P Aux .364 364 17-19/Q-W GENERAL AREA -AREA 6 TRANSMITTER RESID HX 2A CCW OUTLET FLW D/P 2 2FT-0689 RESID Aux 364 364 15-21/L-Q GENERAL AREA TRANSMITI-ER_______________

2 2CC9412A ASSY -MOV 2A RH HX 2RH02AA CC Aux 364 364 17-19/Q-W GENERAL AREA -AREA 6 OUTLET ISOL VLV 2 2CC9412B ASSY -MOV 2B RH HX 2RH02AB CO Aux 364 364 17-19/Q-W GENERAL AREA -AREA 6 OUTLET ISOL VLV 2 2AP05E ASSY -4160V ESF SWGR 241 Aux 426 426 ESF SWGR RM -DIV 21 2 2AP21 E ASSY -480V AUX BLDG ESF MCC 231X1 Aux 364 364 U-2 AREA 7 CURVED WALL AREA 2 2AP22E ASSY -480V AUX BLDG ESF MCC 231X3 Aux 401 383 15-21/N-Q GENERAL AREA 383 U-1 REMOTE SHUTDOWN RM/2 2AP23E ASSY -480VAUX BLDG ESF MCC 232X1 Aux 383 383 U-iETS DWR__________AREA (23-24/N-P) 2 2AP26E ASSY -480V AUX BLDG ESF MCC 231X4 Aux 414 414 CURVED WALL AREA -AREA 7 2 2AP28E ASSY -480V AUX BLDG ESF MCC 232X4 Aux 426 426 AREA 7 CURVED WALL AREA 426 GENERAL AREA -AREA 2 & 3 (10-2 2AP30E ASSY -480V AUX BLDG ESF MCC 231X5 Aux 426 26 EA R 23 I I I I21/L-Q)2 2AP38E ASSY -480V AUX BLDG MCC 233X1 Aux 346 346 15-23/N-Q GENERAL AREA 2 2AP39E ASSY -480V AUX BLDG MCC 234V1 Aux 346 346 15-23/N-Q GENERAL AREA Table B-1 Page 23 of 38 B-25 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2AF006A ASSY -MOV 2A AF PP SX SUCT DWST ISOL Aux 383 383 U-2 AFW PUMP RM (18-21/L-N)

VLV 2 2AF006B ASSY -MOV 2B AF PP SX SUCT DWST ISOL Aux 383 383 U-2 AFW PUMP RM (18-2 lL-N)I VLV Aux 3 3U F U R 8/ASSY -MOV 2A AF PP SX SUCT UPST ISOL 2AF017A VLV Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF017B ASSY -MOV 2B AF PP SX SUCT UPST ISOL Aux 383 383 U-2 AFW PUMP RM (18-21/L-N)

VLV Aux 3 3UA P P (- N 2 2AF01AA 2A MTR DRV AF PP OIL CLR Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01AB 2B DSL DRV AF PP OIL CLR Aux. 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AFO1EA-1 2B DSL DRV AF PP 2A BATT CHGR Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01EA-A 2B DSL DRV AF PP #1 BATT Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01EA-B 2B DSL DRV AF PP #1A BATT Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01EB-1 2B DSL DRV AF PP 2B BATT CHGR Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01EB-A 2B DSL DRV AF PP #2 BATT Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01EB-B 2B DSL DRV AF PP #2A BATT Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01J 2B DSL DRV AF PP STARTUP CONT PNL Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01PA ASSY -2A MTR DRV AF PP Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AFO1 PA-A 2A MTR DRV AF PP AUX LUBE OIL PP Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01PA-L 2A MTR DRVAF PP MAIN LUBE OIL PP Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01PA-M 2A MTR DRVAF PP MOTOR Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01PB ASSY -2B DSL DRV AF PP Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01PB-A 2B DSL DRVAF PP AUX LUBE OIL PP Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01PB-B CONTROL BOX DIESEL ENG DRIVE 0-3322 Aux 383 383 U-2 AFW PUMP RM (18-21/L-N)

AB2*2 2AF01PB-K 2B DSL DRVAF PP DIESEL ENGINE Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF01PB-L 2B DSL DRV AF PP MAIN LUBE OIL PP Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 2AF02A 2B DSL DRVAF PP GEAR OIL CLR Aux 383 383 U-2 AFW PUMP RM (18-21/L-N) 2 1VA08CA Fan 383 2 2VA08CA Fan 383 2 2WO007A Isolation Valve Cont 2 2WO007B Isolation Valve Cont 2 2WO01CA 2A PRI CNMT CHLR Aux 401 2 2WO01CB 2B PRI CNMT CHLR Aux 401 2 2WO01 PA ASSY -2A PRI CNMT WO PP Aux 401 Table B-1 Page 24 of 38 B-26 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2WO01PB ASSY -2B PRI CNMT WO PP Aux 401 2 2WM191 Isolation Valve Cont SX STRAINER DRAIN MANUAL ISOLATION 2 2WE010A Aux 330 VALVE 2 2WE010B SX STRAINER DRAIN MANUAL ISOLATION Aux 330 VALVE 2 2VX01Y DAMPER MOD FO 40WX56H Aux 426 2 2VX04Y DAMPER MOD FO 72WX46H Aux 426 2 2VX16Y DAMPER FIRE SLV-40WX45H Aux 426 2 2VX17Y DAMPER FIRE SLV-58WX47H Aux 426 2 2VX20Y DAMPER FIRE SLV-58WX57H Aux 426 2 2VX22Y DAMPER FIRE SLV-48WX39H Aux 426 2 2VX30Y DAMPER MOD FC 24WX36H ESWCT 888 2 2VX31Y DAMPER ISO FC 48WX24H ESWCT 874 2 2VX33Y DAMPER MOD FO 24WX36H ESWCT 888 2 2VX34Y DAMPER ISO FC 48WX24H ESWCT 874 2 2VX50Y DAMPER BAL 38WX38H Aux 426 2 2VQ001A Containment Purge Supply Isolation Valve Cont 2 2VQ002A Containment Purge Exhaust Isolation Valve Cont AOV U-2 MINIFLOW PURGE SUP INSIDE 2 2VQ004A Cont 455 6 ISOL VLV 2 2VQ005A AOV U-2 MINIFLOW PURGE EXH INSIDE Cont 471 3 ISOL VLV 2 2VQ016 Isolation Valve Cont 2 2VQ017 Isolation Valve Cont AOV U-2 POST LOCA PURGE FLTR INLET 2 2VQ003 Aux 467 6 VLV (EOP VLV)2 2VQ004B AOV U-2 MINIFLOW PURGE SUP OUTSIDE Aux 451 11 ISOL VLV 2 2VQ005B AOV U-2 MINIFLOW PURGE EXH OUTSIDE Aux 467 UPST ISOL VLV (EOP VLV 2 2VQ005C AOV U-2 MINIFLOW PURGE EXH OUTSIDE Aux 467 DWST ISOL VLV (EOP VLV 2 2VP02AA Coil Cooling RCFC Unit Cont 2 2VP02AB Coil Cooling RCFC Unit Cont Table B-1 Page 25 of 38 B-27 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2VP02AC Coil Cooling RCFC Unit Cont 2 2VP02AD Coil Cooling RCFC Unit Cont 2 2VE04Y DAMPER FIRE SLV-42WX41H Aux 451 2 2VE05Y DAMPER FIRE SLV-40WX59H Aux 451 2 2VE06Y DAMPER FIRE SLV-34WX25H Aux 451 2 2VE07Y DAMPER FIRE SLV-42WX27H Aux 451 2 2VE10Y DAMPER BAL 18WX32H Aux 451 2 2VE12Y DAMPER FIRE SLV-34WX25H Aux 451 2 2VE17Y DAMPER FIRE SLV-42WX41H Aux 451 2 2VE20Y DAMPER FIRE SLV-14WX19H Aux 451 2 2VE21Y DAMPER FIRE SLV-14WX19H Aux 451 2 2VE22Y DAMPER FIRE SLV-14WX19H Aux 451 2 2VE23Y DAMPER FIRE SLV-14WX19H Aux 451 2 2VD01YA DAMPER MOD FO 72WX484 Aux 401 INSIDE OF 2B DIESEL GENERATOR 2 2VD01YB DAMPER MOD FO 72WX48H Aux 401 2 2VD05Y DAMPER BAL 10WX22H Aux 401 2 2VD09YA DAMPER MOD FO 72WX48H Aux 401 2 2VD09YB DAMPER MOD FO 72WX48H Aux 401 2 2VD13Y DAMPER BAL 10WX22H Aux 401 2 2VD16YA DAMPER FIRE SLV-60WX43H Aux 401 2 2VD16YB DAMPER FIRE SLV-60WX43H Aux 401 2 2VD17YA DAMPER FIRE SLV-55WX59H Aux 401 2 2VD17YB DAMPER FIRE SLV-55WX59H Aux 401 2 2VD23YA DAMPER FIRE SLV-60WX43H Aux 401 2 2VD23YB DAMPER FIRE SLV-60WX43H Aux 401 2 2VD24YA DAMPER FIRE SLV-55WX59H Aux 401 2 2VD24YB DAMPER FIRE SLV-55WX59H Aux 401 2 2SX004 ASSY -MOV U-2 CC HX 2CC01A SX SUP Aux 330 6 ISOL VLV 2 2SX005 ASSY -MOV U-0 CC HX OCC01A SX SUP Aux 330 +04 (EOP VLV)ISOL VLV 2 2SX007 ASSY -MOV U-2 CC HX 2CC01A SX OUTLET Aux 346 +08 (EOP VLV)ISOL VLV 2 2SX010 ASSY -MOV SXCT BASIN 2A RTRN HDR Aux 346 +06 (EOP VLV)___ ___ ___ISOL VLV__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _Table B-1 Page 26 of 38 B-28 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 ASSY -MOV SXCT BASIN 2A/2BRTRN HDR 2 2SX01 1 XTIE ISOL VLV Aux 346 +08 (EOP VLV)2 2SX016A ASSY -MOV 2A & 2C RCFC SX SUP ISOL Aux 374 +29 (EOP VLV), P-15 2 __2SX016A VLV ASSY -MOV 2B & 2D RCFC SX SUP ISOL -7 2 12SX016B VLV Aux 401 +02 (EOP VLV), P 2 2SX027A ASSY -MOV 2A & 2C RCFC SX RTRN HDR Aux 374 +29 (EOPVLV), P-14 2 _2SX027A ISOL VLV Aux 374 +29_(EOPVLV),_P-14 2 2SX027B ASSY -MOV 2B & 2D RCFC .SX RTRN HDR Aux 401 +02 (EOP VLV), P-9 2_ _ _ _ _ _ _ _ IS O L V L V A u x 4 10__ _ _P 2 2SX104A U-2 DG'S JW HXS SX SUP HDR XTIE ISOL Aux 401 6 VLV ASSY -MOV SX BASIN 2B RTRN HDR ISOL 2 2SX136 _ _ __Aux 346 8 ASSY -MOV 2A SX STRN BKWH OUTLET TO 2 2SX150A Aux 330 1 TR SYS ISOL VLV 2 2SX150B ASSY -MOV 2B SX STRN BKWH OUTLET TO Aux 330 1 TR SYS ISOL VLV 2 2SX168 ASSY -AOV 2B AF PP CUB CLR 2VA08S SX Aux 383 9 OUTLET VLV 2 2SX192A 2A SX PP DSCH HYPO SUP CHK VLV Aux 330 12 2 2SX192B 2B SX PP DSCH HYPO SUP CHK VLV Aux 330 9 2 2SX194 AF PPS RECIRC RTRN TO SX CHK VLV Aux 383 12 2 2SX2077A 2A SI PP BRNG OIL CLR 2SI01SA SX INLET Aux 364 1 ISOL VLV 2B SI PP BRNG OIL CLR 2SI01SB SX INLET 2 2SX2077B Aux 364 1___ ___ ___ ISOL VLV__ _ _ _ _ _ _ _ _ _ _ _ _ _ _2 2SX243 2A AF PP SX SUCT FLUSH CONN 2ND ISOL Aux 383 7 VLV 2 2SX033 ASSY -MOV 2A SX PP DSCH HDR XTIE ISOL Aux 330 +05 (EOP VLV)2 __2SX033 VLV Aux_330_+05_(EOPVLV) 2 2SX034 ASSY -MOV 2B SX PP DSCH HDR XTIE ISOL Aux 330 +05 (EOP VLV)VLV U-2 DG'S JW HXS SX RTRN HDR XTIE ISOL 2 2SX104B V___Aux 401 4 Table B-1 Page 27 of 38 B-29 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION U-2 DG'S JW HXS SX SUP HDR XTIE ISOL 2 2SX105A VVAux 401 6 VLV 2 2SX105B U-2 DG'S JW HXS SX RTRN HDR XTIE ISOL Aux 401 4 VLV 2 2SI8804B MOV 2B RH HX TO 2B SI PP SUCT HDR ISOL Aux 364 +12 (EOP VLV)2___ 2S80B VLV Aux_364_+12_(EOP__LV) 2 2SI8807A ASSY -MOV SI TO U-2 CV PPS SUCT HDR Aux 364 +02 (EOP VLV)2_ 2SI8807A 2A XTIE ISOL VLV Aux_364__02__________

2 2SI8807B ASSY -MOV SI TO U-2 CV PPS SUCT HDR Aux 364 +02 (EOP VLV)2B XTIE ISOL VLV 2 2SI8808A SI Accumulator Tank Outlet Isolation Valve Cont El. 413 R039 2 2SI8808B SI Accumulator Tank Outlet Isolation Valve Cont El. 413 R036 2 2SI8808C SI Accumulator Tank Outlet Isolation Valve Cont El. 413 R028 2 2SI8808D SI Accumulator Tank Outlet Isolation Valve Cont El. 413 R024 2 2SI8809A ASSY -MOV 2A RH HX SI OUTLET DWST Aux 374 +13 (EOP VLV)2 __2SI8809A ISOL VLV Aux_374_+13_(EOPVLV) 2 2518809B3 ASSY -MOV 2B RH HX SI OUTLET DWST Aux 374 +13 (EOP VLV)2 __2SI8809B ISOL VLV Aux_374_+13_(EOPVLV) 2 2SI8815 U-2 COLD LEG HDR SI SUP CHK VLV Cont 377 20 2 2SI8818A LOOP 1 COLD LEG ACCUM INJ CHK VLV Cont 412 10 2 2SI8818B LOOP 2 COLD LEG ACCUM INJ CHK VLV Cont 412 6 2 2SI8818C LOOP 3 COLD LEG ACCUM INJ CHK VLV Cont 377 10 2 2SI8818D LOOP 4 COLD LEG ACCUM INJ CHK VLV Cont 377 12 2 2SI8819A LOOP 1 COLD LEG SI CHK VLV Cont 412 3 2 2SI8819B LOOP 2 COLD LEG SI CHK VLV Cont 412 2 2 2SI8819C LOOP 3 COLD LEG SI CHK VLV Cont 377 5 2 2SI8819D LOOP 4 COLD LEG SI CHK VLV Cont 377 10 2 2SI8823 Isolation Valve Cont 2 2SI8825 Isolation Valve Cont ASSY -MOV U-2 RH HXS TO 2A/2C LOOP HL 2 2SI8840 ISOL VLV Aux 374 +05 (EOP VLV)2 2SI8841A LOOP 3 HOT LEG RH SUCT 1ST CHK VLV Cont 377 8 2 2SI8841B LOOP 1 HOT LEG RH SUCT 1ST CHK VLV Cont 377 2 2 2SI8843 AOV U-2 CV PPS TO CL TEST LINE ISOL Cont 377 +18 P-26 2_ 2SI8843__

1VLV ____ 377__18_P-26 Table B-1 Page 28 of 38 B-30 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2SI8856A 2A RH HX TO 2A/2D LOOP CL RLF VLV Aux 374 +13 P-50 UPST 2SI8809A 2 2SI8856B 2B RH HX TO 2B1/2C LOOP CL RLF VLV Aux 374 +14 P-51 UPST 2SI8809B 2 2SI8871 Isolation Valve Cont 2 2SI8879A ASSY -AOV 2A ACCUM OUTLET LEAK DET Cont 412 +6 DWST 2SI8956A CHK VLV VLV ASSY -AOV 2B ACCUM OUTLET LEAK DET 2 12SI8879B VCont 412 +3 DWST 2SI8956B CHK VLV 2 2SI8879C ASSY -AOV 2C ACCUM OUTLET LEAK DET Cant 412 +3 DWST 2SI8956C CHK VLV I _ VLV 2 2SI8879D ASSY -AOV 2D ACCUM OUTLET LEAK DET Cont 412 +1 DWST 2SI8956D CHK VLV VLV 2 2SI8881 Isolation Valve Cont ASSY -AOV U-2 CV PPS TO CL TEST LINE 2 2SI8882 Cant 377 +18 P-26 ISOL VLV 2 2SI8890A ASSY -AOV 2A RH HX TO 2A/2D LOOP CL Cant 377 15 1 TEST LINE ISOL VLV 2 12SI8890B ASSY -AOV 2B RH HX TO 2B/2C LOOP CL Cant 377 3 TEST LINE ISOL VLV 2 2S18905A Isolation Valve Cont 2 2SI8905B Isolation Valve Cont 2 2SI8905C Isolation Valve Cont 2 2SI8905D Isolation Valve Cont 2 2SI8924 2 2SI8948A 2A ACCUM OUTLET TO RC LOOP 1 2ND Cant 390 4 CHK VLV 2B ACCUM OUTLET TO RC LOOP 2 2ND 2 2SI8948B Cant 390 4 CHK VLV 2 .2SI8948C 2C ACCUM OUTLET TO RC LOOP 3 2ND Cant 390 4 CHK VLV 2 2SI8948D 2D ACCUM OUTLET TO RC LOOP 4 2ND Cant 390 4 CHK VLV 2 12SI8949A LOOP 1 HOT LEG RH SUCT CHK VLV Cnt 377 8 2 2SI8949B LOOP 2 HOT LEG RH SUCT CHK VLV Cont 390 5 2 2SI8949C LOOP 3 HOT LEG RH SUCT CHK VLV Cont 377 8 2. 2SI8949D LOOP 4 HOT LEG RH SUCT CHK VLV Cont 390 5 Table B-1 Page 29 of 38 B-31 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2SI8956A 2A ACCUM OUTLET TO RC LOOP 1 1ST CHK Cont 377 7 VLV 2 2SI8956B 23B ACCUM OUTLET TO RC LOOP 2 1ST CHK Cont 377 9 VLV 2 2SI8956C 2C ACCUM OUTLET TO RC LOOP 3 1ST CHK Cont 377 9 VLV -2 2SI8956D 2D ACCUM OUTLET TO RC LOOP 4 1ST CHK Cont 390 5 VLV 2 2SI8968 Isolation Valve Cont 2 2SA033 Isolation Valve Cont 2 2LT-0462 Pressurizer Level Transmitter Cont El. 407/450 R25 (PRZ Encl.)2A PORV ACCUM 2RY32MA AIR INLET 2ND 2 2RY086A CKV Cont 451 4 CHK VLV 2B PORV ACCUM 2RY32MB AIR INLET 2ND 2 2RY086B Cant 451 4 CHK VLV 2 2RY8026 Isolation Valve Cont 2 2RY8 1 030 ASSY -AOV U-2 PRT PW SUP INSIDE CNMT Cant 390 +1 ABOVE PRT ISOL VLV 2 2RY8031 ASSY -AOV U-2 PRT TO RCDT DRN VLV Cont 377 2 2 2RY8046 U-2 PRT 2RY01T PW SUP CHK VLV Cont 377 18 2 2RY8047 Isolation Valve Cont 2 2RY8081 U-2 VLV LIO TO PRT 2RY01T CHK VLV Cont 390 6 2 2TE-0463 Pressurizer PORV Exit Temperature Element Cont 455 EL. 455 Pressurizer 2 2TE-0464 Pressurizer Safety Relief Valve Exit Cont 455 EL, 455 Pressurizer I__ _ Temperature Element _2 2TE-0465 Pressurizer Safety Relief Valve Exit Cont 455 EL. 455 Pressurizer

_0 Temperature Element 2 2TE-0466 Pressurizer Safety Relief Valve Exit Cont 455 EL. 455 Pressurizer Temperature Element 2 2ZS-RY8010A Pressurizer Relief Valve Limit Switch Cont EL. 455 Pressurizer 2 2ZS-RY8010B Pressurizer Relief Valve Limit Switch Cont EL. 455 Pressurizer 2 2ZS-RY8010C Pressurizer Relief Valve Limit Switch Cont EL. 455 Pressurizer Pressurizer 2 Pressurizer Heater Cont U2 Containment Heater Table B-1 Page 30 of 38 B-32 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION ASSY -AOV 2A RH HX 2RH02AA OUTLET 2 2RH606 Aux 357 VLV (EOP VLV)2 2RH607 ASSY -AOV 2B RH HX 2RH02AB OUTLET Aux 357 10 VLV (EOP VLV)2 2RH618 ASSY -AOV 2A RH HX 2RH02AA BYP VLV Aux 357 10 (EOP VLV)2 2RH619 ASSY -AOV 21 RH HX 2RH02AB BYP VLV Aux 357 10 (EOP VLV)2 2RH8708A 2A RH PP SUCT HDR RLF VLV Aux 364 15 2 2RH8708B 2B RH PP SUCT HDR RLF VLV Aux 364 15 2 2RH8734A 2A RH HX OUTLET TO LTDWN HX ISOL VLV Aux 364 1 I (EOP VLV)2B RH HX OUTLET TO LTDWN HX ISOL VLV 2 2RH8734B Aux 364 1 (EOP VLV)2 2RH8735 U-2 RH RECIRC TO RWST ISOL VLV (EOP Aux 364 12 VLV)2 2RF02MA RCP Lube Oil Drain Tank Cont 377 El. 377 R142 2 2RF02MB RCP Lube Oil Drain Tank Cont 377 El. 377 R136 2AOV U-2 RCDT PP DSCH INSIDE CNMT ISOL 2 2RE1003 Cont 377 11 VLV (EOP VLV)2 2RE9159A Isolation Valve Cont 2 2RE9160A Isolation Valve Cont 2 2RC8003A ASSY -2A RC LOOP BYP VLV Cont 390 4 2 2RC8003B ASSY -MOV 2B RC LOOP BYP VLV Cont 390 4 2 2RC8003C ASSY -MOV 2C RC LOOP BYP VLV Cont 390 4 2 2RC8003D ASSY -MOV 2D RC LOOP BYP VLV Cont 390* +04 BTWN HL & CL 2 2RC8037A ASSY -AOV 2A RC LOOP DRN VLV (EOP Cont 377 2 1_ VLV)2 2RC8037B ASSY -AOV 2B RC LOOP DRN VLV (EOP Cont 377 2 1_ VLV)2 2RC8037C ASSY -AOV 2C RC LOOP DRN VLV (EOP Cont 377 2 VLV)2 2RC8037D ASSY -AOV 2D RC LOOP DRN VLV (EOP Cont 377 2 2 ___________

VLV) _ ___ 377_2 2 2RC8038A 2A RC LOOP CVCS FILL ISOL VLV Cont 377 8 Table B-1 Page 31 of 38 B-33 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2RC8038B 2B RC LOOP CVCS FILL ISOL VLV Cont 377 +9 BTWN 2B S/G & RCP 2 2RC8038C 2C RC LOOP CVCS FILL ISOL VLV Cont 377 9 2 2RC8038D 2D RC LOOP CVCS FILL ISOL VLV Cont 377 9 2 2RC8040A 2A RC LOOP HL DRN VLV Cont 377 7 2 2RC8040B 2B RC LOOP HL DRN VLV Cont 377 7 2 2RC8040C 2C RC LOOP HL DRN VLV Cont 377 7 2 2RC8040D 2D RC LOOP HL DRN VLV Cont 377 7 2A RC LOOP BYP VLV 2RC8003A DISC 2 2RC8045A CHCont 390 2 21RC8045B3 2B3 RC LOOP BYP VLV 2RC8003B DISC Cont 390 1 PRESS EQUAL/OVERPRESS CH 2C RC LOOP BYP VLV 2RC8003C DISC PRESS EQUAL/OVERPRESS CH 2 2RC8045D 2D RC LOOP BYP VLV 2RC8003D DISC Cont 390 1 PRESS EQUAL/OVERPRESS CHC 2 2RC8057 2D RC LOOP CL DRN 1ST ISOL VLV Cont 377 +5 ABOVE RECIRC SUMP 2 2PS231A Isolation Valve Cont 2 2PS231 B Isolation Valve Cont 2 2PS9354A Isolation Valve Cont 2 2PS9355A Isolation Valve Cont 2 2PS9356A Isolation Valve Cont 2 2PS9357A Isolation Valve Cont 2 2PS29J 2PS29J 2 2PRO02G Isolation Valve Cont 2 2PRO02H Isolation Valve Cont 2 2PR032 Isolation Valve Cont 2 20G057A Isolation Valve Cont 2 20G079 Isolation Valve Cont 2 20G080 Isolation Valve Cont 2 20G081 Isolation Valve Cont 2 2MS021A 2A S/G MS OUTLET HDR DRN DWST ISOL MSIV 377 5 VLV (EOP VLV)2 2MS021B 2B S/G MS OUTLET HDR DRN DWST ISOL MSIV 377 5 VLV (EOP VLV) I I Table B-1 Page 32 of 38 B-34 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2MS021C 2C S/G MS OUTLET HDR DRN DWST ISOL MSIV 377 6 VLV (EOP VLV)2 2MS021 D 2D S/G MS OUTLET HDR DRN DWST ISOL MSIV 377 6_ VLV (EOP VLV)2 2MS101A ASSY- AOV 2A MSIV BYP VLV (EOP VLV) MSIV 377 15 2 2MS101B ASSY -AOV 2B MSIV BYP VLV (EOP VLV) MSIV 377 15 2 2MS101C ASSY- AOV 2C MSIV BYP VLV (EOP VLV) MSIV 377 15 2 2MS101D ASSY -AOV 2D MSIV BYP VLV (EOP VLV) MSIV 377 15 2 21A066 Isolation Valve Cont 2 21A091 Isolation Valve Cont 2 2FW015A-D ADD 2FW015A-D 2 2FW036A-D ADD 2FW036A-D 2 2FW037A-D ADD 2FW037A-D 2 2FW039A-D ADD 2FW039A-D 2 2FW036A 2A S/G FW TEMPERING LINE CHK VLV MSIV 377 10 2 2FW036B 2B S/G FWTEMPERING LINE CHKVLV MSIV 377 10 2 2FW036C 2C S/G FWTEMPERING LINE CHK VLV MSIV 377 10 2 2FW036D 2D S/G FW TEMPERING LINE CHK VLV MSIV 377 10 AOV 2A FW PREHTR BYP DWST ISOL VLV 2 2FW039A MSIV 377 10 (EOP VLV)2 2FW039B AOV 2B FW PREHTR BYP DWST ISOL VLV MSIV 377 10 (EOP VLV)2 2FW039C AOV 2C FW PREHTR BYP DWST ISOL VLV MSIV 377 10 (EOP VLV)2 2FW043A AOV 2D FW PREHTR BYP DWST ISOL VLV MSIV 377 1 2 _____ 2W3 V2(EOP VLV) ____ 377_ 2 2 2FW043A AOV 2A S/G FWIV BYP VLV (EOP VLV) MSIV 377 2 2 2FW043B AOV 2B S/G FWlV BYP VLV (EOP VLV) MSIV 377 2 2 2FW043C AOV 2C S/G FWIV BYP VLV (EOP VLV) MSIV 377 2 2 2FW043D AOV 2D S/G FWlV BYP VLV (EOP VLV) MSIV 377 2 2 2FW079A 2A S/G FW SUP CHK VLV MSIV 377 15 2 2FW079B 2B S/G FW SUP CHK VLV MSIV 377 15 2 2FW079C 2C S/G FW SUP CHK VLV MSIV 377 15 2 2FW079D 2D S/G FW SUP CHK VLV MSIV 377 15 2 2FP345 RX2 CNMT FP SUP CHK VLV Cont 377 13 Table B-1 Page 33 of 38 B-35 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2FC009 Isolation Valve Cont 377 2 2FC012 Isolation Valve Cont 377 2 2LS-DO033 DO DAY TANK 2DO02TA Aux 401 2 2LS-DO036 DO DAY TANK 2DO02TB Aux 401 2 2CV01AA Excess Letdown Heat Exchanger Cont El. 426 R031 (In Pit)2 2CV01AB Excess Letdown Heat Exchanger Cont El. 426 R031 (In Pit)2 2CV02P ASSY -U-2 CV PD CHG PP Aux 364 2 2CV03AA Regenerative Heat Exchanger Cont El. 426 R030 (In Pit)2 2CV03AB Regenerative Heat Exchanger Cont El. 426 R029 (In Pit)2 2CV121 ASSY -AOV U-2 CV PPS DSCH HDR FCV Aux 364 7 (EOP VLV)2 2CV184 ASSY -AOV U-2 RC LOOP FILL HDR FCV Aux 364 +25 BELOW BIT S WALL 2 2CV8104 ASSY -MOV U-2 EMER BORATION ISOL VLV 426 +01 (EOP VLV)2 2CV8113 Isolation Valve Cont 2 2CV8117 U-2 LTDWN ORIFICE OUTLET HDR RLF VLV Cont 412 +9 6' FROM R028 2 2CV8121 U-2 PRT 2RY01T RLF VLV Cont 377 +20 8' FROM R028 ON WALL 2 2CV8123 U-2 SEAL WTR HX INLET HDR RLF VLV Aux 383 +5 1' FROM WALL 2A LTDWN HX R 2 2CV8124 U-2 CHG PP SUCT HDR RLF VLV Aux 364 +7 4' E OF S.2 2CV8145 ASSY -AOV U-2 PZR AUX SPRAY HDR ISOL Cont 412 2 VLV (EOP VLV)2 2CV8348 Isolation Valve Cont 2 2CV8355A ASSY -MOV 2A RC PP SEAL WTR INJ INLET Aux 374 +17 (EOP VLV), P-33 2CV8355A___

ISOL VLV A34 1(PL,3 ASSY -MOV 2B RC PP SEAL WTR INJ INLET 2 2CV8355B ISOL VLV Aux 374 +13 (EOP VLV), P-53 2 2CV8355C ASSY -MOV 2C RC PP SEAL WTR INJ INLET Aux 374 +13 (EOP VLV), P-53 2CV8355C____

ISOL VLV Aux_374 +13_(EOPVLV),_P-53 2 2CV8355D ASSY -MOV 2D RC PP SEAL WTR INJ INLET Aux 374 +17 (FOP VLV), P-33 2CV8355D____

ISOL VLV A3 + (PV -2 2CV8368A Isolation Valve Cont 2 2CV8368B Isolation Valve Cont 2 2CV8368C Isolation Valve Cont 2 2CV8368D Isolation Valve Cont Table B-1 Page 34 of 38 B-36 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. I Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2CV8377 U-2 PZR 2RY01S AUX SPRAY HDR CHK VLV Cont 401 18 2 2CV8378A U-2 RC CL LOOP 2 CHG WTR INLET 2ND Cont 377 2 CHK VLV 2 2CV8379A U-2 RC CL LOOP 1 CHG WTR INLET 2ND Cont 377 2 CHK VLV 2 2CV8382A 2A SEAL INJ FLTR 2CV01 FA OUTLET ISOL Aux 383 +1 FLTRVLV AISLE VLV 2 2CV8382B 2B SEAL INJ FLTR 2CV01FB OUTLET ISOL Aux 383 +1 FLTR VLV AISLE VLV 2 2CV8384A 2A SEAL INJ FLTR 2CVO1 FA INLET ISOL VLV Aux 383 +2 FLTR VLV AISLE 2 2CV8384B 2B SEAL INJ FLTR 2CV01 FB INLET ISOL VLV Aux 383 +2 FLTR VLV AISLE 2 2CV8387A 2A CV PP DSCH FCV BYP VLV (EOP VLV) Aux 364 6 2 2CV8387B 2B CV PP DSCH FCV BYP VLV (EOP VLV) Aux 364 10 2 2CV8394 U-2 CV CHG PP 2CV02P SUCT ISOL VLV Aux 364 3 2 2CV8399 U-2 SEAL WTR RTRN FLTR 2CV02F BYP Aux 383 +2 FLTR VLV AISLE VLV 2 2CV8442 U-2 CV EMER BORATION CHK VLV Aux 426 2 PW TO U-2 CV EMER BORATE LINE CHK 2 2CV8445 Aux 426 2 VLV 2 2CV8482 U-2 SEAL WTR HX OUTLET TO VCT ISOL Aux 426 2 VLV (EOP VLV)2 2CV8497 U-2 CV PDCP 2CV02P DSCH CHK VLV Aux 364 4 2 2CS009A CS PUMP 2A SUMP SUCTION VALVE -MOV Aux 343 +06 (EOP VLV)2 2CS009B CS PUMP 2B SUMP SUCTION VALVE -MOV Aux 343 +02 (EOP VLV)2 2CS007A MOV 2A CS PP DSCH HDR ISOL VLV Aux 374 +33 (EOP VLV), ABOVE 2A REC 2 2CS007B MOV 2B CS PP DSCH HDR ISOL VLV Aux 374 +25 (EOP VLV), ABOVE 2B REC 2 2CC060 U-2 PEN CLG RTRN CHK VLV Cont 377 9 2 2CC061 U-2 PEN CLG RTRN CHKVLV Cont 412 5 2 2CC062 VALVE CHECK 21N M-139 M-2167 RX2+07 Cont 412 7 Table B-1 Page 35 of 38 B-37 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION WM M/U TO U-2 CC SURGE TK 2CC01T 2 2CC070A Aux 426 4 INLET CHK VLV PW M/U TO U-2 CC SURGE TK 2CC01T 2 2CC070B Aux 426 4 INLET CHK VLV 2 2CCI 30A ASSY -AOV 2A LTDWN HX OUTLET TCV Aux 383 5 (EOP VLV)ASSY -AOV 2B LTDWN HX OUTLET TCV -2 2CC1 30B Aux 383 5 (EOP VLV)2 2CC21091 U-2 CC CHEM ADD TK 2CC03M OUTLET Aux 426 ISOL VLV 2 2CC21092 U-2 CC CHEM ADD TK 2CC03M INLET ISOL Aux 426 1 VLV ASSY -MOV U-2 RC PPS THERM BARR CC 2 2CC685 RTRN ISOL VLV Aux 374 +21 (EOPVLV)2 2CC9413A ASSY -MOV U-2 RC PPS CC SUP UPST Aux 374 +24 (EOP VLV)ISOLVLV Ax7 +4(PL 2 2CC9413B ASSY -MOV U-2 RC PPS CC SUP DWST Aux 374 +24 (EOP VLV)ISOL VLV Ax7 +4EPL 2 2CC9414 ASSY -MOV U-2 RC PPS CC RTRN OUTSIDE Aux 374 +21 (FOP VLV)CNMT ISOL VLV 2 2CC9415 ASSY -MOV U-2 SERV LOOP ISOL VLV Aux 364 +10 (EOPVLV)2 2CC9416 ASSY -MOV U-2 RC PPS CC RTRN INSIDE Cont 377 +21 (EOP VLV)CNMT ISOLVLV Cont 377_+21_(EOPVLV) 2 2CC9427 U-2 PEN CLG RTRN RLF VLV (EOP VLV) Cont 412 1 ASSY -AOV U-2 EXC LTDWN HX CC SUP 2 2CC9437A Aux 374 13 VLV (EOP VLV)2 2CC9438 ASSY -MOV U-2 RC PPS THERM BARR CC Cont 377 +21 (EOP VLV)RTRN ISOL VLV 2 2CC9454A U-2 CC SURGE TK WM SUP ISOL VLV (EOP Aux 426 4 VLV)2 2CC9473A ASSY -MOV U-2 CC PP DSCH HDR 2A Aux 364 +10 (EOP VLV)ISOL VLV 2 2CC9473B ASSY -MOV U-2 CC PP DSCH HDR 2B XTIE Aux 364 +10 (EOP VLV)ISOL VLV 2 2CC9422A 2A RH HX CC OUTLET HDR RLF VLV Aux 357 24 Table B-1 Page 36 of 38 B-38 Byron Generating Station Unit 2 1200108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2CC9422B 2B RH HX CC OUTLET HDR RLF VLV Aux 364 14 U-2 CST 2CD01T TO 2A AF PP 2AF01 PA 2 2AF001A Aux 383 7 SUCT CHK VLV 2 2AF001IB U-2 CST 2CD01T TO 2B AF PP 2AF01PB Aux 383 8 SUCT CHK VLV 2 2AF004A AOV 2A AF PP 2AF01PA DSCH VLV (EOP Aux 383 12 VLV)2 2AF004B AOV 2B AF PP 2AF01PB DSCH VLV (EOP Aux 383 12 VLV)2 2AF005A ASSY -AOV 2A AF PP DSCH TO 2A S/G FCV Aux 364 6 (EOP VLV)2 2AF005B ASSY -AOV 2A AF PP DSCH TO 2B S/G FCV Aux 364 9 (EOP VLV)ASSY -AOV 2A AF PP DSCH TO 2C S/G FCV 2 2AF005C Aux 364 6 (EOP VLV)2 2AF005D ASSY -AOV 2A AF PP DSCH TO 2D S/G FCV Aux 364 9 (EOP VLV)2 2AF005E ASSY -AOV 2B AF PP DSCH TO 2A S/G FCV Aux 364 1 (EOP VLV)ASSY -AOV 2B AF PP DSCH TO 2B S/G FCV 2 2AF005F Aux 364 2 (EOP VLV)2 12AFOO5G ASSY -AOV 2B AF PP DSCH TO 2C S/G FCV Aux 364 3 (EOP VLV)2 2AF0C05H ASSY -AOV 2B AF PP DSCH TO 2D S/G FCV Aux 364 4 (EOP VLV)ASSY -MOV 2A AF PP DSCH HDR TO 2A S/G 2 2AF013A ISOL VLV Aux 367 +01 (EOP VLV)2 2AF013B ASSY -MOV 2A AF PP DSCH HDR TO 2B S/G Aux 362 +01 (EOP VLV)ISOLVLV A32 0(PL 2 2AFO13C ASSY -MOV 2A AF PP DSCH HDR TO 2C Aux 362 +01 (EOP VLV)S/G ISOL VLV A3 +1 OV 2 2AF01 3D ASSY -MOV 2A AF PP DSCH HDR TO 2D Aux 367 +01 (EOP VLV)S/G ISOL VLV Aux36_+1 (EOPVLV)2 2AF013E ASSY -MOV 2B AF PP DSCH HDR TO 2A S/G Aux 367 +01 (EOP VLV)2 _2AF013E ISOLVLV Aux 367 +01I(EOPVLV)

Table B-1 Page 37 of 38 B-39 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 2 2AF01 3F ASSY -MOV 2B AF PP DSCH HDR TO 2B S/G Aux 362 +01 (EOP VLV)ISOL VLV ASSY -MOV 2B AF PP DSCH HDR TO 2C 2 2AF013HG / SO L Aux 362 +01 (EOP VLV)S/G ISOL VLV_________

____2 2AF01I3H ASSY -MOV 2B3 AF PP DSCH HDR TO 2D Aux 367 +01 (EOP VLV)S/G ISOL VLV ASSY -AOV 2A AF PP DSCH TO CST 2 2AF022A Aux 383 4 RECIRC VLV (EOP VLV)2 2AF02'2B3 ASSY -AOV 2B AF PP DSCH TO CST Aux 383 1 RECIRC VLV (EOP VLV)2 2AF024 ASSY -AOV U-2 AF PPS DSCH TO SX Aux 383 15 RECIRC VLV (EOP VLV)2 2AF026A 2A AF PP 2AF01 PA RECIRC TO SX CHK VLV Aux 383 5 2 2AF026B 28 AF PP 2AF01 PB RECIRC TO SX CHK VLV Aux 383 7 2 2AB8629A U-2 CV CHARGING PUMP TO RECYCLE Aux EVAPORATOR DEMINERALIZER 2 CR Sump A Containment Recirculation Sump A (including Cont 377 El. 377 R126 screen)2 CR Sump B Containment Recirculation Sump B (including Cont 377 El. 377 R128 ,screen) I -III Table B-1 Page 38 of 38 B-40 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Table B-2. Base List 2 ID Description Building Elevation Column No OFC001 REFUEL WTR PURIF PMPS DISCH TO FUEL CASK FILL AUX 401 15 Y OFC002A REFUEL WTR PURIF PMPS DISCH TO SPENT FUEL PIT AUX 385 15 X OFC003 REFUELING WTR PURIF PMP OB SUCTION ISO VLV 364 12 S OFC004 REFUELING WTR PURIF PMP OB DISCH CHECK AUX 364'+8' 12 S OFC006A REFUELING WTR PURIF PMPS SUCT HDR INST ROOT TO OPI-FC003 364 12 S OFC007A REFUELING WTR PURIF PMP OA DISCH INST ROOT TO OPI-FC005 AUX 364 12 S OFC011 REFUELING WTR PURIF PMP OA CASING DRN 364 12 S OFC012 REFUELING WTR PURIF PMPS SUCT HDR INST ISOL TO OPI-FC003 AUX 364 17 Q OFC013 REFUELING WTR PURIF PMP OA DISCH INST ISOL TO OPI-FC005 AUX 364 17 Q OFC03PA PUMP REFUELING WTR PURIFICATION OA ASMBLY AUX 364 12 S 0FC8754 SPENT FUEL PIT HX RTRN ISOL FH 401 18 Y OFC8763 REFUELING WTR PURIF PMP OA DISCH CHECK AUX 364+18' 12 S 0FC8790 SPENT FUEL PIT HX TO BORON RECY HOLDUP TANKS ISOL FH 401 18 Y OHS-FC002 REFUELING WATER PURIF PUMP OA AUX 364 12 S OLS-FC010 SPENT FUEL POOL LEVEL SWITCH 418 20 X OPI-FC003 REFUELING WTR PURIFICATION PUMP GA SUCT PRESS OPI-FC005 RFLG WTR PURIF PUMP GA DISCHARGE GAUGE AUX 364 17 S OTEW-FC007 RFLG WTR PURIF PUMP GA DISCH OTI-FC007 REFUELING WTR PURIFICATION PUMP GA DISCH TEMP IND AUX 364 12 S OTIS-0626 SPENT FUEL POOL TEMP INDICATING SWITCH FH 426 20 X 2FC004A SPENT FUEL PIT HX TUBE SIDE VENT FH 401 20 Z 2FC004B SPENT FUEL PIT HX SHELL SIDE VENT FH 401 19 Y 2FC005 SPENT FUEL PIT PMP CASING DRN FH 401 19 Y 2FC006 SPENT FUEL PIT PMP CASING VENT FH 401 19 Y 2FC007 REFUELING WTR PURIF PMP SUCT FROM U-2 REFU CAVITY DRN/TST CONN AUX 364 23 V 2FC008 SFP FLT DEMIN LOOP RTRN TO U2 REFUEL CAV DRN/TEST CONN AUX 364 24 U 2FC009 REFUELING WTR PURIF PMP SUCT FROM U-2 REFUEL CAV CNMT ISOL CNMT 377 2 R 2FC010 REFUELING WTR PURIF PMP SUCT FROM U-2 REFUEL CAV CNMT ISOL AUX 364 23 V 2FC011 SFP FLT DEMIN LOOP RTRN TO U-2 REFUEL CAV CNMT ISOL AUX 364 24 U 2FC012 SPENT FUEL PIT FLT DEMIN LOOP RTRN TO U-2 REFUEL CAV CNMT ISOL CNMT 377 25 R 2FC013 REFUELING WTR PURIF PMP DISCH TO SFP FLTR DEMIN LOOP AUX 401 19 S 2FC01A SPENT FUEL PIT HEAT EXCHANGER FH 401 19 Z 2FC01P PUMP,SPENT FUEL PIT 12X14-14 FH 401 19Z Table B-2 Page 1 of 2 B-41 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 ID Description Building Elevation Column No 2FC021 SPENT FUEL PIT PMP DISCH INST ISOL TO 2PI-627 FH 401 19 AA 2FC022 SPENT FUEL PIT PMP SUCT INST ISOL TO 2PI-633 FH 401 19 AA 2FC02M SPENT FUEL PIT PUMP START-UP STRAINER 2FC030 REFUEL WTR PURIF PMP SUCT FROM U-2 REFUEL CAVITY CNMT OUTSIDE DRN 364 23 V 2FC033 REFUEL WTR PURIF PMP SUCT FROM U-2 REFUEL CAVITY CNMT INSIDE DRN 2FC036 REFUEL WTR PURIF PMP RTRN TO U2 REFUEL CAVITY CNMT OUTSIDE VENT AUX 364 24 U 2FC03F SPENT FUEL PIT STRAINER 2FC8756 SPENT FUEL PIT PMP SUCTION FH 401 19 Y 2FC8757 SPENT FUEL PIT PMP SUCT INST ROOT TO 2PI-633 FH 401 19 AA 2FC8758 REFUELING WTR PURIF PMP SUCT FROM U-2 RWST AUX 364 23 V 2FC8761 SPENT FUEL PIT PMP DISCH INST ROOT TO 2PI-627 FH 401 19 Y 2FC8762A SPENT FUEL PIT HX INLET FH 401 19 Z 2FC8762B SPENT FUEL PIT HX OUTLET FH 401 20 Z 2FC8765 SPENT FUEL PIT FLTR DEMIN LOOP RTRN TO SPENT FUEL PIT FH 401 18 Z 2FC8766 SPENT FUEL PIT FLTR DEMIN LOOP RTRN TO U-2 RWST CHECK VLV 2FC8792A SPENT FUEL PIT HX TUBE SIDE DRN FH 401 20 Z 2FC8792B SPENT FUEL PIT HX SHELL SIDE DRN FH 401 20 Z 2FC8793 SPENT FUEL PIT PMP DISCH CHECK 401 19 Y 2FC8794 SPENT FUEL PIT FLTR DEMIN LOOP INLT ISOL FH 401 19 Y 2FI-0631 FC DEMIN FLOW INST AUX 383 15 P 2HS-FC001 SPENT FUEL PIT PUMP FH 401 2PI-0627 2FC01P DISCHARGE PRESSURE GAUGE, 0-160 PSIG FH 401 19 BB 2PI-0633 SFP PMP SUCTION PRESSURE INDICATOR FH 401 19 BB Table B-2 Page 2 of 2 B-42 Byron Generating Station Unit 2 12Q01 08.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Table B-3. SWEL 1 Seismic Safety New or IPEEE ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM Replace Enhancement Comments Cat 1? Function(s)

?e ASSY -480V AUX BLDG ESF MCC 414 CURVED 2AP25E 231 L2 (01) Motor Control Centers Aux 414 WALL AREA -AP Y SSAC Y AREA 7 ASSY -480V AUX BLDG ESF MCC 426 AREA 7 2.AP27E 232X2 (01) Motor Control Centers Aux 426 CURVED WALL AP Y SSAC Y AREA 2AP38E ASSY -480V AUX BLDG MCC 233X1 (01) Motor Control Centers Auxiliary 346 346 15-23/ AP Y SSAC Y 2AP92E ASSY -480V SXCT MCC 232Z1, SOUTH (01) Motor Control Centers ESWCT 874 ESWCT AP Y SSAC Y ELEC RM 2AP93E ASSY -MCC 231Z1 ESW COOLING (01) Motor Control Centers ESWCT 874 ESWCT AP Y SSAC Y____TOWER 2AP98E 480V ESF SXCT UNIT SUBSTA 232Z, (01) Motor Control Centers ESWCT 874 ESWCT AP Y SSAC Y SOUTH ELEC RM 2APIOE EQ 480V ESF SUBSTATION BUS 231X (02) Low Voltage Switchgear Auxiliary 426 426 ESF SW AP V SSAC__AP_0E ASMBLY _02)_owVltagewithgea Axlay 46 26EFS AP Y_ SA 2AP05E ASSY -4160V ESF SWGR 241 (03) Medium Voltage Switchgear Auxiliary 426 426 ESF SW AP Y SSAC Y 2AP11E 480V ESF UNIT SUBSTA 231X XFMR (04) Transformers Aux 426 426 ESF SWV R AP Y SSAC Y RM -DIV 21UNTSUBSTATION232X 2AP13E E4 UNIT SUBSTATION 232X TRAN (04) Transformers Auxiliary 426 426 ESF SW AP Y SSAC Y 480V ESF _______21P02E INSTRUMENT BUS 212 TRANSFORMER (04) Transformers Auxiliary 451 451 U-2 DI PI Y SSAC-DIV. 22 1____________

_____ ________________

20 PUMP AUX FEEDWATER, MOTOR (PRA:F-V=7.16e-2AF01PA DRIVEN ASMBLY (05) Horizontal Pumps Auxiliary 363 All AF Y DHR Y 02,RAW=16.99 2CC01PA 2A COMPONENT COOLING WTR PUMP (05) Horizontal Pumps Auxiliary 364 364 15-21/ CC Y UHS____ASMBLY

____ I___2CV01PA PUMP,2A CENTRIFUGAL CHARGING (05) Horizontal Pumps Auxiliary 364 364 2A CV CV Y RCIC Y ASMBLY 2SX01PA PUMP, 2A ESSENTIAL SER WTR (05) Horizontal Pumps Auxiliary 330 33013-18/

SX Y UHS PRA:F-V=5.52E-ASMBLY 02,RAW=3.11 2VA01SA 2A SX Pp COOLER ESSENTIAL SERV (05) Horizontal Pumps Auxiliary 330 330 13-18/ SX Y UHS WATER PUMP 95-10 2RHO1PA PUMP,2A RESIDUAL HEAT REMOVAL (06) Vertical Pumps Auxiliary 346 346 21-25/ RH Y DHR ASMBLY AWW019B JASSY -AOV OA DEEP WELL PP (07) Fluid-Operated Valves ESWCT 860 ESWCT WW Y UHS W OWWO1PA TO OB SXCT LCV_2AF005C S/G 2C FLOW CONT VLV ASMBLY (07) Fluid-Operated Valves Auxiliary 364 364 21-26/ AF Y UHS 2AF005G S/G 2C FLOW CONT VLV ASMBLY (07) Fluid-Operated Valves Auxiliary 364 364 21-26/ AF Y DHR 2MS001C MS ISOL VLV LOOP 2C ASMBLY (07) Fluid-Operated Valves Auxiliary 377 377 U-2 MS MS Y DHR 2RY455A PZR PORV (C/S AT 2PM05J) ASMBLY j(07) Fluid-Operated Valves Cont 461 ABOVE PZR RY Y RCPC 2SI8801A CHG PUMP TO COLD LEG NJ ISOL (07) Fluid-Operated Valves Auxiliary, 375 383 U-2 AR SI Y RCIC r2 _ASMBY IPRA:F-V=2.74E-02 2SX169A DG 2A SX VLV ASMBLY (07) Fluid-Operated Valves Auxiliary 401 401 2A DG SX Y UHS WRAW=2.19 Table B-3 Page 1 of 6 B-43 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Seismic Safety New or IPEEE ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM Cat 1? Function(s)

Replace Enhancement Comments 0SX007 0 CC HX OUTLT VLV ASMBLY (08) Motor-Operated and Solenoid-Operated Valves Auxiliary 346 346 10-18/ SX Y UHS 0SX162B ASSY -MOV 0B SXCT TO BASIN BYP (08) Motor-Operated and ESWCT 872 +01 0B VLV RM, SX Y UHS VLV Solenoid-Operated Valves EEOP VLV)2 AUXILIARY FEEDWATER PMP 2A SX (08) Motor-Operated and 2AF006A SUCT VLV ASMBLY Solenoid-Operated Valves Auxiliary 383 All AF Y DHR AUXILIARY FEEDWATER PMP 2A SX (08) Motor-Operated and 2AF017A SUCT VLV ASMBLY Solenoid-Operated Valves Auxiliary 383 All AF Y DHR CC FROM RH HX 2A OUTLET ISOL (08) Motor-Operated and 2CC9412A ASMBLY Solenoid-Operated Valves Auxiliary 384 364 17-19/ CC Y UHS 2CV112E RWST TO CHG PMPS SUCT VLV C/S (08) Motor-Operated and AT 2PM05J ASMBLY Solenoid-Operated Valves Auxiliary 364 364 U-2 AR CV Y RCIC Y 2CV8105 CHG LINE CNMT ISOL VLV C/S AT (08) Motor-Operated and 2PM05J ASMBLY Solenoid-Operated Valves Auxiliary 375 364 U-2 AR CV Y CF 2CV8804A RH HX 2A TO CV PMP SUCT ISOL V.V; (08) Motor-Operated and C/S AT 2PM06J ASMBLY Solenoid-Operated Valves Auxiliary 364 384 U-2 AR CV Y DHR 2MS018C S/G 2C PORV (08) Motor-Operated and Solenoid-Operated Valves Auxiliary 404 401 U-2 MS MS Y DHR 2MS018D S/G 2D PORV ASMBLY (08) Motor-Operated and Solenoid-Operated Valves Auxiliary 401 401 U-2 MS MS Y DHR 2RH8702A RC LOOP 2C TO RH PMP 2B SUCT (08) Motor-Operated and Cont 377 OMB PEN 75 SX Y DHR ISOL VLV ASMBLY Solenoid-Operated Valves 2SX004 CC HX 2 1INLT VLV ASMBLY (08) Motor-Operated and Solenoid-Operated Valves Auxiliary 330 330 13-18/ SX Y UHS 2SX005 U-0 CC HX INLET VLV ASMBLY (08) Motor-Operated and Solenoid-Operated Valves Auxiliary 330 330 18-23/ SX Y UMS 2SX033 ESSENTIAL SERVICE WTR PMP 2A (08) Motor-Operated and Auxiliary 330 33013-18/

SX Y UHS 3CROSSTIE VLV ASMBLY Solenoid-Operated Valves 2VD01CA DIESEL GENERATOR ROOM VENT FAN (09)Fans Auxiliary 401 401 2A DG VD Y SSHVAC PRA:F-V=1.85E-02 2VD01CASMBLY

_09)_ansAxiliay_401 401_2_DGV Y _SSHVA -02 2VE04C DIV 21 MEER Exh Fan (09) Fans Auxiliary 451 451 U-2 DI VE Y SSHVAC 2VE05C DIV 22 MEER Exh Fan (09) Fans Auxiliary 451 451 U-2 DI VE Y SSHVAC OVC02FA CONTROL RM REC CHARCOAL FILTER (10) Air Handlers Auxiliary 451 451 U-i MV VC Y SSHVAC 0VC02F_ A TRAIN ASMBLY VC Y _SSHVAC 2VA02SA 2A RHR PUMP ROOM CUB CLR (10) Air Handlers Auxiliary 346 346 21-25/ VA Y SSHVAC 2VA02S ASMBLY 2VA06SA COOLERCENTRIFUGAL CHARGING (10) Air Handlers Auxiliary 364 364 2A CV VA Y SSHVAC PUMP2A 2VP01AA CNMT ESSL SERVICE WATER COIL 2 (10) Air Handlers Cont 377 (No Data) VP Y SSHVAC-(RCFC)________

___2DC06EA 125V DC ESF DIST PNL 212 (14) Distribution Panels Auxiliary 451 451 U-2 DI .DC Y SSDC 2DC10J 125V DC FUSE PANEL -DIV. 21 (14) Distribution Panels Auxiliary 451 451 U-2 DI DC Y SSDC 2AF01EA- Battery A (Battery 1 Auxiliary Feedwater (15) Batteries on Racks Auxiliary 383 All AF Y SSDC A Pump Bank A Battery A)Table B-3 Page 2 of 6 B-44 Byron Generating Station Unit 2 1200108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Seismic Safety New or IPEEE ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM Cat 1? Function(s)

Replace Enhancement Comments Ca 1 Fncios ?451 U-2 DIV 22 PRA:F-V=2.62E-02 2DC02E 125V DC BATT 212 (15) Batteries on Racks Aux 451 BATTERY RM 212 DC Y SSDC Y Y RAW=2.61 (28-28.3/P-Q) ,RAW=2.61 2DC04E BATTERY CHARGER 212 DIV. 22 (16) Battery Chargers and Auxiliary 451 451 U-2 D22 DC Y SSDC Y Inverters Axlr 41 4U-D2C Y SC 2DC05E 125V DC ESF DIST CENTER 211 (15) Batteries on Racks Auxiliary 452 452 U-2 D21 DC Y SSDC Y 2DC06E 125V DC ESF DIST CENTER 212 (15) Batteries on Racks Auxiliary 451 451 U-2 D22 DC Y SSDC Y 2DCO3E BATTERY CHARGER 211 DIV. 21 (16) Battery Chargers and Y Inverters Auxiliary 451 451 U-2 DI DC Y SSDC 21P05E INSTRUMENT BUS 211 INVERTER -(16) Battery Chargers and Auxiliary 451 451 U-2 DI IP Y SSDC DIV. 21 Inverters 21P06E INSTRUMENT BUS 212 INVERTER -(16) Battery Chargers and 21P06E DIV. 22 Inverters Auxiliary 451 451 U-2 01 IP Y SSDC 2DG01KA 2A DIESEL GENERATOR SKID (17) Engine-Generators Auxiliary 401 401 2A DG DG Y SSAC PRAF-V=2.3E-01 ,RAW=5.10 2FT-AF012 AF TO SG 2A FLOW TRANSMITTER (18) Instruments on Racks Auxiliary 364 364 21-26/ FT Y DHR 21Y-0606 RH HX 2A OUT I/P TRANSDUCER (18) Instruments on Racks Auxiliary 364 364 17-19/ IY Y DHR 2LT-0459 PRZR LEVEL D/P TRANSMITTER (18) Instruments on Racks Cont 377 2PL50J LT Y RCIC 2LT-0517 S/G LOOP 2A LEVEL D/P XMTTR (18) Instruments on Racks Cont 401 2PL69J LT Y DHR W/FILLED LEG I 2LT-0527 S/G LOOP 2B LEVEL D/P TRANSMITTER W/FILLED LEG (18) Instruments on Racks Cont 377 2PL75J LT Y DHR 2PT-0455 U2 PRESSURIZER PRESS CHANNEL (18) Instruments on Racks Cont 377 2PL50J PT Y RCPC 2PT-0457 PRZR PRESSURE TRANSMITTER (18) Instruments on Racks Cont 377 377-R-26 PT Y RCPC 2PT-0514 STM GEN LOOP 2A STEAM PRESS PR (18) Instruments on Racks Auxiliary 377 377 U-2 MS PT Y DHR 2PT-0546 STM GEN LOOP 2D STEAM PRESS PR (18) Instruments on Racks Auxiliary 377 377 U-2 MS PT Y DHR 2TE-0604 RHR LP 2A RETURN RTD (19) Temperature Sensors Auxiliary 364 364 U-2 AR TE Y DHR 2TE-RC022A RC WIDE RANGE LP 2A TEMP (19) Temperature Sensors Cont 390 TE Y DHR 2TE-RC023A RC WIDE RANGE LP 2B TEMP (19) Temperature Sensors Cont 390 TE Y DHR 0VC01JB CONTROL ROOM HVAC SYST LOCAL (20) Instrumentation and Control Auxiliary 451 451 U-2 HV VC Y VC CONT PANEL ASMBLY Panels and Cabinets AuiirI51 41 _2H VCYVC CAB PROC I+C RACK PROT CH 1 0- (20) Instrumentation and Control 451 U-2 AUX 2PA01J 37BA2PnlanCaiesAux 451 ELECTRIC EQUIP PA Y RRC Y 3373B AB2 Panels and Cabinets RM (23-25/M-Q) 2PA02J CAB PROC I+C RACK PROT CH 2 0- (20) Instrumentation and Control Aux451 U-2 AUX 3373B AB2 Panels and Cabinets RM (23-25/M-Q)

Table B-3 Page 3 of 6 B-45 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Seismic Safety New or IPEEE ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM cReplace Enhancement Comments Cat 1? Function(s)

ReaeEhneet Cmet 2PA03J CAB PROC I+C RACK PROT CH 3 0- (20) Instrumentation and Control Aux451 U-2 AUX 3373B AB2 Panels and Cabinets ELECTRIC EQUIP PA Y RRC Y RM (23-25AM-Q) 2PA04J CAB PROC I+C RACK PROT CH 4 0- (20) Instrumentation and Control 451 U-2 AUX 2P0J333 82PnlsadCaiesAux 451 ELECTRIC EQUIP PA Y RRC 3373B AB2 Panels and Cabinets RM (23-25/M-Q) 2PA06J CAB PROC I+C RACK CONT GRP 2 0- (20) Instrumentation and Control Aux451 U-2 AUX 3373B AB2 Panels and Cabinets RM (23-25/M-Q) 451 U2-25/AUX CAB PROC I+C RACK CONT GRP 3 0- (20) Instrumentation and Control 451 U-2 AUX 2PA07J 3373B AB2 Panels and Cabinets Aux 451 ELECTRIC EQUIP PA Y RRC Y RM (23-25/M-Q) 2PA08J CAB PROC I+C RACK CONT GRP 4 0- (20) Instrumentation and Control Aux451 U-2 AUX 3373B AB2 Panels and Cabinets ELECTRIC EQUIP PA Y RRC Y RM (23-25/M-Q) 2PAO9J CAB PROT SYST SOL ST RX/ESF TRN (20) Instrumentation and Control Aux451 U-2 AUX A 0-3373B AB2 Panels and Cabinets RM (23-25/M-Q) 451 U2-25/AUX 2PA10J CAB PROT SYST SOL ST RX/ESF TRN (20) Instrumentation and Control Aux451 U-2 AUX B 0-3373B AB2 Panels and Cabinets RM (23-25/M-Q) 451 U2-25/AUX CAB TEST SAFEGUARD TRN A 0-3373B (20) Instrumentation and Control 451 U-2 AUX 2PA1 1iJ 8 aesadCbnt Aux 451 ELECTRIC EQUIP PA Y SSESFAS Y AB3 Panels and Cabinets RM (23-25/M-Q)

CAB TEST SAFEGUARD TRN B 0-3373B (20) Instrumentation and Control 451 U-2 AUX 2PA12J BPaesadCbnt Aux 451 ELECTRIC EQUIP PA Y SSESFAS Y AB2 Panels and Cabinets RM (23-25/M-Q)

(20) Instrumentation and Control 451 U-2 AUX 2PA13J CABESFSEQ/ACTTRNA0-3373BAB2 Panels and Cabinets Aux 451 ELECTRIC EQUIP PA Y SSESFAS RM (23-25/M-Q) 2PA14J CAB ESF SEQ/ACT TRN B 0-3373B AB2 (20) Instrumentation and Control 451 U-2 AUX Panels and Cabinets Aux 451 ELECTRIC EQUIP PA Y SSESFAS Y Pnl aRM (23-25/M-Q)

Table B-3 Page 4 of 6 B-46 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev, 1 Correspondence No.: RS-12-161 Seismic Safety New or IPEEE ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM Replace Enhancement Comments Cat 1? Function(s)

? ?2PA27J CAB RELAY AUX SAFEGUARD TRN A 0- (20) Instrumentation and Control Aux451 U-2 AUX 2PA7J 373 A2 Pnel an Cbints ux 51 ELECTRIC EQUIP PA Y SSESFAS 3373B AB2 Panels and Cabinets RM (23-25/M-Q)

CAB RELAY AUX SAFEGUARD TRN B 0- (20) Instrumentation and Control 451 U-2 AUX 2PA28J 3373B AB2 Panels and Cabinets Aux 451 ELECTRIC EQUIP PA Y SSESFAS Y RM (23-25/M-0)

CAB CONT SYSTEM ESF 21 0-3373B (20) Instrumentation and Control Aux451 U-2 AUX 2PA33J A2PnlanCaiesAx 41 ELECTRIC EQUIP PA Y SSESFAS Y AB2 Panels and Cabinets RM (23-25/M-Q)

CAB CONT SYSTEM ESF 22 0-3373B (20) Instrumentation and Control Aux451 U-2 AUX 2PA34J AB2 Panels and Cabinets ELECTRIC EQUIP PA Y SSESFAS Y RM (23-25/M-0)

CAB HJTC RX VESSEL LEVEL CH A 0- (20) Instrumentation and Control 451 U-2 AUX 2PA51 J 37BA2PnlanCaiesAux 451 ELECTRIC EQUIP PA Y RCIC Y 3373B AB2 Panels and Cabinets RM (23-25/M-Q) 2PA52J CAB HJTC RX VESSEL LEVEL CH B 0- (20) Instrumentation and Control Aux451 U-2 AUX 3373B AB2 Panels and Cabinets RM (23-25/M-Q) 2PL07J 2A DG 2DG01KA CONTROL PANEL (20) Instrumentation and Control Auxiliary 401 401 2A DG PL Y SSESFAS Y Panels and Cabinets Axlay 01 412_ PL__ SSESFAS__2PL08J 2B DG 2DG01KB CONTROL PANEL (20) Instrumentation and Control Panels and Cabinets Auxiliary 401 401 2B DG PL Y SSAC 2PM05J MAIN CONTROL BOARD (20) Instrumentation and Control Auxiliary 451 451 MAIN C PM Y SSESFAS Y Panels and Cabinets Auxliry 45 51MIPMSEFS 2PM06J MAIN CONTROL BOARD (20) Instrumentation and Control Auxiliary 451 451 MAIN C PM Y SSESFAS Y Panels and Cabinets A i 5 1PS F 2PM07J MAIN CONTROL BOARD (20) Instrumentation and Control Auxilia 451 451 MAIN C PM Y SSESFAS Y Panels and Cabinets Auxiliary

_45 41ANPM _SESFAS Y 2PM11J MAIN CONTROL BOARD (20) Instrumentation and Control Panels and Cabinets Auxiliary 451 451 MAIN C PM Y SSESFAS Y 451 U-2 DIV 22 2RD05E REACTOR TRIP SWITCHGEAR (20) Instrumentation and Control Aux 451 MISC ELEC Y RRC Y Panels and Cabinets EQUIP RM (26-28/M-Q)_2DO01TA DIESEL OIL STORAGE TANK (21) Tanks and Heat Exchangers Auxiliary 373 383 U-2 D0 DO Y SSAC 2RHF1PA- RH PUMP 2A SEAL COOLER (21) Tanks and Heat Exchangers Auxiliary 346 346 21-25/ RH Y DHR A 2RY32MA 1PRESSURIZER PORV ACCUM 2A (21) Tanks and Heat Exchangers Cont 426 OMB RY Y SSCA Table B-3 Page 5 of 6 B-47 Byron Generating Station Unit 2 1200108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Table B-3 Page 6 of 6 B-48 Byron Generating Staion Unit 2 12Q0108.20-R-002 Rev. I Correspondence No.: RS-12-161 Table B-4. SWEL 2 Seismic Associated ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM Cat 1? with Rapid Draindown?

2FC01P PUMP,SPENT FUEL PIT 12X14-14 (05) Horizontal Pumps FH 401 19 Z FC Y N 2FC009 REFUELING WTR PURIF PMP SUCT FROM U-2 REFUEL CAV CNMT ISOL (00) Other CNMT 377 2 R FC Y N 2FC8758 REFUELING WTR PURIF PMP SUCT FROM U-2 RWST (00) Other AUX 364 23 V AREA 7 FC Y N 0FC012 REFUELING WTR PURIF PMPS SUCT HDR INST ISOL TO OPI-FC003 (00) Other AUX 364 17 Q CENTER AISLE FC Y N OFC006A REFUELING WTR PURIF PMPS SUCT HDR INST ROOT TO OPI-FC003 (00) Other AUX 364 12 S AREA 5 FC Y N 2FC011 SFP FLT DEMIN LOOP RTRN TO U-2 REFUEL CAV CNMT ISOL (00) Other AUX 364 24 U AREA 7 FC Y N 2PI-0633 SFP PMP SUCTION PRESSURE INDICATOR (18) Instruments on Racks FH 401 19 BB PI Y N 2FC012 SPENT FUEL PIT FLT DEMIN LOOP RTRN TO U-2 REFUEL CAV CNMT ISOL (00) Other CNMT 377 25 R FC Y N 2FC01A SPENT FUEL PIT HEAT EXCHANGER

00) Other FH 401 19 Z FC Y N 2FC8762A SPENT FUEL PIT HX INLET (21) Tanks and Heat Exchangers FH 401 19 Z FC Y N 2FC8762B SPENT FUEL PIT HX OUTLET (00) Other FH 401 20 Z FC Y N 0FC8754 SPENT FUEL PIT HX RTRN ISOL (00) Other FH 401 18 Y FC Y N 2FC8792B SPENT FUEL PIT HIX SHELL SIDE DRN (00) Other FH 401 20 Z FC Y N 2FC004B SPENT FUEL PIT HX SHELL SIDE VENT (00) Other FH 401 19 Y FC Y N 0FC8790 SPENT FUEL PIT HX TO BORON RECY HOLDUP TANKS ISOL (00) Other FH 401 18 Y FC Y N 2FC8792A SPENT FUEL PIT HX TUBE SIDE DRN (00) Other FH 401 20 Z FC Y N 2FC004A SPENT FUEL PIT HX TUBE SIDE VENT 00) Other FH 401 20 Z FC Y N 2FC005 SPENT FUEL PIT PMP CASING DRN (00) Other FH 401 19 Y FC Y N 2FC006 SPENT FUEL PIT PMP CASING VENT (00) Other FH 401 19 Y FC Y N 2FC8793 SPENT FUEL PIT PMP DISCH CHECK (00) Other FH 401 19 Y FC Y N 2FC022 SPENT FUEL PIT PMP SUCT INST ISOL TO 2PI-633 00) Other PH 401 19 AA FC Y N 2FC8757 SPENT FUEL PIT PMP SUCT INST ROOT TO 2PI-633 (00) Other PH 401 19 AA FC Y N 2FC8756 SPENT FUEL PIT PMP SUCTION (00) Other FH 401 19 Y FC Y N B-49 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 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 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Table C-1. Summary of Seismic Walkdown Checklists ID DESCRIPTION VERIFI- AREA CATION WALK-BY COMMENTS PAGE REFUELING WTR PURIF PMPS SUCT N/A 36 SWEL 2 C- 7 OFC006A HDR INST ROOT TO OPI-FC003 C-_7 REFUELING WTR PURIF PMPS SUCT N/A 61 SWEL 2 C- 10 OFC012 HDR INST ISOL TO OPI-FC003 C-_10 0FC8754 SPENT FUEL PIT HX RTRN ISOL N/A 42 SWEL 2 C- 13 SPENT FUEL PIT HX TO BORON RECY N/A 42 SWEL 2 C- 16 0FC8790 HOLDUP TANKS ISOL C-_16 0SX007 0 CC HX OUTLT VLV ASMBLY N/A 50 C- 19 OSX02JA OA SX M/U PP OA Control Cabinet Y 45 C- 22 ASSY -MOV OB SXCT TO BASIN BYP C-25 0SX162B VLV N/A 19 CONTROL ROOM HVAC SYST LOCAL, C-28 OVC01JB CONT PANEL ASMBLY N 6 CONTROL RM REC CHARCOAL C- 31 0VC02FA FILTER A TRAIN ASMBLY N 9 OWO01CA MCR B CHILLER Y 64A C- 35 ASSY -AOV OA DEEP WELL PP C-38 OWWO19B 0WW0IPA TO OB SXCT LCV N/A 19 2AF005C S/G 2C FLOW CONT VLV ASMBLY N/A 48 C- 41 2AF005G S/G 2C FLOW CONT VLV ASMBLY N/A 48 C- 44 AUXILIARY FEEDWATER PMP 2A SX 2AF006A SUCT VLV ASMBLY7 --N/A 59 C- 47 AUXILIARY FEEDWATER PMP 2A SX C-50 2AF017A SUCT VLV ASMBLY N/A 59 C Battery A (Battery 1 Auxiliary Feedwater C-53 2AF01EA-A Pump Bank A Battery A) Y 60 PUMP AUX FEEDWATER, MOTOR C- 56 2AF01PA DRIVEN ASMBLY Y 59 2AP05E ASSY -4160V ESF SWGR 241 Y OUTAGE_EQ 480V ESF SUBSTATION BUS 231X 2AP10E ASMBLY Y OUTAGE 2AP1 1 E 480V ESF UNIT SUBSTA 231X XFMR Y 34 C- 59 EQ UNIT SUBSTATION 232X TRAN C-62 2AP13E 480V ESF Y -35 ASSY -480V AUX BLDG ESF MCC C-66 2AP25E 231X2 Y 56 ASSY -480V AUX BLDG ESF MCC 2AP27E 232X2 Y 55C-69 2AP38E ASSY -480V AUX BLDG MCC 233X1 Y 49 C- 73 ASSY -480V SXCT MCC 232Z1, C-77 2AP92E SOUTH ELEC RM Y 21 ASSY -MCC 231Z1 ESW COOLING C- 81 2AP93E TOWER Y 17 480V ESF SXCT UNIT SUBSTA 232Z, C-85 2AP98E SOUTH ELEC RM Y 21 C Table C-1 Page 1 of 5 C-2 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 ID DESCRIPTION VERIFI- AREA COMMENTS PAGE CATION WALK-BY 2A COMPONENT COOLING WTR C- 89 2CC01PA PUMP ASMBLY Y 61 CC FROM RH HX 2A OUTLET ISOL ..2CC9412A ASMBLY .N/A 61 PUMP,2A CENTRIFUGAL CHARGING C- 95 2CV01PA ASMBLY Y 63 RWST TO CHG PMPS SUCT VLV C/S C- 98 2CV1 12E AT 2PM05J ASMBLY N/A 65 CHG LINE CNMT ISOL VLV C/S AT C- 101 2CV8105 2PM05J ASMBLY N/A 65 RH HX 2A TO CV PMP SUCT ISOL VLV; C- 104 2CV8804A C/S AT 2PM06J ASMBLY N/A 65 2DC02E 125V DC BATT 212 Y 3 C- 107 2DC03E BATTERY CHARGER 211 DIV. 21 Y 2 C- 111 2DC04E BATTERY CHARGER 212 DIV. 22 Y 4 C- 114 2DC05E 125V DC ESF DIST CENTER 211 Y 2 C- 118 2DC06E 125V DC ESF DIST CENTER 212 Y 4 C- 122 2DC06EA 125V DC ESF DIST PNL 212 Y 4 C- 126 2DC10J 125V DC FUSE PANEL -DIV. 21 Y 2 _ C- 129 2DG01KA 2A DIESEL GENERATOR SKID Y 25 C- 133 2DO01TA DIESEL OIL STORAGE TANK Y 27 C- 137 N/A 43 SWEL 2 C 4 2FC004A SPENT FUEL PIT HX TUBE SIDE VENT N4__21 SPENT FUEL PIT HX SHELL SIDE N/A 43 SWEL 2 C-143 2FC004B VENT 2FC005 SPENT FUEL PIT PMP CASING DRN N/A 42 SWEL 2 C- 146 2FC006 SPENT FUEL PIT PMP CASING VENT N/A 42 SWEL 2 C- 149 REFUELING WTR PURIF PMP SUCT N/A OUTAGE SWEL 2 2FC009 FROM U-2 REFUEL CAV CNMT ISOL SFP FLT DEMIN LOOP RTRN TO U-2 N/A 65 SWEL 2 C-152 2FC011 REFUEL CAV CNMT ISOL SPENT FUEL PIT FLT DEMIN LOOP N/A OUTAGE SWEL 2 RTRN TO U-2 REFUEL CAV CNMT 2FC012 ISOL 2FC01A SPENT FUEL PIT HEAT EXCHANGER Y 43 SWEL 2 C- 155 2FC01P PUMP,SPENT FUEL PIT 12X14-14 Y 42 SWEL 2 C- 158 SPENT FUEL PIT PMP SUCT INST N/A 44 SWEL 2 C-162 2FC022 ISOL TO 2PI-633 C-_162 2FC8756 SPENT FUEL PIT PMP SUCTION N/A 43 SWEL 2 C- 165 SPENT FUEL PIT PMP SUCT INST N/A 43 SWEL 2 C-168 2FC8757 ROOT TO 2PI-633 C-_168 REFUELING WTR PURIF PMP SUCT N/A 65 SWEL 2 C- 171 2FC8758 FROM U-2 RWST 2FC8762A SPENT FUEL PIT HX INLET N/A 43 SWEL 2 C- 174 2FC8762B SPENT FUEL PIT HX OUTLET N/A 43 SWEL 2 C- 177 2FC8792A SPENT FUEL PIT HX TUBE SIDE DRN N/A 43 SWEL 2 C- 180 Table C-1 Page 2 of 5 C-3 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 ID DESCRIPTION VERIFI- AREA COMMENTS PAGE CATION WALK-BY N/A 43 SWEL 2 C 8 2FC8792B SPENT FUEL PIT HX SHELL SIDE DRN N/A 43 ______2 C- 183 2FC8793 SPENT FUEL PIT PMP DISCH CHECK N/A 42 SWEL 2 C- 186 2FT-AF012 AF TO SG 2A FLOW TRANSMITTER N/A 61 C- 189 INSTRUMENT BUS 212 C-192 21P02E TRANSFORMER

-DIV. 22 N 4 INSTRUMENT BUS 211 INVERTER -21P05E DIV. 21 Y 2 INSTRUMENT BUS 212 INVERTER -C-198 21P06E DIV. 22 Y 4 C-198 21Y-0606 RH HX 2A OUT I/P TRANSDUCER N/A 61 C- 201 2LT-0459 PRZR LEVEL D/P TRANSMITTER N/A OUTAGE S/G LOOP 2A LEVEL D/P XMTTR 2LT-0517 W/FILLED LEG N/A OUTAGE_S/G LOOP 2B LEVEL DIP 2LT-0527 TRANSMITTER W/FILLED LEG N/A OUTAGE 2MS001C MS ISOL VLV LOOP 2C ASMBLY N/A 11 C- 204 2MS018C S/G 2C PORV N/A 11 C- 208 2MS018D S/G 2D PORV ASMBLY N/A 8 C- 211 CAB PROC I+C RACK PROT CH 1 0-2PAOIJ 3373B AB2 N 7 C-214 CAB PROC I+C RACK PROT CH 2 0- C- 218 2PA02J 3373B AB2 N 7 CAB PROC I+C RACK PROT CH 3 0- C- 221 2PA03J 3373B AB2 N 7 CAB PROC I+C RACK PROT CH 4 0- C-224 2PA04J 3373B AB2 N 7 CAB PROC I+C RACK CONT GRP 2 0- C- 227 2PA06J 3373B AB2 N 7 CAB PROC I+C RACK CONT GRP 3 0- C- 230 2PA07J 3373B AB2 N 7 CAB PROC I+C RACK CONT GRP 4 0- C- 233 2PA08J 3373B AB2 N 7 C-2N3 CAB PROT SYST SOL ST RX/ESF TRN236 2PA09J A 0-3373B AB2 N 7 CAB PROT SYST SOL ST RX/ESF TRN C- 239 2PA10J B 0-3373B AB2 N 7 CAB TEST SAFEGUARD TRN A 0- C- 242 2PA11J 3373B AB3 N 7 CAB TEST SAFEGUARD TRN B 0- C-245 2PA12J 3373B AB2 N 7 2PA13J CAB ESF SEQ/ACT TRN A 0-3373B AB2 N 7 C- 248 2PA14J CAB ESF SEQ/ACT TRN B 0-3373B AB2 N 7 C- 251 CAB RELAY AUX SAFEGUARD TRN A 2PA27J 0-3373B AB2 N 7 C-254 Table C-1 Page 3 of 5 C-4 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 ID DESCRIPTION VERIFI- AREA COMMENTS PAGE CATION WALK-BY CAB RELAY AUX SAFEGUARD TRN B 2PA28J 0-3373B AB2 N 7 CAB CONT SYSTEM ESF 21 0-3373B C- 260 2PA33J AB2 N 7 CAB CONT SYSTEM ESF 22 0-3373B C- 263 2PA34J AB2 N 7 CAB HJTC RX VESSEL LEVEL CH A 0- N 7 C- 266 2PA51J 3373B AB2 C-_266 CAB HJTC RX VESSEL LEVEL CH B 0- N 7 C- 270 2PA52J 3373B AB2 C-_270 SFP PMP SUCTION PRESSURE N/A .44 SWEL 2 C- 273 2PI-0633 INDICATOR C-_273 2PL07J 1A DG 1DG01KA CONTROL PANEL Y 25 C- 276 2PL08J 1B DG 1DG01KB CONTROL PANEL Y 24 C- 280 2PM05J MAIN CONTROL BOARD Y 1 C- 284 2PM06J MAIN CONTROL BOARD Y 1 C- 288 2PM07J MAIN CONTROL BOARD N 1 C- 291 2PM11J MAIN CONTROL BOARD N 1 C- 294 U2 PRESSURIZER PRESS CHANNEL N/A OUTAGE 2PT-0455 455 2PT-0457 PRZR PRESSURE TRANSMITTER N/A OUTAGE N/A 10 C-297 2PT-0514 STM GEN LOOP 2A STEAM PRESS PR N/A _10_C- 300*N/A 10C-0 2PT-0546 STM GEN LOOP 2D STEAM PRESS PR _______2RD05E REACTOR TRIP SWITCHGEAR Y OUTAGE PUMP,2A RESIDUAL HEAT REMOVAL Y 67 C- 303 2RH01PA ASMBLY C-_303 2RH01 PA-A RH PUMP 2A SEAL COOLER N/A 67 C- 308 RC LOOP 2C TO RH PMP 2B SUCT N/A OUTAGE 2RH8702A ISOL VLV ASMBLY 2RY32MA PRESSURIZER PORV ACCUM 2A N OUTAGE 2RY32MB PRESSURIZER PORV ACCUM 2B N OUTAGE 2RY455A PZR PORV (C/S AT 2PM05J) ASMBLY N/A OUTAGE CHG PUMP TO COLD LEG INJ ISOL N/A 65 C- 311 2S18801A ASMBLY C-_311 2SX004 CC HX 2 INLT VLV ASMBLY N/A 51 C- 315 2SX005 U-0 CC HX INLET VLV ASMBLY N/A 52 C- 318 2SX01AA 2A SX PUMP LUBE OIL COOLER N/A 51 C- 321 PUMP, 2A ESSENTIAL SER WTR Y 51 C- 324 2SX01PA ASMBLY ESSENTIAL SERVICE WTR PMP 2A N/A 51 C- 328 2SX033 CROSSTIE VLV ASMBLY C-_328 2SX169A DG 2A SX VLV ASMBLY N/A 25 C- 331 2TE-0604 RHR LP 2A RETURN RTD N/A 65 C- 334 2TE-RC022A RC WIDE RANGE LP 2A TEMP N/A OUTAGE I 2TE-RC023A RC WIDE RANGE LP 2B TEMP N/A OUTAGE I Table C-1 Page 4 of 5 C-5 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 ID DESCRIPTION VERIFI- AREA COMMENTS PAGE CATION WALK-BY 2A SX Pp COOLER ESSENTIAL SERV Y 51 C- 337 2VA01SA WATER PUMP 95-10 2A RHR PUMP ROOM CUB CLR Y 67 C- 340 2VA02SA ASMBLY C- 340 COOLER,CENTRIFUGAL CHARGING Y 63 C- 343 2VA06SA PUMP 2A DIESEL GENERATOR ROOM VENT Y 25 C- 346 2VD01CA FAN ASMBLY C-_346 2VE04C DIV 21 MEER Exh Fan N 2 C- 350 2VE05C DIV 22 MEER Exh Fan N 4 C- 353 CNMT ESS'L SERVICE WATER COIL N OUTAGE 2VP01AA 2A (RCFC) I Table C-1 Page 5 of 5 C-6 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OFC006A Equipment Class: (0) Other REFUELING WTR PURIF PMPS SUCT HDR INST ROOT TO OPI-FC003 Equipment

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Description:==

VALVE Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 364.00 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% No of SWEL items requiring such verification)?

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 C-7 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OFC006A Equipment Class: (0) Other REFUELING WTR PURIF PMPS SUCT HDR INST ROOT TO OPI-FC003 Equipment

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Description:==

VALVE 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?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yes 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 M. Delaney & P. Gazda 8/8/12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-8 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OFC006A Equipment Class: (0) Other REFUELING WTR PURIF PMPS SUCT HDR INST ROOT TO OPI-FC003 Equipment

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Description:==

VALVE Photos None.C-9 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: Y N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0FC012 Equipment Class: (0) Other REFUELING WTR PURIF PMPS SUCT HDR INST ISOL TO 0PI-FC003 Equipment

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Description:==

VALVE Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 364.00 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.Anchora-ge

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 C-10 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OFC012 Equipment Class: (0) Other REFUELING WTR PURIF PMPS SUCT HDR INST ISOL TO OPI-FC003 Equipment

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Description:==

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

Yes 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 M. Delaney & P. Gazda 8/20/12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-1l Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OFC012 Equipment Class: (0) Other REFUELING WTR PURIF PMPS SUCT HDR INST ISOL TO OPI-FC003 Equipment

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Description:==

VALVE Photos OFC-012 Byron 1 & 2 8-20-12 071 C-1 2 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0FC8754 Equipment Class: (0) Other Equipment

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Description:==

SPENT FUEL PIT HX RTRN ISOL VALVE Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

FH, 401.00 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 Yes potentially adverse seismic conditions?

C-1 3 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Seismic Walkdown Checklist (SWC)Status: M N U Equipment ID No.: 0FC8754 Equipment Class: (0) Other Equipment

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Description:==

SPENT FUEL PIT HX RTRN ISOL VALVE Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

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

Masonry walls are seismic and would not collapse on the equipment 9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yes Yes Yes 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 M' Delaney & P. Gazda 8/9/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-14 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0FC8754 Equipment Class: (0) Other Equipment

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Description:==

SPENT FUEL PIT HX RTRN ISOL VALVE Photos None.C-1 5 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0FC8790 Equipment Class: (0) Other Equipment

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Description:==

SPENT FUEL PIT HX TO BORON RECY HOLDUP TANKS ISOL VALVE Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

FH, 401.00 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% No of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware?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?Not Applicable Not Applicable Not Applicable Not Applicable 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 C-16 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0FC8790 Equipment Class: (0) Other Equipment

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Description:==

SPENT FUEL PIT HX TO BORON RECY HOLDUP TANKS ISOL VALVE Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

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

Masonry walls are seismic and would not collapse on the equipment 9. Do attached lines have adequate flexibility to avoid damage?Yes 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 M. Delaney & P. Gazda 8/9/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-1 7 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: 5 N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0FC8790 Equipment Class: (0) Other Equipment

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Description:==

SPENT FUEL PIT HX TO BORON RECY HOLDUP TANKS ISOL VALVE Photos 8-9-12 025 C-18 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. I Correspondence No.: RS-12-161 Sheet 1 of 3 Status: [ N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0SX007 Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

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Description:==

0 CC HX OUTLT VLV ASMBLY Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 346.00 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 C-1 9 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0SX007 Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

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Description:==

0 CC HX OUTLT VLV ASMBLY Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes Handwheel extension near insulated pipe but there is adequate clearance.

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

Overhead fire protection well-supported

9. Do attached lines have adequate flexibility to avoid damage?Yes 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 M. Delaney & P. Gazda 8/10/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-20 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OSX007 Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

0 CC HX OUTLT VLV ASMBLY Photos uz~Auu( t yron 1 & z ts-i u-1 z i t C-21 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: FIN U Seismic Walkdown Checklist (SWC)Equipment ID No.: OSX02JA Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

==

Description:==

OA SX M/U PP OA Control Cabinet Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

RSH, 702.00 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% Yes of SWEL items requiring such verification)?

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: Yes This question only applies if.the item is one of the 50% for which an anchorage configuration verification is required.)

Drawing 6E-O-3391D Revision AC Detail 61 6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

C-22 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OSX02JA Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

==

Description:==

OA SX M/U PP OA Control Cabinet Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

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

Open S-hook on lights adjacent to this panel (not directly overhead so would not impact equipment if they fell). IR 1399104 written.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 M. Delaney & P. Gazda 8/9/12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-23 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OSX02JA Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

==

Description:==

OA SX M/U PP OA Control Cabinet Photos C-24 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0SX162B Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

ASSY -MOV OB SXCT TO BASIN BYP VLV Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

ESWCT, 872.00 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 C-25 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0SX162B Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

ASSY -MOV 0B SXCT TO BASIN BYP VLV Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

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?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yes Yes Yes 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 M. Delaney & P. Gazda 8/7/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-26 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0SX162B Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

ASSY -MOV 0B SXCT TO BASIN BYP VLV Photos C-27 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC01JB Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

==

Description:==

CONTROL ROOM HVAC SYST LOCAL CONT PANEL ASMBLY Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 451.00 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.Anchoraqe 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?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?

Cabinet opened to verify that it is welded on the interior of panel Not Applicable Yes C-28 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: EZI- N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC01JB Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

==

Description:==

CONTROL ROOM HVAC SYST LOCAL CONT PANEL ASMBLY Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

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

Overhead HVAC and fire protection piping is well-supported

9. Do attached lines have adequate flexibility to avoid damage?Yes 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 M. Delaney & P. Gazda 8/6/12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-29 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC01JB Equipment Class: (20) Instru Equipment

==

Description:==

CONTRO imentation and Control Panels and Cabinets L ROOM HVAC SYST LOCAL CONT PANEL ASMBLY Photos C-30 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0VC02FA Equipment Class: (10) Air Handlers Equipment

==

Description:==

CONTROL RM REC CHARCOAL FILTER A TRAIN ASMBLY Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 451.00 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% No of SWEL items requiring such verification)?

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.)

Not Applicable

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

Continuous weld at base and stitch weld at top.Yes C-31 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC02FA Equipment Class: (10) Air Handlers Equipment

==

Description:==

CONTROL RM REC CHARCOAL FILTER A TRAIN ASMBLY Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes 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 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 M. Delaney & P. Gazda 8/6/12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-32 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: Equipment Class: Equipment

==

Description:==

OVCO2FA (10) Air Handlers CONTROL RM REC CHARCOAL FILTER A TRAIN ASMBLY Photos C-33 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. I Correspondence No.: RS-12-161 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC02FA Equipment Class: (10) Air Handlers Eauinment DescriDtion:

CONTROL RM REC CHARCOAL FILTER A TRAIN ASMBLY C-34 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OWO01CA Equipment Class: (11) Chillers Equipment

==

Description:==

OA MCR CHLR Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 383.00 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% Yes of SWEL items requiring such verification)?

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 Cracks in grout pad that do not extend to base slab. Not a structural/seismic issue since anchor embedded in concrete as indicated on referenced drawings.

IR 1402729 written.5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Drawing M-1214 Sheet 3 Revision W Detail 49 Section H, Detail HI 6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

C-35 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OWO01CA Equipment Class: (11) Chillers Equipment

==

Description:==

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

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

Masonry wall are seismic and will not collapse on adjacent equipment 9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yes Yes.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 M. Delaney & P. Gazda 8/21/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-36 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: Equipment Class: Equipment

==

Description:==

OW001CA (11) Chillers OA MCR CHLR Photos C-37 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0WNW019B Equipment Class: (7) Fluid-Operated Valves Equipment

==

Description:==

ASSY -AOV GA DEEP WELL PP 0WW01PA TO0B SXCT LCV Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

ESWCT, 860.00 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.Anchorane 1. Is anchorage configuration verification required (i.e., is the item one of the 50% No of SWEL items requiring such verification)?

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 C-38 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: j N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OWWO19B Equipment Class: (7) Fluid-Operated Valves Equipment

==

Description:==

ASSY -AOV OA DEEP WELL PP 0WW01PA TO OB SXCT LCV Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

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 Yes Yes 10. Based on the above seismic interaction evaluations, is equipment free of 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?

Comments Seismic walkdown team M. Delaney & P. Gazda 8/7/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-39 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0WWO19B Equipment Class: (7) Fluid-Operated Valves Equipment

==

Description:==

ASSY -AOV OA DEEP WELL PP OWW01PA TO 0B SXCT LCV Photos C-40 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF005C Equipment Class: (7) Fluid-Operated Valves Equipment

==

Description:==

S/G 2C FLOW CONT VLV ASMBLY Project: Byron 2 SWEL Location-(Bldg, Elev, Room/Area):

Auxiliary, 364.00 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 C-41 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF005C Equipment Class: (7) Fluid-Operated Valves Equipment

==

Description:==

S/G 2C FLOW CONT VLV ASMBLY Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Adjacent to valve 2AF005 with adequate clearance 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

Seismic block walls 9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yes Yes Yes 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 M. Delaney & P. Gazda 8/10/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-42 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF005C Equipment Class: (7) Fluid-Operated Valves Equipment

==

Description:==

S/G 2C FLOW CONT VLV ASMBLY Photos 2AF005C Byron 1 & 2 8-10-12 004 C-43 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF005G Equipment Class: (7) Fluid-Operated Valves Equipment

==

Description:==

S/G 2C FLOW CONT VLV ASMBLY Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 364.00 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 questiononly 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 C-44 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF005G Equipment Class: (7) Fluid-Operated Valves Equipment

==

Description:==

S/G 2C FLOW CONT VLV ASMBLY Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes Adequate clearance (see photo, several inches) exist between valve 2AFOO5G and adjacent valves 2AFOO5E and 2AFOO5H -the valves are supported and lateral movements would not be significant

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?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yes 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 M. Delaney & P. Gazda 8/10/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 S/i "Philip Gazda 10/5/2012 C-45 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF005G Equipment Class: (7) Fluid-Operated Valves Equipment

==

Description:==

SIG 2C FLOW CONT VLV ASMBLY Photos C-46 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: Mi N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF006A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

AUXILIARY FEEDWATER PMP 2A SX SUCT VLV ASMBLY Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 383.00 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 C-47 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF006A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

AUXILIARY FEEDWATER PMP 2A SX SUCT VLV ASMBLY Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes 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?

No structural/seismic issues Comments Seismic Walkdown Team M. Delaney & P. Gazda 8/20/12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-48 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF006A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

AUXILIARY FEEDWATER PMP 2A SX SUCT VLV ASMBLY Photos C-49 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF017A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

AUXILIARY FEEDWATER PMP 2A SX SUCT VLV ASMBLY Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 383.00 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.Anchoraae 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 C-50 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF017A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

AUXILIARY FEEDWATER PMP 2A SXSUCT VLV ASMBLY Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes 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?

No structural/seismic issues Comments Seismic Walkdown Team M. Delaney & P. Gazda 8/20/12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-51 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF017A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

AUXILIARY FEEDWATER PMP 2A SX SUCT VLV ASMBLY Photos 2AF017A Byron 1 & 2 8-20-12 042 C-52 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: I N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF01EA-A Equipment Class: (15) Batteries on Racks Equipment

==

Description:==

BATTERY 1 AUXILIARY FEEDWATER PUMP BANK A BATTERY B Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 383.00 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% Yes of SWEL items requiring such verification)?

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: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Drawing 6E-O-3391AH Revision S 6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

C-53 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF01EA-A Equipment Class: (15) Batteries on Racks Equipment

==

Description:==

BATTERY 1 AUXILIARY FEEDWATER PUMP BANK A BATTERY B Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?(See A WC 60)Fuel level indicator 2LI-AF8000 is well-supported with no structural/seismic issues Masonry walls are seismic and would not collapse on equipment 9. Do attached lines have adequate flexibility to avoid damage?Yes 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 M. Delaney & P. Gazda 8/20/12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-54 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: Equipment Class: Equipment

==

Description:==

Photos 2AFOI EA-A (15) Batteries on Racks BATTERY 1 AUXILIARY FEEDWATER PUMP BANK A BATTERY B 2AF01 EA-A Byron 1 & 2 8-20-12 047 C-55 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF01PA Equipment Class: (5) Horizontal Pumps Equipment

==

Description:==

PUMP AUX FEEDWATER, MOTOR DRIVEN ASMBLY Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 383.00 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.Anchoracie

1. Is anchorage configuration verification required (i.e., is the item one of the 50% Yes of SWEL items requiring such verification)?

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: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Drawing M-1221 Sheet 2 Revision AD 6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

C-56 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF01PA Equipment Class: (5) Horizontal Pumps Equipment

==

Description:==

PUMP AUX FEEDWATER, MOTOR DRIVEN ASMBLY Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

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

Masonry walls are seismic and would not collapse on equipment 9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yes Yes 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 M. Delaney & P. Gazda 8/20/12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-57 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: r-T N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AF01PA Equipment Class: (5) Horizontal Pumps Equipment

==

Description:==

PUMP AUX FEEDWATER, MOTOR DRIVEN ASMBLY Photos C-58 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP1 1 E Equipment Class: (4) Transformers Equipment

==

Description:==

480V ESF UNIT SUBSTA 231X XFMR Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 426.00 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% Yes of SWEL items requiring such verification)?

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: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Drawing 6E-O-3391F Revision AJ Detail 121 Welded on all 4 sides with weld exceeding drawing requirement for length and spacing 6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

C-59 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP11E Equipment Class: (4) Transformers Equipment

==

Description:==

480V ESF UNIT SUBSTA 231X XFMR Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes 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?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yes 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?

Side panel of cabinet is dented but this does not impact the structural/seismic integrity of the cabinet. Equipment tagged with IR 1315939 for excessive noise (not a structural/seismic issue)Comments Seismic walkdown team M. Delaney & P. Gazda 8/8/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-60 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP11E Equipment Class: (4) Transformers Equipment

==

Description:==

480V ESF UNIT SUBSTA 231X XFMR Photos None.C-61 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 4 Status: Y]- N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP13E Equipment Class: (4) Transformers Equipment

==

Description:==

EQ UNIT SUBSTATION 232X TRAN 480V ESF Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 426.00 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% Yes of SWEL items requiring such verification)?

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: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Drawing 6E-O-3391F Revision AJ Welded on all 4 sides with weld exceeding drawing requirements

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

C-62 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP13E Equipment Class: (4) Transformers Equipment

==

Description:==

EQ UNIT SUBSTATION 232X TRAN 480V ESF Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes 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 M. Delaney & P. Gazda 8/8/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-63 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP13E Equipment Class: (4) Transformers Equipment

==

Description:==

EQ UNIT SUBSTATION 232X TRAN 480V ESF Photos 480V ESF TRANSFORMER 232X 2AP13E zmr-i~t myron -i cc z o-o-iz UJo C-64 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP13E Equipment Class: (4) Trans Eauipment

==

Description:==

EQ UNI1 sformers r SUBSTATION 232X TRAN 480V ESF C-65 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP25E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V AUX BLDG ESF MCC 231X2 Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 414.00 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?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Yes Yes 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.)

Drawing 6E-0-3391C Revision BE Weld exceeds drawing requirements

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

Yes C-66 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP25E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V AUX BLDG ESF MCC 231X2 Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes Cabinet is bolted to adjacent cabinet 2AP44E to eliminate spatial interaction issues during a seismic event. This is acceptable.

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?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yes Yes 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 M. Delaney & P. Gazda 8/20/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-67 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP25E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V AUX BLDG ESF MCC 231X2 Photos C-68 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP27E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V AUX BLDG ESF MCC 232X2 Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area).

Auxiliary, 426.00 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?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.)

Drawing 6E-0-3391C Revision BE Weld exceeds or meets drawing requirement

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

Yes Yes Yes Yes Yes C-69 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP27E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V AUX BLDG ESF MCC 232X2 Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Cabinet is bolted to adjacent cabinet 2AP47E to eliminate spatial interaction issues during a seismic event. This is acceptable.

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

Yes 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 M. Delaney & P. Gazda 8/20/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-70 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP27E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V AUX BLDG ESF MCC 232X2 Photos C-71 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP27E Equipment Class: (1) Motor Control Centers ment Descriotion:

ASSY -480V AUX BLDG ESF MCC 232X2 C-72 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 4 Status: I N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP38E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V AUX BLDG MCC 233X1 Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 346.00 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.Anchoraae 1. Is anchorage configuration verification required (i.e., is the item one of the 50% Yes of SWEL items requiring such verification)?

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: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Drawing 6E-0-3391C Revision BE Weld exceeds drawing requirement

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

C-73 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-1 2-161 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP38E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V AUX BLDG MCC 233X1 Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yes Storage equipment near cabinet meets seismic housekeeping requirements (MA-AA-716-026-1001 Revision 2)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 M. Delaney & P. Gazda 8/10/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-74 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: Equipment Class: Equipment

==

Description:==

2AP38E (1) Motor Control Centers ASSY -480V AUX BLDG MCC 233Xl Photos C-75 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP38E Equipment Class: (1) Motor Control Centers EauiDment

==

Description:==

ASSY -480V AUX BLDG MCC 233X1 C-76 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 4 Status: N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP92E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V SXCT MCC 232Z1, SOUTH ELEC RM Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

ESWCT, 874.00 ft, ALL Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document theresults 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% Yes of SWEL items requiring such verification)?

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: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Drawing 6E-0-3391C Revision BE Weld meets or exceeds drawing requirements

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

C-77 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP92E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V SXCT MCC 232Z1, SOUTH ELEC RM Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Cabinet is bolted to adjacent cabinet 2AP88E to eliminate spatial interaction issues during a seismic event. This is acceptable.

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

Yes 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 M. Delaney & P. Gazda 8/7/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 7 "Philip Gazda 10/5/2012 C-78 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 4 Status: MI N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP92E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V SXCT MCC 232Z1, SOUTH ELEC RM Photos C-79 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 4 of 4 Status: N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP92E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -480V SXCT MCC 232Z1, SOUTH ELEC RM zi~rtizt byron i ck z iu C-80 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 4 Status: N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP93E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY- MCC 231Z1 ESW COOLING TOWER Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

ESWCT, 874.00 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.Anchora-ge

1. Is anchorage configuration verification required (i.e., is the item one of the 50% Yes of SWEL items requiring such verification)?

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: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Drawing 6E-0-3391C Revision BE Weld matches or exceeds drawing 6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

C-81 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP93E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY- MCC 231Z1 ESW COOLING TOWER Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Cabinet is bolted to adjacent cabinet 2AP89E to eliminate spatial interaction issues during a seismic event. This is acceptable.

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

See associated Area Walk-by 17 for open S-hooks. IR 1398127 written.Condition acceptable since the S-hooks are partially open and it is unlikely that the chain and S-hook would become disengaged.

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

Back panel was loose in one location -operator fixed. N"ot a structural/seismic issue.Small, hairline cracks in the adjacent wall are-not a structural/seismic issue due to their small size.Comments Seismic walkdown team M. Delaney & P. Gazda 8/7/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-82 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP93E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY -MCC 231Z1 ESW COOLING TOWER Photos ZAV.dst tNr-00) tsiyron 1 a z i (to C-83 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP93E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

ASSY- MCC 231Z1 ESW COOLING TOWER C-84 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 4 Status: N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP98E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

480V ESF SXCT UNIT SUBSTA 232Z, SOUTH ELEC RM Project: Byron 2 SWEL Location (Bldg, Elev, Room/Area):

ESWCT, 874.00 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% Yes of SWEL items requiring such verification)?

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: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Drawing 6E-0-3391C Revision BE Weld exceeds drawing requirements

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

C-85 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP98E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

480V ESF SXCT UNIT SUBSTA 232Z, SOUTH ELEC RM Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

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

S hooks appear closed from floor. IR 1398127 written to address open S hooks in the ESWCT Note that S-hooks that were observed to be open were only partially open and it is unlikely that they will be disengaged.

9. Do attached lines have adequate flexibility to avoid damage?Yes 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?

One bolt on back panel is loose -enough fasteners in place so not a structural/seismic issue. Operator adjusted/fixed.

Comments Seismic walkdown team M. Delaney & P. Gazda 8/7/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-86 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP98E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

480V ESF SXCT UNIT SUBSTA 232Z, SOUTH ELEC RM Photos C-87 Byron Generating Station Unit 2 12Q0108.20-R-002 Rev. 1 Correspondence No.: RS-12-161 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 2AP98E Equipment Class: (1) Motor Control Centers Equipment

==

Description:==

480V ESF SXCT UNIT SUBSTA 232Z, SOUTH ELEC RM 000ka1A Ia ;C-88