ML12341A161

Enclosure 1, 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 1, Report No. 12Q0108.20-R-001, Revision 1

ML12341A161
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-001, Rev 1
Download: ML12341A161 (176)

Text

U.S. Nuclear Regulatory Commission 180-Day Response to 50.54(f) Letter NTTF Recommendation 2.3: Seismic November 27, 2012 Page 4 Enclosure 1 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 1, Report Number: 1200108.20-R-001, Revision 1 (700 pages)

U1 SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 60.54(f) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC for the BYRON GENERATING STATION UNIT I 4450 NORTH GERMAN CHURCH ROAD, BYRON, ILLINOIS 61010-9794 Facility Operating License No. NPF-37 NRC Docket No. STN 50-454 Correspondence No.: RS-12-161 0-" Exelon.Exelon Generation Company, LLC (Exelon)PO Box 805398 Chia,. IL 6068W5318 Prepared by: Stevenn & Auoclas 1661 Feehanvile Drive, Sub 150 Mount Prospect IL 60056 Report Number 12Q010820-R-001, Rev. I Prepwe. Malne Delney Reviewer-Tony Perez Approver Tony Perez Peer Review Team D Lead ReWponeslt Branch ManaeW. Am" catc.senior M=W _"qW espEnglneearQftiI

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[ 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 1 Document Type: Report Report Number: 12Q01 08.20-R-001 Project Name: NTTF R2.3 Seismic Walkdowns for Exelon -Byron Job No.: 12Q0108.20

""Exel~on.

Client: e o This document has been prepared in accordance with the S&A Quality Assurance Program Manual, Revision 17 and project requirements:

Rev. 0 Date: 10131/2012 Prepared by: Marlene Delaney Date: 10/31/2012 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 page C-42 and Delaney Table G-1 11/7/2012 11/7/2012 11/7/2012 DOCUMENT CONTRACT NO.APPROVAL SHEET 12Q0108 Stevenson

& Associates Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Contents L ist o f T a b le s ...................................................................................................

..i Executive Sum m ary ........................................................................

....... .V,:...............

iv I 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 Plant Overview ........................................................................................................

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

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

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

2-.......

...2.1 Overview ......................................................................

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2-1 2.2 Safe Shutdow n Earthquake (SSE) ..........................................................................

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

2-1 3 Personnel Qualifications

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

3 -1 3.2 Walkdown Personnel.....

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3-1 3.2 W alkdow n ersonnel .. ....... ................................................................................

3-3.2.1 Stevenson

& Associates Personnel

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3-2 3.2.2 Additional Personnel

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

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

4 -1 4.2 SW EL Developm ent ................................................................................................

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

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

4-3 5 Seism ic W alkdowns and Area W alk-Bys .................................................................

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

5 -1 5.2 Seism ic W alkdowns ...............................................................................................

5-1 5.2.1 Adverse Anchorage Conditions

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5-2 5.2.2 Visual Inspections

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5-2 5.2.3 Configuration Verification

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5-2 5.2.4 Adverse Seism ic Spatial Interactions

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5-3 Byron Generating Station Unit 1 12Q0108.20-R-001 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 ........................................................................................................

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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5-6 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-1 G IPEEE Vulnerability Status .....................................................................................

G-1 ii Byron Generating Station Unit 1 12Q0108.20-R-001 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 Table 3-1. Personnel R oles ..................................................................................

3-1 Table 5-1. Anchorage Configuration Confirmation

... ...................................................

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 T a b le B -1 .B a se L ist 1 ............................................................................................

B -3 Table B-2. Base List 2. ...............................................

B-38 T a b le B -3 .S W E L 1 .............................................................................................

B -4 0 T a b le B -4 .S W E L 2 ..............................................................................................

B -4 5 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-I. Inaccessible and Deferred Equipment List (Not Used) ..................................

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

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

G-2 iii Byron Generating Station Unit 1 12Q0108.20-R-001 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 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 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 1 in response, in part, to the 50.54(f) letter issued by the NRC.The Nuclear Energy Institute (NEI), supported by industry personnel, cooperated with the NRC to prepare guidance for conducting seismic walkdowns as required in the 50.54(f) letter, Enclosure 3, Recommendation 2.3: Seismic. (Ref. 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 1 12Q0108.20-R-001 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 I 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 1 12Q0108.20-R-001 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 1, the SWEL is comprised of: " SWEL 1 resulted with 106 items for walkdown.* SWEL 2 resulted with 21 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 1 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 (SWEs), the station Lead Responsible Engineer (LRE), a station Equipment Operator, and a station Operations person. The outage walkdowns occurred on September 19 and 22, 2012 with a similar walkdown team.The seismic walkdowns focused on the seismic adequacy of the items on the SWEL.The walkdowns focused on the following:

• Adverse anchorage conditions

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

The Area Walk-By was performed to identify potentially adverse seismic conditions associated with other SSCs vi Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 located in the vicinity of the SWEL item. The key examination factors that were considered in the Area Walk-Bys included the following:

• 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 127 of the 127 components on the SWEL.For Byron Unit 1, anchorage verification was required for minimum of 38 components to meet the 50% verification requirements of the EPRI guidance document. (Ref. 1) A total of 45 anchorage configurations were confirmed to be installed in accordance with the station documentation.

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

Supplemental inspections of 45 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 1 twenty-four (24) Issue Reports (IRs) were issued for conditions such as open fluorescent light fixture S-hooks and cracks in grout pads. Open fluorescent light fixture S-hook conditions were found to be the most common. After evaluation through the CAP, it was determined that none of the conditions identified in the IRs were adverse seismic conditions.

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

The process provides a means to identify, evaluate and document how the identified potentially adverse seismic condition meets a station's seismic licensing basis without entering the condition into a station's Corrective Action Program (CAP). In lieu of this process, Exelon/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 I 12Q0108.20-R-001 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 0 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 1 in accordance with the NRC endorsed walkdown methodology.

All potentially degraded, nonconforming, or unanalyzed conditions identified as a result of the seismic walkdowns have been entered into the 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 1 12Q0108.20-R-001 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 supplemental inspections of 45 electrical cabinets.

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

ix Byron Generating Station Unit 1 12Q0108.20-R-001 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 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 1 in response, in part, to the 50.54(f) letter issued by the NRC.The Nuclear Energy Institute (NEI), supported by industry personnel, cooperated with the NRC to prepare guidance for conducting seismic walkdowns as required in the 50.54(f) letter, Enclosure 3, Recommendation 2.3: Seismic. (Ref. 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 1 12Q0108.20-R-001 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 service water cooling. 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 1 engineering walkdowns and evaluations described in this report. (Ref. 1) In accordance with Reference 1, the following topics are addressed in the subsequent sections of this report:* Seismic Licensing Basis* Personnel Qualifications

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

• IPEEE Vulnerabilities Resolution Report* Peer Review

1.5 CONCLUSION

Seismic walkdowns have been performed at the Byron Generating Station Unit 1 in accordance with the NRC endorsed walkdown methodology.

All potentially degraded, nonconforming, or unanalyzed conditions identified as a result of the seismic walkdowns have been entered into the corrective action program (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 1 12Q0108.20-R-001 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 supplemental inspections of 45 electrical cabinets.

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

1-3 Byron Generating Station Unit 1 12Q0108.20-R-001 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* 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 shutdown earthquake (SSE) and 9% of gravity for operating basis earthquake (OBE).2-1 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 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 concludes 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 1 12Q0108.20-R-001 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 SDecifications 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 ACI 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 ACI 214 Recommended Practice for Evaluation of ANSI A146.1 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.i 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-1980 Division 2, CC 6000 ASME-1992 1992 Addenda, Division 1, Section Xl, 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 MSP-1 I 2-3 Byron Generating Station Unit 1 12QO108.20-R-001 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 1 12Q0108.20-R-001 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 Li NSeint Plant Walkdown censing IPEEE Peer Name Selection Basis Reiwr evwr Engineer Operations Engineer Reviewer Reviewer Reviewer____________________

~(SWE)_____

_____A. Perez X K. Hull X T.K. Ram X1 M. Delaney X X P. Gazda X X J. Griffith X X T. Bacon X W. Djordjevic x2 D. Shaw (Exelon X Contractor)

Davood 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 1 12Q0108.20-R-001 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 Inspections (CDBI), and with INPO in their biennial evaluations.

Throughout his years 3-2 Byron Generating Station Unit I 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 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.He is a licensed Professional Engineer (civil) in the states of California, Ohio, and 3-3 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 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 1 12Q0108.20-R-001 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 I* 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 1. (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 9 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 1 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 I E devices were identified as Safety Category I. Safety Category I and Class 1 E 4-1 Byron Generating Station Unit 1 12Q0108.20-R-001 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 1 12Q0108.20-R-001 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 1 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 I 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 1 structure.

Therefore, the SFP structure is assumed to be 4-3 Byron Generating Station Unit 1 12Q0108.20-R-001 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, (19) Temperature Sensors, 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 1 12Q0108.20-R-001 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 1 12Q0108.20-R-001 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 1 SWEL 2 list.4-6 Byron Generating Station Unit 1 12Q0108.20-R-001 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 (SWEs), in accordance with the EPRI guidance document during the weeks of August 6 and August 20, 2012 and on September 19 and 22, 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 127 of the 127 items identified on the Byron Unit 1 SWEL. The completed SWCs are provided in Appendix C of this report. Additionally, photos have been included with most SWCs to provide a visual record of the item along with any comments noted on the SWC. Drawings and other plant records are cited in some of the SWCs, but are not included with the SWCs because they are readily retrievable documents through the station's document management system.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 1 12Q0108.20-R-001 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.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.

5.2.3 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:

5-2 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161" Design drawings* Seismic qualification reports of analyses or shake table tests* IPEEE or USI A-46 program documentation, as applicable The Table C-1 of Appendix C indicates the anchorage verification status for components as follows: N/A: components that are line-mounted and/or are not directly anchored (with separate anchorage) to the civil structure and therefore do not count in the anchorage confirmation total Y: components that are anchored to the civil structure which were confirmed to be consistent with design drawings and/or other plant documentation N: components that are anchored to the civil structure for which anchorage drawings were not identified and/or retrieved See Table 5-1 below for the accounting of the 50% anchorage configuration confirmations, and the individual SWC forms in Appendix C for the specific drawings used for each anchorage verification confirmation.

Table 5-1. Anchorage Configuration Confirmation No. of SWEL N/A Items Required to SWEL Items Confirm? Items Confirmed (A) (B) (A-B)/2 1 106 35 36 42 2 21 17 2 3 Totals 127 52 38 45 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.

5-3 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-1 2-161 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 in a total of eleven (11)conditions identified and each of these was entered into the station's CAP. All of the identified conditions 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 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-0-3391C 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 5-4 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 detail. The panels impacted are: 1PA01J -1PA12J, 1PA14J, 1PA28J, 1PA33J, 1PA34J, 1PA51J, and 1PA52J.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 51 A'rea Walk-bys were performed for Byron Unit 1.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-04.1,.

Seismic Prequalified Scaffolds* Seismic housekeeping was examined to meet station procedure T&RM MA-BY-716-026-1001, Seismic Housekeeping The Area Walk-Bys are intended to identify adverse seismic conditions that are readily identified by visual inspection, without necessarily stopping to open cabinets or taking an extended look. Therefore, the Area Walk-By took significantly less time than it took to conduct the Seismic Walkdowns described above for a SWEL item. If a potentially adverse seismic condition was identified during the Area Walk-By, then additional time was taken, as necessary, to evaluate adequately whether there was an adverse condition and to document any findings.The results of the Area Walk-Bys are documented on the AWCs included in Appendix D of this report. A separate AWC was filled out for each area inspected.

A single AWC was completed for areas where more than one SWEL item was located.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)5-5 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 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.5.3.2 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 5-6 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 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.

Thirteen (13) 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 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 5-7 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 16. Battery Chargers and Inverters 20. Instrumentation and Control Panels Table E-2 indicates internal accessibility of each cabinet. Cabinets that have been identified as requiring these supplemental internal inspections are those with doors or panels with latches or thumbscrews and can be readily opened during normal maintenance activities.

Also provided for each cabinet is a proposed milestone schedule for performing these internal inspections and the associated station tracking 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.

Table 5-2. Conditions Identified during Seismic Walkdowns Actions Action Complete Item ID Description of Issue Request Yes/No ID (IR) (See Notes 1 &2)1RHI01PB BORIC ACID BUILD UP ON BOLTS 1403165 Yes 1 RH01 PB CRACK IN 1" GROUT PAD AT 2 OF 3 BOLTS 1403131 Yes 1VA02SB CRACK IN GROUT PAD 1403145 Yes OWO01CB CRACK IN GROUT PAD 1402735 Yes 1AP38E SEISMIC HOUSEKEEPING 1399382 Yes 1AP11E MISSING BOLTS ON PANEL COVER 1398659 No 1IDC01IE FLUORESCENT LIGHTING FIXTURE: OPEN S-HOOKS IN 1399377 No BATTERY ROOM 111 1IDC02E FLUORESCENT LIGHTING FIXTURE: OPEN S-HOOKS IN 1399380 No BATTERY ROOM 112 1DO01TB CRACKS IN GROUT 1398190 Yes 1VD01CB PERMANENT SCAFFOLD LABELING 1398177 Yes 1397709 1PA09J GAP BETWEEN AEER CABINETS (1419018)

Yes 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.5-8 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Table 5-3. Conditions Identified during Area Walk-Bys Actions Action Complete Item ID Description of Issue Request Yes/No ID (IR) (See Notes 1& 2)AREA WALK-BY 01 UNIT 1 AND 2 Main Control Room Panel fasteners 1399487 No CONTROL ROOM require repairs Area Walk-by 16 ESWCT El 377 Unit FLUORESCENT LIGHTING 1 SX A Cooling Room /Area Walk-by FIXTURE: Open S hooks 1398127 No 20, ESWCT South Elec Room Area Walk-by 09 Aux El 451 Unit 1 FP Valve 0FP332 is leaking and 2 (Ul HV -0VC01JA, 0VC15J, 1397710 No 0VC02FA)Area Walk-by 09 Aux El 451 Unit 1 Roof drain concern (roof drain is and 2 (U1 HV -0VC0!JA, 0VC15J, shaped like a U without a drain at OVC02FA) the low points and having victaulic 1397711 Yes couplings)

Area Walk-by 32, Aux El 426, Div 12 FLUORESCENT LIGHTING Switchgear Room /Area Walk-by 33, FIXTURE: Open S hooks 1398568 No Aux El 426, U1 4kV Div 1/Div 11 Room Area Walk-by 44, FH El 401 WATER IN TRACKS (NRC Adjacent to trackway IDENTIFIED NON-SEISMIC) 1399113 Yes Area Walk-by 14 Aux El 377 MSIV CRACKED FME COVER 1398194 Yes 1A/1D Room1389 Ye Area Walk-by 15 Aux El 401 MSIV FLOOR SEAL 1398191 No 1 AM1D Room 1911 N AREA WALK-BY 01 UNIT 1 AND 2 DIFFUSER DEGRADED 1397699 No CONTROL ROOM 1969 N Area Walk-by 08 Aux El 451 Unit 1 FLUORESCENT LIGHTING 1397693 No AEER FIXTURE: Open S hooks GENERAL FLUORESCENT LIGHTING 1399405 No FIXTURE: Open S hooks Area Walk-by 39, Area 5 Curved 1CV063 BORIC ACID 1398667 Yes Wall by Penetrations ACCUMULATION Area Walk-by 45, River Screen FLUORESCENT LIGHTING 1399104 No House FIXTURE: Open S hooks 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 1 12Q0108.20-R-001 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 1 12Q0108.20-R-001 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 1 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 1 12Q0108.20-R-001 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 1 12Q0108.20-R-001 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. CoinEd 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-019 Rev. 0, "Byron Risk Importance Listings to Support Development of Seismic Walkdown Equipment List (SWEL)." 9-1 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. I 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 J. Griffith, SWE, Licensing Basis Reviewer ....................................................

A-18 T. Ram, SWEL Peer Reviewer .....................................................................

A-22 W. Djordjevic, Peer Review Team Leader .......................................................

A-24 T .Bacon, Peer R eview er ............................................................................

A -28 D. Karimi (Exelon), Licensing Basis Reviewer, IPEEE Reviewer .........................

A-33 A-1 Byron Generating Station Unit 1 12Q0108.20-R-001 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 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Stevenson

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

-ME/CE/SE Design May 2004 -January 2006" Supervised a staff of 12 to 15 engineers (mechanical, civil, and structural design) who were charged with developing design changes, maintaining design and licensing basis documentation and supporting maintenance." Integrated the civil/structural engineering group and the mechanical engineering group into a cohesive unit that resulted in gained efficiency and a net reduction of one full time equivalent engineer.* Substantially increased the quality of engineering products developed and published by the ME/CE/SE Design Engineering group through coaching and feedback as a result of increased supervisory oversight of engineering products." Developed a work management system for the group that provided a means for prioritizing activities, estimating the level of effort, and scheduling of activities.

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

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

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

DISTRIBUTION PLANNING, INC., Grandville, MI Systems Mechanical Engineer 2000 -2001* Integrated mechanical systems and designed equipment for material handling systems." Procured equipment and coordinated delivery schedules with vendors.Page 2 of 3 A-3 Byron Generating Station Unit 1 12QO108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Stevenson

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

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

Designed access structures such as stair towers, service platforms and catwalks." Calculated foundation loads and point loads of equipment support points.LIFT-TECH INTERNATIONAL, Muskegon, MI Project Engineer 1997-1998-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 1 12Q0108.20-R-OO1 Rev. 1 Correspondence No.: RS-12-161 Byron Generating Station Unit 1 12QO108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Ix'33 Certificate of Completion Tony Perez Successlully Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Bruce M. LoiyZInstructor NTTF 2.3 Seismic Walkdown Course Date: 06/26/12 A-5 Byron Generating Station Unit 1 12Q0108.20-R-001 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 10CFR50.59 analyses." Participated in several regulatory and industry audits, including CDBI and INPO assessments." Experienced as a Technical Specialist performing NUPIC Audits." Well-developed communication skills for preparing technical presentations including lesson plans, project reports, and meetings in support of regulatory activities and inspections." Qualified Shift Technical Advisor for KNPP Operations Group (1980s).PROFESSIONAL EXPERIENCE STEVENSON

& ASSOCIATES

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

Project Manager* Development of plant specific Seismic Walkdown Equipment Lists for multiple Units in response to NRC 50.54(o 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 III/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 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 inspection findings.

Assigned to review all calculations, modification packages, 1OCFR 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 10CFR 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 1 1200108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 A-8 Byron Generating Station Unit 1 12Q0108.20-R-001 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 1 12Q0108.20-R-001 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-10 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 A-11 Byron Generating Station Unit 1 1200108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 A-12 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. I Correspondence No.: RS-12-161 STEVENSON

& ASSOCIATES PHILIP A. GAZDA PROFICIENCIES 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 General Manager, Stevenson

& Associates

-Chicago Stevenson

& Associates 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 CoinEd 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 1007896.1995 -1997 Head -Maintenance Engineering Department, Zion Nuclear Power CoinEd 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.1973- 1995 1986 -1995, Associate and Senior Project Engineer Sargent & Lundy Managed, coordinated and was responsible for the activities of the structural team engaged in the analysis and design of the structural A-13 Byron Generating Station Unit 1 12Q0108.20-R-001 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 1 12Q0108.20-R-001 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 6 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-1 5 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 A-16 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 A-17 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 STEVENSON

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

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

PROFESSIONAL EXPERIENCE Proiect Engineer (Stevenson

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

& Associates.

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

Gathered design information during conceptual field walkdowns and prepared design calculations and drawings.Provided field support during construction." Designed all component supports and concrete foundations for various new indoor equipment." Managed construction during installation of new roof-mounted HVAC system." Designed structural steel support framing and access gallery for new outdoor cooling towers.Maintenance Engineer (CornEd, 1995 to 1998)Responsible for the design of structural repairs to station equipment and facilities.

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

Investigated and developed solutions for structural problems in the field and provided field support during installation of modifications." Designed and supervised field installation of heavy-duty rigging apparatus for replacement of large overhead crane motor." Performed conceptual design and supervised field construction of 60 foot high scaffold work platform for valve replacement." Prepared and reviewed calculations to justify structural acceptability of station equipment during successful completion of Seismic Qualification Utility Group (SQUG) evaluation program.* Acted as engineering liaison to other station departments (Maintenance, Operations, Radiation Protection, etc) to resolve emergent problems regarding:

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

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

1 A-18 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161" Supported field installation of modifications and provided solutions to problems encountered in the field." Designed and monitored field installation of new access galleries for various pieces of equipment.

EDUCATION B.S., Civil and Environmental Engineering, University of Wisconsin, Madison, Wisconsin Continuing Education"Concrete Evaluation and Repair Seminar", Portland Cement Association, Skokie, Illinois, 1996"STAAD III Program Training", Sargent and Lundy Engineers, Chicago, Illinois, 1995"Piping Design, Analysis and AUTOPIPE Training" Vectra Technologies, Inc., Zion, Illinois, 1995"SQUG Walkdown Screening and Seismic Evaluation Training Course", Seismic Qualification Utility Group through ComEd, Downers Grove, Illinois, 1994 PROFESSIONAL REGISTRATIONS Licensed Professional Engineer in State of Wisconsin 2 A-19 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 A-20 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 A-21 Byron Generating Station Unit 1 12Q0108.20-R-001 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

• 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-22 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 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 Thbhawan Ram Page 2 A-23 Byron Generating Station Unit 1 12Q0108.20-R-001 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 resolving 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 MA A-24 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 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 Stationp M , Byron StationPM, 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 fragility 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-25 Byron Generating Station Unit 1 12Q0108.20-R-001 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-106.

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

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

1984 ANS Conference, "Qualification of Class 1E Devices Using In-Situ Testing and Analysis." 1986 Testing of Lithography Components for Vibration Sensitivity, Microelectronics, Cahners Publishing 1990 Nuclear Power Plant Piping and Equipment Conference, "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 A-26 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Certificate of Completion Walter Djordjevic Successfully Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Bruce M. Lorf- Instructor NTTF 2.3 Seismic Walkdown Course Date: 06/26/12 A-27 Byron Generating Station Unit 1 1200108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 275 Mishawum Road, Suite 200, Woburn, A'IA 01801 Tel (781) 932-9580 Fax (781) 933-4428 www. vecsa.corn Stevenson

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

/ Certification Professional Engineer:

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

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

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

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

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

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

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

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

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

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

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

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

These have included the design group for the HDPE buried pipe group of Section III, and the Flaw Analysis group of Section XI.Other Code experience includes the American Institute of Steel Construction (AISC), American Concrete BOSTON eCLEVELA ND eCHICA GO eMINNEA POLISePHOENIX A-28 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 275 Mishawum Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 Fax (781) 933-4428 www. vecsa. coni Stevenson

& Associates Engineering Solutions for Nuclear Power Institute (ACI), and ASME (ANSI) B31.1 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&CLEVELA ND eCHICA GO *MINNEA POLIS&PHOENIX A-29 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 275 A!ishawum Road, Suite 200, Woburn, MA 01801 Tel (78!) 932-9580 Fax (781) 933-4428 WWW. Vecsa. Colr 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 #CLEVELA ND @CHICAGO PMINNEA POLIS@PHOENIX A-30 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 275 Mishawum Road, Suite 200, Woburn, MA 01801 Tel (781) 932-9580 Fay (781) 933-4428 www. vecsa. corn Stevenson

& Associates Engineering Solutions for Nuclear Power Stations, ComEd -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, CornEd -Participated in responding to concerns raised during safety system functional inspection (SSFI) audits.Project Summary Reports and Operability Guidelines, ComEd and AEPSC -Wrote numerous project summary reports and operability guidelines for Commonwealth Edison (CoinEd) and American Electric Power Company (AEPC).Piping, Piping Support and HVAC Modifications, Various Facilities

-Served as Project Engineer for piping, piping support and HVAC modification work for various nuclear plants, including Dresden Units 2 and 3, Quad Cities Units 1 and 2, D. C. Cook Units 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 eCLEVELA ND #CHICAGO *MINNEAPOLIS*PHOENIX A-31 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Certificate of Completion Todd Bacon Successfullj Completed Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns Bruce M.L ry -Instructor NTTF 2.3 Seismic Walkdown Course Date: 06/26/12 A-32 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 DAVOOD KARIMI PROFESSIONAL EXPERIENCE Exelon Nuclear Corp, Byron, IL January, 2012 -Present CIVIL/STRUCTURAL/MECHANICAL ENGINEER* 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 January, 2008 -December, 2011 CIVIL/STRUCTURAL/MECHANICAL ENGINEER" 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-33 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 WSINIC POW(I 3ISMt(H INSVlT!At Certificate of Completion Davood Karimi Training on Near Term Task Force Recommendation 2.3-Plant Seismic Walkdowns June 27, 2012 Ow RabeW K. asw EPAI MbWM.ftueMWu ftsaimy & Iefsgdty A-34 Byron Generating Station Unit 1 12Q0108.20-R-001 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 b le B -I , B a se List 1 ..................................................................................

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

I .................................

B -38 T a ble B -3 , S W E L 1 ....................................................................................

B -4 0 T a ble B -4 , S W E L 2 ....................................................................................

B -4 5 B-1 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 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 1 Kim L. Hull 07/31/2012 Equipment Selection Preparer date Tony Perez -07/31/2012 Equipment Selection Revi date (7 D a David Shaw 7/3//2 62-Station Oper ons Staff Member date Refer to Attachr ~nt 3 for synopsis of Station Operations role and responsibility.

B-2 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Table B-I. Base List 1 UNIT ID DESCRIPTION BUILDING ELEVATION

.LOCATION 0 OWWO1PA ASSY -PUMP DEEP WELL M-83 M-3 GL Out 400 401 OUTSIDE 0 OVWV01PB ASSY -PUMP DEEP WELL M-83 M-3 GL Out 400 401 OUTSIDE 0 oCCol P 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 0PM02J ANNUNCIATOR RSH CONTROL PANEL Aux 451 451 MAIN CONTROL RM U-1 & U-2 0 OVCl5J MCR U-1 HVAC START PNL Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 0CC01E 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 OWWOI9A ASSY -AOV OB DEEP WELL PP OVWV01 PB TO ESWCT 860 ESWCT OA SXCT LCV 0 OWW019B ASSY -AOV OA DEEP WELL PP 0WW01 PA TO ESWCT 860 ESWCT 0B SXCT LCV 0 1WO01CA 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 OWO01PB ASSY -OB MCR WO PP Aux 383 383 CHILLED WTR RMS (8-10/L-P) 0 0W0144A OA MCR WO M/U PRV Aux 383 3 0 0W0144B OB MCR WO M/U PRV Aux 383 3 0 OWO14MA SEPARATOR AIR M-1 18 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 OA MCR CHLD WTR CLG COILS & CAB Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC01AB OB MCR CHLD WTR CLG COILS & CAB Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC01CA ASSY -OA MCR HVAC SUP FAN Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC01CB ASSY -OB MCR HVAC SUP FAN Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC01FA OA MCR HVAC SUP FLTRS Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC01FB OB MCR HVAC SUP FLTRS Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC01JA MCR HVAC OA LOC CONT PNL Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 0VC01JB MCR HVAC OB LOC CONT PNL Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC01SA OA 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)

Table B-1 Page 1 of 35 B-3 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 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) 0 OVC02CA ASSY -OA MCR HVAC RTRN FAN Aux 451 451 U-1 HVAC EQUIP RM (10-1 1/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 (10-11/L-Q) 0 0VC02FB 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 0VC01SA Aux 463 463 HVAC GENERAL ARA (11-1 5/L-Q)FAN 0 OVC03CB ASSY -OB MCR M/U AIR FLTR UNIT FAN Aux 463 463 HVAC GENERAL ARA (21-25/L-Q) 0 OVC05YA DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC05YB DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC05YC DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC05YD DAMPER ISO/MOD FO BF-54 Aux 451 451 U-2 HVAC EQUIP RM (25-26/L-Q) 0 OVC06YA 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)

MCR U-2 HVAC START PNL 451 U-2 AUX ELECTRIC EQUIP RM 0OVCl6J Aux 463 (2-5MQ (23-25/M-Q) 0 OVC17YA DAMPER ISO FC 38WX34H Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 OVC17YB DAMPER ISO FC 38WX34H Aux 451 451 U-1 HVAC EQUIP RM (10-11/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)

Table B-1 Page 2 of 35 B-4 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 0 OVC25Y DAMPER ISO/MOD FO BF-20 Aux 451 451 U-1 HVAC EQUIP RM (10-11/L-Q) 0 0SX007 ASSY -MOV U-0 CC HX OCC01A SX OUTLET Aux 346 +12 (EOP VLV)ISOL VLV 00 0SX03CA ASSY -GA SXCT FAN ESWCT 909 ESWCT 0 OSX03CB ASSY -GB SXCT FAN ESWCT 909 ESWCT 0 OSX03CC ASSY -OC SXCT FAN ESWCT 909 ESWCT 0 OSX03CD ASSY -OD SXCT FAN ESWCT 909 ESWCT 0 GSX03CE ASSY -GE SXCT FAN ESWCT 909 ESWCT 0 GSX03CF ASSY -OF SXCT FAN ESWCT 909 ESWCT 0 GSX03CG ASSY -GG SXCT FAN ESWCT 909 ESWCT 0 GSX03CH ASSY -OH SXCT FAN ESWCT. 909 ESWCT OSX146 ASSY -MOV U-0 CC HX TO U-1 SX RTRN HDR Aux 346 346 15-23/N-Q GENERAL AREA ISOL VLV ASSY -MOV U-0 CC HX TO U-2 SX RTRN HDR 346 15-23/N-Q GENERAL AREA O 0SX147 Aux 346 ISOL VLV 0 OSX157A ASSY -MOV GA SX M/U PP TO GA SXCT ESWCT 872 +04 N CNR VLV RM BASIN ISOL VLV ASSY -MOV GB SX M/U PP TO GB SXCT +04 S CNR VLV RM 00 OSX157B BAI SLVVESWCT 872 BASIN ISOL VLV ASSY -MOV GA SX M/U PP TO GA SXCT +04 N CNR VLV RM 00 OSX158A ESWCT 872 BASIN ISOL VLV____GO0X5B ASSY -MOV GB SX M/U PP TO GB SXCT EWT 82 +04 S CNR VLV RM_____ ____BASIN ISOL VLV _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _00 0SX162A ASSY -MOV GA SXCT TO BASIN BYP VLV ESWCT 872 +01 GA VLV RM, (EOP VLV)0 0SX162B ASSY -MOV GB SXCT TO BASIN BYP VLV ESWCT 872 +01 GB VLV RM, (EOP VLV)0 OSX162C ASSY -MOV GA SXCT TO BASIN BYP VLV ESWCT 872 +01 GA VLV RM, (EOP VLV)0 0SX162D ASSY -MOV GB SXCT TO BASIN BYP VLV ESWCT 872 +01 GB VLV RM, (EOP VLV)0 OSX163A SXCT GA RISER VLV GA L/S HTR ESWCT 874 ESWCT 0 OSX163B SXCT GA RISER VLV GB US HTR ESWCT 874 ESWCT 0 0SX163C SXCT GA RISER VLV 0C L/S HTR ESWCT 874 ESWCT 0 0SX163D SXCT GA RISER VLV GD L/S HTR ESWCT 874 ESWCT 0 0SX163E SXCT GB RISER VLV GE US HTR ESWCT 874 ESWCT 0 OSX163F SXCT GB RISER VLV OF US HTR ESWCT 874 ESWCT 0 OSX163G SXCT GB RISER VLV OG L/S HTR ESWCT 874 ESWCT 0 0SX163H SXCT GB RISER VLV OH L/S HTR ESWCT 874 ESWCT Table B-1 Page 3 of 35 B-5 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 0 OCC01A U-0 CC HX Aux 364 364 15-21/L-Q GENERAL AREA CC HEAT EXCHANGER 0 DISCH 100 OHM 364 15-21/L-Q GENERAL AREA o0TE-0675 Aux 364 PLATINUM RTD o GW0029A GA MCR CLG COIL OVC01AA WO INLET HDR Aux 451 1 DRN VLV GB MCR CLG COIL OVC01AB WO INLET HDR 1 G0WOG29B Aux 451 DRN VLV G GWO111A GA MCR WO AIR SEP 0WO14MA DRN HOSE Aux 383 2 0__ 0WO111A__

CONN ISOL VLV Aux_38 0 OWOIIB 0GB MCR WO AIR SEP GWO14MB DRN HOSE Aux 383 2 CONN ISOL VLV G GW02142A GA MCR WO STANDPIPE 0WO20MA DEMIN Aux 383 5 WTR QUICK FILL ISOL VLV G GW02142B 0B MCR WO STANDPIPE 0WO20MB DEMIN Aux 383 5_ WTR QUICK FILL ISOL VLV 0 0WO205A GA MCR CHLR WTR M/U CHK VLV Aux 383 3 0 GWO205B 0B MCR CHLR WTR M/U CHK VLV Aux 383 3 0 GVC02Y DAMPER ISO/MOD FC BF-54 Aux 451 0 OVC033Y DAMPER ISO FC 84WX34H Aux 451 0 OVC03Y DAMPER ISO FO 54WX46H Aux 451 0 OVC094Y DAMPER ISO FO 20WX46H Aux 463 0 OVC095Y DAMPER ISO FO 40WX20H Aux 463 0 GVC104Y DAMPER ISO FO 36WX24H Aux 463 8 0 0VC133Y DAMPER ISO FO 36WX24H Aux 463 0 OVC140Y 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 0VC18Y DAMPER ISO/MOD FC BF-54 Aux 451 0 GVC19Y DAMPER ISO FO 54WX46H Aux 451 0 OVC217Y DAMPER ISO FO 22WX38H Aux 463 0 OVC312Y DAMPER ISO FC 22WX22H Aux 451 0 GVC313Y DAMPER ISO FC 16WX30H Aux 451 0 GVC51Y DAMPER ISO FC 38WX34H Aux 451 0 iGSX028A GA SX M/U PP OSX02PA DSCH CHK VLV RSH 686 2 Table B-1 Page 4 of 35 B-6 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 0 0SX028B 0B SX M/U PP OSX02PB DSCH CHK VLV RSH 686 2 o 0SX063A ASSY -MOV OA MCR CHLR CNDSR SX INLET Aux 383 +10 (EOP VLV)_VLV 00 0SX063B ASSY -MOV OB MCR CHLR CNDSR SX INLET Aux 383 +10 (EOP VLV)VLV 00 OSX064A ASSY -HMOV OA MCR CHLR CNDSR SX Aux 383 8 OUTLET TCV ASSY -HMOV OB MCR CHLR CNDSR SX 8 0S0X064B Aux 383 OUTLET TCV 0 OSX167A SX TO RESID CHLORINE ANAL OCF03J ISOL Aux 346 +6 4' S OF Q1 1 VLV 0 0SX167B SX TO RESID CHLORINE ANAL OCF04J ISOL Aux 346 +9 8' W OF Q 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 0SX169D SX M/U HDR OD VAC RLF VLV Out 400 BTWN RSH & PLANT 0 0SX169E SX M/U HDR OE VAC RLF VLV Out 400 BTWN RSH & PLANT 0 0SX169F SX M/U HDR OF VAC RLF VLV Out 400 BTWN RSH & PLANT SX TO AUX BLDG FP RING HDR XTIE ISOL 10 0S0X 174 Aux 346 VLV (EOP VLV)0 OSX172 SX TO AUX BLDG FP RING HDR XTIE ISOL Aux 383 2 0 __0_X172 _ VLV (EOP VLV) Aux 383 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 1 1AF006A ASSY -MOV 1A AF PP SX SUCT DWST ISOL Aux 383 383 U-1 AFW PUMP RM (15-18/L-N)

I VLV 1 1AP38E ASSY -480V AUX BLDG MCC 133X1A Aux 346 346 10-18/L-N GENERAL AREA 1 lAP11E 480V ESF UNIT SUBSTA 131X XFMR Aux 426 426 ESF SWGR RM -DIV 11 1 1AP13E 480V ESF UNIT SUBSTA 132X XFMR Aux 426 426 ESF SWGR RM -DIV 11 1 lCC01PB ASSY -1B CC PP Aux 364 364 15-21/L-Q GENERAL AREA 1 1CC01PA ASSY -1A CC PP Aux 364 364 15-21/L-Q GENERAL AREA Table B-1 Page 5 of 35 B-7 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION I 1TE-0674 CC HEAT EX 1 DISCH RTD 100 OHMS Aux 364 364 15-21/L-Q GENERAL AREA PLATINUM TEMP ELEM PANEL CONT MAIN BOARD GEN/AUX PWR 0- 451 MAIN CONTROL RM U-1 & U-2 I 1PM01J Aux 451 3378 MCR 1 1 PM04J PANEL CONT MAIN BOARD FEEDWATER 0- Aux 451 451 MAIN CONTROL RM U-1 & U-2 3378 MCR I 1PM05J PANEL CONT MAIN BOARD RX/CV 0-3378 Aux 451 451 MAIN CONTROL RM U-1 & U-2 MCR PANEL CONT MAIN BOARD ENG SAFETY 0- 451 MAIN CONTROL RM U-1 & U-2 1 1 PM06J Aux 451 3378 MCR 1 1 PM07J PANEL INST NUCLEAR W-RACK 1-4 0-3378 Aux 451 451 MAIN CONTROL RM U-1 & U-2 MCR I IPMIIJ PANEL ISOLATION CONTAINMENT 0-3378 Aux 451 451 MAIN CONTROL RM U-1 & U-2 MCR 1 1PM12J PANEL INST MISC 0-3378 MCR Aux 451 451 MAIN CONTROL RM U-1 & U-2 1 IlP05E INVERTER INST BUS 111 1-3371 AB1 Aux 451 451 DIV 11 MISC ELEC EQUIP RM (9-1O/L-M)1 IP06E INVERTER INST BUS 112 1-3371 AB1 Aux 451 451 DIV 12 MISC ELEC EQUIP RM (9-10/M-Q)1 11P07E INVERTER INST BUS 113 1-3371 AB1 Aux 451 451 DIV 11 MISC ELEC EQUIP RM (9-I4 1 O/L-M)1 11P08E INVERTER INST BUS 114 1-3371 AB1 Aux 451 451 DIV 12 MISC ELEC EQUIP RM (9-u1 10/M-Q)I 1AP21E ASSY -480V AUX BLDG ESF MCC 131X1 Aux 364 364 U-1 AREA 5 CURVED WALL AREA 1 1AF017B ASSY -MOV 1B AF PP SX SUCT UPST ISOL Aux 383 383 U-1 AFW PUMP RM (15-18/L-N)

VLV 1 1CV8152 ASSY -AOV U-1 LTDWN HDR ISOL VLV (EOP Aux 374 383 U-1 AREA 5 CURVED WALL AREA VLV)1 1CV112E ASSY -MOV RWST TO U-1 CHG PPS SUCT Aux 364 364 U-1 AREA 5 CURVED WALL AREA ISOL VLV 1 1RD05E REACTOR TRIP SWlTCHGEAR Aux 451 451 DIV 12 MISC ELEC EQUIP RM (9-10/M-Q)1 lDG01SB AIR COMPRESSOR PACKAGE 1B Aux 401 401 1B DG RM (6-7.7/L-Q) 1 1AP10E ASSY -480V ESF SWGR 131X Aux 426 426 ESF SWGR RM -DIV 11 Table B-1 Page 6 of 35 B-8 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1AP92E ASSY -480V SXCT MCC 132Z1, SOUTH ELEC ESWCT 874 ESWCT RM 1 1AP93E ASSY -480V SXCT MCC 131Z1, NORTH ELEC ESWCT 874 ESWCT RM 1 1AP99E ASSY -480V ESF SXCT UNIT SUBSTA 131Z, ESWCT 874 ESWCT NORTH ELEC RM 1 1AP98E ASSY -480V ESF SXCT UNIT SUBSTA 132Z, ESWCT 874 ESWCT SOUTH ELEC RM 1 1PA01J U-1 PROC I&C RACK PROTECT CH 1 CAB 1 Aux 451 451 U-1 AUX ELEC EQUIP RM (11-I A13/N-Q)1 1PA02J U-1 PROC I&C RACK PROTECT CH 2 CAB 2 Aux 451 451 U-I AUX ELEC EQUIP RM (11-1u 13/N-Q)1 1PA03J U-1 PROC I&C RACK PROTECT CH 3 CAB 3 Aux 451 451 U-1 AUX ELEC EQUIP RM (11-I A13/N-Q)1 1PA04J U-1 PROC I&C RACK PROTECT CH 4 CAB 4 Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 1 PA06J U-1 PROC I&C RACK CONT GRP 2 CAB 6 Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 1PA07J PROC I&C RACK CONT GRP 3 CAB 7 Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 1PA08J U-1 PROC I&C RACK Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 1PA09J CAB PROT SYST SOL ST RX/ESF TRN A 0- Aux 451 451 U-1 AUX ELEC EQUIP RM (11-3371B AB1 13/N-Q)1 1PA10J CAB PROT SYST SOL ST RX/ESF TRN B 0- Aux 451 451 U-1 AUX ELEC EQUIP RM (11-3371B AB1 13/N-Q)1 1PA12J CAB TEST SAFEGUARD TRN B AB1 Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 1PA14J CAB ESF SEQ/ACT TRN B 0-3371B AB1 Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 1PA27J CAB RELAY AUX SAFEGUARD TRN A 0-3371 B Aux 451 451 U-1 AUX ELEC EQUIP RM (11 -AB1 13/N-Q)1 1PA28J CAB RELAY AUX SAFEGUARD TRN B 0-3371 B Aux 451 451 U-1 AUX ELEC EQUIP RM (1i-AB1 13/N-Q)Table B-1 Page 7 of 35 B-9 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1PA33J CAB CONT SYSTEM ESF 11 0-3371B AB1 Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 1PA34J CAB CONT SYSTEM ESF 12 0-3371B AB1 AiX 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 1PA51J CAB HJTC RX VESSEL LEVEL CH A 0-3371 B Aux 451 451 U-1 AUX ELEC EQUIP RM (11-AB1 13/N-Q)1 1PA52J CAB HJTC RX VESSEL LEVEL CH B 0-3371B Aux 451 451 U-1 AUX ELEC EQUIP RM (111-AB1 13/N-Q)1 1PA1IJ CAB TEST SAFEGUARD TRN A 0-3371 B AB1 Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 1PA13J CAB ESF SEQ/ACT TRN A 0-3371 B AB1 Aux 451 451 U-1 AUX ELEC EQUIP RM (11-1u 13/N-Q)1 1DC02E 125V DC BATT 112 Aux 451 451 DIV 12 BATTERY RM 112 (7.7-9/P-Q)1 1AP25E ASSY -480V AUX BLDG ESF MCC 131X2 Aux 414 414 CURVED WALL AREA -AREA 5 1 1AP27E ASSY -480V AUX BLDG ESF MCC 132X2 Aux 426 426 AREA 5 CURVED WALL AREA 1 1DC03E 125V DC BATT CHGR 111 Aux 451 451 DIV 11 MISC ELEC EQUIP RM (9-1 0/L-M)1 1 DC04E 125V DC BATT CHGR 112 Aux 451 451 DIV 12 MISC ELEC EQUIP RM (9-1 0/M-Q)1 1DC05E 125V DC ESF DISTR CENTER BUS 111 Aux 451 451 DIV 11 MISC ELEC EQUIP RM (9-1 0/L-M)1 1DC06E 125V DC ESF DISTR CENTER BUS 112 Aux 451 451 DIV 12 MISC ELEC EQUIP RM (9-10/M-Q)1 1DC01E 125V DC BATT 111 Aux 451 451 DIV 11 BATTERY RM 111 (6-7.7/L-Q)TRANSFORMER REG INSTRUMENT BUS 112 I 11P02E Aux 451 TRANSFORMER REG INSTRUMENT BUS 114 1 11IP04E Aux 451 ASSY -AOV 1B CNMT CHLR SX BYP VLV 401 AREA 5 CHILLED WTR PUMP RM I 1SX147B Aux 401 (1-5QV 1115/Q-V)RSD DIV 11 CONT PNL 383 U-1 REMOTE SHUTDOWN RM I 1 1 PL04J Aux 383 AE 2-4NP AREA (23-24/N-P) 1 1AB02T-FLOOD Recycle Monitor Tank(s) Aux Table B-1 Page 8 of 35 B-1 0 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION ASSY -AOV 1A CNMT CHLR 1WO01CA SX 401 AREA 5 CHILLED WTR PUMP RM 1 1SX112A SUP VLV Aux 401 (11-15/Q-V)

ASSY -AOV 1B CNMT CHLR 1WOO1CB SX 401 AREA 5 CHILLED WTR PUMP RM 1 1SX112B SUVVAux 401 1-/QV SUP VLV (11-1 5/Q-V)1 1WO006A ASSY -MOV 1A & 1C RCFC WO INLET HDR Aux 401 AREA 5 CURVED WALL AREA OUTSIDE ISOL VLV 1 1W0006B ASSY -MOV 1 B & 1D RCFC CLG COILS WO Aux 401 401 AREA 5 CURVED WALL AREA INLET HDR OUTSIDE CN ASSY -MOV 1A & 1C RCFC WO OUTLET HDR 401 AREA 5 CURVED WALL AREA I 1WO020A Aux 374 OUTSIDE ISOL VLV I 1WO020B ASSY -MOV 1B & 1D RCFC WO OUTLET HDR Aux 401 401 AREA 5 CURVED WALL AREA OUTSIDE ISOL VLV I 1WO056A ASSY -MOV 1A & IC RCFC WO OUTLET HDR Cont 401 +05 (EOP VLV)INSIDE ISOL VLV _____401 01 1WO056B ASSY -MOV 1B & 1D RCFC WO OUTLET HDR Cont 401 +05 (EOP VLV)INSIDE ISOL VLV 01 1VXOIC ASSY -FAN VENT ESF SWGR 12 HVAC M-1 15 Aux 426 426 ESF SWGR RM -DIV 12 M-1285 AB1 1 l'XOlj ESF SWGR RM DIV 11 VENT LOC CONT PNL Aux 426 426 ESF SWGR RM -DIV 11 ESF SWGR RM DIV 12 VENT LOC CONT PNL 426 ESF SWGR RM -DIV 12 1 1VX02J Aux 426 1 1VX04C ASSY -FAN VENT ESF 11 HVAC M-1 15 M-1 285 Aux 426 ESF SWGR RM -DIV 11 2 LCSR+08 ASSY -FAN VENT BUS 131Z HVAC M-119 M- ESWCT 1 1VX05C 18 XTESWCT 888 1288 SXCT 0A SXCT SUBSTA BUS 131Z HVAC LOC CONT ESWCT 1 1VX05J ESWCT 874 PNL 1 1VX06C FAN VENT BUS 132Z HVAC M-1 19 M-1288 ESWCT 888 ESWCT SXCT I 1VX06J OB SXCT SUBSTA BUS 132Z HVAC LOC CONT ESWCT 874 ESWCT PNL I 1VX07J ESF SWGR RM DIV 12 HVAC DMPR START Aux 426 426 ESF SWGR RM -DIV 12 1 _1VX07J _PNL Aux 6 I Table B-1 Page 9 of 35 B-11 Byron Generating Station Unit 1 1200108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION I 1VX08J ESF SWGR RM DIV 11 HVAC DMPR START. Aux 426 426 ESF SWGR RM -DIV 11 PNL 1 1VX98J OA SXCT DIV 11 HVAC DMPR START PNL ESWCT 874 ESWCT 1 1VX99J OB SXCT DIV 12 HVAC DMPR START PNL ESWCT 874 ESWCT 1 1VP01AA RCFC 1A ESW COILS Cont 377 1 1VP01AB RCFC 1B ESW COILS Cont 377 1 1VP01AC RCFC lC ESW COILS Cont 377 1 lVP01AD RCFC 1D ESW COILS Cont 377 I 1VPOICA PRIM. CNMT VENT SYSTEM RCFC FAN, Cont 377 MOTOR__ _ _ _ _ _ _ _ _ _ _1 1VP01CB PRIM. CNMT VENT SYSTEM RCFC FAN, Cont 377 MOTOR 1 1VP0lCC PRIM. CNMT VENT SYSTEM RCFC FAN, Cont 377 MOTOR 1 lVP01CD PRIM. CNMT VENT SYSTEM RCFC FAN, Cont 377 MOTOR 1 1VE01C ASSY -U-1 MISC ELEC EQUIP RM VENT FAN, Aux 463 451 DIV 12 MISC ELEC EQUIP RM (9-BATT RM ROOF 1O/M-Q)1 1VE01J U-1 MISC ELEC EQUIP RM VENT LOC CONT Aux 451 451 DIV 12 MISC ELEC EQUIP RM (9-PNL 1A /M-Q)1 1VE01Y DAMPER MOD FO 30WX72H Aux 451 1 1VE02C ASSY -BATT RM 112 EXH FAN, ROOF Aux 463 451 DIV 12 BATTERY RM 112 (7.7-9/P-Q)1 1VE03C ASSY -BATT RM 111 EXH FAN, ROOF Aux 463 451 DIV 11 BATTERY RM 111 (6-7.7/L-Q)1 1VE04C ASSY -U-1 MISC ELEC EQUIP RM DIV 11 EXH Aux 463 451 DIV 11 MISC ELEC EQUIP RM (9-FAN 1 0/L-M)1 1VE04J U-1 MISC ELEC EQUIP RM DMPR START PNL Aux 451 451 NON-ESF SWGR RM (6-7.7/L-Q)

ASSY -U-1 MISC ELEC EQUIP RM DIV 12 EXH 451 DIV 12 MISC ELEC EQUIP RM (9-I 1VE05C FAN Aux 463 1O/M-Q)1 1VD01CA ASSY -1A DG RM VENT FAN Aux 401 401 1A DG RM (7.7-10/L-Q) 1 1VD01CB ASSY -1B DG RM VENT FAN Aux 401 401 1B DG RM (6-7.7/L-Q) 1 1VD01JA 1A DG RM VENT LOC CONT PNL Aux 401 401 1A DG RM (7.7-10/L-Q) 1 1VD01JB 1B DG RM VENT LOC CONT PNL Aux 401 401 1B DG RM (6-7.7/L-Q)

Table B-1 Page 10 of 35 B-12 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1VD02YA DAMPER MOD FC 53WX52H Aux 401 401 1B DG RM (6-7.7/L-Q) 1 1VD02YB DAMPER MOD FC 33WX52H Aux 401 401 1B DG RM (6-7.7/L-Q) 1 1VD04J 1A DG RM HVAC DMPR START PNL Aux 401 401 1A DG RM (7.7-10/L-Q)

_1 1VD05J 1B DG RM HVAC DMPR START PNL Aux 401 401 1B DG RM (6-7.7/L-Q) 1 1VD08YA DAMPER FIRE SLV-55WX59H 401 1 1VD08YB DAMPER FIRE SLV-55WX59H 401 1 1VD10YA DAMPER MOD FC 53WX52H Aux 401 401 1A DG RM (7.7-10/L-Q) 1 1VD10YB DAMPER MOD FC 53WX52H Aux 401 401 1A DG RM (7.7-10/L-Q) 1 IVD22YA DAMPER FIRE SLV-55WX59H 401 1 IVD22YB DAMPER FIRE SLV-55WX59H 401 1 1VA01SA SX PP AREA 1A CUB CLR Aux 330 330 13-18/L-S SX PUMP RM 1 1VA01SB SX PP AREA 1B CUB CLR Aux 330 330 18-23/L-S SX PUMP RM 1 1VA02SA 1A RH PP CUB CLR Aux 343 346 12-15/U-V A RH PUMP RM -U-1 1 1VA02SB 1B RH PP CUB CLR Aux 343 346 1B RH PUMP RM (13/X)_1 1VA04SA 1A SI PP CUB CLR Aux 364 364 1A SI PUMP RM (15/Q)1 1VA04SB 1B SI PP CUB CLR Aux 364 364 1B SI PUMP RM (13NY)1 1VA06SA 1A CV PP CUB CLR Aux 364 364 1A CV PUMP RM (15-17/U)1 1VA06SB 1B CV PP CUB CLR Aux 379 364 1B CV PUMP RM (13/Y)1 1VA08S 1B DSL DRV AF PP CUB CLR Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1VA08CB ASSY -1B DSL DRVAF PP CUB CLR 1VA08S Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1B FAN 1 1VA01J 1A SX PP CUB CLR LOC CONT PNL Aux 330 330 13-18/L-S SX PUMP RM 1 1VA02J 1B SX PP CUB CLR LOC CONT PNL Aux 330 330 18-23/L-S SX PUMP RM 1 1VA03J 1A RH PP CUB CLR LOC CONT PNL Aux 343 346 12-15/U-VA RH PUMP RM -U-1 1 1VA04J 1B RH PP CUB CLR LOC CONT PNL Aux 343 346 1B RH PUMP RM (13/X)1 1VA10J 1A CV PP CUB CLR LOC CONT PNL Aux 364 364 1A CV PUMP RM (15-17/U)I 1VA11J 1B CV PP CUB CLR LOC CONT PNL Aux 364 364 1B CV PUMP RM (13/Y)1SX001A ASSY -MOV 1A SX PP 1SX01PA SUCT ISOL Aux 346 + (EOP VLV), IN PIT VLV 1SX001B ASSY -MOV 1B SX PP 1SX01PB SUCT ISOL Aux 346 + (EOP VLV), IN PIT VLV 1 1SX01AA 1A SX PP 1SX01PA OIL CLR Aux 330 330 13-18/L-S SX PUMP RM 1 1SX01AB 1B SX PP 1SX01PB OIL CLR Aux 330 330 18-23/L-S SX PUMP RM 1 1SX01FA 1A SX PP DSCH STRN Aux 330 330 13-18/L-S SX PUMP RM 1 1SX01FB 1B SX PP DSCH STRN Aux 330 330 18-23/L-S SX PUMP RM Table B-1 Page 11 of 35 B-1 3 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1 SX01 K 11B AF PP ENG CLSD CYCLE HX. Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1SX01PA ASSY -1A SX PP Aux 330 330 13-18/L-S SX PUMP RM 1 1SX01 PA-C 1A SX PP AUX LUBE OIL PP Aux 330 330 13-18/L-S SX PUMP RM 1 1SX01PA-M 1A SX PP MTR Aux 330 330 13-18/L-S SX PUMP RM 1 1SX01PB ASSY -1B SX PP Aux 330 330 18-23/L-S SX PUMP RM 1 1SX01PB-C 1B SX PP AUX LUBE OIL PP Aux 330 330 18-23/L-S SX PUMP RM 1 1SX01PB-M 1B SX PP MTR Aux 330 330 18-23/L-S SX PUMP RM 1 1SX02K 1B AF PP RHT ANGLE GEAR LUBE OIL CLR Aux 383 383 U-1 AFW PUMP RM (15-18/L-N)

I 1SX101A SOY 1A MTR DRY AF PP OIL CLR 1AF01AA SX Aux 383 383 U-1 AFW PUMP RM (15-18/L-N)

OUTLET VLV ASSY -AOV 1A CNMT CHLR 1WO01CA SX 401 AREA 5 CHILLED WTR PUMP RM I RTRN VLV (11-15/Q-V)

ASSY -AOV 1B CNMT CHLR 1WO01CB SX 401 AREA 5 CHILLED WTR PUMP RM I RTRN VLV (11-15/Q-V) 1 1SX169A ASSY -AOV 1A DG JW HX SX OUTLET VLV Aux 401 401 1A DG RM (7.7-10/L-Q)(EOP VLV)1 1SX169B ASSY -AOV 1 B DG JW HX SX OUTLET VLV Aux 401 401 1 B DG RM (6-7.7/L-Q)

_(EOP VLV)I 1SX173 ASSY -AOV 1B DSL DRV AF PP CLG WTR Aux 383 383 U-1 AFW PUMP RM (15-18/L-N)

I SUP VLV (EOP VLV)1 1SX178 ASSY -AOV 1B AF PP HX'S SX RTRN VLV Aux 383 383 U-1 AFW PUMP RM (15-18/L-N)

,(EOP VLV)ASSY -AOV 1A CNMT CHLR SX BYP VLV 401 AREA 5 CHILLED WTR PUMP RM I 1SX147A Aux 401 (11-15/Q-V) 1 1 FT-S1050 SI PMP COLD INJ ORIFICE LOOP 2 FLOW Cont 412 5__ TRANS SI PMP COLD INJ ORIFICE LOOP 3 FLOW 5 1iFT-SI051 Cont 377 1 TRANS 1 11LS-0940A CONTAINMENT SUMP LEVEL Cont 377 5 1 ILS-0941A CONTAINMENT SUMP LEVEL Cont 377 5 1 1LT-0930 REF WTR STG TK LEVEL D/P XMTTR Aux 379 379 U-1 RWST TUNNEL 1 1LT-0931 REF WTR STG TK LVL D/P XMTTR Aux 379 379 U-1 RWST TUNNEL 1 1 LT-0932 REF WTR STG TK LVL D/P XMTTR Aux 379 379 U-1 RWST TUNNEL 1 1 LT-0933 REF WTR STG TK LVL D/P XMTTR Aux 379 379 U-1 RWST TUNNEL Table B-1 Page 12 of 35 B-14 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1PT-0935 CNMT PRESS XMTTR Cant 451 451 U-1 CURVED WALL AREA -AREA 5 I 1PT-0936 CONT PRESS XMTTR Cant 451 451 U-1 CURVED WALL AREA -AREA 1 5 1 1SI01T U-1 RWST, WOF FHB Out 400 401 FH OUTSIDE 1 ISI05TA SUMP CNMT RECIRC M-61-4 M-195 BOT 367 Cant 377 RX1 SUMP CNMT RECIRC M-61-4 M-195 BOT 367 I 1SI05TB Cant 377 RX1 1 1S18811A ASSY -MOV 1A CNMT RECIRC SUMP Aux 364 364 U-1 AREA 5 CURVED WALL AREA OUTLET ISOL VLV 1 1S18811B ASSY -MOV 1 B CNMT RECIRC SUMP Aux 364 364 U-1 AREA 5 CURVED WALL AREA OUTLET ISOL VLV 1 1S18812A ASSY -MOV 1A RH PP RWST SUCT ISOL VLV Aux 343 346 1A CS PUMP RM (13/V)I 1SI8812B ASSY -MOV 1B RH PP RWST SUCT ISOL VLV Aux 346 1B RH PUMP RM (13/X)1 1S18809A ASSY -MOV 1A RH HX SI OUTLET DWST ISOL Aux 374 +13 (EOP VLV)VLV 01 1S18840 MOV U-1 RH HXS TO 1A/iC LOOP HL ISOL Aux 374 +05 (EOP VLV)VLV 01 1S18801A ASSY -MOV U-1 CV PPS TO CL 1A ISOL VLV Aux 383 U-1 AREA 5 CURVED WALL AREA 1 1S18801 ASSY -MOV U-1 CV PPS TO CL 1 B ISOL VLV Aux 383 U-1 AREA 5 CURVED WALL AREA 1 1LT-0459 PRZR LEVEL D/P TRANSMITTER Cont 377 1 1LT-0460 PRZR LEVEL D/P TRANSMITTER Cont 377 6 1 1LT-0461 PRZR LEVEL D/P TRANSMITTER Cont 377 1 1 PT-0455 PRZR PRESS XMTTR Cont 377 1 PL50J 1 1PT-0456 PRZR PRESS XMTTR Cont 377 6 1 1 PT-0457 PRZR PRESS XMTTR Cont 377 1 PL52J 1 1 PT-0458 PRZR PRESS XMTTR Cont 377 1 PL75J 1 1RY01S U-1 PZR Cont 401 1 1RY01T U-1 PZR RLF TK Cont 377 Table B-1 Page 13 of 35 B-15 Byron Generating Station Unit 1 1200108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 I1RY030A 1A PORV ACCUM 1 RY32MA TO PORV Cant 451 6 1 __1R __030A 1 RY455A RLF VLV Cont_451 1B PORV ACCUM 1RY32MB TO PORV 1 RY456 6 1 1RY030B Cant 451 RLF VLV 1 1RY32MA 1A PORV ACCUM, OUTSIDE PZR WALL Cont 453 1 1 RY32MB 1 B PORV ACCUM, OUTSIDE PZR WALL Cont 453 1 1RY455A ASSY -AOV U-1 PZR PORV (EOP VLV) Cont 461 1 1 1RY455B ASSY -AOV 1D PZR LOOP SPRAY VLV (EOP Cont 390 1 VLV)1 1RY455C ASSY -AOV 1C PZR LOOP SPRAY VLV (EOP Cont 390 1 VLV)1 1 RY456 ASSY -AOV U-1 PZR PORV (EOP VLV) Cont 456 1 1 1RY8000A ASSY -MOV 1A PZR RLF ISOL VLV Cont 461 +01 (EOP VLV)01 IRY8000B ASSY -MOV 1B PZR RLF ISOL VLV Cont 451 +01 (EOP VLV)01 1RY801OA 1A PZR RLFVLV Cont 451 2 1 1RY8010B 1B PZR RLF VLV Cont 451 2 1 1RY801OC 1C PZR RLF VLV Cont 451 2 1 1 RY8028 ASSY -AOV U-1 PRT PW SUP OUTSIDE CNMT Aux 383 U-1 AREA 5 CURVED WALL AREA ISOL VLV (EOP VLV)RH HX 1A OUT I/P TRANSDUCER 364 17-19/Q-W GENERAL AREA -11 IY-0606 Aux AREA4 AREA 6 RH HX #1 B OUT I/P TRANSDUCER 364 17-19/Q-W GENERAL AREA -I1 IY-0607 Aux AREA4 AREA 6 1 1RHI01PA ASSY -1A RH PP Aux 343 346 12-15/U-VA RH PUMP RM -U-1 1 1RH01PA-A 1A RH PP SEAL CLR Aux 343 346 12-15/U-VA RH PUMP RM -U-1 1 1RHI01PB ASSY -1B RH PP Aux 343 346 1B RH PUMP RM (13/X)1 1RHI01PB-A COOLER SEAL RHR PUMP M-62 RXB2 Aux 343 346 1B RH PUMP RM (13/X)1 1RH02AA 1A RH HX Aux 357 364 1A RHR HT EXCH RM (15/S)1 1RH02AB 2B RH HX Aux 357 364 1B RHR HT EXCH RM (15/W)I 1RH61 ASSY -MOV 1A RH PP 1RHI01PA RECIRC VLV Aux 346 15/S GENERAL AREA U-1 I 1RH611 ASSY -MOV 1B RH PP 1RH01PB RECIRC VLV Aux 357 364 1B RHR HT EXCH RM (15/W)1 1RH8701A ASSY -MOV 1A RH PP SUCT FROM 1A HL Cont 377 +03 (EOP VLV)DWST ISOL VLV Table B-1 Page 14 of 35 B-16 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 01 1RH8701B ASSY -MOV 1A RH PP SUCT FROM 1A HL Cont 377 +13 (EOP VLV)UPST ISOL VLV 01 1 RH8702A ASSY -MOV 1B RH PP SUCT FROM IC HL Cont 377 +b3 (EOP VLV)DWST ISOL VLV 01 1RH8702B ASSY -MOV 1B RH PP SUCT FROM 1C HL Cont 377 +13 (EOP VLV)UPST ISOL VLV 01 1RH8716A ASSY -MOV 1A RH HX 1 RH02AA OUTLET Aux 364 364 U-1 AREA 5 CURVED WALL AREA ISOL VLV ASSY -MOV 1 B RH HX 1 RH02AB OUTLET 364 U-1 AREA 5 CURVED WALL AREA 1 1RH8716B Aux 364 ISOL VLV ________1 1TE-0604 RHR LP 1A RETURN RTD Aux 364 U-1 AREA 5 CURVED WALL AREA 1 1TE-0605 PLATINUM RTD RHR LP 2 RETURN Aux 364 364 U-1 AREA 5 CURVED WALL AREA AOV U-1 RF PPS DSCH HDR INSIDE CNMT 13 1 1 RF026 Cont 377 ISOL VLV 1 1 RF027 AOV U-1 RF PPS DSCH HDR OUTSIDE CNMT Aux 383 U-1 AREA 5 CURVED WALL AREA ISOL VLV S1RE9170 AOV U-1 RCDT PPS DSCH HDR OUTSIDE Aux 401 401 AREA 5 CURVED WALL AREA CNMT ISOL VLV W-RNG RX COOLANT PRESS LP 1A HOT LEG 364 U-1 AREA 5 CURVED WALL AREA 1 1 PT-0403 Aux 364 XMTTR 1 1 PT-0405 W-RNG RX COOLANT PRESS LP 1C HOT LEG Aux 364 364 U-1 AREA 5 CURVED WALL AREA XMTTR I 1PT-0406 RC HOT LEG WIDE RANGE PRESSURE Cont 1PL75J TRANSMITTER RC HOT LEG WIDE RANGE PRESSURE 1PL66J 1 1PT-0407 Cont 377 TRANSMITTER 1 1RC01BA STEAM GENERATOR 1A Cont 390 1 1RC01BB STEAM GENERATOR 1B Cont 390 1 1RC01BC STEAM GENERATOR IC Cont 390 1 1RC01BD STEAM GENERATOR 1D Cont 390 1 IRC01PA REACTOR COOLANT PUMP 1A Cont 390 1 1RC01PB REACTOR COOLANT PUMP 1B Cont 390 1 1RC01PC REACTOR COOLANT PUMP IC Cont 390 Table B-1 Page 15 of 35 B-1 7 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1 RC01 PD REACTOR COOLANT PUMP 1D Cont 390 1 1RC01R U-1 RX VESSEL Cont 400 1 1 RC8001A ASSY -MOV 1A RC LOOP HL STOP VLV Cont 401 + BY 1A S/G 01 1 RC8001 B ASSY -MOV 1 B RC LOOP HL STOP VLV Cont 401 + BY 1B S/G 01 1RC8001C ASSY -MOV IC RC LOOP HL STOP VLV Cont 401 + BY 1C S/G 01 1RC8001D ASSY -MOV 1D RC LOOP HL STOP VLV Cont 401 + BY 1D S/G 01 1RC8002A ASSY -MOV 1A RC LOOP CL STOP VLV Cont 401 +1 1RC8002B ASSY -MOV 1B RC LOOP CL STOP VLV Cont 401 1 1 1RC8002C ASSY -MOV IC RC LOOP CL STOP VLV Cont 401 1 1 1RC8002D ASSY -MOV 1D RC LOOP CL STOP VLV Cont 401 +1 1TE-RC022A RC WIDE RANGE LP 1A TEMP Cont 390 3 1 1TE-RC022B RC WIDE RANGE LP 1A TEMP Cont 390 3 1 1TE-RC023A RC WIDE RANGE LP 1B TEMP Cont 390 3 1 1TE-RC023B RC WIDE RANGE LP 1 B TEMP Cont 390 3 1 1TE-RC024A RC WIDE RANGE LP 1C TEMP Cont 390 3 1 1TE-RC024B RC WIDE RANGE LP 1C TEMP Cont 390 5 1 1TE-RC025A RC WIDE RANGE LP 1D TEMP Cont 390 3 1 1TE-RC025B RC WIDE RANGE LP 1D TEMP Cont 390 3 RSD DIV 12 CONT PNL 383 U-1 REMOTE SHUTDOWN RM /I PAREA (23-24/N-P) 1 1PL07J 1A DG 1DG01KA CONT PNL Aux 401 401 1A DG RM (7.7-10/L-Q) 1 1PL08J 1B DG 1DG01KB CONT PNL Aux 401 401 1B DG RM (6-7.7/L-Q) 1 1PL10J U-1 PEN AREA FIRE HAZARDS PANEL Aux 426 426 AREA 5 CURVED WALL AREA 1 1PL50J RXl CNMT LOC INST PNL Cont 377 1 1PL52J RX1 CNMT LOC INST PNL Cont 377 1 1PL56J RXI CNMT LOC INST PNL Cont 412 1 1PL57J RX1 CNMT LOC INST PNL Cont 412 1 1PL66J RXl CNMT LOC INST PNL Cont 377 1 1PL67J RXI CNMT LOC INST PNL Cont 377 1 1PL69J RXI CNMT LOC INST PNL Cont 401 1 1PL71J RXI CNMT LOC INST PNL Cont 412 1 1PL72J RXl CNMT LOC INST PNL Cont 412 1 1PL75J RXI CNMT LOC INST PNL Cont 377 1 1PL77JC 1 B SAFETY VLV RM LOC INST PNL Aux 377 377 U-1 MSIV RM B/C 1 1PL79JB 1A SAFETY VLV RM LOC INST PNL Aux 377 377 U-1 MSIV RM ND Table B-1 Page 16 of 35 B-18 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1PL84JB LOC INST PNL Aux 364 383 GENERAL AREA (12-15/N-Q)

I A PL86J LOC INST PNL 364 17-19/Q-W GENERAL AREA -AREA 6 1 A PL97J LOC INST PNL 364 17-19/Q-W GENERAL AREA-I AREA 6 1 1PL84JA LOC INST PNL Aux 364 383 GENERAL AREA (12-1 5/N-Q)1 1NR11E NEUTRON DETECTOR Cont 377 6 1 1NR13E NEUTRON DETECTOR Cont 377 6 1 1MS001A ASSY -HOV 1A S/G MS ISOL VLV Aux 377 377 U-1 MSIV RM A/D 1 1MS001B ASSY -HOV 1B S/G MS ISOL VLV Aux 377 377 U-1 MSIV RM B/C 1 1MS001C ASSY -HOV iC S/G MS ISOL VLV Aux 377 377 U-1 MSIV RM B/C 1 1MS001D ASSY -HOV 1D S/G MS ISOL VLV Aux 377 377 U-1 MSIV RM A/D 1 1MS013A 1A S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM A/D 1 IMS013B 1B S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM B/C 1 1MS013C iC S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM B/C 1 1MS013D 1 D S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM A/D 1 1MS014A 1A S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM A/D 1 lMS014B 1B S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM B/C 1 lMS014C lC S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM B/C 1 IMS014D 1D S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM A/D 1 1MS015A 1A S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM A/D 1 1 MS01 5B 1 B S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM B/C 1 1MS015C lC S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM B/C 1 1MS015D 1D S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM A/D 1 1MS016A 1A S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM A/D 1 lMS016B 1 B S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM B/C 1 1MS016C 1C S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM B/C 1 1MS016D 1D S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM ND 1 lMS017A 1A S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM A/D 1 1MS017B 1B S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM B/C 1 lMS017C lC S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM B/C 1 1MS017D 1D S/G MS OUTLET HDR ATMOS RLF VLV Aux 401 401 U-1 MSIV RM A/D 1 1MS018A ASSY -HOV 1A S/G MS PORV Aux 401 401 U-1 MSIV RM A/D 1 1MS018B ASSY -HOV 1B S/G MS PORV Aux 401 401 U-1 MSIV RM B/C 1 1MS018C ASSY -HOV lC S/G MS PORV Aux 401 401 U-1 MSIV RM B/C Table B-1 Page 17 of 35 B-1 9 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1MS018D ASSY -HOV 1D S/G MS PORV Aux 401 401 U-1 MSIV RM A/D TRANSFORMER REG INSTRUMENT BUS 111 1 11P01E Aux 451 1 11P01J PANEL DIST INSTRUMENT BUS 111 120VAC Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 11P02J PANEL DIST INSTRUMENT BUS 112 120VAC Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)I 1IIP03E TRANSFORMER REG INSTRUMENT BUS 113 Aux 451 1 11P03J PANEL DIST INSTRUMENT BUS 113 120VAC Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 11P04J PANEL DIST INSTRUMENT BUS 114 120VAC Aux 451 451 U-1 AUX ELEC EQUIP RM (11-13/N-Q)1 1 LT-0501 SG LOOP 1A W-RNG LEVEL D/P XMTTR Cont 377 1 PL50J I 1LT-0502 SG LOOP 1 B W-RNG LEVEL D/P Cant 377 1 PL67J TRANSMITTER I 1LT-0503 SG LOOP 1C W-RNG LEVEL D/P Cant 377 1PL75J TRANSMITTER 1 1 LT-0504 SG LOOP 1D W-RNG LEVEL DIP Cant 377 1PL52J TRANSMITTER S/G LOOP 1A LEVEL DIP XMTTR W/FILLED I 1LT-0517 Cant 401 LEG I 1 T-0518 S/G 1A LEVEL LOOP D/P XMTTR 2/FILLED Cant 412 LEG I 1ILT-0519 S/G LOOP LA LEVEL D/P XMTTR W/FILLED Cant 412 1_ LEG S/G LOOP 1B LEVEL D/P TRANSMITTER 1 1 LT-0527 Cant 377 1_ W/FILLED LEG I 1 LT-0528 S/G 1B LEVEL D/P TRANSMITTER W/FILLED Cant 412_ _LEG I 1 LT-0529 S/G LOOP 1B LEVEL D/P XMTTR W/FILLED Cant 412 1_ LEG ITILT-0537 S/G LP IC LVL D/P TRANSMITTER W/FILLED Cant 377 1 __ __1LT_ L G 0537____ __Cont__ __ __377_ __Table B-1 Page 18 of 35 B-20 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION I 1iLT-0538 S/G 1C LEVEL LOOP D/P XMITTER W/FILLED Cont 412 LEG__ _ _ __ _ _ _S/G LP 1C LVL D/P TRANSMITTER W/FILLED I LT-0539 Cont 412 LEG 1 1ILT-0547 S/G LP 1D LVL D/P TRANSMITTER W/FILLED Cont 401 LEG 1 1 LT-0548 S/G 1 D LEVEL LOOP DIP XMTTR W/FILLED Cont 412 LEG I 1iLT-0549 S/G 1D LVL LOOP D/P TRANSMITTER Cont 412 I 1LT-0556 S/G LOOP 1A LEVEL D/P TRANSMITTER Cont 412 W/FILLED LEG S/G I B LEVEL LIP D/P TRANSMITTER I LT-0556 Cont 412 W/FILLED LEG I 1lLT-0558 S/G LOOP IC LEVEL D/P TRANSMITTER Cont 412 W/FILLED LEG I 1 LT-0559 S/G LOOP 10 LEVEL D/P TRANSMITTER Cont 412 W/FILLED LEG I 1 PT-0514 S/G LOOP 1A STM PRESS TRANSMITTER Aux 377 377 U-i MSIV RM ND I IPT-0515 S/G LOOP IA STM PRESS PRESS XMTTR Aux 377 377 U-i MSIV RM A/D S1WPT-0516 S/G LOOP ALSTM PRESS XMTTR Aux 377 377 U-I MSIVRMA/D 1 1PT-0524 S/G LOOP 1B STM PRESS XMTTR Aux 377 377 U-1 MSIV RM B/C 1 1 PT-0525 S/G LOOP 1 B STM PRESS PRESS XMTTR Aux 377 377 U-1 MSIV RM B/C 1 1PT-0526 S/G LOOP 1B STM PRESS XMTTR Aux 377 377 U-1 MSIV RM B/C 1 1PT-0534 S/G LP 1C STM PRESS XMTTR Aux 377 377 U-1 MSIV RM B/C 1 1PT-0535 S/G LP 1C STM PRESS PRESSURE XMTTR Aux 377 377 U-1 MSIV RM B/C 1 1PT-0536 S/G LO 1C PRES PRESS TRANSMITTER Aux 377 377 U-1 MSIV RM B/C 1 1PT-0544 S/G LP 1D STM PRESS PRESSURE XMTTR Aux 377 377 U-1 MSIV RM B/D 1 1PT-0545 S/G LOOP ID STM PRESS XMTTR Aux 377 377 U-1 MSIV RM B/D 1 1PT-0546 S/G LP 1D STM PRESS XMTTR Aux 377 377 U-1 MSIV RM A/D 1 1 FW009A HOV 1A S/G FW ISOL VLV Aux 377 377 U-1 MSIV RM A/D 1 1FW009B HOV 1B S/G FW ISOL VLV Aux 377 377 U-1 MSIV RM B/C 1 1FW009C HOV 1C S/G FW ISOL VLV Aux 377 377 U-1 MSIV RM B/C 1 1FW009D HOV 1D S/G FW ISOL VLV Aux 377 377 U-1 MSIV RM A/D Table B-1 Page 19 of 35 B-21 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1FW035A AOV 1A S/G FW TEMPERING LINE DWST ISOL Aux 377 377 U-1 MSIV RM A/D VLV (EOP VLV)AOV 1 B S/G FW TEMPERING LINE DWST ISOL 377 U-1 MSIV RM B/C 1 1FW035B Aux 377 VLV (EOP VLV)I I FW035C AOV IC S/G FWTEMPERING LINE DWST Aux 377 U-1 MSIV RM B/C ISOL VLV (EOP VLV)1 1 FW035D AOV 1 D S/G FW TEMPERING LINE DWST Aux 377 U-1 MSIV RM AND ISOL VLV (EOP VLV)1 1FP010 AOV RXl CNMT FP SUP ISOL VLV (EOP VLV) Aux 374 383 U-1 AREA 5 CURVED WALL AREA I 1D001PA ASSY -1A DG 1A FO XFER PP Aux 383 U-1 DIESEL OIL STORAGE TANK RMS (6-8/L-P)ASSY -1B DG 1B FO XFER PP 383 U-1 DIESEL OIL STORAGE TANK 1 1IDO01PB Aux 373 RMS (6-8/L-P)ASSY -1A DG 1C FO XFER PP 383 U-1 DIESEL OIL STORAGE TANK RMS (6-8/L-P)ASSY -1B DG 1D FO XFER PP 383 U-1 DIESEL OIL STORAGE TANK RMS (6-8/L-P)1 1DO01TA 1A DO STO TK, 25,000 GAL Aux 373 383 U-1 DIESEL OIL STORAGE TANK RMS (6-8/L-P)1 1DO01TB 1B DO STO TK, 25,000 GAL Aux 373 383 U-1 DIESEL OIL STORAGE TANK RMS (6-8/L-P)1 1DO01TC lC DO STO TK, 25,000 GAL Aux 373 383 U-1 DIESEL OIL STORAGE TANK RMS (6-8/L-P)1 1DO01TD 1D DO STO TK, 25,000 GAL Aux 373 383 U-1 DIESEL OIL STORAGE TANK RMS (6-8/L-P)1 1DO02TA 1A DG FO DAY TK, 500 GAL Aux 401 401 1A DG RM (7.7-10/L-Q) 1 1DO02TB 1B DG FO DAY TK Aux 401 401 1B DG RM (6-7.7/L-Q) 1 1DO10T U-1 DO DAY TK, 500 GAL Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1DO12MA EXHAUST SILENCER Aux 477 477 ROOF OF 1A & 1 B DG RMS (6-IA 10/L-Q)1 1DO12MB EXHAUST SILENCER Aux 477 477 ROOF OF 1A & 1B DG RMS (6-1DA 1 0/L-Q)1 1DG01EA 1A DG GENERATOR Aux 401 401 1A DG RM (7.7-10/L-Q) 1 IDG01EB 1B DG GENERATOR Aux 401 401 1B DG RM (6-7.7/L-Q)

Table B-1 Page 20 of 35 B-22 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1DG01KA ASSY -1A DG DSL ENGINE Aux 401 401 1A DG RM (7.7-10/L-Q) 1 1DG01KB ASSY -1B DG DSL ENGINE Aux 401 401 1B DG RM (6-7.7/L-Q) 1 lDG01SA AIR COMPRESSOR PACKAGE 1A Aux 401 401 1A DG RM (7.7-1 0/L-Q)1 IDG18MA INTAKE SILENCER Aux 401 401 1A DG RM (7.7-10/L-Q) 1 1DG18MB INTAKE SILENCER Aux 401 401 1B DG RM (6-7.7/L-Q) 1 1DG19MA FILTER AIR INTAK 1DG01KA M-152-17 Aux 401 401 1A DG RM (7.7-10/L-Q) 1 1DG19MB FILTER AIR INTAK 1DG01KB M-152-17 Aux 401 401 1B DG RM (6-7.7/L-Q)

DIESEL GENERATOR 1A SYNCHRO-CHECK 426 ESF SWGR RM -DIV 11 I IDG04EA RLYBXAux 426 RELAY BOX I lDG04EB DIESEL GENERATOR 1B SYNCHRO-CHECK Aux 426 426 ESF SWGR RM -DIV 12 RELAY BOX 1DC10J 125V DC FUSE PNL ESF 11 Aux 451 451 DIV 11 MISC ELEC EQUIP RM (9-10/L-M)1DC11J 125V DC FUSE PNL ESF 12 Aux 451 451 DIV 12 MISC ELEC EQUIP RM (9-10/M-Q)1 1CV01FA 1A CV SEAL WTR INJ FLTR Aux 391 383 GENERAL AREA (12-15/N-Q) 1I 1CV01FB 1B CV SEAL WTR INJ FLTR Aux 391 383 GENERAL AREA (12-15/N-Q) 1 1CV01PA ASSY -1A CV CENT CHG PP Aux 364 364 1A CV PUMP RM (15-17/U)1 1CV01PA-A 1A CV CENT CHG PP AUX LUBE OIL PP Aux 364 364 1A CV PUMP RM (15-17/U)1 1CV01PB ASSY -1B CV CENT CHG PP Aux 364 364 1B CV PUMP RM (13/Y)1 1CV01 PB-A 1B CV CENT CHG PP AUX LUBE OIL PP Aux 364 364 1B CV PUMP RM (13/Y)1 1 CV02A U-1 CV SEAL WTR HX Aux 383 383 U-1 SEAL WTR HT EXCH RM (15-17/U)1 1CV02F U-1 CV SEAL WTR RTRN FLTR Aux 391 383 GENERAL AREA (12-15/N-Q) 1 1CV02SA 1A CV CENT CHG PP GEAR CLR Aux 364 364 1A CV PUMP RM (15-17/U)1 1CV02SB 1B CV CENT CHG PP GEAR CLR Aux 364 364 1B CV PUMP RM (13/Y)1 lCV03SA 1A CV PP LUBE OIL CLR Aux 364 364 1A CV PUMP RM (15-17/U)1 1CV03SB 1B CV PP LUBE OIL CLR Aux 364 364 1B CV PUMP RM (13/Y)ASSY -MOV U-1 VCT OUTLET UPST ISOL VLV 426 AREA 6 GENERAL AREA U-1/2 IlCV1 12B Aux 426 VTTN M I VCT TANK RMS ASSY -MOV U-1 VCT OUTLET DWST ISOL 426 AREA 6 GENERAL AREA U-1/2 VLV VCT TANK RMS I 1CV112D ASSY -MOV RWST TO U-1 CHG PPS SUCT Aux 364 364 U-1 AREA 5 CURVED WALL AREA ISOL VLV III Table B-1 Page 21 of 35 B-23 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION ASSY -AOV U-1 RC CL LOOP 3 LTDWN 2ND 2 I 1CV459 Cont 412 ISOL VLV (EOP VLV)ASSY -AOV U-1 RC CL LOOP 3 LTDWN 1ST 12 I ISOL VLV (EOP VLV) Con_37 I 1CV81 ASSY -MOV U-1 RC PPS SEAL L/O HDR Aux 383 U-1 AREA 5 CURVED WALL AREA 1__ 180OUTSIDE CNMT ISOL VLV Aux 37 I 1CV8105 ASSY -MOV U-1 CV CHG PPS DSCH HDR Aux 364 U-1 AREA 5 CURVED WALL AREA DWST ISOL VLV 1 1CV8106 ASSY -MOV U-1 CV CHG PPS DSCH HDR Aux 364 U-1 AREA 5 CURVED WALL AREA UPST ISOL VLV 1 1 CV81 10 ASSY -MOV 1 B CV PP MINIFLOW ISOL VLV Aux 364 364 U-1 AREA 5 CURVED WALL AREA I 1CV81 11 ASSY -MOV 1A CV PP MINIFLOW ISOL VLV Aux 364 364 U-1 AREA 5 CURVED WALL AREA 1 1lCV8112 ASSY -MOV U-1 RC PPS SEAL L/O HDR Cont 377 +18 (EOPVLV)INSIDE CNMT ISOL VLV 01 1CV8114 SOV 1A CV PP ESF MINIFLOW ISOL VLV (EOP Aux 364 364 U-1 AREA 5 CURVED WALL AREA VLV)I 1CV8116 SOV 1 B CV PP ESF MINIFLOW ISOL VLV (EOP Aux 364 364 U-1 AREA 5 CURVED WALL AREA 1 __ICV8116

_ VLV)1 1CV8804A ASSY -MOV 1A RH HX TO U-1 CV PPS SUCT Aux 364 364 U-1 AREA 5 CURVED WALL AREA I HDR ISOL VLV 1 1 FT-0121 CHARGING LINE D/P CELL FLOW XMTTR Aux 364 364 17-19/Q-W GENERAL AREA -AREA 6 1 1 FT-0132 LETDN FLOW D/P CELL Aux 383 383 GENERAL AREA -AREA 6 (17-19/Q-W)1 1FT-0139 LOOP FILL HEADER FLOW XMTTR Aux 383 383 GENERAL AREA -AREA 6 (17-19/Q-W)1 1CV02P-C U-1 CV PD CHG PP FLUID DRIVE OIL CLR Aux 364 364 PDP PUMP RM (15/U)1A CV LTDWN HX 383 U-1 LETDOWN HT EXCH RM (15-I 1CV04AA Aux 383 17UV 17/U-V)1 B CV LTDWN HX 383 U-1 LETDOWN HT EXCH RM (15-1 1 CV04AB Aux 383 17/U-V)1 1CV8160 ASSY -AOV U-1 LTDWN ORIFICES OUTLET Cont 15 HDR ISOL VLV (EOP VL Table B-1 Page 22 of 35 B-24 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1CO01J C02 FP AREA 1S2 LOC CONT CAB Aux 401 401 1A DG RM (7.7-10/L-Q) 1 1CO02J C02 FP AREA 1S4 LOC CONT CAB Aux 401 401 1A DG RM (7.7-10IL-Q) 1 1CO03J C02 FP AREA 1S1 LOC CONT CAB Aux 401 401 1B DG RM (6-7.7/L-Q) 1 1CO04J C02 FP AREA 1S3 LOC CONT CAB Aux 401 401 1B DG RM (6-7.7/L-Q) 1 1CO17JA 1A DG RM FIRE DMPR CONT PNL Aux 401 401 1A DG RM (7.7-1 0/L-Q)1 1CO17JB 1B DG RM FIRE DMPR CONT PNL Aux 401 401 1B DG RM (6-7.7/L-Q) 1 1CO19JA IU-1 LCSR & CBL TNL FIRE DMPR CONT PNL Aux 401 401 1A DG RM (7.7-10/L-Q) 1 1CO19JB U-1 LCSR FIRE DMPR CONT PNL Aux 439 439 GENERAL AREA (17/Q)1 1C020J U-1 UCSR FIRE DMPR CONT PNL Aux 426 426 GENERAL AREA -AREA 2 & 3 (10-1 C21/L-Q)1 1CC01A U-1 CC HX Aux 364 364 15-21/L-Q GENERAL AREA 1 1CC01T U-1 CC SURGE TK Aux 426 426 GENERAL AREA -AREA 2 & 3 (10-21/L-Q)1l1 CC053 SOVAOV U-1 PEN CLG SUP FCV-CBL# Cont 377 +16 (1HS-CC070) 1 CC226 I 1CC9437B ASSY -AOV U-1 EXC LTDWN HX CC RTRN Aux 383 U-1 AREA 5 CURVED WALL AREA_VLV (EOP VLV)RESID HT EXCH 1B CCW OUT DP FLOW 364 17-19/Q-W GENERAL AREA -1 1 FT-0688 XTRAux 364 AE XMTTR AREA 6 1 1FT-0689 RESID HX 1A CCW OUT DP FLOWXMTTR Aux 364 364 15-21/L-Q GENERAL AREA ASSY -MOV 1A RH HX 1 RH02AA CC OUTLET 364 17-19/Q-W GENERAL AREA -1 1 CC9412A ILVVAux 364 AE ISOL VLV AREA 6 ASSY -MOV 1 B RH HX 1 RH02AB CC OUTLET 364 17-19/Q-W GENERAL AREA -1 1CC9412B ISOLVLV Aux 364 AREA 6 1 1AP05E ASSY -4160V ESF SWGR 141 Aux 426 426 ESF SWGR RM -DIV 11 1 1AP06E ASSY -4160V ESF SWGR 142 Aux 426 426 ESF SWGR RM -DIV 12 1 1AP12E ASSY -480V ESF SWGR 132X Aux 426 426 ESF SWGR RM -DIV 12 1 1AP22E ASSY -480VAUX BLDG ESF MCC 131X3 Aux 383 383 15-21/N-Q GENERAL AREA 1 1AP23E ASSY -480V AUX BLDG ESF MCC 132X1 Aux 364 364 15-21/L-Q GENERAL AREA 1 1AP24E ASSY -480V AUX BLDG ESF MCC 132X3 Aux 383 383 15-21/N-Q GENERAL AREA 1 1AP26E ASSY -480V AUX BLDG ESF MCC 131X4 Aux 414 414 CURVED WALL AREA -AREA 5 1 1AP28E ASSY -480V AUX BLDG ESF MCC 132X4 Aux 426 426 AREA 5 CURVED WALL AREA ASSY -480V AUX BLDG ESF MCC 131X5 426 GENERAL AREA- AREA 2 & 3 (10 I 1AP30E IAux 426 21/L-Q)Table B-1 Page 23 of 35 B-25 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1AP32E ASSY -480V AUX BLDG ESF MCC 132X5 Aux 426 426 GENERAL AREA -AREA 2 & 3 (10-21/L-Q)1 1AP39E ASSY -480V AUX BLDG MCC 134V1 Aux 346 346 10-18/L-N GENERAL AREA 1 1AF006B ASSY -MOV 1 B AF PP SX SUCT DWST ISOL Aux 383 383 U-1 AFW PUMP RM (15-18/L-N)

VLV I 1AF017A ASSY -MOV 1AAF PP SX SUCT UPST ISOL Aux 383 383 U-1 AFW PUMP RM (15-18/L-N)

VLV 1 1AF01AA 1A MTR DRV AF PP OIL CLR Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01AB 1B DSL DRVAF PP OIL CLR Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AFOlEA-1 1B DSL DRV AF PP 1B BATT CHGR Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01EA-A 1B DSL DRV AF PP #1 BATT Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AFO1EA-B 1B DSL DRV AF PP #1A BATT Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AFOlEB-1 1B DSL DRV AF PP 1B BATT CHGR Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01EB-A 1B DSL DRV AF PP #2 BATT Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AFOlEB-B 1B DSL DRV AF PP #2A BATT Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01J 1B DSL DRVAF PP STARTUP CONT PNL Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01PA ASSY -1A MTR DRVAF PP Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01PA-A 1A MTR DRV AF PP AUX LUBE OIL PP Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01PA-L 1A MTR DRV AF PP MAIN LUBE OIL PP Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01PA-M 1A MTR DRVAF PP MOTOR Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01PB ASSY- 1B DSL DRV AF PP Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01PB-A 1B DSL DRV AF PP AUX LUBE OIL PP Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01PB-B 1B DSL DRV AF PP CONT JB Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01PB-K 1B DSL DRV AF PP DIESEL ENGINE Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF01PB-L 1B DSL DRV AF PP MAIN LUBE OIL PP Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1AF02A 1B DSL DRV AF PP GEAR OIL CLR Aux 383 383 U-1 AFW PUMP RM (15-18/L-N) 1 1FT-AF011 AUX FWTO SG 1A FLOW XMTTR Aux 364 364 10-15/N-Q GENERAL AREA 1 1FT-AF012 AUX FWTO SG 1A FLOW XMTTR Aux 364 364 10-15/N-Q GENERAL AREA 1 1FT-AF013 AUX FWTO SG 1B FLOW XMTTR Aux 364 364 10-15/N-Q GENERAL AREA 1 1FT-AF014 AUX FWTO SG 1B FLOW XMTTR Aux 364 364 10-15/N-Q GENERAL AREA 1 1FT-AF015 AUX FWTO SG lC FLOW XMTT-R Aux 364 364 10-15/N-Q GENERAL AREA I 1FT-AF016 AUX FWTO SG 1C FLOW XMTTR Aux 364 364 10-15/N-Q GENERAL AREA 1 1FT-AF017 AUX FWTO SG 1D FLOW XMTTR Aux 364 364 10-15/N-Q GENERAL AREA 1 1FT-AF018 AUX FWTO SG 1D FLOW XMTTR Aux 364 364 10-15/N-Q GENERAL AREA Table B-1 Page 24 of 35 B-26 Byron Generating Station Unit 1 12QO108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1PL06J REMOTE CONTROL PANEL (Remote Shutdown Aux 383 383 U-1 REMOTE SHUTDOWN RM /Panel) AREA (23-24/N-P) 1 1WO007A ISOLATION VALVE -CHECK VALVE Cont 401 7 1 1WO007B ISOLATION VALVE -CHECK VALVE Cont 401 2 1 1WM191 ISOLATION VALVE -CHECK VALVE Cont 377 12 I 1WE010A SX STRAINER DRAIN MANUAL ISOLATION Aux 330 1 VALVE I 1WE010B SX STRAINER DRAIN MANUAL ISOLATION Aux 330 VALVE 1 1VX01Y DAMPER MOD FO 40WX56H Aux 426 1 1VX04Y DAMPER MOD FO 72WX46H Aux 426 1 1VX30Y DAMPER MOD FC 24WX36H ESWCT 888 1 1VX31Y DAMPER ISO FC 48WX24H ESWCT 874 1 1VX33Y DAMPER MOD FC 24WX36H ESWCT 888 1 1VX34Y DAMPER ISO FC 48WX24H ESWCT 874 I 1VQ003 AOV U-1 POST LOCA PURGE FLTR INLET VLV Aux 467 6 1 (EOP VLV)I 1VQ004A AOV U-1 MINIFLOW PURGE SUP INSIDE ISOL Cont 6 1_ VLV AOV U-1 MINIFLOW PURGE SUP OUTSIDE 12 IlVQ004B ILLVAux 451 ISOL VLV 1 1VQ005A AOV U-1 MINIFLOW PURGE EXJ INSIDE ISOL Cont 471 3 VLV I 1VQ005B AOV U-1 MINIFLOW PURGE EXH OUTSIDE Aux 467 1_ UPST ISOL VLV (EOP VLV I 1I1 V0005C AOV U-1 MINIFLOW PURGE EXH OUTSIDE Aux 467 DWST ISOL VLV (EOP VLV 1 1VD01YA DAMPER MOD FO 72WX48H Aux 401 1 1VD01YB DAMPER MOD FO 72WX48H Aux 401 1 lVD09YA DAMPER MOD FO 72WX48H Aux 401 1 1VD09YB DAMPER MOD FO 72WX48H Aux 401 1 IVD16YA DAMPER FIRE SLV-60WX43H Aux 401 1 1VD16YB DAMPER FIRE SLV-60WX43H Aux 401 1 1VD17YA DAMPER FIRE SLV-55WX59H Aux 401 1 1VD17YB DAMPER FIRE SLV-55WX59H Aux 401 Table B-1 Page 25 of 35 B-27 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1VD23YA DAMPER FIRE SLV-60WX43H Aux 401 1 1VD23YB DAMPER FIRE SLV-60WX43H Aux 401 1 1VD24YA DAMPER FIRE SLV-55WX59H Aux 401 1 1VD24YB DAMPER FIRE SLV-55WX59H Aux 401 1 1SX004 ASSY -MOV U-1 CC HX 1CC01A SX SUP ISOL Aux 330 11 VLV 1 1SX005 ASSY -MOV U-0 CC HX OCC01A SX SUP ISOL Aux 330 +06 (EOP VLV)I_ VLV 01 1 SX007 ASSY -MOV U-1 CC HX 1CC01A SX OUTLET Aux 346 +13 (EOP VLV)ISOL VLV 01 1SX010 ASSY -MOV SXCT BASIN 1A RTRN HDR ISOL Aux 346 +07 (EOP VLV)VLV 01 1SX011 ASSY -MOV SXCT BASIN 1A/1B RTRN HDR Aux 346 +07 (EOP VLV)XTIE ISOL VLV 01 1SX016A ASSY -MOV 1A & 1C RCFC SX SUP ISOL VLV Aux 374 +29 (EOP VLV), P-15 01 1SX016B ASSY -MOV 1 B & 1 D RCFC SX SUP ISOL VLV Aux 401 +02 (EOP VLV), P-7 01 1SX027A ASSY -MOV 1A & 1C RCFC SX RTRN HDR Aux 374 +29 (EOP VLV), P-14 ISOL VLV 01 1SX027B ASSY -MOV 1B & 1D RCFC SX RTRN HDR Aux 401 +02 (EOP VLV), P-9 ISOL VLV 01 1SX104A U-1 DG'S JW HXS SX SUP HDR XTIE ISOL VLV Aux 401 14 1 1SX150A ASSY -MOV 1A SX STRN BKWH OUTLET TO Aux 330 1 TR SYS ISOL VLV ASSY -MOV 1B SX STRN BKWH OUTLET TO 1 1 1SX150B Aux 330___ ________TR SYS ISOL VLV____I 1SX168 ASSY -AOV 1B AF PP CUB CLR 1VA08S SX Aux 383 10 OUTLET VLV 1 1SX192A 1A SX PP DSCH HYPO SUP CHK VLV Aux 330 12 1 1SX192B 1 B SX PP DSCH HYPO SUP CHK VLV Aux 330 10 1 1SX194 AF PPS RECIRC RTRN TO SX CHK VLV Aux 383 11 I 1SX243 1A AF PP SX SUCT FLUSH CONN 2ND ISOL 383 7 jVLV Table B-1 Page 26 of 35 B-28 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1SX033 MOV 1A SX PP DSCH HDR XTIE ISOL VLV Aux 330 +05 (EOP VLV)01 1 SX034 MOV 1 B SX PP DSCH HDR XTIE ISOL VLV Aux 330 +05 (EOP VLV)U-1 DG'S JW HXS SX RTRN HDR XTIE ISOL 8 01 1SXIO4B Aux 401 VLV U-1 DG'S JW HXS SX SUP HDR XTIE ISOL VLV 14 1 1 SX 105A Aux 401 1 1SX105B U-1 DG'S JW HXS SX RTRN HDR XTIE ISOL Aux 401 8 VLV ASSY -MOV SX BASIN 1B RTRN HDR ISOL 7 I 1SX136 Aux 346 VLV 1 1SI8804B ASSY -MOV 1 B RH HX TO 1 B SI PP SUCT Aux 364 +15 (EOP VLV)HDR ISOL VLV 01 1SI8807A ASSY -MOV SI TO U-1 CV PPS SUCT HDR 1A Aux 364 +02 (EOP VLV)XTIE ISOL VLV 01 1SI8807B ASSY -MOV SI TO U-1 CV PPS SUCT HDR 1B Aux 364 +03 (EOP VLV)XTIE ISOL VLV 01 1SI8808A ASSY -MOV 1AACCUM 1SI04TA OUTLET Cont 412 +01 (EOP VLV)ISOL VLV 01 1SI8808B ASSY -MOV 1BACCUM 1SI04TB OUTLET Cont 412 +01 (EOP VLV)ISOL VLV 01 1SI8808C ASSY -MOV 1C ACCUM 1SI04TC OUTLET Cont 412 +01 (EOP VLV)_ISOL VLV 01 1SI8808D ASSY -MOV 1D ACCUM 1SI04TD OUTLET Cont 412 +01 (EOP VLV)I_ ISOL VLV 01 1SI8809B ASSY -MOV 1B RH HX SI OUTLET DWST ISOL Aux 374 +14 (EOP VLV)I VLV 01 1SI8815 U-1 COLD LEG HDR SI SUP CHK VLV Cont 377 20 1 11SI8818A LOOP 1 COLD LEG ACCUM INJ CHK VLV Cont 412 10 1 11SI8818B LOOP 2 COLD LEG ACCUM INJ CHK VLV Cont 412 6 1 1SI8818C LOOP 3 COLD LEG ACCUM INJ CHK VLV Cont 377 10 1 1S18818D LOOP 4 COLD LEG ACCUM INJ CHK VLV Cont 377 12 1 1S18819A LOOP 1 COLD LEG SI CHK VLV Cont 412 3 1 1S18819B LOOP 2 COLD LEG SI CHK VLV Cont 412 2 1 11SI8819C LOOP 3 COLD LEG SI CHK VLV Cont 377 5 1 1SI8819D LOOP 4 COLD LEG SI CHK VLV Cont 377 10 Table B-1 Page 27 of 35 B-29 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1S18856A 1A RH HX TO 1A/1D LOOP CL RLF VLV Aux 374 +15 P-50 UPST 1S18809A 01 1S18856B 1B RH HX TO 1B/1C LOOP CL RLF VLV Aux 374 +14 P-51 UPST 1S18809B 1A ACCUM OUTLET TO RC LOOP 1 2ND CHK 4 01 1SI8948A Cont 390 VLV I 1S18948B 1B ACCUM OUTLET TO RC LOOP 2 2ND CHK Cont 390 4 VLV 1 1S18948C 1C ACCUM OUTLET TO RC LOOP 3 2ND CHK Cont 390 4 VLV 1 D ACCUM OUTLET TO RC LOOP 4 2ND CHK 4 1 1SI8948D Cont 390 1 ____ 114OPHTEVLV

_____377_1 1S18949A LOOP I HOT LEG RH SUCT CHK VLV Cont 377 8 1 1S18949B LOOP 2 HOT LEG RH SUCT CHK VLV Cont 390 5 1 1S18949C LOOP 3 HOT LEG RH SUCT CHK VLV Cont 377 8 I 1SI8949D LOOP 4 HOT LEG RH SUCT CHK VLV Cont 390 5 1A ACCUM OUTLET TO RC LOOP 1 1ST CHK 7 VLV 1 1S18956B 1 B ACCUM OUTLET TO RC LOOP 2 1ST CHK C9nt 377 VLV 1 1S18956C 1C ACCUM OUTLET TO RC LOOP 3 1ST CHK Cnt 377 9 VLV 1D ACCUM OUTLET TO RC LOOP 4 1ST CHK 5 I 1SI8956D Cant 390 VLV 1 1S18841A LOOP 3 HOT LEG RH SUCT 1ST CHK VLV Cont 377 8 1 1S18841B LOOP 1 HOT LEG RH SUCT 1ST CHK VLV Cont 377 2 1 11RY86A 1A PORV ACCUM 1 RY32MA AIR INLET 2ND Cnt 451 4 CHK VLV 1B PORV ACCUM 1RY32MB AIR INLET 2ND 4 I 1RY086B Cant 451 CHK VLV I 1RY8030 ASSY -AOV U-1 PRT PW SUP INSIDE CNMT Cant 390 +1 ABOVE PRT ISOL VLV 01 1 RY8031 ASSY -AOV U-1 PRT TO RCDT DRN VLV Cont 377 +3 W OF PRT 01 1RY8046 U-1 PRT 1RY01T PW SUP CHK VLV Cont 377 18 1 1RY8081 U-1 VLV L/O TO PRT 1RY01T CHK VLV Cont. 390 6 I I RH606 ASSY -AOV 1A RH HX 1 RH02AA OUTLET VLV Aux 10_(EOP VLV) I I II Table B-1 Page 28 of 35 B-30 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1RH607 ASSY -AOV 1 B RH HX 1 RH02AB OUTLET VLV Aux 357 11 (EOP VLV)ASSY -AOV 1A RH HX 1 RH02AA BYP VLV 10 1 1RH618 Aux 357 (EOP VLV)1 1RH619 ASSY -AOV 1B RH HX 1RH02AB BYP VLV Aux 10 (EOP VLV)1 1RH8708A 1A RH PP SUCT HDR RLF VLV Aux 364 16 1 1RH8708B 1B RH PP SUCT HDR RLF VLV Aux 364 16 1A RH HX OUTLET TO LTDWN HX ISOL VLV 1 1 1 RH8734A Aux 364 (EOP VLV)1 1 RH8734B 1 B RH HX OUTLET TO LTDWN HX ISOL VLV Aux 364 1 (EOP VLV)1 1 RH8735 U-1 RH RECIRC TO RWST ISOL VLV (EOP Aux 364 12 VLV)AOV U-1 RCDT PP DSCH INSIDE CNMT ISOL 11 1 1RE1003 Cont 377 VLV (EOP VLV)1 1RC8003A ASSY -MOV 1A RC LOOP BYP VLV Cont 390 4 1 1 RC8003B ASSY -MOV 1 B RC LOOP BYP VLV Cont 390 4 1 1RC8003C ASSY -MOV 1C RC LOOP BYP VLV Cont 390 4 1 1 RC8003D ASSY -MOV 1 D RC LOOP BYP VLV Cont 390 +04 BTWN HL & CL 01 1RC8037A ASSY -AOV 1A RC.LOOP DRN VLV (EOP VLV) Cont 377 1 1 1RC8037B ASSY -AOV 1B RC LOOP DRN VLV (EOP VLV) Cont 1 1 1 RC8037C ASSY -AOV IC RC LOOP DRN VLV (EOP VLV) Cont 377 1 1 1 RC8037D ASSY -AOV 1 D RC LOOP DRN VLV (EOP VLV) Cont 377 1 1 1 RC8038A 1A RC LOOP CVCS FILL ISOL VLV Cont 377 9 1 1RC8038B 1B RC LOOP CVCS FILL ISOL VLV Cont 377 +10 BTWN 1B S/G & RCP 01 1RC8038C lC RC LOOP CVCS FILL ISOL VLV Cont 377 9 1 1RC8038D 1D RC LOOP CVCS FILL ISOL VLV Cont 377 9 1 1RC8040A 1A RC LOOP HL DRN VLV Cont 377 7 1 1RC8040B 1B RC LOOP HL DRN VLV Cont 377 7 1 1RC8040C IC RC LOOP HL DRN VLV Cont 377 7 Table B-1 Page 29 of 35 B-31 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1RC8040D 1D RC LOOP HL DRN VLV Cont 377 7 1A RC LOOP BYP VLV 1RC8003A DISC PRESS 1 I 1RC8045A EQA/VRRS HCont 390 I 1RC8045B 1 B RC LOOP BYP VLV 1 RC8003B DISC PRESS Cont 390 1 EQUAL/OVERPRESS CH 1 1 RC8045C lC RC LOOP BYP VLV 1RC8003C DISC Cont 390 1 PRESS EQUAL/OVERPRESS CH 1 1 RC8045D 1 D RC LOOP BYP VLV 1 RC8003D DISC Cont 390 1 PRESS EQUAL/OVERPRESS CH 1 1 RC8057 1D RC LOOP CL DRN 1ST ISOL VLV Cont 377 +5 ABOVE RECIRC SUMP 01 ISO2IA 1A S/G MS OUTLET HDR DRN DWST ISOL SIV 377 5 VLV (EOP VLV)1 1 MS21B 1 B S/G MS OUTLET HDR DRN DWST ISOL SIV 377 5 VLV (EOP VLV)IC S/G MS OUTLET HDR DRN DWST ISOL 6 1 1MS021C MSIV 377 VLV (EOP VLV)1 D S/G MS OUTLET HDR DRN DWST ISOL 6 1 1 MS021 D ML EPVV VSIV 377 1 _ _ lM11AS-AV1VLV (EOP VLV) ____37 1 1 1MS101A ASSY-AOV 1A MSIV BYP VLV (EOP VLV) MSIV 377 15 1 1MS101B ASSY- AOV 1B MSIV BYP VLV (EOP VLV) MSIV 377 15 1 1MS101C ASSY- AOV 1C MSIV BYP VLV (EOP VLV) MSIV 377 15 1 1MS101D ASSY-AOV 1D MSIVBYP VLV(EOP VLV) MSIV 377 15 1 1 FW036A 1A S/G FW TEMPERING LINE CHK VLV MSIV 377 10 1 1FW036B 1B S/G FW TEMPERING LINE CHK VLV MSIV 377 10 1 1FW036C 1C S/G FW TEMPERING LINE CHK VLV MSIV 377 10 I 1FW036D ID S/G FWTEMPERING LINE CHK VLV MSIV 377 10 AOV 1A FW PREHTR BYP DWST ISOL VLV 15 I I1FW039A MSIV 377 (EOP VLV)I 1FW039B AOV 1 B FW PREHTR BYP DWST ISOL VLV MSIV 12 (EOP VLV)1 1FW039C AOV 1C FW PREHTR BYP DWST ISOL VLV MSIV 377 15 (EOP VLV)AOV 1D FW PREHTR BYP DWST ISOL VLV 15 1 1 FW039D MEPVV VSIV 377_____ _____(FOP VLV) _ _ _ _1 1 FW043A AOV 1A S/G FWIV BYP VLV (EOP VLV) MSIV 377 2 Table B-1 Page 30 of 35 B-32 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1FW043B AOV lB S/G FWIV BYP VLV (EOP VLV) MS IV 377 3 1 1 FW043C AOV 1 C S/G FWIV BYP VLV (EOP VLV) MS IV 377 3 1 1 FW043D AOV 1 D S/G FWIV BYP VLV (EOP VLV) MSIV 377 3 1 1FW079A 1A S/G FW SUP CHK VLV MSIV 377 15 1 1FW079B 1B S/G FW SUP CHK VLV MSIV 377 15 1 1FW079C lC S/G FW SUP CHK VLV MSIV 377 15 1 1FW079D 1D S/G FW SUP CHK VLV MSIV 377 15 1 1FP345 RX1 CNMT FP SUP CHK VLV Cont 377 13 1 1FC009 ISOLATION VALVE Cont 377 10 1 1FC012 ISOLATION VALVE Cont 377 14 1 1 D0055A 1A & 1C DO XFER PP RECIRC TO STO TK Aux +20 NE OF 1C DO STO TK ISOL VLV 10B & 1B D XFER PP RECIRC TO DO STO TK 23 01 1 D0055B Aux 373 ISOL VLV 1 1CV01AA 1A CV EXC LTDWN HX Cont 401 15 1 1CV01AB 1B CV EXC LTDWN HX Cont 401 15 I 1CV121 ASSY -AOV U-1 CV PPS DSCH HDR FCV Aux 364 7 (EOP VLV)1 lCV184 ASSY -AOV U-1 RC LOOP FILL HDR FCV Aux 364 +26 BELOW BIT N WALL 01 1CV8117 U-1 LTDWN ORIFICE OUTLET HDR RLF VLV Cont 412 +10 6' FROM RO5 1 1CV8121 U-1 PRT 1 RY01T RLF VLV Cont 377 +22 8' FROM RO5 ON WALL 1 1CV8123 U-1 SEAL WTR HX INLET HDR RLF VLV Aux 383 +5 1' FROM 1A LTDWN HX RM WAL 1 1CV8124 U-1 CV CHG PP SUCT HDR RLF VLV Aux 364 +7 4' E OF S ASSY -AOV U-1 PZR AUX SPRAY HDR ISOL 2 1 1lCV8145 VV(O V)Cont 412_____ _____VLV (EOP VLV) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _1 1CV8355A ASSY -MOV 1A RC PP SEAL W"R INJ INLET Aux 374 +18 (EOP VLV), P-33 ISOL VLV 01 1CV8355B ASSY -MOV 1B RC PP SEAL WTR INJ INLET Aux 374 +12 (EOP VLV), P-53 ISOL VLV 01 1CV8355C ASSY -MOV 1C RC PP SEAL WTR INJ INLET Aux 374 +12 (EOP VLV), P-53 ISOL VLV 01 1CV8355D ASSY -MOV 1D RC PP SEAL WTR INJ INLET Aux +18 (EOP VLV), P-33 01_ 1__CV8355D

_ ISOL VLV Aux 374 01 1CV8377 U-1 PZR 1RY01S AUX SPRAY HDR CHK VLV Cont 401 15 Table B-1 Page 31 of 35 B-33 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1CV8378A U-1 RC CL LOOP 2 CHG WTR INLET 2ND CHK Cont 377 2 VLV U-1 RC CL LOOP 1 CHG WTR INLET 2ND CHK 2 1 1 CV8379A Cont 377 VLV PP_______________________Aux364_

1 1CV8387A 1A CV PP DSCH FCV BYP VLV (EOP VLV) Aux 364 9 1 1CV8387B lB CV PP DSCH FCV BYP VLV (EOP VLV) Aux 364 9 1 1CV8394 U-1 CV PD CHG PP 1CV02P SUCT ISOL VLV Aux 364 3 I 1CV8399 U-1 SEAL WTR RTRN FLTR 1CV02F BYP VLV Aux 383 +2 FLTR VLV AISLE 01 1 CV8442 U-i CV EMER BORATION INLET CHK VLV Aux 426 2 1 1 CV8445 PW TO U-I CV EMER BORATE CHK VLV Aux 426 2 I 1CV8482 U-1 SEAL WTR HX OUTLET TO VCT ISOL VLV Aux 426 2 (EOP VLV)1 1CV8497 U-1 CV PDCP 1CV02P DSCH CHK VLV Aux 364 4 1 1CS009A CS PUMP 1A SUMP SUCTION VALVE -MOV Aux 343 +05 (EOP VLV)01 1CS009B CS PUMP 1 B SUMP SUCTION VALVE -MOV Aux 343 +01 (EOP VLV)01 1CS007A MOV 1A CS PP DSCH HDR ISOL VLV Aux 374 +33 (EOP VLV), ABOVE 1A REC 01 1 CS007B MOV 1 B CS PP DSCH HDR ISOL VLV Aux 374 +34 (EOP VLV), ABOVE 1 B REC 1A CS PP 1CS01PA SPRAY NOZL HDR CHK 2 01 ICS008A Cont 401 VLV I 1CS008B 1B CS PP 1CS01PB SPRAY NOZL HDR CHK Cont 401 2 VLV 1 1CC050 ASSY -AOV U-1 PRI WALL PEN CLG FCV Cont 377 17 1 1CC051 U-1 PRI WALL PEN CLG RTRN CHK VLV Cont 377 6 1 1CC060 U-1 PEN CLG RTRN CHK VLV Cont 377 30 1 lCC061 U-1 PEN CLG RTRN CHK VLV Cont 412 6 1 1CC062 U-1 PEN CLG RTRN CHK VLV Cont 412 7 I 1CCO70A WM M/U TO U-1 CC SURGE TK lCC01T INLET Aux 426 3 CHK VLV I 1CCO70B PW M/U TO U-1 CC SURGE TK lCC01T INLET Aux 426 3 CHK VLV I 1CC130A ASSY -AOV 1A LTDWN HX OUTLET TCV (EOP Aux 383 5 VLV) I IlCC130B ASSY -AOV 1 B LTDWN HX OUTLET TCV (EOP Aux 383 5____ M___30B__

VLV) Aux 383 Table B-1 Page 32 of 35 B-34 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION ASSY -MOV U-1 RC PPS THERM BARR CC +21 (EOP VLV)1 1 CC685 RTRN ISOL VLV Aux 374 01 1CC9413A ASSY -MOV U-1 RC PPS CC SUP UPST ISOL Aux 374 +23 (EOP VLV)VLV 01 1CC9413B ASSY -MOV U-1 RC PPS CC SUP DWST ISOL Aux 374 +23 (EOP VLV)VLV 01 1CC9414 ASSY -MOV U-1 RC PPS CC RTRN OUTSIDE Aux 374 +23 (EOP VLV)CNMT ISOL VLV 01 1 CC9415 ASSY -MOV U-1 SERV LOOP ISOL VLV Aux 364 +09 (EOP VLV)01 1CC9416 ASSY -MOV U-1 RC PPS CC RTRN INSIDE Cont 377 +24 (EOP VLV)CNMT ISOL VLV 01 1CC9427 U-1 PEN CLG RTRN RLF VLV (EOP VLV) Cont 377 21 I 1CC9437A ASSY.- AOV U-1 EXC LTDWN HX CC SUP VLV Aux 13 (EOP VLV)1 1lCC9438 ASSY -MOV U-1 RC PPS THERM BARR CC Cont 377 +17 (EOP VLV)RTRN ISOL VLV 01 1CC9473A ASSY -MOV U-1 CC PP DSCH HDR 1A XTIE Aux 364 +10 (EOP VLV)ISOL VLV 01 1CC9473B ASSY -MOV U-1 CC PP DSCH HDR 1B XTIE Aux 364 +10 (EOP VLV)ISOL VLV Aux_364 01 1CC9422A 1A RH HX CC OUTLET HDR RLF VLV Aux 357 9 1 1CC9422B 1B RH HX CC OUTLET HDR RLF VLV Aux 364 12 I 1AF001A U-1 CST 1CD01T TO 1A AF PP 1AF01PA SUCT Aux 383 10 CHK VLV I 1AF001B U-1 CST 1CD01T TO 1BAF PP 1AF01PB SUCT Aux 383 10 CHK VLV ASSY -AOV 1A AF PP 1AF01PA DSCH VLV 6 I 1AF004A EPVL)Aux 383 (EOP VLV)I 1AF004B ASSY- AOV 1B AF PP 1AF01PB DSCH VLV Aux 383 1 1 __1AF004B

__ (EOP VLV) Aux_383 I 1AF005A ASSY -AOV 1A AF PP DSCH TO 1A S/G FCV Aux 364 4 (EOP VLV) I II IAF005B ASSY -AOV 1A AF PP DSCH TO 1B S/G FCV Aux 364 5 (EOP VLV) I I/Table B-1 Page 33 of 35 B-35 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION ASSY -AOV 1A AF PP DSCH TO 1C S/G FCV 4 I 1AF005C EPVL)Aux 364 (EOP VLV)ASSY -AOV 1A AF PP DSCH TO 1D S/G FCV 5 1 1AF005D Aux 364 (EOP VLV)I 1AF005E ASSY -AOV 1B AF PP DSCH TO 1A S/G FCV Aux 364 (EOP VLV)1 1AF005G ASSY -AOV 1B AF PP DSCH TO 1B S/G FCV Aux 364 5 (EOP VLV)ASSY -AOV 1B AF PP DSCH TO 1C S/G FCV 5 I 1AF005G Aux 364 (EOP VLV)I 1AF013H ASSY -AOV 1B AF PP DSCH TO1D S/GFCV Aux 36 (EOP VLV)1 1AF013A ASSY -MOV 1A AF PP DSCH HDR TO 1A S/G Aux 367 +01 (EOP VLV)ISOL VLV 01 1AF013B ASSY -MOV 1A AF PP DSCH HDR TO 1B S/G Aux 362 +01 (EOP VLV)ISOL VLV 01 1AF013C ASSY -MOV 1A AF PP DSCH HDR TO 1C S/G Aux 362 +01 (EOP VLV)ISOL VLV 01 1AF013D ASSY -MOV 1A AF PP DSCH HDR TO 1D S/G Aux 367 +01 (EOP VLV)ISOL VLV 01 1AF013E ASSY -MOV 1B AF PP DSCH HDR TO 1A S/G Aux 367 +01 (EOP VLV)ISOL VLV 01 1AF013F ASSY -MOV 1 B AF PP DSCH HDR TO I B S/G Aux 362 +01 (EOP VLV)ISOL VLV 01 1AF013G ASSY -MOV 1B AF PP DSCH HDR TO 1C S/G Aux 362 +01 (EOP VLV)ISOL VLV 01 1AF023H ASSY -MOV 1A AF PP DSCH TO 1D S/G Aux 367 +01 (EOP VLV)_ISOLVLV ____1 1AF022A ASSY -AOV 1A AF PP DSCH TO CST RECIRC Aux 383 1 VLV (EOP VLV) IIII I 1AF02B ASSY -AOV 1BAF PP DSCH TO CSTRECIRC Aux 383 1 VLV (EOP VLV) III I A04ASSY -AOV U-I AF PPS DSCH TO SX RECIRC Ax33 15____ ___ ___VLV (EOP VLV) _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _Table B-1 Page 34 of 35 B-36 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 UNIT ID DESCRIPTION BUILDING ELEVATION LOCATION 1 1A18629A U-1 CV CHARGING PUMP TO RECYCLEAu 1EVAPORATOR DEMINERALIZER Table B-1 Page 35 of 35 B-37 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Table B-2. Base List 2 ID Description Building Elevation Column 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 0B SUCTION ISO VLV 364 12 S OFC004 REFUELING WTR PURIF PMP GB DISCH CHECK AUX 364'+8' 12 S OFC006A REFUELING WTR PURIF PMPS SUCT HDR INST ROOT TO GPI-FC003 364 12 S OFC007A REFUELING WTR PURIF PMP GA DISCH INST ROOT TO OPI-FC005 AUX 364 12 S OFC011 REFUELING WTR PURIF PMP GA 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 GA DISCH INST ISOL TO OPI-FC005 AUX 364 17 Q OFC03PA PUMP REFUELING WTR PURIFICATION OA ASMBLY AUX 364 12 S OFC8754 SPENT FUEL PIT HX RTRN ISOL FH 401 18 Y OFC8763 REFUELING WTR PURIF PMP OA DISCH CHECK AUX 364+18' 12 S OFC8790 SPENT FUEL PIT HX TO BORON RECY HOLDUP TANKS ISOL FH 401 18 Y OHS-FC002 REFUELING WATER PURIF PUMP GA AUX 364 12 S GLS-FC010 SPENT FUEL POOL LEVEL SWITCH 418 20 X OPI-FC003 REFUELING WTR PURIFICATION PUMP GA SUCT PRESS GPI-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 1FC004A SPENT FUEL PIT HX TUBE SIDE VENT FH 401 17 Z 1FC004B SPENT FUEL PIT HX SHELL SIDE VENT FH 401 17 Y 1FC005 SPENT FUEL PIT PMP CASING DRN FH 401 18 Y 1FC006 SPENT FUEL PIT PMP CASING VENT FH 401 18 Y 1FC007 REFUELING WTR PURIF PMP SUCT FROM U-1 REFU CAVITY DRN TEST CONN AUX 364 12 U 1FC008 SPENT FUEL PIT FLT DEMIN RTRN TO Ul REFUEL CAV DRN TEST CONN AUX 364 12 S 1FC009 REFUELING WTR PURIF PMP SUCT FROM U-1 REFUEL CAV CNMT ISOL CNMT 377 7 R 1FC010 REFUELING WTR PURIF PMP SUCT FROM U-1 REFUEL CAV CNMT ISOL AUX 364 12 U 1FC011 SPENT FUEL PIT FLTR DEMIN LOOP RTRN TO U-1 REFUEL CAV CNMT ISOL AUX 364 12 S 1FC012 SPENT FUEL PIT FLTR DEMIN LOOP RTRN TO U-1 REFUEL CAV CNMT ISOL CNMT 377 8 R 1FC013 REFUELING WTR PURIF PMP DISCH TO SPENT FUEL PIT FLTR DEMIN LOOP AUX 401 17 Q 1FC01A SPENT FUEL PIT HEAT EXCHANGER FH 401 17 Z IlFC01P U-1 FUEL POOL COOLING PUMP AUX 401 18 Y Table B-2 Page 1 of 2 B-38 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 ID Description Building Elevation Column 1FC021 SPENT FUEL PIT PMP DISCH INST ISOL TO 1PI-627 FH 401 17 AA 1 FC022 SPENT FUEL PIT PMP SUCT INST ISOL TO 1 PI-633 FH 401 19 AA 1 FC02M SPENT FUEL PIT PUMP START UP STRAINER 1 FC032 REFUEL WTR PURIF PUMP SUCT FROM U-1 REFUEL CAVITY DRN CONN 364 12 U 1FC03F SPENT FUEL PIT STRAINER 1FC03PA PUMP, OA REFUELING WATER PURIFICATION 1FC8756 U1 SPENT FUEL PIT PMP SUCTION ISOL FH 401 18 Y 1 FC8757 SPENT FUEL PIT PMP SUCT INST ROOT TO 1 PI-633 FH 401 18 Y i1FC8758 REFUELING WTR PURIF PMP SUCT FROM U-1 RWST AUX 364 13 V 1 FC8761 SPENT FUEL PIT PMP DISCH INST ROOT TO 1 PI-627 FH 401 17 Y 1FC8762A SPENT FUEL PIT HX INLET FH 401 17 Z 1FC8762B U1 SPENT FUEL PIT HX OUTLET FH 401 17 Z 1FC8765 SPENT FUEL PIT FLTR DEMIN LOOP RTRN TO SPENT FUEL PIT AUX 401 15 X 1FC8766 SPENT FUEL PIT FLTR DEMIN LOOP RTRN TO U-1 RWST CHECK VLV 1FC8792A SPENT FUEL PIT HX TUBE SIDE DRN FH 401 17 Z 1FC8792B SPENT FUEL PIT HX SHELL SIDE DRN FH 401 17 Z 1FC8793 SPENT FUEL PIT PMP DISCH CHECK FH 401 17 Y 1FC8794 SPENT FUEL PIT FLTR DEMIN LOOP INLT ISOL FH 401 17 Y 1 FI-0631 FC DEMIN FLOW INDICATOR AUX 390 12 N 1 HS-FC001 SPENT FUEL PIT PUMP FH 401 1PI-0627 GAUGE; PRESSURE, U.S. GAUGE CO.,0-160 PSIG FH 401 17 AA 1PI-0630 SPENT FUEL POOL FILTER OUTLET PRESSURE INDICA 1PI-0633 SPENT FUEL PIT PUMP SUCTION PRESSURE INDICATO FH 401 AA-19 1TI-0628 SPENT FUEL POOL HEAT EXCH OUTLET TEMP INDICAT 1TW-0628 SFP HX OUTLET WELL AUX 364 14 V Table B-2 Page 2 of 2 B-39 Byron Generating Station Unit 1 12Q0108.20-R-O01 Rev. 1 Correspondence No.: RS-12-161 Table B-3. SWEL 1 Seismic Safety New or IPEEE ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM Cat. 1? Function(s)

Replace Enhancement?

Comments 1SX01FB 18 SX PP DSCH STRN (00) Other Auxiliary 330 330 18-23/ SX Y UHS 0SX162A ASSY -MOV OA SXCT TO BASIN BYP VLV (08) Motor-Operated and +01 0A VLV RM, S Y UHS Solenoid-Operated Valves ESWCT 872 (EOP VLV) SX YUHS 1AP21E 480V AUX BLDG ESF MCC 131Xl XFORMER (04) Transformers Auxiliary 364 364 U-1 AR AP Y SSAC Y AUXILIARY FEEDWATER PMP 1 B SX SUCT VLV (08) Motor-Operated and 1AF006B ASMBLY; 6" Solenoid-Operated Valves Auxiliary 383 All AF Y DHR 1AP22E 480V AUX BLDG ESF MCC 131X3 ASMBLY (01) Motor Control Centers Auxiliary 383 All AP Y SSAC Y AUXILIARY FEEDWATER PMP 1B SX SUCT VLV (08) Motor-Operated and 1AF017B ASMBLY; 6" Solenoid-Operated Valves Auxiliary 383 All AF Y DHR 1AP24E EQ 480 V AUX BLDG ESF MCC 132X3 ASMBLY (01) Motor Control Centers Auxiliary 383 All AP Y SSAC Y 1 CC685 CC FROM RC PMPS THERMAL BARRIER ISOL VLV (08) Motor-Operated and 383 U-374+21 Ul CC Y CF Penetration

1. 24 1CC685 ASMBLY; 3" Solenoid-Operated Valves Auxiliary 395 AR OVCO8Y TRAIN B MAKEUP AIR FLTR UNIT FAN 0B DISCH (10) Air Handlers Auxiliary 463 463 HVAC G VC Y SSHVAC 0VC08Y_ FLOW CONTROL Axlay 43 63HA GV__YSSHVAC IAP27E EQ 480V AUX BLDG MCC 132X2 ASMBLY (01) Motor Control Centers Auxiliary 426 426 AREA 5 AP Y SSAC Y 1CV1 12E RWST TO CHG PMPS SUCT VLV (C/S AT 1 PM05J) (08) Motor-Operated and RCIC Y 1_V112E ASMBLY; 8" Solenoid-Operated Valves Auxiliary 364 364 U-i AR CV OVCO9Y TRAIN B EMERGENCY MAKEUP INTAKE FROM TURB (10) Air Handlers Auxiliary 451 451 U-2 HV VC Y SSHVAC 0V__9Y BLDG Auxiliary 451 451_U-2_HV VC___SSHVA 1AP38E ASSY -480V AUX BLDG MCC 133X1A (01) Motor Control Centers Auxiliary 346 346 10-18/ AP Y SSAC Y 1VA02SB 1B RHR PUMP ROOM CUB CLR ASMBLY (10) Air Handlers Auxiliary 346 346 1B RH VA Y SSHVAC 1AP99E ASSY -480V ESF SXCT UNIT SUBSTA 131Z, NORTH (01) Motor Control Centers ESWCT 874 ESWCT AP SSAC Y ELEC RM 1MS018A S/G 1A PORV ASMBLY; 8" (08) Motor-Operated and Solenoid-Operated Valves Auxiliary 401 401 U-i MS MS Y DHR 1VA06SA COOLERCENTRIFUGAL CHARGING PUMP 1A (10) Air Handlers Auxiliary 364 364 1A CV VA Y SSHVAC 1AP06E 4160 VOLT ESF SWITCH BUS 142 (03) Medium Voltage Auxiliary 426 426 ESF SW AP Y SSAC Switchgear SW AP Y _SSAC 1MS018B S/G 1B PORV ASMBLY; 8" (08) Motor-Operated and Solenoid-Operated Valves Auxiliary 401 401 U-i MS MS Y DHR 1VA08CB 1B DIESEL DRIVEN AF PUMP CUBICLE CLR (1VA08S) (10) Air Handlers Auxiliary 383 All VA Y SSHVAC 1B FAN EQ 480V ESF UNIT SUB 131X TRANSFORMER (04) Transformers 1AP11E IAP086 Auxiliary 426 426 ESP SW AP Y SSAC RC LOOP 1C TO RH PMP 1B SUCT ISOL VLV (08) Motor-Operated and 1RH8702A ASMBLY; 12" Solenoid-Operated Valves Cont 377 0MB PEN 75 RH Y CF 1VP01AA CNMT ESS'L SERVICE WATER COIL 1A (RCFC) (10) Air Handlers Cont 377 377-R-16 VP Y CF 1AF01PB DIESEL DRIVEN AUX FEED PUMP lBASMBLY (05) Horizontal Pumps Auxiliary 383 All AF Y DHR Y PRA:F-V=4.16E-02, RAW=5.10 1RY8028 PW TO PRT CONTAINMENT ISOLATION VLV (08) Motor-Operated and 374 + 13 12U P- RY Y CF Penetration

1. 44 Solenoid-Operated Valves Aux RXB1 38744 Table B-3 Page 1 of 5 B-40 Byron Generating Station Unit 1 12Q0108.20-R-O01 Rev. 1 Correspondence No.: RS-12-161 New or Seismic Safety Replace IPEEE Comments ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM Cat. 1? Function(s)

Replace Enhancement?

1DC10J 125V DC FUSE PANEL -DIV. 11 (14) Distribution Panels Auxiliary 451 451 DIV 11 DC Y SSDC 1B PUMP, COMPONENT COOLING 12X14-18 M66-3 (05) Horizontal Pumps PRA:F-V=8.337E-1CC01PB ASMBLY Auxiliary 364 364 15-21/ CC Y DHS 03,RAW=1.07 1S18804B ASSY -MOV 1 B RH HX TO 1 B SI PP SUCT HDR ISOL (08) Motor-Operated and Auxiliary 364 364 UNIT I SI Y RCIC VLV Solenoid-Operated Valves 1DC11J 125V DC FUSE PANEL -DIV. 12 (14) Distribution Panels Auxiliary 451 451 DIV 12 DC Y SSDC 1CV01PB PUMPB CENTRIFUGAL CHARGING ASMBLY (05) Horizontal Pumps Auxiliary 364 364 1B CV CV Y RCIC Y RH TO COLD LEGS 1 B/i C ISOL VLV (1 PM06J) (08) Motor-Operated and Auxiliary 364 383 U-1 AR SI Y RClC 1S18809B ASMBLY; 8" Solenoid-Operated Valves 1AFO1EA-1 AF PUMP IB BATTERY CHARGER (15) Batteries on Racks Auxiliary 383 All AF Y SSDC 1SX01PB PUMPIB ESSENTIAL SER WTR ASMBLY (05) Horizontal Pumps Auxiliary 330 330 18-23/ SX Y UHS PRA:F-V=4.27E-02, RAW= 1.77 1AF01EB-A AF BATTERY Bank B BATT A AUXILIARY (15) Batteries on Racks Auxiliary 383 All AF Y SSDC FEEDWATER PUMP 1B 1VA01SB lB SX Pp Cub Cooler ESSENTIAL SERVICE WATER (05) Horizontal Pumps Auxiliary 330 330.18-23/

VA Y UHS 1VA01SB PUMP 95-10 1 SX005 U-0 CC HX INLT VLV ASMBLY; 30" (08) Motor-Operated and Auxiliary 330 33018-23/

SX Y DHR Solenoid-Operated Valves 1DC01E 125V BATTERY 111 DIV. 11 AND Rack (15) Batteries on Racks Auxiliary 451 451 DIV 11 DC Y SSDC Y PRA:F-V=2.62E-02, RAW=2.69 1RH01PB PUMP,1B RESIDUAL HEAT REMOVAL ASMBLY (06) Vertical Pumps Auxiliary 364 346 1B RH RH Y DHR SX SUP VLV TO ENG Driven CLG WTR PP FOR Diesel (08) Motor-Operated and Auxiliary 383 All SX Y DHR lSX173 Driven AF PP ASSY; 6" Solenoid-Operated Valves 1DC02E 125V BATTERY 112 DIV. 12 and Rack (15) Batteries on Racks Auxiliary 451 451 DIV 12 DC Y SSDC PRA:F-V=2.62E-02, 1 DC02E_ Auxiliary 451__ 451 DIV 12 DC Y SSDCRAW=2.69 OSX02PB DIESEL DRIVEN SX MAKE-UP PUMP (06) Vertical Pumps RSH 686'6" 686'6" 2C SX Y UHS PRA:F-V=2.96E-01,____________________________

_______RAW=7.91 1VD01CB 1B DG ROOM HVAC FAN ASMBLY (09) Fans Auxiliary 401 401 1B DG VD Y SSHVAC PRA: F-V=1.85E-02 INVERTER INST BUS 111 1-3371 AB1 .(16) Battery Chargers and 451 DIV 11 MISC lIP05E Inverters Aux 451 ELEC EQUIP RM PO Y SSDC Y (9-10/L-M)

OWWO19A ASSY -AOV 0B DEEP WELL PP OWWO1PB TO OA (07) Pneumatic-Operated ESWCT 874 ESWCT WW Y UHS SXCT LCV Valves 1VE05C ASSY -U-1 MISC ELEC EQUIP RM DIV 12 EXH FAN (09) Fans Auxiliary 463 451 DIV 12 VE Y SSHVAC S/G 1A FLOW CONT VLV ASMBLY; 4" (07) Pneumatic-Operated 1AF005E Valves Auxiliary 364 36410-15/

AF Y DHR Y 1AF024 AF PP SX RECIRC VLVASMBLY; 3" (07) Pneumatic-Operated Auxiliary 383 All AF Y DHR Valves 1MS001A MS ISOL VLV LOOP 1AASMBLY; 30-1/4" (07) Pneumatic-Operated Auxiliary 377 377 U-1 MS MS Y DHR Valves IRH607 RESIDUAL HEAT REMOVAL HX 1B FLOW CONT VLV (07) Pneumatic-Operated Auxiliary 357 364 1B RHR RH Y DHR ASMBLY; 8" Valves 1RY455A PZR PORV (C/S AT 1PM05J) ASMBLY (07) Pneumatic-Operated Cont 451 ABOVE PZR RCS Y RCPC Valves 1S18801B CHG PMP TO COLD LEGS INJECTION ISOL VLV (C/S (07) Pneumatic-Operated Auxiliary 375 383 U-1 AR SI Y RCIC 1SI8801B AT 1PM05J) ASMBLY; 4" Valves _ _ _ _ _ _ __Table B-3 Page 2 of 5 B-41 Byron Generating Station Unit 1 12QO108.20-R-O01 Rev. 1 Correspondence No.: RS-12-161 New or Seismic Safety Ne r IPEEE Cmet ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM Cat. 1? Function(s)

Replace Enhancement?

Comments 1SX169B DG 1B SX VLVASMBLY; 10" (07) Pneumatic-Operated Auxiliary 401 401 1BPRA: F-V=2.74E-02, Valves PRA11F-VRW=2.19 125V DC BATT CHGR 112 (16) Battery Chargers and 451 DIV 12 MISC PRA:F-V=2.62E-02, 1DC04E Inverters Aux 451 ELEC EQUIP RM DC Y SSDC Y RAW=2.69 (9-10/M-Q) 125V DC ESF DISTR CENTER BUS 111 (15) Batteries on Racks 451 DIV 11 MISC lDC05E Aux 451 ELEC EQUIP RM DC Y SSDC Y (9-10/L-M) 125V DC ESF DISTR CENTER BUS 112 (15) Batteries on Racks 451 DIV 12 MISC 1DC06E Aux 451 ELEC EQUIP RM DC Y SSDC Y (9-10/M-Q)

INVERTER INST BUS 113 1-3371 AB1 (16) Battery Chargers and 451 DIV 11 MISC 1IP07E Inverters Aux 451 ELEC EQUIP RM PO Y SSAC Y (9-10/L-M)

INVERTER INST BUS 114 1-3371 ABI (16) Battery Chargers and 451 DIV 12 MISC lIP08E Inverters Aux 451 ELEC EQUIP RM PO Y SSAC Y (9-10/M-Q) 1DG01KB 1B DIESEL GENERATOR (17) Engine-Generators Auxiliary 401 401 1B DG DG Y SSAC PRA: F-V=2.37E-01,__________RW=5.81 1FT-0121 CHARGING LINE D/P CELL FLOW XMITTR (18) Instruments on Racks Auxiliary 364 364 17-19/ FT Y RCIC 1FT-0132 LETDOWN FLOW D/P CELL (18) Instruments on Racks Auxiliary 383 All FT Y RCIC 1FT-AF014 AF TO SG 1B FLOW TRANSMITTER (18) Instruments on Racks Auxiliary 364 364 10-15/ AF Y DHR 1LT-0459 EQ PRESSURIZER LEVEL TRANSMITTER (18) Instruments on Racks Cont 377 377-R-12; LT Y RCIC 1LT-0518 S/G 1A LEVEL LOOP D/PXMTTR 2/FILLED LEG (18) Instruments on Racks Cont 412 (No Data) LT Y DHR 1LT-0932 REF WTR STG TK LVL D/P XMTTR (18) Instruments on Racks Auxiliary 379 379 U-1 RW LT Y RCIC U-1 PROC I&C RACK PROTECT CH 1 CAB 1 (20) Instrumentation and 451 U-1 AUX 1PAO1J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y I_ _ I(11-13/N-Q) 1PT-0516 S/G LOOP IA STM PRESS XMTTR (18) Instruments on Racks Auxiliary 377 377 U-1 MS PT Y DHR U-1 PROC I&C RACK PROTECT CH 2 CAB 2 (20) Instrumentation and 451 U-1 AUX 1 PA02J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (111-13/N-Q) 1TE-0604 RHR LP 1A RETURN TEMPERATURE RTD (19) Temperature Sensors Auxiliary 375 364 U-1 AR TE Y DHR U-1 PROC I&C RACK PROTECT CH 3 CAB 3 (20) Instrumentation and 451 U-1 AUX 1PA03J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y I_ (11-13/N-Q) 1TE- RC WIDE RANGE LP 1A TEMP (19) Temperature Sensors Cont 390 3 TE Y DHR RC022A U-1 PROC I&C RACK PROTECT CH 4 CAB 4 (20) Instrumentation and 451 U-1 AUX 1 PA04J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (20)__ _(11-13/N-Q)

OVC01JA CONT RM HVAC LOCAL CONT PAN ASMBLY (20) Instrumentation and 0VC01JA__

__________________________________

_,Control Panels and Cabinets Auxiliary 451 451 U-i HV WO Y SSHVAC U-1 PROC I&C RACK CONT GRP 2 CAB 6 (20) Instrumentation and 451 U-i AUX CPAO6J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFASY Table B-3 Page 3 of 5 B-42 Byron Generating Station Unit 1 12Q0108.20-R-O01 Rev. 1 Correspondence No.: RS-12-161 I Seismic Safety New or IPEEE ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM SeiicReplace St Comments Cat. 1?Fnto~) Enhancement?

0VC15J MCR U-1 HVAC START PNL (20) Instrumentation and Control Panels and Cabinets Auxiliary 451 451 U-i HV VC Y SSHVAC PROC I&C RACK CONT GRP 3 CAB 7 (20) Instrumentation and 451 U-1 AUX 1PA07J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (11-13/N-Q)

U-1 PROC I&C RACK (20) Instrumentation and 451 U-1 AUX 1PA08J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (1 1-13/N-Q)CAB PROT SYST SOL ST RX/ESF TRN A 0-3371B AB1 (20) Instrumentation and 451 U-1 AUX 1PA09J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (11-13/N-Q)

CAB PROT SYST SOL ST RX/ESF TRN B 0-33718 AB1 (20) Instrumentation and 451 U-1 AUX 1PA1OJ Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (11-13/N-Q)

CAB TEST SAFEGUARD TRN B AB1 (20) Instrumentation and 451 U-1 AUX 1PA12J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (1 1-13/N-Q)_________

CAB ESF SEQ/ACT TRN B 0-3371 B AB1 (20) Instrumentation and 451 U-1 AUX 1PA14J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (11-13/N-Q)

CAB RELAY AUX SAFEGUARD TRN A 0-3371B ABI (20) Instrumentation and 451 U-1 AUX 1PA27J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (11-13/N-Q)

CAB RELAY AUX SAFEGUARD TRN B 0-3371B AB1 (20) Instrumentation and 451 U-1 AUX 1 PA28J Control Panels and Cabinets Atux 451 ELEC EQUIP RM PA Y ESFAS Y (11-13/N-Q)

CAB CONT SYSTEM ESF 11 0-3371B AB1 (20) Instrumentation and 451 U-1 AUX 1PA33J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (11-13/N-Q)

CAB CONT SYSTEM ESF 12 0-3371B ABI (20) Instrumentation and 451 U-1 AUX 1 PA34J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (11-13/N-Q)

CAB HJTC RX VESSEL LEVEL CH A 0-3371B ABI (20) Instrumentation and 451 U-1 AUX 1 PA51 J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (11-13/N-Q)

CAB HJTC RX VESSEL LEVEL CH B 0-3371B AB1 (20) Instrumentation and 451 U-1 AUX 1PA52J Control Panels and Cabinets Aux 451 ELEC EQUIP RM PA Y ESFAS Y (11-13/N-Q) 1PL08J 1B DG CONTROL PANEL (20) Instrumentation and Control Panels and Cabinets Auxiliary 401 401 lB DG PL Y SSAC 1PM05J MAIN CONTROL BOARD (20) Instrumentation and Control Panels and Cabinets Auxiliary 451 451 MAIN C PM Y ESFAS CENTRIFUGAL CHARGING PCUBICLE COOLER (20) Instrumentation and VA1 1J LOCAL CONTROL PANEL Control Panels and Cabinets Auxiliary 364 364 lB CV VA Y RCIC Table B-3 Page 4 of 5 B-43 Byron Generating Station Unit 1 1200108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Seismic Safety New or IPEEE Cmet ID DESCRIPTION CLASS BUILDING ELEVATION LOCATION SYSTEM Cat. 1? Function(s)

Replace Enhancement?

Comments REACTOR TRIP SWITCHGEAR (20) Instrumentation and 451 DIV 12 MISC 1RD05E Control Panels and Cabinets Aux 451 ELEC EQUIP RM RD Y RRC Y_________ 10/M-Q) ____1VX07J ESF SWGR RM DIV 12 HVAC DMPR START PNL (20) Instrumentation and Control Panels and Cabinets Auxiliary 426 426 ESF SW VX Y SSHVAC ICV02SB 1B CENTRIFUGAL CHARGING PUMP GEAR COOLER (21) Tanks and Heat Auxiliary 364 364 1B CV CV Y SSHVAC Exchangers Auxliay_34_34_1 C _V Y SHA 1DO01TB DIESEL OIL STORAGE TANK 1 B (21) Tanks and Heat Auxiliary 373 383 U-i Dl DO Y SSAC Exchangers Auxiiar__7_38_U-

_IDOYSA IDO10T 500 GAL DIESEL OIL DAY TANK (AF) (21) Tanks and Heat Auxiliary 383 All DO Y DHR Exchangers Auilay_8_Al_

OY__1RH01PB-A RH PUMP lB SEAL COOLER (21) Tanks and Heat Auxiliary 346 346 16 RH RH Y DHR Exchangers Axlay 3_361_H R Y DH 1RY32MA PORV ACCUMULATOR 1A (21) Tanks and Heat Cont 426 426-R-8 RY Y RCPC Exchangers

_ont_426_426-R-RYYCP 1SI01T REFUELING WATER STORAGE TANK (21) Tanks and Heat FH Ou 401 401 FH OUT SI Y RCIC Exchangers FHOu_401_401_F OUT _S_ Y _RlC 0D008TB 0B SX Pp 2000 GALLON DIESEL OIL STORAGE TANK (21) Tanks and Heat RSH 702 702 1C7 DO Y UHS Exchangers IAP12E ASSY -480V ESF SWGR 132X (02) Low Voltage Switchgear Aux 426 426 ESF SWGR AP Y SSAC Y RM -DIV 12 1AP13E 480V ESF UNIT SUBSTA 132X XFMR (04) Transformers Aux 426 426 ESF SWGR AP Y SSAC Y RM -DIV 11 ASSY -480V AUX BLDG ESF MCC 131X2 (01) Motor Control Centers 414 CURVED 1AP25E Aux 414 WALL AREA -AP Y SSAC Y AREA 5 1AP92E ASSY -480V SXCT MCC 132Z1, SOUTH ELEC RM (01) Motor Control Centers ESWCT 874 ESWCT AP Y SSAC Y 1AP93E ASSY -480V SXCT MCC 131Z1, NORTH ELEC RM (01) Motor Control Centers ESWCT 874 ESWCT AP Y SSAC Y 1AP98E ASSY -480V ESF SXCT UNIT SUBSTA 132Z, SOUTH (01) Motor Control Centers ESWCT 874 ESWCT AP Y SSAC Y ELEC RM ASSY -AOV U-1 LTDWN HDR ISOL VLV (EOP VLV) (07) Pneumatic-Operated 383 U-1 AREA 5 ICV8152 Valves Aux 374 CURVED WALL CV Y RCIC Y AREA OWO01CB 0B MCR CHLR (11) Chillers Aux CHILLED WTR WO Y SSHVAC IB MCR CHLR 1RMS (8-10/L-P)

I I I Table B-3 Page 5 of 5 B-44 Byron Generating Station Unit 1 1200108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Table B-4. SWEL 2 Associated ID DESCRIPTION Class BUILDING ELEVATION LOCATION SYSTEM Seismic with Rapid Comments Cat. I? Draindlown 0FC8754 SPENT FUEL PIT HX RTRN ISOL (0) Other FH 401 18 Y FC Y N 0FC8763 REFUELING WTR PURIF PMP OA DISCH CHECK (0) Other AUX 364+18' 12 S FC Y N Area 5 1FC010 REFUELING WTR PURIF PMP SUCT FROM U-1 REFUEL CAV CNMT ISOL (0) Other AUX 364 12 U FC Y N Area 5 1FC8756 Ul SPENT FUEL PIT PMP SUCTION ISOL (0) Other FH 401 18 Y FC Y N 1FC8758 REFUELING WTR PURIF PMP SUCT FROM U-1 RWST (0) Other AUX 364 13 V FC Y N Area 5 1FC8762A SPENT FUEL PIT HX INLET (0) Other FH 401 17 Z FC Y N 1FC8762B Ul SPENT FUEL PIT HX OUTLET (0) Other FH 401 17 Z FC Y N 1FC8766 SPENT FUEL PIT FLTR DEMIN LOOP RTRN TO U-1 RWST CHECK VLV (0 Other 364 14 V FC Y N Area 5 1FC8793 SPENT FUEL PIT PMP DISCH CHECK (0) Other FH 401 17 Y FC Y N 1FC8794 SPENT FUEL PIT FLTR DEMIN LOOP INLT ISOL (0) Other FH 401 17 Y FC Y N 1PI-0627 SPENT FUEL PUMP DISCHARGE PRESSURE GAGE (18) Instrument Racks FH 401 17 AA FC Y N OFC03PA PUMP REFUELING WTR PURIFICATION OA ASMBLY (5) Horizontal Pumps AUX 364 12 S FC Y N Area 5 OPI-FCO03 REFUELING WTR PURIFICATION PUMP OA SUCT PRESS (18) Instrument Racks AUX 365 13 S FC Y N Area 5 OPI-FC005 RFLG WTR PURIF PUMP OA DISCHARGE GAUGE -18) Instrument Racks AUX 364 17 S FC Y N Walkway OTI-FC007 REFUELING WTR PURIFICATION PUMP OA DISCH TEMP IND (19) Temperature Sensors AUX 364 12 S FC Y N Area 5 1FC01A SPENT FUEL PIT HEAT EXCHANGER (21) Tanks and Heat Exchangers FH 401 17 Z FC Y N IFC01P U-1 FUEL POOL COOLING PUMP (5) Horizontal Pumps AUX 401 18 Y FC Y N 1HS-FC001 SPENT FUEL PIT PUMP C/S Box on wall (18) Instrument Racks FH 401 17 Y FC Y N 1PI-0633 SPENT FUEL PIT PUMP SUCTION PRESSURE INDICATO (18) Instrument Racks FH 401 AA-19 FC Y N 1TI-0628 SPENT FUEL POOL HEAT EXCH OUTLET TEMP INDICAT (19) Temperature Sensors FH 426 20 X FC Y N OTIS-0626 SPENT FUEL POOL TEMP INDICATING SWITCH (18) Instrument Racks FH 426 20 X FC Y N B-45 Byron Generating Station Unit 1 12Q0108.20-R-001 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 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Table C-1. Summary of Seismic Walkdown Checklists Anchorage AREA ID DESCRIPTION Configuration WALK-BY COMMENTS PAGE Verified ODO08TB OB SX Pp 2000 GALLON DIESEL Y 46 C -8 OIL STORAGE TANK OFC03PA PUMP REFUELING WTR PURIFICATION OA ASMBLY 0FC8754 SPENT FUEL PIT HX RTRN ISOL N/A 42 SWEL 2 C -15 0FC8763 REFUELING WTR PURIF PMP OA N/A 36 SWEL 2 C -18 DISCH CHECK OPI-FC003 REFUELING WTR PURIFICATION N/A 44 SWEL 2 C -21 PUMP 0A SUCT PRESS I OPI-FC005 RFLG WTR PURIF PUMP OA N/A 61 SWEL 2 C -24 DISCHARGE GAUGE OSX02PB DIESEL DRIVEN SX MAKE-UP Y 45 C -27 PUMP ASSY -MOV OA SXCT TO BASIN OSX162A BPV N/A 18 C -32 BYP VLV ___ __REFUELING WTR PURIFICATION 0TI-FC007 PUMP OA DISCH TEMP IND N/A 36 SWEL 2 C -36 OTIS-0626 SPENT FUEL POOL TEMP N/A 40 SWEL 2 C -39 INDICATING SWITCH OVC01JA CONT RM HVAC LOCAL CONT PAN N 9 C -42 ASMBLY OVC08Y TRAIN B MAKEUP AIR FLTR UNIT N/A 5 C -48 FAN OB DISCH FLOW CONTROL TRAIN B EMERGENCY MAKEUP INTAKE FROM TURB BLDG OVC15J MCR U-1 HVAC START PNL N 9 C -56 OWO01CB OB MCR CHILLER Y 64a C -59 OWWO19A ASSY -AOV OB DEEP WELL PP N/A 18 C-62 OWW01 PB TO OA SXCT LCV 1AF005E S/G 1A FLOW CONT VLV ASMBLY; N/A 47 C -65 41" 1AF006B AUXILIARY FEEDWATER PMP 1B N/A 58 C -69 SX SUCT VLV ASMBLY; 6" 1AF017B AUXILIARY FEEDWATER PMP 1B N/A 58 C -72 SX SUCT VLV ASMBLY; 6" 1AF01EA-1 AF PUMP 1B BATTERY CHARGER N 58 C -75 IAF0l EB-A AF BATTERY Bank B BATT A AUXILIARY FEEDWATER PUMP 1B 1AF01PB DIESEL DRIVEN AUX FEED PUMP Y 58 C -81 11 BASMBLY 1AF024 AF PP SX RECIRC VLV_ASMBLY; N/A 58 C -85 13"1 Table C-1 Page 1 of 6 C-2 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Anchorage AREA ID DESCRIPTION Configuration WALK-BY COMMENTS PAGE Verified IAP06E 4160 VOLT ESF SWITCH BUS 142 Y 32 1AP11E EQ 480V ESF UNIT SUB 131X 33 C-97 TRANSFORMER 1AP086 1AP12E ASSY -480V ESF SWGR 132X Y 32 1AP13E 480V ESF UNIT SUBSTA 132X Y 32 C -108 XFMR 1AP21E 480V AUX BLDG ESF MCC Y 36 C-112 131X1 XFORMER 1AP22E 480V AUX BLDG ESF MCC 131X3 Y 59 C- 115 ASMBLY EQ 480 V AUX BLDG ESF MCC 1AP24E I2AMBYY 57 C- 119 132X3 ASMBLY 1AP25E ASSY -480V AUX BLDG ESF MCC y 54 C -123 131X2 1IAP27E EQ 480V AUX BLDG MCC 132X2 Y 53 C -127 ASMBLY ASSY -480V AUX BLDG MCC 1AP38E 13XAY 50 C- 131 133X1A 1AP92E ASSY -480V SXCT MCC 132Z1, Y 20 C -135 SOUTH ELEC RM 1AP93E ASSY -480V SXCT MCC 131Z1, Y 16 C -139 NORTH ELEC RM 1AP98E ASSY -480V ESF SXCT UNIT Y 20 C -144 SUBSTA 132Z, SOUTH ELEC RM 1AP99E ASSY -480V ESF SXCT UNIT Y 16 0-149 SUBSTA 131Z, NORTH ELEC RM 1CC01PB 1B PUMP, COMPONENT COOLING y 61 C- 153 12X14-18 M66-3 ASMBLY 100C685 CC FROM RC PMPS THERMAL N/A 39 C -156 BARRIER ISOL VLV ASMBLY; 3" 1CV01PB PUMP,IB CENTRIFUGAL Y 37 C -159 CHARGING ASMBLY 1 B CENTRIFUGAL CHARGING 1 CV02SB PUPGA OLRN 37 C -162 PUMP GEAR COOLER________

1 CVI 12E RWST TO CHG PMPS SUCT VLV N/A 39 C -165 (C/S AT 1 PM05J) ASMBLY; 8" 10CV8152 ASSY -AOV U-1 LTDWN HDR ISOL N/A 39 0-168 VLV (EOP VLV)IDC01IE 125V BATTERY 111 DIV. 11 AND Y 29 C-171 Rack I DC02E 125V BATTERY 112 DIV. 12.and Y 31 0-174 Rack 1DC04E 125V DC BATT CHGR 112 Y 30 C -177 1IDCO5E 125V DC ESF DISTR CENTER BUS Y 28 C -180_____ ____ 111 _ _ _ _ _ _ _ _ _ _ _ _Table C-1 Page 2 of 6 C-3 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Anchorage AREA ID DESCRIPTION Configuration WALK-BY COMMENTS PAGE Verified 1 DC06E 125V DC ESF DISTR CENTER BUS y 30 C-184 112 lDC10J 125V DC FUSE PANEL -DIV. 11 N 28 C -188 1DC11J 125V DC FUSE PANEL- DIV. 12 N 30 C- 192 1DG01KB 1B DIESEL GENERATOR Y 23 C -195 1DO01TB DIESEL OIL STORAGE TANK 1B Y 26 C -199 1DO10T 500 GAL DIESEL OIL DAY TANK Y 58 C -203 (AF)REFUELING WTR PURIF PMP IFC010 SUCT FROM U-1 REFUEL CAV N/A 39 SWEL 2 C -206 CNMT ISOL 1FC01A SPENT FUEL PIT HEAT Y 41 SWEL 2 C -209 EXCHANGER 1FC01P U-1 FUEL POOL COOLING PUMP Y 42 SWEL 2 C -212 1FC8756 UI SPENT FUEL PIT PMP N/A 42 SWEL2 C -216 SUCTION ISOL 1FC8758 REFUELING WTR PURIF PMP N/A 39 SWEL 2 C -219 SUCT FROM U-1 RWST 1FC8762A SPENT FUEL PIT HX INLET N/A 41 SWEL 2 C -222 1FC8762B UI SPENT FUEL PIT HX OUTLET N/A 41 SWEL 2 C -225 SPENT FUEL PIT FLTR DEMIN 1FC8766 LOOP RTRN TO U-1 RWST CHECK N/A 39 SWEL 2 C -228 VLV SPENT FUEL PIT PMP DISCH 1FC8793 CHECK N/A 41 SWEL 2 C -231 1FC8794 SPENT FUEL PIT FLTR DEMIN N/A 41 SWEL 2 C -234 LOOP INLT ISOL____IFT-0121 CHARGING LINE D/P CELL FLOW N/A 61 C -237 XMITTR 1FT-0132 LETDOWN FLOW D/P CELL N/A 59 C -240 1FT-AF014 AFTOSG1BFLOW N/A 61 C -243 TRANSMITTER IHS-FC001 SPENT FUEL PIT PUMP C/S Box on N 42 SWEL 2 C -246 wall lIP05E INVERTER INST BUS 111 1-3371 Y 28 C-249 AB1 lIP07E INVERTER INST BUS 113 1-3371 Y 28 C -252 AB1 lIP08E INVERTER INST BUS 114 1-3371 Y 30 C -255 ABB1 EQ PRESSURIZER LEVEL 1 LT-0459 TRANSMITTER N/A Outage-6 C -258 S/G 1A LEVEL LOOP D/P XMTTR 1LT-0518 2/FILLED LEG N/A Outage-3 C -261 1 LT-0932 REF WTR STG TK LVL D/P XMTTR N/A 38 C -264 Table C-1 Page 3 of 6 C-4 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Anchorage AREA ID DESCRIPTION Configuration WALK-BY COMMENTS PAGE Verified lMS001A MS ISOL VLV LOOP 1A ASMBLY; N/A 15 C -267 30-1/4" 1MS018A S/G 1A PORV ASMBLY; 8" N/A 15 C- 270 1MS018B S/G 1B PORV ASMBLY; 8" N/A 13 C -274 U-1 PROC I&C RACK PROTECT CH 1PA01J N 8 C -277 1 CAB 1 I PA02J U-1 PROC I&C RACK PROTECT CH N 8 C -280 1 PA03J U-i PROC I&C RACK PROTECT CH N 8 C -283 3 CAB 3 U-1 PROC I&C RACK PROTECT CH I PA03J N 8 C -286 4 CAB 4 1IPA06J U-1 PROC I&C RACK CONT GRP 2 N 8 C -289 4 CAB 6 1IPA07J PROC I&C RACK CONT GRP 3 CAB N 8 C -292 7 1 PA08J U-1 PROC I&C RACK N 8 C -295 1 PA09J CAB PROT SYST SOL ST RX/ESF N 8 C -298 TRN A 0-3371 B ABI 1 PAI OJ CAB PROT SYST SOL ST RX/ESF N 8 C-302 TRN B 0-3371B AB1 CAB TEST SAFEGUARD TRN B 1IPA12J N 8 C -305 AB1 1IPAI 4J CAB ESF SEQ/ACT TRN B 0-3371 B N 8 C -308 AB1 1 PA27J CAB RELAY AUX SAFEGUARD N 8 C -311 TRN A 0-3371 B AB1 CAB RELAY AUX SAFEGUARD 1PA28J TRB-31A1N 8 C -314 TRN B 0-3371 B AB1 1 PA33J CAB CONT SYSTEM ESF 11 0- N 8 C-318 3371 B AB1 1IPA34J CAB CONT SYSTEM ESF 12 0- N 8 C-321 3371B AB1 CAB HJTC RX VESSEL LEVEL CH 1PA51J A-3BA1N 8 C -324 A 0-3371 B AB1 I PA52J CAB HJTC RX VESSEL LEVEL CH N 8 C-327 B 0-3371 B AB1 1 PI-0627 SPENT FUEL PUMP DISCHARGE N/A 44 SWEL 2 C -330 PRESSURE GAGE SPENT FUEL PIT PUMP SUCTION 1 PI-0633 PESSUE IT N/A 44 SWEL 2 C -333 PRESSURE INDICATO 1 PL08J 1 B DG CONTROL PANEL N 23 C -336 1PM05J MAIN CONTROL BOARD Y 1 C -340 1PT-0516 S/G LOOP 1A STM PRESS XMTTR N/A 14 C -343 1 RD05E REACTOR TRIP SWITCHGEAR Y 28 C -347 Table C-1 Page 4 of 6 C-5 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Anchorage AREA ID DESCRIPTION Configuration WALK-BY COMMENTS PAGE Verified 1RH01PB PUMP,1B RESIDUAL HEAT Y 66 C -350 REMOVAL ASMBLY I 1RHO1 PB-A RH PUMP 1B SEAL COOLER N/A 66 C -353 I RH607 RESIDUAL HEAT REMOVAL HX 11B N/A 64 C -356 FLOW CONT VLV ASMBLY; 8" RC LOOP IC TO RH PMP lB SUCT 1RH8702A RC LV 1 C N/A Outage-4 C -359________ISOL VLV ASMBLY; 12"'_____

__1RY32MA PORV ACCUMULATOR 1A N Outage-1 C -363'PZR PORV (C/S AT 1PM05J) N/A Outage-2 C -367 1 RY455A ASMBLY PW TO PRT CONTAINMENT 1 RY8028 ISOLATIONTVLVTN/A 39 C -371 ISOLATION VLV iSI0lT REFUELING WATER STORAGE N 12 C -374 TANK CHG PMP TO COLD LEGS 1S18801B INJECTION ISOL VLV (C/S AT N/A 39 C -377 1PM05J) ASMBLY; 4" 1S18804B ASSY -MOV 1B RH HX TO13SI N/A 38 C-380 PP SUCT HDR ISOL VLV 1S18809B RH TO COLD LEGS 11B/1C ISOL N/A 39 C -383 VLV (1PM06J) ASMBLY; 8" 1SX005 U-0 CC HX INLT VLV ASMBLY; 30" N/A 52 C -386 1SX01FB 1B SX PP DSCH STRN Y 52 C -389 1SX01PB PUMP, 1 B ESSENTIAL SER WTR Y 52 C -393 ASMBLY 1SX169B DG 1B SX VLV ASMBLY; 10" N/A 23 C -396 SX SUP VLV TO ENG Driven CLG 1SX173 WTR PP FOR Diesel Driven AF N/A 58 C -399 PP ASSY; 6" RHR LP 1A RETURN 1TE-0604 TEMPERATRETRT N/A 39 C -402 TEMPERATURE RTD 1TE-RC022A RC WIDE RANGE LP 1A TEMP N/A Outage-7 C -405 1TI-0628 SPENT FUEL POOL HEAT EXCH N/A 41 SWEL 2 C -408 OUTLET TEMP INDICAT 1VA01SB 1B SX Pp Cub Cooler ESSENTIAL Y 52 C -411 SERVICE WATER PUMP 95-10 1VA02SB 1B RHR PUMP ROOM CUB CLR Y 66 C-414 ASMBLY 1VA06SA COOLERCENTRIFUGAL Y 62 C -418 CHARGING PUMP 1A 1B DIESEL DRIVEN AF PUMP 1VA08CB N/A 58 C -421 CUBICLE CLR (IVA08S) 1B FAN CENTRIFUGAL CHARGING 1VA11J PCUBICLE COOLER LOCAL N 37 C -424 1___ _ ICONTROL PANEL I I IVD01CB 1B DG ROOM HVAC FAN ASMBLY Y 23 C -427 Table C-1 Page 5 of 6 C-6 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Anchorage AREA ID DESCRIPTION Configuration WALK-BY COMMENTS PAGE Verified 1VE05C ASSY -U-1 MISC ELEC EQUIP RM N 30 C -431 DIV 12 EXH FAN I CNMT ESS'L SERVICE WATER lVP01AA COIL 1A (RCFC) N Outage-5 C -434 1 VX07J ESF SWGR RM DIV 12 HVAC y 32 C-439_DMPR START PNL I I Table C-1 Page 6 of 6 C-7 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-1 2-161 Sheet 1 of 4 Status: Y N U Seismic Walkdown Checklist (SWC)Equipment ID No.: ODO08TB Equipment Class: (21) Tanks and Heat Exchangers Equipment

==

Description:==

OB SX Pp 2000 GALLON DIESEL OIL STORAGE TANK Project: Byron 1 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 M-1227 Sheet I Revision R 6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

C-8 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: DO08TB Equipment Class: (21) Tanks and Heat Exchangers Equipment

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Description:==

OB SX Pp 2000 GALLON DIESEL OIL STORAGE TANK 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?

Lights supported on S-hooks. See IR 1399104 for open S-hooks. Note that the S-hooks are partially open and it is unlikely that they would become disengaged in a seismic event. Also lights would not damage equipment if they fell.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?

Some leaking (not diesel fuel, appears to be water) on floor but not a structural/seismic issue.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-9 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: ODO08TB Equipment Class: (21) Tanks and Heat Exchangers Equipment

==

Description:==

0B SX Pp 2000 GALLON DIESEL OIL STORAGE TANK Photos C-10 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: Equipment Class: Eauiwment

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Description:==

OD008TB (21) Tanks and Heat Exchangers OB SX Pp 2000 GALLON DIESEL OIL STORAGE TANK C-11 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0FC03PA Equipment Class: (5) Horizontal Pumps Equipment

==

Description:==

PUMP REFUELING WTR PURIFICATION QA ASMBLY Project: Byron 1 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% 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-1220 Sheet 6 Revision J Detail 64A Pump contaminated but bolt diameter visually verified 6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

C-12 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Seismic Walkdown Checklist (SWC)Status: MZ N U Equipment ID No.: OFC03PA Equipment Class: (5) Horizontal Pumps Equipment

==

Description:==

PUMP REFUELING WTR PURIFICATION OA 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?

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-13 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OFC03PA Equipment Class: (5) Horizontal Pumps Equipment

==

Description:==

PUMP REFUELING WTR PURIFICATION OA ASMBLY Photos ui-LuuirA tyron 1 & z us-u-iz u~u C-14 Byron Generating Station Unit 1 12Q0108.20-R-001 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

==

Description:==

SPENT FUEL PIT HX RTRN ISOL Project: Byron 1 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.Anchoracqe

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-15 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0FC8754 Equipment Class: (0) Other Equipment

==

Description:==

SPENT FUEL PIT HX RTRN ISOL 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?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-16 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 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 Photos 0FC8754 Byron 1 & 2 8-9-12 017 C-1 7 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: ML N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0FC8763 Equipment Class: (0) Other Equipment

==

Description:==

REFUELING WTR PURIF PMP 0A DISCH CHECK Project: Byron 1 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 382.00 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% 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-18 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0FC8763 Equipment Class: (0) Other Equipment

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Description:==

REFUELING WTR PURIF PMP OA DISCH CHECK 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 8/8/12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-1 9 Byron Generating Station Unit 1 1200108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0FC8763 Equipment Class: (0) Other Equipment

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Description:==

REFUELING WTR PURIF PMP OA DISCH CHECK Photos wurutoi tyron 1 & z u4z C-20 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet I of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OPI-FC003 Equipment Class: (18) Instruments on Racks Equipment

==

Description:==

REFUELING WTR PURIFICATION PUMP OA SUCT PRESS Project: Byron 1 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 365.00 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?

Instrument securely mounted to well-anchored rack Yes C-21 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OPI-FC003 Equipment Class: (18) Instruments on Racks Equipment

==

Description:==

REFUELING WTR PURIFICATION PUMP OA SUCT PRESS 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 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-22 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OPI-FC003 Equipment Class: (18) Instruments on Racks Equipment

==

Description:==

REFUELING WTR PURIFICATION PUMP OA SUCT PRESS Photos uUII-L;uu3 Byron 1 & 2 t-t-12 )u44 umI-i- uuuj iiyron 1 & z iu-5-i z u4j C-23 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OPI-FC005 Equipment Class: (18) Instruments on Racks Equipment

==

Description:==

RFLG WTR PURIF PUMP OA DISCHARGE GAUGE Project: Byron 1 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?

Instrument is securely attached to well-supported rack Yes C-24 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OPI-FC005 Equipment Class: (18) Instruments on Racks Equipment

==

Description:==

RFLG WTR PURIF PUMP OA DISCHARGE GAUGE 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-25 Byron Generating Station Unit 1 12Q0108.20-R-001 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 OPI-FC005 (18) Instruments on Racks RFLG WTR PURIF PUMP OA DISCHARGE GAUGE urI-rLuuuo tyron 1 &; i j-zu-lz uoo C-26 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 5 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OSX02PB Equipment Class: (6) Vertical Pumps Equipment

==

Description:==

DIESEL DRIVEN SX MAKE-UP PUMP Project: Byron 1 SWEL Location (Bldg, Elev, Room/Area):

RSH, 686.50 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% 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-1227 Sheet 2 Revision K Detail 13 6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

C-27 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 5 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OSX02PB Equipment Class: (6) Vertical Pumps Equipment

==

Description:==

DIESEL DRIVEN SX MAKE-UP PUMP 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 8-9-12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-28 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 5 Status: MI- N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OSX02PB Equipment Class: (6) Vertical Pumps Equipment

==

Description:==

DIESEL DRIVEN SX MAKE-UP PUMP Photos OSX02PB Byron 1 & 2 8-9-12 059 C-29 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 4 of 5 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OSX02PB Equipment Class: (6) Vertical Pumps Equipment

==

Description:==

DIESEL DRIVEN SX MAKE-UP PUMP 0 C-30 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 5 of 5 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OSX02PB Equipment Class: (6) Vertical Pumps Equipment

==

Description:==

DIESEL DRIVEN S ( MAKE-UP PUMP C-31 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. I Correspondence No.: RS-12-161 Sheet 1 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0SX162A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

ASSY -MOV 0A SXCT TO BASIN BYP VLV Project: Byron I 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-32 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0SX162A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

ASSY -MOV OA SXCT TO BASIN BYP VLV 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?

Hairline crack in nearby wall is small and not a structural/seismic concern.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-33 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OSX162A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

ASSY -MOV OA SXCT TO BASIN BYP VLV Photos OSX162A Byron 1 & 2 179 C-34 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OSX162A Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

==

Description:==

ASSY -MOV GA SXCT TO BASIN BYP VLV C-35 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OTI-FC007 Equipment Class: (19) Temperature Sensors Equipment

==

Description:==

REFUELING WTR PURIFICATION PUMP OA DISCH TEMP IND Project: Byron 1 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-36 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OTI-FC007 Equipment Class: (19) Temperature Sensors Equipment

==

Description:==

REFUELING WTR PURIFICATION PUMP GA DISCH TEMP IND 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 8/8/12 pm Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-37 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: [-Y N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OTI-FC007 Equipment Class: (19) Temperature Sensors Equipment

==

Description:==

REFUELING WTR PURIFICATION PUMP OA DISCH TEMP IND Photos None.C-38 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OTIS-0626 Equipment Class: (18) Instruments on Racks Equipment

==

Description:==

SPENT FUEL POOL TEMP INDICATING SWITCH Project: Byron 1 SWEL Location (Bldg, Elev, Room/Area):

FH, 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.Anchora-qe

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?

Instrument securely supported on well-anchored rack Yes C-39 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: [M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OTIS-0626 Equipment Class: (18) Instruments on Racks Equipment

==

Description:==

SPENT FUEL POOL TEMP INDICATING SWITCH 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?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 8/9/12 am Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-40 Byron Generating Station Unit 1 12Q0108.20-R-001 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:==

OTIS-0626 (18) Instruments on Racks SPENT FUEL POOL TEMP INDICATING SWITCH Photos OTIS-0626 Byron 1 & 2 8-9-12 002 C-41 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 6 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC01JA Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

==

Description:==

CONT RM HVAC LOCAL CONT PAN ASMBLY Project: Byron 1 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%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.)

Not Applicable

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

Panel is welded at base with greater than 2" of weld at approximately 8" spacing which exceeds the typical cabinet base weld.Yes C-42 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 6 Status: Y] N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC01JA Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

==

Description:==

CONT RM HVAC LOCAL CONT PAN ASMBLY 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?

Roof drain line with Victau/ic couplings enters room and drops down and up (similar to a U shape) and exits room. Line could swing from side to side resulting in leaking at the top couplings however the equipment below is partially sealed with closed entry points and tops so no water damage could occur. IR 1397711 was written.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-43 Byron Generating Station Unit I 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 6 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC01JA Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

==

Description:==

CONT RM HVAC LOCAL CONT PAN ASMBLY Photos C-44 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 4 of 6 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVCO1JA Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

==

Description:==

CONT RM HVAC LOCAL CONT PAN ASMBLY C-45 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 5 of 6 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: 0VC01JA Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

==

Description:==

CONT RM HVAC LOCAL CONT PAN ASMBLY C-46 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 6 of 6 Status: r N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC01JA Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

==

Description:==

CONT RM HVAC LOCAL CONT PAN ASMBLY C-47 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 3 Status: M-j N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC08Y Equipment Class: (10) Air Handlers Equipment

==

Description:==

TRAIN B MAKEUP AIR FLTR UNIT FAN OB DISCH FLOW CONTROL Project: Byron 1 SWEL Location (Bldg, Elev, Room/Area):

Auxiliary, 463.00 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?

An anchorage verification/inspection is not required since the equipment is mounted in-line without direct anchorage to the civil structure Yes C-48 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC08Y Equipment Class: (10) Air Handlers Equipment

==

Description:==

TRAIN B MAKEUP AIR FLTR UNIT FAN OB DISCH FLOW CONTROL 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 8/6/12 pm M Delaney and P Gazda Evaluated by: Marlene Delaney Date: 10/5/2012 Philip Gazda 10/5/2012 C-49 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC08Y Equipment Class: (10) Air Handlers Equipment

==

Description:==

TRAIN B MAKEUP AIR FLTR UNIT FAN 0B DISCH FLOW CONTROL Photos None.C-50 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 1 of 5 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC09Y Equipment Class: (10) Air Handlers Equipment

==

Description:==

TRAIN B EMERGENCY MAKEUP INTAKE FROM TURB BLDG Project: Byron 1 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%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?

An anchorage verification/inspection is not required since the equipment is mounted in-line without direct anchorage to the civil structure Yes C-51 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 2 of 5 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC09Y Equipment Class: (10) Air Handlers Equipment

==

Description:==

TRAIN B EMERGENCY MAKEUP INTAKE FROM TURB BLDG 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?

Water on the floor is not a structural/seismic issue and is not near critical components.

The bent cable tray cover is not a structural/seismic issue since the cover is not a structural component.

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-52 Byron Generating Station Unit 1 12Q0108.20-R-O01 Rev. 1 Correspondence No.: RS-12-161 Sheet 3 of 5 Status: Y N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC09Y Equipment Class: (10) Air Handlers Equipment

==

Description:==

TRAIN B EMERGENCY MAKEUP INTAKE FROM TURB BLDG UV 1.S 042 C-53 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 4 of 5 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC09Y Equipment Class: (10) Air Handlers Equipment

==

Description:==

TRAIN B EMERGENCY MAKEUP INTAKE FROM TURB BLDG C-54 Byron Generating Station Unit 1 12Q0108.20-R-001 Rev. 1 Correspondence No.: RS-12-161 Sheet 5 of 5 Status: M N U Seismic Walkdown Checklist (SWC)Equipment ID No.: OVC09Y Equipment Class: (10) Air Handlers Equipment

==

Description:==

TRAIN B EMERO ICY MAKEUP INTAKE FROM TURB BLDG C-55