NL-12-2271, Vogtle, Unit 2, SNCV061-RPT-02, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 14

Vogtle, Unit 2, SNCV061-RPT-02, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 14

ML12355A035
Person / Time
Site:	Vogtle
Issue date:	11/26/2012
From:	Volodarsky D Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
References
NL-12-2271 SNCV061-RPT-02, Ver 1.0
Download: ML12355A035 (137)

Text

NO. SNCV061-RPT-02 PROJECT REPORT VERSION 1.0 COVER SHEET Page I of 49 Vogtle Unit 2 SEISMIC WALKDOWN REPORT, RER SNC432485 For Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic Prepared by: Reviewed by: Approved by: (ENERCON)Project Manager or Designee David Volodarsky Patrick Kelly fe1 #Bill Henne Date: Date: Date:/-ZO- 201/Z 0i- 2 -2OJ2.Approved by: I (SNC)TeeMcna Lead or Deigwe'Peer Review Team Leader Approved by:.(SNO Melanie Brown David Whitman Date: Date: Project Manager or Designee VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 2 OF 49 TABLE OF CONTENTS Section Title Page 1.0 SCOPE AND OBJECTIVE

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4 2.0 SEISMIC WALKDOWN PROGRAM IMPLEMENTATION APPROACH ..................

5 3.0 SEISMIC LICENSING BASIS

SUMMARY

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6 3.1 SAFE SHUTDOWN EARTHQUAKE

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6 3.2 DESIGN CODES, STANDARDS, AND METHODS ...........................................................

7 4.0 PERSONNEL QUALIFICATIONS

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8 4.1 OVERVIEW OF PROJECT RESPONSIBILITIES

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9 4.2 TEAM EXPERIENCE SUMMARIES

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11 5.0 IPEEE VULNERABILITIES REPORTING

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17 6.0 SEISMIC WALKDOWN EQUIPMENT LIST DEVELOPMENT

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18 6.1 D EV ELO PM EN T O F SW EL 1 ................................................................................................

18 6.2 DEVELOPMENT OF SWEL 2 ..........................................................................................

20 7.0 SEISMIC WALKDOWNS AND AREA WALK-BYS ......................................................

22 7.1 IN A CCESSIBLE ITEM S. ..................................................................................................

24 8.0 RE SULTS ..................................................................................................................................

31 8.1 POTENTIALLY ADVERSE SEISMIC CONDITIONS

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31 8.2 EQUIPMENT OPERABILITY

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41 8.3 PL A N T C H A N G E S .................................................................................................................

42 8.4 OTHER NON-SEISMIC CONDITIONS

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42 9.0 PEER REVIEW ........................................................................................................................

43 9.1 PEER REV IEW PRO CESS ..................................................................................................

43 9.2 PEER REVIEW RESULTS

SUMMARY

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43

10.0 REFERENCES

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48 11.0 ATTACHMENTS

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49 VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 3 OF 49 EXECUTIVE

SUMMARY

The Seismic Walkdowns at Vogtle Unit 2 in response to the NRC 50.54(f) letter dated March 12, 2012,"Enclosure 3, Recommendation 2.3: Seismic" are not complete as all items on the SWEL have not been accessible.

A supplementary report will be required.

The walkdowns are being performed using the methodology outlined in the NRC endorsed "Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic" (EPRI Report number 1025286).Plant Vogtle Unit 2 had no significant degraded, non-conforming or unanalyzed conditions that warranted modification to the plant. Plant Vogtle Unit 2 had no as-found conditions that would prevent SSCs from performing their required safety functions.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 4 OF 49 1.0 SCOPE AND OBJECTIVE The objective of this report is to document the results of the Seismic Walkdowns at Vogtle Unit 2 in response to the NRC 50.54(f) letter dated March 12, 2012, "Enclosure 3, Recommendation 2.3: Seismic" (Reference 10.1).The Seismic Walkdowns followed the guidance contained in EPRI Report 1025286 (Reference 10.2), which was endorsed by the NRC on May 31, 2012. The scope of the walkdowns was to identify potentially degraded, unanalyzed, or nonconforming conditions relative to the seismic licensing basis.The 2.3: Seismic Walkdowns for Vogtle Unit 2 are not complete as all items on the SWEL have not been accessible.

A supplementary report will be required.

This report documents the findings from all Seismic Walkdowns and Area Walk-bys completedto date.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 5 OF 49 2.0 SEISMIC WALKDOWN PROGRAM IMPLEMENTATION APPROACH The requirements of the 50.54(f) Letter are satisfied by application of and compliance with the NRC endorsed methodology provided in EPRI Report 1025286 (Reference 10.2). In accordance with EPRI Report 1025286 (Reference 10.2), the following topics are addressed in this report: " Documentation of the seismic licensing basis for the SSCs in the plant (Section 3.0);" Assignment of appropriately qualified personnel (Section 4.0);* Reporting of actions taken to reduce/eliminate seismic vulnerabilities identified by the Individual Plant Examination for External Events (IPEEE) program (Section 5.0);* Selection of SSCs to be inspected in the plant (Section 6.0);" Performance of the Seismic Walkdowns and Area Walk-bys (Section 7.0);* Evaluation of potentially adverse seismic conditions with respect to the seismic licensing bases (Section 8.0); and" Performance of Peer Reviews (Section 9.0).Supplemental guidance/clarification for opening cabinets to inspect for adverse conditions was received on September 18, 2012. This required the opening of cabinets, electrical boxes, and switchgear to inspect the internals for potentially adverse seismic conditions, even when opening the components was not required to inspect the anchorage.

At the time of this supplemental guidance/clarification, the Vogtle Unit 2 walkdowns were complete.

However, the affected components were identified and scheduled for re-inspection with component doors opened. Further discussion is provided in Section 7.0.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 6 OF 49 3.0 SEISMIC LICENSING BASIS

SUMMARY

This section provides a summary of the licensing bases for the Seismic Category I Structures, Systems, and Components (SSCs) in the plant. It includes a discussion of the Safe Shutdown Earthquake (SSE)and the codes and standards used in the design of the Seismic Category I SSCs for meeting the plant-specific seismic licensing basis requirements.

3.1 SAFE SHUTDOWN EARTHQUAKE The plant site geologic and seismologic investigations are covered in Section 2.5 of the Vogtle FSAR (Reference 10.7). Based on this data, the peak ground accelerations for Safe Shutdown Earthquake (SSE) and Operating Basis Earthquake (OBE) are established as 0.20g and 0.12g, respectively, as discussed in subsection 2.5.2 (Reference 10.7).The VEGP site design response spectra are provided in Figures 3.7.B.1-1 and 3.7.B.1-2 for the horizontal and vertical components of the SSE and in Figures 3.7.B.1-3 and 3.7.B.1-4 for the horizontal and vertical components of the OBE (Reference 10.7). The design response spectra are in conformance with Regulatory Guide 1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants (Reference 10.5). The ground spectra were applied to models of the various structures and amplified in-structure response spectra were generated taking into account the flexibility of the soil and structure.

POWER GENERATION DESIGN BASES Seismic Category I systems, structures and components are designed so that stresses remain within normal code allowable limits during the OBE and to ensure that they will perform their safety-related functions during and/or after an SSE.MAJOR COMPONENT DESIGN BASES The horizontal and vertical OBE and SSE in-structure response spectra curves form the basis for the seismic qualification and design of Category I SSCs and for demonstrating the structural integrity of Seismic Category II SSCs, where required.

In addition, systems running between structures shall be designed to withstand the seismic relative displacements.

The seismic analysis of safety related systems, equipment, and components is based on the response spectra method, time-history method, or equivalent static method.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 7 OF 49 All Seismic Category I safety-related instrumentation and mechanical and electrical equipment meet the requirements and recommendations of IEEE 344-1975.

Damping values are consistent with those specified in Regulatory Guide 1.61 (Reference 10.10).3.2 DESIGN CODES, STANDARDS, AND METHODS The design codes and standards for seismic qualification are listed in Chapter 3 of the Vogtle FSAR (Reference 10.7). Examples of the pertinent codes, standards, and methods used in the original design of Vogtle Unit 2 are listed below.* ANSI B3 1.1, Power Piping" ANSI/ASME Boiler and Pressure Vessel Code,Section III, Rules for Construction of Nuclear Power Plant Components, Division 1" ANSI/ASME Boiler and Pressure Vessel Code,Section III, Division 1-A, Appendix N, Dynamic Analysis Methods" IEEE 317-1976, Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations IEEE 323-1974, Standard for Qualifying Class lE Equipment for Nuclear Power Generating Stations IEEE 344-1975, Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations* Manual of Steel Construction (AISC), 7th Edition VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR FOR -VERSION 1.0 RESOLUTION OF FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 8 OF 49 4.0 PERSONNEL QUALIFICATIONS Table 4-1 identifies the project team members and their project responsibilities per EPRI Report 1025286 (Reference 10.2). Table 4-2 identifies the Peer Review Team members and responsibilities.

Section 4.1 provides an overview of the project responsibilities.

Section 4.2 includes brief experience summaries for all project personnel in alphabetical order.Table 4-1. Project Team Members and Responsibilities Site Equipment Seismic Licensing Name Point of Selection

/ Plant Walkdown Basis Contact IPEEE Operations Engineer Reviewer (POC) Reviewer (SWE)Justo Chacon X X X James Dovel X X Parimal Gandhi X X Jose Hernandez X X X X Thomas Petrak X X Winston Stewart* X X David Volodarsky X X Matthew X X Wilkinson Frank Yao X X VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 9 OF 49 Table 4-2. Peer Review Team Members and Responsibilities Peer SWEL Walkdown Licensing Submittal NameReview SWeL Waer Basis Report Name Tem Peer Peer Pe Leader Reviewer Reviewer Peer Leader Reviewer Reviewers Robert Ashworth

• X X X X Melanie Brown* X X X X Richard Starck

• X X Kenneth Whitmore

• X X X X Notes (Table 4-1 and Table 4-2): 1)

• Indicates Seismic Capability Engineer 2) As stated in Section 7.0, all potentially adverse conditions were entered into the plant Corrective Action Program (CAP) system. However, as part of the process of entering the condition into the CAP, the SWEs made a preliminary assessment of the condition with respect to the plant licensing basis. Further licensing basis reviews were performed as discussed in Section 8.0 as part of the CAP resolution process by personnel not directly involved in the walkdowns.

4.1 OVERVIEW OF PROJECT RESPONSIBILITIES The Site Point of Contact (POC) is a site engineer from Southern Nuclear that has experience with the site equipment, site procedures, plant operations, and overall personnel organization.

The site POC coordinated site access for walkdown personnel and any resources required for the walkdowns such as inspection equipment and support from plant operations.

The POC was responsible for development of the walkdown schedule and any updates to the schedule based on equipment availability.

Equipment Selection Personnel (ESP) were responsible for identifying the sample of SSCs for the Seismic Walkdowns.

The ESP have knowledge of plant operations, plant documentation, and VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 10 OF 49 associated SSCs. The ESP also have knowledge of the IPEEE program. For this project, site engineers and plant operations personnel participated in the equipment selection.

The ESP also performed the responsibilities of the IPEEE Reviewers.

The IPEEE Reviewers also ensured that the walkdown scope included a sample of equipment that had IPEEE seismic vulnerabilities.

Plant Operations Personnel provided detailed review of the sample of SSCs to ensure the walkdown scope included equipment located in a variety of environments, equipment in a variety of systems, and equipment accessible for a walkdown.

For the Vogtle Unit 2 project, the Plant Operations Personnel (POP) is a former licensed Senior Reactor Operator.The SWEs were trained on the NTTF Recommendation 2.3: Seismic, and on the material contained in EPRI Report 1025286 (Reference 10.2). SWEs that had previously completed the Seismic Walkdown Training Class developed by the Seismic Qualification Utilities Group (SQUG) were not required to complete training on the NTTF Seismic recommendations but were trained on the differences between SQUG activities and activities associated with the NTTF Seismic recommendations.

The Licensing Basis Reviewer was responsible for determining whether any potentially adverse seismic conditions identified by the SWEs met the plant seismic licensing basis. The Licensing Basis Reviewer has knowledge of and experience with the seismic licensing basis and documentation for the SSCs at Vogtle.A Peer Review Team was formed for this project to provide both oversight and review of all aspects of the walkdowns.

'The Peer Review Team members have extensive experience in seismic design and qualification of structures, systems and components as well as extensive field experience.

The Peer Review Team for this project interfaced with the ESP and SWEs to ensure that the walkdown program satisfied the guidance in EPRI Report 1025286 (Reference 10.2).

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 11 OF 49 4.2 TEAM EXPERIENCE SUMMARIES Robert Ashworth, SCE (MPR)Mr. Ashworth has more than six years of experience providing engineering solutions for a wide variety of nuclear power plant components and systems. His experience includes equipment walkdowns at industrial facilities to assess material condition, structural modeling and analyses, and seismic qualification in accordance with current industry standards for mechanical and electrical equipment in nuclear power plants. Mr. Ashworth has completed the training course for the EPRI Report 1025286 and is also a Seismic Capability Engineer (SCE) as defined in the SQUG Generic Implementation Procedure (GIP) for resolution of unresolved safety issue (USI) A-46.Melanie Brown, SCE (SNC)Ms. Brown has over 31 years of experience with Southern Company, the majority of which has been serving the nuclear fleet. Ms. Brown's most recent assignment was as a Seismic Qualification Engineer in the Fleet Design Department, where she was responsible for performing activities associated with the Governance, Oversight, Support, and Perform (GOSP) Model including:

0 Management of the seismic design bases, 0 Seismic equipment qualification, 0 Seismic evaluation of plant structures and components, 0 Design documentation and configuration management.

She is currently serving as the Southern Nuclear Seismic Technical Lead for the Fukushima Near-Term Task Force (NTTF) 2.3 Seismic Walkdowns for all three Southern Nuclear plants.Justo S Chacon, SWE (SNC)Mr. Chacon is an engineer with Southern Nuclear Operating Company. He is working at Vogtle Nuclear Plant in the Modification Group in the Civil/Mechanical area. Mr. Chacon has a degree in Industrial Engineering and has worked on numerous site projects associated with civil/mechanical applications.

Being part of Modification Group, he is exposed to the seismic engineering issues as they apply to nuclear power plants. His extensive experience also as a Reactor Operator (roughly 6 years) provides experience with nuclear power equipment.

Mr. Chacon completed his training on Near Term Task Force Recommendation 2.3 -Seismic Walkdowns as a SWE.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSMIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 12 OF 49 James Dovel, SWE (ENERCON)Mr. Dovel is a Registered Professional Engineer with over 20 years of Civil/Structural experience in the design and construction of nuclear power plants, and in commercial and Industrial design. Mr.Dovel is a Civil Lead Engineer.

In this capacity he has provided structural support of modification packages for numerous Entergy plants including Grand Gulf Nuclear Station (GGNS), River Bend Station, Arkansas Nuclear One (ANO), Pilgrim Nuclear Power Station, and Waterford

3. Mr. Dovel also supported the extended power uprate (EPU) for FPL's Turkey Point plant, pipe stress analysis for DC Cook and the design of new power plants for China. Mr. Dovel completed his training on Near Term Task Force Recommendation 2.3 -Seismic Walkdowns as a SWE.Parimal Gandhi, SWE (SNC)Mr. Gandhi is a senior engineer with Southern Nuclear Operating Company. For the past 25 years, he has been working with the design and modifications of numerous Nuclear Power Plants and other industrial facilities including evaluating the condition of structural steel and concrete.

His experience includes static and dynamic analysis of steel frames, platforms, towers, crane girders, and various miscellaneous structures and finite element analysis of pressure vessel and lifting devices. Mr.Gandhi completed his training on Near Term Task Force Recommendation 2.3 -Seismic Walkdowns as a SWE.Jose Hernandez, SWE (SNC)Mr. Hernandez is an engineer with Southern Nuclear Operating Company. He is working at Vogtle Nuclear Plant in the Site Design department.

Mr. Hernandez is a registered professional engineer in the state of Georgia. His experience consists of 8 years in reinforced concrete analysis and design, elastic design, seismic rehabilitation, nonlinear analysis, nuclear design engineering, and geotechnical elements on reinforced concrete structures.

Mr. Hernandez is familiar in-depth with structural and civil construction codes. Mr. Hernandez managed the internal project team and subcontractors on numerous site projects.

Mr. Hernandez's previous experience includes participation in several researches that investigated the seismic vulnerability of existing school and hospital buildings located in high intensity activity seismic zones. Mr. Hernandez completed his training on Near Term Task Force Recommendation 2.3 -Seismic Walkdowns as SWE.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR FOR VERSION 1.0 RESOLUTION OF FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 13 OF 49 Thomas Petrak (SNC)Mr. Petrak has 30 years of nuclear power plant experience with 26 years at Plant Vogtle. Mr.Petrak's current assignment is the Fukushima Project Manager -Vogtle. During his time at Plant Vogtle, Mr. Petrak maintained an active SRO license for twenty years, 1989 -2009. Positions held by Mr. Petrak include:* Engineering Systems Manager* Shift Manager" Unit Shift Supervisor

• Support Shift Supervisor

• Maintenance Superintendent" I&C Team Leader* Engineering Supervisor Richard Starck, SCE (MPR)Mr. Starck is a registered Professional Engineer with more than 30 years of experience in seismic qualification of nuclear plant equipment.

He is the principal author of the EPRI Report 1025286 (Reference 10.2). He developed and taught the six sessions of the NTTF 2.3 Seismic Walkdown Training Course to more than 200 engineers.

He has provided technical oversight of work for various SQUG projects aimed at resolving USI A-46. Mr. Starck developed for SQUG the generic guidelines, criteria, and procedure for identifying safe shutdown equipment for resolution of USI A-46, is the editor and principal author of the SQUG Generic Implementation Procedure, and has interfaced with the NRC Staff and the SQUG Steering Group to resolve open issues on several revisions of the GIP. Mr. Starck is a SCE and has performed Seismic Walkdowns and evaluations of nuclear plant electric and mechanical equipment as part of the NRC required USI A-46 program.This work included equipment qualification, anchorage evaluation, seismic interaction review, outlier resolution, and operability determination.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 14 OF 49 Winston Stewart, SCE (ENERCON)Mr. Stewart is a Mechanical Engineer with over eight years of experience in various capacities including:

Modification Engineer, Engineering Mentor, 1OCFR50.59 Evaluator, Apparent Cause Evaluator, Contract Administration and Designated Representative, Project Manager, Procedure Technical Reviewer, and Environmental Monitoring Team Leader for Emergency Response Organization.

Mr. Stewart was responsible for the preparation of technical evaluations for various configuration changes to plant systems, structures, or components, as well as the preparation and revision of civil/structural calculations, pipe stress calculations, and other design documents.

He also served as subject matter expert for Pipe Stress Analysis and Pipe Flaw Evaluation (ASME B31.1,Section III and Section XI). During this time he qualified as SQUG Seismic Capability Engineer.Mr. Stewart completed his EPRI training on Near Term Task Force Recommendation 2.3 -Seismic Walkdowns as a SWE.David Volodarsky, SWE (ENERCON)Mr. Volodarsky is a Registered Professional Engineer with over 30 years of Civil/Structural experience in the design and construction of nuclear power plants. Mr. Volodarsky is a civil supervisor with Enercon Services.

His design experience includes field survey; piping design and stress analysis; seismic qualification of equipment, parts and structures; design of supports for various systems (piping, ductwork, raceways) for nuclear power plants. His recent work is associated with 10 CFR 73.55 nuclear plant security upgrades at Plant Farley, Plant Hatch, and Plant Vogtle. Mr.Volodarsky supported modification packages for the installation of the Emergency Sump Strainer for Davis Besse, Crystal River Unit 3, McGuire Nuclear Station Unit 1 & 2, Catawba Nuclear Station Unit 1 & 2, Indian Point Unit 2 & 3, Shearon Harris Nuclear Plant, Three Mile Island Nuclear Station Unit 1 and Qinshan Nuclear Power Plant Unit 3. Mr. Volodarsky completed his training on Near Term Task Force Recommendation 2.3 -Seismic Walkdowns as a SWE.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 15 OF 49 Kenneth Whitmore, SCE (ENERCON)Mr. Whitmore is a Registered Professional Engineer with more than 30 years of experience in seismic design and seismic equipment qualification in nuclear power plants. Mr. Whitmore is a Seismic Capability Engineer that was involved in the development of the SQUG methodology for verification of nuclear plant components.

Specifically, Mr. Whitmore served on the sub-committee that developed the SQUG methodology for evaluation of raceways and on the sub-committee that performed the peer review of the SQUG walkdown training class. Mr. Whitmore performed A-46 and IPEEE walkdowns at Oyster Creek and Three Mile Island and has subsequently performed SQUG evaluations at numerous nuclear power plants. Mr. Whitmore served as both Chairman and Technical Chairman of the Seismic Qualification Reporting and Testing Service (SQRTS), has witnessed numerous seismic tests and is a recognized industry expert in seismic qualification of components.

Mr. Whitmore has significant experience in all aspects of structural analysis and design and has extensive experience in performing plant walkdowns associated with seismic issues. Mr. Whitmore completed his EPRI training on Near Term Task Force Recommendation 2.3 -Seismic Walkdowns as a SWE.Matthew Wilkinson, SWE (ENERCON)Mr. Wilkinson is a Civil Engineer with over 5 years of experience.

He has a B.S. in Civil Engineering.

As a civil engineer, he is responsible for the development of engineering packages, calculations, analyses, drawings, and reports. Mr. Wilkinson has significant design experience with Florida Power and Light, primarily providing his services for Turkey Point Nuclear Station (PTN) on several modification packages and calculations.

Mr. Wilkinson has significant site support experience at PTN, McGuire Nuclear Station and River Bend Nuclear Station. Moreover, Mr. Wilkinson worked directly at PTN for the majority of 2010 to support the Independent Spent Fuel Storage Installation (ISFSI) construction and 2011 to 2012 to support the Extended Power Uprate (EPU) project design phase. Mr. Wilkinson completed his training on Near Term Task Force Recommendation 2.3 -Seismic Walkdowns as a SWE.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 16 OF 49 Frank Yao, SWE (ENERCON)Mr. Yao is a Registered Professional Engineer with over 40 years of Civil/Structural experience in the design and construction of nuclear and fossil power plants and highway bridge design. His design experience includes structural steel design (including anchorages);

supports for suspended systems (piping, ductwork, raceways);

seismic qualification of equipment, parts and structures; rigging and scaffold; and retaining walls, cooling towers concrete slabs, beams and foundations.

His recent work associated with 10 CFR 73.55 nuclear plant security upgrades at Plant Hatch, and Plant Vogtle. Mr.Yao supported modification packages for the installation of the Emergency Sump Strainer for Davis Besse Nuclear Power Station, Catawba Unit 1 & 2, McGuire Unit 1 & 2, Qinshan Unit 3 & 4 (China), and Ling Ao Unit 3 & 4 (China). He has also supported several plants during the implementation phase of the strainers, providing engineering support, resolving construction issues and performing structural evaluation to qualify changes made during the installation phase of the project. Mr. Yao completed his training on Near Term Task Force Recommendation 2.3 -Seismic Walkdowns as a SWE.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 17 OF 49 5.0 IPEEE VULNERABILITIES REPORTING Information on the seismic vulnerabilities identified during the IPEEE program is reported in Attachment

5. Within this context, "vulnerabilities" means seismic anomalies, outliers, or other findings.

For each vulnerability, Attachment 5 also reports a description of the action taken to eliminate or reduce the seismic vulnerability, and specifies whether the configuration management program has maintained the IPEEE action (including procedural changes) to ensure that the vulnerability continues to be addressed.

As part of a Seismic PRA/IPEEE update, in May 2012, Plant Vogtle conducted a walkdown of Equipment modified under the IPEEE -Seismic. As a result of this walkdown, Document No.12L0075-RPT-001 was issued (Reference 10.9). That walkdown revisited systems and components that have been either significantly modified or replaced since the issuance of the original VEGP IPEEE- Seismic Report to NRC (Reference 10.8). The findings of the walkdown conducted in May are documented in Appendix A-2 (Previous IPEEE Open Item Walkdown Resolution Notes) (Reference 10.9). Appendix A-2 is included in Attachment

5. The purpose of these walkdowns was to ensure that the IPEEE vulnerabilities had been resolved.

During those walkdowns, one outlier was discovered that was potentially unresolved (either had never been resolved or were currently no longer resolved, i.e., the problem had "re-occurred).

The item dealt with clearance for an air regulator and air pump associated with component 2-HV-15196 (See CR 502493).The seismic walkdown equipment list (SWEL) for Vogtle Unit 2 included 5 components that had seismic vulnerabilities previously identified during the IPEEE program. Even though the items identified as IPEEE vulnerabilities had been walked down in May 2012, implementation of these modifications for SWEL items was verified again during the walkdowns performed for resolution of the NTTF Recommendations 2.3, Seismic. During the walkdowns, the walkdown teams verified that the recommended resolutions to the IPEEE vulnerabilities associated with these five items had been implemented, with the exception of the valve clearance issue discussed in the preceding paragraph.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 18 OF 49 6.0 SEISMIC WALKDOWN EQUIPMENT LIST DEVELOPMENT A team of individuals with extensive knowledge of Plant Vogtle systems and components developed the SWEL. Qualifications of the personnel responsible for developing the SWEL are provided in Section 4.0 of this report. The equipment selection personnel used a SNC-template to ensure compliance with EPRI Report 1025286 (Reference 10.2) and consistency across the fleet.Two SWELs were developed (SWEL 1 and SWEL 2) consistent with the guidance in EPRI Report 1025286 (Reference 10.2). SWEL 1 consists of a sample of equipment related to safe shutdown of the reactor and maintaining containment integrity as described in Section 3.0 of the EPRI Report 1025286 (Reference 10.2). SWEL 2 consists of items related to the spent fuel pool as described in Section 3.0 of EPRI Report 1025286 (Reference 10.2). The two SWELs form the overall SWEL for the plant.Attachment 1 provides the final SWEL 1 and SWEL 2.In some cases, components listed on the SWEL were removed from the SWEL or were replaced with equivalent components.

These changes were made when it was determined during the Seismic Walkdown that access to the equipment on the original SWEL would be impractical to achieve during a walkdown.

For example, components located very high overhead were replaced with equivalent items that could be seen without erecting scaffolding.

All such changes meet the provisions of the EPRI Report 1025286 (Reference 10.2). The SWELs provided in Attachment 1 reflect the final SWELs after all changes were incorporated.

6.1 DEVELOPMENT OF SWEL 1 SWEL 1 was developed using the four screens described in EPRI Report 1025286 (Reference 10.2).Screens 1 to 3 Screens 1 to 3 were used to select Seismic Category I equipment that do not undergo regular inspection and support the five safety functions.

In accordance with the EPRI Seismic Walkdown Guidance (page 3-3), Screens 1 through 3 can be satisfied using previous equipment lists developed for the IPEEE program. Consequently, the Seismic Review Safe Shutdown Equipment List (SSEL) developed for the Vogtle Nuclear Plant IPEEE Unit 2 (Reference 10.8) was used as Base List I for the development of SWEL 1.The specific guidance used to create the IPEEE Seismic SSEL was EPRI Report NP-6041, "A Methodology for Assessment of Nuclear Power Plant Seismic Margin" (Reference 10.12). The Seismic SSEL from IPEEE -Seismic was checked and verified to meet the intentions set forth in the VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR VERSION 1.0 RESOLUTION OF FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 19 OF 49 EPRI Report 1025286 (Reference 10.2). The intent of the Base List 1 was to provide an equipment list of the SSCs used to safely shut down the reactor and maintain containment integrity following a Seismic Safe Shutdown Earthquake.

The EPRI Report 1025286 (page 3-1) listed three screens to use in selecting the Base List 1 if a utility was to not start from an existing equipment list used in previous plant evaluations.

Applying these three screens would result in an acceptable base list that was comprised of Seismic Category I SSCs associated with maintaining the five safety functions:

• Reactor reactivity control" Reactor coolant pressure control* Reactor coolant inventory control" Decay heat removal, and* Containment function.The criteria used in selection of the Seismic SSEL are detailed in Section 3.1.2.5 of the IPEEE -Seismic Report (Reference 10.8).Therefore, based upon the review of the Base List, it was determined that the list did satisfy the requirements as specified in the EPRI Report 1025286 (Reference 10.2) which is a list comprised of Seismic Category I SSCs associated with maintaining the five safety functions described in EPRI Report 1025286 (Reference 10.2), which are used to safely shut down the reactor and maintain containment cooling integrity.

Base List 1 is presented in Attachment

1. However, before proceeding any further with the subsequent screens for the base list, it was necessary to confirm that the components satisfied screens 1 to 3. Hence, screens 1 to 3 were applied to the base list and a small number of components were identified and screened out of the base list.Screen 4 Screen 4 provides the sample considerations to select components from the Base List 1. The selection of components for SWEL 1 was developed through an iterative process that ensured a representative sample (i.e., Screen 4 from EPRI Report 1025286).

Various drafts of SWEL 1 were provided to POP for review and input. The POP identified and recommended inclusion of additional equipment important to plant operations.

The following list summarizes the sample considerations used to develop SWEL 1: " Variety of systems" Major new or replacement equipment* Classes of equipment VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 20 OF 49" Variety of environments" Equipment enhanced due to vulnerabilities identified during the IPEEE program* Risk significance Variety of Systems -EPRI Report 1025286 specifies that equipment from a variety of plant systems must be included on the SWEL 1. The systems represented in the Base List were reviewed and components from a majority of these systems are included on the SWEL.Major New and Replacement Equipment

-Major new or replacement equipment installed within the previous 15 years was identified through a search of work order (WO) histories for selected equipment and input from the plant personnel familiar with plant modification and from the PRA group on equipment changes to components that are included in the PRA.Variety of Equipment Classes -A list of the 21 Classes of Equipment that should be included on the SWEL is provided in Appendix B of the EPRI Report 1025286. SWEL 1 includes components from each equipment class except Class 12 (Air Compressors) and Class 13 (Motor Generators)., Vogtle does not contain any safety-related Air Compressors or Motor Generators.

Variety of Environments

-The EPRI Report 1025286 specifies that the SWEL contain components located in various plant environments, including environments subject to corrosion and high temperatures.

SWEL 1 includes equipment in three environment types. These include Harsh (e.g.Containment Building, Main Steam Valve Room), Mild (e.g. Control Room, Auxiliary Building), and Outdoors/Intake Structures (e.g. valve boxes, Service Water Intake Structure).

IPEEE Vulnerabilities

-SWEL 1 includes equipment identified with seismic vulnerabilities identified in Reference 10.8.Risk Significance

-Information from the Vogtle Unit 2 PRA and the Maintenance Rule implementation documentation were used to determine whether items were risk significant.

Representative samples of Risk Significant items are included in the SWEL.6.2 DEVELOPMENT OF SWEL 2 SWEL 2 is developed using four screens described in EPRI Report 1025286 (Reference 10.2). SWEL 2 is presented in Attachment 1.Screens 1 to 2 The equipment selected through Screens 1 and 2 provide any Seismic Category I components associated with the Spent Fuel Pool (SFP) that are also accessible for a walkdown.

For Vogtle Unit 2, VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 21 OF 49 the only Seismic Category 1 equipment associated with the SFP is the Spent Fuel Cooling and Purification System. The SSCs in the Spent Fuel Cooling and Purification System that are accessible and available for a walkdown comprise Base List 2.Screen 3 Screen 3 provides the sample considerations that ensure that a broad category of equipment included in SWEL 2. These considerations include:* Variety of systems* Major new or replacement equipment* Classes of equipment" Variety of environments For Vogtle Unit 2, SWEL 2 is developed from the Base list 2 which is provided in Attachment 1.Screen 4 Screen 4 identifies any items that could potentially lead to rapid drain down of the SFP. These include any penetrations in the SFP that are below 10 feet above the top of the fuel assemblies.

For Vogtle Unit 2, there are no SFP penetrations within 10 feet above the fuel in the SFP. All piping connected to the SFP, either terminates more than 10 feet above the fuel or has anti-siphon holes, located more than 10 feet above the fuel, to prevent rapid drain-down of the SFP. Based on the fact that there are no penetrations within 10 feet of the fuel and accompanied with the design of the anti-siphon hole in the SFP discharge piping, no rapid drain-down items exist.Therefore, there are no components associated with rapid drain down of the Spent Fuel Pool included on SWEL 2.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR FOR VERSION 1.0 RESOLUTION OF FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 22 OF 49 7.0 SEISMIC WALKDOWNS AND AREA WALK-BYS Walkdowns were performed for all components on the (combined)

SWEL. A Seismic Walkdown Checklist (SWC) was completed for each component and an Area Walk-by Checklist (AWC) was completed for each area containing equipment on the SWEL. Copies of the SWCs and AWCs are provided in Attachments 3 and 4, respectively.

The personnel performing walkdowns received training on the NTTF 2.3 seismic walkdown guidance.Prior to the walkdown teams arriving onsite, walkdown packages were assembled into folders that contained the SWCs and AWCs and other pertinent information (e.g., calculations, test reports, IPEEE walkdowns, equipment location, and layout drawings).

Each walkdown team consisted of two SWEs.The walkdown teams spent the first week on site obtaining unescorted plant access and organizing for the walkdowns.

Organization included assignment of specific components to the teams; review of the walkdown packages; development of a process for tracking the Seismic Walkdowns and Area Walk-bys; and familiarization with the plant.The second week began with peer reviewers (Whitmore and Ashworth) providing an overview on the information contained in the EPRI Report 1025286 (Reference 10.2). Expectations for the walkdowns were discussed and questions were answered.

After this overview, each walkdown team performed an initial Seismic Walkdown and Area Walk-by. This initial walkdown was performed in the presence of the other teams and at least one peer reviewer.

The purpose of this initial walkdown was to ensure consistency between the different teams, to reinforce the expectations for identifying potentially adverse seismic conditions, and to allow team members to provide and obtain feedback.Following the initial walkdowns, the walkdown teams began performing the Seismic Walkdowns and Area Walk-bys.

Support from plant personnel (operators, electricians, engineering) was obtained as required to open equipment and to assist in locating and identifying components.

All Component Walkdowns and Area Walk-bys were documented on the SWCs and AWCs, respectively.

The final status of all SWCs and AWCs indicated one of the three following statuses:* "Y" -Yes, the equipment is free from potentially adverse seismic conditions;" "N" -No, the equipment is not free from at least one potentially adverse seismic condition;" "U" -Undetermined, a portion(s) of the walkdown could not be completed due to equipment inaccessibility and the condition is not known.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 23 OF 49 The walkdown focused on anchorage and seismic spatial interactions but also included inspections for other potentially adverse seismic conditions.

Anchorage in all cases was considered to be anchorage to the structure.

This included anchor bolts to concrete walls or floors, structural bolts to structural steel and welds to structural steel or embedded plates. For welds, the walkdown team looked for cracks and corrosion in the weld and base metal. Other bolts such as flange bolts on in-line components were not considered to be anchorage.

These connections were evaluated and any potentially adverse seismic concerns were documented under "other adverse seismic conditions." As part of the walkdown, the anchorage of at least 50% of the anchored components was evaluated to verify if the anchorage was consistent with plant documentation.

The document that provides the anchorage configuration was identified on the SWC and the anchorage in the field was compared to the information on this referenced document.

In cases where the anchorage could not be observed (e. g.where the anchorage is inside a, cabinet that could not be opened at the time of the watkdown), the items related to anchorage were marked as "U" (Undetermined) and deferred until the piece of equipment was available for inspection.

However, all other possible inspections associated with that item were completed and the results were documented on the SWC. These items were considered to be incomplete at that time and deferred to a time when they would be available for inspection.

In cases where the seismic walkdown team members identified a potentially adverse condition, the condition was noted on the SWC or on the AWC and a Condition Report (CR) was written to document and evaluate/resolve the condition.

As part of the process of generating the CR, preliminary licensing basis evaluations were performed by the SWEs during the walkdowns.

Additionally, detailed licensing basis reviews were conducted as part of the resolution of the CR, as required.

Conditions that were not obviously acceptable were documented on the checklists and a basis was provided for why the observed condition was determined to be acceptable.

Area Walk-bys were performed in the rooms containing the SSCs for walkdowns.

For cases in which the room where a component was located was large, the extent of the area encompassed by the Area-Walk-by was clearly indicated on the AWCs. For large areas, the walk-by included all structures, systems and components within a 35-foot radius of the equipment being walked down, as described on the AWC. The AWCs are included in Attachment 4.SWEL 1 Walkdowns A total of 100 Component Walkdowns were performed.

All areas of the plant that contain items on the SWEL were included in the Area Walk-bys.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR FOR VERSION 1.0 RESOLUTION OF FUKUSHIMA NEAR-TERM E TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 24 OF 49 SWEL 2 Walkdowns A total of 4 component walkdowns were performed.

In addition, a total of 3 Area Walk-bys were completed.

All areas of the plant that contain items on the SWEL were included in the Area Walk-bys.7.1 INACCESSIBLE ITEMS Table 7-1 identifies the components originally determined to be inaccessible for walkdowns.

These items are located throughout the plant and the required Seismic Walkdowns and Area Walk-bys are not complete for these items.0 Table 7-1. Inaccessible Equipment per Original Walkdown Scope# Item No. Description Access Remaining Completion Walkdown Date Scope 1. 2-1606- Reactor Trip No cabinet door opening Inspect Outage 2R16 S6-002 Switchgear was allowed during plant anchorage operation 2. 2-1804- 4160V Switchgear No cabinet door opening Inspect Outage 2R16$3-A02 2AA02 was allowed during plant anchorage operation 3. 2-1501- CTB Cooling Unit Inside containment.

Not SWC & Outage 2R16 A7-00 1- & Motor accessible during plant AWC 000 operation (see Note 1)4. 2-HV- Reactor Head Inside containment.

Not SWC & Outage 2R16 0442A Letdown Line accessible during plant AWC Control SOV operation (see Note 1)

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 25 OF 49 Table 7-1. Inaccessible Equipment per Original Walkdown Scope# Item No. Description Access Remaining Completion Walkdown Date Scope 5. 2-HV- Accumulator Inside containment.

Not SWC & Outage 2R16 0943B Nitrogen HDR accessible during plant AWC Vent- Solenoid operation(see Note 1)Operated Valve 6. 2-HV- ACCW Supply to Inside containment.

Not SWC & Outage 2R16 1978 RCP Coolers MOV accessible during plant AWC operation (see Note 1)7. 2-HV- Normal CTB Purge Inside containment.

Not SWC & Outage 2R16 2626B Supply and accessible during plant AWC Equalizing AOV operation (see Note 1)8. 2-HV- Accumulator 3 Inside containment.

Not SWC & Outage 2R16 8875C Nitrogen Vent -accessible during plant AWC Solenoid Operated operation (see Note 1)Valve 9. 2-LT- SG 1 Wide Range Inside containment.

Not SWC & Outage 2R16 0501 Level accessible during plant AWC operation (see Note 1)10. 2-1511- CTB Reactor Inside containment.

Not SWC & Outage 2R16 E7-00 1- Cavity Cooling accessible during plant AWC 000 Coil operation (see Note 1)11. 2-1515- CTB Aux Air Inside containment.

Not SWC & Outage 2R16 A7-001- Cooling Unit (Coil) accessible during plant AWC 000 operation (see Note 1)

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 26 OF 49 Table Notes: 1) With the exception of the Reactor Trip Switchgear and 4160V Switchgear 2AA02, all components determined to be inaccessible during the initial walkdowns were located inside an area of the plant not accessible during normal plant operation, such as inside Containment.

Walkdowns of these components and of the associated plant areas were deferred to an outage.Inspection of the cabinet internals could not be performed without opening the doors of the equipment.

Opening doors on these types of components was not permitted by plant operations at the time of the initial Seismic Walkdowns due to equipment deemed too sensitive to permit access, or requiring special, planned precautions, to open the doors.Supplemental guidance/clarification for opening cabinets to inspect for adverse conditions was received on September 18, 2012. This required the opening of cabinets, electrical boxes, and switchgear to inspect the internals for potentially adverse seismic conditions, even when opening the components was, not required to inspect the anchorage.

At the time of this supplemental guidance/clarification, the Vogtle Unit 2 Seismic Walkdowns were complete.

However, the affected components were identified and scheduled for re-inspection with component doors opened.The following table provides a list of components that had to be opened in order to inspect for "other adverse conditions" inside the cabinets.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 27 OF 49 Table 7-2. Inaccessible Equipment Resulting from Guidance on Opening Cabinets to Inspect for Other Adverse Conditions

1. Item No. Description Remaining Completion Walkdown Date Scope 1. 2-1500-Q5-HVC HVAC PANEL Inspect Outage 2R16 Internals 2. 2-1604-Q5-PCl PROCESS CONTROL GROUP 1 Inspect Outage 2R16 Internals 3. 2-1604-Q5-PS I PROCESS I&C PROTECT I Inspect Outage 2R16 Internals 4. 2-1605-C5-ASI ALTERNATE SHDN IND EAGLE 21 Inspect Outage 2R16 CAB Internals 5. 2-1605-P5-SDA SHUTDOWN PANEL TRN A Inspect Outage 2R16 Internals 6. 2-1605-Q5-STA SAFEGUARD TEST CAB-TRN A Inspect Outage 2R16 Internals 7. 2-1606-S6-002 REACTOR TRIP SWITCHGEAR Inspect Outage 2R 16 Internals 8. 2-1623-D5-001 REMOTE PROCESSING UNIT A CAB Inspect Outage 2R16 1 Internals 9. 2-1804-$3-A02 4160V SWITCHGEAR 2AA02 Inspect Outage 2R16 Internals 10. 2-1805-S3-ABA 480V MOT CONTROL CTR 2ABA Inspect Outage 2R16 Internals VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 28 OF 49 Table 7-2. Inaccessible Equipment Resulting from Guidance on Opening Cabinets to Inspect for Other Adverse Conditions

1. Item No. Description Remaining Completion Walkdown Date Scope 11. 2-1805-S3-ABB 480V MOT CONTROL CTR 2ABB Inspect Outage 2R16 Internals 12. 2-1805-S3-BBC 480V MOT CONTROL CTR 2BBC Inspect Outage 2R16 Internals 13. 2-1806-S3-DCC 125 VDC MCC 2CD1M Inspect Outage 2R16 Internals 14. 2-1805-S3-B04 480V SWITCHGEAR 2AB04 Inspect Outage 2R16 Internals 15. 2-1805-S3-RHR1A STARTER/RHR 2-HV-8701B Inspect Outage 2R 16 Internals 16. 2-1805-Y3-IC5 RHR ISO VLV INVERTER Inspect Outage 2R16 Internals 17. 2-1807-Y3-ID4R VITAL AC INVERTER 2DD 114 Inspect Outage 2R16 Internals 18. 2-1806-B3-CAA BATTERY CHARGER 2AD 1CA Inspect Outage 2R16 Internals 19. 2-1806-Q3-DA1 125 VDC DISTR. PANEL 2AD1 1 Inspect Outage 2R16 Internals 20. 2-1806-S3-DSA 125 VDC SWITCHGEAR 2AD1 Inspect Outage 2R16 Internals VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 29 OF 49 Table 7-2. Inaccessible Equipment Resulting from Guidance on Opening Cabinets to Inspect for Other Adverse Conditions

1. Item No. Description Remaining Completion Walkdown Date Scope 21. 2-1807-Q3-VI6 120 VAC VITAL DIST PANEL 2BY2B Inspect Outage 2R16 Internals 22. 2-1807-Q3-VI4 120 VAC VITAL PANEL 2DY1B Inspect Outage 2R16 Internals 23. 2-1807-Q3-VIl 120 VAC VITAL PANEL 2AY1A Inspect Outage 2R16 Internals 24. 2-1816-U3-001 AUXILIARY RELAY PANEL A Inspect Outage 2R16 Internals 25. 2-1816-U3-014 AUXILIARY RELAY PANEL Inspect Outage 2R 16 Internals 26. 2-1821-U3-001 SF SEQUENCER BOARD TRAIN A Inspect Outage 2R16 Internals 27. 2-2403-P5-DG1 DG IA GEN CTL PNL Inspect Outage 2R16 Internals 28. 2-1805-S3-BBF 480V MCC 2BBF Inspect Outage 2R16 Internals Table Notes: 1) Vogtle Unit 2 has 3 transformers (Equipment Class 4) in the SWEL-1. The transformers were inspected to the extent practical.

All visible anchors, hardware and surfaces were inspected.

The anchorage for the transformers was visible without opening the component.

To inspect the transformer further would require disassembly and therefore would not be considered part of a normal electrical inspection.

The inspection of the transformers meets the requirements of the VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 30 OF 49 guidance document and the 50.54(f) letter. The transformers are as listed below: 2-1807-Y3-14 Regulated Transformer 2BBC42RX Feeds 2BYC I 2-1807-Y3-10 Regulated Transformer 2ABC09RX Standby Feed to 2AY 1A 2-1807-Y3-15 Regulated Transformer 2ABE51RX Feeds 2AYE I VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM VERSION 1.0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 31 OF 49 8.0 RESULTS This section discusses the results of the Seismic Walkdowns that were performed in response to the NRC 50.54(f) letter dated March 12, 2012, "Enclosure 3, Recommendation 2.3: Seismic".

As potentially adverse conditions were identified conditions reports were initiated in the Plant CAP program and evaluated.

The sections below discuss the results of these walkdowns and evaluations.

8.1 POTENTIALLY ADVERSE SEISMIC CONDITIONS All potentially adverse conditions were conservatively entered into the site Corrective Action Program (CAP) per Southern Nuclear expectations in a timely manner. While some preliminary licensing basis evaluations were performed by the SWEs as part of the generation of the CAP entries, the items did not first undergo a detailed seismic licensing basis review as described in EPRI Report 1025286 (Reference 10.2). Consequently, the as-found conditions in Table 8-1 below do not necessarily indicate that SSCs were deficient or not in conformance with their seismic licensing basis. Instead, it is an indication that Southern Nuclear has a very low threshold for CRs and actively uses the system.SNC personnel familiar with the Plant Vogtle Seismic Licensing basis, Plant Vogtle seismic qualification methods and documentation, and Southern Nuclear requirements and procedures for entering items into the CAP reviewed and dispositioned all of the potentially adverse seismic conditions as part of the CAP process. The subsections below summarize the key findings from the CAP reviews that pertain to equipment operability, SSC conformance with the seismic licensing basis, and any required plant changes.During the course of the seismic walkdowns, a total of 15 Unit 2 Potentially Adverse Conditions were identified and entered into the Corrective Action Program. In addition, another 4 were entered that are Common to both Units 1 and 2. Table 8-1 provides additional details on the SSCs that were identified during the walkdowns and entered into the CAP as degraded, nonconforming, or unanalyzed relative to their seismic licensing basis.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 32 OF 49 Table 8-1. Potentially Adverse Conditions Action Taken or Status Component Brief Description of Potentially Adverse CR # Brief Discussion of Planned to (Open/Clsd)

/ Area Seismic Condition Analysis/Conclusion Address/Resolve the Condition Area Materials/equipment (under a tarp) were found 500988 Perform an evaluation Cart is properly Closed Control stored in a temporary storage area in the U2 to identify the need for secured with all Bldg 325 Control Building Room 325. According to a any corrective actions. four wheels Temp Storage Sign, the materials were stored clamped.there under MWO SNC 142333. It could not be Temporary storage determined what was under the tarp, however, it is now in full was noted only one wheel on the cart was compliance with restrained which is not consistent with the 00352-C.procedure 00352-C "General Plant Housekeeping and In-Process Materials Control".

The storage area was near MCC 2-1805-S3-ABA.

The Temp Storage area should be reviewed to ensure it is in full compliance with Procedure 00352-C.Component An improperly restrained light fixture was found 500990 The Vogtle site design Replace/repair Open 2LT-5111 above level transmitter 2-1302-LT-5 111 located at group performed an light restraint.

Due the bottom of RWST. It is judged by the evaluation of the as 1/31/2013 Area walkdown team that the light could become found condition and CST dislodged during a seismic event and impact the concluded that no transmitter.

This should be further evaluated for seismic interaction significance.

hazards exists that could affect equipment operability.

Repair/replace hook.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 33 OF 49 Table 8-1. Potentially Adverse Conditions Action Taken or Status Component Brief Description of Potentially Adverse CR # Brief Discussion of Planned to (Open/Clsd)

/ Area Seismic Condition Analysis/Conclusion Address/Resolve the Condition Components The chains of a monorail crane above both 502483 The seismic team The hoist has been Closed 2PV-3000 & Atmospheric Relieve Valves 2-PV-3030 and 2- judged no operability secured.2PV-3,030 PV-3000 were in contact with such valves. It was concerns for this the judgment of the Seismic Walkdown Team that condition.

Secure Area in a seismic event the chains could possibly strike hoist.Aux Bldg, or become entangled with the ARVs. This is not in R159 accordance with procedure 00352-C which states that safety-related equipment will not be vulnerable to impacts from chain or controllers of hoists and cranes during a seismic event.Component A component associated with the valve operator 2- 502493 Analysis is in progress Complete analysis Open 2HV-15196 HV- 15196 was measured to be less than 1/4/4 inch to determine final and implement Due from the wall. The seismic team judged that in corrective actions. corrective actions. 11/30/2012 case of a seismic event the component would have the potential to collide with the wall due to proximity.

This concern was previously identified in the IPEEE list and a solution was provided to resolve the condition, however, it has not being implemented.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCVO61-RPT-02 FOR RESOLUTION OF FIJKUSHIMA NEAR-TERM RE"V. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 34 OF 49 Table 8-1. Potentially Adverse Conditions Action Taken or Status Component Brief Description of Potentially Adverse CR # Brief Discussion of Planned to (Open/CIsd)

/ Area Seismic Condition Analysis/Conclusion Address/Resolve the Condition Component Seismic team raised a concern regarding the 502509 Seismic adequacy of None required Closed 2HV-3006B adequacy of the fire protection pipe supports fire protection piping located in the U2 South Main Steam Isolation was confirmed.

Valve room, located near and above the Main Steam Safety Relief Valves 2-PSV-3001 to 3005, the 2-HV-3006A and 2-HV-3006A outboard MSIV and the 2-PV-3000 Atmospheric Relieve Valve, among other components.

This fire protection piping was judged by the walkdown team to have a potential of loss of pressure boundary capability during a seismic event. This is due to the very long unsupported spans and extremely long flexible rod hanger supports.While it is unlikely that this pipe will fall and damage any safety-related components, especially if the system is normally dry, a seismic event could cause the piping system to collapse during a seismic event. There are no operability concerns for this area if the piping is normally dry. If the piping is normally wet, further investigation is required to determine if the resulting spray would create any operability concerns.

Even if the system is normally dry, the configuration appears not to be consistent with normal practice for seismic II/I configurations.

Analysis is required to show that the piping meets seismic II/I conditions.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 35 OF 49 Table 8-1. Potentially Adverse Conditions Action Taken or Status Component Brief Description of Potentially Adverse CR # Brief Discussion of Planned to (Open/Clsd)

/ Area Seismic Condition Analysis/Conclusion Address/Resolve the Condition Area The seismic team along with the NRC Inspector 502522 The seismic walkdown Seismic adequacy Closed Diesel Gen Resident identified a potential issue regarding a team concluded that the of the cover plate Bldg, R101 floor cover plate near the Engine Control Panel for bent plate was presently confirmed.

the 1B Diesel Generator (location 1-2403-P5-not a seismic/structural DG4). This plate is not required to be bolted down, concern based on the but the walkdown team identified some minor configuration (shape), deflection in the plate. (Note: D/G's IA, 2A and the location of the 2B all have the same condition) cover, and proximity to surrounding equipment.

However, this CR is to initiate an evaluation to determine the long-term adequacy of the cover plate and identify the need for any corrective actions.Component A lighting hook was found that was not fully 504862- Perform seismic Complete seismic Open 2-1807-Q3-closed. It was found in Room R147 in the analysis.

Repair/replace analysis.

Due V16 Auxiliary Building Unit 2. The light was above hook. Repair/replace 1/31/2013 the panel 2-1807-Q3-VI6.

This condition needs.to hook.Area be investigated to determine the adequacy of this Aux Bldg, connection.

R147 VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 36 OF 49 Table 8-1. Potentially Adverse Conditions Action Taken or Status Component Brief Description of Potentially Adverse CR # Brief Discussion of Planned to (Open/Clsd)

/ Area Seismic Condition Analysis/Conclusion Address/Resolve the Condition Area Two lighting hooks were found to be not fully 504862 Perform seismic Complete seismic Open Aux Bldg, closed. It was found in Room R147 in the analysis.

Repair/replace analysis.

Due R147 Auxiliary Building Unit 2. Both lights were above hook. Repair/replace 1/31/2013 Room the panel 2-1805-S3-BBB.

hook.Area An exit sign hook was found to be not fully closed. 505324 It was judged by the Complete seismic Open Aux Bldg, This was found in Room RB 130 in the Auxiliary Seismic walkdown team analysis.

Due RB 130 Building.

This sign was nearby the rack location that this does not Repair/replace 1/31/2013 number 2-1407-P5-SG5.

represent a seismic hook.concern. There are no operability concerns for these conditions.

This CR is written to initiate the investigation of the condition and identify the need for any corrective actions.Repair/replace hook.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM "EV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 37 OF 49 Table 8-1. Potentially Adverse Conditions Action Taken or Status Component Brief Description of Potentially Adverse CR # Brief Discussion of Planned to (Open/Clsd)

/ Area Seismic Condition Analysis/Conclusion Address/Resolve the Condition Component A discrepancy was found between the as-built 505327 There is no operability Subsequent to the Closed 2-1604-Q5-condition and the drawing anchorage details. The concerns related to this initial walkdown, PC 1 drawing shows the connection to be bolted while condition.

The seismic the correct the as-built condition was found to be welded. team judged that in case anchorage of a seismic event the drawings were component would not obtained and a have the potential to fail second walkdown and the connection does confirmed that the not show any sign of as built anchorage degradation.

matched the drawing details.Component A fluorescent lighting fixture is inside the "spatial 509115 This CR is to initiate an Complete seismic Open 2-1807-Q3-interaction" of cabinet 2-1807-Q3-VI I. This evaluation to determine analysis and Due Outage Vi1 means that the lightning fixture could have the adequacy of the implement 2R17 physical contact with this cabinet on a seismic condition and identify corrective actions.Area event. Unistrut for light fixture is within z2" of 2- the need for any Control 1806-S3-DSA (125VDC MCC 2AD1M) and could corrective actions.Bldg, RB29 impact top of panel during seismic event. There is no operability concerns related to this condition.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM X* 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 38 OF 49 Table 8-1. Potentially Adverse Conditions Action Taken or Status Component Brief Description of Potentially Adverse CR # Brief Discussion of Planned to (Open/CIsd)

/ Area Seismic Condition Analysis/Conclusion Address/Resolve the Condition Component The base of the U2 NSCW Exhaust Fan 2-1540- 513338 The seismic walkdown Repair concrete.

Open 2-1540-B7-B7-003-000 has voids in the concrete where the judged that this Due 003 anchor bolts that support this fan are installed, condition does not 10/12/2013 represent a seismic concern or operability.

However, this condition does meet the Vogtle standards per procedure 25026-C Installation of Concrete.Area The Seismic Walkdown team found that none of 517075 The seismic walkdown The trashcan Open Control the trashcans barrels on the control room (R163 & judged that this barrels are not Due Bldg, R164 R 164) are secured or unrestrained, condition does not located near any 1/31/2013 represent an operability SR equipemt;concern. However, this trashcans to be condition does meet the. replaced with Vogtle standards per suitable trashcans.

procedure 00352-C General Plant Housekeeping and In-Process Materials Control.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR FOR REV. 0 RESOLUTION OF FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 39 OF 49 Table 8-1. Potentially Adverse Conditions Component./ Area Brief Description of Potentially Adverse Seismic Condition Brief Discussion of Analysis/Conclusion Action Taken or Planned to Address/Resolve the Condition Status (Open/Clsd)

Component 2-1606-S6-002 Area Control Bldg, B07 The Seismic Walkdown team found an apparent case of a rigid connection between a cabinet 2-1606-S6-002 and a conduit. Reactor Trip Breaker.517082 The seismic walkdown team judged that this condition does not represent a seismic or operability concern.The equivalent Unit 1 cabinet should also be evaluated to determine if this is a case of an extended condition.

The Vogtle site design group has conformed that the installation is per the current design.Site design group to confirm seismic adequacy of the design.Confirm seismic adequacy of the current design.Open Due 1/31/2013 VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 40 OF 49 Table 8-1. Potentially Adverse Conditions Action Taken or Status Component Brief Description of Potentially Adverse CR # Brief Discussion of Planned to (Open/Clsd)

/ Area Seismic Condition Analysis/Conclusion Address/Resolve the Condition Component Seismic walkdown team found a fluorescent 540146 The qualified seismic Based on the Closed 2-1806-B3-lightning fixture to be directly above the cabinet walkdown team evaluation CCB with the location number 2-1806-B3-CCB.

concluded that in case performed, the as-that a seismic event found condition occurs, the lightning provides tubes could dislodge reasonable from the fixture and expectation that no impact the cabinet since seismic hazard they were installed exists that could directly above the adversely affect cabinet. This CR is to the safety related initiate an evaluation to component 2-determine the adequacy 1806-B3-CCB of the condition and operability if it is identify the need for impacted by the any corrective actions. fluorescent bulb There is no operability tubes.concerns related to this condition.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 41 OF 49 During the course of the walkdowns the team identified issues that, while not rising to the level of a seismic concern, warranted evaluation to determine if programmatic enhancements are warranted.

These issues have been entered into the SNC corrective action program.CR 537446: While performing a review of the Condition Reports resulting from the SAM NTTF 2.3 Seismic Walkdowns, a possible trend was identified with regards to the failure of plant personnel to properly secure hoist and cranes following use. 00352-C requires that "that safety related equipment will not be vulnerable to impacts, from chains or controllers of hoists and monorail cranes, during a seismic event. Place any hoist or monorail cranes in the vicinity of the safety related equipment in a location where, during a seismic event, the chains and controllers cannot strike or become entangled with the equipment." Contrary to the requirements of 00352-C, 3 of 4 hoist controllers near the D/G electrical panels and a hoist near Unit 2 Loops 1&4 ARV's were not properly secured. All controllers have seen been secured. Reference CR's 502483 & 504859.CR 537451: While performing a review of the Condition Reports resulting from the SAM NTTF 2.3 Seismic Walkdowns, a possible trend was identified with regards to the failure of plant personnel to maintain housekeeping and temporary storage areas in accordance with procedure 00352-C. Reference CR's 500988, 504853, 504860, 504882, 504895, 504901, 511980, 513336 & 517075.CR 537453: While performing a review of the Condition Reports resulting from the SAM NTTF 2.3 Seismic Walkdowns, a possible trend was identified with regards to the management of seismic restraints of lighting fixtures.

Reference CR's 500990, 501548, 504862, 504868, 505324 & 505954.CR 537454: While performing a review of the Condition Reports resulting from the SAM NTTF 2.3 Seismic Walkdowns, a possible trend was identified with regards to fasteners and hardware.

Several CR's were generated which identified missing or loose fasteners and hardware.

Reference CR's 501546, 501650, 504850, 505329, 507939, 509102, 513331, 524560, 524568, 525039, 525046, 525340 & 525343.8.2 EQUIPMENT OPERABILITY Plant Vogtle Unit 2 had no as-found conditions that would prevent SSCs from performing their required safety functions.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 42 OF 49 8.3 PLANT CHANGES There were no plant changes that resulted from the as-found conditions.

Plant changes are any planned or newly installed protection and mitigation features (i.e., plant modifications) that result from the Seismic Walkdowns or Area Walk-bys.8.4 OTHER NON-SEISMIC CONDITIONS Housekeeping items were identified during walkdowns and walk-bys that were not potentially seismic adverse conditions.

All such items were brought to the attention of plant personnel and CRs were generated as necessary.

These issues included water on the floor and loose items (small tools, trash, etc.) stored in the plant areas. These items were processed through the site CAP process and are not specifically documented in this report though are available in the Plant CAP database.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSMIMA NEAR-TERM E 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 43 OF 49 9.0 PEER REVIEW 9.1 PEER REVIEW PROCESS The peer review for the Near Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdowns was performed in accordance with Section 6 of EPRI Report 1025286 (Reference 10.2). The peer review included an evaluation of the following activities:

• review of the selection of the structures, systems, and components (SSCs) that are included in the Seismic Walkdown Equipment List (SWEL);" review of a sample of the checklists prepared for the Seismic Walkdowns and Area Walk-bys;* review of licensing basis evaluations and decisions for entering the potentially adverse seismic conditions in to the plant's Corrective Action Plan (CAP); and* review of the final submittal report.This report provides results of the review process for each review activity as well as the results of the peer review.9.2 PEER REVIEW RESULTS

SUMMARY

9.2.1 Seismic Walkdown Equipment List Development The selection of items for the SWEL underwent peer review according to the guidance in Section 3 of EPRI Report 1025286 (Reference 10.2). The SSCs to be evaluated during the Seismic Walkdown were selected as described in Section 6.0 of this report. The list of components was provided to the members of the Peer Review Team, which consisted of all four peer reviewers listed in Section 4.0. The Peer Review Team members independently provided comments to the personnel who selected the components on the SWEL. All comments were addressed and the Peer Review Team reviewed the changes made to the SWEL and the final SWEL, to ensure all recommendations from EPRI Report 1025286 (Reference 10.2) were met. Specifically, the Peer Reviewers confirmed that all SSCs in SWEL 1 and 2 were Seismic Category I components that do not undergo regular inspections.

Specific considerations for the peer review process are described below for SWEL 1 and SWEL 2. The peer review check sheet of the SWEL is provided in Attachment 2.For SWEL 1, the Peer Review Team verified that the list of SSCs represented a diverse sample of the equipment required to perform the following five safety functions, as specified by EPRI Report 1025286 (Reference 10.2):

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM RE 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 44 OF 49* Reactor Reactivity Control* Reactor Coolant Pressure Control* Reactor Coolant Inventory Control* Decay Heat Removal and" Containment Function For SWEL 1, the Peer Review Team also verified that the SSCs included an appropriate representation of items having the following sample selection attributes:

• Various types of systems* Major new and replacement equipment" Various types of equipment* Various environments

• Equipment enhanced based on the findings of the IPEEE and" Risk insight consideration The final SWEL 1 contains items that perform each of the five safety functions specified by EPRI Report 1025286 (Reference 10.2). Numerous components perform more than one of the safety functions and all five safety functions are well represented by the components on the list.SWEL 1 contains components from all the classes of equipment listed in Appendix B of EPRI.Report 1025286 (Reference 10.2), except for cases where there are no safety-related components at the plant that fall into that specific equipment class. The list contains major new and replacement items, and items enhanced based on the IPEEE as well as equipment located in various environments and areas of the plant. All major safety-related systems are represented and risk factors were considered in the development of the list.For SWEL 2, the Peer Review Team determined that the process to select spent fuel pool related items complied with EPRI Report 1025286 (Reference 10.2). Portions of the spent fuel pool cooling system at Vogtle Unit 2 are Seismic Category I and all different types of components are represented on the SWEL 2. No items that could cause rapid drain down of the Spent Fuel Pool for Vogtle Unit 2 were identified.

Therefore, SWEL 2 does not contain any components associated with potentially rapid drain down of the pool. The Peer Review Team concluded that the bases for including/excluding items associated with the spent fuel pool were well documented and that the final SWEL 2 complies with EPRI Report 1025286 (Reference 10.2).

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 45 OF 49 In summary, all of the Peer Review comments made during development of SWEL 1 and SWEL 2 were resolved by the team that prepared the SWELs. The resolutions were reviewed by the Peer Review Team and it was determined that all comments were adequately addressed.

The SWEL was determined to incorporate all comments made by the Peer Review Team during the process.During the process of conducting the walkdowns, a small number of isolated components that were not accessible were removed from the list and in most cases equivalent items that were determined to be accessible were added. The Peer Review Team reviewed all changes made to the SWELs and determined that these changes had no impact on the adequacy of the SWELS with respect to the provisions contained in EPRI Report 1025286 (Reference 10.2). The Peer Review Team concludes that the team that developed the SWELs appropriately followed the SWEL development process described in Section 3 of EPRI Report 1025286 (Reference 10.2).The Peer Review Checklist of the SWEL is provided in Attachment 2.9.2.2 Seismic Walkdowns and Area Walk-Bys The Peer Review Team was on-site and very involved with the Seismic Component Walkdowns and Area Walk-bys.

The Peer Review was performed as follows:* Each of the three walkdown teams performed an initial equipment Seismic Walkdown and an Area Walk-by under the observation of the other teams and the walkdown Peer Review Team. The Peer Review Team provided comments and suggestions and answered questions raised by the team performing the walkdown and the other walkdown teams." During the first week of walkdowns, a member of the walkdown Peer Review Team individually accompanied each of the SWE walkdown teams and observed the SWE team conducting the Seismic Walkdowns and Area Walk-bys.

The Peer Review Team confirmed first-hand that the SWE walkdown teams performed the Seismic Walkdowns and Area Walk-bys as described in Section 4 of EPRI Report 1025286 (Reference 10.2). A member of the Peer Review Team accompanied each of the three walkdown teams on at least one full day of walkdowns.

SWE walkdown teams were encouraged and expected to carry a copy of Section 4 from the EPRI Report 1025286 (Reference 10.2) and refer to it, as necessary, during conduct of the Seismic walkdowns and Area Walk-bys." Finally, the walkdown Peer Review Team reviewed the Seismic Walkdown and Area Walk-by packages completed during the first week to ensure that the checklists were completed in accordance with the guidance provided in EPRI Report 1025286 (Reference 10.2). The walkdown Peer Review Team confirmed that the Seismic Walkdown and Area VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 46 OF 49 Walk-by packages were consistent, thorough, and the packages accurately reflected the results of the walkdowns and walk-bys as witnessed during the first week of walkdowns.

The Peer Review Team concluded that the SWE teams were familiar with the process for Seismic Equipment Walkdowns and Area Walk-bys.

The SWE teams adequately demonstrated their ability to identify potentially adverse seismic conditions such as adverse anchorage, adverse spatial interaction, and other adverse conditions related to anchorage, and perform anchorage configuration verifications, where applicable.

The SWEs also demonstrated the ability to identify seismically-induced flooding interactions and seismically-induced fire interactions.

The SWEs documented the results of the Seismic Walkdowns and Area Walk-bys on the appropriate checklists from Appendix C of EPRI Report 1025286 (Reference 10.2).The Peer Review Team inspected all the checklists completed during the first week of Seismic Walkdowns, which represents approximately 30% of the total number of the checklists.

Peer review of the Seismic Walkdowns and Area Walk-bys identified minor editorial errors and also some instances where comments in the checklists required additional explanation and information.

Mr. Ashworth and Mr. Whitmore provided verbal feedback to the SWEs to adjust these entries accordingly.

The SWEs understood the comments and incorporated the recommendations and updates from the Peer Review Team.Since the peer review occurred at the start of the Seismic Walkdowns, the peer reviewers were able to provide comments at the early stages of the walkdown process to ensure consistency in the reporting for all packages.

Subsequently, the Peer Review Team considered the number of completed walkdown packages reviewed to be appropriate.

In addition, all members of the Peer Review Team, including Mr. Ashworth, Ms. Brown, Mr. Starck and Mr. Whitmore were available by phone as necessary during the entire Walkdown process.9.2.3 Licensing Basis Evaluations All potentially adverse seismic conditions identified were immediately entered into the plant CAP for further review and disposition as discussed in Section 8.1 of this report. Therefore, the seismic walkdown teams did not perform licensing basis evaluations apart from evaluations performed as part -for the CAP. The Peer Review Team considers this CAP process approach fully comprehensive and acceptable for addressing the potentially adverse seismic conditions observed during the Seismic Walkdowns.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 47 OF 49 9.2.4 Submittal Report The Peer Review Team was provided with drafts of the submittal report. This allowed the Peer Review Team to provide guidance and input and verify the submittal report would meet the objectives and requirements of EPRI Report 1025286 (Reference 10.2).The Peer Review Team provided both verbal and written comments on the draft reports and was active in ensuring the report was thorough, complete and accurate.

The final version of the submittal report includes all necessary elements of the Peer Review and meets the requirements of the 50.54(f) letter.

VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSIIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 48 OF 49

10.0 REFERENCES

10.1 1OCFR50.54(f)

Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident, March 12, 2012 10.2 EPRI 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, June 2012 10.3 Generic Letter No. 88-20, Supplement 4, Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities 10.4 Generic Letter No. 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue (USI) A-46 10.5 Regulatory Guide 1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants, December 1973 10.6 NMP-GM-033-GLO1 Ver. 1.0, SAM NTTF Seismic Walkdowns Guide 10.7 VEGP FSAR, Rev.18, September 2012 10.8 Individual Plant Examination of External Events (IPEEE) -Seismic, Vogtle Electric Generating Plant, Unit 1 and Unit 2 10.9 Document No. 12L0075-RPT-001, Revision 0, May 18, 2012, "Southern Nuclear Company Seismic IPEEE Walkdown of Modified Equipment in Support of 1OCFR50.69 Risk Informed Project -Plant Vogtle" 10.10 Regulatory Guide 1.61, Damping Values for Seismic Design of Nuclear Power Plants, October 1973 10.11 NUREG/CR-0098, Development of Criteria for Seismic Review of Selected Nuclear Power Plants, May 1978 10.12 EPRI Report NP-6041, A Methodology for Assessment of Nuclear Power Plant Seismic Margin, Revision 1, August 1991 VOGTLE UNIT 2 SEISMIC WALKDOWN REPORT NO. SNCV061-RPT-02 FOR RESOLUTION OF FUKUSHIMA NEAR-TERM REV. 0 TASK FORCE RECOMMENDATION 2.3: SEISMIC PAGE 49 OF 49 11.0 ATTACHMENTS ATTACHMENT 1 -SEISMIC WALKDOWN EQUIPMENT LISTS ATTACHMENT 2 -PEER REVIEW CHECKLIST FOR THE SWEL 1 AND 2 ATTACHMENT 3 -SEISMIC WALKDOWN CHECKLISTS ATTACHMENT 4 -AREA WALK-BY CHECKLISTS ATTACHMENT 5 -IPEEE VULNERABILITIES INFORMATION ATTACHMENT 6 -SEISMIC WALKDOWN ENGINEER CERTIFICATIONS ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 ATTACHMENT 1 UNIT 2 -SEISMIC WALKDOWN EQUIPMENT LISTS NO. SNCV061-RPT-02 Equipment List Pages Unit 2 -Base List 1 2-21 Unit 2 -SWEL 1 22-30 Unit 2 -Base List 2 31-33 Unit 2 -SWEL 2 34-36 Page 1 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 ATTACHMENT 1 SEISMIC WALKDOWN EQUIPMENT LISTS UNIT 2 -BASE LIST 1 NO. SNCV061-RPT-02 Equipment List Panes Unit 2 -Base List 1 2 -21 Unit 2 -SWEL 1 22-30 Unit 2 -Base List 2 31-33 Unit 2 -SWEL 2 34-36 Page 2 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EOUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARKNO 10035 09 2-1532-B7-001-000 10036 09 2-1532-87-002-000 10039 09 2-1539-A7-001-000 10040 09 2-1539-A7-002-000 10041 09 2-1539-A7-005-000 1004S 09 2-1540-87-001-000 10046 09 2-1540-87-002-000 10047 09 2-1540-87-003-000 10048 09 2-1540-87-004-000 10049 09 2-1540-87-005-000 10054 09 2-15SS-A7-001-000 10055 09 2-1555-A7-002-000 10056 09 2-1555-A7-003-000 10057 09 2-1555-A7-004-000 10058 09 2-1555-A7-005-000 10059 09 2-155-A7-O06-000 10078 09 2-1561-E7-001-000 10079 09 2-1561-E7-002-000 10080 09 2-1561-N7-001-O00 10081 09 2-1561-N7-002-000 10090 09 2-1566-B7-001-000 10091 09 2-1566-87-002-000 10092 09 2-1566-87-003-000 10093 09 2-1566-B7-004-000 10098 11 2-1592-C7-001 10099 11 2-1592-C7-002 10100 05 2-1592-P7-001 10101 05 2-1592-P7-002 10102 21 2-1592-T7-O01 10103 21 2-1592-T7-002 10110 09 2-1593-87-001 10111 09 2-1593-87-002 DESCRIPT BATTERY RM EXHAUST FAN & MOTOR BAITERY RM EXHAUST FAN & MOTOR CB AUX RELAY RM ESF A/C UNIT CB AUX RELAY RM ESF A/C UNIT CB NORMAL AC RM ESF A/C UNIT DIESEL POWER CABLE TUNNEL EXHAUST FAN UNIT DIESEL POWER CABLE TUNNEL EXHAUST FAN UNIT NSCW TOWER CABLE TUNNEL EXHAUST FAN UNIT NSCW TOWER CABLE TUNNEL EXHAUST FAN UNIT AUX BLDG TRAIN A TUNNEL SUPPLY FAN UNIT ELEC SWGR AND MCC ROOM COOLER A ELEC SWGR AND MCC ROOM COOLER B ELEC SWGR AND MCC ROOM COOLER A ELEC SWGR AND MCC ROOM COOLER B ELEC SWGR AND MCC ROOM COOLER A ELEC SWGR AND MCC ROOM COOLER B PIPING PENETRATION AREA COOLER PIPING PENETRATION AREA COOLER PIPING PENETRATION ROOM FILTRATION AND EXHAUST UNIT PIPING PENETRATION ROOM FILTRATION AND EXHAUST UNIT DG A BLDG ESF SUPPLY FAN NO. 1 DG B BLDG ESF SUPPLY FAN NO. 2 DG A BLDG ESF SUPPLY FAN NO. 3 DG B BLDG ESF SUPPLY FAN NO. 4 CB ESSENTIAL CHILLER CB ESSENTIAL CHILLER ESSENTIAL CHILLED WATER PUMP ESSENTIAL CHILLED WATER PUMP ESSENTIAL CHILLED WATER EXPANSION TANK ESSENTIAL CHILLED WATER EXPANSION TANK AFW PUMP A SUPPLY FAN & MOTOR AFW PUMP B SUPPLY FAN & MOTOR BUILDING CONTROL CONTROL CONTROL CONTROL CONTROL TUNNEL TUNNEL TUNNEL TUNNEL AUX AUX AUX AUX AUX AUX AUX AUX AUX AUX AUX DG DG DG DG CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL AFWP HOUSE AFWP HOUSE ELEV 180'-0" 200'-0" 240'-0" 260'-0" 1951-0S" 180-0" 220'-0" 220'-0" 245'-0" 119'-3" 245'-0" 180,-0S" 180'-S" 220'-0" 220'-0" 245'-0" 245'-0" 245'-0" 245'-0" 255'-0" 255'-0" 255'-0" 255'-0" 260'-0" 260'-0" 260'-0" 260'-0" 260'-0" 260'-0" 220'-0" 220'-0" ROOM R833 RB32 RA81 R223 R325 1T4A @ DGB 1T4B @ DGB 1T5A @ NSCW 1T5B @ NSCW R221 RD02 R221 RB123 RB121 R149 R147 R219 R219 R219 R220 R208 R203 R208 R203 R310 R308 R310 R308 R310 R308 R101 R102 Page 3 of 36 ATTACHMENT I SEISMIC WALKIDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARK-NO DESCRIPT BUILDING ELEV ROOM 13000 20 2-1601-QS-MCB MAIN CONTROL BOARD CONTROL 220'-0" R164 13001 20 2-1601-U3-TO3 MN CONT BD TERMINATION CABINET CONTROL 200'-0" RA23 13002 20 2-1601-U3-T04 MN CONT BD TERMINATION CABINET CONTROL 240'-0" R224 13003 20 2-1601-U3-TO5 MN CONT RD TERMINATION CABINET CONTROL 200'-0" RA23 13004 20 2-1601-U3-T06 MN CONT RD TERMINATION CABINET CONTROL 240'-0" R224 13005 20 2-1601-U3-TO7 MN CONT RD TERMINATION CABINET CONTROL 200'-0" RA23 13006 20 2-1601-U3-TO8 MN CONT RD TERMINATION CABINET CONTROL 240'-0" R224 13007 20 2-1601-U3-TI0 MN CONT BI TERMINATION CABINET CONTROL 240'-G' R224 13008 20 2-1601-U3-Tll MN CONT BD TERMINATION CABINET CONTROL 200'-0" RA23 13009 20 2-1601-U3-TI4 MN CONT BD TERMINATION CABINET CONTROL 240'-0" R224 13010 20 2-1601-U3-TIS MN CONT RD TERMINATION CABINET CONTROL 200'-0" RA23 13011 20 2-1601-U3-T19 MN CONT BD TERMINATION CABINET CONTROL 200'-0" RA23 13012 20 2-1601-U3-T20 MN CONT BD TERMINATION CABINET CONTROL 240'-0" R224 13013 20 2-1601-U3-T27 MN CONT BD TERMINATION CABINET CONTROL 200'-0" RA23 14002 18 2-1602-QS-NIR NUCLEAR INST RACKS CONTROL 220'-0" R164 20 2-1602-PS-NFB GAMMA-METRICS N32/N36 SR/IR APMPLIFIER Train B CONTROL 180'-0" RB19 15000 20 2-1604-QS-PC1 PROCESS CONTROL GROUP 1 CONTROL 220'-0" R164 15001 20 2-1604-QS-PC2 PROCESS CONTROL GROUP 2 CONTROL 220'-0" R164 15002 20 2-1604-QS-PC3 PROCESS CONTROL GROUP 3 CONTROL 220'-0" R164 15003 20 2-1604-QS-PC4 PROCESS CONTROL GROUP 4 CONTROL 220'-0" R164 15013 20 2-1604-Q5-PCG BOP CONTROL PANEL I CONTROL 220'-0" R164 15004 20 2-1604-OS-PCP MISC SYS/EQPT PANEL CONTROL 220'-0" R164 15005 20 2-1604-QS-PP1 BOP PROTECTION CH 1 PANEL CONTROL 220'-0" R164 15006 20 2-1604-QS-PP2 BOP PROTECTION CH 2 PANEL CONTROL 220'-0" R164 1S007 20 2-1604-QS-PP3 BOP PROTECTION CH 3 PANEL CONTROL 220'-0" R164 15008 20 2-1604-QS-PP4 BOP PROTECTION CH 4 PANEL CONTROL 220'-0" R164 15009 20 2-1604-QS-PS1 PROCESS I&C PROTECT I CONTROL 220'-0" R164 15010 20 2-1604-QS-PS2 PROCESS I&C PROTECT II CONTROL 220'-0" R164 15011 20 2-1604-QS-PS8 PROCESS I&C PROTECT III CONTROL 220'-0" R164 15012 20 2-1604-QS-PS4 PROCESS I&C PROTECT IV CONTROL 220'-0" R164 16000 20 2-1605-CS-ASI ALTERNATE SHDN IND EAGLE 21 CAB CONTROL 240'-0" R264 16001 20 2-1605-PS-SDA SHUTDOWN PANEL TRN A CONTROL 200'-0" RA76 Page 4 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARKNO DESCRIPT BUILDING ELEV ROOM 16002 20 2-1EE-PS-SDB SHUTDOWN PANEL TRN 8 CONTROL 200'-0" RA24 16003 20 2-1605-QS-SPA SOLID STATE PROT SYS CAB-TRN A CONTROL 220'-0" R164 16004 20 2-1605-QS-SPE SOLID STATE PROT SYS CAB-TRN B CONTROL 220'-0" R164 1600E 20 2-1605-QS-SPC SOLID STATE PROT SYS CAB-TRN C CONTROL 220'-0" R164 16006 20 2-1605-QS-SPD SOLID STATE PROT SYS CAB-TRN D CONTROL 220'-0" R164 16007 20 2-1605-QO-STA SAFEGUARD TEST CAB-TRN A CONTROL 220'-0" R164 16008 20 2-1605-QS-STB SAFEGUARD TEST CAB-TRN B CONTROL 220'-0" R164 21001 20 2-1606-S6-002 REACTOR TRIP SWITCHGEAR CONTROL 180'-0" RB07 21002 20 2-1620-QS-ESF BOP ESF PANEL CONTROL 220'-0" R164 17000 20 2-1623-D5-001 REMOTE PROCESSING UNITA CAB S CONTROL 200'-0" RAS6 17001 20 2-1623-DS-002 REMOTE PROCESSING UNIT A CAB 2 CONTROL 200'-0" RA16 17002 20 2-1623-DS-003 REMOTE PROCESSING UNIT E CAB 1 CONTROL 240'-0" R264 17003 20 2-1623-D5-004 REMOTE PROCESSING UNIT B CAB 2 CONTROL 240'-0" R264 17004 20 2-1623-DS-OOEA DISPLAY PROCESSING UNITA CONTROL 200'-0" RA16 17005 20 2-1623-DS-006B DISPLAY PROCESSING UNIT B CONTROL 240'-0" R264 18000 03 2-1804-S3-A02 4160V SWITCHGEAR IAA02 CONTROL 200'-0" RAS6 18001 03 2-1804-$3-AS3 4160V SWITCHGEAR EBA03 CONTROL 200'-0" RA15 18002 01 2-180S-S3-ABA 480V MOT CONTROL CTR SABA CONTROL 260'-0" R325 18003 01 2-1805-53-ABE 480V MOT CONTROL CTR lABB AUX 220'-0" R149 18004 01 2-1805-53-ABC 480V MOT CONTROL CTR 2ABC CONTROL 180'-0" RB04 18005 01 2-1805-S3-ABD 480V MOT CONTROL CTR LABD AUX 143'-6" RC07 18006 01 2-1805-S3-ABE 48EV MOT CONTROL CTR 1ABE CONTROL 180'-0" R01 18007 01 2-1805-S3-ABF 48EV MOT CONTROL CTR 1ABF DG 220'-0" RO0E 18008 02 2-1805-S3-BEO 480V SWITCHGEAR INB01 CONTROL 180'-0" RB14 18009 02 2-1SEE-S3-BE4 480V SWITCHGEAR 1AB04 CONTROL 180'-0" RB04 18009 02 2-1805-S3-BO4XR 480V SWITCHGEAR 1AB04 CONTROL 180'-O" RB04 18010 02 2-1805-S3-B05 480V SWITCHGEAR 1AB05 CONTROL 180'-0" RB04 18010 02 2-1805-53-BOSXR 480V SWITCHGEAR SA805 CONTROL 180'-0" RB04 18011 02 2-1805-S3-BE6 480V SWITCHGEAR 1BBE6 CONTROL 180'-C" R6IE 18011 02 2-1805-S3-BORXR 480V SWITCHGEAR IBB06 CONTROL 180'-0" RB18 18012 02 2-1805-$3-BE7 480V SWITCHGEAR SBB07 CONTROL 180'-0" RB18 18012 02 2-1805-S3-BO7X 480V SWITCHGEAR SBB07 CONTROL 180'-0" RE18 Page 5 of 36 ATTACHMENT 1: SEISMIC WALKIDOWN EQUPMENT LISTS NO. SNCVO61-RPT-02, VERSION 1.0 LINE NO. CLASS MARKNO DESCRIPT BUILDING ELEV ROOM 18013 02 2-1805-$3-810 480V SWITCHGEAR 1NB10 CONTROL 180'-0" RB33 18013 02 2-1805-$3-B10X 480V SWITCHGEAR INB1O CONTROL 180'-0" R833 18014 02 2-1805-S3-815 480V IWITCHGEAR IAB15 AUX 119'-3" RD104 18014 02 2-1805-S3-B5XR 480V SWITCHGEAR IABiS AUX 119'-3" RD104 18015 02 2-1805-S3-816 480V SWITCHGEAR 1BB16 AUX 245'-0" R223 18015 02 2-1805-S3-B16X 480V SWITCHGEAR 1BB16 AUX 245'-0" R223 18016 01 2-1805-S3-BBA 480V MOT CONTROL CTR 1BBA CONTROL 260'-0" R305 18017 01 2-1805-S3-8B8 480V MOT CONTROL CTR 1888 AUX 220'-0" R147 18018 01 2-1805-$3-BBC 480V MOT CONTROL CTR 1BBC CONTROL 180'-0" RB18 18019 01 2-1805-S3-BBD 480V MOT CONTROL CTR 1BD AUX 1801-0" R8122 18020 01 2-1805-S3-88E 480V MOT CONTROL CTR 18BE CONTROL 200'-0" RA79 18021 01 2-1805-53-BBF 480V MOT CONTROL CTR 1BBF DG 220'-0" R103 18022 02 2-1805-S3-NBR 480V MCC 1NBR CONTROL 180'-0" R833 18023 02 2-1805-S3-NBS 480V MCC 1NBS CONTROL 180'-0" RB14 18052 23 2-1805-S3-RHR1A STARTER/RHR HV-8701B CONTROL 180'-0" RB26 18053 23 2-1805-53-RHR2A STARTER/RHR HV-8702A CONTROL 180'-0" RB31 18054 16 2-1805-Y3-IC5 RHR ISO VLV INVERTER CONTROL 180'-0" RB26 18055 16 2-1805-Y3-1D6 RHR ISO VLV INVERTER CONTROL 180'-0" R831 19001 15 2-1806-83-BN3 125 VDC BATTERY iND3AB CONTROL 280'-0" R406 19002 15 2-1806-83-BYA 125 VDC BATTERY 1ADEB CONTROL 180'-0" RB27 19003 15 2-1806-83-BYB 125 VOC BATTERY 1BDB CONTROL 180'-0" R832 19004 15 2-1806-83-BYC 125 VDC BATTERY ICDIB CONTROL 180-0" RB25 19005 15 2-1806-83-BYD 125 VDC BATTERY 1DD1B CONTROL 180'-0" RB37 19006 16 2-1806-83-CAA BATTERY CHARGER lADiCA CONTROL 180'-0" R829 19007 16 2-1806-83-CAB BATTERY CHARGER SAD1CB CONTROL 180'-0" RB29 19008 16 2-1806-83-CBA BATTERY CHARGER 1BDlCA CONTROL 180'-0" RB36 19009 16 2-1806-83-CBB BATTERY CHARGER EBDOCB CONTROL 180'-0" RB36 19010 16 2-1806-83-CCA BATTERY CHARGER iCDlCA CONTROL 180'-0" RB26 19011 16 2-1806-B3-CCB BATTERY CHARGER 1CDOCB CONTROL 180'-0" RB26 19012 16 2-1806-B3-CDA BATTERY CHARGER 1DDICA CONTROL 180'-0" RB31 19013 16 2-1806-83-CDB BATTERY CHARGER 1DD1CB CONTROL 180'-0" RB31 19014 14 2-1806-Q3-DAS 125 VDC DISTR. PANEL 1AD11 CONTROL 180'-0" R829 Page 6 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARKNO 19015 14 2-1806-Q3-DA2 19016 14 2-1806-Q3-DB1 19017 14 2-1806-Q3-DB2 19018 14 2-1806-Q3-DCS 19019 14 2-1806-Q3-DD1 19020 01 2-1806-S3-DCA 19021 01 2-1806-S3-DCB 19022 01 2-1806-53-DCC 19000 02 2-1806-53-DN3 19023 02 2-1806-S3-DSA 19024 02 2-1806-13-DS8 19025 02 2-1806-53-DSC 19026 02 2-1806-53-DSD 18024 14 2-1807-Q3-VI1 18025 14 2-1807-Q3-VI2 18026 14 2-1807-Q3-VI3 18027 14 2-1807-Q3-Vi4 18028 14 2-1807-Q3-VIS 18029 14 2-1807-Q3-VI6 18030 14 2-1807-Q3-VN1 18031 14 2-1807-Q3-VN2 18032 14 2-1807-Q3-VN4 2-1807-Y3-31OR 2-1807-Y3-911R 2-1807-Y3-312R 2-1807-Y3-313R 2-1807-Y3-314R 2-1807-Y3-315R 18039 16 2-1807-Y3-12R 18040 16 2-1807-Y3-13R 18041 16 2-1807-Y3-14R 18042 16 2-1807-Y3-IASR DESCRIPT 125 VDC DISTR. PANEL 1AD12 125 VDC DISTR. PANEL 1BD11 125 VDC DISTR. PANEL 18D12 125 VDC DISTR. PANEL 1CDl1 125 VDC DISTR. PANEL 1DD11 125 VDC MCC 1ADIM 125 VDC MCC 1BDIM 125 VDC MCC 1COIM 125 VDC SWITCHGEAR 1ND3A 125 VDC SWITCHGEAR lAD1 125 VDC SWITCHGEAR 1BD1.125 VDC SWITCHGEAR iCD1 125 VDC SWITCHGEAR 1DD1 120 VAC VITAL PANEL lAYlA 120 VAC VITAL PANEL 1BYlB 120 VAC VITAL PANEL iCYIA 120 VAC VITAL PANEL 1DYSB 120 VAC VITAL DIST PANEL 1AY2A 120 VAC VITAL DIST PANEL 18Y28 120 VAC ESSENT PANEL 1NYIN 120 VAC ESSENT PANEL 1NY2N 120 VAC ESSENT PANEL 1NY4N REGULATED TRANSFORMER REGULATED TRANSFORMER REGULATED TRANSFORMER REGULATED TRANSFORMER REGULATED TRANSFORMER REGULATED TRANSFORMER ESSENTIAL AC INVERTER IND312 ESSENTIAL AC INVERTER IND313 ESSENTIAL AC INVERTER iND314 VITAL AC INVERTER IAD111 BUILDING CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL AUX AUX CONTROL CONTROL CONTROL ELEV 180,-0., 200'-0" 200'-0" 200'-0" 200'-0" 200'-0" 200'-D" 200'-D" 280'-0" 200'-0" 200'-0" 200'-0" 200'-0" 180'-0" 180'-0" 1801-0" 180'-0" 220'-0" 220'-0" 180'-0" 180'-0" 260'-0" ROOM RB29 RB36 RB36 R826 RB31 RB29 RB36 RB85 R407 RB29 RB36 RB26 RB31 RB29 RB36 RB26 RB31 R149 R147 RB28 RB28 R305 RB28 R828 R305 RB29 CONTROL 180'-0" CONTROL 180'-0" CONTROL 260'-0" CONTROL 180'-0" Page 7 of 36 ATTACHMENT 1: SEISMIC WALKOOWN EOUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARK-NO 18043 16 2-1807-Y3-1A11R 18044 16 2-1807-Y3-1B12R 18045 16 2-1807-Y3-IB2R 18046 16 2-1807-Y3-1C3 18047 16 2-1807-Y3-ID4R 2-1807-Y3-RX25R 2-1807-Y3-RX26R 2-1807-Y3-RX21R 2-1807-Y3-RX22R 2-1808-T3-116R 2-1808-T3-113R 2-1808-T3-114 2-1808-T3-115 22000 14 2-1808-Q3-L12 22001 14 2-1808-Q3-L19 22002 14 2-1808-QS-L29 22003 14 2-1808-QS-L32 22004 14 2-1808-Q3-L47 22005 14 2-1808-Q3-L50 22006 04 2-1808-T3-003 22007 04 2-1808-T3-053 20000 20 2-1816-U3-001 20001 20 2-1816-U3-002 20002 20 2-1816-U3-003 20003 20 2-1816-U3-004 20004 20 2-1816-U3-005 20005 20 2-1816-U3-006 20006 20 2-1816-U3-007 20007 20 2-1816-U3-009 20008 20 2-1816-U3-010 20009 20 2-1816-U3-014 20010 20 2-1816-U3-015 DESCRIPT VITAL AC INVERTER 1AD1111 VITAL AC INVERTER 1BD1112 VITAL AC INVERTER 1BD12 VITAL AC INVERTER 1CD113 VITAL AC INVERTER 1DD114 REGULATED TRANSFORMER REGULATED TRANSFORMER REGULATED TRANSFORMER REGULATED TRANSFORMER ISOLATION LTG. TRANSFORMER REGULATED TRANSFORMER BUILDING ELEV ROOM AUX 220'-0" R149 AUX 220'-0" R147 CONTROL 180'-0" RB36 CONTROL 180'-0" RB26 CONTROL 180'-0" RB31 ESSENTIAL LTG DIST PANEL 1NLP12 ESSENTIAL LTG DIST PANEL 1NLP19 EMERGENCY LTG DIST PANEL 1NLP29 EMERGENCY LTG DIST PANEL 1NLP32 EMERGENCY LTG DIST PANEL 1NLP47 EMERGENCY LTG DIST PANEL 1NLP50 LTG DIST XFMR 1NBR11X LTG DIST XFMR 1NBS14X AUXILIARY RELAY PANEL A AUXILIARY RELAY PANEL N-A AUXILIARY RELAY PANEL B AUXILIARY RELAY PANEL N-B ISOLATION DEVICE PANEL AB ISOLATION DEVICE PANEL B-C ELECTRICAL AUXILIARY BOARD ISOLATION DEVICE PANEL C ISOLATION DEVICE PANEL AUXILIARY RELAY PANEL AUXILIARY RELAY PANEL AUX 195'-0" RA75 AUX 143'-6" RC31 CONTROL 220'-0" R131 CONTROL 220'-0" R131 DG 220'-0" R103 DG 220'-0" R101 AUX 195'-0" RA75 AUX 143'-6" RC31 CONTROL 200'-0" RA22 CONTROL 200'-0" RA22 CONTROL 240'-0" R223 CONTROL 240'-0" R223 CONTROL 220'-0" R164 CONTROL 220'-0" R164 CONTROL 220'-0" R164 CONTROL 220'-0" R164 CONTROL 220'-0" R164 CONTROL 200'-0" RA22 CONTROL 240'-0" RA22 Page 8 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARKNO DESCRIPT 20011 20 2-1816-U3-017 AUXILIARY RELAY PANEL 20012 20 2-1816-U3-018 AUXILIARY RELAY PANEL 21003 20 2-1821-U3-001 SF SEQUENCER BOARD TRAIN A 21004 20 2-1821-U3-002 SF SEQUENCER BOARD TRAIN B 21005 20 2-1823-QS-BPS SYSTEM STATUS MONITOR PANEL 21006 03 2-1825-S3-1AAA 13800V RCP SWITCHGEAR 1AAA 21007 03 2-1825-S3-SBAB 13800V RCP SWITCHGEAR 1BAB 21008 03 2-1825-S3-SCAC 13800V RCP SWITCHGEAR 1CAC 21009 03 2-1825-S3-1DAD 13800V RCP SWITCHGEAR 1DAD 11002 17 2-2403-G4-001 DIESEL GENERATOR A 11003 24 2-2403-G4-0S1-FOl DG INTAKE AIR FILTER 11004 24 2-2403-G4-001-F02 DG EXHAUST AIR SILENCER 11005 21 2-2403-G4-001-VOl DG AIR START RECEIVER 11006 21 2-2403-G4-001-V02 DG AIR START RECEIVER 11007 17 2-2403-G4-002 DIESEL GENERATOR B 11008 24 2-2403-G4-002-FO1 DG INTAKE AIR FILTER 11009 24 2-2403-G4-002-F02 DG EXHAUST AIR SILENCER 11010 21 2-2403-G4-002-VOl DG AIR START RECEIVER 11011 21 2-24030G4-002-V02 DG AIR START RECEIVER 11012 06 2-2403-P4-001 DIESEL FUEL OIL TRANSFER PUMP 11013 06 2-2403-P4-003 DIESEL FUEL OIL TRANSFER PUMP 11014 20 2-2403-PS-DGS DG IA GEN CTL PNL 11015 20 2-2403-PS-DG2 DG 1A ENG CTL PNL 11016 20 2-2403-PS-DG3 DG 1B GEN CTL PNL 11017 20 2-2403-PS-DG4 DG 1B ENG CTL PNL 11018 20 2-2403-T3-NGA DG 1A NEUTRAL GND CABINET 11019 20 2-2403-T3-NGB DG 1B NEUTRAL GND CABINET 11020 21 2-2403-T4-001 DIESEL FUEL OIL STORAGE TANK 11021 21 2-2403-T4-002 DIESEL FUEL OIL STORAGE TANK 11022 21 2-2403-T4-003 DIESEL FUEL OIL DAY TANK 11023 21 2-2403-T4-004 DIESEL FUEL OIL DAY TANK 02010 07 2-CV-9446 NSCT BLOWDOWN ISO AOV BUILDING ELEV CONTROL 200'-0" CONTROL 200'-0" CONTROL 200'-0" CONTROL 200'-0" CONTROL 220'-0" CONTROL 200'-0" CONTROL 200'-0" CONTROL 200'-0" CONTROL 200'-0" DG 220'-0" DG 255'-0" DG 255'-0" DG 220'-0" DG 220'-0" DG 220'-0" DG 255'-0" DG 255'-0" DG 220'-0" DG 220'-0" DFOST 211'-6" DFOST 211'-6" DG 220'-0" DG 220'-0" DG 220'-0" DG 220'-0" DG 220'-0" DG 220'-0" DFOST 211'-6" DFOST 211'-6" DG 220'-0" DG 220'-0" NSCT 206'-0" ROOM RA22 RA15 RA16 RA15 R164 RA01 RA01 RAl1 RAl1 R101 R20S R204 R101 R101 R103 R210 R103 R103 R103 RAO0 RA03 R101 R101 R103 R103 R101 R103 RA01 RA03 R104 R102 R402 Page 9 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EOUPMENT LISTS*NO. SNCV061-RPT-02, VERSION 1.0 LINE NO.02011 05006 05007 02012 02013 10019 10020 06010 06011 06012 06013 06014 06045 06046 05008 05009 04004 04005 04006 02014 02015 03010 03011 10104 10105 09004 09005 09006 09007 09008 09009 05010 CLASS MARKNO 07 2-CV-9447 19 2-FIS-0610 19 2-FIS-0611 19 2-FIT-1640A 19 2-FIT-1641A 19 2-FSL-12045 19 2-FSL-12046 19 2-FT-0138 19 2-FT-0142 19 2-FT-0143 19 2-FT-0144R 19 2-FT-0145R 19 2-FT-0406 19 2-FT-0407 19 2-FT-0618 19 2-FT-0619 19 2-FT-0917 19 2-FT-O91SR 19 2-FT-0922R 19 2-FT-1802 19 2-FT-1803 19 2-FT-1876 19 2-FT-1877 19 2-FT-22425 19 2-FT-22426 19 2-FT-5150 19 2-FT-5151 19 2-FT-5152 19 2-FT-5153 19 2-FT-5154 19 2-FT-5155 08. 2-FV-0610 DESCRIPT NSCT SLOWDOWN ISO AOV RHR PUMP A FLOW TO MINIFLOW VALVE RHR PUMP B FLOW TO MINIFLOW VALVE NSCW RETURN FLOW NSCW RETURN FLOW INTERLOCK FLOW SWTCH CNTL SLD..CLOSES ON LOW AIR INTERLOCK FLOW SWTCH CNTL BLD..CLOSES ON AIR-FLO CCP A FLOW RCP 4 SEAL INJ FLOW RCP 0 SEAL INJ FLOW RCP 2 SEAL INJ FLOW RCP I SEAL INJ FLOW REACTOR HEAD LETDOWN LINE FLOW REACTOR HEAD LETDOWN LINE FLOW RHR A FLOW RHR B FLOW CCP INJECTION FLOW SIP A FLOW SIP 8 FLOW NSCW FLOW TO CB ESS CHILLER NSCW FLOW TO CS ESS CHILLER CCW A FLOW CCW S FLOW ECW FLOW ECW FLOW AFW FLOW TO SG 4 AFW FLOW TO SG 2 AFW FLOW TO SG 1 AFW FLOW TO SG 3 AFW B FLOW TO MINIFLOW VALVE AFW A FLOW TO MINIFLOW VAVLE RHR PUMP A MINIFLOW MOV BUILDING NSCT AUX AUX NSCT NSCT CONTROL CONTROL AUX FB FB AUX AUX CTB CTB AUX AUX AUX AUX AUX CONTROL CONTROL AUX AUX CONTROL CONTROL AUX CONTROL AUX CONTROL AFWP HOUSE AFWP HOUSE AUX ELEV 206'-0" 119'-3" 119'-3" 195'-0" 195'-0" 260'-0" 260'-0" 143-6" 200'-0" 200'-0" 195,-0a, 1951-0'183'-0" 183'-0" 119'-3" 143'-6" 180,-0", 180,-0", 180,-0", 260'-0" 260'-0" 195,-0I, 195'-0" 260-0"'260'-0" 195'-0" 200'-0" 195'-01" 200'-D" 220'-0" 220'-0" 143'-6" ROOM R302 RD113 RD41 TUNNEL 1T2A TUNNEL 1T2B R276 R254 RC11 RA01 RA01 RA103 RA0I3 RB03 RB03 RD41 RD41 RA39 RB119 R8117 R310 R308 RA98 RA96 R310 R308 RA61 RA02 RA102 RA1O R102 R1101 RC25 Page 10 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EOUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARK-NO DESCRIPT BUILDING ELEV ROOM 05011 08a 2-FV-0611 RHR PUMP B MINIFLOW MOV AUX 143'-6" RC26 AFWP 09010 08a 2-FV-5154 AFW PUMP B MINIFLOW MOV HOUSE 220'-0" R102 AFWP 09011 08a 2-FV-51S5 AFW PUMP A MINIFLOW MOV HOUSE 220'-0" R101 06015 08b 2-HV-0190A CCP A SAFETY GRADE CHARGING SOLENOID OP VLV AUX 1951-0" RA103 06016 08b 2-HV-0190B CCP B SAFETY GRADE CHARGING SOLENOID OP VLV AUX 143'-6" RC18 06047 08b 2-HV-0442A REACTOR HEAD LETDOWN LINE CONTROL SOV CTB 183'-0" RB03 06048 08b 2-HV-0442B REACTOR HEAD LETDOWN LINE CONTROL SOV CTB 183'-0" RB03 12005 07 2-HV-0780 NORMAL CTB SUMP PUMP DISCHARGE AOV CTB 1986-0S RB10 12006 07 2-HV-07B1 NORMAL CTB SUMP PUMP DISCHARGE AOV AUX 195'-0" RA103 04007 08b 2-HV-0943A ACCUMULATOR NITROGEN HDR VENT--SOLENOID OPERATED VALVE CTB 180'-0" RB10 04008 08b 2-HV-0943B ACCUMULATOR NITROGEN HDR VENT--SOLENOID OPERATED VALVE CTB 183'-0" RB1E 04009 07 2-HV-10957 RWST TO SLUDGE MIXING PUMP SUCTION AOV RWST 220'-0" R101 04010 07 2-HV-109S RWST TO SLUDGE MIXING PUMP SUCTION AOV RWST 220'-0" R101 02016 S8a 2-HV-11600 NSCW PUMP 1 DISCHARGE MOV NSCT 220'-S" R403 02017 08a 2-HV-11606 NSCW PUMP 3 DISCHARGE MOV NSCT 220'-0" R403 02018 08a 2-HV-11607 NSCW PUMP 2 DISCHARGE MOV NSCT 245'-0" R303 02019 08a 2-HV-11613 NSCW PUMP 4 DISCHARGE MOV NSCT 245'-0" R303 AFWP 10112 08a 2-HV-12005 AFW PUMP HOUSE AIR SUPPLY DAMPER HOUSE 220'-0" R102 AFWP 10113 08a 2-HV-12006 AFW PUMP HOUSE AIR SUPPLY DAMPER HOUSE 220'-0" R101 10094 08a 2-HV-12050R DG A AIR SUPPLY DAMPER FOR FAN NO. 1 DG 255'-0" R209 10095 08a 2-HV-12051R DG A AIR SUPPLY DAMPER FOR FAN NO.3 DG 255'-0" R209 10096 08a 2-HV-12053R DG AAIR SUPPLY DAMPER FOR FAN NO.2 DG 255'-0" R208 10097 08a 2-HV-12054R DG A AIR SUPPLY DAMPER FOR FAN NO.4 DG 255'-0" R208 10021 08a 2-HV-12128 CBCR FILTER UNIT AIR SUPPLY DAMPER CONTROL 220'-0" R140 10022 08a 2-HV-12129 CBCR FILTER UNIT AIR SUPPLY DAMPER CONTROL 220'-0" R127 10023 08a 2-HV-12130 CBCR FILTER UNIT AIR RETURN DAMPER CONTROL 220'-0" R140 10024 08a 2-HV-12131 CBCR FILTER UNIT AIR RETURN DAMPER CONTROL 220'-0" R127 10025 07 2-HV-12146 CBCR NORMAL AIR SUPPLY DAMPER CONTROL 240'-0" R264 10026 07 2-HV-12147 CBCR NORMAL AIR SUPPLY DAMPER CONTROL 240'-0" R264 10027 07 2-HV-12148 CBCR NORMAL AIR RETURN DAMPER CONTROL 240'-0" R264 10028 07 2-HV-12149 CBCR NORMAL AIR RETURN DAMPER CONTROL 240'-0" R264 10082 07 2-HV-12604 PPG PENETRATION NORMAL RETURN AIR ISOLATION DAMPER AUX 245'-0" R220 Page 11 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EOUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARK-NO 10083 07 2-HV-12605 10084 07 2-HV-12806 10085 07 2-HV-12607 10086 0eC 2-HV-12614 10087 08c 2-HV-12616 12021 Ob 2-HV-12976 12022 08b 2-HV-12977 08000 07 2-HV-13005A 08001 07 2-HV-13005B 08002 07 2-HV-13006A 08003 07 2-HV-13006B 08004 07 2-HV-13007A 08005 07 2-HV-13007B 08006 07 2-HV-13008A 08007 07 2-HV-13008B 07005 07 2-HV-15196 07006 07 2-HV-15197 07007 07 2-HV-15198 07008 07 2-HV-15199 02020 Oa 2-HV-1668A 02021 08a 2-HV-1668B 02022 08a 2-HV-1669A 02023 Oa 2-HV-16698 12007 Oa 2-HV-1974 12008 08a 2-HV-1975 12009 Oa 2-HV-1978 12010 Oa 2-HV-1979 12015 07 2-HV-2626B 12016 07 2-HV-2627B 12017 07 2-HV-2628B 12018 07 2-HV-2629B 08008 08c 2-HV-3006A DESCRIPT PPG PENETRATION NORMAL AIR SUPPLY ISOLATION DAMPER PPG PENETRATION NORMAL AIR SUPPLY ISOLATION DAMPER PPG PENETRATION NORMAL RETURN AIR ISOLATION DAMPER PPG PEN FILTRATION AND EXHAUST UNIT SUCTION DAMPER PPG PEN FILTRATION AND EXHAUST UNIT SUCTION DAMPER CTB AIR RADIATION MONITOR INLET SOV CTB AIR RADIATION MONITOR OUTLET SOV INBOARD MSIV BYPASS AOV--SG 1 OUTBOARD MSIV BYPASS AOV--SG 1 INBOARD MSIV BYPASS AOV--SG 4 OUTBOARD MSIV BYPASS AOV--SG 4 INBOARD MSIV BYPASS AOV-SG 2 OUTBOARD MSIV BYPASS AOV--SG 2 INBOARD MSIV BYPASS ADV-SG 3 OUTBOARD MSIV BYPASS AOV--SG 3 BFIV FOR SG 1 BFIV FOR SG 2 BFIV FOR SG 3 BFIV FOR SG 4 NSCW SPRAY VALVE NSCW TOWER BYPASS MOV NSCW SPRAY VALVE NSCW TOWER BYPASS MOV ACCW RETURN FROM RCP COOLERS MOV ACCW RETURN FROM RCP COOLERS MOV ACCW SUPPLY TO RCP COOLERS MOV ACCW SUPPLY TO RCP COOLERS MOV NORMAL CTB PURGE SUPPLY & EQUALIZING AOV NORMAL CTB PURGE SUPPLY & EQUALIZING AOV NORMAL CTB PURGE EXHAUST & EQUALIZING AOV NORMAL CTB PURGE EXHAUST & EQUALIZING AOV INBOARD MSIV--SG 1 BUILDING ELEV ROOM AUX 245'-0" R220 AUX 245'-0" R220 AUX 245'-0" R220 AUX 245'-0" R219 AUX 245'-0" R220 AUX 180'-0" RB131 AUX 180-0S' RB131 AUX 220'-0" R159 AUX 220'-0" R159 AUX 220'-0" R159 AUX 220'-0" R159 CONTROL 220'-0" R123 CONTROL 220'-0" R123 CONTROL 220'-0" R122 CONTROL 220'-0" R122 AUX 1951-0" RA104 CONTROL 200'-0" RA09 CONTROL 200'-0" RA09 AUX 195'-0" RA105 NSCT 195'-0" R410 NSCT 220"-0" R410 NSCT 195'-0" R31S NSCT 220'-0" R310 CTB 1981-0" RB03 AUX 195'-0" RA105 CTB 1981-0" RB03 AUX 1951-0" RA105 CTB 220'-0" R101 CONTROL 220'-0" R125 CTB 220'-0" R101 CONTROL 220'-0" R117 AUX 220'-0" R159 Page 12 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARKNO 08009 08c 2-HV-3006B 08010 08c 2-HV-3016A 08011 08c 2-HV-3016B 08012 08c 2-HV-3026A 08013 08c 2-HV-3026B 08014 08c 2-HV-3036A 08015 08c 2-HV-3036B 12023 07 2-HV-3502 12024 07 2-HV-3508 12025 07 2-HV-3514 09012 08a 2-HV-5132 09013 08a 2-HV-5134 09014 08a 2-HV-5137 09015 08a 2-HV-5139 07009 08c 2-HV-5227 07010 08c 2-HV-5228 07011 08c 2-HV-5229 07012 08c 2-HV-5230 12019 07 2-HV-7136 12026 07 2-HV-7150 08016 07 2-HV-7603A 08017 07 2-HV-7603B 08018 07 2-HV-7603C 08019 07 2-HV-7603D 12020 07 2-HV-7699 01010 08a 2-HV-8000A 01011 08a 2-HV-8OOOB 06041 08b 2-HV-8095A 06042 08b 2-HV-8095B 06043 08b 2-HV-8096A 06044 08b 2-HV-80968 12003 08a 2-HV-8100 DESCRIPT OUTBOARD MSIV-SG 1 INBOARD MSIV--SG 2 OUTBOARD MSIV--SG 2 INBOARD MSIV--SG 3 OUTBOARD MSIV--SG 3 INBOARD MSIV--SG 4 OUTBOARD MSIV-SG 4 HOT LEG SAMPLE & GFF DET AOV PRESSURIZER LIQUID SAMPLE AOV PRESSURIZER STEAM SAMPLE AOV AFW PUMP B DISCHARGE MOV AFW PUMP B DISCHARGE MOV AFW PUMP A DISCHARGE MOV AFW PUMP A DISCHARGE MOV MFIV FOR SG 1 MIV FOR SG 2 MFIV FOR SG 3 MFIV FOR SG 4 REACTOR COOLANT DRAIN TANK PUMP DISCHARGE AOV RCDT VENT AOV SG 1 BLOWDOWN ISOLATION AOV SG 2 BLOWDOWN ISOLATION AOV SG 3 BLOWDOWN ISOLATION AOV SG 4 BLOWDOWN ISOLATION AOV REACTOR COOLANT DRAIN TANK PUMP DISCHARGE AOV PORV BLOCK VALVE PORV BLOCK VALVE REACTOR HEAD LETDOWN LINE ISOLATION SOV REACTOR HEAD LETDOWN LINE ISOLATION SOV REACTOR HEAD LETDOWN LINE ISOLATION SOV REACTOR HEAD LETDOWN LINE ISOLATION SOV EXCESS LETDOWN & SEAL WATER LEAKOFF ISOLATION MOV BUILDING ELEV AUX 220'-0" CONTROL 220'-0" CONTROL 220'-0" CONTROL 220'-0" CONTROL 220'-0" AUX 220'-0" AUX 220'-0" FB 180-0a" FB 180'-0" FB 180-01" CONTROL 195'-0" CONTROL 195'-0" AUX 195-05" AUX 195'-0" AUX 195'-0" CONTROL 200'-0" CONTROL 200'-0" AUX 195'-0" FB 200'-0" FB 180'-0" AUX 1801-0", AUX 180'-0" AUX 180'-0" AUX 180'-0" CTE 183'-0" CTE 238'-0" CTB 238'-0" CTB 183'-0" CTB 183'-0" CTB 183'-0" CTB 183'-0" AUX 195'-0" ROOM R159 R123 R123 R123 R123 R159 R159 RA01 RA01 RAO1 RA09 RA09 RA1OS RAlE5 RA104 RA09 RA09 RAlE5 RA01 RA01 RB131 RB131 RB131 RB131 RB10 Rl10 Rl1G RB02 RB02 RB02 RBS2 RA103 Page 13 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EOUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARK-NO 06017 08a 2-HV-8105 06018 08a 2-HV-8106 06019 08a 2-HV-8110 06020 08a 2-HV-8111A 06021 08a 2-HV-8111B 12004 08a 2-HV-8112 06022 08a 2-HV-8116 06023 07 2-HV-8149A 06024 07 2-HV-8149B 06025 07 2-HV-8149C 06026 07 2-HV-8152 06027 07 2-HV-8154 06026 07 2-HV-5160 06029 08a 2-HV-8485A 06030 08a 2-HV-8485B 06031 08a 2-HV-8508A 06032 08a 2-HV-SS08B 05012 08a 2-HV-8701A 05013 08a 2-HV-87018 05014 08a 2-HV-8702A 05015 08a 2-HV-8702B 05016 08a 2-HV-8716A 05017 08a 2-HV-8716B 04011 08a 2-HV-8801A 04012 08a 2-HV-8801B 05018 0Sa 2-HV-8804A 05019 08a 2-HV-8804B 04013 08a 2-HV-8807A 04014 08a 2-HV-8807BR 05020 08a 2-HV-8811A 05021 08a 2-HV-8811B 05022 08a 2-HV-8812A DESCRIPT CHARGING TO REGEN HX MOV CHARGING DISCHARGE MOV CCP A & B COMMON MINIFLOW MOV CCP A MINIFLOW MOV CCP B MINIFLOW MOV EXCESS LETDOWN & SEAL WATER LEAKOFF ISOLATION MOV CCP A SAFETY GRADE CHARGING ISO MOV LETDOWN ISOLATION AOV LETDOWN ISOLATION AOV LETDOWN ISOLATION AOV LETDOWN ISOLATION AOV EXCESS LETDOWN ISOLATION AOV LETDOWN ISOLATION AOV CCP A DISCHARGE ISO MOV CCP B DISCHARGE MOV CCP A ALT. MINIFLOW MOV CCP B ALT. MINIFLOW MOV RCS TO RHR PUMP A SUCTION MOV RCS TO RHR PUMP A SUCTION MOV RCS TO RHR PUMP B SUCTION MOV RCS TO RHR PUMP B SUCTION MOV RHR TRAIN A TO RCS HOT LEG ISOLATION MOV RHR TRAIN B TO RCS HOT LEG ISOLATION MOV CCP INJECTION MOV CCP INJECTION MOV RHR TO CCP SUCTION HEADER MOV RHR TO SIP SUCTION HEADER MOV CCP/SIP SUCTION HEADER CROSS-CONNECT MOV CCP/SIP SUCTION HEADER CROSS-CONNECT MOV CTMT SUMP TO RHR PUMP A SUCTION MOV CTMT SUMP TO RHR PUMP B SUCTION MOV RWST TO RHR PUMP A SUCTION MOV BUILDING ELEV ROOM AUX 1951-0" RA103 AUX 1951-0" RA103 AUX 180'-0" RB115 AUX 143'-6" RC11 AUX 143'-6" RC1S CTB 1985-0" RB03 AUX 195-05" RA103 CTB 183'-0" RB03 CTB 183'-0" RB03 CTB 183'-0" RB03 AUX 195'-0" RA103 CTB 183'-0" RB03 CTR 195'-0" RB03 AUX 143'-6" RC11 AUX 143'-6" RC18 AUX 143'-6" RC11 AUX 143'-6" RC18 CT1 1801-0" R803 CTB 180-0-" RB02 CTB 180-05" RB03 CTB 1801-0" RB03 AUX 1191-0" RD22 AUX 1191-0" RD21 AUX 195-05" RA18 AUX 195'-0" RA1S AUX 143'-6" RC2S AUX 143'-6" RC26 AUX 1801-0" RB119 AUX 1801-0" RB117 AUX 143'-6" RC124 AUX 143'-6" RC01 AUX 119'-0" RD22 Page 14 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02.

VERSION 1.0 LINE NO. CLASS MARKNO 05023 Oa 2-HV-5812B 04015 08a 2-HV-8813 04016 08a 2-HV-8814 04017 08b 2-HV-8875A 04018 08b 2-HV-8875B 04019 08b 2-HV-8875C 04020 08b 2-HV-88750 04021 08b 2-HV-8875E 04022 08b 2-HV-8875F 04023 08b 2-HV-8875G 04024 08b 2-HV-R875H 04025 08a 2-HV-8920 06054 19 2-HY-0190A 06055 19 2-HY-OlSOS 06056 19 2-HY-0442A 06057 19 2-HY-0442B 04030 19 2-HY-0943A 04031 19 2-HY-0943B 12028 08b 2-HY-7150 12027 08b 2-HY-7699 06049 08b 2-HY-8149A 06050 08b 2-HY-8149B 06051 08b 2-HY-8149C 06052 08b 2-HY-8154 06053 08b 2-HY-8160 11024 19 2-LSH-9020 11025 19 2-LSH-9021 11026 19 2-LSL-9020 11027 19 2-LSL-9021 03012 19 2-LSLL-1852 03013 19 2-LSLL-1853 03014 19 2-LSLL-1854 DESCRIPT RWST TO RHR PUMP B SUCTION MOV SIP COMMON MINIFLOW MOV SIP A MINIFLOW MOV ACCUMULATOR I NITROGEN VENT--SOLENOID OPERATED VALVE ACCUMULATOR 2 NITROGEN VENT--SOLENOID OPERATED VALVE ACCUMULATOR 3 NITROGEN VENT-SOLENOID OPERATED VALVE ACCUMULATOR 4 NITROGEN VENT-SOLENOID OPERATED VALVE ACCUMULATOR 1 NITROGEN VENT-SOLENOID OPERATED VALVE ACCUMULATOR 2 NITROGEN VENT-SOLENOID OPERATED VALVE ACCUMULATOR 3 NITROGEN VENT--SOLENOID OPERATED VALVE ACCUMULATOR 4 NITROGEN VENT-SOLENOID OPERATED VALVE SIP B MINIFLOW MOV I/P CONVERTER FOR HV-0190A I/P CONVERTER FOR HV-0190B I/P CONVERTER FOR HV-0442A I/P CONVERTER FOR HV-0442B I/P CONVERTER FOR HV-0943A I/P CONVERTER FOR HV-0943B SOLENOID VALVE FOR 2-HV-7150 SOLENOID VALVE FOR 2-HV-7699 SOLENOID VALVE FOR 2-HV-8149A SOLENOID VALVE FOR 2-HV-8149B SOLENOID VALVE FOR 2-HV-8149C SOLENOID VALVE FOR 2-HV-8154 SOLENOID VALVE FOR 2-HV-8160 F.O. DAY TANK 3 LEVEL F.O. DAY TANK 4 LEVEL F.O. DAY TANK 3 LEVEL F.O. DAY TANK 4 LEVEL CCW SURGE TK 1 LEVEL CCW SURGE TK 2 LEVEL CCW SURGE TK 1 LEVEL BUILDING ELEV AUX 1191-0" AUX 180'-0" AUX 180'-0" CTB 183'-0" CTS 183'-0" CTB 183'-0" CTB 183'-0" CTB 183'-0'CTB 183'-0" CTB 183'-0" CTB 183'-0" AUX 1801-0" AUX 195'-0" AUX 143'-6" CONTROL 180'-0" CONTROL 180'-0" CONTROL 180'-0" CONTROL 180'-0" FB 1801-0" CTB 183'-0" CTB 183'-0" CTS 183'-0" CT8 183'-0" CTB 183'-0" CTB 183'-0" DG 220'-0" DG 220'-0" DG 220'-0" DG 220'-0" AUX 245'-0" AUX 245'-0" AUX 245'-0" ROOM RD21 RB117 RB119 RB03 RBSO RBIO RB03 RB03 RBIO R810 RB03 RB117 RA98 RC19 RB02 RB10 RB02 R0IO RA01 RB10 RB03 RB03 RB03 RB03 RB03 R102 R104 R102 R104 R227 R226 R227 Page 15 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARK-NO 03015 19 2-LSLL-1855 06033 19 2-LT-0112 06034 19 2-LT-0185 01012 19 2-LT-0459 01013 19 2-LT-0460 01014 19 2-LT-0461 08020 19 2-LT-0501 08021 19 2-LT-0502 08022 19 2-LT-0503 08023 19 2-LT-0504 08024 19 2-LT-0517 08025 19 2-LT-0518 08026 19 2-LT-0519 08027 19 2-LT-0527 08028 19 2-LT-0528 08029 19 2-LT-0529 08030 19 2-LT-0537 08031 19 2-LT-0538 08032 19 2-LT-0539 08033 19 2-LT-0547 08034 19 2-LT-0548 08035 19 2-LT-0549 08064 19 2-LT-0551 08065 19 2-LT-0552 08066 19 2-LT-0553 08067 19 2-LT-0554 05024 19 2-LT-0764 05025 19 2-LT-0765 04026 19 2-LT-0990 04027 19 2-LT-0991 04028 19 2-LT-0992 04029 19 2-LT-0993 DESCRIPT CCW SURGE TK 2 LEVEL VCT LEVEL VCT LEVEL PRESSURIZER LEVEL PRESSURIZER LEVEL PRESSURIZER LEVEL SG 1 WIDE RANGE LEVEL SG 2 WIDE RANGE LEVEL 5G 3 WIDE RANGE LEVEL SG 4 WIDE RANGE LEVEL SG 1 NARROW RANGE LEVEL SG I NARROW RANGE LEVEL SG 1 NARROW RANGE LEVEL SG 2 NARROW RANGE LEVEL SG 2 NARROW RANGE LEVEL SG 2 NARROW RANGE LEVEL SG 3 NARROW RANGE LEVEL SG 3 NARROW RANGE LEVEL SG 3 NARROW RANGE LEVEL SG 4 NARROW RANGE LEVEL SG 4 NARROW RANGE LEVEL SG 4 NARROW RANGE LEVEL SG 1 NARROW RANGE LEVEL SG 2 NARROW RANGE LEVEL SG 3 NARROW RANGE LEVEL SG 4 NARROW RANGE LEVEL CNMT EMERGENCY SUMP LEVEL CNMT EMERGENCY SUMP LEVEL RWST LEVEL RWOT LEVEL RWST LEVEL RWST LEVEL BUILDING ELEV ROOM AUX 245'-0" R226 AUX 1950-0" RA69 AUX 1950-0" RA69 CTB 183'-0" RB02 CTB 183'-0" RB02 CTB 183'-0" RB02 CTB 183'-0" R803 CTB 183'-0" 6810 CTB 183'-0" RBIO CTE 183'-0" RB03 CTB 220'-0" R102 CTB 220'-0" R1OS CTB 220'-0" R101 CTB 220'-0" R101 CTB 220'-0" R101 CTB 220'-0" R101 CTB 220'-0" R101 CTB 220'-0" R101 CTB 220'-0" R101 CTB 220'-0" R101 CTB 220'-0" R101 CT8 220'-0" R101 CTB 220'-0" R101 CTB 220'-0" R101 CTR 220'-0" R101 CTB 220'-0" 6101 CTB 183'-0" RB03 CTB 183'-0" RB03 RWST 220'-0" R101 RWST 220'-0" R101 RWST 220'-0" R101 RWST 220'-0" R101 Page 16 of 36 ATTACHMENT 1: SEISMIC WALKIDOWN EOUPMENT LISTS NO. SNCV061 -RPT-02, VERSION 1.0 LINE NO.09016 06035 06036 06037 06038 14003 14004 14005 14006 08036 08037 08038 08039 01019 01020 01021 01022 08040 08041 08042 08043 08044 08045 08046 08047 08048 08049 08050 08051 CLASS MARKNO 19 2-LT-5111 2-LT-5116 08a 2-LV-0112B 08a 2-LV-0112C 08a 2-LV-01120 08a 2-LV-0112E 19 2-NE-0041 19 2-NE-0042 19 2-NE-0043 19 2-NE-0044 2-PS-8508AR 2-PS-8508BR 00 2-PSV-3001 00 2-PSV-3011 00 2-PSV-3021 00 2-PSV-3031 19 2-PT-0455 19 2-PT-0456 19 2-PT-0457 19 2-PT-0458 19 2-PT-0514R 19 2-PT-O515R 19 2-PT-0516R 19 2-PT-0524R 19 2-PT-0525R 19 2-PT-0526R 19 2-PT-0534R 19 2-PT-0535R 19 2-PT-O536R 19 2-PT-0544R 19 2-PT-0545R 19 2-PT-0546R DESCRIPT CST NO. 1 LEVEL CONDENSATE STORAGE TANK CST LEVEL TRANSMITTER VCT DISCHARGE ISOLATION MOV VCT DISCHARGE ISOLATION MOV CCP SUCTION FROM RWST MOV CCP SUCTION FROM RWST MOV NIS DETECTOR--CH.1 NIS DETECTOR-CH.2 NIS DETECTOR--CH.3 NIS DETECTOR--CH.4 PRESSURE SWITCH PRESSURE SWITCH MAIN STEAM SAFETY RELIEF VALVE MAIN STEAM SAFETY RELIEF VALVE MAIN STEAM SAFETY RELIEF VALVE MAIN STEAM SAFETY RELIEF VALVE PRESSURIZER PRESSURE PRESSURIZER PRESSURE PRESSURIZER PRESSURE PRESSURIZER PRESSURE SG 1 PRESSURE 5G 1 PRESSURE SG 1 PRESSURE SG 2 PRESSURE SG 2 PRESSURE SG 2 PRESSURE SG 3 PRESSURE SG 3 PRESSURE SG 3 PRESSURE SG 4 PRESSURE SG 4 PRESSURE SG 4 PRESSURE BUILDING ELEV CST NO. 1 220'-0" AUX AUX AUX AUX CTB CT8 CTB CTB AUX CONTROL CONTROL AUX CTB CTB CTB CT8 AUX AUX AUX CONTROL CONTROL CONTROL CONTROL CONTROL CONTROL AUX AUX AUX 195'-0" 195'-0" 143'-6" 143'-6" 220'-0" 220'-0" 220'-0" 220'-0" 183'-0" 183'-0" 183'-0" 183'-0" 195'-0" 195'-0" 195'-0" 200'-0" 2001-0" 200'-0" 200'-0" 220'-0" 220'-0" 220'-0" 220'-0" 220'-0" ROOM R103 RA78 RA78 RC1O RC19 R159 R123 R123 R159 RB03 RB02 RB02 RB02 RA103 RA103 RA103 RA04 RAO2 RA04 RA14 RA1O RA14 R155 RIS1 R157 Page 17 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EOUPMENT LISTS NO. SNCVB161-RPT-02, VERSION 1.0 LINE NO. CLASS MARKNO DESCRIPT BUILDING ELEV ROOM 12000 19 2-PT-0934 CNMT PRESSURE FB 2001-0" RA01 12001 19 2-PT-0935 CNMT PRESSURE AUX 180'-0, RR131 12002 19 2-PT-0936 CNMT PRESSURE FB 1801-0" RBOS 08052 19 2-PT-3000 SG 1 PRESSURE TO ARV TRANSMITTER AUX 195'-0" RA103 08053 19 2-PT-30S0 SG 2 PRESSURE TO ARV TRANSMITTER CONTROL 200'-0" RA02 08054 19 2-PT-3020 SG 3 PRESSURE TO ARV TRANSMITTER CONTROL 200'-0" RA1O 08055 19 2-PT-3030 SG 4 PRESSURE TO ARV TRANSMITTER AUX 220'-0" R1S5 01023 08b 2-PV-0455A PRESSURIZER PORV CTR 238'-0" R110 01024 Ob 2-PV-O456A PRESSURIZER PORV CTB 238'-0" R110 10088 08a 2-PV-2550A PPG PEN FILTRATION AND EXHAUST UNIT DISCHARGE DAMPER AUX 245'-0" R219 10089 08a 2-PV-2551A PPG PEN FILTRATION AND EXHAUST UNIT DISCHARGE DAMPER AUX 245'-0" R220 08056 08c 2-PV-3000 ATMOS. RELIEF VALVE--SG 1 AUX 245'-0" R159 08057 08c 2-PV-3010 ATMOS. RELIEF VALVE--SG 2 CONTROL 220'-0" R121 08058 08c 2-PV-3020 ATMOS. RELIEF VALVE--SG 3 CONTROL 220'-0" R122 08059 08c 2-PV-3030 ATMOS. RELIEF VALVE--SG 4 AUX 220'-0" R159 08060 19 2-PY-3000 SG 1 PRESSURE TO ARV CONTROLLER AUX 245'-0" R229 08061 19 2-PY-3010 SG 2 PRESSURE TO ARV CONTROLLER CONTROL 200'-0" RAO6 08062 19 2-PY-3020 SG 3 PRESSURE TO ARV CONTROLLER CONTROL 200'-0" RA06 08063 19 2-PY-3030 SG 4 PRESSURE TO ARV CONTROLLER AUX 245'-0" R229 10106 19 2-TDC-4170 ECW TEMP DIFF CONTROL TO NSCW VLV TV-11740 CONTROL 260'-0" R310 10107 19 2-TDC-4193 ECW TEMP DIFF CONTROL TO NSCW VLV TV-11675 CONTROL 260'-0" R308 01025 19 2-TE-0413A RCS HOT LEG TEMP--LOOP 1 CTR 183'-0" RB02 01026 19 2-TE-0413B RCS COLD LEG TEMP--LOOP 1 CTB 183'-0" RB02 01027 19 2-TE-0423A RCS HOT LEG TEMP--LOOP 2 CTR 183'-0" RB02 01028 19 2-TE-0423B RCS COLD LEG TEMP--LOOP 2 CTB 183'-0" RB02 01029 19 2-TE-0433A RCS HOT LEG TEMP--LOOP 3 CTR 183-01" RB02 01030 19 2-TE-0433R RCS COLD LEG TEMP--LOOP 3 CTR 183'-0" RB02 01031 19 2-TE-0443A RCS HOT LEG TEMP--LOOP 4 CTB 183'-0" RB02 01032 19 2-TE-0443B RCS COLD LEG TEMP--LOOP 4 CTB 183'-0" RB02 02026 19 2-TE-11641 NSCW A RETURN TO FAN 1 CONTROL NSCT 220'-0" R402 02027 19 2-TE-11642 NSCW A RETURN TO FAN 2 CONTROL NSCT 220'-0" R402 02038 19 2-TE-11644 NSCW A RETURN TO FAN 4 CONTROL NSCT 220'-0" R402 Page 18 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCVO61-RPT-02, VERSION 1.0 LINE NO. CLASS MARK-NO 02029 19 2-TE-11646 02030 19 2-TE-11647 02039 19 2-TE-11649 10029 19 2-TE-12124 10030 19 2-TE-12125 10037 19 2-TE-12725 10038 19 2-TE-12740 02032 19 2-TE-1668 02033 19 2-TE-1669 10043 19 2-TIC-13150 10114 19 2-TIS-12005 10115 19 2-TIS-12OO6 10141 19 2-TIS-12300 10142 19 2-TIS-12303 10072 19 2-TISH-12200 10073 19 2-TISH-12201 10074 19 2-TISH-12202 10075 19 2-TISH-12203 10076 19 2-TISH-12204 10077 19 2-TISH-12205 10116 19 2-TISH-22501 10050 19 2-TISH-22505 10051 19 2-TISH-22509 10052 19 2-TISH-22516 10053 19 2-TISH-22519 02034 O8c 2-TV-11675R 02035 08c 2-TV-11740R 10119 07 2-TV-12085 10120 07 2-TV-120B5A 10121 07 2-TV-12086 10122 07 2-TV-12OB6A 10123 07 2-TV-12094A DESCRIPT NSCW B RETURN TO FAN 1 CONTROL NSCW B RETURN TO FAN 2 CONTROL NSCW B RETURN TO FAN 4 CONTROL CB CR RETURN AIR TEMP CB CR RETURN AIR TEMP ELEC EQUIP RM TEMP ELEC EQUIP RM TEMP NSCW A RETURN TO SPRAY/BYPASS VALVES NSCW B RETURN TO SPRAY/BYPASS VALVES CB NORMAL A/C RM ESF A/C UNIT CONTROLLER AFW PUMP B ROOM SUPPLY FAN CONTROLLER AFW PUMP A ROOM SUPPLY FAN CONTROLLER CBCR CHILLER RM VENT FAN CONTROLLER CBCR CHILLER RM VENT FAN CONTROLLER ELECT SWGR & MCC RM A7001 COOLER CONTROLLER ELECT SWGR & MCC RM A7002 COOLER CONTROLLER ELECT SWGR & MCC RM A7003 COOLER CONTROLLER ELECT SWGR & MCC RM A7004 COOLER CONTROLLER ELECT SWGR & MCC RM A7005 COOLER CONTROLLER ELECT SWGR & MCC RM A7006 COOLER CONTROLLER DIESEL POWER CABLE TUNNEL EXH FAN CONTROLLER DIESEL POWER CABLE TUNNEL EXH FAN CONTROLLER TB & AB TRAIN A TUNNEL SUPPLY FAN CONTROLLER NSCW TWR CABLE TUNN TRN A FAN CONTROLLER NSCW TWR CABLE TUNN TRN B FAN CONTROLLER NSCW TO ESSENTIAL CHILLER CONDENSER (E/H) CONTROL VLV NSCW TO ESSENTIAL CHILLER CONDENSER (E/H) CONTROL VLV DG BLDG OUTSIDE AIR DAMPER DG BLDG OUTSIDE AIR DAMPER DG BLDG OUTSIDE AIR DAMPER DG BLDG OUTSIDE AIR DAMPER DG BLDG OUTSIDE AIR DAMPER BUILDING ELEV NSCT 220'-0" NSCT 220'-0" NSCT 220'-0" CONTROL 260'-0" CONTROL 260'-0" CONTROL 180'-0" CONTROL 180'-0" NSCT 220'-0" NSCT 220'-0" CONTROL 260'-0" AFWP HOUSE 220'-0" AFWP HOUSE 220'-0" CONTROL 260'-0" CONTROL 260'-0" AUX 119'-3" AUX 245'-0" AUX 143'-6" AUX 180'-0" AUX 220'-0" AUX 2201-0" TUNNEL 220'-0" TUNNEL 220'-0" CONTROL 180'-0" TUNNEL 220'-0" TUNNEL 220'-0" CONTROL 260'-0" CONTROL 260'-0" DG 220'-0" DG 220'-0" DG 220'-0" DG 220'-0" DG 255'-0" ROOM R302 R302 R302 R311 R305 RB32 RB27 R402 R302 R325 R102 R101 R311 B308 RD104 R223 RCO7 RB122 R149 R147@DG OT4B @ DGO RC08 1T5A @ NSCW iTSB @ NSCW R308 R310 R103 R103 R101 R101 R209 Page 19 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EOUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARKNO DESCRIPT BUILDING ELEV ROOM 10124 07 2-TV-12094B DG BLDG OUTSIDE AIR DAMPER CG 255'-0" R209 10125 07 2-TV-12094C DG BLDG OUTSIDE AIR DAMPER DG 255'-0" R209 10126 07 2-TV-12094D DG BLDG OUTSIDE AIR DAMPER DG 255'-0" R209 10127 07 2-TV-12095A DG BLDG OUTSIDE AIR DAMPER DG 255'-0" R208 10128 07 2-TV-12095B DG BLDG OUTSIDE AIR DAMPER DG 255'-0" R208 10129 07 2-TV-12095C DG BLDG OUTSIDE AIR DAMPER DG 255'-0" R208 10130 07 2-TV-12095D DG BLDG OUTSIDE AIR DAMPER DG 255'-0" R208 10131 07 2-TV-12096 DG BLDG OUTSIDE AIR DAMPER DG 220'-0" R101 10132 07 2-TV-12096A DG BLDG OUTSIDE AIR DAMPER DG 220'-0" R101 10133 07 2-TV-12097 DG BLDG OUTSIDE AIR DAMPER DG 220'-0" R101 10134 07 2-TV-12097A DG BLDG OUTSIDE AIR DAMPER DG 220'-0" R101 10135 07 2-TV-12098 DG BLDG OUTSIDE AIR DAMPER DG 220'-0" R103 10136 07 2-TV-12098A DG BLDG OUTSIDE AIR DAMPER DG 220'-0" R103 10137 07 2-TV-12099 DG BLDG OUTSIDE AIR DAMPER DG 220'-0" R103 10138 07 2-TV-12099A DG BLDG OUTSIDE AIR DAMPER DG 220'-0" R103 10031 08c 2-TV-12124R ECW TEMPERATURE CONTROL VALVE (E/H) CONTROL 260'-0" R311 10032 08c 2-TV-12125R ECW TEMPERATURE CONTROL VALVE (E/H) CONTROL 260'-0" R305 10108 08c 2-TV-12725 ECW TO ESR ELEC EQUIP RM HVAC UNIT CONTROL VALVE CONTROL 180'-0" RB17 10109 08c 2-TV-12740 ECW TO ESF ELEC EQUIP RM HVAC UNIT CONTROL VALVE CONTROL 180'-0" RB16 02040 19 2-TY-11675 CONVERTER FOR TV-11675 CONTROL 260'-0" R30R 02041 19 2-TY-11740 CONVERTER FOR TV-11740 CONTROL 260'-0" R310 10143 19 2-TY-12124A CONVERTER FOR TV-12124 CONTROL 260'-0" R311 10144 19 2-TY-12125A CONVERTER FOR TV-12125 CONTROL 260'-0" R30S 01004 00 2-1201-P6-001 REACTOR COOLANT PUMP NO. 1 CTB 183'-0" RA02 01005 00 2-1201-P6-002 REACTOR COOLANT PUMP NO. 2 CTB 183'-0" RAOS 01006 00 2-1201-P6-003 REACTOR COOLANT PUMP NO. 3 CTB 1830-0" RA05 01007 00 2-1201-P6-004 REACTOR COOLANT PUMP NO. 4 CTB 183'-0" RA02 03006 05 2-1203-P4-005 CCW PUMP NO. 5 AUX 1955-0" RA98 03007 05 2-1203-P4-006 CCW PUMP NO. 6 AUX 195,-0a, RA96 07000 05 2-1206-P6-001 CNTMT SPRAY PUMP A AUX 119'-3" RD05 07001 05 2-1206-P6-002 CNTMT SPRAY PUMP B AUX 119'-3" RD04 06001 24 2-1208-F4-004 SEAL INJ BACKFLUSHABLE FILTER AUX 180'-0" RB151 Page 20 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 LINE NO. CLASS MARK-NO DESCRIPT BUILDING ELEV ROOM 06002 24 2-1208-F4-00S SEAL INJ BACKFLUSHABLE FILTER AUX 1800-0" RB182 06003 05 2-1208-P6-001 POSITIVE DISPLACEMENT CHARGING PUMP (PDP) AUX 143'-6" RC12 AFWP 09000 05 2-1302-P4-001 AFW PUMP C AND TURBINE DRIVER HOUSE 220'-0" R106 10007 09 2-1501-A7-005-000 CTB COOLING UNIT CTB 220'-G" R101 10008 09 2-1501-A7-006-000 CTB COOLING UNIT CTB 220'-0" R101 10009 09 2-1501-A7-007-000 CTB COOLING UNIT CTB 220'-0" R101 10010 09 2-1501-A7-008-000 CTB COOLING UNIT CTB 220'-0" R101 10011 09 2-1511-E7-001-000 CTB REACTOR CAVITY COOLING COIL CTB 1831-0" R1Ol 10012 09 2-1511-E7-002-000 CTB REACTOR CAVITY COOLING COIL CTB 183'-0" RBIO 10013 09 2-1515-A7-001-000 CTB AUX AIR COOLING UNIT (COIL) CTB 238'-0" R301 10014 09 2-1515-A7-002-000 CTB AUX AIR COOLING UNIT (COIL) CTB 238'-0" R302 10015 09 2-1531-07-005-000 CBCR RETURN AIR FAN CONTROL 260'-0" R311 10016 09 2-1531-87-006-000 CBCR RETURN AIR FAN CONTROL 260'-0" R305 10117 09 2-1532-07-003-000 BATTERY RM EXHAUST FAN & MOTOR CONTROL 180'-0" RB26 10118 09 2-1532-$7-004-000 BATTERY RM EXHAUST FAN & MOTOR CONTROL 180'-0" R832 10060 09 2-1555-A7-007-000 RHR PUMP ROOM COOLER A AUX 119'-3" RD112 10061 09 2-1555-A7-008-000 RHR PUMP ROOM COOLER B AUX 119'-3" RDl12 10062 09 2-1555-A7-009-000 CS PUMP ROOM COOLER A AUX 119'-3" RD02 10063 09 2-1555-A7-010-000 CS PUMP ROOM COOLER B AUX 119'-3" RD04 10064 09 2-1555-A7-011-000 CCW PUMP ROOM COOLER A AUX 195'-0" RA98 10065 09 2-1555-A7-012-000 CCW PUMP ROOM COOLER B AUX 195'-0' RA96 10066 09 2-1555-A7-013-000 CVCS CHARGING PUMP ROOM COOLER A AUX 143'-6" RC16 10067 09 2-1555-A7-014-000 CVCS CHARGING PUMP ROOM COOLER B AUX 143'-6" RC17 10068 09 2-1555-A7-015-000 SIS PUMP ROOM COOLER A AUX 1800-0" RB119 10069 09 2-1555-A7-016-000 SIS PUMP ROOM COOLER B AUX 180'-0" RB117 10070 09 2-1555-A7-017-000 SFP HX AND PUMP ROOM COOLER A AUX 195'-0" RA91 10071 09 2-1555-A7-018-000 SFP HX AND PUMP ROOM COOLER B FB 200'-0" RA04 06009 21 2-1208-V4-001 POP SUCTION DAMPENER AUX 143'-6" RC12 Page 21 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 ATTACHMENT 1 SEISMIC WALKDOWN EQUIPMENT LISTS UNIT 2 -SWEL 1 NO. SNCV061-RPT-02 Equipment List Pages Unit 2 -Base List 1 2-21 Unit 2 -SWEL 1 22-30 Unit 2 -Base List 2 31-33 Unit 2 -SWEL 2 34-36 Page 22 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 Plant Vogtle Unit 2 SWEL-1 Plant Vogtle Unit 2 SWEL-2 SWEL Revision Date: October 23, 2012 Originator:

print: 'S -1.. .signature:

-Reviewer:

print: -JAST'O S'. slgna t *Date: Date: p rint -OI.. jV AA-S 6 t -P rt4A-signature:

ý4, Date: 10-a2Z-( 2-Ops Reviewer: Peer Revlewer: print:

signature:

Date: -Peer Reviewer: Peer Reviewer: print: \ 4.h4-Mrt i4. signature:

Date: ______p rint: " we r"..O8C L o si.. Z Date: o / z_Peer Reviewer:

print:.7-4a

-k ..-k signature". " Date: 2-Page 23 of 36 0 0 9 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02.

VERSION 1.0 2 --2 -C1CS-E .SUOCOGFC i yes SCT-O0 =0CB sCOCVICF ICCC-S-E "ICCST'NIP C0 yS EMS ' CSF CSACMCT SC-CCSA. E I ACO1.M 61.CY5 OF 5-- As CSEM/6 2-I~-CEE1 -CSTA. yS AGS 1C4A3 F11 CAUICIAM/RA CS B-OSC-E CUSS yes O L 14CM --C -CGCCS-/TM 2C -117-M-C SAMEBMMSTOAACCBUSS yes Gl CB-- RC COUC-CTC CCC-CIT-S-EM AUGCMRUSGTyes ES FAA 1F CECU-fS CFACSSOUC SBSSFAT SBEUNCSI yes TSC1-A- RS AUSCCAG CSL J-TUF S5-..SCCESMGGSMSCCC N.ES -PCS IM12- 111CCC -=CMBMT CI-CSS-AS PMSC5SBMFUSECEAys

_0MB:7.: CS-, FUS CCSACUCCG BC B-RA-SEM-C ESTSFCSCMOU 21FTTCCSBASGTe e EO 1FA C CSSC-U BC2-CS:O=E CSSBEOAAECICC lyes C- -1SU .50A AC MSCCIS CB-CSSO-L2-1.ASRRA SBG. 1M yes CUSUO 2US- SO SAC- A 33T BIUSe-A ATOCFFAC5S yes lUT1.U- AC SUIE S BC 2-1EM-A VeCSTSTWTC5 yS RC. E1.- .155 AA-CR ST2 6-US CUSC STEMTCS/AC-CET yes USTSCW MTA SC6AC AS-1-CMT-121-CAS DTC ICSFTBS.C 0.CI8 yes 2MBTMLCMA 1R1l UCR-11C2C A2 -7S-ACM RANS-TCC P-SCB2-8 YeS C-SC -0M -AS CC-A S0 CCM-1B CBM PGTEMSGSP-E yes COTTUI 2S- SSM US-CAG-AýSF1 IRA-1-14 111 MS MU CT-ICA yes CA:TTC USI- 50C US--M sM A2- O- 1C DlA GCIVATTOC FUSE U.A~O ET IRA.-A -I5C S-AMC~Jr~FCCBFJSM6UOS.A~FSAOBI

____ SC _________GSMSTTM if CSBASSBSTTSOSSSMEBB.W CMGB,0 5 SEACAT BC OsIss 5BSAW ASSEUS SS.So..C BMSS.SUTSBCeCMSCS)FSSOC.A CAOCSST CEMSCC CSTTFCSST TCSS~STS.S TCFSsM ASMSTFMSBSCOFOTSSS AAMMSCS FCE6FTOSO CSCSSM CMTMS.SCC CEpTI ~C A~L SCOSOASSI

-________ __________________

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Page 24 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 222/.OI TI RR3/ 2 120-22,,14 00 / 02 C RIOTER yes Dw 19S' R 02I012.TIF 6 0 1MP A FLO M F5 0U 112".- 1 201 1 2I 1-212. -yeI ER -0 FLOW -2TL BLD. CLOSi O LTW 1n yes -V1 Ib -12/0-F 4 8 bR P A T/LOW yes A02 119-2 RC1I B120 1 70 7 RI{

RH T OE.0CR10101 0TL50.1 .LOW-R yes 010 01-.0- 2D02 2B20/1-/02 0 1--0 A CP FLOW V0S AU. 010 Rsl9 'u/2 -11717.1-501 2 FLOWTO .O i yes 10 0250 0210 1220212L-

'0100 704-,17 CTElTE200 7000 OCCTO O , 1 yes 20.0010 100 00201101 TI 2-T-O7 MF 71 yes -u1 190'- 01 -1 OR -T-I 5220MINISW0 I yes 200 '"v 2000 112 2110 00240-70 R04T LESATO 100 495EGI M e 000'00 0020811/70 yes 1 0'0 2101 0020 X-I110 7. -S -S'U e yes 2 " .1. XOz~-.O-Rl T T -yes -x -2'7 rs zoes-u~L* T... yes Q. -Bz 71 v.2 R. N e .TO T RCS T yes XS ~ I RD22 TR20'0I.-O

.-E2 TMP T 3D OOELIG yes 1 9. 2'" 011 1 2110.212F 12 2-2-3111TO 1/R URN0rRF yeRONO 0007 R2 1 1R1 112001-ýER 10so.12oo1r

-m yes -..R..Z -1o6-V.O17M Lo 2110-71SO -WOOT02 00 0 yes -0 0922 1 102O 2103-O 2 I0 In1W --R0R 1- OV yes 20 100- 100 02x411700005 224002 0-110231200102 yes 212 000k- 0012O~~3I-T94 01e222 -00 1.0040 yes40-010 000 0219-00502 23 170- 2F201-ROHF 1012-2 I405 000 2110 52 00020-1107Y 20 27F-~ 00 COROJO TO1200000000 40 00 1290 201 02090510000 29-000 ..0...212205 4 01 ORRE0 yes -10000- 170 200 2291119 012-00-10200

~ ~ ~ ~ ~ Ye C0190 0 ~012 0 ONTROL 260-0 200. 0011-00 40-022001 OT IT UNIF I09 4CRO 000 m I9-- 90 02400.20-00000 -011 EA0001 0- UIsE 01112 4es m1220 1V ROT -100OI1100 22 B --5T075 IsCRE11TR911R1 010 499 1901-200 RI 222009 01-0921740-

.OO O R -.- 0022 yRe 00 0-0' 112 0220I00 10.14027-

-1T200F9 0401. .. 0200900420 yes I10 000 3209 U0e2000IlE 1,02 II0 E11121 -I0 2 01001 f 0.210 O-20 V 02J2 0090 f ll2'RR102121 12 R.-20 020020222 290 9.200 321.1 4020 14 .1 -0230 E20.2 Is,2 0 0/210021010032 R.I x sxx A7, s, 21 x ,s v lax o FlO.FILFIZFL7 I I8] s F4 7 N f4 a x x F 1F 1 r 16 N N Page 25 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 c-- -17'B)5 f.s.5175.7 U)1 11 77 7111,C 111-F yes- t,5 517'S 57 --I1 7 Vhss s n777,.75 ,Smlpps3 Ps rl ,p~plo Th as 151 orMII ~nrt 77111 a 1,11. 1317 557, 37Th s~g.e11777..1 17h 1h5e 7117o7n1 a1 D7. of 4n77no in 37ndi51E 4- Rill¢ -DCg11 Io K-e-e -3, i-iio 1.e i ~u I The- _o~on -r t h-e I -h WELE -l d- -o1e -.--l~ IPEFE -d. .n -g5 Page 26 of36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 Table B-I SAFE-Y FUNCTIOrt-SvSTEM IMATRIX FOR PWRs Safnt-, Functiorc, A. Reactivity Cuitrol Frontl I .o Sys tfei That Perfom a Safet' Fict ic, Fl Rezcvto Irlp Systm-Chmrical amd Volumt F2 rnntrdl borWati)0. 10S Prvssure Control F3 Turbine Trip Impwrlant in* kactor Trip ,lSwitch.uar

• Manual Acttation Circuit* fontrol Ski.d Drive Assemblies

• tlinrging Pimps* PA-on lIjecticn TTLks (R[l)* I.zaters; IkaL Tracirrj* Notor-Oprratod Valves for Siction and lrrjectlon Al igrm2nt I Tiwbine Stops Valvas* TUibine C:nLrol Valves* Electric Trip Soleroid Valves* Electric THp Valves s tchdanical Trip Pilot Valves* TuMýa--Ilrlven Foeckator Pwrups (IWluding ttrbline auxi liaries and Stewm surpl y)* tkrr-Urlyan Feeartater Parps* t r.r-CpesraLed Valves for Suction and Injectici Alignisant Sconrensate Storagje Tank F4 M.in Steam Isolation Val ves5 E xxiliary F eedG-,tr F5 .Systen Steam Generator Pcter-F6 Operated Atrwsxseric Rmlief Valves F7 Pressurizer Kmranr-.Opratied Ra ie f Valves C. RCS F8 High Pressure Injection

• llgh Pressure Safety Irdnection control System FtOPS a Rotnr-pinralM Val ves for Swction and IrjeaLion Al iftpsnt e Refuelleig Water Storaqe lank (i.e., 1mrated water)FOUTt This matrix was developed assuming that offisiLe power is unavailable, 0.-8 Page 27 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 Tablu 0-1 (Continued)

SAFETY FUKCTIDN-SYSTEM FOR PWRs fQtw~ZionL...

Fronti inr Systmrs That Purfoym a aL and Vo1Lv, C.ntrol System F9 in lhe !CS vcde}High Pressure F10 RKeculatian Syst.n SLs Prnssure [njacticn System Fli Iemcrtnnt Caeio ents in* thaylrnj PuNps*

Valves for Suction ard Injection Aligrnmt* WTA~9 High Prssure Safety lrdectlon Pops* a"rging Pimps* ttotor-Operate'd Valves for Suction and Injection Algi _nt SSu Recirculation Vales* FIR fpksps* Rif RAPS* Retcsr,-V~ratad Valvesý for Suction ad lfanjton Alignment* RAT*H Pu1 Rps* tloor-Operated Valves for Suction and Injection Alignwiat*Suip Rcirvu1atim VnWrt* See Above* RIR Pimps* F ll Heat [xchan':,ers

• Xoto,-oper-atp Valves fo'r Suction and Injection D. 10S Heat Resval Low Pressure F12 Rerircu~latin System F13 Auxi l tary Stpan Generatar Poje?-F14 OQwratd A'.rmsplieric Relief Valves Pressurizer Pwr-F15 operatod Relief Valves HigN Pre~ssue injec~tion F16 or Recirculation System Residual Heat Raroval F17 Syste 0TE;' This matrix was dovoloped assuming that offsite power is unavailablo, 6-9 Page 28 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 Tabloe 8-: MAJDA COMPIONENTS ir& survTmi SYSlI'I-S 1. Ac S$2. x Peovr 52 3. Engineered Safet.y foeaturos Actuatite S3 4-ky Bus~es.iuse. Ce...raLorS Ciesel Caver-ator Auxilliari

'es, Fuel Ol and Air-Start Systems Frafis for-ers.Autvnzatic Fast Tranfer Switchlgear Fncnjoncy Pcmuar Seqtiencc-r Ctýhi. switchsjear jiontildinq relays au4 breko3rs)(~STraysq ESCV UnTt Substations 4ý!OV all es Motor COF3trol Centers Load Centers Distribution Panels!201Y Instrurrent Sujses Invarters b lses 121W Bizesc fiamlt"resPI¢~~i~

Ltt~e~fltiov-ry Packs Dattery Charswrs'Distribution Panels iC Power Cables (able frays.Grourrd. Qetectivl M (ulEDrint Cab14tip from, Lhe Sensrsýr to ithe Sipiel Processirel itluipetent Aic~iet ion Subsy,,ncsis CebLPnctS (ald ýoiLtd[VAC)11 contral uards Rei ayss Bi stables, treak~ers*31.4 Page 29 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 lable Fj-3 (Coni~tnued)

MV0R COMPONENTS IN SUPPORT SY'STCKS suppn4rt sysi.0m 4. Seevice~ Water and Cmpon~nt Cooling W~ater S4 Systems~Maior Cnmocuwents Horizontal Pum-ps Vertical Pumps rMotnr-Oper'ated Values Air-Operatimd Valves Check Valves Man~ual Valvecs ROWie Valves Piping Heal. Exrhangers Surge I'anks Makeup Pumrps IIVAC SystemTs Iraveling Screen~s anid Scraon Mash Pumps Strainers Intake Bay Cates Coolinvg Towers Cool ing Towor Pumps Cooling Tower Fans Cerp ress ers P ec~eivep a Solenod -Operatad Valves Check Walaea Dryttrs rilters Fans Dampers Chillers and Refrigcmr-Aiwi Uni~tS~Ieaters Ductwork 5. Compressed Air System S5 6. 1IVAC Systems S6[B-15 Page 30 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 ATTACHMENT 1 SEISMIC WALKDOWN EQUIPMENT LISTS UNIT 2 -BASE LIST 2 NO. SNCV061-RPT-02 Equipment List Pages Unit 2 -Base List 1 2-21 Unit 2 -SWEL 1 22-30 Unit 2- Base List 2 31-33 Unit 2 -SWEL 2 34-36 Page 31 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 Vogtle Unit 2 BASE LIST 2 Component ID 21213E6001 21213E6002 212131P6002 21213P6002M01 21213P6005 21213P6005M01 21213U4054 21213U4055 21213U6001 21213U6003 21213U6005 21213U6007 21213U6009 21213U6010 21213U6028 21213U6030 21213U6050 21213U6051 21213U6053 21213U6057 21213LU6058 21213U6064 2HV8754A 2HV8754B Description SPENT FUEL PIT HX A SPENT FUEL PIT HX B SFCPS SPENT FUEL PIT COOLING PUMP A SPENT FUEL PIT PUMP MTR SPENT FUEL PIT COOLING PUMP B SPENT FUEL PIT PUMP MTR SFPCPS RX M/U WATER SUPPLY ISO TO SFP SFPCPS DEMIN WATER SUPPLY ISO TO SFP (20P2-416)SFPCPS SPENT FUEL PIT PUMP A SUCTION SFPCPS SPENT FUEL PIT PUMP B SUCTION SFPCPS SPENT FUEL PIT PUMP A DISCHARGE, SRLV (20P2-300)

SFPCPS SPENT FUEL PIT PUMP B DISCHARGE (201P2-296)

SFPCPS SPENT FUEL PIT HX A OUTLET SFPCPS SPENT FUEL PIT HX B OUTLET SFPCPS SPENT FUEL PIT PUMP A OUTTO DEMIN SFPCPS SPENT FUEL PIT PUMP B OUT TO DEMIN SFPCPS SFP FLTR OUT TO REFUELING CAVITY ORC (201P2-241)

SFPCPS SFP FLTR OUT TO REFUELING CAVITY IRC SFPCPS PURIFICATION LOOP RETURN TO SFP SFPCPS PURIFICATION LOOP RETURN TO SFP SFPCPS PURIFICATION LOOP RETURN TO SFP SFPCPS,PURIFICATION,LOOP RETURN,TO SFP CHECK,*,-,*

SFPCPS SPENT FUEL PIT HX A OUT THROTTLE VLV SFCS SPENT FUEL PIT HX B OUT THROTT-LE VLV Unit 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 Plant System Seismic Category 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 Type HX HX Pump Motor Pump Motor Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Manual Valve Page 32 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 Vogtle Unit 2 BASE LIST 2 Component ID 21213E6001 21213E6002 21213P6002 21213P6002M01 21213P6005 21213P6005M01 21213U4054 21213U4055 21213U6001 21213U6003 21213U6005 21213U6007 21213U6009 21213U6010 21213U6028 21213U6030 21213U6050 21213U6051 21213U6053 21213U6057 21213U6058 21213U6064 2HV8754A 2HV8754B Description Unit SPENT FUEL PIT HX A 2 SPENT FUEL PIT HX B 2 SFCPS SPENT FUEL PIT COOLING PUMP A 2 SPENT FUEL PIT PUMP MTR 2 SPENT FUEL PIT COOLING PUMP B 2 SPENT FUEL PIT PUMP MTR 2 SFPCPS RX M/U WATER SUPPLY ISO TO SFP 2 SFPCPS DEMIN WATER SUPPLY ISO TO SFP (20P2- 2 416)SFPCPS SPENT FUEL PIT PUMP A SUCTION 2 SFPCPS SPENT FUEL PIT PUMP B SUCTION 2 SFPCPS SPENT FUEL PIT PUMP A DISCHARGE, 2 SRLV (20P2-300)

SFPCPS SPENT FUEL PIT PUMP B DISCHARGE 2 (201P2-296)

SFPCPS SPENT FUEL PIT HX A OUTLET 2 SFPCPS SPENT FUEL PIT HX B OUTLET 2 SFPCPS SPENT FUEL PIT PUMP A OUTTO DEMIN 2 SFPCPS SPENT FUEL PIT PUMP B OUTTO DEMIN 2 SFPCPS SFP FLTR OUT TO REFUELING CAVITY ORC 2 (201P2-241)

SFPCPS SFP FLTR OUT TO REFUELING CAVITY IRC 2 SFPCPS PURIFICATION LOOP RETURN TO SFP 2 SFPCPS PURIFICATION LOOP RETURN TO SFP 2 SFPCPS PURIFICATION LOOP RETURN TO SFP 2 SFPCPS,PURIFICATION,LOOP RETURN,TO SFP 2 CHECK,*,*,*

SFPCPS SPENT FUEL PIT HX A OUT THROTTLE VLV 2 SFCS SPENT FUEL PIT HX B OUT THROTTLE VLV 2 Plant System Seismic Category 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 1213 Type 1 HX 1 HX 1 Pump 1 Motor 1 Pump 1 Motor 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve 1 Manual Valve Page 33 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 ATTACHMENT 1 SEISMIC WALKDOWN EQUIPMENT LISTS UNIT 2 -SWEL 2 SNCV061-RPT-02 Equipment List Pages Unit 2 -Base List 1 2-21 Unit 2 -SWEL 1 22-30 Unit 2 -Base List 2 31-33 Unit 2 -SWEL 2 34-36 Page 34 of 36 ATTACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS NO. SNCV061-RPT-02, VERSION 1.0 Plant Vogtle Unit 2 SWEL-1 Plant Vogtle Unit 2 SWEL-2 SWEL Revision Date: October 23, 2012 Originator:

print:S o rL. CL. t .Reviewer:

print: J(S1O .GAcog signature:'

.-s/X- nat-Ops Reviewer: , 14.fl -signature: .._Peer Reviewer.

print: , .a~f,/t signature:

Peer Reviewer:

print: \N/i --signature:".-.

Date: Date: Date; /O,,'-( .Date: /o -2) 'Date: ____ .Date: Peer Reviewer:

print:i?,ga t A-gooew, Peer Reviewer:

print:Z4 kflk. .- signature.

& Date: 2-Page 35 of 36 9 ACHMENT 1: SEISMIC WALKDOWN EQUPMENT LISTS 0 NO. SNCV061-RPT-02, VERSIO4P 0 Vogtle Unit 2 SWEL 2 Spent Fuel Pool Related Items NTTF Recommendation 2.3: Seismic Walkdowns Screen 04 Variety of Major new types of SEISMIC or equipmentAnorechk Room Dr 21ussen Variety of environments required?

Rapid Drain-Down CAT I Drawing replcmnt (21 Casses Walkdown must MPL 0 Description Building Elevation or equpmnt from (50% of Column B) be deferred to Comments Reference (5) Appendix B) outage?Hydraulic lines connected to the SFP Not and the equipment connected to Class # Submerged Submerged Other Yes No those lines 2-1213-E6-002 SFP HX B Yes FHB 195'-0" A04 2X4DB130/C4 I2 X X (4) NO 2-1213-P6-002 SFP PumpA Yes ASS 59S5-0" A9S 21400130/CS 5 0 0 (4) NO 312-.213-U6-001 SFP Pump A suction isolation valve Yes FOB S95S'- A05 254R1530/F4

_ X (0) (4) NO 42HV-8754A SFP A HX outlet isolation valve Yes AUX 195'-0" A91 12X4Dt13/F3 1 0 X (6) (4) NO Notes: 1 The Vogtle SFP System has a very basic system design with very limited componenet types. There is only one active component in each train;the SFP Cooling pump.2 The fuel transfer tube is seismic category I and therfore is considered pa rt of the SFP structure.

Therefore the transfer tube was not included in the SWEL 3 The 5FP weir gates are seismic category 1 and therfore considered to be part of the SFP structure.

Therfore the weir gates will not be inlcuded in the SWEL.4 There are no SFP penetrations below 10ft above the fuel in the SFP. All piping connected to the SFP, either terminate greater than 10ft above the fuel or have anti-siphon holes, located greater than 10 ft above the fuel, to prevent draindown of the SFP.5 There have been no new or replaced SFP system equipment.

6 These components are valves and are not anchored.Page 36 of 36 ATTACHMENT 2: PEER REVIEW CHECKLIST FOR THE SWEL 1 AND 2 NO. SNCV061-RTP-02, VERSION 1.0 ATTACHMENT 2 UNIT 2 -PEER REVIEW CHECKLIST FOR THE SWEL 1 AND 2 NO. SNCV061-RPT-02 Page 1 of 3 ATTACHMENT 2: PEER REVIEW CHECKLIST FOR THE SWEL 1 AND 2 NO. SNCV061-RTP-02, VERSION 1.0 Sheet 1 of 2 Peer Review Checklist for SWEL For Vogtle Unit 2 Instructions for Completing Checklist This peer review checklist may be used to document the review of the Seismic Walkdown Equipment List (SWEL) in accordance with Section 6: Peer Review. The space below each question in this checklist should be used to describe any findings identified during the peer review process and how the SWEL may have changed to address those findings.

Additional space is provided at the end of this checklist for documenting other comments.1. Were the five safety functions adequately represented in the SWEL 1 selection?

YZ NEI SWEL Ifor Vogtle Unit 2 meets the requirements of having 90 to 120 items and addresses allfive safety functions.

Many components provide safetyfunctionsfor multiple systems, and/or are part offrontline support systems. Allfive safety functions discussed in EPRI Report 1025286 are well represented in the SWEL 1.2. Does SWEL I include an appropriate representation of items having the following sample selection attributes:

a. Various types of systems? YN NEI Items included on the SWEL comprise a variety of systems such as Emergency Diesel Generators and Auxiliaries, Service Water System, Component Cooling Water System, Automatic Depressurization, Residual Heat Removal System, Vital A/C and D/C systems.b. Major new and replacement equipment?

YM NEI New and replacement components are identified in SWEL 1.c. Various types of equipment?

YN NEi SWEL I includes at least one example of each of the 21 classes of equipment, except Class 12 (Air Compressors) or Class 13 (Motor Generators).

These components did not meet the screening criteria for incorporation in the SWEL as discussed in Section 6 of the submittal report.All other equipment classes were well represented.

In general, the number of components in each class is proportional to the number of safety-related components of that class in the plant as a whole, except that the number of in-line valves is proportionally smaller than anchored equipment.

Anchored equipment is more vulnerable to seismic loads.d. Various environments?

YN N[]The SWEL contains components in mild, harsh, and outdoor environments.

The components are located in different buildings, rooms, and/or on different building elevations.

The SWEL also includes components located inside primary containment.

e. Equipment enhanced based on the findings of the IPEEE (or equivalent) program? YI NWl The SWEL included equipment that had been modified as a result of the IPEEE program. Section 5 and Attachment 5 of the submittal report provides information on resolution of the IPEEE findings.

The SWEL and individual component checklists provide information about the IPEEE modifications and verification of modification incorporation.

Page 2 of 3 ATTACHMENT 2: PEER REVIEW CHECKLIST FOR THE SWEL 1 AND 2 NO. SNCV061-RTP-02, VERSION 1.0 Sheet 2 of 2 Peer Review Checklist for SWEL For Vogtle Unit 2 f. Were risk insights considered in the development of SWEL 1? YN NFl SWEL I includes high risk components based on risk significance in the plant probabilistic risk assessment (PRA) models. Section 6 of the submittal report discusses the risk insights used for SWEL development.

3. For SWEL 2: a. Were spent fuel pool related items considered, and if applicable included in YZ NEI SWEL 2?SWEL 2 includes components for maintaining cooling of the SFP, which are Seismic Category I components.

b. Was an appropriate justification documented for spent fuel pool related items not YED NEI-included in SWEL 2?Section 6.2 of the submittal report provides the justification for excluding items on SWEL 2. There were no components identified that could contribute to rapid SFP drain down. Note that there were no new/replacement equipment in SWEL 2 because there have been no major modifications to the Spent Fuel Pool systems that would have affected equipment that meets the screening requirements to be included on SWEL 2.4. Provide any other comments related to the peer review of the SWELs.The peer review team reviewed the initial SWEL I and SWEL 2 and provided comments and suggestions for enhancement of the SWELs. Comments included suggestions to include additional electrical components and more equipment mounted to the structure, since such equipment has shown more potential to be adversely impacted by seismic loads than in-line mounted components.

In addition, comments were made suggesting that certain equipment classes contain more components and that explanations be provided for not including certain equipment (e. g. there are no safety-related or Seismic Category I components in that equipment class installed in the plant). The peer reviewers ensured that the SWELs met the requirements of EPRI Report 1025286. Changes deemed necessary during the walkdown due to inaccessibility were reviewed by the peer reviewers to ensure that the changes did not impact the level of compliance to the EPRI report. The final SWEL meets all requirements of EPRI Report 1025286.5. Have all peer review comments been adequately addressed in the final SWEL? YEJ NDI Peer Reviewer #1: Robert Ashworth Peer Reviewer #2: Melanie Brownl/Date: 11/05/2012 Date: 11/05/2012 Page 3 of 3 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 ATTACHMENT 3 UNIT 2 -SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02 PAGE 1 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 1 of 2 Status:I@

N U Seismic Walkdown Checklist (SWC)EquipmentIDNo.

7WZ Sa-A 7-rAi4 Equip. Class 1 2 , (64%5 [)Equipment Description ,VL/tY ",4e. -rg A__N__,__,_-_,, A Location:

Bldg. keX' .FloorEl. IT'o'OQ Room,A4area

/ 2. Manufacturer, Model, Etc. (optional but recommended)

/01r<',0C4ani" 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.Anchoraste

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

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

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

Y 2--N E UD- N/AD1 YO'ND UD N/ADE]Y[NI-] UD N/AED Y, NED UD N/ADJ X 50irl If o 1 -7, if o P 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YIND UD 12 Enter t)e equipmnent class name from Appendix B: Classes of Equipment.

< C-3 >-PAGE 2 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)EquipmentIDNo.

2 -O-P5--7i4i Equip. Class'2 , _k (i' !i-)Equipment Description g(/Lr5 , T,-I -,/xw 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 coUapse 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?Y NO U-] N/AD]YZNE UD N/A[]YO 4 NI-- U-1 N/A]]U]F Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could Y01UE ] U adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: ,S/1 .7 e -/ -Date: _ I__ , __ .U/ I< C--4 >PAGE 3 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 W PAGE 4 of 433 OTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSIO*PAGE 5 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 1 of 2 StatusC) N U Seismic Walkdown Checklist (SWC)Equipment ID No. 2-/2, ./ Equip. Class" Equipment Description d? .d, fv ,/# _Location:

Bldg. f Floor El. -Room, Area ho' 4O3 Manufacturer, Model, Etc. (optional but recommended) 4 eto_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 the anchorage configuration verification required (i.e., is the item one YO] N12 of the 50% of SWEL items requiring such verification)?

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

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

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

Y[9'Nr UEJ NIAEJ YR2"NO UQ N/AO YO 'NO UOE N/AU]YO] NO] tE] N/A&-YIO"NE UOE 2Enter the cquipinent class tiame fromn Appendix 13 Classes of Equripment.

PAGE 6 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)EquipmentIDNo.

Z- (Z -' Equip. Class'2 , (-. f 6 .Equipment Description

/.S6(,61 ?TA4XA, A

/. /Interaction Effccts 7. Are soft targets free from impact by nearby equipment or structures?

8. Are overhead equipment, distribution systems, ceiling tilcs 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?Y[U'ND U- N/AD Y[ZN[1 UD N/AD YFY ND UD N/AD Y60N UD Other Adverse Conditions/

11. Have you looked for and found no other seismic conditions that could Y[ <N ED UE-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated bv: f Ylj,%Ri~1 an 6A Date: i<C-I >-PAGE 7 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS 0 NO. SNCV061-RPT-02, VERSIONPOI PAGE 8 of 433

'ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSIONOO I I/08282012 PAGE 9 of 433 fACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION .0 PAGE 10 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 1 of 2 Status:(Q N U Seismic Walkdown Checklist (SWC)EquipmentlDNo.

7-1Zw3-44-21 Equip. ClassU ... , a. , 1/e1f .Rmfinment Deserintion

/.6G~I H~ ~xc#4,J~i A Location:

Bldg. AQY( FloorEL. 7-1'f--C9"'

Room, Area 4Z z-.7 Manufacturer, Model, Etc. (optional but recommended)

/,d14e6- Qc, -P£,4F,-A r4,, V 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 I. Is the anchorage configuration verification required (i.e., is the item one Yq(N'--D of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than inld 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.)

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

Yký'N El Uli N/AD Y4NEI U0 N/AD YW'NEI Ul N/A[D YK NE UFi N/AD]YV N10 U0 12 Enter the equipment class name from Appendix B: Classes of Equipment.

< C-3 >-PAGE 11 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)EquipmentlDNo.

.-/Oz33-9q-9&f Equip. Class" 2-,rL.s .. h aoo.e/. (6 1!u Zd)

/~C(A/ /~A7 F i 1~4AJ4De-; -e-t D-cri tion 6 C W Hr-A 7- CX,ý A4AJ1-Ze 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 attacheo lines have adequate flexibility to avoid damage?7t r I'P,0 7 ofl( ,c,,f O L/E1 e.10. Based.on the above seismic interaction evaluations, is equipment free of'potentially adverse seismic interaction effects?YW NO UV- N/A"-YVNr UrI N/All YO- NO U-- N/Akl Ypq NEI U-Other Adverse Conditions I. 1. Have you looked for and found no other seismic conditions that could YAN- U-adversely affect the safety functions of the equipment?

Comments (Additional pages may bc added as necessary)

Evaluated by: *WW -M~ Wilkinson Date:-< C-4 >PAGE 12 of 433 9 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION .0 PAGE 13 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 PAGE 14 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 bheet 1 of 2 Status: (D N U Seismic Walkdown Checklist (SWC)Equipment ID No. J- 1203 -p' "-o0a Equip.Clas 12 PAmp)I e Equipment Description CcO W Pm No Location:

Bldg. _ ... Floor El. Iq"-' Room, Area AA q Manufacturer, Model, Etc. (optional but reconunended) 4 A 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 ofjudgments and findings.

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

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

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

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

Y. NEI U[E N/AE YX NEI UfE N/A[E Y NE UE N/AE YE NEI U NIAX'Y&'N UEJ 12 Enter the equipment class name from Appendix B: Classes of Equipment< C-3 >" PAGE 15 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)Equipment ID No. 1--1n3- P+-001 Equip. Class' 5( flunM % 5)Equipment Description C:A4 Ptm 1 No1./Interaction Effects 7. Axe 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 interactionevaluations, is equipment free of potentially adverse seismic interaction effects?Yk NO2 UD N/AEJ Y4NOl UQ N/AUJ YKfNO UQ N/A-UFJ Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y)(N- U-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

F-0 F, 4orh VW-'¶ 0 w~roST, SffE 2-I+'-Qr0140 Evaluated by.: i 4'!s~Date: /26L< C-4 >PAGE 16 of 433 97ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION .0 PAGE 17 of 433 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSIONPO PAGE 18 of 433 NO. SNCV061-RPT-02, VERSION 1.0 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS Sheet I of 2 Status:0 N U Seismic Walkdown Checklist (SWC)Equipment IDNo. :2-2-03-T4-001 Equip. Class t 2 2"1(Th 1 5 , -Equipment Description

(.(,W Location:

Bldg. AVY, Floor El. 4'5' Room, Area 2-27 Manufacturer, Model, Etc. (optional but recommended)

Q 1R d ,, fef ..Insteuctians 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 ofjudgments and findings.

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

Y9.qNO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

Y6 NO U- N/AC1 YgO (: N/AC1 Yg NO U] N/A[]Y4NO UOi N/A-YX/NO UOEnter (he equipment class name from Appendix B: Classes 3f Equipment.

< C.3 >-PAGE 19 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)EquipmentlDNo.

7Z0.o -"1Ft O-Ot Equip. Class"' "(,,s ,- [ie.4 ,,.p -&a-/e Z1 1/Equipment Description Ef We ctsic&& 1-2wk Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

YfNI-1 UL N/A-1 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, UFI N/A0 and masonry block walls not likely to collapse onto the equipment?

'N 9. Do attached lines have adequate flexibility to avoid damage?Pl/p!,VU C,0-..o ,"/eTj,0jA15 Of!ý e $! !10. Based on the above seismic interaction evaluations, is equipment free of.potentially adverse seismic interaction effects?YO EJI UE YYXNEU11u N/AA Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YX N[l UI-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Eval uated by: e44v( 1V/01 ~2O S /VDate: t.?V ZO/ z< C-4 >PAGE 20 of 433 9 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSIOONO PAGE 21 of 433

• ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS 0 NO. SNCV061-RPT-02, VERSION 1.0 PAGE 22 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 1 of 2 Status&. N U Seismic Walkdown Checklist (SWC)Equipment ID No. Z/-12&q-9-00 Equip. Class 1 2/ P-1.1py -e /-Sr 57-Eouinment Descriotion f5 441-,0 A Location:

Bldg. *1, .Floor El. /Wo¢ ,c ' Room, Area A.. 6( Ic.Manufacturer, Model, Etc. (optional but recommended)

PYWA f 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 ofjudgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchoragze

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

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

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

A,X20,o3Aao.ZJ.

PeR. 2-o 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YK N YX NEI UD N/AD ,1 NEI U1 N/AO Y' NEI UO N/AD Y' NO U-- N/AD YX NO 1f-2 Enter the equipment class name from Appendix B: Classes of Equipment.

< C-3 >PAGE 23 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)Equipment ID No. .-/. -On.5 Equip. Class 1 2-, A,.-.?C41./; 1 (-c 1 $ .5-<,r pump A V~lAAUfA L.JUnLL; ';J quipmen escr p --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?Yg NO U- N/AC YA NO UC N/AO YP NO UC N/Ar Y NO UC Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YX NEI U-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

NtOAi e Evaluated by: I/ Y4V ,, 1=A44V/D 0P~A o09Rrq / Pao */k Date:< C-4 >-PAGE 24 of 433 O ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061 -RPT-02, VERSION P PAGE 25 of 433

• t ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS 0 NO. SNCV061-RPT-02, VERSIO.NI PAGE 26 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet I of 2 Starus:(Q N U Seismic Walkdown Checklist (SWC)EquipmentIDNo.

Equip. Class" Equipment Description ke.-u i,. l, ,,-pej,_ _ ,- .f -., -Location:

Bldg. (R -4S- FloorEl. Room, Area YutiM*. 0 1P Manufacturer, Model, Etc. (optional but recommended)..

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.Anchorace 1. Is the anchorage configuration verification required (i.e., is the item one YD N41 of the 50% of SWEL items requiring such verification)?

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

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

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

YR-N-- UD NIAD YE-NE] UO N/AD YRE-ND U N/AD YO ND UD N/Ar,/Y[<'NO UD 12 Enter the equipment class name from Appendix B: Classei of Equipmenr< C-3 >.PAGE 27 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)Equipment IDNo. 1-1204-a/.--o4 Equip. Class" 1 2-1 Equipment Description .L4,..4 h ' ..Interaction Effect 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?Yi/Ni-- UC N/Afl Yf'N-I UL- N/AEJ Y[A/ND UQI N/ACl Other Adverse Conditions

11. [lave you looked for and found no other seismic conditions that could YUZ/ND ur-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

VJ& j Teý-tc a- ý t~A~ CL 4L-*a- t Evaluated by: tA LY/3 PASIAtl-~

&~~Date: 'ij< C-4>PAGE 28 of 433 O ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSIOVO r'-1 PAGE 29 of 433 9 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSIONOO 08 152012 PAGE 30 of 433 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS 0 NO. SNCV061-RPT-02, VERSION 9.I$ffi I I I I PAGE 31 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 1 of 2 Status: N U Seismic Walkdown Checklist (SWC)EquipmentlDNo.

Zt -"o( Equip. Class" 2-,ak ,, -" Z(...Equipment Description st' " Hr.4 f cgA-vAF ,4 Location:

Bldg. A'A X. Floor El. lq3i-46 Room, Area Xe6 1- 5 Manufacturer, Model, Etc. (optional but recommended)

7!'as.f,.4" ,eA ,.S'., 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 the anchorage configuration verification required (i.e., is the item one Y2</N[]of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configaration 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.)

YDl9UE N/AEI YDU160 UN/A[/YL-UE UE1 N/A[E YD u£ UCN/A[]O~QlNA~$§zX 6XF-P- 4x p ,z Zyý2-!, ' A' f- /1ZPH 07--f~YeDU0 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

12 Enter the equipment class name from Appendix 13: Classes ofEquipment.

<(C-3 >-PAGE 32 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)Equipment ID No. 2-f-/Zor'- -d / Equip. Class 1 2 ,.., I j:c, ,.s -AF(, 2/Equipment Description 9t ItCA' "C -- -Exc t'-+A-.ln

,4-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?YO NEl UE N/AE3 YfJ-*fr Uf- N/ADl/" YB-5l UO N/AD Y ZNEIU Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Ya<l UIJ adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

I>'Evaluated by: IV -An Date:/<C4>PAGE 33 of 433 A ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO, SNCV061-RPT-02, VERSION 1.0 PAGE 34 of 433 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSIONOO PAGE 35 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 1 of 2 Statufs: N U Seismic Walkdown Checklist (SWC)EquipmentID No. Z-1 Equip. Class'2________ p -EquipmentDescription

&m s2 P A Location:

Bldg. Au' Floor El. _.2 J -3' Room, Area 9Oz- z Manufacturer, Model, Etc. (optional but recommended)

I', eero //- iR d Instructions for Completing Checklist This checklist.may be used to. document the results of the Seismic Walkdown of an item of equipment on the SWFL. The space below each of the following questions may be used to record the results ofjudgments and findings.

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

2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than rmild 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.)

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

Y[/ND UD] N/AED Y EN U-1 N/ADE YDI ND UOi N/A[/YS/ND UD 2 Enter the equipment class name frontAppendix B: Classes of Equipment.

< C-3 >PAGE 36 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)EquipmentlDNo.

1z"'T-P6'ot0 Equip. Class'. Werlco- .F. 5 -_-5,sJ Equipment Description

-/,-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 ayoid damage?10. Based on theabove seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YM/NO UO N/AD Yf'NDN UVD N/AD Y ND U0J N/AD Yif<D UD Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could Y/ND UD.adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Aio, Evaluated by: Dae ji L.Date: 1P---< C-4 )" PAGE 37 of 433 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION*PAGE 38 of 433 3 ATTACHMENT 3: SEISMIC WALKIDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION .0 PAGE 39 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet I of 2 Status:9 N U Seismic Walkdown Checklist (SWC)EquipmentlDNo.

2-(tZ fPO9-oZ Equip. Class' [2Nor.' ,Wlv , /C(4, 5 Equipment Description 6 t'C E,'i T .

Pi,-,P -"7ý"4. -Location:

Bldg. ,AUt Y Floor El. Ir3'- 6"" Room, Area I , Manufacturer, Model, Etc. (optional but recommended)

[9c,',c PcA,, __,_Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWELI.. The space below each of the following questions may be used to record the results ofjudgments and findings.

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

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

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

,4 o ,94VoO0 YVE P, 2.0O XX Z-O 94 V'~o '7Y V 6-f-, 1 ' .O 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seisimnic conditions?

Y"Z NO UEH N/A[:]Y$ NEI UE N/A/c YKNO UO] N/AO YW NEI UL N/AL YK NE UD"~Enter the eqaiiimcnt class name from Appendix B: Classes of.Equipmcnt.

< C-3 >~PAGE 40 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)EquipmentlD No. Equip. Class;Equipment Description

._ec/CS , <H4/,.2sk.

VIC- 7'A1-'A) t_-Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Yy ND UD N/AD 8. Are overhead equipment, distribution systems, ceilingtiles and lighting, Yy NDI UE3 N/AD and masonry block walls not likely t.o 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?NDI UI N/AD NI NDU Other Adverse Conditions 11, Have you looked for and found no other seismic conditions that could YP(N[] UL[adversely affect the safety finctions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluatedby:

Date: e13-120/a ma W-^'0Vj ýji'ikifl So rj S/3Y2IJ(L<C-4>PAGE 41 of 433

• ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSIONOO PAGE 42 of 433 9 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION*PAGE 43 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 1 of 2 Status:cf N u Seismic Walkdown Checklist (SWC)EquipmentlD No, 2-LtV 1 "15" Equip.Class" 0 Equipment Description ft AJ .5L r`a VieV?. wr,\ Location:

Bldg. ____X Floor El. J43.'-IV'l Room, Area RC[1 Manufacturer, Model, Etc. (optional but recommended)

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

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

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

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

yxNEo UOI NIA2V-UEI N/AO Y U[ N/AQ YO NOl U[l N/Aal yN UN/A-11u/2Enter the equipment class name from Appendix B: Classes of Equipment.

< C-3 >PAGE 44 of 433 ATTACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION 1.0 Sheet 2 of 2 Seismic Walkdown Checklist (SWC)Equipment ID No. " 1 U " fS I Equip. Class 5 2_0.Equipment Description 5OU l 3 ( 6 ns 4 ydt/bl WAjL]( 46A /Ao"d 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?Y NE UO N/AO Y Q1< UQ N/A[YE<IUEI N/ALI Y eNýOU Other Adverse Conditions

/1 11. Have you looked for and found no other seismic conditions that could Y2--N UE adversely affect the safety functidns of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: -, .5 ,?,eL-0Ct Date: t/'7!<4C- >-PAGE 45 of 433

• ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSION .0 PAGE 46 of 433

• ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERS1000 PAGE 47 of 433 ACHMENT 3: SEISMIC WALKDOWN CHECKLISTS NO. SNCV061-RPT-02, VERSIONOO PAGE 48 of 433 A ATTACHMENT 3: SEISMIC WALKIDOWN CHECKLISTS 0 NO. SNCV061-RPT-02, VERSION 1.0 PAGE 49 of 433