ML12362A050

Engineering Report VY-RPT-12-00019, Vermont Yankee Seismic Walkdown Submitted Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page 204 of 505

ML12362A050
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Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	11/20/2012
From:	Abramovici J Enercon Services
To:	Office of Nuclear Reactor Regulation, Entergy Nuclear Operations
References
BVY 12-080 VY-RPT-12-00019
Download: ML12362A050 (259)

Text

ATTACHMENT 2 BVY 12-080 VERMONT YANKEE SEISMIC WALKDOWN SUBMITTAL REPORT

Report Number VY-RPT-12-00019 Rev 0 Page 1 of 28 ENTERGY NUCLEAR

• Envztery Engineering Report Cover Sheet Engineering Report

Title:

VERMONT YANKEE Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic Engineering Report Type:

New 0 Revision 5] Cancelled EJ Superseded 51 Superseded by:

Applicable Site(s)

IPI 0 IP2 0 IP3 0 JAF 0 PNPS 0 vy 0 wpo El ANOI E] ANO2 " ECH [3 GGNS El RBS 0 WF3 0 PLP []

EC No. 40647 Report Origin: 5l Entergy 0 Vendor Vendor Document No.: N/A Quality-Related: 0[ Yes P [D No Prepared by: Julien Abramoac, P.E. (ENERCONT I /A*i '- E)ate: //-2"',LZ Reviewed by: Jeffrey Horton P.E (ENERCON) / Q Date: _____

u Other Reviewed by: Juan Vizcaya (ENERCON) / Date: _______

Peer RW:iewer Reviewed by: Steven M Buckley Date: /1-20-ZiZ Approved by: ScttrviDoroManger Date: iO~j SuprV Isor-/ Maaer

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 2 of 28 TABLE OF CONTENTS Section Description Page 1.0 SCO PE AND OBJECTIVE .................................................................................................... 3 2.0 SEISMIC LICENSING BASIS

SUMMARY

............................................................................. 4 2.1 Safe Shutdown Earthquake ................................................................................................. 4 2.2 Design Codes, Standards and M ethods ............................................................................... 5 3.0 SEISMIC WALKDOWN PROGRAM IMPLEMENTATION APPROACH .......................... 6 4.0 PERSONNEL QUALIFICATIONS .......................................................................................... 6 4.1 Equipment Selection Personnel .......................................................................................... 10 4.2 Seismic Walkdown Engineers ............................................................................................. 10 4.3 Licensing Basis Review ers ................................................................................................ 10 4.4 IPEEE Review ers .................................................................................................................. 10 4.5 Peer Review Team ................................................................................................................ 10 5.0 IPEEE VULNERABILITIES REPORTING ........................................................................... 12 6.0 SEISMIC WALKDOWN EQUIPMENT LIST DEVELOPMENT ............................................ 12 6.1 Base List ............................................................................................................................... 13 6.2 SWEL I ................................................................................................................................ 14 6.3 Spent Fuel Pool Item s ............................................................................................................ 16 6.4 Deferred, Inaccessible Items on SW EL ............................................................................. 17 7.0 SEISMIC WALKDOWNS AND AREA WALK-BYS ................................................................. 18 7.1 Seism ic W alkdowns .............................................................................................................. 18 8.0 LICENSING BASIS EVALUATIONS ................................................................................... 20 8.1 Licensing Basis Evaluations .............................................................................................. 20 8.2 Corrective Action Program Entries ................................................................................... 21 8.3 Plant Changes ........................................................................................................................ 22 9.0 PEER RE VIEW ............................................................................................................................ 22 9.1 Peer Review Process .............................................................................................................. 22 9.2 Peer Review Results Sum mary .......................................................................................... 23 10.0 RE FEREN CES ............................................................................................................................. 28 11.0 A TTACHME NTS ......................................................................................................................... 28

Engineering Report No. VY-RPT-12-00019 Rev. 0 Page 3 of 28 1.0 SCOPE AND OBJECTIVE The Great Tohoku Earthquake of March 11, 2011 and the resulting tsunami caused an accident at the Fukushima Dai-ichi nuclear power plant in Japan' In response to this accident, the Nuclear Regulatory Commission (NRC) established the Near-Term Task Force (NTTF), tasked with conducting a systematic and methodical review of NRC processes and regulations and determining if the agency should make additional improvements to its regulatory system. On March 12, 2012 the NRC issued a 10CFR50.54(f) letter (Ref. 10.1) requesting information from all licensees to support the NRC staff's evaluation of several of the NTTF recommendations. To support NTTF 2.3, Enclosure 3 to the 50.54(f) letter requested that all licensees perform seismic walkdowns to gather and report information from the plant related to degraded, non-conforming, or unanalyzed conditions with respect to its current seismic licensing basis.

The Electric Power Research Institute (EPRI), with support and direction from the Nuclear Energy Institute (NEI), published industry guidance for conducting and documenting the seismic walkdowns which represented the results of extensive interaction between NRC, NEI, and other stakeholders. This industry guidance document, EPRI Report 1025286 (Ref. 10.2), hereafter referred to as "the Guidance,"

was formally endorsed by the NRC on May 31, 2012. Entergy Vermont Yankee Nuclear Power Station (VYNPS) has committed to using this NRC-endorsed guidance as the basis for conducting and documenting seismic walkdowns for resolution of NTTF Recommendation 2.3: Seismic.

The objective of this report is to document the results of the seismic walkdown effort undertaken for resolution of the Fukushima Near Term Task Force (NTTF) Recommendation 2.3, Seismic.

This report summarizes the basis, planning, preparation, execution and findings of the seismic walkdowns and constitutes the "Submittal Report" as described in Section 8 of the Guidance dated June 2012. The objective of the walkdown effort was to provide responses to the 10 CFR 50.54(f) letter issued by the NRC on 3/12/12 (Ref. 10.1). This included walkdowns of a sample of components and walk-bys of associated areas of the plant to identify potentially adverse seismic conditions within the parameters provided in EPRI Report 1025286 (Ref. 10.2). Adverse seismic conditions included those that could, due to a seismic event:

• interfere with/prevent the proper functioning of the subject component

" create the possibility of flood of the subject area

" potentially cause spray on equipment

" potentially cause/enable fires in the subject area and

• cause unanticipated, rapid drain down of the spent fuel pool(s)

A sample population of components for inspection was developed as discussed in Section 6.0. This component sample constituted the Seismic Walkdown Equipment List (SWEL) which satisfies the requirements for sampling as outlined in EPRI Report 1025286.

Using the SWEL, walkdown teams consisting of two Seismic Walkdown Engineers (SWEs) per team walked down the subject components. Results of the walkdowns were recorded on Seismic Walkdown Checklists (SWCs). All accessible items on the SWEL were walked down. Inaccessible items are listed in Section 6.4 and will be walked down when the specific equipment or area is operationally accessible. In addition, an area walk-by (AWB) was performed for each room/area of the plant containing a component listed in the SWEL. Results of the area walk-bys were recorded on Area Walk-by Checklists (AWCs).

Engineering Report No. VY-RPT- 12-00019 Rev. 0 f Page 4 of 28 Area Walk-bys supplemented the seismic walkdowns and provided for inspections of general areas in the vicinities of the subject equipment. This eliminated tunnel-vision and allowed a vehicle to report other potentially adverse conditions. In cases where multiple SWEL items were located in the same room/area of the plant, a single AWB was conducted. Plant rooms/areas were generally found to be sufficiently compact to allow for robust AWBs under these conditions. In the cases where a component was located in a very large area/room, the walk-by was limited to an area with a radius of approximately 35 feet around the component on the SWEL. The limits of the walk-by for these cases are defined on the Area Walk-by Checklist.

The intent of the walkdowns/walk-bys was to identify potentially adverse seismic conditions with a focus on anchorage and seismic spatial interactions. Potentially adverse seismic conditions were noted on the SWCs and AWCs, and were ultimately entered into the plant's Corrective Action Program (CAP) for documentation, evaluation and resolution.

Results of the component walkdowns and area walk-bys are discussed and summarized in Section 7.0.

Copies of the walkdown and walk-by checklists are provided in Attachments C and D.

Section 8.0 contains a discussion of potentially adverse seismic conditions identified during the field inspections. A list of potentially adverse seismic conditions is provided in Attachment E.

Licensing basis evaluations (LBEs) were performed as part of the resolution of the CRs that were initiated to document potentially adverse seismic conditions. The results of the LBEs are discussed in Section 8.0 and additional information is provided in Attachment F.

2.0 SEISMIC LICENSING BASIS

SUMMARY

Vermont Yankee Nuclear Power Station (VYNPS) is a boiling water reactor (BWR) located in Vernon, Vermont. The Nuclear Steam Supply System (NSSS) was originally designed by GE and VYNPS began commercial operation in November of 1972, and is currently rated at 1912 MWt power. This section summarizes the seismic licensing basis of structures, systems and components (SSCs) at VYNPS which bound the context of the NTTF 2.3 Seismic Walkdown program.

2.1 Safe Shutdown Earthquake In accordance with Draft Criterion 2, "Design Bases for Protection Against Natural Phenomena", of 10 CFR 50, Appendix A, structures, systems, and components important to safety are designed to withstand the effects of natural phenomena such as earthquakes without loss of the capability to perform those safety functions necessary to cope with appropriate margin to account for uncertainties in the historical data. Appendix C of the original Final Safety Analysis Report (FSAR) documents that the plant satisfies the earthquake principal design criteria described in draft AEC Criterion 2.

The Safe Shutdown Earthquake (SSE) for VYNPS is based on a recurrence of the largest historical earthquake in the region applied at the closest known location of faulting. It is specifically characterized by a Housner spectral shape anchored at 0. 14g (SSE) peak horizontal ground acceleration with vertical accelerations equal to 2/3 of the horizontal ground acceleration (Ref. 10. 14).

The damping factors used in the dynamic seismic analysis are given in the Updated Final Safety Analysis Report (UFSAR).

Engineering Report No. VY-RPT-12-00019 Rev. 0 Page 5 of 28 Additionally, the UFSAR Section 1.6.1.1.7 states:

"Based on a three-fold seismic evaluation, the site was found to be relatively quiescent from a seismic standpoint. From these studies the design earthquake has been established at 0.07g horizontal ground acceleration and the maximum hypothetical earthquake at 0.14g horizontal ground acceleration. The seismic evaluation consisted of a review of historical data from the New England area, an analysis of instrument and historical records for the Vermont area, and a study of earthquake intensity attenuation with distance for the northeast United States."

2.2 Design Codes, Standards and Methods Seismic Input to Structures and Equipment:

VYNPS was designed to withstand the effects of seismic events applicable to Class I systems.

The Updated Final Safety Analysis Report (UFSAR) (Ref. 10.14) describes Class I SSCs as those structures, equipment, and components whose failure or malfunction might cause or increase the severity of an accident which would endanger the public health and safety. This category includes those structures, equipment, and components required for safe shutdown and isolation of the reactor. Both the vertical and either of the responses- of the two horizontal seismic motions are considered to be applied simultaneously and in combination with all other applicable design loads. The larger combination controls the design.

Structures, Equipment and Components:,

Seismic Class I structures applicable to the scope of the NTTF 2.3 Seismic Walkdown Program include the Reactor Building, Control Building, Intake Structure and Emergency Diesel Generator Rooms including day tank enclosures located in the Turbine Building. Seismic design of Class I SSCs is in accordance with Section 12.2 of the UFSAR and Topical Design Basis Document for External Events (Ref 10.15).

Class I equipment analysis considers vertical and horizontal ground motions. The horizontal motion accounts for the equipment elevation above grade and also considers the stiffness of equipment supports. Appendix C to the UFSAR provides the Seismic Class I criteria for equipment and piping design. Appendix A to the UFSAR provides the description, scope and design methodologies for Class I piping systems.

Methodology based on earthquake experience data developed by the Seismic Qualification Utility Group (SQUG) and documented in the Generic Implementation Procedure (GIP),

Revision 2, plus any addition to the GIP reviewed and accepted by the NRC for resolving Unresolved Safety Issue (USI) A-46 in response to NRC Generic Letter 87-02, was used to verify the seismic adequacy of equipment included within the scope USI A-46.

An extensive list of design codes, standards, methods, studies and tests utilized for seismic design is provided in the VYNPS UFSAR. A summary of the more relevant references for the design of Seismic Category I structures, systems and components is provided here.

2.2.1 ASME Boiler and Pressure Vessel Code, various sections 2.2.2 American Concrete Institute (ACI) Building Code Requirements for Reinforced Concrete

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 6 of 28 2.2.3 American Welding Society (AWS) Standard Code for Arc and Gas Welding in Building Construction 2.2.4 American Institute of Steel Construction (AISC) Specification for the Design, Fabrication, and Erection of Structural Steel for Buildings 2.2.5 Uniform Building Code (UBC) 3.0 SEISMIC WALKDOWN PROGRAM IMPLEMENTATION APPROACH Entergy VYNPS has committed to conduct and document seismic walkdowns for resolution of NTTF Recommendation 2.3: Seismic in accordance with the EPRI Seismic Walkdown Guidance (Ref. 10.2).

Entergy developed procedure EN-DC-168, "Fukushima Near-Term Task Force Recommendation 2.3 Seismic Walk-down Procedure" (Ref. 10.13), outlining the guidelines, processes and required documentation generated during the walkdowns. The approach provided in the guidance for addressing the actions and information requested in Enclosure 3 to the 50.54(f) letter includes the following activities, the results of which are presented in the sections shown in parenthesis:

• Assignment of appropriately qualified personnel (Section 4.0)

• Reporting of actions taken to reduce or eliminate the seismic vulnerabilities identified by the Individual Plant Examination of External Events (IPEEE) program (Section 5.0)

" Selection of structures, systems and components (SSCs) to be evaluated (Section 6.0)

" Performance of the seismic walkdowns and area walk-bys (Section 7.0)

• Evaluation and treatment of potentially adverse seismic conditions with respect to the seismic licensing basis of the plant (Section 8.0)

" Performance of peer reviews (Section 9.0)

The coordination and conduct of these activities was initiated and tracked by Entergy corporate leadership, which provided guidance to each Entergy site throughout the seismic walkdown program, including VYNPS. Entergy contracted with an outside nuclear services company to provide engineering and project management resources to supplement and assist each individual site. VYNPS had dedicated engineering contractors, supported by their own project management and technical oversight, who worked closely with plant personnel.

4.0 PERSONNEL QUALIFICATIONS The NTTF 2.3 Seismic Walkdown Program involved the participation of numerous personnel with various responsibilities. This section identifies -the project team members and their project responsibilities, and provides brief experience summaries for each person. Training certificates of those qualified as Seismic Walkdown Engineers are included in Attachment H.

The following table summarizes the names and responsibilities of personnel used to conduct the seismic walkdowns. Experience summaries of each person follow.

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 7 of 28 Table 4-1 Equipment Seismic Licensing IPEEE Name Selection Walkdown Basis Personnel Engineer Reviewer Steven Buckley (Vermont Yankee) x2 X X Mark Palionis (Vermont Yankee) X X Ed Harms (Vermont Yankee) X1 Scott Goodwin (Vermont Yankee) X Marcus Hecht-Nielsen (ENERCON/ARES) X Randall Stephens (ENERCON/ARES) X Raymond Tworek (ENERCON/ARES) X Kirit Parikh (ENERCON) X Michael Rose (Vermont Yankee) X David Grimes (Vermont Yankee) X Notes:

2. Plant Operations representative

2. Designated lead SWE Mr. Steven Buckley Mr. Buckley is a Professional Engineer (Structural) with over 25 years of seismic design experience in the nuclear power industry. He holds a Bachelor of Science degree in Civil/Structural Engineering from the University of Massachusetts (Lowell MA). Mr. Buckley has completed the "SQUG Walkdown Screening and Seismic Evaluation" training course. He was part of a two man team that performed all the walkdowns required by the USI-A46 and Seismic IPEEE programs at Vermont Yankee Nuclear Power Station.

Mr. Buckley is currently a Senior Civil/Structural/Mechanical Design Engineer for Vermont Yankee, serving as the Lead Engineer for the response to Fukushima-related seismic issues. His primary duties at Vermont Yankee include technical oversight of contracted design projects and serving as lead design engineer for civil/structural/mechanical projects developed in-house. He has performed design related work for Vermont Yankee Nuclear Power Station for more than 20 years.

He provided technical oversight and direction to the SWE teams during performance of the Seismic walkdowns and was the lead engineer responsible for addressing issues documented in the Correct Action Program.

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 8 of 28 Mr. Mark Palionis Mr. Palionis is an engineer with over 30 years of experience in the nuclear power industry. He holds a Bachelor of Science degree in Mechanical Engineering from the Polytechnic Institute of Brooklyn, as well as holding Senior Reactor Operator & Shift Technical Advisor Certifications.

Currently, Mr. Palionis is working as a Senior Engineer at Vermont Yankee Nuclear Power Station (Entergy), serving as the Lead Probabilistic Safety Analysis (PSA) Engineer for Vermont Yankee. His primary duties include maintenance and update of the Vermont Yankee PRA model, providing risk assessments as required in support of licensing initiatives (e.g., Tech Spec amendments for changes in system AOT, Operating License changes, etc.), in support of the NRC reactor oversight process (e.g.,

SDP - Significance Determination Process), and in support of risk-based engineering programs (i.e.,

ISI, IST, MOV/AOV programs, etc.).

Prior to transitioning to the PSA Engineering Group, Mr. Palionis worked in both the Vermont Yankee System Engineering Department and in the Operations Department. While working in the Operations Department, Mr. Palionis served as a Shift Technical Advisor as well as Senior Operations Engineer, responsible for development and maintenance of the Emergency Operating Procedures and providing oversight of the ISI/IST, E-plan and Fire Protection program functions provided by the Operations Department.

Mr. Palionis also worked for the General Electric Company as a field engineer, providing support for the installation and servicing of GE/Boiling Water Reactors and of GE/Large Steam Turbines and Generators, with principal work experience in the areas of installation and repair of RPV internals and NSS systems for GE/BWRs.

Mr. Ed Harms Mr. Harms is the Assistant Operations Manager - Support for Vermont Yankee Nuclear Power Station.

He has over 18 years of experience in Vermont Yankee Operations Department since joining the Operation Department as an Assistant Ops Manager. He has a Senior Reactor Operator license since 2003. His previous position was Assistant Operations Manager - Training. His current Operations responsibilities include oversight of the budget, procedures, scheduling, hiring process and Correction Action Program issues.

Mr. Scott Goodwin Mr. Goodwin holds a B.S. Degree in Civil Engineering (Structural) from Lowell Technological Institute. He has over 30 years of nuclear experience both in the field and office at/for numerous utilities, AEs, and consulting firms. Included within this experience, he has held positions in technical supervision and management for 23 years. He was the lead individual for Vermont Yankee as the participating representative to the SQUG organization for development of resolution of USI A-46 under GL 87-02. He has completed the "SQUG Walkdown Screening and Seismic Evaluation" training course. Mr. Goodwin was the manager for implementation of Vermont Yankee's SQUG program and the seismic portion of the IPEEE program.

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 9 of 28 Marcus Hecht-Nielsen Mr. Marcus Hecht-Nielsen is a licensed professional engineer with over 7 years experience. He has a B.S degree in Structural Engineering from University of California at San Diego and an M.S. in Structural Engineering also from University of California at San Diego. He is a qualified Seismic Walkdown Engineer who is trained to EPRI Near-Term Task Force (NTTF) 2.3 requirements for performing seismic verification walkdowns of equipment and distribution systems at nuclear power plants and facilities. He is employed by Tobolski Watkins Engineering and has provided seismic qualifications for the US Mixed Oxide Fuel Fabrication Facility for Flanders Corporation. His experience includes many other structural design related projects.

Randall Stephens Mr. Randy Stephens is a degreed mechanical engineer with nuclear design experience. He is a qualified Seismic Walkdown Engineer who is trained to EPRI Near-Term Task Force (NTTF) 2.3 requirements for performing seismic verification walkdowns of equipment and distribution systems at nuclear power plants and facilities. His experience includes supporting design tasks and special engineering efforts associated with general mechanical systems and components. This includes preparing and/or assisting in the preparation of design drawings, specifications and calculations, and participating on design teams for projects involving the design of equipment, systems, buildings, and facilities.

Raymond Tworek Mr. Ray Tworek is a degreed mechanical engineer and a qualified Seismic Walkdown Engineer trained to EPRI Near-Term Task Force (NTTF) 2.3 requirements for performing seismic verification walkdowns of equipment and distribution systems at nuclear power plants and facilities. He supports mechanical design activities related to both facilities and specialty hardware for ARES clients across the United States. This support encompasses engineering, design, analysis, fabrication, and testing of structures, systems, and components in the energy, aerospace, and oil & gas industries.

Kirit Parikh Mr. Kirit Parikh is a degreed Mechanical Engineer with over 30 years experience, most in the nuclear field. He has successfully completed EPRI Training on Near Term Task Force Recommendation 2.3 Plant Walkdowns. He has worked for various companies including many nuclear utilities in United States and abroad. His experience includes pipe support design, plant modifications, as well as home office and field assignments.

David F. Grimes Mr. Grimes is a Civil engineer with over 29 years of experience in the nuclear power industry. He holds a Bachelor of Science and Masters of Science degrees in Civil Engineering from the Northeastern University (Boston MA). Mr. Grimes is currently a Senior Civil/Structural/Mechanical Design Engineer for Vermont Yankee. His primary duties at Vermont Yankee include technical oversight of contracted design projects and serving as design engineer for Civil/Structural/Mechanical projects developed in-house. He has performed design related work for Vermont Yankee Nuclear Power Station for more than 25 years. He is also responsible for the programmatic monitoring of structures to meet the requirements of the Maintenance Rule Inspection Program.

For this project Mr. Grimes completed walkdowns for the Spent Fuel Pool SWEL 2 items as part of a two man team.

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 10 of 28 Michael Rose Mr. Rose has over 2 years experience working for Entergy Vermont Yankee. He holds a Bachelor's degree in Civil/Structural Engineering from the University of Massachusetts. Mr. Rose is currently a Civil/Structural/Mechanical Design Engineer for Vermont Yankee. Major tasks while at Vermont Yankee have included Seismic scaffold package preparation and inspections, Structural portions of Engineering Changes, and calculation preparation.

For this project Mr. Rose assisted in preparation of the Base Lists and SWELs, provided project oversight for the walkdown teams, and completed walkdowns for the Spent Fuel Pool SWEL 2 items as part of a two man team.

4.1 Equipment Selection Personnel A total of 3 individuals served as Equipment Selection Personnel - see Table 4-1.

4.2 Seismic Walkdown Engineers A total of 6 individuals served as Seismic Walkdown Engineers - see Table 4-1.

4.3 Licensing Basis Reviewers A total of 2 individuals served as Licensing Basis Reviewers - see Table 4-1.

4.4 IPEEE Reviewers A total of 2 individuals served as IPEEE Reviewers - see Table 4-1.

The IPEEE review was performed by plant personnel led by Mr. Steven Buckley with support from Mark Palionas (PRA Group), both from Vermont Yankee.

4.5 Peer Review Team Table 4-2 summarizes the names and responsibilities of personnel used to conduct peer reviews of the seismic walkdown program. Experience summaries of each person follow.

Table 4-2 Walkdown Submittal Name SWEL Peer Peer Report Peer Reviewer Reviewer Julien Abramovici (ENERCON) X1 X1 Juan Vizcaya (ENERCON) X X2 Laura Maclay (ENERCON) X I I Jeffrey Horton (ENERCON) X Notes:

1. SWEL and Walkdown Peer Review Team Leader

2. Submittal Peer Review Team Leader

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 11 of 28 Peer Review Team Leader Mr. Julien Abramovici P.E. has over 39 years of nuclear power plant experience. He held various positions such as component engineer, system engineer, manager of mechanical components and many others.

Presently Mr. Abramovici is employed by ENERCON where he is a consulting engineer.

During his career, Mr. Abramovici was involved with many aspects related to seismic adequacy of components and structures, such as IEB 80-11, component seismic qualifications, 3rd party reviews of seismic stress reports and seismic qualification testing, piping analysis, etc. Mr.

Abramovici also performed and reviewed many 50.59 evaluations as well as Root Cause Evaluations.

SWEL Peer Reviewer Laura Maclay Ms. Maclay has over three years of experience as a structural engineer with Enercon Services and holds a Bachelor's degree in Structural Engineering from Drexel University. Her tasks have ranged. from assisting with the development and preparation of design change packages to performing design calculations and markups, comment resolutions, and drawing revisions. She spent a year on site at Turkey Point Nuclear Plant preparing structural evaluations of SSC's for an Extended Power Uprate (EPU). She designed safety related supports for computer and electrical equipment for the Turbine Digital Controls Upgrade package and other similar packages. Her responsibilities also included the review of calculations, drawings and vendor documentation for the seismic evaluation of the Unit 3 Palfinger Crane inside containment and new platforms in the High Pressure Turbine enclosure.

Recent work includes Fukushima flooding walkdowns at Limerick Generating Station and seismic walkdowns at Plant Farley. As a member of a two person team, she was responsible for evaluating equipment anchorage, special interactions and any other potentially adverse conditions.

Walkdown Peer Reviewer Mr. Juan Vizcaya Mr. Vizcaya has over 30 years of structural engineering and design experience. He has significant experience being the structural lead engineer on ISFSI projects and overall nuclear plant modifications and has a wide range of design/engineering experience. Projects range from the seismic analysis and design of concrete and steel structures and concrete pads to the analysis and design and restraint systems for a vertical cask vendor stack-up configurations.

Other projects include heavy load drop assessments and the analysis and design of protective structures, foundations and various mechanical and structural modifications using sophisticated finite element models. Mr. Vizcaya is skilled at using finite element analyses in the design process, and at the practical design of mechanical components, along with concrete and steel structures. He leads a group structural staff on issues involving structures, stress analysis, and site work such as layout, excavation, roads, drainage and subterranean structures.

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 12 of 28 Licensing Basis Peer Reviewers Seismic Licensing Peer Reviewers were Mr. Steven Buckley and Mr. Scott Goodwin.

Submittal Peer Reviewer Mr. Jeffrey Horton P.E Mr. Jeffrey Horton P.E. served as report reviewer. Mr. Horton is a Register Professional Engineer with over 39 years' experience in the nuclear industry doing structural design. He holds a B.S. in Aerospace Engineering from Parks College of St Louis University in Missouri and a M.S. in Material Science specializing in Solid Mechanics from Rutgers University in New Jersey. Mr. Horton leads a group structural staff on issues involving pipe stress analysis, pipe support analysis and vessel analysis.

Submittal Report peer reviewers were Mr' Juan Vizcaya and Mr. Jeffrey Horton P.E. Mr.

Vizcaya bio is presented above, as he served also as a Walkdown Peer Reviewer.

5.0 IPEEE VULNERABILITIES REPORTING During the IPEEE program in response to NRC Generic Letter 88-20 (Ref. 10.3), plant-specific seismic vulnerabilities were identified at many plants. In this context, "vulnerabilities" refers to conditions found during the IPEEE program related to seismic anomalies, outliers, or other findings.

The IPEEE final report (Ref. 10.10) and supporting documentation was reviewed to identify items determined to present a seismic vulnerability. The IPEEE Reviewers then reviewed additional plant documentation to identify the eventual resolutions to those seismic vulnerabilities not resolved when the IPEEE report was submitted.

The seismic vulnerabilities identified for VYNPS during the IPEEE program are reported in Attachment A. A total of five seismic vulnerabilities were identified by the VYNPS IPEEE program.

For each identified seismic vulnerability, the table in Attachment A includes three pieces of information requested by Enclosure 3 of the 50.54(f) Letter:

• A description of the action taken to eliminate or reduce the seismic vulnerability

• Whether the configuration management program has maintained the IPEEE action (including procedural changes) such that the vulnerability continues to be addressed

• When the resolution actions were completed.

The list of IPEEE vulnerabilities provided in Attachment A was used to ensure that some equipment enhanced as a result of the IPEEE program were included in SWEL 1. Documents describing these equipment enhancements and other modifications initiated by identification of IPEEE vulnerabilities were available and provided to the SWEs during the NTTF 2.3 Seismic Walkdowns.

6.0 SEISMIC WALKDOWN EQUIPMENT LIST DEVELOPMENT This section summarizes the process used to select the SSCs that were included in the Seismic Walkdown Equipment List (SWEL) in accordance with Section 3 of the Guidance. A team of equipment selection personnel with extensive knowledge of plant systems and components was selected to develop the SWEL. The SWEL is comprised of two groups of items:

Engineering Report No. VY-RPT-12-00019 Rev. 0 Page 13 of 28

" SWEL 1 consists of a sample of equipment required for safe shutdown of the reactor and to maintain containment integrity (i.e., supporting the five safety functions) .

• SWEL 2 consists of items related to the safety related spent fuel pool system The final SWEL is the combination of SWEL 1 and SWEL 2. The development of these two groups is described in the following sections.

Sample of Required Items For The Five Safety Functions Safe shutdown of the reactor involves four safety functions:

• Reactor reactivity control (RRC)

• Reactor coolant pressure control (RCPC)

• Reactor coolant inventory control (RCIC)

• Decay heat removal (DHR)

Maintaining containment integrity is the fifth safety function:

• Containment function (CF)

The overall process for developing a sample of equipment to support these five safety functions is summarized in Figure 1-1 of the Guidance. Figure 1-1 of the Guidance provides a screening method for selecting SSCs, starting with all of the plant SSCs and reducing the number based on a series of screening criteria. The equipment coming out of Screen #3 and entering Screen #4 is defined as Base List 1. The equipment coming out of Screen #4 is the first Seismic Walkdown Equipment List, or SWEL 1. Development of these lists is described separately in the following sections:

6.1 Base List A spreadsheet was developed to tabulate the total number of equipment for each of the twenty two (22) GIP equipment classes. The total equipment number was approximately 750 items.

The target number of equipment for the SWEL 1 list is approximately 100 to 110 items.

Therefore, approximately 15 % of the original A46/IPEEE equipment will be used to develop the SWEL 1 list to perform seismic verification of the equipment.

Based on Figure 1-1 and Section 3 of the Guidance, Base List 1 should represent a set of Seismic Category (SC) I equipment or systems that support the five safety functions. The IPEEE program was intended to address the seismic margin of SSCs associated with each of the five safety functions. At Vermont Yankee Nuclear Station, the EPRI Seismic Margin Assessment (EPRI SMA) method was used to complete the seismic IPEEE program, based on EPRI Report NP-6041 titled "A Methodology for assessment of Nuclear Power Plant Seismic Margin." As described in Section 3.2.2.1 of the Vermont Yankee Nuclear Station IPEEE report (Ref. 10.10), an equipment list was developed representing the SSCs necessary for one preferred and one alternate "success path" capable of achieving and maintaining a safe shutdown condition for at least seventy-two hours following a SSE event. This equipment list of SSCs on the success paths is consistent with the requirements of Screens #1 through #3 of the Guidance. Therefore, the IPEEE equipment list of SSCs on the success paths is used as a starting point for the NTTF 2.3 Seismic Walkdown Base List 1.

Base List 1 is presented in Table 9.4.1 of Attachment B, and has 736 total items.

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 14 of 28 6.2 SWEL 1 Based on the target of 105 items, each equipment class total was factored down by 15% to obtain an idealized number of equipment in each equipment class to be selected to maintain the same equipment diversity as the original A46/IPEEE equipment list.

In parallel with the above, a risk ranking assessment was performed to determine the most risk significant equipment from the A46/IPEEE list. This assessment method (see Attachment J) resulted in the assignment of risk value to A46/IPEEE SSEL equipment. The equipment was sorted to identify all equipment that exceeded a pre-determined risk threshold.

The above equipment sort for equipment risk ranking fulfills the risk ranking requirement shown in Reference 10.2, Figure 1-1 graphic that defines the process to develop the SWEL 1 list. This risk ranking fulfills the requirement to select equipment that supports the 5 required safety functions The resultant risk ranking listing contained redundant trains of multiple systems. Each equipment type on the risk ranking list was selected to cover the maximum amount of building areas where the system are located. For example, both A & B EDG components were selected to cover all areas of each room and any unique features such as the EDG B penthouse louvers located on the roof of the EDG B room. The RHR equipment in the corner rooms of the Reactor Building was selected to minimize dose exposure for the walkdown personnel and have equipment on each level of each corner room. Once the risk significant equipment was represented the "Sample Considerations screen was applied. Throughout the application of this screen, dose surveys for the equipment areas were reviewed to ensure equipment in the lower dose areas were selected if there was an option.

During application of the above screens the overall GIP equipment class percentages were maintained to ensure equipment diversity and representation of the makeup of the original A46/

IPEEE equipment list.

Equipment with anchorage modifications as a result of the A46/IPEEE programs were selected whenever possible to complete the target number in each equipment classification. These modifications were designed to IPEEE seismic levels and thereby are considered an IPEEE enhancement. In addition, two new components were added that were not on the original A46/IPEEE lists. One component is a new inverter that replaces a battery & charger system and the other is a new nitrogen bottle system used to support Safety Relief Valve (SRV) actuation from outside the primary containment. Equipment was also selected to ensure adequate representation from various environments. Specifically, Based on Figure 1-1 and Section 3 of the Guidance, SWEL 1 should represent a diverse population of items on Base List 1 including representative items from some of the variations within each of five sample selection attributes.

Additionally, the selection of SWEL 1 items includes consideration of the importance of the contribution to risk for the SSCs. Equipment Selection Personnel developed SWEL 1 using an iterative process. The following paragraphs describe how the equipment selected for inclusion on the final SWEL 1 are representative with respect to each of the five sample selection attributes while also considering risk significance. In general, preference for inclusion on SWEL 1 was given to items that are accessible and have visible anchorage while still maintaining the sample selection attributes.

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 15 of 28 SWEL 1 is presented as Table 9.4.2 in Attachment B, and has 102 total items.

Variety of Types of Systems Items were selected from Base List 1. ensuring that each of the five safety functions was well represented. Additionally, components from a variety of frontline and support systems, as listed in Appendix E of the Guidance, were selected. The system type of each item on SWEL 1 is listed on Table 9.4.2 of Attachment B.

Major New and Replacement Equipment With. assistance from Plant Operations, Equipment Selection Personnel identified items on Base List 1 which are either major new or replacement equipment installed within the past 15 years, or have been modified or upgraded recently. These items are designated as such on Base List 1 in Table 9.4.1 of Attachment B. A robust sampling of these items is represented on SWEL 1.

Variety of Equipment Types According to Appendix B of the Guidance, there are 22 classes of mechanical and electrical equipment. The items on Base List 1 were classified accordingly and the total number from each class was determined. Items were then selected from Base List 1 ensuring that each of the equipment classes represented there was also represented on SWEL 1 in approximately the same ratios. The equipment class of each -item on SWEL 1 is listed on Table 9.4.2 of Attachment B.

Variety of Environments Items were selected from Base List 1 located in a variety of buildings, rooms, and elevations.

These item locations included environments that were both inside and outside, as well as having high temperature and/or elevated humidity and within containment. The location and environment of each item on SWEL 1 is listed on Table 9.4.2 of Attachment B.

IPEEE Enhancements With assistance from IPEEE Reviewers, Equipment Selection Personnel identified items on Base List 1 which were enhanced as a result of seismic vulnerabilities identified during the IPEEE program. These items are designated as such on Base List 1 in Table 9.4.1 of Attachment B. Several of these items are represented on SWEL 1.

Risk Significance Information from the plant Probabilistic Risk Analysis (PRA) model was used to determine whether items were risk significant (see Attachment J for details). Where otherwise comparable items could be chosen relative to the sample selection attributes, the item with higher risk significance was chosen.

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 16 of 28 6.3 Spent Fuel Pool Items The overall process for developing a sample of SSCs associated with the spent fuel pool (SFP) is similar to that of the screening process for SWEL 1 and is summarized in Figure 1-2 of the Guidance. The equipment coming out of Screen #2 and entering Screen #3 is defined as Base List 2. The items coming out of Screen #4 are the items that could potentially cause the SFP to drain rapidly. The items coming out of either Screen #3 or Screen #4 are the second Seismic Walkdown Equipment List, or SWEL 2. Development of these lists is described separately in the following sections.

The process for selecting spent fuel pool related items is illustrated in Figure 1-2 of Reference 10.2. This process produces the second Seismic Walkdown Equipment List (SWEL 2).

6.3.1 Base List 2 The following drawings were reviewed to determine the scope of systems and equipment associated with the SWEL 2 development:

G-191173 Sheet 1, Rev. 40, "Flow Diagram Fuel Pool Cooling & Clean Up System" G-191173 Sheet 2, Rev. 10, "Flow Diagram Fuel Pool Cooling & Clean Up System" G- 191218, Rev. 12, "Reactor Fuel Storage Pool Piping Plan" 5920-00280, Rev. 11, "Arrangement Refueling Facilities" G-191688, Rev. 10, "Reactor Building Pool Liner & Gates - SH 1" G-191689, Rev. 7, "Reactor Building Pool Liner & Gates - SH 2" G-191690, Rev. 3, "Reactor Building Pool Liner & Gates - SH 3" G-191691, Rev. 9, "Reactor Building Pool Liner & Gates - SH 4" 5920-06889, Sheet I of 3, "Fuel Storage Rack Arrays - Sheet 1" Base List 2 is presented in Table 9.4.3 of Attachment B.

6.3.2 Rapid Drain Down A review of spent fuel pool drawings was performed to assess any potential rapid drain down paths. One determination was to review these drawings to identify any Spent Fuel Pool (SFP) penetrations below about 10 feet above the top of fuel assemblies. The result of the review confirmed there are no penetrations meeting the above criteria in the SFP.

It was noted that during refueling operations when the SFP is communicating with the flooded reactor cavity there is a potential drain path from the reactor cavity drain lines.

Yankee Atomic Electric Company (YAEC) Report #1493, "Vermont Yankee Nuclear Power Plant Evaluation of Potential Failures of the Spent Fuel Pool Storage System", was prepared in response to IE Bulletin 84-03, "Refueling Cavity Water Seal". This report evaluates the potential for, and consequences of, a cavity seal failure. It considered the potential drain paths through attached piping for the fuel pool, refueling cavity and dryer separator storage pit. The

Engineering Report No. VY-RPT-12-00019 Rev. 0 Page 17 of 28 "Seismic Event" section evaluates this piping. The seismic piping is concluded to be adequate and the failure of the non-seismic piping is considered a "very unlikely scenario and conservative assumption". The postulated failure of all non-seismic drain lines was addressed by evaluating inventory loss rate and available makeup source rates. It was concluded this connected piping failure would drain the top 6 feet of the SPF in 54 minutes with no Operator action and the makeup capacity exceeds the leak rate capacity 6.3.3 SWEL 2 The first screen of Seismic Category I (SCI) equipment limits the scope to the Standby Fuel Pool Cooling System and associated SCI support equipment. A review of G-191173 flow diagrams provided the source for the identification of SCI equipment. Using sampling considerations defined in Reference 10.2, the resulting equipment is a pump, valve, heat exchanger, control panel and instrument rack and associated indicating instruments. A total of eleven (11) components were selected. SWEL 2 is presented in Table 9.4.5 of Attachment B.

6.4 Deferred, Inaccessible Items on SWEL Each item on the SWEL shall be walked down as part of the NTTF 2.3 Seismic Walkdown program. In order to perform the seismic walkdowns of these items, it is necessary to have access to them and to be able to view their anchorage. In some cases, it was not feasible to gain access to the equipment or view its anchorage because Vermont Yankee Nuclear Station was at power during the entire 180-day response period of Enclosure 3 to the 50.54(f) letter. For these cases, walkdowns of these items have been deferred until the next refueling outage (RFO 30) in March of 2013. An updated submittal report incorporating these deferred walkdowns will be provided within 90 days from the end of RFO 30.

Deferred items are summarized in the table below. A total of 13 items are deferred due to lack of access (high radiation areas). Eight (8) items are in the Steam Tunnel and five (5) items are in the Drywell.

SWEL# Equipment ID Description Location Reason SWEL-1-029 V23-15 HPCI/STEAM SUPPLY MOV DRYWELL High rad.

266' INICTINDRYWELL High rad.

SWEL-1-041 TE-16-19-030A DW TEMPERATURE INDICATION Hg 268' SWEL-1-052 V2-80D MAIN STEAM/INBOARD MSIV DRYWELL High rad.

254' DRYWELL High rad.

SWEL-1-055 RV-2-71C MAIN STEAM/RELIEF VALVE 275' _______

275' SAFETY RELIEF VALVE/NITROGEN DRYWELL High rad.

SUPPLY ACCUMULATOR 275' SWEL-1-030 V23-16 HPCI/STEAM SUPPLY MOV STEAM igh rad.

TUNNEL 251' STEAM High rad.

SWEL-1-053 V2-86A MAIN STEAM/IOUTBOARD MSIV TEL 251' rad.

TUNNEL 251' L0S-2-6A MAIN STEAM/IOUTBOARD IINSTRUMENT MSIV AIR SUPPLY ACCUMULATOR STEAM 251' TUNNEL High rad.

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 18 of 28 SWEL# Equipment ID Description Location Reason TS-23-11A HPCI/STEAM LEAK DETECTOR STEAM High rad.

SWEL-1-073 TUNNEL 251' TS-23-102A HPCI/STEAM LEAK DETECTOR STEAM High rad.

SWEL-1-074 TUNNEL 251' TS-23-103A HPCI/STEAM LEAK DETECTOR STEAM High rad.

SWEL-1-075 TUNNEL 251' TS-23-104A HPCI/STEAM LEAK DETECTOR STEAM High rad.

SWEL-1-076 TUNNEL 251' STEAM High rad.

SE-2-86A-1 MS/OUTBOARD MSIV SOLENOID AC/DC TEL 251' SWEL-1-077 TUNNEL 25 1' 7.0 SEISMIC WALKDOWNS AND AREA WALK-BYS The NTTF 2.3 Seismic Walkdown Program, conducted in accordance with the Guidance, involves two primary walkdown activities: Seismic Walkdowns and Area Walk-Bys. These activities were conducted at VYNPS by teams of two, trained and qualified Seismic Walkdown Engineers (SWEs) (see Section 4.0). Each team included one engineer with at least several years of experience in seismic design and qualification of power plant SSCs. A total of three SWE teams were used. Each walkdown team was accompanied by at least one plant representative to assure personnel and equipment safety, and support maximum application of ALARA principles.

The seismic walkdowns and area walk-bys were conducted over the course of 3 weeks during October of 2012. Each morning, a pre-job brief with all personnel involved was conducted. This pre-job brief was used to outline the components and areas that would be walked down that day, to ensure consistency between the teams, to reinforce expectations, to identifying potential personnel safety issues specific to that day, and to allow team members to ask questions and share lessons learned in the field. The SWE teams brought cameras, tape measures, flashlights and, mirrors, as well as the required forms and supporting drawings into the field to assist with the seismic walkdowns and area walk-bys.

7.1 Seismic Walkdowns Seismic walkdowns were performed in accordance with Section 4 of the Guidance for all items on the SWEL (SWEL 1 plus SWEL 2), except for those determined to be inaccessible and deferred. To document the results of the walkdown, a Seismic Walkdown Checklist (SWC) with the same content as that included in Appendix C of the Guidance was created for each item. Additionally, photographs were taken of each item and included on the corresponding SWC.

The SWE teams conducted preliminary "scouting" walkdowns to get a general understanding of plant layout and to identify items on the draft SWEL that were inaccessible. One item that was identified to be inaccessible on these "scouting" walkdowns was a valve covered in insulation. After discussion with the Equipment Selection Personnel, the valve was replaced with another valve in similar environment while ensuring that the overall integrity of the final SWEL was not compromised.

Prior to- performance of the walkdowns, documentation packages were developed that contained the pre-filled SWC and other pertinent information including the location drawings, response spectra information, previous A-46 and IPEEE seismic walkdown documentation, and anchorage drawings where applicable. These documentation packages were brought with the

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 19 of 28 SWE teams into the plant during the seismic walkdowns.

Walkdown inspections focused on anchorages and seismic spatial interactions, but also included inspections for other potentially adverse seismic conditions. Anchorage, in all cases, was considered to specifically mean anchorage of the component 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 or connections, such as flange bolts on in-line components were not considered as equipment anchorage. These bolts and connections were evaluated by the SWEs and any potential adverse seismic concerns were documented under "other adverse seismic conditions" rather than under "anchorage". Thus, components with no attachments to the structure are considered as not having anchorage. Nevertheless, the attachment of these components to other equipment was evaluated and inspected for potentially adverse seismic conditions.-

Cabinets/panels on the SWEL that could be reasonably opened without presenting safety or operational hazards were opened during the walkdown. This allowed visual observation of internal anchorage to the structure (where present), as well as inspection for "other adverse seismic conditions" related to internal components if it could be observed without breaking the plane of the equipment being opened. Where opening the cabinet/panel required extensive disassembly (e.g., doors or panels were secured by more than latches, thumbscrews, or similar),

justification for how the inspection met the program goal without opening the cabinet/panel was included on the SWC and the walkdown of that item is considered complete.

In addition to the general inspection requirements, at least 50% of the SWEL items required confirmation that the anchorage configuration was consistent with plant documentation. Of the 100 SWEL items inspected, 53 anchorage inspections were conducted and documented which is greater than the 50% requirement. When anchorage configuration verification was conducted, the specific plant documentation used for comparison to the as-found conditions was referenced on the SWC.

The SWC for each SWEL item where a seismic walkdown has been initiated is included in Attachment C. A total of 100 SWCs are attached; 100 with completion status marked "Y" and 0 with completion status marked "N". Therefore, the 100 completed SWCs represent the completed walkdowns of each SWEL item accessible during the walkdown period.

A total of eighty-nine (89) items were walked down for SWEL 1 and eleven (11) for SWEL 2.

Thirty nine (39) Area Walk-By were also performed.

It should be noted that SWEL 1 contains 102 items with 13 out of the 102 items (8 in the Steam Tunnel and 5 in the Drywell) deferred to the next refueling outage due to access and ALARA considerations. Seven of these 13 deferred SWEL 1 items will include an anchorage configuration verification. There were no deferred items for SWEL 2.

Area Walk-Bys Seismic area walk-bys were performed in accordance with Section 4 of the Guidance for all plant areas containing items on the SWEL (SWEL 1 plus SWEL 2) except for those SWEL items located in plant areas inaccessible during the walkdown period. A separate Area Walk-

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 20 of 28 By Checklist (AWC) with the same content as that included in Appendix C of the Guidance was used to document the results of each area walk-by performed. Photographs were taken of each area, and included on the corresponding SWC.

Area walk-bys were conducted once for plant areas containing more than one SWEL item. In cases where the room or area containing a component was very large, the extent of the area encompassed by the area walk-by was limited to a radius of approximately 35 ft. around the subject equipment. The extent of the areas included in the area walk-bys is described on the AWC for that area. Because certain areas contained more than one SWEL item, there are fewer total area walk-bys conducted than seismic walkdowns. A total of 39 area walk-bys were necessary to cover all plant areas containing at least one accessible SWEL item.

The AWC for each area walk-by completed is included in Attachment D. A total of 39 AWCs are attached, which represent all of the areas containing a SVWEL item that were accessible during the walkdown period. An additional 5 estimated area walk-bys of areas inside the Drywell and Steam Tunnel will be completed together with the deferred walkdowns for those inaccessible items.

8.0 LICENSING BASIS EVALUATIONS During the course of the seismic walkdowns and area walk-bys, the objective of the SWE teams was to identify existing degraded, non-conforming, or unanalyzed plant conditions with respect to its current seismic licensing basis. This section summarizes the process used to handle conditions identified, what conditions were found, and how they were treated for eventual resolution.

Condition Identification When an unusual condition was observed by a SWE team in the field, the condition was noted on the SWC or AWC form and briefly discussed between the two SWEs to agree upon whether it was a potentially adverse seismic condition. These initial conclusions were based on conservative engineering judgment and the training required for SWE qualification.

For conditions that were reasonably judged as insignificant to seismic response, the disposition was included on the SWC or AWC checklist and the appropriate question was marked "Y", indicating that no associated potentially adverse seismic condition was observed. Unusual or uncertain conditions were reported to site personnel for further resolution through the Corrective Action Program (CAP). A total of 131 seismically insignificant conditions were identified. These conditions were generally related to either housekeeping or minor non-consequential degradation. No seismically significant conditions were found.

Unusual conditions that were potentially seismically significant were entered into the CAP directly.

Further resolution of these conditions is not tracked or reported as part of the NTTF 2.3 Seismic Walkdown program, except by noting the CR numbers generated on the applicable SWCs and AWCs.

8.1 Licensing Basis Evaluations There were no Licensing Basis Evaluations required. All unusual conditions were entered into the CAP system immediately and dispositioned for operability, with no operability issues identified.

Engineering Report No. VY-RPT-12-00019 Rev. 0 Page 21 of 28 8.2 Corrective Action Program Entries The following CRs were generated:

CR-VTY-2012-04979:

MCC-8B panels have loose/missing screws; Condition: During Fukushima seismic walkdowns in the Reactor Building 280' Elevation, the inspection team noted two loose panel screws and one missing cubicle screw on MCC-8B. Requirement not met: All available panel fasteners need to be secured.

CR-VTY-2012-04816:

Two loose panel screws (2 OF 3) on MCC-9A and EDG A Voltage Regulator Cabinet panel door screw (1 of 4) not engaged.

CR-VTY-2012-04870:

Junction box B679 SII (EDG A Day Tank room) missing two of four cover screws and EDG A skid has a 3/4" drain line from SR-24-1A relief valve to the floor drain with a disengaged support clip.

CR-VTY-2012-05006:

Junction Box B-666 has missing cover screws Condition: During Fukushima seismic walkdowns in the Reactor Building 252 Elevation, the inspection team noted four of eight cover screws are missing on Junction Box B-666.

Requirement not met: All fasteners should be installed CR-VTY-2012-05007:

During Fukushima seismic walkdowns on Reactor Building floor elevation 303', an interior panel inspection was performed on the 24V DC-ECCS panel mounted on column line (10,1 lz),

south side of the column. One of the four nuts that secure the interior mounting panel was engaged only half the depth of the nut. Requirement: Full thread engagement of nut CR-VTY-2012-05008:

Nitrogen supply tanks CYL 1A and CYL 1B have loose nuts on mounting U-bolts Condition: During Fukushima seismic walkdowns in the Reactor Building 252 Elevation, the inspection team noted three loose nuts on CYL-72-1A and CYL-72-1B mounting system.

Requirement not met: All nuts should be securely fastened.

CR-VTY-2012-5091:

During Fukushima seismic. walkdowns on the HPCI Turbine skid located on the Reactor Building floor elevation 213'-9", it was identified that some of the ten anchorage locations have grout between the bottom of the skid support (channel shaped steel attachment) and the surface of the foundation and some do not. Grout is not required under the channel steel per the attached Operability Recommendation.

CR-VTY-2012-5097:

During Fukushima seismic walkdowns in the Control Room, the inspection team noted 4 missing panel screws on CRP-9-46 during the area walk-by.

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 22 of 28 CR-VTY-2012-5099:

During Fukushima seismic walkdowns surface corrosion was observed on Valve CV-3-126 27 associated with HCU 10-27 (north bank) at the bonnet and yoke body interface area.

Corrosion in a tapped hole of the yoke body was identified as a source.

CR-VTY-2012-5118:

During Fukushima seismic walkdowns in the Reactor Building, HPCI Room for Rack 25-50B, the inspection team noted one of four screws attaching the PI-23-81 mounting plate to the rack was missing. The three remaining screws are securely fastened.

CR-VTY-2012-5126:

During Fukushima seismic walkdowns in the Cable Vault, the inspection team noted two of 15 cover screws are missing on the west edge of Junction Box B-638.

CR-VTY-2012-5369:

During Fukushima seismic walkdowns in the West Switchgear Room, the inspection team noted that the ladder support mounted on the south block wall (G-191627-22) is starting to pull away from the wall.

CR-VTY-2012-5371:

During Fukushima seismic walkdowns in the Fuel Pool Cooling Heat Exchanger Room, the inspection team noted poor housekeeping including; ladders stored on the floor that are not tagged per Procedure AP-0019, multiple bags of RAD trash, empty tool bucket, and other out of place small work tools in the room.

All above CRs were evaluated immediately for operability and determined to be operable. All CRs are closed and have been rolled-up to CR-VTY-2012-5021 Rollup Condition Report for "Minor" Equipment Issues Identified during Tier 1 Seismic Walkdown.

CR-VTY-2012-5021:

Rollup Condition Report for "Minor" Equipment Issues Identified during Tier 1 Seismic Walkdown This CR provides a roll-up of minor equipment issues identified during the NRC Tier 1 (2.3)

Seismic Walkdowns. The CAs identified requires performance of minor maintenance. The CAs that are initiated ensure that the required Work Orders are properly prioritized and executed.

8.3 Plant Changes There are no changes required as a result of this effort.

9.0 PEER REVIEW This section summarizes the process and results of each peer review activity.

9.1 Peer Review Process The peer review for the NTTF Recommendation 2.3 Seismic Walkdowns was performed in accordance with Section 6 of the Guidance. The peer review included an evaluation of the following activities:

Engineering Report No. VY-RPT-12-00019 Rev. 0 Page 23 of 28

• 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 conditions in to the plant's Corrective Action Plan (CAP); and

• review of the final submittal report.

At least two members of the peer review team (see Section 4.5) were involved in the peer review of each activity, the team member with the most relevant knowledge and experience taking the lead for that particular activity. A designated overall Peer Review Team Leader provided oversight related to the process and technical aspects of the peer review, paying special attention to the interface between peer review activities involving different members of the peer review team.

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 the Guidance. The SSCs to be evaluated during the seismic walkdown were selected as described in Section 6.0. The list of components was provided to the members of the peer review team listed in Section 4.5. The peer review members independently provided comments to the personnel who selected the components. All comments were addressed and the peer review team reviewed the changes made to the SWEL and the final SWEL, to ensure all recommenditions from the Guidance were met. Specific considerations for the peer review process are described below for SWEL 1 and SWEL 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 in the Guidance:

• Reactor Reactivity Control;

• Reactor Coolant Pressure Control;

• Reactor Coolant Inventory Control;

• Decay Heat Removal; and

• Containment Function.

For SWEL 1, the peer review 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

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 24 of 28 Ilisk insight consideration.

The final SWEL 1 contains a number of items that perform each of the five safety functions specified in the Guidance. 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 the Guidance, 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 development of the list.

For SWEL 2, the peer review team determined that the process to select spent fuel pool related items complied with the Guidance. Portions of the spent fuel pool cooling system at Vermont Yankee are safety related Seismic Category I and all different types of components associated with the safety-related system are represented on the SWEL 2. No items that could cause rapid drain down of the Spent Fuel Pool for Vermont Yankee were identified. Therefore, SWEL 2 does not contain any components associated with potential 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 the Guidance.

All of the peer review comments made during development of SWEL 1 and 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.

9.2.2 Seismic Walkdowns and Area Walk-Bys Peer review of the seismic walkdowns and area walk-bys was conducted by two peer reviewers, each of whom is a qualified SWE and has broad knowledge of seismic engineering applied to nuclear power plants. One of the peer reviewers participated in the seismic walkdown program for a different utility. The peer reviews were conducted at the VYNPS concurrent with the conduct of walkdowns, at approximately 50% completion. The peer review was performed as follows:

" The peer review team reviewed the walkdown packages (including checklists, photos, drawings, etc.) for SWEL items already completed to ensure that the checklists were completed in accordance with the Guidance. A total 19 SWC and 11 AWC forms were reviewed, each representing approximately 20% of their respective totals. In the context of the Guidance, the peer review team considered the number of walkdown packages reviewed to be appropriate. The packages reviewed represent a variety of equipment types in various plant areas. While reviewing the walkdown packages, the peer reviewers conducted informal interviews of the SWEs and asked clarifying questions to verify that they were conducting walkdowns and area walk-bys in accordance with the Guidance.

• The peer review team held a meeting with the SWE teams to provide feedback on the walkdown and walk-by packages reviewed and the informal interviews, and discuss potential modifications to the documentation packages in the context of the Guidance.

• Each peer reviewer accompanied each SWE team into the field and observed them perform a walkdown of a SWEL component and its associated area walk-by. During

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 25 of 28 these observations, the peer reviewers asked clarifying questions to verify the walkdown and walk-by process being followed was in accordance with the Guidance.

The items walked down under the observation of a peer reviewer are listed below. The associated area walk-bys performed under the observation of a peer reviewer are listed below.

The peer review team held a meeting with the SWE teams to provide feedback on the walkdown and walk-by observations, and discuss how lessons learned from review of the walkdown packages had been incorporated into the walkdown process.

As a result of the peer review activities, the SWIE teams modified their documentation process to include additional clarifying details, particularly related to checklist questions marked "N/A" and where conditions were observed but judged as insignificant. The peer review team felt these modifications would be of benefit for future reviews of checklists incorporated into the final report. These modifications were recommended following review of the walkdown and area walk-by packages, and the observation walkdowns and area walk-bys demonstrated that the SWEs understood the recommendations and were incorporating them into the walkdown and area walk-by process. Previously completed checklists were revised to reflect lessons learned from the peer review process.

Based on completion of the walkdown and walk-by peer review activities described, the peer review team concludes that the SWE teams are familiar with and followed the process for conducting seismic walkdowns and area walk-bys in accordance with the Guidance. 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 such as the examples described in Section 4 of the Guidance. The SWEs demonstrated appropriate use of self-checks and peer checks. They discussed their observations with a questioning attitude, and documented the results of the seismic walkdowns and area walk-bys on appropriate checklists.

One of the Peer Reviewers was present on site for two out of the three weeks of the walkdowns.

SWELs and AWCs documentation was randomly reviewed and discussed with the respective team.

The SWEL items included the following:

1. SWEL-102 CY1-72-lA N2 cylinder

2. SWEL-079 NG-13A CAD SOV

3. SWEL-032, RRV-8

4. SWEL-058 P-10-D RHRPump'

5. SWEL-059 V-10-65B RHR Bypass valve

6. SWEL-005 P-46-1A CS Pump

7. SWEL-061 P-8-1C RHRSW Pump

8. SWEL-062 V-10-89A RHR Supply MOV

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 26 of 28

9. SWEL-027 P44-lA HPCI Pump

10. SWEL-068 TU-I-IA HPCI Turbine

11. SWEL-094/095 HPCI Instrument Rack

12. SWEL-001 CRD HCU (Both banks)

13. SWEL-004 CV-3-26 (inlet valves)

14. SWEL-003 PCV-3-32B

15. SWEL-020 MCC-9D In addition, as the Peer Reviewer walked to the selected SWEL, a survey of the area to the respective SWEL was also performed.

The AWC items reviewed were in the Reactor Building as follows:

1. AWC-014

2. AWC-027

3. AWC-029

4. AWC-030

5. AWC-034

6. AWC-032

7. AWC-007

8. AWC-009

9. AWC-031

10. AWC-003

11. AWC-013 In all the above SWEL and AWC walkdowns no seismic issues were identified. Housekeeping items identified are captured in CRs listed above.

A second Peer Reviewer checked all SWEL and AWC forms for completeness, checked AWC

-SWEL relationship and selected some SWELs to walkdown.. The SWEL selected were:

1. SWELI -007

2. SWELl-040

3. SWELl-043

4. SWELl-092 9.2.3 Licensing Basis Evaluations There were no Licensing Basis Evaluations required. Operability determinations were

Engineering Report No. VY-RPT- 12-00019 Rev. 0 Page 27 of 28 performed as part of the CAP process.

The method used to perform Licensing Bases Evaluations (LBEs) for the Vermont Yankee effort was more conservative than recommended in the Walkdown Guidance document. The Guidance discussed performing an LBE to first determine if a reported condition complies with the plant licensing bases prior to entering the condition in the plant CAP. Then, if the LBE concluded the condition was in compliance with plant licensing bases, it would be so documented and no further effort would be required.

Instead, all potentially adverse seismic conditions identified during the walkdowns and AWBs were immediately entered into the CAP (within several hours of discovery). LBEs performed to establish compliance with the plant licensing bases were included in the dispositions of the CRs.

This approach was preferred by Vermont Yankee since it provided immediate notification to the Main Control Room of all potential adverse impacts. This was reasonable and justifiable since the Vermont Yankee CAP requires immediate assessment of potentially adverse conditions for plant operability, which by definition, required review and understanding of the design and licensing bases of the subject components.

9.2.4 Submittal Report The peer review team was provided with an early draft of this submittal report for peer review.

The peer review team verified that the submittal report met the objectives and requirements of to the 50.54(f) Letter, and documented the NTTF 2.3 Seismic Walkdown program performed in accordance with the Guidance. The peer review team provided the results of review activities to the SWE team for consideration. The SWE team satisfactorily addressed all peer review comments in the final version of the submittal report. The signature of the Peer Review Team Leader provides documentation that all elements of the peer review as described in Section 6 of the Guidance were completed.

Engineering Report No. VY-RPT-12-00019 Rev. 0 Page 28 of 28

10.0 REFERENCES

10.1 10CFR50.54(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, dated 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 - 10CFR50.54(f)", June 1991 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 Seismic Qualification Utility Group (SQUG) Procedure: Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Power Plant Equipment, Revision 3A, December 2001 10.6 USNRC NUREG 1407 "Procedural and Submittal Guidance for Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities" June 1991 10.7 EPRI NP-6041-SL Rev. 1, "A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1)", August 1991 10.8 Seismic Qualification Utility Group (SQUG) Rev. 2, "Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Power Plant Equipment", dated February 1992, corrected February 14, 199210.9 NRC Letter to Vermont Yankee NVY 99-23, dated February 26, 1999, "Request for additional Information on Vermont Yankee Nuclear Power Station Individual Plant Examination of External Events (IPEEE) Submittal (TAC No. M83689)"

10.10 NRC Letter to Vermont Yankee NVY 0 1-23, dated March 22, 2001, "Vermont Yankee Nuclear Power Station Individual Plant Examination of External Events (IPEEE) Submittal (TAC No.

M83689)"

10.11 NRC Letter to Vermont Yankee NVY 2001-124, dated December 14, 2001, "Vermont Yankee Nuclear Power Station - Correction to Individual Plant Examination of External Events (IPEEE) Staff Evaluation Report (TAC no. MB3290)"

10.12 Vermont Yankee Letter to NRC BVY 01-75, dated October 4, 2001, "Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271), IPEEE Staff Evaluation Report Comments" 10.13 Entergy Procedure EN-DC-168, Rev. 0, "Fukushima Near-Term Task Force Recommendation 2.3 Seismic Walk-down Procedure" 10.14 Vermont Yankee Nuclear Power Station Updated Final Safety Analysis Report (UFSAR) 10.15 Vermont Yankee Nuclear Power Station Topical Design Basis Document for External Events Rev. 5 11.0 ATTACHMENTS ATTACHMENT A - IPEEE VULNERABILTIES TABLE ATTACHMENT B - SEISMIC WALKDOWN EQUIPMENT LISTS ATTACHMENT C - SEISMIC WALKDOWN CHECKLISTS (SWCs)

ATTACHMENT D - AREA WALK-BY CHECKLISTS (AWCs)

ATTACHMENT E - POTENTIALLY ADVERSE SEISMIC CONDITIONS ATTACHMENT F - LICENSING BASIS EVALUATION FORMS ATTACHMENT G - PEER REVIEW CHECKLIST FOR SWEL ATTACHMENT H - SEISMIC WALKDOWN ENGINEER TRAINING CERTIFICATES ATTACHMENT I - PEER REVIEW COMMENTS FOR SWCs AND AWCs ATTACHMENT J - SWELl RISK RANKING PROCESS

Attachment A Engineering Report No. VTY-RPT-12-00019 Rev. 0 Page 1 of 2 Attachment A IPEEE Vulnerabilities Table

Attachment A Engineering Report No. VY-RPT-12-00019 Rev. 0 Page 2 of 2 AT-rACHMENT 9.3 IPEEE VULNERABILMES TABLE FORM ANDINSTRUCTIONS V-01 A-46 Program outliers. Complete A-46 program and resolve all outliers. Modifications Vermont Yankee calculation, VYC-2068, "Final Summary of USI A- Y NRC Letter NVY designed to IPEEE seismic levels. IPEEE submittal Table 3.4.1 46 Outlier Resolution" and VYC-2119, "IPEEE Seismic Component 01-023, dated defined modifications made for A46 and IPEEE. Table 3.4.2 HCLPF Evaluations Summary. Associated modifications are March 22, 2001 documented A46/ IPEEE outliers to be resolved, referenced within these documents.

Per NRC Letter NVY 01-023, dated March 22, 2001, all A46/ IPEEE outliers described in Table 3.4.2 have been resolved to meet 46 criteria and to assure a HCLPF > 0.3g.

Y Accepted per V-02 Condensate Storage Tank (CST) has a HCLPF of 0.25g. To further evaluate for possible modification or upgrade of seismic Vermont Yankee concluded that no simple cost effective conclusions capacity, and its associated risk to total CDF using PRA methods, enhancement could be identified that would improve CST seismic presented in NVY capacity.01-023, dated March 22, 2001 V-03 Diesel Fire Pump Fuel Tank is weak at the tank shelt to saddle Tubing will be rerouted to accommodate span flexibility to account Tubing reroute eliminated the potential crimping concern during a Y Vermont Yankee interface and potential seismic loads could cause crimping of the for seismic displacement of the tank relative to the saddle supports. seismic event. The adjacent masonry wall reviewed in comparison Work Order 99-fuel supply tubing. Also a potential seismic interaction with an Review seismic capacity of the wall, the masonry wall sampling that was performed for the IPEEE 011585-000; adjacent masonry wall. program and determined to be enveloped by the seismic capacity of Complete the masonry wall evaluated and documented in Table 3.2.4 of the 7/14/2000 VY IPEEE submittal.

Minor V-04 The support of the fire system northwest standpipe in the Reactor Proposed improvements to enhance the support of the fire system Vermont Yankee calculation, VYC-2136, documents the design of Y Modification Building requires more robust support. northwest standpipe in the Reactor Building. enhanced deadweight supports and additional lateral supports for (MM) 2000-27 the Reactor Building northwest standpipe. implemented the modification; Complete 11/21/2000 Y Accepted per V-05 Seismic resistance of the hydrogen piping in the Turbine Building Proposed improvements to the Turbine Building hydrogen piping No cost effective improvements could be identified, conclusions could be improved. seismic resistance capacity. presented in NW 01 -023, dated March 22, 2001 Prepared by: Steven M Buckley - Date: 11-14-2012 EN-DC-168 REV 0

Attachment B Engineering Report No. VTY-RPT-12-00019 Rev. 0 Page 1 of 24 Attachment B Seismic Walkdown Equipment-List

Attachment B VY-RPT-12-00019 Rev. 0 Page 2 of 24 ATTACHMENT 9.4 SEISMIC WALKDOWN EQUIPMENT LIsTS FORM AND INSTRUCTIONS Seismic Walkdown Equipment List Approval (Final SWELl & SWEL2)**

Prepared by: Steven M BucklIey.<ý-,--.- Date: ZO~ 2/2-,5/Z Equipment Selectin Personnel Reviewed by: Julien Abramovici thIll Date: / 2/(,;,

Peer R~ewer Concurrence by: Edward Harms Date:

Operations Personnel

• • During implementation of the Seismic Walkdowns SWEL-065 was determined to be inaccessible for inspection. This SWEL number was valve FCV-104-17D, SW/D TRAVELLING SCREEN CONTROL VALVE. It was replaced with Valve LCV-108-3 which is located in the Fuel Oil Pump House. This valve is a similar GIP 07 class valve and is also located in a humid environment as was FCV-104-17D. No other SWELl & SWEL2 items have been changed since the original SWEL approval prior to Seismic Walkdowns.

Table 9.4.1- Base List 1 Attachment VY-RPT-12-00019 Rev. 0 Paae 3of 24 SCREEN11 SCREEN 2 I SCREEN3 SCREEN 4 SQUG CURRENT Undergo Maintains at Environment Decay Reactivity Pressure Inventory UNIl EQUIPMENT EQUIPMENT ID SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Seismic Regular least one of Inside/ High Tempi Heat Containment ControI Control IControl CLASS 1? Configuration theE safety Replaced'. IPEEE Outside? Humidity?.

Borated Removal Inspections? Functions System?

(110) (TIH)

HCU- .RD/HYDRAULIC CONTROL UNITS (89) YES

,RDONORTHSOV INSTRUMENT VOLUME YES 3-33A LCV-3-33A  :;RDISCRAM DISCHARGE VOLUME DRAIN VALVE YES NO YES I NO I X 1 07 LCV-3-338 LCV-M3B ,RD/SCRAM DISCHARGE VOLUME DRAIN VALVE YES NO YES NO NO x 1 1 07 LCV-3-33C LCV-3-33C 7RDISCRAM DISCHARGE VOLUME DRAIN VALVE NO YES NO NO x LCV-3-330 LCV,4-330 C;RD/SCRAM DISCHARGE VOLUME DRAIN VALVE NO YES NO PCV-3-32A PCV-3-32A .RDISCRAM DISCHARGE VOLUME VENT VALVE NO YES NO PCV-3-32B PCV-3-32B .,RD/SCRAM DISCHARGE VOLUME VENT VALVES YES NO YES NO x 1 1 07 CV-3-126- CV-3-126- Z.RD/SCRAM VALVES (89) INLET YES NO YES NO NO x 1 07 CV-3-127- CV-3-127- YES NO YES NO NO X YES NO YES P-46-1A P-46-lA YES NO YES P-46-18 P-46-1B .SPB" CORE SPAY PUMP YES NO YES 1 SoA IV14-11A V14-11A ,S/CS INJECTION MOV YES NO YES NO NO x 1 0EA V14-11B V14-118 YES NO YES NO NO x 1 0EA V1l V14-12A YES NO YES NO NO x 1 V14-12B YES NO YES NO x V14-26A -SIFULL FLOW TEST MOV YES NO YES NO -x V14-268 V14-2SB .S/FULL FLOW TEST MOV YES NO YES NO NO x I 08A V14-SA V14-5A .SIMIN-FLOW MOV YES NO YES NO NO x 1 08A v14-Sti NO NO NO YES v14-7A NO YES NO V14-7it .3SIPUMP SUCTION MOV YES NO YES NO TK-80-lA )G START AIR/AIR RECEIVER TANK A YES NO NO NO NO 21 TK-80-18 TK-80-1 8 DG START AIR/AIR RECEIVER TANK B YES NO 1 NO NO YES NO TK-80-1 C ," YES NO 1 21 TK-80-iC )G START AIR/AIR RECEIVER TANK C NO NO YES NO TK-80-1 0 YES NO NO NO 1 21 TK-80-10 )G START AIR/AIR RECEIVER TANK 0 PS-24-1A YES NO NO 1 18 PS-24-lA )G START AIR/COMP CONT NO PS-24-16 NO NO 1 18 PS-24-1B 7G START AIR/COMP CONT YES NO C-3-1A NO NO 1 12 C-3-1A DG START AIR/COMPRESSOR A YES NO NO 12 C-,-18 C-3-18 )G START AIR/COMPRESSOR B NO NO NO 1 YES NO 085 AS-24-1A AS-24-IA 3G START AIR/DG AIR SUPPLY YES NO NO 1

AS-24-I B NO NO 1 088 AS-24-1B AS-24C2A 7G START AIR/DG AIR SUPPLY YES 1 08B AS-24-2A 7G START AIR/DG AIR SUPPLY YES NO NO AS-24-2B 1 088 AS-24-2B 7G START AIR/DG AIR SUPPLY YES NO NO NO NO PI524.SAP-lA 1 18 P-.24-SAP-1A )G START AIR/PRESS BOUND YES NO NO NO NO PI-24-SAPlB 7G START AIR/PRESS BOUND YES NO NO NO PS-24-APLA-1 NO-

)G START AIR/PRESS BOUND YES NO NO NO PS-24-APLA-1E NO

)G START AIR/PRESS BOUND YES NO NO 1 17 lOG-lA DG-1A DIESEL GENERATOR A NO NO DG-1B YES NO NO 1 17 DO-la DIESEL GENERATOR B YES NO NO NO NO LSH-1O8-2A 1 18 LSH-101 FUEL OIL/DAY TANK A HIGH/PRESS B YES NO NO NO NO LSL-108-3A FUELOIL/DAYTANKA LOW/PRESS B YES NO NO NO LSH-108-2B FUELOIL/DAYTANKB HIGH/PRESS B NO YES NO NO LSL-108-38 FUELOIL/DAYTANKBLOW/PRESS B YES NO NO NO 1 SL-108-3B LCV-108-*SA NO 1 07 FUEL OIL/DAY TANK FILL YES NO NO CV-108-2A NO NO 1 07 FUEL OIL/DAY TANK FILL NO NO NO FUEL OIL/DIESEL OIL DAY FUEL OIL/DIESEL OIL DAY NK B K40-1A rK-40-1A FUEL OIL/FUEL OIL STORAGE TANK YES NO 0 NO

Table 9.4.1- Base List 1 Attachment B VY-RPT-12-00019 Rev. 0 PornA nf O

Page 4 of 24 SCREEN11 SCREEN 2 SCREEN3 SCREEN 4 SQUG Undergo Maintains at Environment Decay Reactivity Pressure Inventory UNn EQUIPMENT EQUIPMENT DESCRIPTION Seismic Regular least one of Inside/ High Tempi Borated Heat Containment EQUIPMEN ID SSEL EQUIPMENT ID Control Control Control the 5 safety ReplacedI CLASS IPEEE Removal 1? Configuration Outside? Humidity?

System?

Inspections? Functions (10O) IT / H) 11 05  !-2-lA !P-g2-1A IFUEL OIL/FUEL OILTRANSFER PUMP A YES NO i NO 1 NO I1 H INO 1 05 J-92-1 IP-92-18 FUEL OIL/FUEL OIL TRANSFER PUMP B YES NO NO NO I H NO 1 07 ILCV-108-3 LCV-108-3 -UEL OIL/HEAT TK BOILER TANK FILL YES NO NO NO H NO VAC-A 120 VAC VAC-A VITAL SUBPANEL IO0AA YES INO NO NO NO IAC-1 120/240V AC INSTRUMENTATION OISTR NO NO NO VAC-1 120/240V UNINTERRUPTIBLE (VITAL)AC -I.

NO NO NO MG-2-1A 120/240V VITALAC MG SET NO NO NO 1 1 16 BC-1-1A BC-I-lA 125V DC MAIN STATION BATTERY CHAF 4 IYEST NO NO NO 1 16 BC-1-1B eC-1-16 125V DC MAIN STATION BATTERY CHARGER B ON DC-2 YES NO NO NO NO BC-AS-2 IRMAL I C-2AS YES NO NO NO NO BC-AS-2-1 YES NO NO NO NO B-AS-2 YES NO NO NO NO 1 i 1 [B-1-lA B-i-lA 125V 1 -1 YES NO NO NO NO 1 is 3-1-18 B-1-1B 125V DC STATION BATTERY ON DC-2 YES NO NO NO YES NO OC-3 L DOC-3600AMP YES NO NO NO NO YES NO NO NO NO YES NO NO NO NO 1 YES NO NO NO NO 1 14 IOC-2AS DC-2AS 125V DC DISTRIBUTION PANEL YES NO NO NO NO 1 [ 14 IDC-2C OC-2C 125V DC DISTR PNL DC-2C 100AMP YES NO NO NO NO MCC-OC-2A 125V DC MCC DC-2A 600AMP YES NO NO NO MCC4-C-1A 125V DC MCC DC-lA (HPCI) 600AMP YES NO NO NO I MCC-OC-1B 125V DC MCC DC-lB (HPCI) 600AMP YES NO NO NO 1 14 IDC-ECCS-A DC-ECCS-A 24 VDC ECCS PNL (A) YES NO NO NO NO 1 1 14 IDC-ECCS-B DC-ECCS-8 24 VOC ECCS PNL (B) YES NO NO NO NO B-UPS-lA UPS-lA BATTERY BANK NO NO NO NOI B-UPS-lB UPS-IB BATTERY BANK NO NO NO 1 MCC-SA 480V AC MCC-SA - SWITCHGEAR ROOM (SIl) NO NO NO 1 0l IMCC-9C MCC-9C 480V ESS AC MCC-gC - DIESEL 1A ROOM (SII) YES NO NO NO YES I NO 11 jMCC-8 MCC-8C 480V ESS MCC-EC - DIESEL lB ROOM (SI) YES NO NO NO YES I NO 1 01 CC-8E MCC-6E 480V ESS AC MCC-SE - REACTOR BLDG YES NO NO NO YES I NO MCC-9D 480V ESS AC MCC-SD - REACTOR BLDG YES NO NO NO 1 01 MCC-so MCC-89B 480V ESS AC MCC-898 - REACTOR BLDG (SI) YES NO NO NO MCC-8B 480V ESS AC MCC-SB - REACTOR BLDG (SI) YES NO NO NO YES I I F I NO 1 01 IMOC-9SA MCC-89A 480V ESS AC MCC-9A- REACTOR BLDG(SII) YES NO NO NO NO 1 01 Mcc-9s MCC-EB YES NO NO NO YES NO 1 01 1MCC-8A MCC-EA YES NO NO NO NO I 02 BUS-8 BUS-8 YES NO NO NO NO 1 02 IBUS-9 BUS-9 480V /

• P (SIll YES NO NO NO NO

• 1 03 BUS-3 BUS-3 4KV -4160V SWITCHGEAR BUS NO.3 1200AMP (SI) YES NO NO NO NO 1 03 BUS-4 BUS-4 4KV-' YES NO NO NO NO 1 20 CP-82-2 YES NO NO NO NO 1 04 T-8-1A YES NO NO NO NO 1 04 T-9-IA IT-9-1A STATION SERVICE TRANS 41601480 BUSNO.9 YES NO NO NO NO 1 21 TK-4-IA CONDENSATE STORAGE TANK YES NO YES NO 0 NO x x 1 07 LCV-23-53 LCV-+/--5 HPCI/COND DRAIN TO CONDENSER YES NO YES NO NO X X 1 07 LCV-23-39 HPCI/COND PUMP TO RW 1 07 LCV-23-40 HPCI/COND PUMP TO RW 1 18 LS-23-98 HPCI/EXHAUSTSTEAM DRAIN POT LEVEL SWI1 1 08A V23-21 HPCI/FULL FLOW TEST MOV

Table 9.4.1- Base List Attachment VY-RPT-12-00019 Rev. 0 Paeqe5 of 24 SCREEN1 SCREEN 2 1 SCREEN 3 SCREEN 4 SQG CURRENT Undergo Maintains at Environment Decay SQUG Reactivity Pressue Inventory UNIT EQUIPMENT EQUIPMENTID SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Seismic Regular least one of Inside/ Nigh Temp/ Borated Heat Containment Replaced~l IPEEE Control Control Control CLASS 1? Configuration the 5 safety Outside? Humidity? Removal Inspections? System?

Functions (110) (TIH)

HPCIIFULL FLOWTEST MOV YES NO HPCIIGLAND SEALCONDENSER YES NO A FN-2-1A HPCI/GLAND SEALEXHAUSTER YES NO YES YES I NO x x 1 18 _t7 AFLOWTRIP YES NO NO DPIS-2-75 PS-3-76 liP' YES NO x X 1 18 DPI 3-77 YES NO YES NO NO X XI YES NO NO X YES NO X NO P4 YES YES NO NO0 X x x 1 07 PCV-23-50 PCV-23-50 HPCIILOCOOLING YES NO YES NO NO X 1 07 V23-SOA V23-SOA DOLING YES -NO YES NO NO X x 1 21 E-it-1A E-19-IA YES NO NO x x 1 SEA V23-25 V23-25 NO X X X

1 08A V23-17 V23-17 NO X x

X 1 18 FT-23-M2 FT-23-82 I AN.eMIIIR" lb YES NO YES NO NO 1 SEA V23-19 V23-19 YES NO YES NO T NO x X 1 S8A V23-20 V23-20 NO YES NO x L 1 18 PS-23-64-1 PS-23-84-1 YES 1 SEA V23-57 V23-57 YES NO NO 1 SEA V23-58 V23-58 HPCI/PUMP TORUS SUCTIONMOV YES NO YES NO x X 1 SEA V23-14 V23-14 HPCIISTEAM SUPPLY MOV YES NO Y7ES NO x x 1 SEA V23-15 V23-15 HPCIISTEAM HIPCIISTEAM SUPPLY MOV SUPPLY MOV YES NO YES NO I T I NO I~ i ~x X L 1 SEA V23-16 V23-16 YES NO YES NO 1 08 LCV-23-U4 LCV-23-54 HPCIrTURBINE DRAINPOT YES NO YES NO 1 18 PS.23-97A PS-23-97A HPCI/TURBINE EXHAUSTPRESSURE SWITCH YES NO YES NO x

'IT( YES 1 18 PS-23-978 PS-23-97B NO YES NO NO X x 1 10 SAC-1A SAC-1A YES NO NO NO NO 1 09 SAC-iS SAC-1S YES NO NO NO NO 1 10 SAC-i SAC-i YES NO NO NO NO 1 10 SAC-2 SAC-2 YES NO NO NO NO 1 1i1 SCH-1 SCH-1 NITI YES NO NO NO NO 1 11 SCH-2 SCH-2 Z.RHVAC/CHILLERMASTERUNIT YES NO NO NO NO 1 05 SPA1 SP-1 3RHVAC/CHILLER PUMP YES NO NO NO NO 1 05 SP-2 SP-2 .ZRHVAC/CHILLER PUMP YES NO NO NO NO 1 10 SACC-1A SACC-1A .RHVAC/CONDENSER CHILLERS YES NO NO NO NO 1 10 IACC-18 SACC-1S Z"RHVAC/CONDENSER CHILLERS YES NO NO NO NO 1 5 TEF-2 TEF-2 :7GA ROOMVENTILATION/EXHAU! YES NO NO NO NO 1 09 TEF-3 TEF-3 0G E ROOMVENTILATION/EXHAU! YES NO NO NO NO 1 10 RRU-5 RRU-5 COOLING 3WIECCSRMCOOLING YES NO NO NO NO 1 10 RRU-6 RRU-6COOLING 3WIECCSRMCOOLING YES NO NO NO NO 1 10 RRU-7 RRU-7COOLING sW/ECCS RM COOLING YES NO NO NO NO 1 10 RRU-8 RRU-8 COOLING YES NO NO NO NO 1 18 LT-3-231A LT-3-231A YES NO NO NO NO is LT-3-2318 YES NO NO 1L LT-3-2318 NO 18 LT-3-231C LT-3-231C YES NO NO 1 NO 18 LT-3-231D LT-3-231D YES NO NO 1 NO NO LT-3-231E YES NO NO 1 18 LT-3-231E NO NO NO NO NO NO NO 18 LT-3-231F LT-3-231F YES 18 LT-3-231G YES YES S,RHRPERMISSIVE YES x

Table 94.1- Base List 1 Attachment VY-RPT-12-00019 Rev. 0 fl, nf A Pa e 6 of 24 SCREEN11 SCREEN2 SCREEN3 SCREEN4 CURRENT Undergo Maintains at Environment Decay SQUG Reactivity Pressure Inventory UNn EQUIPMENT EQUIPMENT ID SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Seismic Regular least one of Inside/ High Temp' Containment CLASS Replaced?] IPEEE Outside? Humidity? Elorated Control Control Control Remuva 1? Configuration the 5 safety Inspections? Functions System' (110) (TIH) 1 18 T-2-03.52D !PT-2-3-520 .S, RHR PERMISSIVE YES NO NO ci 1 18 .T-107-SA LT-107-6A CSTILEVEL TRANSMITTER YES NO I H NO 1 18 -.T-07-SB LT-107-58 ;STILEVEL TRANSMITTER YES NO YES NO H NO

'T-10-101A PT-10-101A )W PRESSURE ECCS YES NO NO NO NO PT-10-101B YES NO NO NO NO PT-i0-i01C YES NO NO NO 1 1i 'T-1 PT-10-101D YES NO NO NO 1 18 -T-16-19-29A PT-16-19-29A EINDICATION YES NO NO NO NO 1 is PT-16-19-298 PT-16-19-298 EINDICATION YES NO NO NO NO 1 18 PT-5-12A PT-5-i1A ESCRAM YES NO NO NO NO 1 18 PT-5-12a PT-5-12B SCRAM YES NO NO NO 1 18 PT-5-12C PT--5-12C SCRAM YES NO NO NO 1 18 PT-S-12D PT-5-12D *M YES NO NO NO NO 1 19 TE-16-i19-30A TE-16-19-30A )W TEMP II YES NO NO NO T NO 1 19 TE-16-19-30E TE-16-19-30B NO NO NO T NO 1 20 TI-16-19-308 TI-16*19-30E NO NO 1 25 rR.16-19--45 TR-16t-t-4 NO NO 1 itt S-23-68A PS-23-68A HPCI/PCIS ON LOWSTEAMPRESSURE YES NO YES NO NO 1 is IPS-23-688 PS-23-68E HPCI/PCIS ON LOWSTEAMPRESSURE YES NO YES NO NO x x PS-23-68C HPCI/PCIS ON LOWSTEAMPRESSURE YES NO YES NO NO x x PS-23-68D HPCI/PCIS ON LOWSTEAMPRESSURE YES NO YES NO PS-2-128B REACTOR PRESS (HI)FOR RHR INTERLOCK YES NO NO NO 1 i 18 PS-2-128A PS-2-128A REACTOR PRESS (HI)FOR RHR INTERLOCK YES NO- NO NO NO FT-2-110A REACTOR F YES NO NO NO NO FT.2-11OB YES NO NO NO NO 18 FT-2-110C FT-2-110C YES NO NO NO NO FT-2-11OD YES NO NO NO NO 1 i18 ILT-2-3-72A T-2-3-72A RVLEVELFORRHR,DG, HPCI,RCIC,ADS, CS YES NO YES NO NO 1 18 ILT-2-3-728 JX-2-3-728 RVLEVELFORRHR,DG, HPCI,RCIC,ADS, CS YES NO YES NO- NO x J-2-3-72C [YES NO YES NO NO x JX-2-3-720 NO YES NO NO 1 J-2-M-7A NO YES NO NO 1 18 ILT-2-3476 J-2-3-578 RV LEVELSCRAM& PCIS YES NO YES NO NO 1 18 PLT-2-3-58A T-2-3-68A RV LEVELSCRAM&PCIS YES NO YES -NOF NO 1 I 18 T-2-3-586ti RV LEVELSCRAM& PCIS YES NO YES NO NO x 1 20 LT-2-3-588 PI-2-3-56A a1-23-56.SA RV PRESS. IND. YES NO NO NO 1 NO 1 20 JPI-2-3-568 2-3-568 RV PRESS. IND. NO YES NO NO x 1 18 IPT-2-3-56A 'T-2-3-56A RV PRESSURE ECCS NO YES NO NO 11 18 JPT-2-3-568 IT-2-3-568 RV PRESSURE ECCS YES NO NO NO NO x RV PRESSURE ECCS YES NO NO NO NO IT-2-3-56D RV PRESSURE ECCS YES NO NO NO NO

-T-2-3-566D RV PRESSURE SCRAM YES NO NO 1 18 IPT-2-3-558 RV PRESSURE SCRAM YES NO NO 1 18 PT-2-3-55C 'T-2-3-WS RV PRESSURE SCRAM YES NO NO NO NO I PT-2-3-55D IT-2-3-550 RV PRESSURE SCRAM YES NO NO NO NO

.T-2-3-73A RV SHROUD LEVEL,CONT SPR YES NO NO NO NO RV SHROUD LEVEL,CONT SPR YES NO NO NO NO 21 20 ELIL--3-91A .1-24-91aA RV WTR LEVELIND. YES NO NO NO NO 1 20 LI2.3418it 2-3-918 RV WTR LEVELIND. YES NO NO NO No YF.% N(} N() N(] H N[)

---1 18 IPS-104-53A SW/PUMP A PRESSUR E SWITCH YES NO NO

Attachment B VY-RPT-12-00019 Rev. 0 Pao 7 of 24

-T I V 1 1- .. I- - - r----------r -----.. - 7 1~ 'I V

'CREN11 SCREEN 2 1 SCREEN 3 SCREEN 4 SQUG SQG CURRENT Undergo Maintains at Environment Decay UNIT EQUIPMENT EQUIPMENT ID SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Reactivity Pressure Inventory eaty Containment Seismic Regular least one of Insidel High Tempi CLASS Replaced?I IPEEE orated Control Control Control Removal 1? Configuration the 5 safety Outside? Humidity?

Inspections? Functions Systeml (110) (TIH)

NO NO NO H NO 1 NO NO NO 1 18 IPS-104-530 IPS-104-530 SW/PUMP D PRESSURE SWITCH NO NO NO 1 20 IPI-16-19-36A JPI-16-19-36A YES NO NO NO l 20 IPI-16-19-36B P1-r-16-19-368 NO YES NO NO NO 18 is PT-16-19-36A IPT-16-19-36A NO NO NO NO 1 18 IPT-16-19-368 IPT-16-19-368 NO NO NO NO I-1 20 fLI-PI-16-19-12A ILI-I-16-19-12A TORUS WTRLEVEL/DWPRESS. IND. NO NO NO 1 19 ITE.16-19-33A TE-16-19-33A TORUS WTRTEMP. IND. YES NO NO NO 1 18 LT-16-19-10A  ?.LEVEL YES NO NO NO NO 1 18 ILT-16-19-10B YES NO NO NO NO 1 20 LII-I-6i 9-1128 NO NO NO NO 1 19 ITE-16-19-33C =TE-16-19-13C - TORUS WTR. TEMP. IND. NO NO NO NO 1 20 TI-16-19-33$A TI-16-19-S3A TOUSU WIR. TEMP, IND, YES NO NO NO NO 1 20 T1-16-199*3C TORUS WTR. TEMP. IND. NO Ti-16-19-33C YES NO NO NO I 08A V2-74

/2-74 YES NO YES NO T NO x 1 08A V2.77 /2-77 YES NO YES NO NO x 1 07 V2-80A /2-80A YES NO YES NO NO x 1 07 1V2-801 /2-SOB YES NO YES NO NO YES NO YES NO T NO YES NC) YES NI) T N* Y UMULATOR TS N YESIT VX NO _ I NO ACCUMULATOR YES NO YES NO T NO x PPLY ACCUMULATOR YES NO YES NO T NO x N SUPPLY ACCUMULATOR YES NO YES NO T " NO x YES NO YES NO T NO x 1 YES NO YES NO NO T x 1 07 1V2-86C /2-86C MAINSTEAM/OUTBOARO MSIV YES NO YES NO T IS VZ5 1 07 JV2-t6U V2-860 MAINSTEAM/OUTB3ARD MSIV YES NO YES NO T 1 21 1S-2-6A 5-2-6A MAINSTEAM/OUTBOARD MSIVINST AIRSUPPLY ACCUMULATOR YES NO YES NO T NO 1 21 S-2-6B S-2-EB MAINSTEAM/OUTBOARD MSIVINSTAIRSUPPLY ACCUMULATOR YES NO YES NO I T NO 1 21 JS-2-6C MAINSTEAM/OUTBOARD MSIVINSTAIRSUPPLY ACCUMULATOR YES NO YES NO T NO 1 21 S-2-6D 5-2-SO MAINSTEAM/OUTBOARD MSIVINSTAIRSUPPLY ACCUMULATOR YES NO YES NO T NO 1 07 RV-2-71A "RV-2-71A 'MAi~l*IN SAM/fI:ELII:FI VALVE:: YES NO YES NO T NO 1 07 RV-2-716 RV-2-718 MAINSTEAM/RELIEF VALVE YES NO YES NO T NO x 1 07 RV-2-71C IYES NO YES NO T NO x 1 07 RV-2-710 1 0 E-1000-3 NO YES NO T NO I - x MAKE-UP GAS TRIMHEATER NO YES NO x 1 21 ITK-55-1A TK-55-1A N2AIRRECIEVER YES NO YES NO x PCV-1-156-75 E REGULATOR YES NO YES NO NO X 3-2-13A CCUMULATOR YES NO YES NO T NO 3-2-138 YES NO YES T NO x NO 1 21 IS-2-13C S-2-13C YES NO YES 1 21 S-2-13D YES YES NO YES NO YES X

Table 9.4.1- Base List Attachment B VY-RPT-12-00019 Rev. 0 Pen A of 24

-T r T T rrr~--,- I n r -r SCREEN11 SCREEN 2 I SCREEN 3 SCREEN 4 SQUG Undergo Maintains at Environment Decay CURRENT cn,,u~T n SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Reactivity Pressure Inventoy HeatI UNn EQUIPMENT Seismic Regular least one of Inside1 Temp Containment CLASS 1? Configuration theS safety IReplaced?l IPEEE Outside? Humidity? Boradte Control Control Control Removal Inspections? Functions (1lO) (TIH) System?

YES NO YES NO NO x YES NO YES NO NO x x YES NO NO 1 1 08A IV10-65A V10-65A RHR/HEAT XC BYPASS MOV YES NO NO x x 1 I 08A IV10-656 VIO-5B RHR/HEAT XC BYPASS MOV 4YES NO YES NO NO V10-27A CTIONMOV YES NO YES NO NO x

/10-27B NO YES NO NO x

/10-16A NO x 1 08A /V10-16B V10-16B :ZHR/MIN-FLOWMOV NO 1 08A V10-15A /10-15A :HRJRECIRC SUCTIONMOV YES NO YES NO x 1 /10-15C YES NO YES NO NO 1 V10-158 IYES NO YES NO NO x 1 V/O-15D NO YES NO NO x 1 SEA IVIO-34A VIO-34A NO YES NO NO _x 1 SEA v10-34E V10-348 RHRITORUS COOLINGMOV NO NO YES YES NO x 1_ SEA V10-39A VIO-39A RHR/TORUS COOLINGMOV NO YES NO YES NO _x 1 SEA V10-398 V,10-398 RHR/TORUS COOLINGMOV VIO-38A YES NO YES NO NO x

_L S8A V10-38A RHR/TORUS SPRAY MOV YES NO NO x I 08A V10-38B RHRITORUS SPRAY MOV V10-388 YES NO NO 1 0SA V10-13A VI0-13A RHRITORUS SUCTIONMOV YES NO YES NO NO 1 0SA V10-130 V10-130 RHRPTORUS SUCTIONMOV YES NO YES NO NO 1I 07 PCV-104-69A PCV-104-69A RHRSW/RHRSW A PRESSURE YES NO NO NO NO 1 07 PCV-104-698 PCV-104-696 RHRSWIRHRSW B PRESSURE NO NO NO 1 06 P-8-1A P-8-1A RHRSW/A RHRSW PUMP YES NO NO 1 06 P-8-18 P-8-1B RHRSW/B RHRSW PUMP YES NO YES NO NO 1 06 IP-8-1C P-S-1C RHRSW/CRHRSW PUMP YES NO YES NO NO RHRSW/DRHRSW PUMP YES NO YES NO NO x RHRSW/SW SUPPLY MOV YES NO YES NO NO x x RHRSW/SW SUPPLY MOV YES NO YES NO 1 1 07 ISP-70-3A SP-70-3A tACKWASHFLOWCONTROL YES NO NO NO NO 1 07 ISP-70-36 SP-70-38 tACKWASHFLOWCONTROL YES NO NO NO I H NOI 1 06 P.7-1A P-7-1A SWIASW PUMP YES NO NO NO H NO 1 07 FCV-104-17A FCV-104-17A SWIATRAVELLING YES NO NO NO H NO 1 06 IP-7-1B P-7-1l SW/BSW PUMP YES NO NO NO H NO 1 07 -FCV-104-17B FCV-104-17B 3W/BTRAVELLING NO H NO YES NO NO I 0L C7-1-C P-7-1C SW/CSWPUMP YES NO NO NO H NO 1 07 itV-104-17C FCV-104-17C 1LVALVE H NO YES NO NO NO P-7-1D YES NO NO NO H NO FCV-104-17D YES NO NO NO NO 1 57 PCV-1E4-2EA FCV-104-28A YES NO NO NO NO 1 07 'CV-!_4-28B FCV-104-288 SW/DGCOOLING NO YES NO NO NO li~-il(I- YES NO NO NO NO TK-67-1S ,W/DG-EEXPANSIONTANK YES NO NO NO NO FCV-104-1: SW/ETRAVELLING SCREEN CONTROL VA_ YES NO NO H NO J- j0 FC-104-V70-19A SWITURB BLDGISOLMOV YES NO V70-198 SW/TURB BLDGISOLMOV YES NO II 8SA JV70-20 V70-20 SWrTURB BLDGISOLMOV YES NO NO NO NO C-3-1A YES NO NO NO NO NO NO NO NO0 NO NO NO I I I NO I -A I

Table 9.4.1- Base List Attachment B VY-RPT-12-00019 Rev. 0 Pace 9 of 24 SCREEN1 SCREEN2 SCREEN3 SCREEN4 SQUG CURRENT Undergo Maintatns at Environment Decay UNITEQUIPMENT CURRENT SSEL EQUIPMENTID EQUIPMENT DESCRIPTION Seismic Regular least one of Inside Reactivity Pressure Inventory Heat Containment Outside? Humidity? Sysatem? otolCnrl oto CLASS 1? Configuration the 5 safety Replaced? IPEEE side! Hgh.Tamp! Borated Control Removal Inspections? Functions (110) (TI H) System?

1 05 P-85-1A P-85-1A HPCIIAUX OIL PUMP YES NO YES NO I NO X X 1 088 LSO-23-53 LSO-23-53 HPCI/COND DRAINTO COND YES NO YES NO I NO X x 1 05 P-87-lA P-87-IA HPCI/CONDENSATE PUMP YES NO YES NO I NO X X x 1 05 TU-1-IA TU-1-1A HPCIIHPCI TURBINE YES NO YES NO I NO X X 1 07 -HPCIITURBINECONTROL VALVE YES NO YES NO I NO X X 1 07 HPCI/TURBINE STOP VALVE YES NO YES NO I NO X X 1 0 AOD-113-1 AOD-113-1 CRHVAC/ISOLATION DAMPER FOR SAC-lA YES NO NO NO I NO 1 11 CRHVACILOW AMBIENTTEMP COND PRESS CONTROLPACKSACC-1A YES NO NO NO I NO 1 11 CRHVAC/LOW AMBIENTTEMP COND PRESS CONTROLPACKSACC-1B YES NO NO NO I NO 1 10 CRHVAC/SAC-1A COOLING COIL YES NO NO NO I NO 1 10 CRHVAC/SAC-1A FILTERSECTION YES NO NO NO I NO 1 10 -* CRHVAC/SAC-1A HEATINGCOIL YES NO NO NO I NO 1 0 DO-1A-INTAKB DOG-A-INTAKE DGROOMVENTILATION/DG ROOMA LOUVER YES NO NO NO I NO 1 0 POS-113-2011 POS-113-2011 DGROOMVENTILATION/DG ROOMA LOUVEROPERATOR YES NO NO NO I NO S1 0 IPOS-113-20XOOXIPOS-113-20XXX )G ROOMVENTILATION/DG ROOMB LOUVEROPERATORS(6 TOTAL) YES NO NO NO NO It 0OG-l )G ROOMVENTILATION/OG ROOMB LOUVERS (6 TOTAL) YES NO NO NO 0 NO 3WIRRU-5FAN YES NO

,W/RRU-5MOTOR YES NO I RRU-6 FAN SWIRRU-6FAN YES NO NO 1 10 1RRU-6MOTOR RRU-6 MOTOR W/IRRU-6MOTOR YES NO NO NO NO 10 IRRU-7FAN YES NO NO I NO YES NO YES NO NO INO 1 10 IRRU- MOTOR IRRU-8MOTOR SW/RRU-8 MOTOR YES NO i INO 1 I 0 06 P-8-lA COOL COIL P-8-1ACOOL COIL RHRSW/P-8-1 LINGCOIL YES NO YES NO NO x NO YES NO NO x NO NO NO NO 1 088 SE-3-31A CRD/SCRAM DISCHARGE VOLUMEVENT/DRAIN SOV YES NO NO NO x 1 088 SE-3-318 SE-3-316 'RD/SCRAM DISCHARGE VOLUMEVENT/DRAIN SOV YES NO YES NO NO x 11 088 SO-3-1 SO-3-117-XX. CRD/SCRAM PILOT VALVES (89) YES NO YES NO NO x SO-3-118-XX. RD/SCRAM PILOT VALVES(89) YES NO YES NO NO LSO-108-2A FUELOIL/DGDAYTKFILL YES NO NO NO NO LSO-108-28 *UELOIL/DGDAYTKFILL YES NO NO NO NO 1 1 08e ILSO-108-3 LSO-108-3 -UELOILI RTKFILL YES NO NO NO H NO 1 0813 ISE-23-0A YES NO YES NO NO X X YES NO YES NO X YES NO YES NO FI-23-1 YES NO YES NO 11 S8B LSO-23-40 LSO-23-40 HPCIGOS.CONDDISCH TO RW YES NO YES NO I NO x x See LSO-23-39 LSO-23-39 HPCIG.S. COND PP DISCH YES NO YES NO I NO X x 1 20 _ ES-23-110 8ES-23-110 HPCIINSTPWR SUPPLY YES NO YES NO I NO X x HPCISO RT CONV-FLOW NO YES NO I NO HPCI/DCIAC INVERTER NO YES NO I NO 1 0 23-1 SE-23-1 HPCI/REMOTE TURBINETRIP YES NO YES NO I NO x 1 0 1T-2301A TS-23-101A HPCI/STEAM LEAKDETECTOR YES NO YES NO I T NO -T x 1 0 ITS-23-1018 TS-23-101B YES NO YES NO I NO X X TS-23-101C 1 TS-23-1010 TS-23-1028

Table 9.4.1- Base List 1 Attachment VY-RPT-1 2-00019 Rev. 0 Paae 10 of 24 5CREEN1I SCREEN 2 1 SCREEN 3 SCREEN 4 SQUG Undergo Maintaiins at Environment CURRENT Reactivity Pressure Inventory Heat UNfl EQUIPMENT EQUIPMENT ID SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Seismic Regular least one of Inside/ HIghTemp/ Control Control ContR Cema Containment Replaced? IPEEE Borated emol CLASS 1? Configuration the 5 safety Outside? Humidity?

System?

Inspections? Functions (110) j (TIH) 1 0 rS-23-102C HPCI/STEAM LEAKDETECTOR YES NO YES NO NO X X HPCI/STEAM LEAKDETECTOR YES NO YES NO x x HPCIISTEAM LEAKDETECTOR YES NO NO _x X TS-23-103A HPCI/STEAM LEAKDETECTOR YES NO NO x x 4YES NO 1 0 ITS-23-1038 TS-23-1038 HPCI/STEAM LEAKDETECTOR YES NO NO _x x 1 0 TS-23-103C TS-23-103C HPCI/STEAM LEAKDETECTOR YES NO YES NO NO x x 1 0 TS-23-1030 TS-23-1030 HPCI/STEAM LEAKDETECTOR NO YES X x I~

1 0 TS-23-104A TS-23-104A HPCI/STEAM LEAKDETECTOR NO x 1 0 TS-23-1048 TS-23-104B HPCI/STEAM LEAKDETECTOR NO _x 1 0 TS-23-104C TS-23-104C HPCI/STEAM LEAKDETECTOR YES NO NO I NO x 1 0 TS-23-104D TS-23-1040 HPCI/STEAM LEAKDETECTOR YES NO YES NO NO x x 1 20 LSL-107-SA LSL-107.SA CST/LEVEL SWITCHES YES NO YES NO NO x I 1 20 LSL-107-58 LSL-10-58 CSTILEVELSWITCHES YES NO YES NO NO 1 20 LR-23-73 LR-23-73 CST/RECORDER YES NO YES N NO NO YES I NO 1 088 SE-2-80A-1 SE-2-80A-1 INBOARD MSIVSOLENOID AC/DC YES T NO x 1 088 SE-2-80B-1 SE-2-808-1 INBOARD MSIVSOLENOID AC/DC YES NO YES I NO T NO x 1 088 SE-2-80C-1 SE-2-BOC-1 iv / YES NO YES I NO T NO x 1 08s 5E-2-80D-1 SE-2-SOD-I YES NO T NO 1 08B FSO-2-39 FSO-2-39 YES NO T NO x 1 088 FSO-2-40 FSO-2-40 RECIRC/SAMPLE LINEOUTBOARD ISOLATION YES NO NO NO 1 088 SE-2-71A SE-2-71A MS" YES NO YES NO T NO x 1 088 SE-2-718 SE-2-718 YES NO YES I NO T NO x I 088 SE-2-71C SE-2-71C YES NO T NO 1 088 SE-2-71D SE-2-71D YES NO T NO x X

1 088 SE-2-86A-1 SE-2-86A-1 MS/OUTBOARD MSIVSOLENOID ACIDC YES NO NO T NO X T NO 1 088 SE-2-868-1 SE-2-868-1 ILE YES NO YES NO x 1 088 SE-2-86C-1 SE-2-86C-1 YES NO YES NO T NO 1 088 SE-2-86D-1 SE-2-86D-1 NO YES NO T 1 07 FCV-10-160 FCV-10-160 NO YES NO 1 085 P$0-10-160 FSO-10-160 RHR/SYS PROCESS SAMPLE SOLENOID FCV-10-160 NO YES NO NO 1 088 FSO-104-17A FSO-104-17A SW/ATRAVELLING SCREEN FL( 1-- YES NO NO D PCV-104-17A NO H NO D FCV-104-176 ND YES NO NO NO So-O- 1: 7C9 :10417B NO 10S8 NO NO H NO NO NO NO NO SW/DG A FLOWCONTROLLER NO NO NO NO 1 18 PC-104-288 FC-104-288 SW/DG B FLOWCONTROLLER YES NO NO NO YES NO 1 088 FSO-104-28A FSO-104-28A SW/DG COOLING FCV-104-28A YES NO NO Y1E-S NO NO 1 08B FSO-104-28B FSO-104-28B YES NO NO Y7ES NO NO 1 088 FSO-104-17E FSO-104-17E NO NO 1 088 NG-128 NO-128 CACSOV AIRISOLATION (INBD)INJECTIONTO TORUS PNLB YES NO NO 1 O0A VG-22A VG-22A CADMOVVENTISOLATION(OUTBD) YES NO YES NO NO 1 S8A VG-22B VG-22S CADMOVVENTISOLATION(OUTED) YES NO YES NO NO x 1 08B NG-11A CADSOVAIR ISOLATION (OUTBD) COMPR DISCHARGE PNLA YES NO YES NO NO _x 1 088 NG-13A CADSOV AIR ISOLATION (INBD)INJECTIONTO DWPNLA YES NO YES NO x NO 1 088 NG-13B CADSOVAIR ISOLATION (INBD)INJECTIONTO DWPNL B YES NO YES _x X

1 088 NG-12A NG-12A CADSOVAIR ISOLATION (INSD) INJECTIONTO TORUS PNLA YES NO -NO NO YES x 1 088 NC-118 NG-11B CADSOVAIR ISOLATION (OUTED) COMPDISCHARGE PNLB 1- YES NO NO NO[

1 088 VG-26 AMPL Y YES NO -NO NO

_x

Table 9.4.1- Base List 1 Attachment B VY-RPT-12-00019 Rev. 0 Pae11 nf 24

-,~~~~Pg - - V _ 11 of 24I-SCREEN1 SCREEN2 t SCREEN3 SCREEN4

___ I SQUG CURRENT Undergo Maintains at Environment Decay UNITEQUIPMENT EQUIPMENTI EQUIPMENT DESCRIPTION Reactivity Pressure Inventory Heat EQUIMENTIDSSEL EQUIPMENTID Seismic Regular least one of Inside/ High Tempi Borated Containment CLASS 1? ReplacedI IPEEE Control Control Control I Removal Configuration the 5 safety Outside? Humidity?. System?

Inspections? Functions (1/O) (TIH)

FSO-109-75A-4 E ISOlU t..t - t t-~-t 4 4 4 * +-

dO-gB.7A-

'LY PNL A YES NO YES NO NO x S PNLB YES NO YES NO NO X VG-9A YES NO NO x

-S50109-76A NO x 1 1 088 IFSO-109-768 :SO-105.766 SAMPLESYSTEM ISOLU NO -x 1 07 IV20-94 /20-94 DRYWELL I ')AOV YES I NO I YES NO NO x 1 07 V20-95 DRYWELL I AOV YES NO YES NO NO 1 07 IV20-83 NO YES NO NO x 1 0 jL20, NO YES NO NO x 1 07 CACSUCTIONAOV NO YES NO NO 1 1 07 IV72-38B /72-38B CACSUCTIONAOV YES NO YES NO NO SB-11 q (INBO) YES NO YES NO NO x X

$8-12 X YES NO YES NO NO YES SB-a0 NO I NO x 1 1 07 loB-a YES NO 1 1 07 PFCV-2-39 FCV-2.99 RECIRC/SAMPLE LINEINBOARDISOLATION NO YES NO YES x 1 07 FCV-2-40 FCV-2-40 RECIRC/SAMPLE LINEOUTBOARD ISOLATIOI YES NO YES NO NO 1 07 SB-16-19-7A SE-16-19-7A 18" DRYWELL VENTAOVISOLATION (INBD) YES NO YES NO NO x 1 07 SB-16-19-7B SE-16-19-7B 18" TORUS VENTAOVISOLATION (INBD) YES NO YES NO NO x 1 07 SB-16-19-6A SB-16-I-6A 3" DRYWELL VENTAOVISOLATION (INBD) YES NO YES NO 1 07 SB-16-19-6B SB-16-19-68 3"TORUS VENTAOVISOLATION (INBD) YES YES NO YES NO x X

1 07 SB-15-19-9 SB-16-19-9 AIRPURGE SUPPLY ISOLATION(OUTBD)AOV YES NO NO I NO I 1 088 V16-20-22A V16-20-22A N2 MAKEUPISOLATION (INBD)SOLENOID YES NO YES NO NO x 1 08B V16-20-228 V16-20-22B N2 MAKEUPISOLATION (INBD)SOLENOID YES NO YES NO NO x 1 08B V16-20-20 V16-20-20 N2 MAKEUPISOLATION (OUTED)SOLENOID YES NO YES NO x 1 07 SB-16-19-23 SB-16-19-23 N2 PURGE SUPPLY ISOLATION (OUTBD)AOV YES NO- YES NO NO 1 07 SB-16-19-11A SB-16-19-11A YES YES NO I NO 1 07 SB-16-1-9118 SB-16-19-11B YES NO YES NO NO x x 1 07 SB--16 SB-16-19-6 YES NO YES NO NO 1 07 SB-16-19-7 Se-16-19-7 DLATION YES NO YES NO NO x 1 07 SB-16-19.- SB-Id-19-8 AOV YES NO NO0 YES NO 1 07 SB-16-19-10 SB-16-19-10 YE-S YES NO YES NO .x 1 08A V'70-117 V70-117 YES NO YES NO x 1 08A V13-15 V13-15 RCICISTEAM SUPPLY MOV YES NO YES NO 1 08A V13-16 V13-16 L VALVE MOV NO- YES NO I NO 1 08A V10-57 Vi1-57 YES NO YES NO NO 1 08A V10-66 V10-66 YES NO YES NO I NO x 1 08A V10-17 V10-17 YES NO YES NO Ix 1 08A '/10-18 Vi-18 RHRISDCVALVE YES NO YES NO I T 1 /12-15 ATION MOV YES NO YES NO I T 1

1 1

1 0 ~V2-27A V12-18 V2-96A

)LATION MO YES YES YES NO NO NO NO YES YES NO NO NO I T

T NO NO NO

[ x V2-27A YES x 1 V2-2aA FDW/INBOARD CHECKVALVE YES NO x 1

0 V2-2SB V2-28B YES NO YES I NO I _ T NO x 1 NO YES YES NO I I __ NO NO x I NFO-YES x 1 DPT-2-116C x 1 is )PT-2-1160 0PT-2-1160 1ISISTEAM DIFF PRESSURE TRANSMITTER A x

Table 9.4.1- Base List 1 Attachment VY-RPT-12-00019 Rev. 0 Paae 12 of 24 7 T r r- S---I -- - r r -r SCREEN11 SCREEN 2 1 SCREEN 3 SCREEN 4 SQUG CURRENT Undergo Maintalns at Environment Inventory Decay UNII EQUIPMENT QUIPMENT1 SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Reactivity Pressure Heat Containment Seismic Regular least one of Inside/ High Temp/ Control Control IPEEE Borated CLASS 1? Conficuration t 8Se safety Replaced?I Outside? Humidity?

Cl Removal Inspections? Functions System?

(110) (TIH) 1 DPT-2-117A MS/STEAM DIFFPRESSURE TRANSMITTER E YES NO YES NO NO x 0PT-2-1178 MSISTEAM DIFFPRESSURE TRANSMITTER B YES NO YES NO I NO - x 1

1 DPT-21 17C MS/STEAM DIFFPRESSURE TRANSMITTER B YES NO YES 18 JDPT-2-1170 DPT-2-l 17D MS/STEAM 0IFF PRESSURE TRANSMITTER B YES NO YES x 1 18 IDPT-2-11aA DPT-2-118A MS/STEAM DIFFPRESSURE TRANSMITTER C YES NO YES NO I NO 1 18 DPT-2-1188 DPT-2-1188 MS/STEAM DIFFPRESSURE TRANSMITTER C YES NO YES NO NO x 1 18 DPT-2-118C DPT-2-118C MS/STEAM DIFFPRESSURE TRANSMITTER C YES NO YES NO NO x 1 18 DPT-2-118D DPT-2-118D MS/STEAM DIFF PRESSURE TRANSMITTER C YES NO 1 18 OPT-2-119A DPT-2-119A MS/STEAM 0IFF PRESSURE TRANSMITTER D YES NO X x

1 18 DPT-2-1198 DPT-2-1159 MS/STEAM DIFF PRESSURE TRANSMITTER D YES NO YES NO I I F 1 NO I xX 1 18 OPT-2-119C 0PT-2-119C MS/STEAM DIFF PRESSURE TRANSMITTER D YES NO YES NO NO 1 18 OPT-2-119D DPT-2-1190 MS/STEAM 0IFF PRESSURE TRANSMITTER D YES NO YES NO NO x 1 0 V70-113 V70-113 RBCCW/RC ISOLATION CHECKVALVE YES NO NO 1 18 PS-13-87A PS-13-87A RCIC/LOW STEAMPRESSURE ISOLATION YES NO NO x 1 18 PS-13-878 PS-13-878 RCIC/LOW STEAMPRESSURE ISOLATION YES NO YES NO NO 1 18 PS-13-87C PS-13-87C RCIC/LOW STEAMPRESSURE ISOLATION YES NO YES NO NO x 1 18 PS-13-87D PS-13-87D RCIC/LOW STEAMPRESSURE ISOLATION YES NO YES NO NO x 1 0 TS-13-79A TS-13-79A RCIC/STEAM LEAKDETECTION YES NO 1 0 TS-13-80A TS-13-80A RCIC/STEAM LEAKDETECTION YES NO x 1 0 TS.13-81A TS-13-81A :CIC/STEAM LEAKDETECTION YES NO YES NO I T NO 1 0 TS-13-82A TS-13-82A :CIC/STEAM LEAKDETECTION YES NO YES NO T NO x 1 2 PI-104-T0A FI-104-70A tHRSW/PUMP A COOLINGWATERFLOW INDICATOR YES NO NO NO x 1 F1-104-708 IF-104-708 RHRSW/PUMP 8 COOLINGWATER FLOW INDICATOR YES NO NO 1 0 FI-104-70C FI-104-70C :HRSW/PUMP C COOLINGWATERFLOWINDICATOR YES NO NO 1 0 FI-104-700 FI-104-700 RHRSW/PUMP D COOLINGWATERFLOWINDICATOR YES NO YES NO NO 1 Ij 58A VI0-184 VIO-184 RHR/RHRTORHRSW TIE YES NO YES NO NO x VIO-183 :HR/RHR TORHRSW TIE YES NO YES NO NO x F-24-18 G0STARTAIR/FILTER B YES NO NO 1 LPw1AH OG"A"LIGHTING PNL YES NO NO 1 04 IT-LP-1AH r-LP-1AH TRANSFORMER FOR LP-1AHDG A YES NO NO NO I I I NO I 1 14 jLP-1AJ LP-1AJ  :)G'B" LI ",IL YES NO NO NO NO 1 04 T-LP-P1AJ T-LP-1AJ YES NO NO NO NO 1 1 AC-P- AC-OP-S YES NO NO ND NO 1 14 PP-AL LP-1L YES NO NO NO NO 1 14 JPP-9A PP-9A 240/120VACPOWER PANELATMCC-9AFOR SBGT YES NO NO NO NO 1 14 ICP-82-1 OP-82-1 L YES NO NO NO NO 1 14 CP-82-3 CP-82-3 Ht YES NO NO NO NO 1 20 CRP 9"03 CRP 9-03 NO NO NO NO 1 20 CRP 9-04 CRP9-04 NO NO NO NO 1 20 JCRP 9-05 ONTROL ROOMPANEL CRP 9-5 YES NO NO NO NO 1 20 CRPg-"6 CRP 9-06 ,ONTROLROOMPANEL YES NO NO NO NO 1 20 ORP9-07 ,ONTROLROOMPANEL YES NO NO NO NO CRP9-08 ORP9-08 .ONTROLROOMPANEL YES NO NO NO I NO 1 2 20 CRP 9-10 CRP 9-10 .ONTROLROOMPANEL YES NO NO NO 1 20 lCRP 9-12  ;RP 9-12 .ONTROLROOMPANEL YES NO NO NO 1 20 CRP 9-14 ORP9-14 ,ONTROLROOMPANEL YES NO INO NO NO 1 20 CRP 9.15 cRP 9-15 ONTROLI YES NO NO NO NO 1 20 CRP 9A7 x 1 20 CRP 9-19 x 1 __20 CRP 9-20 9LROOMPANEL

Table 9.4.1- Base List 1 Attachment VY-RPT-12-00019 Rev. 0 Pace 13 of 24

-, 1 I ,vrrzr-r 7 r r~r r r'-------

3CREEN11 SCREEN 2 SCREEN3 SCREEN 4 SQUG Undergo Maintainsat Environment CURRENT Reactivity RectviyPrssr Inetr Decay Heat Containment UNf EQUIPMENT CLASS EQUIPMENT EL EQUIPMENTID EQUIPMENT DESCRIPTION Seismic Regular 1? - Configuration least one of the 5 safety IReplaced? Inside/

Outside? HighTemp/

Humidity? Borated System?

Control Control Control emoval Inspections? Functions (110) (TIH) 1 20 ICRP9-22 CONTROL ROOMPANEL YES NO NO NO NO CONTROL ROOMPANEL YES NO NO CONTROL ROOMPANEL YES NO CONTROL ROOMPANEL YES NO 1 20 CRP9.30 CRP 9-30 CONTROL ROOMPANEL 4YES N NO NO NO 1 20 CRP9-32 CRP 9-32 CONTROL ROOMPANEL YES NO NO NO NO 1 20 CRP9-33 CRP 9-33 NO NO NO I NO 1 20 CRP9-39 CRP 9-39 NO 1 20 CRP9-41 CRP9-41 L NO 1 20 CRP9-42 CRP 9-42 CONTROL ROOMPANEL YES NO NO NO 1 20 CRP9-45 CRP9-45 CONTROL ROOMPANEL YES NO NO NO NO 1 20 CRP9-46 CRP 9-46 CONTROL ROOMPANEL NO NO NO NO 1 20 CRP9-47 CRP9-47 CONTROL ROOMPANEL NO NO NO 1 20 CADPNLA CADPNLA CONTROL ROOMPANEL NO NO NO 1 20 CADPNLB CADPNLB CONTROL ROOMPANEL YES NO NO NO INO 1 20 PPP-A-1 PPP-A-1 L PNLA-1 YES NO YES NO NO x 1 20 PPP-A-2 YES NO YES NO NO x 1 20 RPP-B-1 YES NO 1 20 PPP-.-2 YES NO DOGVOLTREG CAB 0G RMa VOLTAGE REGULATOR CAB YES NO NO NO YES NO

• 1 20

• 1 20 NEUTRAL TRANSCAB DGRMA NEUTRAL' YES NO NO NO YES NO 1 20 CONT BOARD YES NO NO YES NO NO YES 1 20 ENGINSTPNL NO YES 1 20 ENGCONTACTOR CAB NO YES 1 17 DOGSKID DOGRM A EQUIP SKID NO NO NO ND 1 iS LSL-108-13A LSL-108.13A DIESEL FUELOILTRANSFER F YES NO NO NO NO 1 18 LSL-1OS-13B LSL-108-13B DIESEL FUELOILTRANSFER F YES NO NO NO NO I 1 18 LSH-108-12A LSHI108-12A DIESEL FUELOILTRANSFER F YES NO 1 1 LSHI-108-12B LSH-108-12B DIESEL FUEL OILTRANSFER F YES NO 1 18 PS-23-1 PS-23-1 HPCI/AUX OILPUMP START YES NO NO NO 1 18 LSH-23-90 LSH-23-90 HPCI/MS C 3 CONTROL YES NO YES NO NO x x 1 08E FS0-O10-161 FP0-10-161 YES NO YES NO NO x PS-2-134A YES NO NO x PS-2-1348 YES NO NO xX PS-2-134C MSLINEPRESS YES NO NO x 1 1 18 IPS-2-1340 PS-2-134D YES NO YES NO I NO x 1 I 18 'S-2-11A PS-2-11A YES NO YES ND NO x S-2-11B YES NO NO x YES NO xX YES NO X 1 PS-10-106A RHR PP A DISCHPRESS INTERLOCK YES NO YES NO NO 1 19 18 Ps-IA rs,-1*15NIL PS-10-1058 RHR PP B DISCHPRESS INTERLOCK YES NO YES NO NO 1 18 PS-1j10SC PS-10-10-C RHR PP C 01SCHPRESS INTERLOCK YES NO YES NO NO x 1 18 PS-10-1050 PS-10-105D RHR PP 0 OISCHPRESS INTERLOCK YES NO YES NO NO t 18 PS-0-10512 PS-10-105E RHR PP A OISCHPRESS INTERLOCK NO YES NO NO PS-10-lOSF YES 1 is PS-10-105F RHR PP 6 DISCHPRESS II NO YES NO NO YES 1 18 Ps-10-105ZF Ps-i$-i-05G -YES NO YES NO NO X

1 18 IPS-10-105H YES NO YES NO

Table 9.4.1- Base List 1 Attachment B VY-RPT-1 2-00019 Rev. 0 Po14 rnf?4

-F T~Pg 1-4 of 24I SCREEN11 SCREEN2 1 SCREEN3 1 SCREEN4 5QG CURRENT + ..--

Environment I I Decay SQ'UG Undergo Maintains at Reactivity UNIl EQUIPMENT SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Pressure Inventory De c n n Seismic Regular least one of CLASS Replaced! IPEEE Inside/ High Tempt Borated Co0 o Ctrol Control ControlReoHeat Remva Containment 1? Configuration the 5 safety Outside? Humidity?

Inspections? Functions System?

(110) (TIH)

SE-1-125-9C NO YES NO NO X SE-1-125-10A YES NO YES NO NO X SE-i-125-10B YES YES NO YES NO NO X 1 088 SE-1-125-10C SE-1-125-10C 38-10 soy YES NO YES NO NO x 1 085 SE-1-125-11A SE-1-125-11A 3B-1I SOV NO NO N3 YES YES x SE-1-125-11B 3B-iI SOV NO YES NO INO x.

3B-1I SOV YES NO YES NO NO x 3B-12 SOV YES NO YES NO NO x 1 08B SE-1-125-12B 3B-12 SOY YES NO YES NO x 1 08B 5E-1-125-12C ISE-1-125-12C SB-12SOV YES NO YES NO x rT-12-1A IFT-12-1A RWCU/FLOW TRANSMITTER X-I RWCU/FLOW1TRANSMITTER YES NO YES NO I NO x YES NO YES NO NO TORUS VACUUM VV CONTROL TORUSVACUUMW CONTROL YES NO YES NO0 NO x 1 1 -TEF-2DGEXHFANCONTROLS YES NO YES NO X 1 20 15-1098 B-1098 TEF-2 DGEXHFANCONTROLS YES NO NO NO 1 20 B-1099 8-1099 YES NO NO NO NO TEF-3 00 EXHFANCONTROLS 1 20 5-1100 5-1100 TEF-3 DGEXHFANCONTROLS YES NO NO NO NO 1 20 5-1101 B-1101 YES NO NO NO NO 1 0 a-wl106 -1106 BUS 3 TRANSFER SWITCH YES NO NO NO 1 20 5-892 B-892 MCC-9C LOADSHEDDING RELAYBOX YES NO NO NO 1 0 B-1059 B-1059 'L SYS TB BOX YES NO YES NO I I 1 NO 1 0 5-1060 B-1060 YES NO YES NO NO 1 0 5-1061 -1061 YES NO YES NO NO x 1 5 8-1082 E-1062. YES ND YES NO NO x 1 0 B-1063 B-1063 RWCU/HITEMP ISOLSYS TE BOX YES NO YES NO NO 1 0 18-1064 B-1064 L SYS TB BOX YES NO -YES NO X NO- NO YES NO YES NO YES NO YES NO NO X YES NO NO NO NO 1 1 20 "HVSGP-8 HVSGP-B RRU5,6,7,8 SWITCHBOX YES NO NO NO NO 1 14J HVRP-A HVFRP-A HVAC"A"CONT PNL YES NO NO NO NO 1 30JHA C PL HVACPNL HVACPNL- SAC-I YES NO NO NO NO FANCONI IYES NO NO NO NO I IaT2i PP-89 NO NO NO N N0 L-16 DG "A"RMDAMPER MOTOR NO NO NO L-17 DOG"B" RMDAMPER MOTOR NO NO NO 1I2oIRA S-1A RATS-1A DG-1ARM THERMOSTAT YES NO NO NO NO RATS-1B DG-1B RM THERMOSTAT YES NO NO NO NO TS-113-4001 SAC-i FREEZESTAT SWITCH YES NO NO NO NO FS-1i3-4001 SP-1 DISCHFLOWSWITCH YES NO NO NO 11 0 :S-113-4005 FS-113-4005 SP-2 DISCH FLOWSWITCH YES NO NO NO 11 085 ISE-113-2007 SE-113-2007 DG RMA DAMPER SOV YES NO NO NO YES NO NO NO NO YES NO NO NO NO YES NO NO NO 1 20 1265-A 25-BA - ANALOGCABINET YES NO NO NO 1 1 20 125-Be 25-5E ANALOGCABINET YES NO NO NO ANALOGCABINET YES NO ND NO NO NO YES NO NO NO YES NO NO NO I I NO NO

Table 9.4.1- Base List 1 Attachment B VY-RPT-12-00019 Rev. 0 nKiRf 1 9A Pae 15 of 24 SCREENlI SCREEN2 1 SCREEN3 SCREEN4 UG  : IECURRENT Undergo Maintains at Environment Decay EQUIPMENT DESCRIPTION Reactivity Pressure Inventory Hest UNIn EQUIPMENT EQSELEQUIPMENTID Seismic Regular least one of Inside/ High Templ Borated Control Control Control Containment Replaced' IPEEE Outside? Humidity? Removal CLASS 1? Configuration the 5 safety System?

Inspections? Functions (110) I(TIH)

I tANALOGCABINET NO 1 k CONTROLPANELFOR VITALAC MG-2-1A NO 20 CONT BOARD JDGRM B CONTROL BOARD YES NO NO -NO YES I NO x 1 20 RCAB YES NO NO NO NO x 20 NO NO NO I NO x 17 NO 20 L TRANSFORMER CAB NO 1 20 OG VOLTREG CAB DGRMA VOLTAGEREGULATOR CAB YES NO NO YES I NO x 1 04 T-LP-1L T-LP-1L RFOR LP-1LII IL ROOM YES NO NO NO NO 1 0 TS-13-79B TS-13-798 YES NO YES NO NO X 1 0 TS-13-7gC TS-13-79C YES NO NO 1 0 TO-13-790 TS-1i3-79 YES NO NO x 1 0 TS-13-80E TS-13-80B '1CICISTEAM LEAKDETECTION YES NO NO x NO 1 0 TS-13-80C TS-13-80C '1CIC/STEAM LEAKDETECTION YES NO YES NO NO X 1 0 TS-i 3-EOD TS-i3-800 RCIC/STEAM LEAKDETECTION NO YES NO NO X 1 0 TS-13-818 TS-13-81E '1CIC/STEAM LEAKDETECTION NO 1 0 TS-13-810 TS-13-81C RCIC/STEAM LEAKDETECTION NO x 1 0 TS-13-810 TS-13-1D :1CICISTEAM LEAKDETECTION YES NO NO NO 1 0 TS-13-82B TS-13-82B :1CICISTEAM LEAKDETECTION YES NO YES NO NO x 1 0 TS-13-82C TS-13i-2C RCIC/STEAM LEAKDETECTION YES NO YES NO NO X 1 0 TS-13-82D TS-i3-12D RCICISTEAM LEAKDETECTION YES NO 1 14 FANCONT BOXB -iVACSACC-1B FANCONTROL BOX YES 1 20 ES-16-19-13A ES-16-19-13A 'OWER SUPPLY FORTORUS LT-10A;PT-29A;LI/PI-12A YES NO NoI NO 1 20 ES-16-19-13SB ES-1-19-138 '1-12B YES NO NO NO NO 1 20 ES-10-145A ES-t01-EA YES NO NO NO NO 1 20 ES-16-i9-43 ES-16-19-43 YES NO 1 20 PR-16-19-44 PR-16-19-44 YES NO 1 18 EGM-23-1 EGM-23-1 -IPCIAEGM CONTROL BOX (TURBSPEED CONTROLLER) YES NO YES NO NO

_N 1 18 RGSC-23-1 RGSC-23-1 1.SIG.CONW.(TURB ROLLER) YES; NO YES NO NO X X LSB-V23-16 LSB-V23-16 YES NO YES NO NO X X LSB-V23-19 YES NO YES NO NO LSB-V23-20 YES NO YES NO NO TS-12-101A '1WCU/LINE TEMP MONITORING YES NO YES NO NO S TS-101B 0-11-1010

'TS-12-1OIB 4WCUILNI:N TMP MONITORING YES NO YES NO NO X 1

0 S-2-102A OWCU/LINETEMP MONITORING YES NO YES NO NO x 1

0 IS-12-1028 RWCU/LINE TEMP MONITORING YES NO YES NO X t NO 1 0 ITS-12-103A RWCUILINE TEMP MONITORING YES NO x 0 iS-12-1038 TS-12-1038 YES NO NO X 7 RWCUILINE TEMP MONITORING X 0 ITS-12-106A TS-12-106A TWOD/ILINETEMP MONITORING YES NO NO NO __

X 1 0 TS-12-106B TS-12-1068 JRWC YES NO YES NO NO __

xX 1 20 1-12-107A 1TS-12-107A RW YES NO YES NO NO 1 0 TO-12.107B TS-12-107B RW, YES NO X YES NO xX 1 0 TS-12-10EA TS-12-108A RW YES NO X x 1 0 TS-12-108E TS-12-108B RWCU/LINETEMP MONITORING YES TS-12-109A RWCU/LINETEMP MONITORING YES NO YES NO NO X 1i 00 rS-12.109A TS-12-1098 1I TS-12-109B RWCU/LINETEMP MONITORING YES NO YES NO NO 1L 0 TS-12-110A TS-12-110A RWCU/LINETEMP MONITORING YES NO NO 0 TS-12-110B TS-12-1108 RWCU/LINETEMPMONITORING YES NO NO 0 TS-12-111A TS-12-111A RWCU/LINETEMPMONITORING YES NO NO NO 11-11-110'TS-12-1118 011 11 YES NO NO X 1 O U 1*-12-111B riWCUILIINETE=MP" MONITORPINGL YE* NO0

Table 9.4.1- Base List 1 Attachment B VY-RPT-12-00019 Rev. 0 Pan 16 of 24 SCREEN1I SCREEN2 1 SCREEN3 SCREEN 4 t t I -. -

SQUG Environment Decay UNITEQUIPMENT EQUIPMENT CURRENT CQURRENT ~

ID SEL EQUIPMENTID EQUIPMENT DESCRIPTION Seismic Undergo Regular Maintains at least one of Inside/ High Templ Borated Reactlvty Control Pressure Control Inventory Control Heat Containment CLASS Replaced?I IPEEE Removal 1? Configuration the 5 safety Outside? Humidity?

Inspections? Functions System?

(110) (TIH) 1 0 ITS-12-112A TS-12-112A =MP MONITORING YES NO YES NO NO x 1 1 0 ITS-12-1128 TS-12-112B RWCU/LINE TEMP MONITORING YES NO YES NO NO x FIS-14-45A CS/FLOW INDICATION YES NO YES NO NO FIS-14-45B CS/FLOW INDICATION YES NO YES NO NO PS-1444A CSrA PUMP DISCHARGE PRESSURE YES NO YES NO NO 1 1 18 PS-14-448 IPS-14-448 CS/"B" PUMP DISCHARGE PRESSURE YES NO YES NO NO x 1 18 PS-14-44C PS-14-44C =PRESSURE YES NO YES NO NO X PS-14-440 YES NO YES NO NO X YES NO YES NO NO YES NO YES NO- .NO NO 1 18 )-1488 RHRiV10-168 CONT. ON LOW FLOW YES NO YES NO x 1 08t IFSO-109-75A-1 IFSO-109-75A-1 CAD SOV SAMPLE ISOLATION(INDO) ILA YES NO YES NO NO X 088 FSO-109-75A-2 fS( CAD SOV SAMPLE ISOLATION(OUTS YES NO YES NO NO x 1 o B-787 B-7: LOCALTERM BOX- V10-57 YES NO YES NO NO A 1 0 "is8B. LOCALTERM BOX- V10-17 YES NO YES NO NO A 1 0 B-1 102 B-1 LOCALTERM BOX- V12-18 YES NO YES NO NO x 1 01 LOCAL-13-16 LO(CAL-13-16 RCIC/LOCAL, f-16 MOV YES YES N;O NO x NO 1 0 B-862 B-8* NO YES NO T NO x 1 04 T-AC-OP-5 T-A NO NO 1 04 DT-3 DT. NO NO 1 04 DT-6 DT- 480t240-120 VACDISTTRANSFORMER YES NO NO NO NO 1 04 DT-10 OT.10 YES NO NO NO 1 1 04 1DT-4 DT- YES NO NO NO NO YES NO NO NO YES NO NO NO S-1i 480 VACUPS-1B MG SET YES NO NO NO NOI NýO 1 1 20 lCP-UPS-1A lCP-UPS-1A 480 VACUPS-1A CONTROL PANEL YES NO NO NO 1 20 ICP-UPS-1B CP-UPS-lB JPS-1i CONTROL PANEL jYES NO NO NO NO 1 18 PT-104-208 PT-1 NO NO NO NO 1 18 PS.104-120A NO NO NO NO 1 18 PS-104-120B IV70-19A,S,20 ISOLATION YES NO NO NO NO 1 18 PS.104-120C NO PS-104-120C crc-ivAn 20 IOOLAIIOIN V70-iSA,, 03 ISOLATION YES NO NO NO 1 18 PS.104-120D V70-19A,B, 20 ISOLATION NO NO PS-104-120D YES NO NO POWER SUPPLY FOR LSL-107-5B YES YES ES-1-156-5 NO RK26-01 CS (A)INST. RACK YES YES RK25-60 CS (B)INST. RACK YES YES NO 1 18 RK2-7A tK25-7A REACTOR RECIRC INST.RACK(A) YES NO YES NO NO X 1 18 RKZ.5T7 tK25-7B REACTOR RECIRC INST.RACK(e) YES NO YES NO NO X YES NO YES 1 18 IRK25-23 RK25-23 NO 1 18 RK25-24 YES NO YES RK25-24 NO 1 18 RK2?5-50A tK25-50A YES NO YES NO 1 18 RK2"-08 RK25-50B HPCI INST. RACK(B) _____ YES NO YES NO NO x x 1 18 RK25-51A JET PUMP INST. RACK(5 YES YES t-25-51A NO NO NO X 1 18 RK25-51B JET PUMP INST.RACK(5 YES YES NO RK25-51 B NO NO RIK25-52A JET PUMP INST.RACK(S NO YES NO RK25-528 JET PUMP INST.RACK(5S NO YES NO NO0 RK25-56A RCICRMINST. RACK(A) YES NO NO NO NO NPO-1 18 IRK2.5-56 RK25-568 RCICRaMINST. RACK(B) YES NO NO NO 1 18 RK25-a9 RK2S-5s YES NO YES NO _ NO I x 1 18 RK25- 976K2i-62 OK(5) YES NO YES NO I NO I X

Table 9.4.1- Base List 1 Attachment B VY-RPT-12-00019 Rev. 0 Pn17 nf 2A4

-rag SCREEN1I SCREEN 2 SCREEN 3 1 SCREEN 4 17 of 24-.

SQUG .

QUGMN CURRENT Undergo Maintains at Environment Decay UNIT EQUIPMENT EQUIPMENT ID SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Reactivity Pressure Inventor Seismic Regular least one of Insidel High Tempi Heat Containment Replaced' IPEEE Control Control Control CLASS 1? Configuration the 5 safety Outside? Humidity? Berated Removal Inspections? Functions System?

(110) (TIH)

RK25-5A REACTOR PROT. &NSSS INST. RACK I I - -l---t--~--F - t -- t +

YES NO YES I NO NO X RK25-58 REACTOR PROT. & NSSS INST.RACK YES NO YES NO NO X RK25-6A REACTORPROT. & NSSS INST.RACK YES NO YES NO YES I NO X 1 18 RK25-68 REACTORPROT. & NSSS INST.RACK YES NO YES NO 1 08A V70-257A V70-257A SW/E-19-2A OUTLET YES NO NO NO I 08A IV70-2578 V70-257B SW/E-19-2EOUTLET YES NO NO NO 1 YES NO NO NO NO 1 YES NO YES NO x X NO 1 YES NO NO NO NO 1 SAC-1DISCHARGE TEMPERATURE NO 0 ITC-113-4002 ITC-113-4002 YES NO NO NO 1 0 LATIONDAMPERFOR SAC-1A YES NO wo- NO NO 1 0 LA YES NO NO NO NO 1 0 YES NO NO NO NO 1 0 NO NO NO YES 1 20 ICRFIREDAMPERCONTROLSWITCH NO YES NO NO 1 21 3CH-1EXPANSION TANK YES NO NO NO 1 3CH-2 YES NO NO NO NOI YES NO NO NO NO 1

YES NO NO NO NO 07 IPCV-1-156-1073AIPCV.11.56,1073A 42 PRESSURE REGULATOR YES NO YES NO NO 1 07 IPCV-1-1WE1073BJPCV.1.ise-10738 12PRESSURE REGULATOR YES NO YES NO NO 1 S-1-1E6-76 YES NO YES NO NO YES NO YES NO NO X 1

YES NO NO NO NO 0 OUTLETVALVE-IDRYER YES NO N-ýO NO NO NO 1 0 IV72-898 V72-898 I2IRCISOLATION CHECK VALVE YES NO NO NO NO 1 V72-89C J2/RCISOLATIONCHECK VALVE YES NO 7NO NO 1 12CYLINDERS (18TOTAL)ANDMANIFOLD YES NO YES NO NO x I RK-25-66 ..ST INST. RACK YES NO YES NO H NO x 1 20 SE-113-4002 3AC-iA EXHAUSTDAMPERCONTROL SE-113-4002 YES NO NO NO NO 1 20 SE-113-4003 SE.113-4003 3AC-1BINLET/OUTLET DAMPER CONTROL YES NO NO NO NO H NO SE-70-3A 3ACKWASH FLOWCONTROL YES NO NO NO 3ACKWASH FLOWCONTROL YES NO NO NO H NO

'OWER SUPPLY FOR ECCS PANEL A POWERSUPPLY FOR ECCS PANELB NO NO

?7O0 NýO-1 21 ICYL-72-1B NO )) I] ]TINOII X is SWEL Item

Table 9.4.2- SWEL 1 Attachment B VY-RPT-12-00019 Rev, 0 Page 18 of 24 SSEL# I SWEL1# I EQUIPMENT ID DESCRIPTION BLDG. DWG 000002 SWELl-001 CRD/HYDRAULIC CONTROLUNITS(89) 000007 SWELI-002 ILCV-3-33C CRD/SCRAM DISCHARGE VOLUMEDRAINVALVE 000010 SWELl-003 CRD/SCRAM DISCHARGE VOLUMEVENTVALVES 000011 SWELl-004 SCRAMVALVES(89) INLET 1 07 N NECR A 3 06 Y 5920-2258 252' EDGR A A 1,2,3,4,5 12 Y TB 252' EDGRB B 1,2,3,4,5 17 Y TB 252' DAY TK RM A A 1,2,3,4,5 07 N Ft TB 252' DAY TK RM B B 1,2,3,4,5 21 Y 0 TK-40-1A Ft ETANK YARD 252' 1,2,3,4,5 21 0 Y 000064 SWELl-011 P-92-1A FUELOIL/FUEL OILTRANSFER PUMP A FO 241' A 1,2,3,4,5 05 I, H Y 000060 SWELl-012 MG-2-1A 120/240V VITALAC MGSET RB 280' 1,2,3,4,5 13 1 Y 5920-4463 000061 SWELl-013 BC-I-IA 125VDC MAINSTATIONBATTERYCHARGER A ON DC-1 CB 248' SWGR WEST 1,2,3,4,5 16 1 Y 000065 SWEL1-014 B-AS-2 125VDC STATIONBATTERYON BUS DC-2AS TB 252' EDGRA 1,2,3,4,5 15 1 Y 000067 SWELl-015 B-1-i 125VDC STATIONBATTERYONDC-2 CB 262' CABLE VAULT 1,2,3,4,5 is I Y 5920-4411 000069 SWELl-016 DC-i 128V DC DISTR PNL DC-11600AMP CB 262' CABLE VAULT 1,2,3,4,5 14 1 N 000071 SWELl-017 DC-2 125VDC DISTRPNL DC-21600AMP CB 262' CABLE VAULT 1,2,3,4,5 14 1 N 5920-4835 000081 SWELl-018 DC-ECCS-B 24 VDCECCS PNL(B) RB 303' B 1,2,3,4,5 14 1 Y 5920-4836 000085 SWELl-019 MCC-9C 480V ESS AC MCC-9C- DIESEL 1AROOM(SII) TB 252' EDG A 1,2,3,4,5 01 1 Y 000088 SWELI-020 MCC-90 480V ESS AC MCC-9D- REACTOR BLDG RB 252' 1,2,3,4,5 01 1 N 000090 SWELl-021 MCC-88 480V ESS AC MCC-8B- REACTOR BLDG(SI) RB 280' 1,2,3,4,5 01 1 Y 000092 SWELl-022 MCC-98 480V ESS AC MCC REACTOR BLDG(SII) RB 280' 1,2,3,4,5 01 1 Y 000095 SWELl-023 BUS-9 480V AC SWITCHGEAR BUS NO.9 1600AMP (SII) CB 248' SWGR EAST 1,2,3,4,5 02 1 N 000096 SWELl-024 BUS-3 4KV-4160V SWITCHGEAR BUS NO.3 1200AMP (SI) CE 248' SWGR WEST 1,2,3,4,5 03 1 N 000101 SWELl-025 T-8-1A STATIONSERVICE TRANS4160/480 BUS NO.8 CB 248' SWGR WEST 1,2,3,4,5 04 1 Y 000103 SWELl-026 TK-4-1A CONDENSATE STORAGE TANK YARD 252' 2,3 21 0 N 000116 SWELl-027 P.44-1A HPCI/HPCI PUMP RB 213' HPCI 2,3 05 1 Y 5920-0622 000125 SWELl-028 PS-23-84-1 HPCI/PUMP SUCTIONPRESSURE SWITCH RB 213' HPCI 2,3 18 1 Y 000129 SWELl-029 V23-15 HPCI/STEAM SUPPLY MOV DW 266' 2,3 08A I, T N 000130 SWELl-030 V23-16 HPCI/STEAM SUPPLY MOV ST 251' 2,3 0aA I, T N 5920-1835 000145 SWELl-031 TEF-3 DGB ROOMVENTILATION/EXHAUST FAN TB 252' EDG B B 1,2,3,4,5 09 1 Y 5920-4449 000164 SWELl-032 RRU-8 SWIECCS RMCOOLING RB 213' SECR 1,2,3,4,5 10 I N 5920-4683 000174 SWELl-033 PT-2-3-52C CS, RHRPERMISSIVE RB 252' 3 18 I Y 5920-3055/5920-3057 000176 SWELl-034 LT-107-SA CST/LEVEL TRANSMITTER CST VALVE 252' 3 18 I, H Y 000177 SWELl-035 LT-107-S5 CST/LEVEL TRANSMITTER CST VALVE 252' 3 18 I, H Y 5920-6041 000178 SWELl-036 PT-10-101A OWPRESSURE ECCS RB 280' 5 18 I Y 5920-3016/5920-3017 000180 SWELI-037 PT-10-1O1C DWPRESSURE ECCS RB 280' 5 18 1 Y 5920-3016/5920-3017 000182 SWELl-038 PT-16-19-29A )W PRESSURE INDICATION RB 280' 5 18 1 Y 5920-3016/5920-3017 000188 SWELl-039 PT-5-12C OWPRESSURE SCRAM RB 280' 5 18 1 Y 5920-3016/5920-3017 000187 SWEL1-040 PT-5-120 OWPRESSURE SCRAM RB 280' 5 18 1 Y 5920-3016/5920-3017 000188 SWELl-041 TE-16-19-30A W TEMPINDICATION DW 268' 5 19 IT Y 000203 SWELl-042 LT-2-3-72A RVLEVELFOR RHR,DOG, HPCI,RCIC, ADS, CS RB 280' 3 18 1 1 Y 5920-3016/5920-3017 000205 SWELl-043 ILT-2-3-72C RVLEVELFOR RHR,DOG, HPCI,RCIC, ADS, CS RB 280' 18 Y 5920-3016/5920-3017 000209 SWELl-044 ILT-2-3-58A RVLEVELSCRAM& PCIS RB 280' 18 Y 5920-ý 000210 SWELl-045 ILT-2-3-588 RVLEVELSCRAM& PCIS RB 280' 18 Y 000213 ISWELl-046 IPT-2-3-56A RVPRESSURE ECCS RB 280' 000215 ISWELl-047 IPT-2-3-56C RVPRESSURE ECCS RB 280' 000219 ISWELl-048 IPT-2-3-55C RVPRESSURE SCRAM RB 280' 000220 ISWELI-049 IPT-2-3-55D RVPRESSURE SCRAM RB 280' 000221 SWELl-D50 LT-2-3-73A RV SHROUD LEVEL,CONT SPRAY PERMISSIVE RB 000227 SWELl-051 IPS-104-53A ISW/PUMP A PRESSURE SWITCH is

Table 9.4.2- SWEL 1 Attachment B VY-RPT-12-00019 Rev, 0 Pace I of 24 SSEL# SWEL1# EQUIPMENT ID DESCRIPTION BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIORNMENT ANC DWG 000248 SWELl-052 V2.80D MAINSTEAM/INBOARD MSIV DW 254' 5 07 1, T N 000253 SWELl-053 M2-8sA MAINSTEAM/OUTBOARD MSIV ST 251' 5 07 I, T N 000257 SWELl-054 M-2-6A MAINSTEAM/OUTBOARD MSIVINSTAIRSUPPLY ACCUMULATOR ST 251' 5 21 I, T Y 0002653 SWELI-055 RV-2-71C MAINSTEAMIRELOEF VALVE DW 275' 2 07 i, T N 000266 SWELl-056 TK-55-1A N2 AIR RECIEVER RB 303' 2 21 1 N 5920-5017 000268 SWEL1-057 S-2-13A SAFETYRELIEFVALVE/NITROGEN SUPPLY ACCUMULATOR DW 275' 2 21 1,T Y 000279 SWELl-058 P-10-10 RHR/DRHR PUMP RB 213' SECR B 4 06 1 N 5920-1611 000281 SWELl-059 V10-65B RHRIHEAT XC BYPASS MOV RB 232' SECR B 4 08A I N 5920-9288 000282 SWELl-060 V10-27A RHR/LPCIINJECTIONMOV RB 252' 4 08A I N 5920-5564/5920-5565 000306 SWELl-061 P-8-1 8 CHRSWC C RHRSW PUMP RB 232' NECR A 4 06 1 Y 5920-3855/5920-3944 000312 SWELl-062 10-89A CHRSW/SW SUPPLYMOV RB 232' NECR A 4 08B I N 5920-11020 000314 SWELI-063 SP-70-3A BACKWASH FLOWCONTROL IS 237' SW ROOM A 1,2,3A5 07 H N 5920-1811 000320 SWELI-064 P.7-103W/C SW PUMP IS 237' SW ROOM A 1,2,3.4,5 06 H Y 5920-3947/5920-4602 000394 I-SWEL1-065 "LCV.08-03 *PFUEL OIL/HEAT BOILERTKFILL FO 241' 1,2,3,4,5 07 1. H N 000324 SWELl-066 FCV.-104-28A WI/DGCOOLING TB 252' EDGR A A 1,2,3,4,5 07 N 000335 SWELl-077 V70-20A MW/OURBOADG ISOLMOV RB 246' TORUS CW 1,2,3,45 08A IN 000353 SWELI-068 VU-I22A HPCI/HPCI TURBINE RB 213' HPCI 2,3 05 Y 000371 SWELl-069 NG-13-INTAKE-1

-6 DGROOMVENTILATION/DG ROOMB LOUVERS (6 TOTAL) TB 252' EDGR B B 1,2,3,4.5 0 Y 5920-9096 000401 SWELl-070 BS-23-110 PIPC O SUPPLY VNST PWR CB 272' CONT RM 2,3 20 I N 5920-2678 000402 SWELl-071 CRTA-23-118 PCISQ RT CONV-FLOW CE 272' CONT RM 2,3 20 1 N 5920-3258 000404 SWEL1-072 P-23.94 CTPCILDCOAC INVERTER CB 272' CONT RM 2,3 20 1 N 5920-3258 000420 SWELl-073 *S-23-101A HPCI/STEAM LEAKDETECTOR ST 251' 2,3 0 I T Y 000426 SWELl-074 0s923,102A HPCIRSTEAM LEAKDETECTOR ST 251' 2,3 0 1T y 000428 SWELl-075 DSR23,103A HPCI/STEAM LEAKDETECTOR ST 251' 2,3 0 T Y 000432 SWELl-076 LS-23104A DRPCI/STEAM LEAKDETECTOR ST 251' 2,3 0 T Y 000496 SWELl-077 SE.2-86A-1 IGS/OUTBOARD MSIVSOLENOID ACIDC ST 251' 5 208 I, T N 000512 SWELl-078 G-1-202A2 A MOVVENTISOLATION (OUTBTD) RB 303' 5 08A I N 000515 SWEL1-079 O-13A CADSOVAIRISOLATION (INND)INJECTION TO OWPNLA RB 222' TORUS AREA 5 , 081 N 000154 SWELl-080 DG-1-9 PRIMARY CONTAINMENT VENTTO SBGTISOLATION AOV (OUTBTB RB 303' 5 07 1 Y 5920-4892/5920-4901 001210 SWELl-081 _ DRP9-03 ONTROLROOMPANEL CB 272' CONT RM 2,3 201 Y 5920-3258 001221 SWELl-082 LRP9-19 TONTROLROOMPANEL CB 272' CONT RM 2,3 20 1 N 5920-2678 001222 SWELl-083 CRP 9-20 PONTROL ROOMPANEL CB 272' CONT RM 2,3 20 N 5920-3770 001242 SWEL1-094 A G RMBVOLTAGE REGULATOR CAB TB 252' EDGR B B 1.2,3,45 20 N 5920-3911/5920-4592 001243 SWEL1-085 RG RMA NEUTRAL TRANSFORMER CAB TB 252' ECGRA A 1,2,34,5 20 Y 5920-4593 001354 SWELl-086 K-17 A GJ"B"RMDAMPERMOTOR TB 252' EDGR B B 1,2,3,4,5 0 Y N

001355 SWELl-087 R2ATSA1A JET-1ARM THERMOSTAT TB 252' EDGR A A 1,2,3,4,5 20 N 5 001375 SWELl-088 S*E-113-2022 DG RM B DAMPER SOY TB 252' EDGR B B 1,2,3,4,5 O8B IN 001387 SWELl-089 DGRMBENGINECONTACTOR CAB TB 252' EDGR B 1,2,3,4,5 1 20 59Y 001358 SWELl-090 DG RM ENGINER INSTRPNL TB 252' EDGR B B 1,2,3,4,5 2O1 Y 5920-4801/5920-4802 001389 SWELl-091 R2G S RM EQUIP SKID TB 252' EDGR B B 1,2,3,4,5 17 1 Y 001396 SWELI-092 T-LP-I1L TRANFORMER FOR LP-1L- IN CONTROL ROOM CBI 262' CABLE VAULT 1,2,3,4,5 04 1N 001514 SWELl-093 ES-1-156-5 POWER SUPPLY FOR LSL-107-E B CB 272' CONTRM 2,3 20 1 N 001522 SWELl-094 RK25-50A HPCIINST.RACK(A) RB 213' HPCI 2,3 18 Y 5920-3044/5920-3045 001523 SWELl-095 RK25-508 HPCI INST. RACK (B) RB 213' HPCI 2,3 15 Y 5920-3044/5920-3045 001526 SWELl-096 RK25-52A JET PUMP INST. RACK (52A) RB 252' is1 Y .5920-3055/5920-3057 001527 SWELl-097 RK25-52B JET PUMP INST. RACK (52B) RB_ 252' 1 81 Y 5920-3055/5920-3057 001534 SWELl-098 RK25-6A REACTOR PROT. & NSSS INST. RACK RB 280' 118 Y 5920-3016/5920-3017 001535 ISWELl-099 RK25-68 REACTOR PROT. & NSSS INST. RACK RB 280' 118 Y 5920-3016/5920-3017 001566 SELl-100 IRK.25-66 CST INST. RACK CST 252' 318 1, H Y 5920-6041 SWLl-10 r-24 C-2 POER SUPYFR ECCS PANEL B CB 248' SWGR EAST 241 ISWE~-0 CY7-1 NIRGE ZoE FOR BACKUP SRV SUPPLY Re 252' A 221 1N

Table 9.4.2- SWEL 1 Attachment B VY-RPT-12-00019 Rev. 0 Paoe 20 of 24 I SSEL# I SWELl# I EQUIPMENT IDI DESCRIPTION BLDG. I ELEV. I ROOM I TRAIN SYSTEM TYPE ICLASS IENVIORNMENTI ANC I DWG =

System 1 Reactivity Control 2 Pressure Control 3 Inventory Control 4 Decay Heat Removal 5 Containment

• • During implementation of the Seismic Walkdowns SWEL-065 was determined to be inaccessible for inspection. This SWEL number was valve FCV-104-17D, SW/D TRAVELLING SCREEN CONTROL VALVE. It was replaced with Valve LCV-108-3 which is located in the Fuel Oil Pump House. This valve is a similar GIP 07 class valve and is also located in a humid environment as was FCV-104-17D. No other SWELl & SWEL2 items have been changed since the original SWEL approval prior to Seismic Walkdowns.

Table 9.4.3- Base List 2 Attachment B VY-RPT-12-00019 Rev. 0 Page 21 of 24 BL2# EQUIPMENT ID DESCRIPTION BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT N/R 2001 ES-19-818 20 I ISFP( 18 2003 ITI-19-73B 272' Control Room SFPC 18 2004 IdP1-19-768 .RB 272' Control Room SFPC 18 2005 IES-19-768 Power Supply (CAD PNLA) CRB 272' Control Room SFPC 20 2006 IES-19-81A Power Supply (CAD PNLB) Z.RB 272' SFPC 20 2007 PI-19-BIA Pressure Indicator (CADPNLB) :RB 1272' SFPC 1C 2008 TI-19-73A Temperature Indicator (CADPNLBR) R8 272' SFPC 18 2009 dPI-19-76A Differential Pressure Indicator (CADPNL 8) JRB 1272' SFPC 18 1 2010 ES-19-76A Power Supply (CADPNL 3) RB 1272' SFPC 20 x 2011 IRK-10AA Rack 303' SFPC 18 X 2012 PI-19-82A Pr DIK-10AA) B _ 1303' SFPC 18 1 X 2013 dPT-19-76A D*i Transmitter (RK-10AA) RB 303 1 SFPC 18_ __1 x 2014 PT-19-S1A Pr er(RK-l0AAI 303' SFPC 18 2015 PI-19-83A Pr RK-1OAA) R8 1303' SFPC 18 x 2016 PS-19-ROA Pressure Switch (RK-10AAI 303' SPFc 18 X 2017 PI-19-P Pressure Indicator tRK-1OAAI 303' SFPC 18 Rack RB 303' Pressure Indicator (RK-10ABI RB 303 SFPC Differential Pressure Transmitter IRK-1OAB) RB SFPC Pressure Transmitter (RK-1OABl SFPC K-1t SF-PC SFPC SFPC SFPC SFPC.

2027 TE-19-73B SFPC 19 2028 FE-19-73 FP Hx Room SFPC 0 x 2029 IFI-19-73 303' FPHx Room SFPC 0 2030 ITI-104-60 Temperature Indicator 303' SFPC 0 2031 ITI-104-61 Temperature Indicator 303' SFPC 0 2032 V70-257A SW MOV SFPC Hx Outlet RB 1303' FP Hx Rm SFPC 8A x 2033 V70-2578 SW MOV SFPC Hx outlet RB 303' FP Hx Rmr SFPC BA x 2034 P-19-2A SFPCPump R8 303' FP Hx Rm SFPC _

2035 P-19-28 SFPCPump R8 303' PPHx Rm SFPC 5 X 2036 E-19-2A SFPCHeat Exchanger RB 303' FP Hx Rm SFPC 21 2037 E-19-28 SFPCHeat Exchanger RE; 303' FP Hx Rm SFPC 21 2038 CADPanelA Panel CR6 272' Control Room SFPC/FPC 20 X 2039 CADPanel B Panel CR6 272' [Control Room SFPC/FPC 20 2040 RK-10 Rack 303' FPC 18 2041 T1-191- Temperature indicator (RK-10) 303' 18 2042 Pressure Switch (RK-10) 303' Pressure Switch (RK-10) RB 303' Pressure Indicator (RK-10) RB Pressure Indi-ator fRK-lOt FPC FPC

)-63A 'Control Room P~C

Table 9,4.3- Base List 2 Attachment B VY-RPT-12-00019 Rev. 0 Page 22 of 24 BL2#I EQUIPMENT ID DESCRIPTION BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT NIR f'DQ [:D/"*

205 II-19-71A (CAD PNL13) CRB 272' lC lR FP RB 303' IFPHx Room FPC 2053 ITE-19-70B Temoerature Element RA 303' FP H. Room FPC 2054 ITE-19-70C Temperature Element RB 303' FP Ho Roo FPC 2055 1TE-19-IA Temperature Element RB 303' FPC 2056 ITE-19-1B Temperature Element RB 303' FPC 2057 IPS-19-6SA Pressure Switch RB 303' FPC Pressure Switch RB 303' FPC 0 Temperature Element RB 345' FPC 19 Temperature Element RB 345' FPC 19 Level Transmitter RB 345' 0 Level Transmitter RB 345' FPC 0 Pressure Indicator RB 318' FPC 0 Pressure Indicator RB 318' FPC 0 Pressure Indicator RB 318' Skim Pump Rm FPC 0 2066 IPI-19-66B Pressure Indicator RB 318' Skim Pump Rm FPC 0 20kIj15-20_ F >( n isolation MOV RB 1303' IFP HX Rm FPC &A 2068IV1-221 ... iFP C n isolation MOV RB 303' FP Hx Rm _ FPC &A 2069 P-82-1A FPC Skimmer Pump RB 318' Skim Pump Rm FPC S 2070 P-82-1B FPC Skimmer Pump RB 318' Skim Pump Rm FPC S 2071 P-9-1A FPC Pump RB 303' FP Hx Rm FPC 5 2072 P-9-1B FPC Pump RB 303' FP Hx Rm FPC 5 2073 E-9-1A FPC Heat Exchanger RB 303' FP Hx Rm FPC 21 2074 E-9-1B FPC Heat Exchanger RB 303' FP Hx Rm FPC 21 2075 -T-104-808 Flow Transmitter (RK-10AB) RB 303' SW 18 2076 FI-104-80B Flow Indicator (CADPNL A) SW to SFPC Hx CR8 272' Control Room SW 18 2077 ES-104-80B Power SupplyI CADPNL A) SW to SFPC Hx CRB 272' Control Room SW 20 2078 FI-104-80A Flow Indicator (CADPNL B)SW to SFPC Hx CRB 272' Control Room SW 18 2079 ES-104-80A Power Supply (CADPNL B) SW to SFPC Hx CRB 272' Control Room SW 20 2080 PI-104-93A Pressure indicator (RK-10AA) R8 303' SW 18 X 2081 FT-104-80A Flow Transmitter (RK-1OAA) RB 303' SW 18 2082 PI-104-93B Pressure indicator (RK-10AB) RB 303' SW 18 2083 MCC-6A MCC RB 280' 480A 1 2084 MCC-6C MCC RWB 252' Control Room 480A 1 2085 MCC-6D MCC RWB 252' Control Room 480A 1 2086 MCC-7A MCC R8 280' 480A 1 2087 MCC-8B MCC RB _ 280' 480A 1 Z088 MCC-9B MCC RB 1280' 480A 1 Z089 MCC-BE MCC RB 252' 480A 1 x is SWEL Item

Table 9.4.4- Rapid Drain-Down Attachment B VY-RPT-12-00019 Rev. 0 P ae 23 of 24 ROD# DESCRIPTION BASIS FOR INCLUSIONIEXCLUSION iRDD No Rapid Drain-Down items were identified during the development of the SWEL 2.

Table 9.4,5- SWEL 2 Attachment B VY-RPT-12-00019 Rev. 0 Page 24 of 24 SWEL 2# EQUIPMENT ID DESCRIPTION BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT N/R RDD SWEL2-001 RK-1OAA Rack RB 303' 4 18 SWEL2-002 dPT-19-76A Differential Pressure Transmitter RK-10AA) RB 303' 4 18 SWEL2-003 PT-19-81A Pressure Transmitter (RK-1OAA) R8 303' 4 18 SWEL2-004 PS-19-80A Pressure Switch (RK-10AA) R8 303' 4 18 SWEL2-005 PI-19-84A Pressure Indicator (RK-1OAA) RB 303' 4 18 SWEL2-006 F1-19-73 Flow Indicator RB 303' FP Hx Room 4 0 SWEL2-007 V70-2578 SW MOV SFPC Hx outlet RB 303' FP Hx Rm B 4 8A SWEL2-008 P-19-2A SFPC Pump RB 303' FP Hx Rm A 4 5 SWEL2-009 E-19-2A SFPC Heat Exchanger RB 303' FP He Rm A 4 21 SWEL2-010 CADPanel B Panel CRB 272' Control Room 8 4 20 1 SWEL2-011 FT-104-80A Flow Transmitter (RK-OAA) 303' _RB 4 18 1 System 1 Reactivity Control 2 Pressure Control 3 Inventory Control 4 Decay Heat Removal 5 Containment

Attachment C Engineering Report No. VTY-RPT-12-00019 Rev. 0 Page 1 of 505 Attachment C Seismic Walkdown Checklists (SWCs)

Attachment C Engineering Report No. VTY-RPT-12-00019 Rev. 0 Page 2 of 505 SWEL1# EQUIPMENT ID DESCRIPTION PAGE SWELl-001 CRD/HYDRAULIC CONTROL UNITS (89) 5 SWELl-002 LCV-3-33C CRD/SCRAM DISCHARGE VOLUME DRAIN VALVE 10 SWELI-003 PCV-3-32B CRD/SCRAM DISCHARGE VOLUME VENT VALVES 15 SWELl-004 CV-3-126- CRD/SCRAM VALVES (89) INLET 20 SWELl-005 P-46-1A CS/"A" CORE SPRAY PUMP 25 SWELl-006 C-3-1A DG START AIR/COMPRESSOR A 30 SWELl-007 DG-1B DIESEL GENERATOR B 35 SWELl-008 LCV-108-2A FUEL OIL/DAY TANK FILL 40 SWELl-009 TK-42-1B FUEL OIL/DIESEL OIL DAY TANK B 45 SWELl-010 TK-40-1A FUEL OIL/FUEL OIL STORAGE TANK 50 SWELl-011 P-92-1A FUEL OIL/FUEL OIL TRANSFER PUMP A 55 SWELI-012 MG-2-1A 120/240V VITAL AC MG SET 60 SWELl-013 BC-i-lA 125V DC MAIN STATION BATTERY CHARGER A ON DC-i" 65 SWELl-014 B-AS-2 125V DC STATION BATTERY ON BUS DC-2AS 70 SWELl-015 B-i-lB 125V DC STATION BATTERY ON DC-2 75 SWELl-016 DC-1 125V DC DISTR PNL DC-1 1600AMP 80 SWELI-017 DC-2 125V DC DISTR PNL DC-2 1600AMP 85 SWELl-018 DC-ECCS-B 24 VDC ECCS PNL (B) 90 SWELl-019 MCC-9C 480V ESS AC MCC-9C - DIESEL 1A ROOM (SII) 95 SWELI-020 MCC-9D 480V ESS AC MCC-9D - REACTOR BLDG 100 SWELl-021 MCC-8B 480V ESS AC MCC-8B - REACTOR BLDG (SI) 105 SWELl-022 MCC-9B 480V ESS AC MCC-9B - REACTOR BLDG (SI1) 110 SWELI-023 BUS-9 480V AC SWITCHGEAR BUS NO.9 1600AMP (SIl) 115 SWELI-024 BUS-3 4KV - 4160V SWITCHGEAR BUS NO.3 1200AMP (SI) 120 SWELl-025 T-8-1A STATION SERVICE TRANS 4160/480 BUS NO.8 125 SWELl-026 TK-4-1A CONDENSATE STORAGE TANK 130 SWELI-027 P-44-IA HPCI/HPCI PUMP 135 SWELl-028 P5-23-84-1 HPCI/PUMP SUCTION PRESSURE SWITCH 140 SWELl-031 TEF-3 DG B ROOM VENTILATION/EXHAUST FAN 145 SWELl-032 RRU-8 SW/ECCS RM COOLING 150 SWELI-033 PT-2-3-52C CS, RHR PERMISSIVE 155 SWELl-034 LT-107-SA CST/LEVEL TRANSMITTER 160 SWELl-035 LT-107-SB CST/LEVEL TRANSMITTER 165 SWELl-036 PT-iO-lOlA DW PRESSURE ECCS 170 SWELl-037 PT-10-101C DW PRESSURE ECCS 175 SWELl-038 PT-16-19-29A DW PRESSURE INDICATION 180 SWELl-039 PT-5-12C DW PRESSURE SCRAM 185 SWELl-040 PT-5-12D DW PRESSURE SCRAM 190 SWELl-042 LT-2-3-72A RV LEVEL FOR RHR, DG, HPCI, RCIC, ADS, CS 195 SWELl-043 LT-2-3-72C RV LEVEL FOR RHR, DG, HPCI, RCIC, ADS, CS 200 SWELl-044 LT-2-3-58A RV LEVEL SCRAM & PCIS 205 SWELl-045 LT-2-3-58B RV LEVEL SCRAM & PCIS 210 SWELl-046 PT-2-3-56A RV PRESSURE ECCS 215 SWELl-047 PT-2-3-56C RV PRESSURE ECCS 220 SWELl-048 PT-2-3-SSC RV PRESSURE SCRAM 225

Attachment C Engineering Report No. VTY-RPT-12-00019 Rev. 0 Page 3 of 505 SWEL1# EQUIPMENT ID DESCRIPTION PAGE SWELl-049 PT-2-3-55D RV PRESSURE SCRAM 230 SWELl-050 LT-2-3-73A RV SHROUD LEVEL, CONT SPRAY PERMISSIVE 235 SWELl-051 PS-104-53A SW/PUMP A PRESSURE SWITCH 240 SWELl-056 TK-55-1A N2 AIR RECIEVER 245 SWELl-058 P-10-ID RHR/D RHR PUMP 250 SWELl-059 V10-65B RHR/HEAT XC BYPASS MOV 255 SWELl-060 V10-27A RHR/LPCI INJECTION MOV 260 SWELl-061 P-8-1C RHRSW/C RHRSW PUMP 265 SWELI-062 VlO-89A RHRSW/SW SUPPLY MOV 270 SWELl-063 SP-70-3A BACKWASH FLOW CONTROL 275 SWELl-064 P-7-1C SW/C SW PUMP 280 SWELl-065 FCV-104-17D SW/D TRAVELLING SCREEN CONTROL VALVE 285 SWEL1-066 FCV-104-28A SW/DG COOLING 290 SWELl-067 V70-20 SW/TURB BLDG ISOL MOV 295 SWELl-068 TU-1-1A HPCI/HPCI TURBINE 300 SWELl-069 DG-1B-INTAKE-X DG ROOM VENTILATION/DG ROOM B LOUVERS (6 tOTAL) 305 SWELl-070 ES-23-110 HPCI INST PWR SUPPLY 310 SWELl-071 FTA-23-118 HPCI SQ RT CONV-FLOW 315 SWELl-072 ES-23-94 HPCI/DC/AC INVERTER 320 SWELI-078 VG-22A CAD MOV VENT ISOLATION (OUTBD) 325 SWELl-079 NG-13A CAD SOV AIR ISOLATION (INBD) INJECTION TO DW PNL A 330 SWELI-080 SB-16-19-6 PRIMARY CONTAINMENT VENT TO SBGT ISOLATION 335 (OUTBD) AOV SWELI-081 CRP 9-03 CONTROL ROOM PANEL 340 SWELl-082 CRP 9-19 CONTROL ROOM PANEL 345 SWELl-083 CRP 9-20 CONTROL ROOM PANEL 350 SWEL1-084 DG RM B VOLTAGE REGULATOR CAB 355 SWELl-085 DG RM A NEUTRAL TRANSFORMER CAB 360 SWELl-086 L-17 DG "B" RM DAMPER MOTOR 365 SWEL1-087 RATS-lA DG-1A RM THERMOSTAT 370 SWELI-088 SE-113-2022 DG RM B DAMPER SOV 375 SWELl-089 DG RM B ENGINE CONTACTOR CAB 380 SWELl-090 DG RM B ENGINE INSTR PNL 385 SWELl-091 DG RM B EQUIP SKID 390 SWELl-092 T-LP-1L TRANFORMER FOR LP-1L IN CONTROL ROOM 395 SWELI-093 ES-1-156-5 POWER SUPPLY FOR LSL-107-5B 400 SWELl-094 RK25-50A HPCI INST. RACK (A) 405 SWELl-095 RK25-50B HPCI INST. RACK (B) 410 SWELl-096 RK25-52A JET PUMP INST. RACK (52A) 415 SWELl-097 RK25-52B JET PUMP INST. RACK (52B) 420 SWELl-098 RK25-6A REACTOR PROT. & NSSS INST. RACK 425 SWELl-099 RK25-6B REACTOR PROT. & NSSS INST. RACK 430 SWELl-lO0 RK-25-66 CST INST. RACK 435 SWELl-1O1 ES-24DC-2 POWER SUPPLY FOR ECCS PANEL B 440 SWELl-102 CYL-71-1A NITROGEN BOTTLE FOR BACKUP SRV SUPPLY 445

Attachment C Engineering Report No. VTY-RPT-12-00019 Rev. 0 Page 4 of 505 SWEL1# EQUIPMENT ID DESCRIPTION PAGE SWEL2-001 RK-10AA Rack 450 SWEL2-002 dPT-19-76A Differential Pressure Transmitter (RK-10AA) 455 SWEL2-003 PT-19-81A Pressure Transmitter (RK-10AA) 460 SWEL2-004 PS-19-80A Pressure Switch (RK-10AA) 465 SWEL2-005 PI-19-84A Pressure Indicator (RK-10AA) 470 SWEL2-006 FI-19-73 Flow Indicator 475 SWEL2-007 V70-257B SW MOV SFPC Hx outlet 480 SWEL2-008 P-19-2A SFPC Pump 485 SWEL2-009 E-19-2A SFPC Heat Exchanger 490 SWEL2-010 CAD Panel B Panel 495 SWEL2-011 FT-104-80A Flow Transmitter (RK-10AA) 500 Items Differed to RFO 30 (March 2013) 505

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 5 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YS NEI U-Seismic Walkdowq Checklist (SWC) SWELl- 001 Equipment ID No. Equip. Class 1 0 to -QIY ( 2, Equipment Description CRD/HYDRAULIC CONTROL UNITS (89)

Location: Bidg. RB Floor El. 252' Room, Area SOUTH AND NORTH BANKS 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.

Anchoraae

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

2. Is the anchorage free of bent, broken, missing or loose hardware? YZ NEI IMu N/A[]

3. Is the anchorage free of corrosion that is more than mild surface YO NEI UI- N/AD7 oxidation?

4. Is the anchorage free of visible cracks in the concrete near the Y0 NEI UE- N/A-anchors?

4 ~ ~

4.4ki ~L (e-2 S-iL IEnter the equipment class name from EPRI I025286, Appendix B: Classes of EquipmenL EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 6 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YN NE] ULI Seismic Walkdown Checklist (SWC) SWEL1- 001 Equipment ID No.. f Equip. Class' 0 Equipment Description CRD/HYDRAU IC CONTROL UNITS (89)

5. Is the anchorage configuration consistent with plant documentation? YO- NEI ur- N/A[K (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 YN NE] U[]

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y9 NE] U-' N/AE]

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NE] UE] N/AE]

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YE NE] UE] N/AE]

10. Based on the above seismic interaction evaluations, is equipment free YS NO] U of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 7 of 505 ATTACHME14T9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YE N7 U7-Seismic Walkdown Checklist (SW SWELl- 0 Equipment ID No/-eert . Equip. Class' Equipment Description CRD/HYDRAULIC CONTROL UN ITS (89)

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y[EN[-]UC adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

NOTE: South bank Inspected 10/04/12 and the North bank Inspected 10/16/12.

Reference Documents:

A46/IPEEE - SSEL Line No. 000002 Evaluated b ate; I10/16/2012 Randy Steohensi R06-1~U I ~( UA 10/16/2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 8 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YV N[-] U[3 Seismic Walkdow!?4"W Checklist WC) ,.,--SWEL1-

=#/aQ--r(SLA . 11 001 Equipment ID No. Equip. Class' 0 Equipment Description CRD/HYDRA ULIC CONTROL UNITS (89)

Photographs (south bank)

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 9 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 5 of 5 Status: YN NEI UE" Seismic Walkdown Checklist (SWC, SWELl- 001 Equipment ID No. 4 Q . Equip. Class 0 Equipment Description CRD/HYDRAULIC CONTROL UNITS (89)

(south bank) (nort bank)

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 10 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y9 NE UM Seismic Walkdown Checklist (SWC) SWELl- 002 Equipment ID No. LCV-3-33C Equip, Class 1' 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME DRAIN VALVE Location: Bldg. RB Floor El. 252' Room, Area 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.

Anchoracie

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

2. Is the anchorage free of bent, broken, missing or loose hardware? YEI NE- U[3 N/A[K

3. Is the anchorage free of corrosion that is more than mild surface Y[E1 NE] UE' NIA13 oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YE- NE UE3 N/AZ anchors?

IEnter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 11 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 2 of 5 Status: YZ ND U7 Seismic Walkdown Checklist (SWC) SWELl- 002 Equipment ID No. LCV-3-33C Equip. Class' 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME DRAIN VALVE

5. Is the anchorage configuration consistent with plant documentation? YE] NEI U[] N/A0 (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of YZ NEI UE-1 potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YZ NEI U[3 N/AD

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UE- .N/AE--

and masonry block walls not likely to collapse onto the equipment?

9, Do attached lines have adequate flexibility to avoid damage? YED N[-] U-1 N/A[-E

10. Based on the above seismic interaction evaluations, is equipment free YZ NEI UE-]

of potentially adverse seismic interaction effects?

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 12 of 505 ATTACHMEN4T 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y0g NEI UEI Seismic Walkdown Checklist (SWC) SWELl- 002 Equipment ID No. LCV-3.33C Equip. Class' 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME DRAIN VALVE Other Adverse Conditions

11. Have you looked for. and found no other seismic conditions that could YZ N[3 UO adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Marcus Hecht-Niese n'~ ~ 5--/-

i /G Date: 10-04-2012 Raymond Tworek 2=2.7,rt4,0,,ý 10-04-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 13 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YN N[] U[3 Seismic Walkdown Checklist (SWC) SWELl- 002 Equipment ID No. LCV-3-33C Equip. Class1 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME DRAIN VALVE Photographs NO PHOTO Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 14 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y] NF- UI-Seismic Walkdown Checklist (SWC) SWELl- 002 Equipment ID No. LCV-3-33C Equip. Class1 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME DRAIN VALVE NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 15 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y[ NO" U-Seismic Walkdown Checklist (SWC) SWELl- 003 Equipment ID No. PCV-3-32B Equip. Class' 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VALVES Location: Bidg. RB Floor El. 252' Room, Area Reactor Building (South Wall)

Manufacturer, Model, Etc. (optional but recommended) Conval 2" Globe. 1500#. model 2-12G2GJ-105 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of Judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchoraqe

1. Is the anchorage configuration verification required (i.e. Is the item one YO-- NtR]

of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YE] NE ur"] N/A0 In-fine valve, no anchorage.

3. Is the anchorage free of corrosion that is more than mild surface YE NO U-] N/A[

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YE NE UI N/AN anchors?

I Emer the.equipment class name from EPRI 1025286, Appe!dix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 16 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y[ N-I Ur-1 Seismic Walkdown Checklist (SWC) SWELl- 003 Equipment ID No. PCV-3-32B Equip. Class 1 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VAL VES

5. Is the anchorage configuration consistent with plant documentation? Y[E NEI UE- N/A{[

(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 YZ NEI UE-potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y9 N[E] uE1 N/AEl

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y] NE"] UE- N/AE' and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Y[K NE:I UE N/AM

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

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 17 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ NEI Ui Seismic Walkdown Checklist (SWC) SWELl- 003 Equipment ID No. PCV-3-32B Equip. Class' 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VALVES Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YN NEI U[

adversely affect the safety functions of the equipment?

Comments (Additional pages may be'added as necessary)

Reference Documents:

A46/IPEEE - SSEL Line No. 000010 Evaluated by: K/rit Parikh ý-C- 10 llgl 201?- Date: 10/04/2012 Randyý Ste hens Rqu~~~~n~h " -- r I 'ýU M- 10/04/2012 EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 18 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORM Sheet 4 of 5 Status: Y0 NM' UF1 Seismic Walkdown Checklist (SWC) SWELI- 003 Equipment ID No. PCV-3-32B Equip. Class' 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VALVES Photographs Note: Looking up at valve # PCV-3-32B.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 19 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NEl ULI Seismic Walkdown Checklist (SWC) SWELl- 003 Equipment ID No. PCV-3-32B Equip. Class1 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VALVES EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 20 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YN NLJ UR-]

Seismic Walkdown Checklist (SWC) SWELl- 004 Equipment ID No. CV-3-126- Equip. Class1 07 Equipment Description CRD/SCRAM VALVES (89) INLET Location: Bldg. RB Floor El. 252' Room, Area Reactor Building (North/South)

Manufacturer, Model, Etc. (optional but recommended) Hammel-Dahl, model # 2500ASA-V999Z1205 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 YE1 NO of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YZ NEI UE- N/AE-

3. Is the anchorage free of corrosion that is more than mild surface YZ NEI U'I N/AE-oxidation?

4. Is the anchorage free of Visible cracks in the concrete near the YZ NE UI N/AD anchors?

' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 21 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y[ NEI UL-Seismic Walkdown Checklist (SWC) SWELl- 004 Equipment ID No. CV-3-126- Equip. Class' 07 Equipment Description CRD/SCRAM VALVES (89) INLET

5. Is the anchorage configuration consistent with plant documentation? YE NEI UE N/A (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 Y[E NE UE potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YN NEI. U0 N/AE

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0 NEI U-- N/AE and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YN NJ--E UE N/A[-]

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

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 22 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 3 of 5 Status: YN NI Ur]

Seismic Walkdown Checklist (SWC) SWELl- 004 Equipment ID No. CV.3-126- Equip. Class' 07 Equipment Description CRD/SCRAM VALVES (89) INLET Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YN NEI U["]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Note: South bank inspected 10/04/12 and the North bank inspected 10/16/12.

Note: Surface corrosion was observed on valve CV-3-126-10-27associatedwith HCU 10-27(north bank) at the bonnet andyoke interface (see photos page 5). This surface corrosiondoes not pose an adverse seismic condition. See CR- VTY-2012-05099.

Reference Documents:

A46/IPEEE - SSEL Line No. 000011 Evaluated by: Kirit Parikh k2V a.-AA06,-

4,f , 10119 Date: 10/16/2012 RandyStephens. 10/16/2012 EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 23 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YN NEI UL0 Seismic Walkdown Checklist (SWC) SWELl- 004 Equipment ID No. CV-3-126- Equip. Class 1 07 Equipment Description CRD/SCRAM VALVES (89) INLET Photographs EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 24 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NEI U-I Seismic Walkdown Checklist (SWC) SWELl- 004 Equipment ID No. CV-3-126- Equip. Class 1 07 Eauloment Descriotion CRD/SCRAM VALVES (89) INLET FIlUIU; IVUI LII LUJil (I . V t'num iyptvicw IYrffl DvFK vaIvusnflwf or showing surface corrosion. comparison.

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 25 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YN NDI UM Seismic Walkdown Checklist (SWC) SWELl- 005 Equipment ID No. P-46-1A Equip. Class1 06 Equipment Description CS/A" CORE SPRAY PUMP Location: Bldg. RB Floor El. 213' Room, Area NECR 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

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y[K N-3 UDI N/AD-

3. Is the anchorage free of corrosion that is more than mild surface Y[ NEI U[-- N/A[D-]

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YN NDl UtJ N/AD]

anchors?

' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 26 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y[D N[] UM Seismic Walkdown Checklist (SWC) SWELl- 005 Equipment ID No. P-46-1A Equip. Class' 06 Equipment Description CS/'A" CORE SPRAY PUMP

5. Is the anchorage configuration consistent with plant documentation? YZ NE U[--] N/AE-(Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See drawing 5920-2258.

6. Based on the above anchorage evaluations, is the anchorage free of Y[R N7 UEI potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? .YZ NE-] u[] N/A[E]

8. Are overhead equipment, distribution systems, ceiling tiles and Iightlng, YO NEI UE] N/AEl and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ NEI U[-E-N/AE1

10. Based on the above seismic interaction evaluations, is equipment free Y[ NEI U[-]

of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 27 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y9 NEI U-Seismic Walkdown Checklist (SWC) SWELl- 005 Equipment ID No. P-46-1A Equip. Class' 06 Equipment Description CS/'A" CORE SPRAY PUMP Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y[9 N[] U[-]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Note:

Picture originally taken at 10/11/2012 inspection was blurred, Re-inspected 10/17/2012 and took another picture, Reference Documents:

Drawing 5920-2258 A46/1PEEE - SSEL Line No, 000015 Evaluated by: Kirit Parikh 119 12-0 12 Date: 10/17/2012 RandySte~hns iOA:<ý b la-II~ s"L(A~~- 10/17/2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 28 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y1Z NEI UM Seismic Walkdown Checklist (SWC) SWELl- 005 Equipment ID No. P-46-1A Equip. Class 1 06 Equipment Description CS/"A" CORE SPRAY PUMP Photographs NO PHOTO Note:

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 29 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ NEI U"]

Seismic Walkdown Checklist (SWC) SWELl- 005 Equipment ID No. P-46-1A Equip. Class 1 06 Equipment Description CSI'A" CORE SPRAY PUMP NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 30 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YE NEI UM Seismic Walkdown Checklist (SWC) SWEL1- 006 Equipment ID No, C-3-1A Equip. Class1 12. AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR A Location: Bldg. T8 Floor El. 252 Room, Area EDGRA 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, Anchlorape

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

2. Is the anchorage free of bent, broken, missing or loose hardware? YN NE-] UE- N/AE-

3. Is the anchorage free of corrosion that is more than mild surface YEJ NE U[] N/AD-oxidation?

4. Is the anchorage free of visible cracks in the concrete near the Y(9 NE- ur- N/AED anchors?

Enter the equipment class name from EPRI 1025286. Appendix B: Classes of Equipment.

EN-DC-168 REV 0

I Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 31 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI UM Seismic Walkdown Checklist (SWC) SWELl- 006 Equipment ID No. C-3-1A Equip. Class' 12- AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR A

5. Is the anchorage configuration consistent with plant documentation? YE N] U[-I N/AEl (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See A46/IPEEE - SSEL Line No. 000033

6. Based on the above anchorage evaluations, is the anchorage free of YN N[E] UEI potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from Impact by nearby equipment or structures? YS NE UEI N/AEI

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y] NE U[iE N/A[--

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Y[D NE uE- N/AEl There is a rigid connection but seismically they will move together and are acceptable based on engineeringjudgment.

10. Based on the above seismic Interaction evaluations, is equipment free YO NEI UIJ of potentially adverse seismic interaction effects?

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 32 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ N-I UMJ Seismic Walkdown Checklist (SWC) SWELl- 006 Equipment ID No. C.3-1A Equip. Class1 12 - AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR A Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ N[:UE1 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference Documents:

A46//PEEE - SSEL Line No. 000033 Evaluated by: Marcus Hecht-Nielsen . Date: 10-01.20 12 RaymondTworek teliql 10-01-2012 EN-DC-168 REV 0

I Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 33 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YV NO] UM-Seismic Walkdown Checklist (SWC) SWELl- 006 Equipment ID No. C-3-1A Equip. Class1 12- AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR A Photographs I I! I Note: C-3-1A ISO VIEW EN-DC-1 68 REV 0

ý. 11 Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 34 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ NEI U' Seismic Walkdown Checklist (SWC) SWELl- 006 Equipmentl1D No. C-3-1A Equip. Class1 12- AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR A NO PHOTO NO PHOTO Note: Note:

EN-DC-1 68 REV 0

61 Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 35 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y[0 NE] UI--

Seismic Walkdown pecklist (SWC) SWELl- 007 Equipment ID No. qp. Glass 17 Equipment Description DIESEL GENERA OR 0-Location: Bldg. TB Floor El. 252' Room, Area EDGR B 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 SW EL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchoraqe

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y[ NEI UE-1 N/AF-

3. Is the anchorage free of corrosion that is more than mild surface YN NE:] U[-] N/A[-'

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the Y[E] NE UEI N/AZ anchors?

Steel structure,no concrete.

1. • cL~P"- r~t/ .b I/O-Zr- / 2.-

'Enter the equipment class name from EPRI 1025286, Appendix B:.Classes of Equipment.

EN-DC-168 REV 0

'a Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 36 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NE] uM Seismic Walkdown Checklist (SM/C) SWELl- 007 Equipment ID No. -&6040- 4 .Equip. Class' 17 Equipment Description DIESEL GENERATOR B 5, Is the anchorage configuration consistent with plant documentation? YZ N" UM N/AEI (Note: This question only applies If the Item Is one of the 50% for which anchorage configuration verification Is required.)

The diesel generatorcomes attached to the skid. The skid is properly attachedto the foundation (see Swel 1-091 and VYEM-olo7) and the generatoris attachedto the skid with 8-1 4"diameterbolts. Thus, the generatorfalls under the rule of the box. Seismically acceptable by engineeringjudgment.

6. Based on the above anchorage evaluations, Is the anchorage free of Y0R NO U[3 potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YZ NEI U-' N/A['

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[K NO U17 N/A[--

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ NO U['- N/A7l

10. Based on the above seismic interaction evaluations, is equipment free YZ NEI UE-of potentially adverse seismic interaction effects? I EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 37 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ NE"I ur-Seismic Walkdown Checklist (SWC) .-

Equipment ID No. 1j 2 Equip. Class' ti m to -z.I- ITZ Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 N[3 UE]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawing5920-3991, G- 191566, and VYEM-0 107 A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000044 Evaluated by: Marcus ehtNls,/OKI,. I,ý/ - Date: 10-03-2012 Ravmond Tworek 10-03-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 38 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NI] ur]

Seismic Walkdown Checklist (SWC) SWEL1- 007 b- H0 cY;A-47V /

Equipment ID No. W A/ Equip. Class 1 17 Equipment Description DIESEL GENERATOR B Photographs EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 39 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ NiM UM Seismic Walkdown Checklist (SW9) SW L1- I Equipment ID No.* .qL Equip. Class' Ep t" B.

_p-IR.AR Equipment Description DIESEL GENERATOR B EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0

.. Page 40 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN UHECKLIST IORM Sheet 1 of 5 Status: YZ NEI UII-Seismic Walkdown Checklist (SWC) SWELl- 008 Equipment ID No. LCV- 108-2A Equip. Class 1 07- FLUID OPERATED VALVES Equipment Description FUEL OILDAY TANK FILLVALVE Location: Bldg. TS Floor El. 252' Room, Area DAY TK RM A Manufacturer, Model, Etc. (optional but recommended) ACF #70-14-2-RH Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment On the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.,

Anchoraae

1. Is the anchorage configuration verification required (i~e. is the iten one Y[3 NO of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YE NEI UF- NWAN In-line valve, no anchorage.

3. Is the anchorage free of corrosion that is more than mild surface YE" NE U-E N/AZ oxidation?

4. Is the anchorage free of Visible cracks in the concrete near the YEI NEI U-I N/AZ anchors?

IEnter the equipment class name from EPRI 1025286, Appendix B: Classes or Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 41 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: y[0 NEI UEr Seismic Walkdown Checklist (SWC) SWELl- 008 Equipment ID No, LCV-108-2A Equip. Class1 07 - FLUID OPERATED VALVES Equipment Description FUEL QILIDA Y TANK FILL VALVE

5. Is the anchorage configurati'0on consistent with plant documentation? YE NEI U- N/AN (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 Y[R NEI U[-E potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y0 NEI U0 N/AE]

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0 NEI UE-- N/AE-and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YE" NEI UE:1 N/A]

No attachedlines exist.

10. Based on the above seismic interaction evaluations, is equipment free YR NEI UE]

of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 42 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y0 NI- U"]

Seismic Walkdown Checklist (SWC) SWELl- 008 Equipment ID No. LCV-1.O-2A Equip. Class1 07- FLUID OPERATED VALVES Equipment Description FUEL O/L/DAY TANK FILL VALVE Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ NO UE adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference Documents:

A46/IPEEE- SSEL Line No. 000049 Evaluated by: Kirit Parikh V-P__ tc> I1A, 120 12- Date: 10/02/2012 Rangy Stephens gA &L ( 10/02/2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 43 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Shoot 4 of 5 Status: Y0 NO"Uo]

Seismic Walkdown Checklist (SWC) SWELl- 008 Equipment ID No. LCV-108-2A Equip. Class1 07- FLUID OPERATED VALVES Equipment Description FUEL OILIDAY TANK FILL VALVE PhotoaraDhs EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 44 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NEI UC-Seismic Walkdown Checklist (SWC) SWELl- 008 Equipment ID No, LCV-1OB-2A Equip. Class 1 07- FLUID OPERATED VALVES Equipment Description FUEL QILIDAY TANK FILL VALVE NO PHOTO Note:

EN-DC-168 REV 0

t' Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 45 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST. FORM Sheet 1 of 5 Status: Y[ NEI U[-

Seismic Walkdown Checklist (SWC) SWELl- 009 Equipment ID No. TK-42-1B Equip. Class1 21 - TANKS & HEAT EXCHANGERS Equipment Description FUEL OIL/DIESEL OIL DAY TANK B Location: Bldg. TB Floor El. 252 Room, Area DAY TK RM B Manufacturer, Model, Etc. (optional but recommended) Buffulo Tank Div.

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 YN NEi of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YN NEJ U[i] N/A-

3. Is the anchorage free of corrosion that is more than mild surface YN NE] UE] N/A--

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the Y] NEI UEI N/A[:

anchors?

Two groutpads on the east side of the tank are slightly damaged, but do not effect seismic performanceor reliability.

,Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 46 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ Nr-j UIr-Seismic Walkdown Checklist (SWC) SWELl- 009 Equipment ID No. TK-42-1B Equip. Class' 21 - TANKS & HEAT EXCHANGERS Equipment Description FUEL OIL/DIESEL OIL DAY TANK B

5. Is the anchorage configuration consistent with plant documentation? YI[ Nr-3EU[I- N/Ar-3 (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See A46/IPEEE - SSEL Line No. 000052

6. Based on the above anchorage evaluations, is the anchorage free of Y[ NEI U-I potentially adverse seismic conditions?

7. Are soft targets free from impact by nearby equipment or structures? YZ N[3 U[-] N/Am3

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI ULi N/A[-

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Y; NEI UI- N/A[D

10. Based on the above seismic interaction evaluations, is equipment free YZ NEI U7 of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 47 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 3 of 5 Status: Y[] N-] U[-I SWELl- 009 Seismic Walkdown Checklist (SWC)

Equipment ID No. TK-42-IB Equip. Class' 21 - TANKS & HEAT EXCHANGERS Equipment Description FUEL OIUDIESEL OIL DAY TANK B Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZJ NU1 U[I adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference Documents:

A46/IPEEE- SSEL Line No. 000052 Drawing 5920.4047 and B.191261, sheet 54.

Modification MM 99.021 Calculation VYC- 1891 Evaluated by: Marcus Hecht-Nielsen Date: 10-03-2012 Raymond Tworek 1Z01j 10ý11ii.1-.- 10-03.2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 48 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NE] ULI Seismic Walkdown Checklist (SWC) SWELl- 009 Equipment ID No. TK-42r-1B Equip. Class 1 21 - TANKS & HEAT EXCHANGERS Equipment Description FUEL OIUDIESEL OIL DAY TANK B Photographs EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 49 of 505 ATTACHMEI NT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NEI UL-J Seismic Walkdown Checklist (SWC) SWELl- 009 Equipment ID No. TK-42-1B Equip. Class 1 21 - TANKS & HEAT EXCHANGERS Equipment Description FUEL O/UDIESEL OIL DAY TANK B EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 50 of 505 ATTACHMENT 9.6 SEISMIC WALKOOWN CHECKLIST FORM Sheet 1 of 5 Status: Y0 N7l! U7-"

Seismic Walkdown Checklist (SWC) SWELl- 010 Equipment ID No. TK-40-1A Equip. Class' 21 Equipment Description FUEL OIUFUEL OIL STORAGE TANK (FOST)

Location: Bldg. YARD Floor El. 252' Room, Area YARD 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.

Anchoraae

1. Is the anchorage configuration verification required (i.e., is the item one YZ N[3 of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YZ NEI UE- N/Ar"

3. Is the anchorage free of corrosion that is more than mild surface YN NEI UrI N/AE-oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YC9 N[l UE- N/AE anchors?

A small hairline crack is seen nearNorth-East bolt, seismically insignificantby engineeringjudgment since only small areahas this crack. All other areasare without any cracks.

'Enter the equipment class name from EPRI 1025286. Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 51 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 N-" U[-Z Seismic Walkdown Checklist (SWC) SWELl- 010 Equipment ID No. TK-40-IA Equip. Class1 21 Equipment Description FUEL O/L/FUEL OIL STORAGE TANK (FOST)

5. Is the anchorage configuration consistent with plant documentation? Y[9 NEI UE] N/AE (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

See Drawing G- 191606 and calculation VYC- 1469.

6. Based on the above anchorage evaluations, is the anchorage free of Y[K NE] uE-potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YZ NEI U[] N/AE"]

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[] NEI UE- N/AE1 and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YEI NE3 UF1 N/AZ No flexible items connected 10., Based on the above seismic interaction evaluations, is equipment free Y[D N[-] UE]

of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 52 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ N[] u(-]

Seismic Walkdown Checklist (SWC) SWELl- 010 Equipment IDNo. TK-40-IA Equip. Class' 21 Equipment Description FUEL OILUFUEL OIL STORAGE TANK (FOST)

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ NE] UE]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawing G-191606 Calculation VYC- 1469 A46//PEEE - Screening Evaluation Work Sheet, SSEL Line No. 00053 Evaluated by: Kirit Parikh ifý ý-e, 10 11 8,ý 2- a 12- - Date: 10/10312 RandySteihens f~IA-.&Yq, . 1741iz i-L-. 10/03/12 EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 53 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0 Nr" Un Seismic Walkdown Checklist (SWC) SWELl- 010 Equipment ID No. TK-40-IA Equip. Class1 21 Equipment Description FUEL OIL/FUEL OIL STORAGE TANK (FOST)

Photographs EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 54 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NEI UE]

Seismic Walkdown Checklist (SWC) SWELl- 010 Equipment ID No. TK-40-1A Equip. Class 1 21 Equipment Description FUEL OIUFUEL OIL STORAGE TANK (FOST)

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 55 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet I of 5 Status: Y0 NO] U-Seismic Walkdown Checklist (SWC) SWELl- 011 Equipment ID No. P-92-IA Equip. Class1 05 Equipment Description FUEL OIL/FUEL OIL TRANSFER PUMPA Location: Bldg. FO Floor El. 241' Room, Area SWCR 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

1. Is the anchorage configuration verification required (i.e., is the item one Y NO]

of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Y[] N[-' UEI N/A[

3. Is the anchorage free of corrosion that is more than mild surface Y[9 N[-1] U- N/A[-

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YZ NEI] UI N/A'-

anchors?

' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 56 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI UI-Seismic Walkdown Checklist (SWC) SWELl- 011 Equipment ID No. P-92-1A Equip. Class1 05 Equipment Description FUEL OIL/FUEL OIL TRANSFER PUMPA

5. Is the anchorage configuration consistent with plant documentation? Y0R NEI UiE N/AFE (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

See SSEL Line No. 00054 and associatedanchoragecalculation.

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

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y21 NEI UE- N/AE1

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEI UE1 N/A[-]

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YO NEI UE] N/ArE

10. Based on the above seismic interaction evaluations, is equipment free Y*; NE: UE of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 57 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y[ NEI Ur-Seismic Walkdown Checklist (SWC) SWELl-Equipment ID No. P-92-1A Equip. Class1 EouiDment DescriDtion FUEL IlUFUEL OIL TRANSFEf Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y[ NI' U[E]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 00054 Evaluated by:- Kirit Parikh D Z-o 12, Date: 10/03/2012 Randy Stephens & t 2&- 10/03/2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 58 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NEI U-]

Seismic Walkdown Checklist (SWC) SWELl- 011 Equipment ID No. P-92-1A Equip. Class' 05 Equipment Description FUEL OIL/FUEL OIL TRANSFER PUMPA Photographs NO PHOTO Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 59 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 5 of 5 Status: Y0 Nr-EI U0-Seismic Walkdown Checklist (SWC) SWELl- 011 Equipment ID No. P-92-1A Equip. Class' 05 Equipment Description FUEL QI/FUEL OIL TRANSFER PUMPA

.NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 60 of 505 ATTACHMEIN5T9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 SWELl- 012 Status: Y0* Nr- U[--

(SWC)

Seismic Walkdown Checklist Equipment ID No. MG-2-1A Equip. Class 1 13 Equipment Description 120/240V VITAL AC MG SET Location: Bldg. RB Floor El. 280' Room, Area Manufacturer, Model, Etc. (optional but recommended), G.E. # 5LS4404A22Y37 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 YN N7 of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Y0 NEl U-' N/AEC

3. Is the anchorage free of corrosion that is more than mild surface Y[ NE- u-' N/A[C oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YS NED U-1 N/A'-

anchors?

' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-1 68 REV 0

,I-,

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 61 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 NE7 U Seismic Walkdown Checklist (SWC) SWELl- 012 Equipment ID No. MG-2-1A Equip. Class 1 13 Equipment Description 120/240V VITAL AC MG SET

5. Is the anchorage configuration'consistent with plant documentation? YZ NO UE] N/A--

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

See drawings 5920-12739 and 5920-4463

6. Based on the above anchorage evaluations, is the anchorage free of Y0 NEr UE]

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO NEI UE- NAE

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NE3 UE- N/AE and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YN NE uE] N/AF"

10. Based on the above seismic interaction evaluations, is equipment free YZ NEI UE3 of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

ýv Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 62 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YN N[-] Ul-W Seismic Walkdown Checklist (SWC) SWELl- I Equipment ID No. MG-2-1A Equip. Class 1 Equipment Description 120/240V VITAL AC MG SET Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Reference Documents:

Drawing5920-4463, Sheet 1, Rev.0 and 5920-12739 A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000060 Evaluated by: Marcus Hecht-Nielse n Date: 10-09-2012 Raymond Tworek etI.ý-a1L.--4 - -F 10 1'3Ar7-- 10-09-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 63 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0 NEI UEI Seismic Walkdown Checklist (SWC) SWELl- 012 Equipment ID No. MG-2.1A Equip. Class'1 3 Equipment Description 120/240V VITAL AC MG SET Photographs Note: Modification EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 64 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ NEI UEI Seismic Walkdown Checklist (SWC) SWELl- 012 Equipment ID No. MG-2-1A Equip. Class1 13 Equipment Description 120/240V VITAL AC MG SET NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 65 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YS NEI UM Seismic Walkdown Checklist (SWC) SWELl- 013 Equipment ID No. BC-i-IA Equip. Class1 16 Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-1 Location: Bldg. CS Floor El, 248' Room, Area SWGR WEST Manufacturer, Model, Etc. (optional but recommended) C&D Power Systems. # ARR13OK15OF Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchoraae

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

2. Is the anchorage free of bent, broken, missing or loose hardware? YZ NEI UI-] N/A--

3. Is the anchorage free of corrosibn that is more than mild surface Y] NEI U[I N/AU oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YE NEi U[I N/AU anchors?

Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

V Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 66 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI ULI Seismic Walkdown Checklist (SWC) SWELl- 013 Equipment ID No. BC.1-1A Equip. Class1 16 Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-1

5. Is the anchorage configuration consistent with plant documentation? YZ NE] UEI N/A[

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

6. Based on the above anchorage evaluations, is the anchorage free of YE NEI UE--

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y; NEI UD] N/AU

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0Z NEI u N/AU-and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ Nr- UU] N/AU--]

10. Based on the above seismic interaction evaluations, is equipment free YN NF-1U'--

of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 67 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YN NEI UEJ Seismic Walkdown Checklist (SWC) SWELl- 013 Equipment ID No. BC-1i1A Equip. Class1 16 Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-i Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Reference Documents:

Drawing5920-10849, Sheet 1, Rev. I A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000061 Evaluated by: Marcus Hecht-Nielsen*Ž*/c' _ Date: 10-09-2012 Raymond Tworek ý3 V, 0 .. L /ij i 10-09-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 68 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YEE NEI UF]

Seismic Walkdown Checklist (SWC) SWELl- 013 Equipment IDNo, BC-1-A Equip. Class' 16 Equipment Description .125V DC MAIN STATION BATTERY CHARGER A ON DC-1 Photographs NO PHOTO Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 69 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NO" U7 Seismic Walkdown Checklist (SWC) SWELl- 013 Equipment ID No. BC-I-IA Equip. Class1 16 Equipment Description 125VDC MAIN STATION BATTERY CHARGER A ON DC-1 NO PHOTO NO PHOTO Note: Note:

EN-DC-1 68 REV 0

t.

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 70 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YN N[i UM Seismic Walkdown Checklist (SWC) SWELl- 014 Equipment ID No. B-AS.2 Equip. Class' 15 - BATTERIES ON RACKS Equipment Description 125V DC STATION BATTERY ON BUS DC-2AS Location: Bldg. TB Floor El. 252 Room, Area EDGR A Manufacturer, Model, Etc. (optional but recommended) CID, KC-9. 59 cells, flat Plate 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 Y[D NEr of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YS NED UE- N/AE-

3. Is the anchorage free of corrosion that is more than mild surface Y0 NE] UE- N/AE-oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YZ NEI UEI N/A[-

anchors?

IEner the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 71 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y[0 NEI U" Seismic Walkdown Checklist (SWC) SWELl- 014 Equipment ID No. B-AS-2 Equip. Class' 15- BATTERIES ON RACKS Equipment Description 125V DC STATION BATTERY ON BUS DC-2AS

5. Is the anchorage configuration consistent with plant documentation? YZ NO Ur3 N/AEl (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See drawing G-191572

6. Based on the above anchorage evaluations, is the anchorage free of Y0 NE) UE-potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO NE U-- N/A[-]

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Yv NEI uEF N/A[-]

and masonry block walls not likely to collapse onto the equipment?

Expansion tank TK 1A located above the battery rack is adequately supported (see EDCR 12) no issue.

9. Do attached lines have adequate flexibility to avoid damage? YZ N[E] UM N/A["]

IOr Based on the above seismic interaction evaluations, is equipment free Y9 N[-] UEr of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 72 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YN NEI U-'

Seismic Walkdown Checklist (SWC) SWELl- 014 Equipment ID No. B-AS-2 Equip. Class1 15 - BATTERIES ON RACKS Equipment Description 125V DC STATION BATTERY ON BUS DC-2AS Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YN NO U7 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference Documents:

A46/IPEEE - SSEL Line No. 000065 See SSEL# 000328, TK-67-1A, and EDCR 82-12 Drawings G-191572 &5920-11085 Evaluated by: Marcuse l , Date: 10-01-2012 RavmondTworek 1I,(1I- 10-01-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 73 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y9 NOI UI Seismic Walkdown Checklist (SWC) SWELl- 014 Equipment ID No. B-AS-2 Equip. Class' 15 - BATTERIES ON RACKS Equipment Description 125V DC STATION BATTERY ON BUS DC-2AS Photographs EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 74 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YS NEI uM Seismic Walkdown Checklist (SWC) SWELl- 014 Equipment ID No. B-AS-2 Equip. Class1 15- BAITER/ES ON RACKS Equipment Description 125V DC STATION BATTERY ON BUS DC-2AS NO PHOTO Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 75 of 505 ATTACHMEINT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: Y[ NI] UM]

Seismic Walkdown Checklist (SWC) SWELl- 015 Equipment ID No. B-1-1B Equip. Class1 15 Equipment Description 125V DC STATION BATTERY ON DC-2 Location: Bldg. CB Floor El. 262' Room, Area CABLE VAULT 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

1. Is the anchorage configuration verification required (i.e., is the item one YC9 NE]

of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YZ NEI UI] N/Ar]

3. Is the anchorage free of corrosion that is more than mild surface YZ NI7 uE N/A[]

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the Y[9 NI] U-I N/AL-'

anchors?

IEnter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 76 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI Ui-Seismic Walkdown Checklist (SWC) SWELl- 015 Equipment ID No. B-I-IB Equip. Class 1 15 Equipment Description 125V DC STATION BATTERY ON DC-2

5. Is the anchorage configuration consistent with plant documentation? Y; N[] U[] N/AEl (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See drawings B- I-1A and B-i-lB

6. Based on the above anchorage evaluations, is the anchorage free of YZJ N[E] U[-]

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YN NEI U[:] N/A[-

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO NEI U[: N/AE-and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ NE-] UE] N/A[]

10. Based on the above seismic interaction evaluations, is equipment free YN N[: U[]

of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 77 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Yv NE] UE]

Seismic Walkdown Checklist (SWC) SWELl- 015 Equipment ID No. B-1-lB Equip. Class1 15 Equipment Description 125V DC STATION BATTERY ON DC-2 Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 NE-] UI-]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference Documents:

Drawing5920-4411, C&D BATTERIES, Sheet 1 Drawing5920-11884, Duke Engineering &Services, Sheets 1-4 DrawingsB-1-A and B-1.1B A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000067 Evaluated by: Marcus Hecht-N/e/sen..--is,,en*/,/,*l,/*/,*

'-- Date: 10-09-20 12 Raymond Tworek 10-09-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 78 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YO NO U-I Seismic Walkdown Checklist (SWC) SWELl- 015 Equipment ID No. B-1-18 Equip. Class1 15 Equipment Description 125VDC STATION BATTERY ON DC-2 Photographs Note: B--1lB Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 79 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORM Sheet 5 of 5 Status: YZ NEI UI-Seismic Walkdown Checklist (SWC) SWELl- 015 Equipment ID No. B-1-1B Equip. Class' 15 Equipment Description 125V DC STATION BATTERY ON DC-2 EN-DC-168 REV 0

.A Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 80 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YED NO] UE-J Seismic Walkdown Checklist (SWC) SWELl- 016 Equipment ID No. DC-1 Equip. Class 1 14 Equipment Description 125VDC DISTR PNL DC-1 1600AMP Location: Bldg. CB Floor El. 262' Room, Area CABLE VAULT Manufacturer, Model, Etc. (optional but recommended) Westinghouse, NEMA II Switchboard 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 Y[-L NZ of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YE-] NE] U[-] N/A0

3. Is the anchorage free of corrosion that is more than mild surface YE Nf-' U[-- N/ACK oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YN NEI UE" N/A[

anchors?

I Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 81 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YED NEI UE-Seismic Walkdown Checklist (SWC) SWELl- 016 Equipment ID No. DC-1 Equip. Class1 14 Equipment Description 125V DC D/STR PNL DC-1 1600AMP

5. Is the anchorage configuration consistent with plant documentation? YEI NEI UE] N/AZ (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of YZ NEl UE]

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y0 NE- U[E- N/A[-]

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[E NEl UE- N/AE and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YN N[3 U(3 N/AE-]

10. Based on the above seismic interaction evaluations, is equipment free YZ N[E] U-of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 82 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ NE] UMI Seismic Walkdown Checklist (SWC) SWEL1- 016 Equipment ID No. D.C-1 Equip. Class1 14 Cniminwnr%+ nterirM,;n i oI/ fl'n nlcT"D DAII '".'1 "I4lnA AD 9

~liI*ll ~ l I~L *OClJltiklII l~' JVbV L il.I U rDF I 5 l, iV -~I i~V~L -ifl -i Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ NE] UQ-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference Documents:

Drawing5920-11819, Sheets 1-2, Rev.0 Drawing5920-4835, Sheet 1, Rev. 0 A46//PEEE - Screening Evaluation Work Sheet, SSEL Line No. 000069 Evaluated by: Marcus Hecht-Nielsen Date: 10-09-2012 RavmondTworek lo/i1r-~ 10-09-20102 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 83 of 505 ATTACHMENT 9.6 SEISmiC WALKDOWN CHECKUST FORM Sheet 4 of 5 Status: YZ NO Ur" Seismic Walkdown Checklist (SWC) SWELl- 016 Equipment ID No. DC-I Equip. Class' 14 Equipment Description 125VDC DISTR PNL DC-1 1600AMP Photographs EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 84 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 5 of 5 Status: Y0 Nr" Uf1 Seismic Walkdown Checklist (SWC) SWELl- 016 Equipment ID No. DC-I Equip. Class' 14 Equipment Description 125VDC DISTR PNL DC-iI1600AMP NO PHOTO Note: 125VDC Distr. Pni. DC-1 Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 85 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRM Sheet I of 5 Status: YZ N[- UL-Seismic Walkdown Checklist (SWC) SWELl- 017 Equipment ID No. DC-2 Equip. Class1 14 Equipment Description 125V DC DISTF? PNL DC-2 1600AMP Location: Bldg. CB Floor El. 262' Room, Area CABLE VAULT Manufacturer, Model, Etc. (optional but recommended) Westinghouse, NEMA II Switchboard Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchora-ae

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y[-] N[] UE'] NWA

3. Is the anchorage free of corrosion that is more than mild surface Y[] NO] U[] N/AZ oxidation?

4. Is the anchorage free of visible cracks In the concrete near the Y[R NE-" U[3 N/Ar anchors?

IEnter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment,.

EN-DC-168 REV 0

4-Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 86 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ N-] U[I Seismic Walkdown Checklist (SWC) SWELl- 017 Equipment ID No. DC-2 Equip. Class 1 14 Equipment Description 125V DC DISTR PNL DC-2 1600AMP

5. Is the anchorage configuration consistent with plant documentation? YO NE- U-E N/A[E (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

6. Based on the above anchorage evaluationsjis the anchorage free of Y0 NED U[3 potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipmentor structures? YE] NEI ULI N/AE

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0 NEI uEr N/AE]

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Y0 NEI UIE N/AE

10. Based on the above seismic interaction evaluations, is equipment free Y9 NEI U-'

of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

/+

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 87 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ N[] ui-Seismic Walkdown Checklist (SWC) SWELl- 017 Equipment ID No. DC-2 Equip. Class' 14 Equipment Description 125V DC DISTR PNL DC-2 1600AMP Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 NECU[3 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference Documents; Drawing 5920.11819, Sheets 1-2, Rev.0 Drawing5920-4836, Sheet 1, Rev.2 A46/1PEEE - Screening Evaluation Work Sheet, SSEL Line No. 000071 Raymond Tworek i/5J.. 10-09-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 88 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y*;; N[] Ul" SWELl- 017 Seismic Walkdown Checklist (SWC)

Equipment ID No. DC-2 Equip. Class1 14 Equipment Description 125V DC DISTR PNL DC-2 1600AMP Photographs Note:

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 89 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YN NEI Urj Seismic Walkdown Checklist (SWC) SWELl- 017 Equipment ID No. DC-2 Equip. Class 1 14 Equipment Description 125V DC DISTR PNL DC-2 1600AMP EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 90 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y[9 NEI Ur-Seismic Walkdown Checklist (SWC) SWELl- 018 Equipment ID No. DC.ECCS-B Equip. Class1 14- DISTRIBUTION PANELS Equipment Description 24 VDC ECCS PNL (B)

Location: Bldg. RB Floor El. 303' Room, Area EAST 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.

Anchoraae

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

2. Is the anchorage free of bent, broken, missing or loose hardware? YE NI- ' N/AD-]

3, Is the anchorage free of corrosion that is more than mild surface Y0 NDI U-- N/A[-]

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YZ NDI ULIEN/A[D anchors?

IEnter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 91 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI UE-Seismic Walkdown Checklist (SWC) SWELl- 010 Equipment ID No. DC.ECCS-B Equip. Class' 14 - DISTRIBUTION PANELS Equipment Description 24 VDC ECCS PNL (B)

5. Is the anchorage configuration consistent with plant documentation? Y0 No U[-] N/A[

(Note: This question only applies if the Item is one of the 50% for which anchorage configuration verification is required.)

See SSEL Line No. 00008 1(attachmentA).

6. Based on the above anchorage evaluations, Is the anchorage free of Y9 NDI UD3 potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from Impact by nearby equipment or structures? Y9 ND-] U[3 N/AD

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0 NEI U"l N/AD-and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YN NED UEI N/AD 10., Based on the above seismic interaction evaluations, is equipment free YS N-' UM of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 92 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YER N7 UF-Seismic Walkdown Checklist (SWC) SWELl- 018 Equipment ID No. DC-ECCS-B Equip. Class 1 14 - DISTRIBUTION PANELS Equipment Description 24 VDC ECCS PNL (B)

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y[E NE] UD-adversely affect the safety functions of the equipment?

1 - 3/8" nut (right upper in cabinet-see attachedphoto) is not fully engaged. About 50% of the nut is engaged. Remaining nuts are fully engaged. With this observation the panel is secured and will not be impacted due to seismic condition.

CR # CR-VTY-2012-05021 / 05007 generated to fix the engagement.

Comments (Additional pages may be added as necessary)

Note: Originalinspection completed 10/10/2012. Re-inspected 10/11/2012 when cabinet door was opened by qualified plant personnel.

Reference Documents:

A46/IPEEE- SSEL Line No. 000081.

A46/IPEEE - SSEL Line No. 000081(attachmentA)

Evaluated by: Kirit Parikh 10 ýIg (zo I?- Date: 10/11/2012 Randy Stei~hens'~ & .4ýA 10/11/2012 5

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 93 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 4 of 5 Status: YZ NO Ur" Seismic Walkdown Checklist (SWC) SWEL1- 018 Equipment ID No. DC-ECCS-B Equip. Class' 14 - DISTRIBUTION PANELS Equipment Description 24 VDC ECCS PNL (B)

Photographs EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 94 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ NEI UL'-

Seismic Walkdown Checklist (SWC) SWELl- 018 Equipment ID No. DQ-ECCS-B Equip. Class' 14 - DISTRIBUTION PANELS Equipment Description 24 VDC EccS PNL (B)

Note: Cabinet opened 10/11/12 and re-inspection completed. One nut not engaged for 50% of thread.

No seismic concerns since 3 nuts are fully engaged.

EN-DC-168 REV 0

'V Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 95 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y0 NE] U-]

Seismic Walkdown Checklist (SWC) SWELl- 019 Equipment ID No. MCC-9C Equip. Class1 01 - Motor Control Centers Equipment Description 480V ESS AC MCC-9C - DIESEL 1A ROOM (S/I)

Location: Bldg. TB Floor El. 252 Room, Area EDG A Manufacturer, Model, Etc. (optional but recommended) Westinohouse. Type W 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 (.e., is the item one YZ NEI of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YZ NEI U[- N/A[]

On October 11, 2012 revisited the unit and removed upperand lower panels. With upperpanel removed was able to verify attachmentof angle to unit.

3. Is the anchorage free of corrosion that is more than mild surface Y0 NF- U[I N/A[-

oxidation?

On October 11, 2012 revisited the unit and removed upper and lower panels. With upperpanel removed was able to verify attachmentof angle to unit.

4. Is the anchorage free of visible cracks in the concrete near the Y0 NEI U[-] N/A-anchors?

Crack on eastside of the floor. The crack goes thru the grout pad and the comer of hduse pad (SE Corner). By engineeringjudgment the crack, hairline, is not a seismic issue. No photos of crack included because the crack was not visible in the picture.

Enter the equipment class name from EPRI 1025286, Append!x B:: Classes of Equipment.

EN-DC-168 REV 0

0 Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 96 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI UO Seismic Walkdown Checklist (SWC) SWELl- 019 Equipment ID No. MCC-9C Equip. Class1 01 - Motor Control Centers Equipment Description 480V ESS AC MCC-9C- DIESEL 1A ROOM (SII)

5. Is the anchorage configuration consistent with plant documentation? YZ NEI UE] N/AE-(Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See SK92403-06-A

6. Based on the above anchorage evaluations, is the anchorage free of Y0 NEI UEJ potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO NE-1 UE- N/AE]

8. Are overhead equipment, distribution systems, ceiling tiles and-lighting, YN NEI UEI N/AO and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ NEI UEI N/AE1

10. Based on the above seismic interaction evaluations, is equipment free Y[E NEI UF' of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

VI Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 97 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YN NIM UM]

Seismic Walkdown Checklist (SWC) SWELl- 019 Equipment ID No. MCC-9C Equip. Class1 01 - Motor Control Centers Equipment Description 480V ESS AC MCC-9C - DIESEL IA ROOM (SII)

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YN N[i Ut]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Two loose screws on front east side of cabinet. The screws still have positive attachmentand given the number and the weight of the cabinetdoor the system is acceptable.

See CR- VTY-2012-04816 for corrective action.

Reference Documents:

A46/IPEEE - SSEL Line No. 000085 Evaluated by: Marcus.Hecht.Nielsenie Date: 10-11-12 Raymond Tworek ~ ~~ L ID/I ICL 10-11-12 EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 98 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 4 of 5 Status: YED NO] ur]

Seismic Walkdown Checklist (SWC) SWELl- 019 Equipment ID No. MCC-9C Equip. Class1 01 - Motor Control Centers Equipment Description 480V ESS AC MCC-9C - DIESEL 1A ROOM (S$I)

Photographs NO PHOTO Note: Note:

EN-DC-168 REV 0

,9 Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 99 of 505 ATTACHMENT 9.6 -SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y[9 NO] UL]

Seismic Walkdown Checklist (SWC) SWELl- 019 Equipment ID No. MCC-9C Equip. Class1 01 - Motor Control Centers Equipment Description 480V ESS AC MCC-9C - DIESEL 1A ROOM (SII)

NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 100 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: Y0 NM ULI Seismic Walkdown Checklist (SWC) SWELl- 020 Equipment ID No, MCC-9D Equip. Class 1 01 Equipment Description 480V ESS AC MCC-9D - REACTOR BLDG Location: Bldg, RB Floor El. 252' Room, Area Reactor Buildno Manufacturer, Model, Etc. (optional but recommended) Westinghouse 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.

Anchoraoe

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

2. Is the anchorage free of bent, broken, missing or loose hardware? YZ NEI UE1 N/AZ Two small screws used to attach the South end panel are missing. See photo on sheet 5. Not a seismic concern as the modified anchorage securely attaches the end panel. The modified bolts are a replacement for the screws above it. The bolts clamping force far exceeds the fasteners (2 screws) clamping force. The end panel is securely fastened.

3. Is the anchorage free of corrosion that is more than mild surface YZ NEI UE- N/AZJ oxidation?

4, Is the anchorage free of visible cracks in the concrete near the YZ NEI ur] N/A[]

anchors?

IEnter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 101 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YN NI U[r]

Seismic Walkdown Checklist (SWC) SWELl- 020 Equipment ID No. MCC-9D Equip. Class1 01 Equipment Description 480V ESS AC MCC-9D - REACTOR BLDG

5. Is the anchorage configuration consistent with plant documentation? YE-I N3 UEI] N/AS (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 Y0D Nr- U[-]

potentially adverse seismic conditions?

The right upper panel was not opened due to interference concerns with internal components. Anchorage is secure at the bolted connections. No adverse seismic condition.

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y0 NEI Ur] N/AC"I

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NC"I UC" N/AC-and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ NCI UC' N/AC-

10. Based on the above seismic interaction evaluations, is equipment free YZ NEI U-of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 102 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ N" UE]

Seismic Walkdown Checklist (SWC) SWELl- 020 Equipment ID No. MCC-9D Equip. Class 1 01 Equipment Description 480V ESS AC MCC-9D - REACTOR BLDG Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ N[- U[-3 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Note: Originalinspection completed 10/04/2012. Re-inspected 10/11/2012 when cabinetpanels were opened by qualifiedplant personnel exposing the anchorageconnections.

Reference Documents:

A46/IPEEE - SSEL Line No. 000088 Evaluated by; Kirit Parikh 10 1 jZ/0Z- Date: 10/11/2012 Stephens-, :ýtjl%

Randy .4 I aM.z 10g 12012 10/11/2012 EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 103 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y] NO UL-Seismic Walkdown Checklist (SWC) SWELl- 020 Equipment ID No. MCC-9D Equip. Class1 01 Equipment Description 480V ESS AC MCC-9D - REACTOR BLDG Photoaraohe EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 104 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NM UM Seismic Walkdown Checklist (SWC) SWELl- 020 Equipment ID No, MCC-9D Equip. Class' 01 Equipment Description 480V E$S AC MCC-9D - REACTOR BLDG Note: Two small screws are missing from the Note: Re-inspected 10/11/12 when cabinetpanels South end of MCC-9D.See item I comment on were opened.

page 1.

EN-DC-168 REV 0

49 Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 105 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 1 of 5 Status: Y0 NE] Uf'-

Seismic Walkdown Checklist (SWC) SWELI- 021 Equipment ID No. MCC-8B Equip. Class' 01 Equipment Description 480V ESS AC MCC REACTOR BLDG (SI)

Location: Bldg. RB Floor El. 280' Room, Area Manufacturer, Model, Etc. (optional but recommended) Westinghouse. Time W Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchoraae

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

2. Is the anchorage free of bent, broken, missing or loose hardware? YZ NEI UO] N/AE-See comments.

3. Is the anchorage free of corrosion that is more than mild surface Y[9 NEI ur-] N/AF-oxidation?

See comments.

4, Is the anchorage free of visible cracks in the concrete near the YZ NE] UE" N/AF' anchors?

There Is a protective cover on the concrete and the concrete is not visible. However, the protective cover shows no signs of stress or cracking and Is seismically okay by engineeringjudgment.

IEnter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 106 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y[ NiE ur-Seismic Walkdown Checklist (SWC) SWELl- 021 Equipment ID No. MCC-8B Equip. Class 1 01 Equipment Description 480V ESS AC MCC-8B - REACTOR BLDG (SI)

5. Is the anchorage configuration consistent with plant documentation? YN NO Ul N/A" (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See drawing5920-11776

6. Based on the above anchorage evaluations, is the anchorage free of YZ NO UO[

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y] NE u[:] N/A-

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0 NE ur N/A-and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Y0 NEI ur N/AO

10. Based on the above seismic interaction evaluations, is equipment free YC9 NO UM of potentially adverse seismic interaction effects?

EN-DC-168 REVO0

• r Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 107 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YN NEI- U[-M Seismic Walkdown Checklist (SWC) SWELl- 021 Equipment ID No. MCC-8B Equip. Class' 01 Equipment Description 480V ESS AC MCC-8B - REACTOR BLDG (SI)

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Notes:

1. At the location where MCC 7A and 8B come together there are 3 loose screws and there is a screw missing on panel 8M. Neither issue is a seismic concern, see CR-VTY-2012-04979 for corrective action.

2. Was unable to view anchorageon 10-09-2012. Returned on 10-11-2012 and removed the bottom panels at locations IM, 4M, 6M, and 9M and top panels at 1C, 5C, 6B, and 1OBL, as well as, the verticalpanel between MCC 7A and MCC 8B come together. With the aid of a flashlight and a telescopic inspection mirror was able to verify anchorage.

Reference Documents:

Drawing 5920-11776, Sheets 1-2, Rev. 0 A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000090 Evaluated by: Marcus Hecht-Nielsen D : 10-11-2012 Date: 1 2 Ray-mond Tworek to fe -L-- 10-11-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 108 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NEI u17 Seismic Walkdown Checklist (SWC) SWELl- 021 Equipment ID No. MCC-8B Equip. Class' 01 Equipment Description 480V ESS AC MCC REACTOR BLDG (SO)

Photographs R~UM LUOSU uou.5 at cunnetrion ur 1W MCC7 EN-DC-168 REV 0

eI Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 109 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 5 of 5 Status: Y0 NEI Ur-1 Seismic Walkdown Checklist (SWC) SWELl- 021 Equipment ID No. MCC-88 Equip. Class' 01 Equipment Description 480V ESS AC MCC-8B - REACTOR BLDG (SI)

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 110 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: Y0 NOL U1" Seismic Walkdown Checklist (SWC) SWELl- 022 Equipment ID No. MCC-9B Equip. Class1 01 Equipment Description 480V ESS AC MCC REACTOR BLDG (811)

Location: Bldg. RB Floor El. 280' Room, Area 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.

Anchorsae

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y0 NEI UE1 N/AEC

3. Is the anchorage free of corrosion that is more than mild surface YZ NE] IM- N/A[-C oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YZ Nil LIE- N/A['

anchors?

There is a protective cover on the concrete and the concrete Is not visible. However, the protective cover shows no signs of stress or cracking and is seismically okay by engineeringjudgment.

IEnter the equipment class name from EPRI 1025286. Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 111 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y9 NEI UF-]

Seismic Walkdown Checklist (SWC) SWELl- 022 Equipment ID No. MCC-9B Equip. Class 1 01 Equipment Description 480V ESS AC MCC-9B - REACTOR BLDG (S11)

5. Is the anchorage configuration consistent with plant documentation? Y0 NDI uiD N/ADI (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See drawing 5920-11776

6. Based on the above anchorage evaluations, is the anchorage free of YE ND] ur7 potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YIj N[] U-1 N/A-'

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ N[-1 Ur7 N/AD]

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ( N[- U'- N/AD-

10. Based on the above seismic Interaction evaluations, Is equipment free YV NEI U-I of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 112 of 505 ATTACHMENT 9.6 SEISMIC'WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y0* Nil U12 (SWC) SWELl- 022 Seismic Walkdown Checklist Equipment ID No. MCC-98 Equip. Class 1 01 Equipment Description 48OVESSAC MCC-9B - REACTOR BLDG (S11)

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 N[-] UE-adversely affect the safety functions of the equipment?

Loose screws between rows 1C to IM and 2C to 2M. 10-18-2012 Went to verify that the electrician tightened all the screw (on 10-11-2012 while we were opening the panels to verify anchorage) and all screws are tight.

Comments (Additional pages may be added as necessary)

Notes:

1. Was unable to view anchorageon 10-09-2012. Returned on 10-11-2012 and removed the bottom panels at locations IM, 5M, 8M, 9M, and I IM and top panels at 2C, 5C, 7C, and lOB, as well as, the verticalpanel between MCC 6 and MCC 9 come together. With the aid of a flashlight anda telescopic Inspection mirrorwas able to verify anchorage.

Reference Documents:

Drawing5920711776, Sheets 1-2, Rev.0 A46/1PEEE - Screening Evaluation Work Sheet, SSEL Line No. 000092 Evaluated by: Marcus Hecht-NleZsen g Date: 10-11.2012 Raymond Tworak toll t 10-11-20.12 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 113 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NM] ur-Seismic Walkdown Checklist (SWC) SWELl- 022 Equipment ID No. MCC-9B Equip. Class1 01 Equipment Description 48OV ESS AC MCC.9B - REACTOR BLDG (SI)

Photographs EN-DC-168 REV 0

Attnrwhmnnt r Engineering Report VTY-RPT-12-00019 Rev. 0 Page 114 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y[] N5] UEJ (SWC) SWEWl1- 022 Seismic Walkdown Checklist Equipment ID No. MCC-9B Equip. Class1 01 Equipment Description 480V ESS AC MCC-9B - REACTOR BLDG (S/I)

NO PHOTO NO PHOTO Note: Note:

EN-DC-1 68 REV 0

9 f Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 115 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: Y[ NEI Uf]

Seismic Walkdown Checklist (SWC) SWELl- 023 Equipment ID No. BUS-9 Equip. Class' 02 Equipment Description 480VAC SWITCHGEAR BUS NO.9 1600AMP (SI/)

Location: Bldg. CB Floor El, 248' Room, Area SWGR EAST Manufacturer, Model, Etc. (optional but recommended) GEAKD-5 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 YE] N[R of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YE] NE] UEI N/A0

3. Is the anchorage free of corrosion that is more than mild surface Y[E N[-E] uE- N/AZ oxidation?

4. Is the anchorage free of visible cracks in the concrete near the Y1] N7] uL] N/AZ anchors?

IEnter the equipment class name from EPRI 1025286, Appendix B: Classes of EquipmenL EN-DC-1 68 REV 0

9..

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 116 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 2 of 5 Status: YN NO U[-

Seismic Walkdown Checklist (SWC) SWELl- 023 Equipment ID No. BUS-9 Equip. Class' 02 Equipment Description 480VAC SWITCHGEAR BUS NO.9 1600AMP (SI!)

5. Is the anchorage configuration consistent with plant documentation? YE-' NEI UE N/A (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

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

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YZ NE uE"] N/AE:]

8. Are overhead equipment, distribution systems, ceiling tiles and Ilghting, YN NE U[E] N/AE and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YN NE- UE] N/AE

10. Based on the above seismic interaction evaluations, is equipment free YN NO U-of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 117 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ NO] Ur" Seismic Walkdown Checklist (SWC) SWELl- 023 Equipment ID No. BUS-9 Equip. Class 1 02 Eouioment Descrintion 480V AC SWITCHGEAR BUS NO.9 I600AMP (Sil)

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 N[3 Ur" adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Marcus He ht-Nielsen , Date: 10-09"2012 Raymond Tworek , ,o1r 10-09-2012 EN-DC-168 REV 0

0 Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 118 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FO,,

Sheet 4 of 5 Status: Y0 NEI ur" Seismic Walkdown Checklist (SWC) SWELl- 023 Equipment ID No. BUS-9 Equip. Class' 02 Equipment Descr*ptlon 480VAC SWITCHGEAR BUS NO.9 1600AMP (S§1)

Photographs NO PHOTO Note:

EN-DC-168 REV 0

Affnrthmrnf r Engineering Report VTY-RPT-12-00019 Rev. 0 Page 119 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0* N[E] Ul-']

(SWC) SWELl- 023 Seismic Walkdown Checklist Equipment ID No. BUS-9 Equip. Class1 02 Equipment Description 480VAC SWITCHGEAR BUS NO.9 1600AMP (SII)

NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 120 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YN NEI UM Seismic Walkdown Checklist (SWC) SWELl- 024 Equipment ID No. BUS-3 Equip. Class 1 03 Equipment Description 4KV- 416OVSWITCHGEAR BUS NO.3 1200AMP (SO)

Location: Bldg. CB Floor El. 248' Room, Area SWGR WEST Manufacturer, Model, Etc. (optional but recommended) GE 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 Y[-I NO of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YE- NEi uEr N/A0

3. Is the anchorage free of corrosion that is more than mild surface YEr NE- UE] N/AZ oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YEI NEI U'- N/AZ anchors?

' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

4.

OF Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 121 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y*; N"! UE-'

(SWC) SWELl- 024 Seismic Walkdown Checklist Equipment ID No. BUS-3 Equip. Class' 03 Equipment Description 4KV- 4160V SWITCHGEAR BUS NO.3 1200AMP (SI)

5. Is the anchorage configuration consistent with plant documentation? YE3 NE:] UE N/AZ (Note: This question only applies if the item is one of the 50%.for which anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Y0 NEI UE]

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y[] NEi UE" N/AE"

8. Are overhead equipment, distribution systems, ceiling files and lighting, YZ NEl urE] N/AE-and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ N[ u3 N/AU

10. Based on the above seismic interaction evaluations, is equipment free Y0*Nr"CU[

of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

.2. Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 122 of 505 ATTACHMENT 9.6 ,SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Yv NEI url Seismic Walkdown Checklist (SWC) SWELl- 024 Equipment ID No. BUS-3 Equip. Class ' 03 Eaulnment Description 4KV- 4160V SWITCHGEAR BUS NO.3 1200AMP (SI)

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Reference Documents:

A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000096 Evaluated by: Marcus Hecht-Nielsen Date: 10-09-2012 RavmondLworek ~IvAiRJ4 to/t T/ 10-09-2012 EN-DC-1 68 REV 0

'f Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 123 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0D N[] Ur-Seismic Walkdown Checklist (SWC) SWELl- 024 Equipment ID No. BUVS-3 Equip. Class' 03 Equipment Description 4KV- 4160V SWITCHGEAR BUS NO.3 1200AMP (S/)

Photographs NO PHOTO Note:

EN-DC-188 REV 0

Attnr.hmnnt *,

Engineering Report VTY-RPT-12-00019 Rev. 0 Page 124 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y[* Nj] UEI (SWC) SWELl- 024 Seismic Walkdown Checklist Equipment ID No. BUS-3 Equip. Class1 03 Equipment Description 4KV- 4160V SWITCHGEAR BUS NO.3 1200AMP (SI)

NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C e Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 125 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRM Sheet 1 of 5 Status: YZ NEI- UE-Seismic Walkdown Checklist (SWC) SWELl- 025 Equipment ID No. T-8-1A Equip. Class1 04 Equipment Description STATION SERVICE TRANS 4160/480 BUS NO.8 Location: Bldg. CB Floor El. 248' Room, Area SWGR WEST Manufacturer, Model, Etc. (optional but recommended) ASEA BROWN BOVERI # PAL2721. 3 phase, type RSL 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 YZ NEI of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YO NEI U'- N/AC:]

3. Is the anchorage free of corrosion that is more than mild surface YZ NEI Ur1 N/ACI oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YZ NOi U- N/A"1 anchors?

Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 126 of 505 ATrACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YN NEI UrM Seismic Walkdown Checklist (SWC) SWELl- 025 Equipment ID No. T-8-1A Equip. Class1 04 Equipment Description STATION SERVICE TRANS 4160/480 BUS NO.8

5. Is the anchorage configuration consistent with plant documentation? YZ Nil U-- N/A["C (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See calculation VYC - 1046

6. Based on the above anchorage evaluations, is the anchorage free of YU NE! UI' potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y[9 NED U[C N/A[]

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y] NC UC N/AC and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Y] NO U- N/AC

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

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 127 of 505 ATTACHMEINT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ NEI UM Seismic Walkdown Checklist (SWC) SWELl- 025 Equipment ID No. T-8-1A Equip. Class' 04 Equipment Description STATION SERVICE TRANS 4160/480 BUS NO.8 Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y9 NEIUO adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference Documents:

A46/IPEEE- Screening Evaluation Work Sheet, SSEL Line No. 000101 CalculationVYC - 1046 Evaluated by: Marcus Hecht-Nielsen 4e ./..

o/-Date: 10-09-2012 Raymond Tworek SN9 M.,hr W4 4 A izVIiir-%- 10-09-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 128 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 4 of 5 Status: YO NEI UEr Seismic Walkdown Checklist (SWC) SWELl- 025 Equipment ID No. T-8-1A Equip. Class' 04 Equipment Description STATION SERVICE TRANS 4160/480 BUS NO.8 Photographs MOTO. I- 7-1A EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 129 of 505 ATTACHMENT 9.6 SEISMIC .WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YS NOt U7-Seismic Walkdown Checklist (SWC) SWELl- 025 Equipment ID No. T-8-1A Equip. Class 1 04 Equipment Description STATION SERVICE TRANS 4160/480 BUS NO.8 NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 130 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YO NEI U7 Seismic Walkdown Checklist (SWC) SWELl- 026 Equipment ID No. TK-4-1A Equip. Class1 21 Equipment Description CONDENSATE STORAGE TANK Location: Bldg. YARD Floor El. 252' Room, Area OUTSIDE 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.

Anchoraqe

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

2. Is the anchorage free of bent, broken, missing or loose hardware? YO NEI U[3 N/A[D Entire tank covered with insulation.Anchorage is not visible. Cannot be determined that these are true but evidence of visual inspection around the tank and the nearby areas,indicates that anchorageis free of bent, broken, missing or loose hardware.

3. Is the anchorage free of corrosion that is more than mild surface Y[O NEI UD" N/AD-1 oxidation?

Same as above

4. Is the anchorage free of visible cracks'in the concrete near the Y[; ND1 UrJ N/AD-anchors?

No cracks in the concrete base.

'Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 131 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NE3 UM Seismic Walkdown Checklist (SWC) SWELl- 026 EquipmentID No. TK-4-1A Equip. Class1 21 Equipment Description CONDENSATE STORAGE TANK

5. Is the anchorage configuration consistent with plant documentation? "YE" NE- UE- N/A]

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

6.- Based on the above anchorage evaluations, is the anchorage free of YC@ NE] UE]

potentially adverse seismic conditions?

Entire tank covered with insulation.Anchorage Is not visible.

However, based on reviewing equipment documentation (see reference page 3) and seeing no modifications surroundingthe anchorage,it Is our engineeringjudgment through area walkdown and visual Inspections that no adverse seismic condition exists.

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YE3 NEI UE N/AS No soft target found.

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UE[ N/AE-]

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Y ] N[I U[-] N/A[E

10. Based on the above seismic interaction evaluations, is equipment free Y9 NE: UEl of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 132 of 505 ATTACHMENT 9.6 SEISMIC WALKD0WN CHECKLIST FORM Sheet 3 of 5 Status: Y0R NEI UC]

Seismic Walkdown Checklist (SWC) SWELl- 026 Equipment ID No. TK-4-1A Equip. Class1 21 Equipment Description CONDENSATE STORAGE TANK Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y; N[] urI adversely affect the safety functions of the equipment?

No adverse condition around the tank.

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawings: G- 191605,G- 191603, G- 191630, 5920-3589, 5920-3596, and 5920-3588 A46//PEEE- Screening Evaluation Work Sheet, SSEL Line No, 000103 Evaluated by: Kirlt Parlkh ~,; /eL~ /Olle 12XI / 2- Date: 10/02/2012 Randy Stephens 44*J " / /' 2(." 10/02/2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 133 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y19 ND- U" Seismic Walkdown Checklist (SWC) SWEL*- 026 Equipment ID No. TK-4-1A Equip. Class1 21 Equipment Description CONDENSATE STORAGE TANK Photograph.

moire: (,onoensare zrorage /fanK- ,Ancnorage covered by insulation. No visible cracks aroundthe tank foundation EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 134 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 5 of 5 Status: YZ NO UM Seismic Walkdown Checklist (SWC) SWELl- 026 Equipment ID No. TK-4-1A Equip. Class1 21 Equipment Description CONDENSATE STORAGE TANK NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 135 of 505 ATTACHMEI NT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YZ NEI UEI Seismic Walkdown Checklist (SWC) - SWELl- 027 Equipment ID No. P.44-1A Equip. Class 1 0-5 HORIZONTAL PUMPS Equipment Description HPCI/HPCIPUMP Location: Bldg. RB Floor El. 213' Room, Area HPCI 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.

Anchoraae

1. Is the anchorage configuration verification required (i.e., is the item one YZ N[-'

of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YO NC[ Ui N/Al:

3. Is the anchorage free of corrosion that is more than mild surface YCD N'- Uil N/A[--

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YZ NO u-- N/A[]

anchors?

• Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 136 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI U" Seismic Walkdown Checklist (SWC) SWELl- 027 Equipment ID No. P-44-IA Equip. Class1 0-5 HORIZONTAL PUMPS Equipment Description HPCI/HPCIPUMP

5. Is the anchorage configuration consistent with plant documentation? YZ NEI U' N/A"]

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

See SSEL Line No, 000116 (andassociatedcalculation)and drawing No. 5920-0622.

6, Based on the above anchorage evaluations, is the anchorage free of Y[; N["] UF-potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y[9 NEI UF1 N/A[E

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y9 NE UE] N/A and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YO NEI UEI N/AEl

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

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 137 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Yl Ni] UI-Seismic Walkdown Checklist (SWC) SWELl- 027 Equipment ID No. P.44-.A Equip. Class 1 0-5 HORIZONTAL PUMPS Eauioment Description HPCI/HPCIPUMP Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ N[] UE]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000116 Drawing No. 5920-0622 Evaluated by: Kifit Parikh I 6-I tIIe{to 2-D ate: 10/09/2012 Randy Steg gng t ( z z 10/09/2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 138 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YN Nr-'D UE' Seismic Walkdown Checklist (SWC) SWEl1- 027 Equipment ID No. P-44-1A Equip. Class' 0-5 HORIZONTAL PUMPS Equipment Description HPCI/HPCIPUMP Photographs NO PHOTO Note:

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 139 of 505 ATrACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y; NEI UI-Seismic Walkdown Checklist (SWC) SWELl- 027 Equipment ID No. P A Equip. Class1 0-5 HORIZONTAL PUMPS Equipment Description HPCI/HPCIPUMP EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 140 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YZ N[] U-J Seismic Walkdown Checklist (SWC) SWELl- 028-Equipment ID No. PS-23-84-1 Equip. Class1 18- INSTRUMENTS ON THE RACK Equipment Description HPCI/PUMPSUCTION PRESSURE SWITCH Location: Bldg. B Floor El. 213' Room, Area HPCI 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

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y[9 NEI U- N/AE

3. Is the anchorage free of corrosion that is more than mild surface YS NE U- N/AD oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YZ NEI U[] N/Ar-anchors?

I Enter Ihe equipment class name from EPRI 1025286. Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 141 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y; NEI U-'

Seismic Walkdown Checklist (SWC) SWELl- 028 Equipment ID No. PS-23-84.1 Equip. Class1 18- INSTRUMENTS ON THE RACK Equipment Description HPCI/PUMPSUCTIONPRESSURE SWITCH

5. Is the anchorage configuration consistent with plant documentation? YEE NEI UE- N/A--

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

See SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks

6. Based on the above anchorage evaluations, is the anchorage free of Y0 NEI UE-potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y[O NEI UE- N/AEF-

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[9 NE UEr N/AE1 and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibifity to avoid damage? YN NE1 u[- N/A[-]

10. Based on the above seismic interaction evaluations, is equipment free YN NEI Ur:

of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 142 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Yv NE] uM Seismic Walkdown Checklist (SWC) SWELl- 028 Equipment ID No. PS-23.84-1 Equip. Class1 18- INSTRUMENTS ON THE RACK Equipment Description HPCI/PUMPSUCTIONPRESSURE SWITCH Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y9 NEI UE-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

A46/IPEEE- Screening Evaluation Work Sheet, SSEL Line No. 000125 SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks Evaluated by: Kiit Parikh 6JQ ý ol12-2-iI ite: 10/09/2012

.Ran&,,Stebhensag eL izj~ ~ sw. 10/09/2012 EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 143 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YS NEI UM Seismic Walkdown Checklist (SWC) SWELI- 028 Equipment ID No. PS-23-84-1 Equip. Class' 18- INSTRUMENTS ON THE RACK Equipment Description HPCI/PUMPSUCTIONPRE$SSURE SWITCH Photographs NO PHOTO Note:

EN-DC-168 REV 0

Attn*hm*.nt Engineering Report VTY-RPT-12-00019 Rev. 0 Page 144 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YI* NE-J UI-(SWC) SWELl- 028 Seismic Walkdown Checklist Equipment ID No. PS-23-84-1 Equip. Class1 18- INSTRUMENTS ON THE RACK Equipment Description HPCI/PUMPSUCTIONPRESSURE SWITCH NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 145 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y0 NEI UE]

Seismic Walkdown Checklist (SWC) SWEL!- 031 Equipment ID No. TEF-3 Equip. Class' 09 Equipment Description DG B ROOM VENTILATION/EXAUST FAN Location: Bldg. TB Floor El. 252' Room, Area EDGR B 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, Anchoraae

1. Is the anchorage configuration verification required (iLe., Is the item one YZ NI-of the 50% of SWEL items requiring such verification)?

2. is the anchorage free of bent, broken, missing or loose hardware? YZ N[] U'- N/A[d

3. Is the anchorage free of corrosion that is more than mild surface YZ NC3 ULI N/AI-oxidation?

4. Is the anchorage free of visible cracks in the concrete near the Y[9 NE- UE- N/A[]

anchors?

There is a hairlinecrack in the upper right hand comer. No seismic concern by engineeringjudgment.

IEnter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

T Attachment C V1 Engineering Report VTY-RPT-12-00019 Rev. 0 Page 146 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 NEI U[-_

Seismic Walkdown Checklist (SWC) SWELl- 031 Equipment ID No. TEF-3 Equip. Class' 09 Equipment Description DG B ROOM VENTILA TION/EXAUST FAN

5. Is the anchorage configuration consistent with plant documentation? YZ NEI Ur] N/AE" (Note: This question only applies if the Item is one of the 50% for which anchorage configuration verification is required.)

See A46/IPEEE -Screening Evaluation Work Sheet, SSEL Line No.

000145

6. Based on the above anchorage evaluations, is the anchorage free of Y0 NO: UO-"

potentially adverse seismic conditions?

Rule of the box used for motor.

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?. YEI NiO U-" N/AO

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEI U-] N/AD and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YO N-- U[-] N/AE

10. Based on the above seismic interaction evaluations, is equipment free YN NEI UI' of potentially adverse seismic interaction effects?

EN-DC-1 68 REV 0

P Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 147 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YO NE] UEI Seismic Walkdown Checklist (SWC) SWELl- 031 Equipment ID No. TEF.3 Equip. Class' 09 Equipment Description DO B ROOM VENTILA TION/EXAUST FAN Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawing5920-4449 A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. ooo045 Evaluated by: Marcus Hecht4Vielsen __,_,_Date: 10-03-2012 Rayinond Tworek  :ý .- Lo14)tIr (-~- 10-03-2012 EN-DC-168 REV 0

6*

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 148 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NI7 UM Seismic Walkdown Checklist (SWC) SWELl- 031 Equipment ID No. TEF-3 Equip. Class1 09 Equipment Description DG B ROOM VENTILA TION/EXAUST FAN Photographs Note: 7 EN-DC-168 REV 0 I

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKJ3LT M 505 Sheet 5 of 5 Status: YS NED U-Seismic Walkdown Checklist (SWC) SWELl- 031 Equipment ID No. TEF.3 Equip. Class' 09 Equipment Description DG B ROOM VENTILATION/EXAUST FAN No Photo No Photo Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 150 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: Y[ NiE UE-'

Seismic Walkdown Checklist (SWC) SWELl- 032 Equipment ID No. RRU-8 Equip. Class' 10 Equipment Description SW/ECCS RM COOLING Location: Bldg. RB Floor El. 213' Room, Area SECR Manufacturer, Model, Etc. (optional but recommended) HK PORTER-MARLO COIL WORKS, Model # 41-523-H 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 Y-- NED of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YZ NEI UED NIAI"

3. Is the anchorage free of corrosion that is more than mild surface YZ N- U-' N/AD oxidation?

4. Is the anchorage free of Visible cracks in the concrete near the YIZ NEI UD! N/A-anchors?

Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipmen.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 151 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YO NO UE-1 Seismic Walkdown Checklist (SWC) SWELl- 032 Equipment IDNo. RRU-8 Equip. Class' 10 Equipment Description SW/ECCS RM COOLING

5. Is the anchorage configuration consistent with plant documentation? YE NEI UE" N/AZ (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 Y[9 NEi UE]

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y0 N[-] UM N/A-'

8. Are overhead equipment, distribution systems, ceiling tiles and lighfing, YN NEI U- N/AE-]

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ NEI U-- N/AC'

10. Based on the above seismic interaction evaluations, is equipment free YO NEi UE-of potentially adverse seismic interaction effects?

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 152 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y[9 NEJ U0i Seismic Walkdown Checklist (SWC) SWELl- 032 Equipment ID No. RRU-8 Equip. Class' 10 Equipment Description SW/ECCS RM COOLING Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YN NE] UM adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference Documents:

A46//PEEE- SSEL Line No. 000164 Evaluated by: Kirit Parikh 10 llg-f zo lz Date: 10/11/2012 RangkSteens., ,ý L.cz 1t,(Icwt 10/11/2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 153 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0 Nr" U-]

Seismic Walkdown Checklist (SWC) SWELl- 032 Equipment ID No. RRU-8 Equip. Class' 10 Equipment Description SW/ECCS RM COOLNG Photographs 1II EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 154 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ NEI UEr Seismic Walkdown Checklist (SWC) SWELl- 032 Equipment ID No. RRU-8 Equip. Class 1 10 Equipment Description SW/ECCS RM COOLING NO PHOTO NO PHOTO Note: Note:

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 155 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YE NC UC-Seismic Walkdown Checklist (SWC) SWELl- 033 Equipment ID No. PT-2-3-52C Equip. Class 1 18 Equipment Description CS, RHR PERMISSIVE Location: Bldg. RB Floor El. 252' Room, Area 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.

Anchoracqe

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y9 NC UC-'] N/AC

3. Is the anchorage free of corrosion that is more than mild surface Y0 NCI UC N/AC oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YC NCI UCI N/AZ anchors?

Equipment has a steel attachment.

'Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 156 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YO NEI U7 Seismic Walkdown Checklist (SWC) SWELl- 033 Equipment ID No. PT-2-3-52C Equip. Class' 18 Equipment Description CS, RHR PERMISSIVE

5. Is the anchorage configuration consistent with plant documentation? Y] NEI "UM' N/Ar-(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required,)

See SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks.

6. Based on the above anchorage evaluations, is the anchorage free of Y[ NE] U-'

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YZ NEI U[3 N/AEI

8. Are overhead equipment, distribution systems,ceiling tiles and lighting, YZ NEI uE- N/A[I and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Y[Z NF-] UF- N/A["'

YN NE" uENA

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

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 157 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ N(I ULI Seismic Walkdown Checklist (SWC) SWELl- 033 Equipment ID No. PT-2-3-52C Equip. Class' 18 Equipment Description CS, RHR PERMISSIVE Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 NFI U-]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference Documents:

Drawing 5920-6200, Rev. 0 A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000174 SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks.

Evaluated by: Marcus Hecht-Nielsen.-i , Date: 10-04-2012 Raymond Tworek PeF^ý Lo IIrflý 10-04-2012 EN-DC-168 REV 0

0 Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 158 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NiM U[]

Seismic Walkdown Checklist (SWC) SWELl- 033 Equipment ID No. PT-2-3-52C Equip. Class1 18 Equipment Description CS RHR PERMISSIVE Photographs NO PHOTO Note: PT Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 159 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y[*; Ni UC-(SWC) SWELl- 033 Seismic Walkdown Checklist Equipment ID No. PT-2-3-52C Equip. Class1 18 Equipment Description CS, RHR PERMISSIVE NO PHOTO NO PHOTO Note: Note:

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 160 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YZ NEI U7 Seismic Walkdown Checklist (SWC) SWELl- 034 Equipment ID No. LT-107-5A Equip. Class' 18 Equipment Description CST/LEVEL TRANSMITTER Location: Bldg. CST Valve Floor El. 252' Room, Area 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 YS NEI of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YN NEI U[-] N/AE

3. Is the anchorage free of corrosion that is more than mild surface YZ NE] U[-E N/A[]

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the Y[ NEI UE] N/AE1 anchors?

I Enter the equipment class name from EPRI 1025286, Appendix B: Classes of .quipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 161 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0Z NEI- U1-Seismic Walkdown Checklist (SWC) SWELl- 034 Equipment ID No. LT-107-5A Equip. Class' 18 Equipment Description CST/LEVEL TRANSMITTER

5. Is the anchorage configuration consistent with plant documentation? YZ NEI Ur- N/ArI (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See drawing 5920-6041

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

Interaction Effects

7. Are soft targets free from Impact by nearby equipment or structures? Y9 NE UEI] N/AF-

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y ] NEI U[-] N/A[-]

and masonry block walls not likely to collapse onto the equipment?

9, Do attached lines have adequate flexibility to avoid damage? Y] NEI U-] N/A-C

10. Based on the above seismic interaction evaluations, is equipment free Y] N'] UM of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 162 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y[D NEI uF-Seismic Walkdown Checklist (SWC) SWELl- 034 Equipment ID No. LT-107-5A Equip. Class 1 18 Equipment Description CST/LEVEL TRANSMITTER Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y[0 NEI U7 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawings: 5920-6041 A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000176 Evaluated by: Marcus Hecht-Nielsen , Date: 10-02-2012 Raymond Tworek ~ 4 LoIV 10-02-2012 EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 163 of 505 ATTACHMENT 9.5 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NO UrM Seismic Walkdown Checklist (SWC) SWELl- 034 Equipment ID No. LT-107-5A Equip. Class' 18 Equipment Description CST/LEVEL TRANSMITTER Photographs NO PHOTO Note: LT- Note:

EN-DC.168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 164 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN.CHECKLIST FORM Sheet 5 of 5 Status: Y0 Nn U-'

Seismic Walkdown Checklist (SWC) SWELl- 034 Equipment ID No. LT-107-5A Equip. Class' 18 Equipment Description CST/LEVEL TRANSMITTER NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

. ifI Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 165 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YZ NEI Ur" Seismic Walkdown Checklist (SWC) SWELl- 035 Equipment IDNo. LT-1O7-58 Equip. Class1 18 Equipment Description CST/LEVEL TRANSMITTER Location: Bidg. CST Valve Floor El. 252' Room, Area 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.

Anchoraae

1. Is the anchorage configuration verification required (I.e., Is the Item one YN NEI of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Y21 NE] U[:] N/AF"

3. Is the anchorage free of corrosion that is more than mild surface YN NEI U[r] N/A[]

oxidation?.

4. Is the anchorage free of visible cracks in the concrete near the YO NEi UE"1 N/A[-

anchors?

Enter the equipment class name from EPRI 1025286, Appendix B; Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 166 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 NEI ULI Seismic Walkdown Checklist (SWC) SWELl- 035 Equipment ID No. LT-107-5B Equip. Class ' 18 Equipment Description CST/LEVEL TRANSMITTER

5. Is the anchorage configuration consistent with plant documentation? YZ NE3 UE- N/AE-(Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See drawing 5920-6041

6. Based on the above anchorage evaluations, is the anchorage free of YZ N[] U(-]

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from Impact by nearby equipment or structures? YN NE U[E1 N/A[-]

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEl U[E N/A[--

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YS N[-] UE] N/A--

10. Based on the above seismic interaction evaluations, is equipment free YN NE: UE-of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

!ýi Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 167 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ NEI UM Seismic Walkdown Checklist (SWC) SWELl- 035 Equipment ID No. LT-107-5B Equip. Class 1 18 Equipment Description CST/LEVEL TRANSMITTER Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ N[3 UE-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawings: 5920-6041 A46/IPEEE-.ScreeningEvaluation Work Sheet, SSEL Line No. 000177 Evaluated by: Marcus Hecht-Nielsen Date: 10-02-2012 Raymond Tworek fWLC~jif' 10-02-2012 EN-DC-168 REV 0

o! Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 168 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0 NEI U-Seismic Walkdown Checklist (SWC) SWELl- 035 Equipment ID No. LT-107-SB Equip. Class' 18 Equipment Description CST/LEVEL TRANSMITTER Photographs Note: LT-10; EN-DC-168 REV 0

.f Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 169 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ N-I UM Seismic Walkdown Checklist (SWC) SWELl- 035 Equipment ID No. LT-107-5B Equip. Class' 18 Equipment Description CST/LEVEL TRANSMITTER NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

-1 V..

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 170 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YZ NEI UL-'

Seismic Walkdown Checklist (SWC) SWELl- 036 Equipment ID No. PT-10-1OA Equip. Class' 18 Equipment Description DW PRESSURE ECCS Location: Bldg. RB Floor El. 280' Room, Area 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

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y0R N[I UE N/A[I

3. Is'the anchorage free of corrosion that is more than mild surface YZ NO UEI N/A[E oxidation?

4. Is the anchorage free of visible cracks in the concrete near the Y[D NE3 UM N/A[K anchors?

Attached to rack.

Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-1 68 REV 0

.Jý Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 171 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YN NO- UL-Seismic Walkdown Checklist (SWC) SWELl- 036 Equipment ID No. PT-10-1OIA Equip. Class' 18 Equipment Description DW PRESSURE ECCS

5. Is the anchorage configuration consistent with plant documentation? YZ N[: UE] N/AE!

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

See SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks

6. Based on the above anchorage evaluations, is the anchorage free of Y0 N[E! U[:-

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y0 NEI U[3 N/A[!

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[ N[-! UE N/A[]

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Y] NEI ur] N/AE!

10. Based on the above seismic interaction evaluatlonsjs equipment free Y] NO UE!

of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 172 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y0 NI] UEI Seismic Walkdown Checklist (SWC) SWELl- 036 Equipment ID No. PT-I1-1OIA Equip. Class 1 18 Equipment Description DW PRESSURE ECCS Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YO NfE U[f adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawings: 5920-3016, 5920-3017, 5920-3018, and sketch no. SK-VY-94411-1 A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000178 SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks Evaluated by: Marcus Hecht-Nielsen -- Date: 10-09-2012

........ Twrn 10-09-2012 Ravrnond Tworak I ~'

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 173 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NEI UM Seismic Walkdown Checklist (SWC) SWEL1- 038 Equipment ID No. PT-10-1O1A Equip. Class1 18 Equipment Description DW PRESSURE ECMS Photographs Note: PT-10-IOIA EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 174 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YN NEI UI-Seismic Walkdown Checklist (SWC) SWELl- 036 Equipment ID No. PT-10-10A Equip. Class1 18 Equipment Description DW PRESSURE ECCS NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 175 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YED NEI- UF Seismic Walkdown Checklist (SWC) SWELl- 037 Equipment ID No. PT-10-IOIC Equip. Class' 18 Equipment Description DW PRESSURE ECCS Location: Bldg. RB Floor El. 280' Room, Area 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.

Anchoraae I.

1. Is the anchorage configuration verification required (i.e., is the item one Y1 NO of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YZ NEI U[I N/AO

3. Is the anchorage free of corrosion that is more than mild surface Y0 NE:] U-I N/AE1 oxidation?

4. Is the anchorage free of visible cracks in the concrete near the Y-- NEI UE- NWA anchors?

Attached to rack.

' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 176 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 2 of 5 Status: Y'0 NEI U-1 Seismic Walkdown Checklist (SWC) SWELl- 037 Equipment ID No. PT-1O-101C Equip. Class' 18 Equipment Description DW PRESSURE ECCS

5. Is the anchorage configuration consistent with plant documentation? Y] NDI U-] N/AD3 (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks

6. Based on the above anchorage evaluations, is the anchorage free of Y[ NDI UD]

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from Impact by nearby equipment or structures? YZ NEI U[D N/AD-

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ Nn U-Q N/A[D and masonry block walls not likely to collapse onto the equipment?

9, Do attached lines have adequate flexibility to avoid damage? YO ND'] UD- N/A[D

10. Based on the above seismic interaction evaluations, ,s equipment free YZ N-- U-of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 177 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YER NEI UE-Seismic Walkdown Checklist (SWC) SWELl- 037 Equipment ID No. PT-10.101C Equip. Class1 18 Equipment Description DW PRESSURE ECCS Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y[K NC] U[]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawings: 5920-3016, 5920-3017, 5920-3018, and sketch no. SK-VY-944 11-1 A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000180 SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks Evaluated by: Marcus Hecht-Nielsen ... Date: 10-09-2012 Raymond Tworek w , i r P IVj 10-09-2012 EN-DC-168 REV 0

$r Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 178 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 4 of 5 Status: YN NEI U-'

Seismic Walkdown Checklist (SWC) SWELl- 037 Equipment ID No. PT-1O-101C Equip. Class1 18 Equipment Description DW PRESSURE ECCS Photographs NO PHOTO Note: PT-1O- Note:

EN-DC-168 REV 0 I

P.

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 179 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ NEI UM Seismic Walkdown Checklist (SWC) SWELl-Equipment ID No. PT-10-IO1C IEquip. Class1 Equipment Description DW PRESSURE ECCS EN-DC-I 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 180 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet I of 5 Status: YE NE] U"]

Seismic Walkdown Checklist (SWC) SWELl- 038 Equipment ID No. PT-16-19-29A Equip. Class' 18 Equipment Description DW PRESSURE INDICATION Location: Bldg. RB Floor El. 2 .0' Room, Area 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.

Anchoraoe

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

2. Is the anchorage free of bent; broken, missing or loose hardware? YN N[1 U- N/AEI

3. Is the anchorage free of corrosion that is more than mild surface YCK NEi UC- N/AC-]

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YEI NE- UCI N/AZ anchors?

Attached to rack.

'Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DCo168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 181 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI U[3 Seismic Walkdown Checklist (SWC) SWELl- 038 Equipment ID No. PT-16-19-29A Equip. Class' 18 Equipment Description DW PRESSURE INDICA TION

5. Is the anchorage configuration consistent with plant documentation? Y0 N[] U[] N/AF-(Note: This question only applies if the item Is one of the 50% for which anchorage configuration verification Is required.)

See SQUG, November 9-13, 1992, Section V87, Equipment Category 7 Instruments on Racks

6. Based on the above anchorage evaluations, Is the anchorage free of YE NE] Ur' potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y[D N[: U-] N/A[-

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NM U[-1 N/AC3 and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Y[ N[D U[D N/Al!

10. Based on the above seismic'interaction evaluations, is equipment free Y[D NEI UE1 of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 182 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YED NEI UE-Seismic Walkdown Checklist (SWC) SWELl- 038 Equipment ID No. PT-16-19-29A Equip. Class' 18 Equipment Description DW PRESSURE INDICATION Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 NEI UEJ adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawings: 5920-3016, 5920-3017, 5920-3018, and sketch no. SK- VY-944 11-1 A46//PEEE - Screening Evaluation Work Sheet, SSEL Line No. 000182 SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks Evaluated by: Marcus Hecht-Nielsen Date: 10-09-2012 Raymond Tworek

-I QAm -, -J I m I

-,4-I I 1-P/ "r I (I--

J I 10-09-2012 EN-DC-168 REV 0

Ir Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 183 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YI* N1-' uFIJ (SWC) SWELl- 038 Seismic Walkdown Checklist Equipment ID No. PT.16-19-29A Equip. Class' 18 Equipment Description DW PRESSURE INDICATION Photographs NO PHOTO Note: Note:

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 184 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y9 N-I U7i Seismic Walkdown Checklist (SWC) SWELl- 038 Equipment ID No. PT-16-19-29A Equip. Class' 18 Equipment Description DW PRESSURE INDICATION NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 185 of 505 ATTACHMENT 9.6 SEISMIC WALKOOWN CHECKLIST FORM Sheet I of 5 Status: YN NEI UL-Seismic Walkdown Checklist (SWC) SWELl- 039 Equipment ID No. PT-5-12C Equip. Class' 18 Equipment Description OW PRESSURE SCRAM Location: Bldg. RB Floor El. 280' Room, Area 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.

Anchoraoe 1, Is the anchorage configuration verification required (i.e., is the item one YZ NC3 of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Y9 NEI U(:] N/A[(]

3. Is the anchorage free of corrosion that is more than mild surface YO N-' U- N/AE-oxidation?.

4. Is the anchorage free of visible cracks in the concrete near the YO] NF1 UEI N/AZ anchors?

Attached to rack.

Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

0 Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 186 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ N[3 UM Seismic Walkdown Checklist (SWC) SWELl- 039 Equipment ID No. PT-5-12C Equip. Class' 18 Equipment Description DW PRESSURE SCRAM

5. Is the anchorage configuration consistent with plant documentation? YN NEI UE-- N/AE (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks

6. Based on the above anchorage evaluations, is the anchorage free of Y[9 NM U[-l potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YN NE] ur-j N/Ar]

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEi UI- N/AF and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ NCi u-' N/AC]

10. Based on the above seismic interaction evaluations, is equipment free YZ N[ urI of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 187 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 3 of 5 Status' YED NEI uE-Seismic Walkdown Checklist (SWC) SWELl- 039 Equipment ID No. PT-5-12C Equip. Class1 18 Equipment Description DW PRESSURE SCRAM Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YIE N[-] U[-]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawings: 5920.3016, 5920-3017, 5920-3018, and sketch no. SK-VY-944 11-1 A46//PEEE - Screening Evaluation Work Sheet, SSEL Line No. 000186 SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks Evaluated by: Marcus Hecht-Nielgen -. Date: 10-09-2012 Raymond Tworek -a4 o,,.g,. 10-09-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 188 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ N"- UM" Seismic Walkdown Checklist (SWC) SWELl- 039 Equipment ID No. PT-5-12C Equip. Class 1 18 Equipment Description DW PRESSURE SCRAM Photographs NO PHOTO Note: PT-5-1 Note:

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-1 2-00019 Rev. 0 Page 189 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YN NEI UM' Seismic Walkdown Checklist (SWC) SWELl- 039 Equipment ID No. PT-5-12C Equip. Class1 18 Equipment Description DW PRESSURE SCRAM NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 190 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y0 NO UEI Seismic Walkdown Checklist (SWC) SWELl.- 040 Equipment ID No. PT-5-12D Equip. Class' 18 Equipment Description DW PRESSURE SCRAM Location: Bldg. RB Floor El. 280' Room, Area 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

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y0 NOI UI N/A[-I

3. Is the anchorage free of corrosion that is more than mild surface Y0 NO UQ N/AD oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YO NED U" N/AZ anchors?

Attached to rack.

'Enter the equipment class name from EPRI 10252.,6, Appe.nidix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 191 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YN NE* U-]

Seismic Walkdown Checklist (SWC) SWELl- 040 Equipment ID No. PT-5-12D Equip. Class' 18 Equipment Description DW PRESSURE SCRAM

5. is the anchorage configuration consistent with plant documentation? " 0 NFE]' -' N/A[I (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks

6. Based on the above anchorage evaluations, Is the anchorage free of Y0 NE] U[]

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y0 NEI UF- N/A--

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NE] UCI N/AUI and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ NE] U- N/AM

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

EN-DC-1 68 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 192 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YE NE] UJ-Seismic Walkdown Checklist (SWC) SWELl- 040 Equipment ID No. PT-5-12D Equip. Class' 18 Equipment Description DW PRESSURE SCRAM Other Adverse Condltions

11. Have you looked for and found no other seismic conditions that could YO N[3 U[-_

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawings: 5920-3016, 5920-3017, 5920-3018,.andsketch no. SK-VY-944 11-1 A46//PEEE - Screening Evaluation Work Sheet, SSEL Line No. 000187 SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks Evaluated by: Marcus Hecht-Nie.sen-.---*./..5. Date: 10-09-2012 Raymond Tworek 10-09-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 193 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NEI UL--

Seismic Walkdown Checklist (SWC) SWELl- 040 Equipment ID No. PT-5-12D Equip. Class' 18 Equipment Description DW PRESSURE SCRAM Photographs Note: PT-5-1 EN-DC-1 68 REV 0 I

"I[ Attnr.hm*.nt C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 194 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y[] N5- UI"-

(SWC) SWELl- 040 Seismic Walkdown Checklist Equipment ID No. PT-5.12D Equip, Class 1 18 Equipment Description DW PRESSURE SCRAM NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 195 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: Y0 N('I UMI Seismic Walkdown Checklist (SWC) SWELl- 042 Equipment IDNo. LT-2-3-72A Equip. Class1 18 Equipment Description RVLEVEL FOR RHR, DG, HPCI, PCIC, ADS, CS Location: Bldg. RB Floor El. 280' Room, Area 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.

Anchoracie

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y9 NEI UE N/AsJ Two alignment screws have no nuts attached,however, all other screws are secure. No seismic issue by engineeringjudgment.

3. Is the anchorage free of corrosion that is more than mild surface YZ N[3 UEJ N/A[--

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YEll NM UEI N/AZ anchors ?

Attached to rack.

IEnter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 "I

Rev. 0 Page 196 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NE"' U0 Seismic Walkdown Checklist (SWC) SWEll- 042 Equipment ID No. LT-2-3-72A Equip. Class1 18 Equipment Description RV LEVEL FOR RHR, DG, HPCI, PCIC, ADS, CS

5. Is the anchorage configuration consistent with plant documentation? Y0 NEI UC- N/A[I (Note: This question only applies ifthe item is one of the 50% for which anchorage configuration verification Is required.)

See SQUG, November 9-13, 1992, Section V87, Equipment Category 7 Instruments on Racks

6. Based on the above anchorage evaluations, is the anchorage free of YZ N[: U[3 potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YN N[l UDI N/AD1

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YE N[3 U[I N/AC1 and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YN N[3 UE" N/AD-

10. Based on the above seismic interaction evaluations, is equipment free YN NO U0 of potentially adverse seismic interaction effects?,

EN-DC-168 REV 0

Pr Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 197 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Shoot 3 of 5 .....

Status: YZ NEI UEI Seismic Walkdown Checklist (SWC) SWELl- 042 Equipment ID No. LT-2-3.72A Equip. Class' 18 Equipment Description RV LEVEL FOR RHR, DG, HPCI,. PCIC, ADS, CS Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawings: 5920-3016, 5920-3017, 5920-3018, and sketch no. SK- VY-944 11-1 A46/IPEEE - Screening Evaluation Work Sheet, SSEL Line No. 000203 SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks Evaluated by: Marcus Hecht-Nielsen ,Date: ý 10-09-2012 Raymond Tworek -R-Am "S', !L LzfITII I'2-- 10-09-2012 Ramond Tworek EN-DC-1 68 REV 0

rp Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 198 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YEE N7 Ur-Seismic Walkdown Checklist (SWC) SWEL1- 042 Equipment ID No, LT-2-3-72A Equip. Class 1 18 Equipment Description RV LEVEL FOR RHR, DG, HPCI, PCIC, ADS. CS Photographs Note: : LT.2 EN-DC-168 REV 0

ýe-, Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 P.p. . 1, Af 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ N[-C U-Seismic Walkdown Checklist (SWC) SWELl- 042 Equipment ID No. LT-2-3-72A Equip. Class' 18 Equipment Description RV LEVEL FOR RHR, DG, HPC. PC/C,ADS, CS NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 200 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: Y[* NjiJ ULI (SWC) SWELl- 043 Seismic Walkdown Checklist Equipment ID No. LT-2-3-72C Equip. Class1 18 Equipment Description RV LEVEL FOR RHR, DG, HPCI, PCIC, ADS, CS Location: Bldg. RB Floor El. 28Q' Room, Area 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

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

2, Is the anchorage free of bent, broken, missing or loose hardware? Y0 N[-] ULD] N/AD]

3. Is the anchorage free of corrosibn that is more than mild surface YX NDI U-I N/AD-oxidation?

4. Is the anchorage free of visible cracks in the concrete near the YEI NEI U[I N/AZ anchors?

Attached to rack.

'Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-1 o 2-00019 Rev. 0 Page 201 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 NEI U-Seismic Walkdown Checklist (SWC) SWELl- 043 Equipment ID No. LT-2-3-72C Equip. Class' 18 Equipment Description RV LEVEL FOR RHR. DG, HPCI, PC/C,ADS, CS

5. Is the anchorage configuration consistent with plant documentation? YZ NEI UCI N/AEC (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks

6. Based on the above anchorage evaluations, is the anchorage free of YO N[] U--]

potentially adverse seismic conditions?

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yv NEI UEr N/AC

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NE] UE-- N/A[

and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YO NE] UE- N/AC-

10. Based on the above seismic interaction evaluations, is equipment free YZ NE1 U(-]

of potentially adverse seismic interaction effects?

EN-DC-168 REV 0

-a Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 202 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y] NEI UE1 Seismic Walkdown Checklist (SWC) SWELl- 043 Equipment ID No. LT-2-3-72C Equip. Class1 18 Equipment Description RV LEVEL FOR RHR, DG. HPCI, PCIC, ADS, CS Other Adverse Conditions

11. Have you looked for and found no bther seismic conditions that could Y0 N[i UE]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawings: 5920-3016, 5920-3017, 5920-3018, and sketch no. SK-VY-944 11-1 A46/IPEEE- ScreeningEvaluation Work Sheet, SSEL Line No. 000205 SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on Racks Evaluated by: Marcus Hecht-Nielsen .. Date: 10-09-2012 Raymond Tworek Zkv.-w-,-o3~i'. 10-09-2012 EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019

,/

Rev. 0 Page 203 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NM U-I Seismic Walkdown Checklist (SWC) SWELl- 043 Equipment ID No. LT-2-.3-72C Equip. Class 1 18 Equipment Description RV LEVEL FOR RHR, DG, HPCI, PCIC, ADS, CS Photographs Note: LT-2-3-72C EN-DC-168 REV 0

Attachment C Engineering Report VTY-RPT-12-00019 Rev. 0 Page 204 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FOAM Sheet 5 of 5 Status: Y[E NEI U'-

Seismic Walkdown Checklist (SWC) SWELl- 043 Equipment ID No. LT-2-3-72C Equip. Class' 18 Equipment Description RV LEVEL FOR RHR, DG, HPCI, PCIC, ADS, CS NO PHOTO NO PHOTO Note: Note:

EN-DC-168 REV 0