BVY 13-061, VY-RPT-12-00019, Revision 1, Vermont Yankee Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page 159 of 505 of Attachment C

VY-RPT-12-00019, Revision 1, Vermont Yankee Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page 159 of 505 of Attachment C

ML13200A161
Person / Time
Site:	Vermont Yankee
Issue date:	06/20/2013
From:	Buckley S M Entergy Nuclear Operations
To:	Office of Nuclear Reactor Regulation
References
BVY 13-061 VY-RPT-12-00019, Rev 1
Download: ML13200A161 (210)

Text

Engineering Report No. VY-RPT-12-00019 Rev I Page 1 of 33~Enter"y ENTERGY NUCLEAR 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of Fukushima Near-Term Task Force Recommendation 2.3: Seismic Engineering Report Type: New rl Revision ED Cancelled Ml Superseded Superseded by: Applicable Site(s)IPI El ANOI El EC No. 44934 IP2 El ANO2 IP3 El ECH El JAF El GGNS El PNPS El RBS El VYW WF3 El WPO PLP El E]Report Origin: 0 Entergy El Vendor Vendor Document No.: N/A Quality-Related:

El Yes 0 No Prepared by: f Steen M. Buckley (ENAERGY)Reviewed by: Reviewed by: Approved by: Scott 15,Qodo (~Repo'~viewer, ENTERGY)Scotb.Goowin(Peer Reviewer, ENTERGY)Date: Date: Date: Date: ,/Z LI// 3 Brede (Supervisor/

Manager, ENTERGY)

Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 2 of 33 Report Number VY-RPT-12-00019 Rev q Page I of 28*Ente ENTERGY NUCLEAR 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 C]Cancelled

[I Superseded

[]Superseded by-Applicable Site(s)'p 1 1 IP2 01 1P3 C1 Jj&.F 01 PP~S 0 Vy 0 WPO 11 ANOI []AN02 [ECH [I GGNS [I RBS [E WF3 0l PLP El EC No. 40647 Report Origin:[E Entergy 0 Vendor Vendor Document No.: 1N-A Quality-Related:

No Prepared by-Reviewed by: Reviewed by: Reviewed by: Approved by: Jeffrey Horton P.E (ENERCON)

/ A " Other Juan Vizcaya (ENERCoN)

I Peer RLiewer Steven M Buckley al " Scott D Goodwin /....-./{7Y.,y-L.)

_vf Superviwsr Manager Date: /-2o ',/2 Date: _ -_ '_Date: 114042 Date: ll-20-ZOiZ Date- __ECi___

Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 3 of 33 Revision Recordao f on 0 Initial issue.Revision 0 Report was revised to incorporate inspection of the deferred items during Refueling Outage (RFO 30) in March of 2013.-Retained Revision 0 Cover Sheet and signatures as page 2 to provide a record of the personnel responsible for the Revision 0 content.-Revised Table of Contents, Table 4-1, Table 4-2, and other text revisions or additions required to reflect deferred inspections as denoted by revision bars.-Minor editorial formatting changes only in Section 6.4 table with no Revision 0 information changes.-Attachment C, page 3 of 505, Table of Contents was updated to match the Equipment ID and Description on the SWC for SWELl -065. Editorial correction only.-Attachment C, page 505 of 505, the table for the Drywell deferred items was placed above the Steam Tunnel table to match the format of the table of contents for SWCs presented in Attachments K.-Added new sections 4.2.1, 4.3.1, 6.4.1, 7.1.1, 8.0.1 and 9.2.2.1.-Added Reference 10.16, Attachment K and Attachment L.-All other pages remain the same as Revision 0 text.-i Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 4 of 33 TABLE OF CONTENTS Section Description Page 1.0 SCO PE AND O BJECTIVE .......................................................................................................

5 2.0 SEISMIC LICENSING BASIS

SUMMARY

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

6 2.1 Safe Shutdown Earthquake

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

6 2.2 Design Codes, Standards and M ethods ...................................................................................

7 3.0 SEISMIC WALKDOWN PROGRAM IMPLEMENTATION APPROACH ..........................

8 4.0 PERSO NNEL Q UALIFICATIO NS .............................................................................................

8 4.1 Equipment Selection Personnel

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

12 4.2 Seism ic W alkdown Engineers

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

12 4.3 Licensing Basis Reviewers

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

12 4.4 IPEEE Reviewers

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

12 4.5 Peer Review Team .....................................................................................................................

13 5.0 IPEEE VULNERABILITIES REPORTING

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

15 6.0 SEISMIC WALKDOWN EQUIPMENT LIST DEVELOPMENT

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

15 6.1 Base List .....................................................................................................................................

16 6.2 SW EL I ......................................................................................................................................

16 6.3 Spent Fuel Pool Item s ............................................................................................................

18 6.4 Deferred, Inaccessible Item s on SW EL .................................................................................

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

21 7.1 Seism ic W alkdowns ...............................................................................................................

21 8.0 LICENSING BASIS EVALUATIO NS ........................................................................................

23 8.1 Licensing Basis Evaluations

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

23 8.2 Corrective Action Program Entries ........................................................................................

24 8.3 Plant Changes .............................................................................................................................

25 9.0 PEER REVIEW .................................................................................................................................

26 9.1 Peer Review Process ..................................................................................................................

26 9.2 Peer Review Results Sum m ary ..............................................................................................

26

10.0 REFERENCES

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

32 11.0 ATTACH M ENTS ..............................................................................................................................

33 Engineering Report No. VY-RPT-12-00019 Rev. 1 Page 5 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 1OCFR50.54(f) letter (Ref. 10.1) requesting information from all licensees to support the NRC staffs 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 (NED, 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. 1 Page 6 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. 1 Page 7 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. 1 Page 8 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. 1 Page 9 of 33 Table 4-1 Equipment Seismic Licensing IPEEE Name Selection Walkdown Basis Reviewer Personnel Engineer Reviewer Steven Buckley (Vermont Yankee) X2 x2,3 x3 X Mark Palionis (Vermont Yankee) X X Ed Harms (Vermont Yankee) X'Scott Goodwin (Vermont Yankee) X3 Marcus Hecht-Nielsen (ENERCON/ARES)

X Randall Stephens (ENERCON/ARES)

X Raymond Tworek (ENERCON/ARES)

X Kirit Parikh (ENERCON)

X Michael Rose (Vermont Yankee) x3 David Grimes (Vermont Yankee) X Notes: I I 1.2.3.Plant Operations representative Designated lead SWE Deferred walkdown SWEL items and Revision 0 responsibilities for SWEL items 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. 1 Page 10 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 BS 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. 1 Page 11 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. 1 Page 12 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 4-1.4.2.1 For the walkdown of the deferred SWEL items, there are 2 SWEs.4.3 Licensing Basis Reviewers A total of 2 individuals served as Licensing Basis Reviewers

-see Table 4- 1.4.3.1 For the walkdown of the deferred SWEL items, there are 2 Licensing Basis Reviewers.

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.

Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 13 of 33 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 SWEL Walkdown Submittal Name Peer Peer Report Peer Reviewer Reviewer Reviewer Julien Abramovici (ENERCON)

X_ Xl Juan Vizcaya (ENERCON)

X X2 Laura Maclay (ENERCON)

X Jeffrey Horton (ENERCON)

X Scott Goodwin (Vermont Yankee) x4 x4 David Grimes (Vermont Yankee) X 3 x3 Notes: 1. SWEL and Walkdown Peer Review Team Leader 2. Submittal Peer Review Team Leader 3. Peer Review for the deferred SWEL items and Submittal Report 4. Peer Review Team Leader for deferred SWEL items 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, 3 rd 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.

Engineering Report No. VY-RPT-12-00019 Rev. 1 Page 14 of 33 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.

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.

Engineering Report No. VY-RPT-12-00019 Rev. 1 Page 15 of 33 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: " 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 I 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)

Engineering Report No. VY-RPT-12-00019 Rev. 1 Page 16 of 33 Maintaining containment integrity is the fifth safety function: 0 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 I list is approximately 100 to 110 items.Therefore, approximately 15 % of the original A46/IPEEE equipment will be used to develop the SWEL I 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 I is presented in Table 9.4.1 of Attachment B, and has 736 total items.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 I list. This risk ranking fulfills the requirement to select equipment that supports the 5 required safety functions Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 17 of 33 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 I should represent a diverse population of items on Base List I 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.

SWEL I 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.

Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 18 of 33 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 I 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 I which were enhanced as a result of seismic vulnerabilities identified during the IPEEE program. These items are designated as such on Base List I 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.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).

Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 19 of 33 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 1 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"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 Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 20 of 33 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 SWELI-029 V23-15 HPCI/STEAM SUPPLY MOV DRYWELL High rad.266'SWELI-041 TE- 16-19-030A DW TEMPERATURE INDICATION DRYWELL High rad.268'DRYWELL High rad.SWELI-052 V2-80D MAIN STEAM/INBOARD MSIV 254'254'VLEDRYWELL High rad.SWELI-055 RV-2-71C MAIN STEAM/RELIEF VALVE 275'SAFETY RELIEF VALVE/NITROGEN DRYWELL High rad.SUPPLY ACCUMULATOR 275'SWELI-030 V23-16 HPCI/STEAM SUPPLY MOV STEAM High rad.TUNNEL 251'SWELI-053 V2-86A MAIN STEAM/IOUTBOARD MSIV STEAM High rad.TUNNEL 251'SWELI-054 S-2-6A MAIN STEAM/IOUTBOARD MSIV STEAM High rad.INSTRUMENT AIR SUPPLY ACCUMULATOR TUNNEL 251'SWELI-073 TS-23-IOIA HPCIISTEAM LEAK DETECTOR STEAM High rad._________TUNNEL 25 1'SWELI-074 TS-23-102A HPCI/STEAM LEAK DETECTOR STEAM High rad.TUNNEL 251'SWEL1-075 TS-23-103A HPCI/STEAM LEAK DETECTOR STEAM High rad.TUNNEL 251'SWEL1-076 TS-23-104A HPCI/STEAM LEAK DETECTOR STEAM High rad.TUNNEL 251'SWELI-077 SE-2-86A-1 MS/OUTBOARD MSIV SOLENOID AC/DC STEAM High rad.I ,_ TUNNEL 251' Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 21 of 33 6.4.1 During the March 2013 Refueling Outage (RFO 30), the deferred equipment defined in this Section 6.4 was walked down as part of the NTTF 2.3 Seismic Walkdown Program. The walkdowns were conducted in accordance with the Guidance as described within Section 7.0.7.0 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 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 Engineering Report No. VY-RPT-12-00019 Rev. 1 Page 22 of 33 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 I 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-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 Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 23 of 33 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 SWEL 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.7.1.1 The March 2013 walkdown results for the 13 deferred SWEL items are included in Attachment K. There were 3 additional AWCs created for the areas containing the 13 deferred SWEL items. These AWCs are included in Attachment L.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.8.0.1 No potentially seismically significant conditions were discovered during the deferred SWEL item walkdowns during RFO 30.8.1 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. 1 Page 24 of 33 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 3/4/4" 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 (10,11 z), 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-72-1A and CYL-72-1B 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-IA 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. 1 Page 25 of 33 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.

Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 26 of 33 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:

• 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 recommendations from the Guidance were met. Specific considerations for the peer review process are described below for SWEL I 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.

Engineering Report No. VY-RPT-12-00019 Rev. 1 Page 27 of 33 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* Risk 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 Engineering Report No. VY-RPT- 12-00019 Rev. 1 Page 28 of 33 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 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 SWE 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.

Engineering Report No. VY-RPT-12-00019 Rev. 1 Page 29 of 33 The SWEL items included the following:

1. SWEL-102 2. SWEL-079 3. SWEL-032 4. SWEL-058 5. SWEL-059 6. SWEL-005 7. SWEL-061 8. SWEL-062 9. SWEL-027 10. SWEL-068 11. SWEL-094/095

12. SWEL-001 13. SWEL-004 14. SWEL-003 15. SWEL-020 CYI-72-1A N2 cylinder NG-13A CAD SOV RRV-8 P-10-1D RHR Pump V-10-65B RHR Bypass valve P-46-1A CS Pump P-8-1C RHRSW Pump V-10-89A RHR Supply MOV P44-lA HPCI Pump TU- 1-1A HPCI Turbine HPCI Instrument Rack CRD HCU (Both banks)CV-3-26 (inlet valves)PCV-3-32B 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: 1.2.3.4.5.6.7.8.9.10.it.AWC-014 AWC-027 AWC-029 AWC-030 AWC-034 AWC-032 AWC-007 AWC-009 AWC-031 AWC-003 AWC--013 In all the above SWEL and AWC walkdowns no seismic issues were identified.

Housekeeping items identified are captured in CRs listed above.

Engineering Report No. VY-RPT-12-00019 Rev. 1 Page 30 of 33 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. SWEL1-007 2. SWELI-040 3. SWELI-043 4. SWEL1-092 9.2.2.1 Deferred SWEL Items Seismic Walkdowns and Area Walk-Bys The original walk down scope and schedule identified a subset of components that were deferred due to inaccessibility at the time of initial walk downs. This deferred list is identified in report Section 6.4 and comprises thirteen (13) components.

Five (5)components are located in the Drywell (DW) and eight (8) components in the Main Steam Tunnel (MST). All deferred components were walked down during the Spring refueling outage (RFO 30) that was recently completed when plant conditions allowed access to these areas. For the deferred walk downs, the peer reviewer performed a review of all completed seismic walk down checklists (SWCs) and area walk by checklists (AWCs) for deferred components (refer to Attachment K and L). The peer reviewer also accompanied the Lead Seismic Walkdown Engineer (SWE) into the DW and independently inspected the five (5) deferred items in this area and also the two (2) AWCs related to deferred DW equipment inspections.

The peer reviewer concluded that the SWC and AWC checklists were accurate, thorough, and complete.There were no Licensing Basis Evaluations (LBEs) required to be performed as a result of the deferred walk down scope.9.2.3 Licensing Basis Evaluations There were no Licensing Basis Evaluations required.

Operability determinations were 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 Engineering Report No. VY-RPT-12-00019 Rev. 1 Page 31 of 33 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 Enclosure 3 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. 1 Page 32 of 33

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

-1OCFR50.54(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 01-23, 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 B VY 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 10.16 Vermont Yankee Letter to NRC, BVY 12-080, dated November 27, 2012, Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271), "Seismic Walkdown Report" Engineering Report No. VY-RPT-12-00019 Rev. 1 Page 33 of 33 11.0 ATTACHMENTS ATTACHMENT A -ATTACHMENT B -ATTACHMENT C -ATTACHMENT D -ATTACHMENT E -ATTACHMENT F -ATTACHMENT G -ATTACHMENT H -ATTACHMENT I -ATTACHMENT J -ATTACHMENT K -ATTACHMENT L -IPEEE VULNERABILTIES TABLE SEISMIC WALKDOWN EQUIPMENT LISTS SEISMIC WALKDOWN CHECKLISTS (SWCs)AREA WALK-BY CHECKLISTS (AWCs)POTENTIALLY ADVERSE SEISMIC CONDITIONS LICENSING BASIS EVALUATION FORMS PEER REVIEW CHECKLIST FOR SWEL SEISMIC WALKDOWN ENGINEER TRAINING CERTIFICATES PEER REVIEW COMMENTS FOR SWCs AND AWCs SWELl RISK RANKING PROCESS DEFERRED SEISMIC WALKDOWN CHECKLISTS (SWCs)DEFERRED AREA WALK-BY CHECKLISTS (AWCs)

Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 1 of 2 Attachment A Attachment A IPEEE Vulnerabilities Table Engineering Report No. VTY.RPT-12-00019 Rev. 1 Page 2 of 2 Attachment A ATTACHMENT 9.3 IPEEE VULNERABILITIES TABLE FORM AND INSTRUCTIONS

• ~ ~ 4 RES A-46 Program outliers.Complete A-46 program and resolve all outliers.

Modifications designed to IPEEE seismic levels. IPEEE submittal Table 3.4,1 defined modifications made for A46 and IPE:EE. Table 3.4.2 documented A46/ IPEEE outliers to be resclved.Vermont Yankee calculation, VYC-2068, "Final Summary of USI A-46 Outlier Resolution" and VYC-2119, "IPEEE Seismic Component HCLPF Evaluations Summary. Associated modifications are referenced within these documents.

Per NRC Letter NVY 01-023. dated March 22, 2001, all A461 IPEEE outliers described in Table 3.4.2 have been resolved to meet 46 criteria and to assure a HCLPF > 0.3g.'1~NRC Letter NVY 01-023, dated March 22, 2001 Condensate Storage Tank (CST) has a HCLPF of 0.25g.To further evaluate for possible modification or upgrade of seismic capacity, and its associated risk to total COF using PRA methods.Y Vermont Yankee concluded that no simple cost effective enhancement could be identified that would improve CST seismic capaciy.Accepted per conclusions presented in NVY 01-023, dated March 22. 2001 Vermont Yankee Work Order 99-011585-000; Complete 7/14/2000 V-03 Diesel Fire Il=unp Fuel Tank is weak at the tank shell to saddle interface and potential seismic loads could cause crimping of the fuel supply lubing. Also a potential seismic interaction with an adjacent masonry wall.Tubing will be rerouted to accommodate span flexibility to account for seismic displacement of the tank relative to the saddle supports.Review seismic capacity of the wall.Tubing reroute eliminated the potential crimping concern during a seismic event. The adjacent masonry wall reviewed in comparison the masonry wall sampling that was performed for the IPElE program and determined to be enveloped by the seismic capacity of the masonry wall evaluated and documented in Table 3.2.4 of the VY IPEEE submittal.

Y V-04 The support of the fire system northwest standpipe in the Reactor Building requires more robust support.Proposed improvements to enhance the support of the fire system northwest standpipe in the Reactor Building.Vermont Yankee calculation, VYC-2136, documents the design of enhanced deadweight supports and additional lateral supports for the Reactor Building northwest standpipe.

y Minor Modification (MM) 2000-27 implemented the modification; Complete 11/21/2000 VnY Accepted per V-OS Seismic resstance 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 NVY I 01-023, dated____________________________________________

j _______________________________________

____________________________________March___22rch22,000 Prepared by: Steven M Buckley 2 / A .Date: 11-14-2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 1 of 24 Attachment B Attachment B Seismic Walkdown Equipment List Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 2 of 24 Attachment B ATTACHMENT 9.4 SEISMIC WALKDOWN EQUIPMENT LISTS FORM AND INSTRUCTIONS Seismic Walkdown Equipment List Approval (Final SWELl & SWEL2)**Prepared by: Steven M Buckle y.i./-L-_/

Equipment SelectL n PersonnelP Reviewed by: Julien Abramovici , <-,4 .Peer Reýiewer Date: A01 2-2"L.-Date: a-Concurrence by: Edward Harms .$j.,z Date: /1 ///Operations Personnel** During implementation of the Seismic Walkdowns SWEL-065 was determined to be inaccessible for inspection.

This SWEL number was valve FCV-1 04-17D, SW/D TRAVELLING SCREEN CONTROL VALVE. It was replaced with ValveLCV-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 Engineeing Report No. VTY.RPT-12-00019 Rev. I Peg. 3 of 24 Aflaccnrrent B x x x SCREEN1 SCREEN 2 SCREEN3 SCREEN 4 SQUG CURRENT UndergoReactivity Pressure Inventory_

neovy JNIE EQUIPMENT SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Seismic Regular least one of Ilsded High Temp/ -otroli ConProe nontol Heat Containment CLASS EQUIPMENT I ? Configuration the 5 safety Replaced?

IPEE de Humidity?

Borated Control Control Control Inspections?

Functions O)tside H Systeon?tI 10) (TI H 1 0 HCU- CRI/1HYDRAULIC CONTROL UNITS /89) YES NO YES NO I NO X 1 21 CRDiNORTH SDV INSTRUMENT VOLUME YES NO YES NO I NO X 1 07 LCV-3-33A LCV-3-33A CRDiSCRAM DISCHARGE VOLUME DRAIN VALVE YES NO YES NO I NO X 1 07 LCV-3-336 LCV-3-338 CRDiSCRAM DISCHARGE VOLUME DRAIN VALVE YES NO YES NO I NO X 1 07 LCV-3-33C LCV-3-33C CRDSCRAM DISCHARGE VOLUME DRAIN VALVE YES NO YES NO I NO X 1 07 LCV-3-330 LCV-3-330 CR0iSCRAM DISCHARGE VOLUME DRAIN VALVE YES NO YES NO I NO X 1 07 PCV-3-32A PCV-3-32A CR0/SCRAM DISCHARGE VOLUME VENT VALVE YES NO YES NO I NO X 1 07 PCV-3-32B PCV-3-32B CR0/SCRAM DISCHARGE VOLUME VENT VALVES YES NO YES NO I NO X 1 07 CV-3-12E-CV-3-126-CRDiSCRAM VALVES (9,) INLET YES NO YES NO I NO X 1 07 CV-3-1.7-CV-3-127-CRDSCRAM VALVES tI5S OUTLET YES NO YES NO I NO X 1 21 CRD/SOUTH SDV INSTRUMENT VOLUME YES NO YES NO I NO X 1 06 P-46-1A P.465-A CSi"A COPE SPRAY PUMP YES NO YES NO I NO X 1 06 P-,5-tB P-46-1B CSrECORSPAYPUMP YES NO YES NO I NO X I 0SA VI,-llA VI4-11A CS/CS INJECTION MOV YES NO YES NO I NO X 1 0SA V14-118 V14-11E CSCS INJECTION MDV YES NO YES NO I NO X 1 0EA V14-12A VI 4-12A CS/CS INJECTION MOV YES NO YES NO I NO X 1 08A V1.-1'E V14-128 CSCS INJECTION MOV YES NO YES NO I NO X 1 0MA V14-26A V14-26A CS/FULL FLOW TEST MOV YES NO YES NO I NO X 1 08A V14-26E V1,-266 CS/PULL FLOW TEST MOV YES NO YES NO I NO X 1 08A V14-5A VI-5A CSiMIN-FLOW MOV YES NO YES NO I NO X 1 03A V14-SB Vi4-SE C./MIN-FLOW MOV YES NO YES NO I NO X 1 03A V1&-TA VI4-7A CS/PUMP SUCTION MOV YES NO YES NO I NO X 1 08A V14-/B VI -/7B CS/PUMP SUCTION MOV YES NO YES NO I NO X 1 21 TK-8.-IA TK-80-1A DG START AIR/AIR RECEIVER TANK A YES NO NO NO YES I NO 1 21 TK-58-B1 TK.80-1B DG START AIR/AIR RECEIVER TANK 5 YES NO NO NO YES I NO 1 21 TK-8I-IC TK-80-1C DG START AIR/AIR RECEIVER TANK C YES NO NO NO YES I NO 1 21 TK.8S-1D TK-80-1D DG START AJR/AJR RECEIVER TANK D YES NO NO NO YES I NO 1 18 PS-24-IA PS.24-IA DG START AJR/COMP CONT YES NO NO NO I NO 1 18 PS-24-1 PS-24-1 8G START AIPRCOMP CONT YES NO NO NO I NO 1 12 C-3.1A C-3-1A DG START AIR/COMPRESSOR A YES NO NO NO I NO 1 12 C-3.18 C-3-1B DG START AiRCOMPRESSOR B YES NO NO NO I NO 1 SEB AS.24-IA .S.2,-IA DGSTARTAIR/DGAJRSUPPLY YES NO NO NO I NO 1 036 AS-24-tB AS-2.1-lB DG START AIR/DG A R SUPPLY YES NO NO NO I NO 1 0SiB AS-24-2A AS-24-2A DG START AIRDGAIR SUPPLY YES NO NO NO I NO 1 086 AS-24-28 AS-24-2E DG START AIR/DG AIR SUPPLY YES NO NO NO I NO 1 1 PFl-d2-SAP-lA Pt-24-SAP-1A DG START AIR/PRESS BOUND YES NO NO NO I NO I 18 PI-24-SAP-lB PI-24-SAP-lBI DG START AIR/PRESS BOUND YES NO NO NO I r NO 1 1l PS-24-APLA-IA PS-24-APLA-IA DOG START AIR/PRESS BOUND YES NO NO NO I NO 1 18 PS-24-APLA-1 PS-24-APLA-1B DG START AIR/PRESSBOUND YES NO NO NO I NO 1 17 0G-1A DG-IA DIESEL GENERATOR A YES NO NO NO I NO 1 17 DOG-B Do-is DIESEL GENERATOR 8 YES NO NO NO I NO 1 18 LSH-108-2A LSH-I1082A FUEL OIL/DAY TANK A HIGHIPRESS S YES NO NO NO I NO 1 18 LSL-100-3A LEL.108-3A FUEL OIL/DAY TANK A LOW/PRESS B YES NO NO NO I NO 1 1 LSH-1--2E LSH-108-2B FUEL OIL/DAY TANK B HIGH/PRESS 5 YES NO NO NO I NO 1 18 LSL-1S-38E LSL-108-3B FUEL OILUDAYTANK B LOW/PRESS E YES NO NO NO I NO 1 07 LCV-104-2A LCV-108-2A FUEL OILiDAY TANK FILL YES NO NO NO I ND 1 07 LCV-108-2E LCVA103-2E FUEL OILDAY TANK FILL YES NO NO NO I NO 21 TK-42-IA TK-42-IA FUEL OIL/DIESEL OIL DAY TANK A YES NO NO NO I YES I I NO x TK-42-1B NO NO NO NO NO NO TK-AS-lA Table 9A4.1- Base List 1 Enoneerirtg Reporl No. VTY-RPT-12-00019 Rev. I Page 24 Allahmrenl B r I T ~ 1 I .. -e UNIT SCREEN11 SCREEN 2 1 SCREEN 3 SCREEN4 CURRENT EQUIPMENT I SSEL EQUIPMENT ID... EQUIPMENT ID EQUIPMENT DESCRIPTION Seismic 1?Undergo Regular Configuration Inspections?

Maintains at least one of the S safety Functions Replacedai IPEEE Environment Insidel [igh Tampi Outside? Humidity?(1/0) 'tH)Borated System?Reactivity Pressure Inventory Decay Control Control Control Reat Removel NO 1 07 LCV-108-3 LC%-I 08-3 T TK BOILER TANK RLL NO NO NO NO NO NO NO NO-H NO 1 14 VAC-A VA C-A 120 VAC VAC-A VITAL SUBPANEL 100AMP YES I II IN 5 I I A I I{] N U£% I R WIL YES AC INSTRUMENTATION DISTR PNL 200AMP -ýO- --ý-o NO V/IC-1 VAC-1 lGf-2-IA BC-I-IA BC-I-I B BC-AS-2 120,240V UNINTERRUPTIBLE CVITAILl AC DISTR PNL 225AMP 120i,40V VITAL AC MG SET 125V DC MAIN STATION BATTERY CHARGER A ON DC-I 125V DC MAIN STATION BATTERY CHARGER B ON DC-2 125V DC NORMAL BATTERY CHARGER ON BUS DC-2AS YES NO NO NO NO 1 ¶-~~~-t------1-----t r-~---t p-I- i--a SC-1-1 YES YES YES YES YES NO NO NO NO NO NO NO YES I NO NO I 1 NO 16 SC-AS-2 NO NO NO NO NO x x 1 16 SC-AS-2-1 1 15 B-AS-2 1 15 S-I-1 1 15 B-1-16+1t4ý OC-3 BC-AS-2.1 125V DC ALTERNATE BATTERY CHARGER ON BUS DC-2AS NO 5 DC-2AS YES YES YES YES YES NO NO NO NO NO NO NO DC-3 1125V DC DISTRPNL DC-3 60AMP NO NO NO NO NO NO YES I NO 1 14 DC-I 1 14 0C-1C 1 14 DC-2 1 14 0C-2AS 1 14 0C-2C 1 01 MCC-OC-2A 1 01 MCC-OC-lA I ol MCC-0C-lB 1 14 DC-ECCS-A I 14 DC-ECCS-B o.-1 125V DC DISTRPNL DC-I 1600AMP c-1 C DC-2 DC-2AS DC-2C MCC-DC-2A 125V DC DISTR PNL DC-1C 1WAMP YES NO NO I YES II NOI NO 125V OC I NO NO NO NO NO NO YES I I-NO NO 125V DC MCC OC-ZA 600/AMP YES NO MCC-DC-IA MCC-DC-1B DC-ECCS-A DC-ECCS-B B-UPS-lA 125V DC MCC DC-lA (HPCI) 600AMP YES NO NO I YES I I NOI YES NO NO NO NO NO NO0 NO YES I NO NO NO I is 3-UPS-lA JPS-1A BATTERY BANK 1YESI is B-UPS-lB IICO-SA mCC-SC 11CC-SC VCC-SE B-UPS-1B JPS-lB BATTERY BANK YES NO YES NO NO NO NO NO NO NO YES I NO NO NO YES I 01 MCC-BE 480V ESS AC MCC-BE -REACTOR ELDG NO NO NO NO NO VCC-SD MCC-9D s80V ESS AC MCC-SD -REACTOR BLDG YES NO NO YES TOR BLDG (SI)1 1 01 11CC-gB 1 01 JMCC-SA MCC-SB MCC-SA BUS-8 BUS-S BUS-3 BUS-4 CP;2-2 T-8-IA 480V ESS AC MCC-gA -SWITCHGEAR ROOM (SI)480V AC SWITCHGEAR BUS NO.8 1600AMP (SI)480V AC SY/tTCHGEAR BUS NO.9 1600AMP (SiI)4KV-4160V SWITCHGEAR BUS NO.3 1200AMP (SI 4KV -4160V SWITCHGEAR BUS NO.4 1200AMP (SI ALTERNATE SHUTDOWN PANEL YES YES YES 7ES YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO YES I NO NO NO NO NO NO NO NO 1 03 1 20 1 04 1 04 1 21 1 07 1 07 U S-4-8.2-2 r-8-1A NO NO NO NO NO NO NO-TNO ITRANS 41601480 BUS NO.9 YES j NO YES NO#NNO NO NO 0 X CV-23m39 LCV-23-39 IHPCICOND PUMP TO RW X X X It X It-t--------

1~ I~~2 --- --I 18 ILS-23-98 LUV-42-41 LS-23-98 HPCIiEXHAlPUMT STEAM DRAINVV HPCIIEXHAUST STEAM DRAIN POT LEVEL SWITCH/LSO-23-54' YES YES NO NO YES YES NO NO X 1 08A :V23-21 V23-21 HPCI/FULL FLOW TEST MOV YES NO YES NI N 1 NO x X Table 9.4.1- Base List 1 Enpnearing Report No. VrY-RPT-12-00019 Re,. 1 Page 5 of 24 Aglachment 8 SCREEN11 SCREEN 2 I SCREEN 3 SCREEN4 UNIT SQUG EQUIPMENT EQU ENT CLASS I 08A IV23-24 I 1 09 F -IA 1 18 DPIS-23ý7(18 DPIS23-7ý1 0 LSH-25.1 SSEL EQUIPMENT ID V23-24--18-IA FN.2.IA DPIS-23-76 EQUIPMENT DESCRIPTION HPCliFULL FLOW TEST MOV HPCI/GLAND SEAL CONDENSER HPCI!GLAND SEAL EXHAUSTER Seismic 1?YES YES YES YES Undergo Regular Configuration Inspections?

NO NO NO NO Maintains at least one of the 5 safety Functions Replaced?I IPEEE Environment Insidel High Tempi Outside? Hamidity?(liD) (TIH)Borated System,?Reactivity Control Deacy Pressure Inventory Heat Control CorlmRo on Containment YES NO YES NO YES NO YES NO YES No I NO X x X X X x X X HPCI/HIGH STEAM FLOW TRIP DPIS-23-77 HPCI/HIGH STEAM FLOW TRIP YES YES YES YES NO NO P.44-1A AHI/HPLI PUI/P PCV-23-50 HIPCOLO COOLING NO NO NO NO NO YES NO NO X X 1 07 IV23-50A q23-5DA HPCIhLOiGS COOLING YES YES NO I NO X X I 21 E-l9-IA 17)17A 1ý1"ý2-25.1 7 1 18 !FT-23-82 08A V23.19 E-IS-IA V23-25 V23-17 Fr-23-82 V23-19 1 08A IV23-20 x 1 18 PS-23-84.1 I MA V23m57 1 08A V,3-58 1 08A V23-14 I 08A V23-IS x I 08A V23ý15 HPCILUBE OIL COOLER HPCIIMIN-FLOW MOV HPCI/PUMP CST SUCTION MOV HPCI/PUMP DISCHARGE FLOW TRANSMITTER HPCI/PUMP DISCHARGE MOV HPCI/PUMP DISCHARGE MOV HPCI/PUMP SUCTION PRESSURE SWITCH HPCIIPUMP TORUS SUCTION MOV HPCIPUMP TORUS SUCTION MOV HPCIUSTEAM SUPPLY MOV IPCI/STEAM SUPPLY MOV HPCI/STEAM SUPPLY MOV HPCI/TURBINE DRAJNPOT HPCIITURBINE EXHAUST PRESSURE SWITCH HPCOrTUPRINE EXHAUST PRESSURE SW'ICH YES YES YES YES YES NO NO NO NO NO YES NO NO X YES NO NO NO NO NO NO X X-- T ~ NO X X YES YES YES YES YES NO YES NO X X NO NO NO NO YES NO I NO NO NO NO NO X X cOO-tO 023-15 YES YES YES 7ES YES NO YES NO I X x NO NO NO NO SAC-IA 1I 10 SAC-IA CRHVAC/SAC-1

/CRHVAC/SAC-1/

UNIT/FAN 1 I 09 S SAC-B ISAC-1E.,RHVACtCHILLER MASTER UNIT 1 I 11 ISCH-2 5CH-2^,RHVAC/CHILLi R UNIT J~EL 1 09 ITEF-2 DO A ROOM VENTILATION]EXHAUST FAN US ITEF7 x x 1 09 T3EF-3 rTl-.3 ILi T FAN YES YES YES YES Y7ES YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO I NO I NO NO I NO I No I NO NO NO I NO NO NO I NO I NO I NO I NO I NO I NO I T NO NO NO NO NO NO NO NO NO NO NO NO.1 -1 10 RRU-5 x X NO NO NO NO NO NO NO RRUOR COC T-3-231A 1 1 1 1 1 1 ILT-3-231A 3W/ECCS RM COOLING_RD/SDV LEVEL TRANSt R0/SDV LEVEL TRANSt R (NORTH)18 ILT-3-2318 ILT-3-2318 18 LT-3-231F T-3-231F:RD/SDV LEVEL TRANSMITTER (SOUTH).RO/SDV LEVEL TRANSMITTER (SOUTH)-RD/SDV LEVEL TRANSMITTER (SOUTH)NO NO NO NO NO I NO I NO NO IS~~~ ~~~ 3 G IS LT-Tý!P 11 3-21 18I PT2S -2 JPT-2 52C NO NO I NO YES NO I I NO Table 9.4.1- Base List 1 Engneering Report No. VTY-RPT-12-00019 Reo. I Page 6 of 24 Atahnhent B SCREENI SCREEN 2 SCREEN 3 SCREEN4____ t 4 ~-e---. -UNII SOUG SOG CURRENT EQUIPMENT EQUIPMENT ID CLASS SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Seismic 1?Undergo Regular Configuration Inspections?

Maintains at least one of the 5 safety Functions Replacedl Ip=EE Environment Insidel High Tempi Outside? Humidty?(110) Ir/H)Borated Systma?Decay Reactivity Pressure Inventory Heat Control Control Conrol 0 ~Remoinal Containment I .~ 0 1 I-~---t4--i f.....~...-j I --1 1 18 PT-2-3-52D PT-2-3-520 CS. I YES NO YES NO NO x LT-1 IYES NO NO NO NO NO YES NO H NO X 1 18s IT-Olt ItT106S~ IDW PRESSURE ECCS YES NO NO NO NO NO NO NO NO NO H NO NO NO NO NO x 1 1I PT.-0 I0tC PT-I11 0 C OW PRESSURE ECCS YES IPT.I0-10tD YES NO I NO NO NO NO NO NO NO NO NO N17O NO NO NO NO NO NO NO NO NO NO 18 PT-5-128 P'T-5-12B I YES 1 18 IPT-5-12C 1 13 PT-5-120 1 19 7E.1&1--30A 1 ' 9 !TE-16-196308 1 20 TIA6.19-308 PrT-5-t2C YES PT-5-1 YES YES YES YES YES NO NO NO NO NO NO NO NO 1"-1-6-19-308 OW TEMP. IND.NO NO NO NO NO T NO NO NO NO NO 1 20 JTR-1-!9-45 1 18 IPS-23-CSA 1 3 PS-23-t,88 1 18 IPS-23-68C 1 18 IPS-23-680 TR.I5-19-455 PS-83-68A PS-23-sB B P5-23-A SC P5S-23-550 aBSt2-12 DW TEMP. F HPCI/PCIS C HPCI!PCIS C HPCI/PCIS C HPCIIPCIS C YES YES YES YES YES NO NO NO NO NO YES x X YES NO NO NO NO NO NO NO NO NO NO x X 1 1 8 PS-2-128B R INTERLOCK a PS-2-128A'S-2-t 28A:T-2-11 OA'T2. 11 SC:T.2.1100 R II YES YES YES YES YES NO NO 1 t8 FT-2-1 IOC NO NO NO NO NO NO NO NO YES NO NO NO NO NO NO NO NO NO 1 I 18 IFT.2-1100 REACTOR RECIRC FLOW FOR RPS l 1 18 1LT.2-3 2A T.2.3-72A RV LEVEL FOR RHR. DGO HPCI, RCIC, ADS, CS RV LEVEL FOR RHR. DG. HPCI. RCIC, ADS, CS RV LEVEL FOR RHR. DG, HPCI. RCIC, ADS. CS RV LEVEL FOR RHR, QG. HPCI. RCIC. ADS. CS RV LEVEL SCRAM & PCIS YES YES YES YES YES NO NO NO NO I 1 18 ILT-2-3-57A 1 18 ILT-2-3-57B 1 1 20 PI-2-3-56E 1 1 PT-2.3-56A 1 15 P1-2-3-858 1 1i P1:-2.3-56C 1 18 PT.2-3-560 1 18 PT.2-3-55A 1 18 PT-2-3-5t 1 is PT-2-3-55C 1 18 PT-2-3-55D 1 1i LT-2-3-.IA 1 18 LT-2-3-78B 1 20 LI-2-3-g1A 1 20 LI-2-3-018

.1.2-3-57B 11-2-3-56A

.1-2-3-SitE1 at. 2-3-S 6A at. 2-3-5166 aT..53- 56 -IT-2.3-560

'T-2-3-55A IT-4,2155A IT-23-355C RV LEVEL SCRAM & PCIS RV LEVEL SCRAM & PEES RV LEVEL SCRAM & PCIS RV PRESS. IND.RV PRESS. IND.RV PRESSURE ECCS RV PRESSURE ECCS RV PRESSURE ECCS RV PRESSURE ECCS RV PRESSURE SCRAM RV PRESSURE SCRAM YES YES YES YES YES YES YES YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO YES YES YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO-NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO x x NO x x jYES j NO IRV WTR LEVEL IND., 3-91E RV WTR LEVEL IND.YES NO NO NO---- a~...a ______ J .L...~.O......-I.

____ L.....L ______ L-..--O.--L

_____ L ____ll].;,*b3p,tJn 3A YES NO NO NO NO-i TRble 9.4.1- Base List 1 Engneering Report No. VIY-RPT-12-00019 Rea. I Page 7 0A 24 AgOchmerr B r I r t,-r~~r-----------I T --- V T 7 r1 SCREEN11 SCREEN 2 1 SCREEN 3 SCREEN4 UNIT SQUG CURRENT EQUPMN EQUIPMENT 1O CLASS SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Seismic 1?Undergo Regular Configuration Inspections?

Maintains at least on0 of the 5 safety Functions ReplacedP IPEEE Environment InsideI High Tempi Outside? Humidity?(1IO) (T I H)Borated Syst em?S In r Decay Reactii~tp Pressure iInventory Heet Control Cotral Con Re eatContainment 1 18 IPS-104-538 PS-1 04-538 SWITCH 1 1 18 PS-104-53C PS-1 04-53C P1.I1-19-36A PI-16-19-368-YES NO YES NO YES NO YES NO YES NO NO NO NO NO NO NO NO NO NO NO H NO-16-19-368 TORUS PRESSURE INDICATION NO 1- -,-~-~--1 18 PT isPT-16-9.36A PT-i 5-1 D-36A TOUSU PRESURE INC[;YES NO NO NO 1 t1 PT-16-19.368 IJPT-ý1-9-3118 TORUS PRESSURE INC NO NO NO I NO NO NO NO NO TORUS WTR. LEVEL I YES I NO 1 18 ILT-16-19-10E LT-IP6-1.5110E R. LEVEL YES NO NO NO NO 1 20 LI-PI-16-19-12 ILI.PI.16-19-12I 1 9 TE-16-19-33C TE-1619 33C 1 2C TI-16-19-33A T1IF t6-1-33A 1 20 TI-16-10-33C T 16-19-33C 1 08A V2-74 V2-7, U, YES NO NO NO NO NO YES NO NO NO NO NO NO ------ --NO NO MAIN STEAIWDRAIN VALVE MOV YES NO T NO X 1 1 08A IV2-77 V2.77 E MOV V2-SCA YES YES YES YES YES NO NO NO NO NO YES NO NO NO NO NO NO X MAIN STEAM/lNBOARD MSIV YES NO X 1I 21 1S-2-SA S.-25A MAIN STEAM/INBOARD MSIV NITROGEN SUPPLY ACCUMULATOR YES NO YES NO T NO X 1 21 S-2-5B S-2-sE MAIN STEAM1ANEOARD MSIV NITROGEN SUPPLY ACCUMULATOR YES [ NO YES NO I T NO X 1 1 21 IS-2-SC S-2-SC MAIN STEAMANBOARD MSEV NITROGEN SUPPLY ACCUMULATOR YES NO YES NO T NO X 11 21 jS-2-5D 11 07 IVU-6A D I MAIN STEAM/INBOARD MSIV NITROGEN SUPPLY ACCUMULATOR YES NO YES NO I T NO X A'MAIN STEAM/OUTBOARD MSIV YES NO YES NO T NO x 1 07 IV2.86E V2-.66 YES NO YES NO T NO X 1 j 07 IV2C-6C JV2C-6C A/C IS-2-Sc Am, x x MAIN STEAM'RELIEF VALVE YES NO YES NO T NO X 1 I 07 IRV-2-710 RV-2-710 MAIN STEAM;RELIEF VALVE YES NO YES NO 1 O S 6E-o0C-3 E-1000-3 TK-55.IA PCV-1.15 S-2-13A S-2-13E MAKE-NO NO NO NO NO NO X X 7 X X SAFETY RELIEF VALVE/NITROGEN SUPPLY ACCUMULATOR YES NO YES NO T 1 21 &S2-13B SAFETY RELIEF VALVEINITROGEN SUPPLY ACCUMULATOR YES NO YES NO NO x 1I 21 S-2-13C S-2-t 3C S-C-I1CO"-1D.1A V10-26A SAFETY RELII YES YES YES YES YES NO NO NO NO NO YES YES YES YES YES NO NO NO NO T NO X O RHR/E RHR HEAT EXCHANGER NO X 1 MA IVIO-26A 1 1 8A VIt 0..26C EVI-26 TSPRAY MOV YES NO YES NO I NO x SPRAY MOV YES NO YES NO I NO X Table 9.4.1- Base List 1 Enpneenng Report No. VTY.RPT-12-00019 Rev. I Page 8 of 24 Afchrroent B I -r t ~ 0 T -T SCREEN1I SCREEN2 1 SCREEN3 SCREEN4____ + + r-.UNIT SQIJG CURRENT EQ~tMN EQUIPMENT ID CLASS SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Undergo Maintains at Seismic Regular least one of 1? Configuration the 5 afeaty Inspections?

Functions IPEEE Environment Inside) High Temp/Outside? Humoidity?

(110) TrIH)Borated System?Reactivity Pressre Inventory Decay Cent Containment oy "ureConrolRemovel

_______ _____ ______x x 08OA JV1031AN I 08A V 1031 a 1 06 P-IS-IC I 01A VIO-65A 1 08A 0l-656 VIO-31A YES NO YES I NO NO 0-316 YES YES YES YES YES NO NO NO NO NO YES NO NO X X YES IVI0-658 RHRIHEAT XC BYPASS MOV NO NO NO NO NO NO NO NO NO NO 1 08A V I-27A X V1 0-27A RHRLPCI INJECTION MOV X X X X V10-278 LI10-16A JIO-15A VIO-15C YES NO YES I 0UA NO NO NO NO NO YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO 1 rSA Vto-f C[RHRIRECIRC SUCTION MOV-1 YES x 7 X X I 2SA V10-158 VI-tU58 0SA VU-1so VIt0-150 U 08A VIU-34A V10-34A 1 08A VIt-348 Vt1-346 1 08A V1D-39A VIG-39A 1 0A V1D-398 VII-398 1 08A VID-38A V1U-38A 1 03A VtU-38B VIO-336 I 08A VIt-13A VIt-13A 1 U8A VI-130 1 VIU-130 07 PCV-1U.-69A PC'V'.tU0,6A I .a7 PCV,-104-696 IPCV-104-696 1 06 P,.8-1A >,,8-1A 1 06 P,.8-1B P-8-1 6 1 00 jP-fýlC P-8-1tC 1-L 06 1P.8.1D [P-6-1D YES YES YES YES YES YES NO NO NO NO NO YES NO NO NO I RHR(TORUS COOLING MOV NO NO NO NO NO X x 7 x 7 X S G MOV YES YES YES YES YES YES NO NO NO NO NO YES NO YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO E CONTROL VALVE X S X E CONTROL VALVE YES NO YVES NO x YES YES YES YES YES NO NO NO NO RHRSWD RHRSW PUMP NO YES X 7 L x 7 1 1 088 VIO-89A/1 O-S9A YES NO NO LYES NO NO NO NO NO YES NO NO NO NO-NO NO I H NO US P-7-1A SW/A SW PUMP YES--.......-

S -.-~1 1 f 07 IFV-104-17A F.7- I O4-17A'SW/A TRAU-VE:LLIING3 SCREEIN CO N VALVE: YES NO I H NO N-1-IS I YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO I H NO H NO 1 1 07 IFCV-104-17C FCV-104-17C

_L DC P-7-1D [P-7-1D 1 07 104--170 FCV-104-170 1 07 FCV-104-2aA FC11,104-28A 1 07 FGV-104-2081 FCV-104-288 1 21 TK-67-1A _ rK.67-1A 1 21 TK-67-il.

TK-67-1 S SWID SW PUMP SW/D TRAVELLING SCREEN SWIDG COOLING SWIDG COOLING SW/OG-A EXPANSION TrANK SW/DG-B EXPANSION TANK IL VALVE YES YES YES YES YES YES NO NO 0 H NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO I 07 FCV-10t-17E IFCV-*04-17E LING SCREEN CONTROL VALVE NO H NO NO YES NO YES NO YES NO YES NO YES NO 1 11210-3-1B G--1IB DG START A 3 MOTOR NO I NO NO 1 [I p 1A J I I pJ WJI" I L I 77- --5 YES NO Tgble 9.4.1- BFse List 1 Engineervg Report No. VTY-RPT-12-O0019 Rev. 1 Page 9 of 24 AN1,hment B SCREEN1 SCREEN 2 1 SCREEN 3 SCREEN4 SOUG CURRENT UNIT EQUIPMENT SSEL EQUIPMENT ID EQUIPMENT IC CLASS EQUIPMENT DESCRIPTION HPCliAUX OIL PUMP HPCICOND DRAIN TO COND HPCI'CONDENSATE PUMP Seismnic 1?Undergo Regular Configuration Inspections?

Maintains at leant ene of the 5 safety Functions Replaced?IPEEE Environment Inside/ High Tempi Btrated Outaide? Hmidity? System?(1/0) (T I HI m Reoctivity Pressure Inventory ecat Control Control Control Heat I I ReMOva Containment 1 05 p-.NO YES NO I I NO X x 1A 1 1-1A rU-- 1IA HPCIHPCI TURBINE YES NO NO x 1 07 1dPC ITUI 1 07 CRHVAC/LOW AMBIENT TEMP CON CRHVACILOW AMBIENT TEMP CON CRHVAC/SAC-1A COOLING COIL CRHVACISAC-1A FILTER SECTION YES YES YES YES YES YES YES YES NO YES NO NO x NO NO NO NO NO NO NO YES NO NO NO NO _ NO_NO N NO X NO 1 CRHVAC/SAC-1A HEATING COIL DG ROOM VENTILATIONIDG ROC NO NO 11 0 1 0 1 10 DG-A-INTAKE POS.113-20 11 Pos1 13-20XXX DG-IE-INTAKE-X RRUL5 FAN RRU-5 MOTOR RRUB AFAN G--IA4NTAKE LOUVER YES NO jEOS-1 13-2011-IRRU S MOTOR NO YES NO NO INO I I I I I NO I NO NO OTAL) YES NO NO NO NO TN-NO NO NO NO NO NO NO:kRU-, FAN 1 10 SWJRR U-5 MOTOR SWfRRU-6 FAN SW!RRU-6 MOTORFAN SWiRRU-7 MOTOR SWRRU-8 FAN YES NO NO YES 1 10 RRU-8 MOTOR RRU-8 MOTOR 1 06 P.8-1A COOL COIL F-8-lA COOL COIL 1 06 P-8.1B COOL COIL P-8-18 COOL COIL 1 06 P.8-tC COOL COIL P-0-1C COOL COIL 1 06 P-S-1D COOL COIL P-81-D COOL COIL 1 088 SE-3,31A SE-3-31A 1 088 SE-34318 E.-3-318 1 08E SO-3-117-XX-XX SO-3-117-XX-XX 1 088 SO-3-118-XX-XX SO1 -X-XX-X 1 085 LSO-108-2A LSO6-10-2A 1 088 LSO-108-2B LSO-108-2E SWIRRU-8 MOTOR YES YES YES YES YES YES YES YES YES YES YES RHRSWIP-8-1D MOTOR COOLING COIL CRD/SCRAM DISCHARGE VOLUME VENTIDRAIN SOV FUEL OIIjDG DAY TK FILL FUEL OILIDG DAY TK FILL FUEL OILIHEAT BOILER TK NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO YES NO III YES NO I YES NO I YES NO I NO NO I NO NO I NO NO I YES NO I NO NO YES NO YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO X i X1 1 08B ILSO-108-3 1 088 SE-25-5 I 08B LSO-23-5d 1 20 FIC-23-108 20 F623,008m!

1 088 LSOý23-40 SO-108-3:1-23-10?,I HPCI FLOW CON HPCI FLOW IND qPCI GOS. COND YES YES YES YES YES YES YES YES YES____ YES____ YES YES 11 088 ILSO-23-39 ILSO-25-39

_H YES NO YES NO YES NO YES NO YES NO YES NO YES NO YES NO X x x 7 x 7 x S X S X X 7 X X X X X X 7 X 1 1 08B 1ISE-3-1 5-,23-94 IHPCIlDCIAC INVERTER iE-23-t I 1 0 ITS23-101A

-TSr23-101A HPCIlREMOTE TURBINE TRIP HPCI/STEAM LEAK DETECTOR HPCI,STEAM LEAK DETECTOR HPCIiSTEAM LEAK DETECTOR HPCItSTEAM LEAK DETECTOR T 3-1010i TS-23-1 6BD I-WO [501-1JOB rlIIOIAM NAKUICUUM YS INO 3-1028 T.-23-1028

'HF'CISTEAM LEAK DETECTOR YES I NO I Engineering Report No. VIY-RPr-12-O0019 Rev, I page 1l0of 24 Allaonmerd B UNII SQUG EQUIPMENT CLASS SCREEN1I SCREEN 2 1 SCREEN 3-I4 n-CURN SSEL EQUIPMENT ID EQUIPMENT IG EQUIPMENT DESCRIPTION Seismnic 1?Undergo Regular Configuration Inspections?

Maintains at least One Of the 8 safety FunctionsIPEEE SCREEN4 Environment Insidel High Tempi Outside? Humidity?(I/O) ( /H)Borated Systemn Reactivity Pressure Inventory Control Control Control 1 IOITS 102A ITS.23.102A 4 -- 4--11t-ýAlvl LEAK DETECTOR YES NO YES NO I NO X x x x AM I YES NO YES NO I T NO X X NO YES TS-23-103B IHPCI/STEAM LEAK DETECTOR NO NO NO NO NO NO NO NO NO NO X X 0 ITS-23-103C TS--1A03C HPCI/STEAM LEAK DETECTOR YES NO 1 1 0 17S-23-1030 ITS-2a-1030

<DETECTOR ,1 04A YES YES YES YES YES YES NO YES X X NO NO NO NO NO YES YES YES YES YES NO NO NO NO NO T NO NO NO NO NO X X 1 TS-.23-O4D HPCI,STEAM LEAK DETECTOR CSTILEVEL SWITCHES 1 20 SL-10/-SA LSL-107-SA S 1 20 TULEVEL I YES NO YES NO NO X NO sE.2-s 08.1 INBOARD MSIV SOLENOID AC/DC YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO I x 1 8OE ISE-2450.-r SE-2-80C-I 1 08E ISE-2-80D-1 SE-2-8SM-1 NBOARD MSIV SOLENOID ACIDC INBOARD MSIV SOLENOID AC/DC RECIRCiSAMPLE LINE INBOARD ISOLA'RECIRC/SAMPLE LINE OUTBOARD ISOl MS SAFETY/RELIEF VALVE SOLENOID MS SAFETY/REUEF VALVE SOLENOID YES NO YES NO T X NO YES YES YES YES YES NO NO NO NO NO T T T T NO NO NO NO NO x x x x x 088 SE-2-71B YES NO 1 085 3E.2-71C 1 088 SE-2-71 D 1 088 SE-2-86A-A 1 088 1 088 SE-2-86c-1 ONE E-2-.86D.1 1 07 FCV-10-160 SE-2-71 C 96-2-7ID SE-2-86A-I SE-2-866-1 SE.2-tt C-i SE-2-86D-1 FCV-IO-160 FSO-11 0-180 F60.104-1/A FDO-l0.1 lB FSO-t54-1

/0 MS 0 YES NO YES YES YES YES YES YES MSIOUTBOARD MSIV SOLENOID AC/DC SWiB TRAVELLING SCREEN FLOW SOLENOID FCV-104-17B 1 08E IFSO-104-7C 11 08 IFSO.104-17D IFSO-l04-I10 SW/C TRAVELLING SCREEN FLOW SOLEN(SWID TRAVELLING SCREEN FLOW SOLEN(SW/DG A FLOW CONTROLLER SW/DG B FLOW CONTROLLER SWeDG COOLING FCV-104-28A SW/DG COOLING FCV-104,-286 SW/E TRAVELLING SCREEN FLOW SOLENC CAC SOV AIR ISOLATION (INBD) INJECTION 1-17C-1 7D YES YES YES YES YES YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO ND NO NO YES YES NO YES N3 YES NO 1 NO T T T T T H H H H H NO NO NO NO NO NO NO X x X NO NO NO x NO NO Y 1 1 088 1 08B FSO.104.17E 1I1 088E NG-12B FSO-104-28B FSO-104-1IE NO-lOB VG-22A VG-22B NO-1A FL-17E S PNL B NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO I CAD SOV AIR ISOLATION (OUTED) COMPR DISCHARGE PNL A YES NO YES NO YES NO YES NO YES NO YES NO YES NO S x x x x x x x 085 NG-13A CAD SOV AIR ISOLATION (INBD) INJI CAD SOV AIR ISOLATION (INBD) INJI TO DW PNL A STO DW PNL 8 I 088 ING-13B ING-138 YES YES YES YES YES YES Table 9.4.1- Base List 1 Erlgineering Report No. VIY-RPT-12-00019 Rev. I Page 11 of 24 Attachmnent B I 7 r ,~e -*e SCREEN1 SCREEN 2 SCREEN 3 SCREEN4-t + +r -UNIT QSO2U" CURRENT EQUIPMENTEQUIPMENT ID CLASS SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Undergo Maintains at Seismic Regular least one of 1? Configuration the 5 safety Inspections?

Functions Replaced7l IPEEE EnLironment Inside/ High Tempi Outside? Humidity?(110) (TIH)Borated System?Decay Reuctivity Pressure Inenltcry Heat Containment Control Control Control Re Removal___ ___ -- -t -- t--t-t---t 1-1 t ~ -t --S 081E FSO-109.75A4 FSO-109-75A-4 1 LISE VG-SE VG.5 I 08B VI-. A VT-,A 1 08B FSO-109.76A PSO-10S-75A 1 088 FSO-109-765 PSO-109-76E E ISOLATION YES NO YES NO NO IYES NO NO NO NO NO YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO x SAMPLE SYSTEM ISOLATION (OUTED) CAM RETURN TO TORUS YES x X X X X 1 07 V20-94 V20-94 DRYWELL EQUIPMENT DRAINS ISOLATION (INBD)AOV YES DRYWELL I)AOV YES YES YES YES YES NO NO NO NO NO YES YES YES YES YES YES NO NO NO NO NO NO NO x 1 07 IV72-38A-V72-33A CAC SUCTION AOV x x K x 1 07 IV72-368 V72-388 CAC SUCTION AOV 1 56-11 q (INED)YES NO NO-NO I 07 SE-" YES YES YES YES NO NO NO NO NO NO NO NO NO NO X 1 07 FCV-2-39;CV-2-39 1 07 FCV-2-40 CCV-2.40 RECIRCiSAMPLE LINE INBOARD ISOLATION RECIRCSAMPLE LINE OUTBOARD ISOLATION 18" DRYWELL VENT AOV ISOLATION (INED)18" TORUS VENT AOV ISOLATION (INBD)3' DRYWELL VENT AOV ISOLATION (INED)3 TORUS VENT AOV ISOLATION (INBD)YES NO x X K X-X YES NO-- NO 1 YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO 1 07 ISE-16-19-68 K X K K X I 07 SE-1.-19-9 55-I 9-IS-S ,IR PURGE)AOV YES NO Vi&-20-22A YES YES YES YES NO 1 YES YES YES YES YES NO NO I NO NO 1 07 SE-1-19-23 S.-16-1g-23 1 07 SI..16-19-11A S6-IS-19-11-A 1 07 55-15-IS-11E SE-IS-IS-1IE I 07 S-1E19-I 8 SE-1619-IS 1 07 SB-16-IS-?

S-16-l-I7-1 07 SE-S16.19-I-S.E-119-I I 07 SE-16-1S-10 SE-la-19-ID 1 08A V70-117 ,V70-117 I 08A V13-1b V13-15 1 08A V13-16 V13-1S 1 OaA V10-57 V`I -57 1 O8A Vyb-66 V1 0-.6 I 08A V10-17 V1;-17 1 08A Vi1-IS V10-18 1 0A V12-15 V1t-15 1 08A V12-18 V12-1I 1 21 1 0 VV-SNA v2-g6A 1 0 V2.-7A V2-27A 1 0 V2-28A V'2-28A YES NO NO I I I I NO N2 PURGE SUPPLY ISOLATION (OUTED) AOV YES NO DN(OUTBO)AOV YES NO ON(OUTBD)AOV YES NO YES NO YES YES YES YES YES YES YES YES NO NO NO NO NO NO K x NO NO NO NO NO NO NO X RCICJSTEAM SUPPLY MOV IYES"'. I-4 .. .:U Vq 1LV-. -Xv RHRXMOV TO RW RHRJMOV TO RW RHR/SDC VALVE RHRJSDC VALVE YES NO 4YES NO YES Nf YES NO YES NOC YES 0NO YES NO NO x I NO I NO x YES NO I T NO YES NO NO YES YES YES YES YES YES YES NO NO NO NO NO NO NO NO X x FDW/INSOARD CHECK VALVE YES NO YES NO 1 I 0 V2-20E Ii T NO NO iRA YES I NO K X NO -is DOPT-2-116D DPT.2-1160 IlSISTEAM DIFF PRESSURE TRANSMITTER A YES Table 9.4,1- Base List 1 Engneering Rupod No. VTY-RPT-12-00019 Rev. 1 Page 12 of 24 Attnhmerd B SCREEN11 SCREEN 2 SCREEN 3 SCREEN4 UNIT CURRENT EQUIMN EU E EQUIPMENT 10 CLASS SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Seismic 1?Undergo Regular Configuration Inspections?

Maintains at least one of the 5 safety Functions YES YES YES Replaced?j IPEEE Environment Inside./ High T!mpl Outside? Humidity?(110) I I/H)Berated System?NO NO I I Decay Reactivity Pressure Inventory Heat Control Control Control Removal 1 18 OPT-2-117A DPT-2-117A 1 18 DPT-2.117C OPT-2-1178 1 18 0PT-2-117C DPTý-2117C 1 18 OPT-2-117C DPT.2-1t7D 1 18 OPT-2-118A DPT.2-11I A I _i8 OPT-2-11813 OPI"-.-11I8a 1 M8 0PT-2-118C DPT.2-11I8C B YES NO B YES NO Containment x X x x YES NO NO IYES NO NO NO NO NO YES YES YES YES YES NO NO NO NO NO NO 1 18 DPT-2-118D DPT-2-t OPT-2m-1 19A VpT-T-115E9 DPT-2wl iSC OPT-2.t119D V70013I MSJSTEAM 0lFF PRESSURE TRANSMITTER C MSISTEAM DIFF PRESSURE TRANSMITTER C MSISTEAM DIFF PRESSURE TRANSMITTER 0 MSISTEAM DIFF PRESSURE TRANSMITTER D MSISTEAM D0FF PRESSURE TRANSMITTER D MSJSTEAM 01FF PRESSURE TRANSMITTER D RBCCWiRC ISOLATION CHECK VALVE YES NOI x x x x x YES YES YES YES YES NO YES NO NO NO NO NO NO 1 1 18 I DPT-2-1190 YES YES YES YES NO NO NO NO NO NO NO NO NO NO 1 0 x V70- 1.1 x x x_x x PS-13-ITA PS-1.3-37A PS-13-81C P.1-1-870)

TS-13-79A RCIC/LOW 8 YES YES YES YES YES YE-S NO NO NO NO NO NO YES YES YES NO NO NO NO NO NO 1 1 0 ITS-I3-79A 1 0 ITS-13mBOA 2 imilE2:21 l, I 11ZA_1 0 IFI.104.,DA_

1 0 FI-10ý7013 TS-13-80A TS.13-81A TS-13-82A PI-104-7 TA PI-104-708B RCICISTEAM LEAK DETECTION RCIC/STEAM LEAK DETECTION RCIC/STEAM LEAK DETECTION RCIC/STEAM LEAK DETECTION RHRSWPUMP A COOLING WATER FLOW INDICATOR RHRSWiPUMP B COOLING WATER FLOW INDICATOR NO x X_x X x YES YES YES YES YES NO YES NO T NO NO YES NO NO NO NO NO NO NO NO NO NO x 1x1 I ffl i"" 1 0 IFI-104-IOC 1 0_L _03A ý,na I 08A IVIO-183 1 0 lFm24-16 FI.104-70C RHRSWJPUMP C COOLI R FLOW INDICATOR NO FI-1T4-7TO 1/10-133 LP. lAH-IMP 0 COOLI R FLC YES YES YES YES YES NO YES NO YES NO NO NO NO NO NO X 1 I 14 ILP-IAH DG "A" LIGHTING PNL NO I T-LP1A1-HýP-IAJ T-LP.IAJ AC-OP-S 771-L RP-.9A R FOR LP-1AH DG "A" YES NO NO NO 1 14 AC-OP.S 1 14 LP.IL 1 14 PP.gA 1 14 CP-82-1 1 14 CP-82.3 1 20 CRP 903 1 2) CRP 9-04 1 20 CRP 9M5 1 20 CRP 9.06 1 20 CRP 9-07 1 20 CRP 90a I 20 CRP 9-10 1 20 CRP 9-12 1 20 CRP 9-14 1 20 CRP 9-15 I 20 CRP 9.17 1 20: ORP9Ei1 1 20 CRP 9-20 LIGHTING PNL-I20V AC 240;12 TAC POWER PANEL AT MCC-9A FOR SEGT ALTERNATE SHUTDOWN PANEL ALTERNATE SHUTDOWN PANEL CONTROL ROOM PANEL CONTROL ROOM PANEL CONTROL ROOM PANEL CONTROL ROOM PANEL YES YES YES YES YES YES YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO I NO NO NO NO NO NO NO NO NO NO NO^RP 9-01^RP 9-07;RP 9-08 TRP 9-10-RP 9-12 TRP 9-14^RP 9-15 TRP 9-17 TAP 9-la TRP 9-20 NO NO NO NO NO NO NO NO NO NO NO NO NO NO CONTROL ROOM PANEL CONTROLI"_L_YES YES IYES NO NO NO NO NO NO NO NO CONTROL ROOM PANEL ,ONTROL ROOM PANEL Table 9.4.1- Base List Engineenng Report No. VTY-RPT-12-00019 RPe .I Page 13 of 24 Alachment 8 SCREENI SCREEN 2 SCREEN 3 SCREEN4 SQUG CURRENT Undergo Maintains at Environment Rea tory Decay UNIT EQUIPMENT EQUIPNT T ID SSEL EQUIPMENT EQUIPMENT DESCRIPTION seismic Regular least O o eplaced IPEEE Inide High Tempi Brated Control Control Cntrl Heat Containment CLASS 1? Configuration tho 5 flety Outside? Humidity?

Removal Inspections?

Functions (I a O) (iT y H) System?1 20 CRP 9.22 CRP 9-22 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9-25 CRP 9.25 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9.26 CRP 9-26 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9-27 CRP 9-27 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9-30 CRP 9-30 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9-32 CRP 9.32 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9.33 CRP 9-33 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9.39 CRP 9-39 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9.41 CRP 9-41 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9-42 CRP 9-42 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9.45 CRP 9.45 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9-46 CRP 9.46 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CRP 9-L47 CRP 9-47 CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CAI PNL A CAD PNL A CONTROL ROOM PANEL YES NO NO NO I NO 1 20 CAD PNL B CAD PNL E CONTROL ROOM PANEL YES NO NO NO I NO 1 20 PPP-A-1 PPP.A.I RPS PVAR PROTECTION PNL PNL A-1 YES NO YES NO I NO X 1 20 PPP-A-2 PPP-A.2 RPS PWR PROTECTION PNL PNL A-2 YES NO YES NO I NO X 1 20 PPPR-B- PPP.B.1 RPS PWR PROTECTION PNL PNL B-I YES NO YES NO I NO X 1 20 PPP-E-2 PPP-B-2 RPS PWR PROTECTION PNL PNL-B-2 YES NO YES NO I NO X 1 20 DOG VOLT REQ CAB DO RMS VOLTAGE REGULATOR CAB YES NO NO NO YES I NO 1 20 NEUTRAL TRANSCAB DRMANEUTRAL TRANSFORMER CAB YES NO NO NO YES I NO 1 1 1 1 20 20 20 17 18 CONTBOARD)G RM A CONTROL BOARD YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO YES NO O.SL.10B-13A ILSL-108-13A DIESEL FUEL OIL TRANSFER PUMP START NO I 19 SL-100-13B LSL-108-13A DIESEL FUEL OIL 1 3-12A LSVI-108-12A L OIL YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO 18 ILSH-23-90-PCIIMS COND DRAIN POT LCV-23-53 CONTROL YES I NO I x x 1 089 18 11 18 IS;SO-10-161 FSO-10-t61 RHRISYS PROCESS SAMPLE-S-2-I w4 PS-2-134A JIS LINE PRESS YES YES YES YES YES NO YES NO YESI NO IJI NO NO NO NO NO x x.S-2-.4S LINE PRESS NO YES NO IC 18'S-2-1 IA PS-2-t1A 1 18 1 PS-2-1 16 fps-2-ils 1 18 PS-2-1 I C PS-2-11C 1 18 PS-2mi 10 P&2w!!D 18 PSwi0w1D5A PS-10-1175A 1 18 PS-10-IDBB PSi0wi05S 1 18 PS-10-105C -PS-10-105C ONDENSER VACUUM.ONDENSER VACUUM 3ONDENSER VACUUM 3ONDENSER VACUUM kHR PP A DISCH PRESS INTERLOCK OHR PP B DISCH PRESS INTERLOCK YES NO YES NO NO X YES YES YES YES YES NO NO NO NO NO0 YES NO NO X YES NO NO x DISCH F 1 18 jPS-1O-12ID PS-10-D050 OHR PP D DISCH PRESS INTERLOCK RHR PP A DISCH PRESS INTERLOCK RHR PP B DISCH PRESS INTERLOCK RHR PP C DISCH PRESS INTERLOCK YES YES YES YES YES NO YES NO NO YES NO NO NO NO NO NO x x x x 1 NO YES NO I 1 18 IPS-1AG10-SH PSI.-109i HR PP D DISCH PR YES NO YES NO NO 1 1 08B j S E.1-9A 99-1-129-SB SB-9 SOV 1 08B ISE-1-15g SEI12,9 EB- SOVY___IY B YS I NO YES JNNO YEIO________

__YES__ I_ _ I _ NO_ YESN x x Table 9.4.1- Base List Engneering Report No. VTY-RPT-12-00019 Re,. I Page 14 of 24 Airachmerd B r.-z-tzr, --a * --, , -SQUG UNITI EQUIPMENT CLASS CURRENT EQUIPMENT ID SCREEN11 SCREEN 2 I SCREEN 3 t 4-, -SCREEN4 SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Seismic 17 Undergo Regular Configuration Inspections?

Maintains at least one of the 5 safety Functions IPEEE Replaced.Environment Inside! High Temp)Outside? Humidity?(1IO) (TIH)eorated System.Reactivity Pressure Inventory Hecaty otimn Control Control Control e Continment Control Removal SE-t SBý9 SOV YEO YES YES YES YES NO YES NO NO X NO USB ISE.1-125.iOC I SE-. 1251kC ISE-I0SsOy YES YES YES YES YES NO NO NO NO NO NO NO NO NO TNO x x I USE ISE'1-125.1 1A SE- '1 ,1 1 A SBEI1 SOV NO X x X X SE-t-t 25-118 I USE SE-I-1 I DB3 SE-1-125-12C ISE.1-125-120 SB-1I SOV SB-I SOV SBA-2 SOV SBE-2 SOV SBE 12 SOV RWCU/FLOW TRANSMITTER RWCU/FLOW TRANSMITTER TORUS VACUUM W CONTROL TORUS VACUUM W CONTROL TEF-2 DG EXH FAN CONTROLS YES YES YES YES YES NO YES NO NO NO NO NO NO INO YES NO I NO X 1 18 JFT.12-IA 1 18 FT-12-IS 1 18 OPIS-16-1!

1 18 OPIS.16-v^10 B-1093 FT-I12-IA NO YES YES YES YES YES YES NO YES NO X-NO E-1098 YES YES NO NO NO NO NO NO NO7-NTO NO NO NO NO NO X X 20 E6-1099 B.1099 rEF-2 DG EXH FAN CONTROLS NO BA 100 B-1101 B-I92 B-1052 TEF-3 DO EXH F YES NO 20 Ismi US?105 MCC-SC L NO NO NO NO NO NO NO YES YES NO NO NO NO NO NO NO NO NO NO RWCUIHI TEMP ISOL SYS TB BOX YES 1 B5-1060 13-i 061 8-1062 5-I1013 s-tU0.: LI YES YES RWCUV NO NO NO NO NO YES YES YES YES YES NO NO NO NO NO-NO0 1 0 B-1064 X RWCU/HI TEMP ISOL SYS TE BOX YES I NO NO NO NO NO X B-1065 B-1066 HVSGP-A HVSGP-B HVFRP-A HVAC PNL 2 B-1 065 8-1066 IIVSGP-A HVSGP-S HVFRP-A HVAC PNL 2 RWCU/HI TEMP ISOL I RWCU/HI TrEMP ISOL I RRU 5.6.7.8 SWITCH B RRU 5.6.7.8 SWITCH B HVAC "A" CONT PNL HVAC PNL -SAC-I YES YES 1 20 NO NO NO NO NO NO YES NO NO NO NO NO NO NO NO NO NO NO X I 14 1 0 L-1I 1 20 RATS-lA 1 20 RATS-1B 1 0 TS-113-4001 1 U FS-113-4001 o U FS-113-4005 1 08U SE-113-2007 1 08B SE-113-2021 1 USE SE-1T13-2022 S 088 SEt-132-023 1 20 25-5A 1 20 25-5B L&17 RATS.IA RATFS-18 TSE.113..4001 FýS.113..4001 F $.,113-4005 SE-`113-2007 SE-113-2021 DG "B RM DAMPER MOTOR DO-lA RM THERMOSTAT DO-iB RM THERMOSTAT SAC-1 FREEZESTAT SWITCH SP-I DISCH FLOW SWITCH SP-2 DISCH FLOW SWITCH DOG RM A DAMPER SOV DG RM 8 DAMPER SOV DOG RM B DAMPER SOV DO RM B DAMPER SOV ANALOG CABINET ANALOG CABINET ANALOG CABINET YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO________________

YES NO NO N ___ I ___ I.N i___ I___ ___ __

Table 9.4.1- Base List Engineering Report No. VTY.RPT-12-00019 Rev. I Page 15 of 24 Attachment B r r rT .. r t CREEN11 SCREEN 2 1 SCREEN3 SCREEN4 UNIn CURRENT EQUIPMENTEQUIPMENT CLASS 7 SSEL EQUIPMENT ID R5-56B ONL-VAC-MG-2-tA-ONT BOARD 1 I EQUIPMENT DESCRIPTION ANALOG CABINET CONTROL PANEL FOR VITAL AC MG-2-IA DG RM B CONTROL BOARD DG RM B ENGINE CONTACTOR CAB DG RM B ENGINE INSTR PNL DG RM B EQUIP SKID DG RM B NEUTRAL TRANSFORMER CAB DG RM A VOLTAGE REGULATOR CAB Seismic 1?YES YES YES YES Undergo Regular Configuration Inspections?

Maintains at leant one of the 5 safety Functions ReplacedI IPEEE Environment Inside/ : High Temp/Outside? I Humidity?(1/0) (T/H)NO NO NO NO NO NO NO Borated System?Reactivity Pressure I Inventory He C o n Control Control Control Remofol I Removal x x t 20 20 17 20 20:NG CONTACTOR CAB NO NO YES YES YES YES YES NO NO NO 1 3 CAB NO NO NO NO YES NO NO NO NO NO NO NO NO NO NO 1 04 T-LP-IL r-LP.IL TRANFORMER FOR LP-1L IN CONTROL ROOM NO TB.i3.75B TS.1-W9C TB-I13-790 TS-13-80E TS-13-80C LEAK [YES NO YES YES YES YES YES NO NO NO NO NO YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO X 0 TS-13-80C RCIC/STEAM LEAK DETECTION X x X X 1 0 TS,-13-SM TS-11-800 TB-13-SD TS-13-81C TS-13-8ID TS-13-82B LEAK YES YES YES YES YES NO NO NO NO NO YES NO NO YES YES YES YES 1 0 ITS-13-82B RCICOSTEAM LEAK DETECTION NO NO NO NO NO NO X X 1 1 I 1 7 0- tE,-13-,82C 0 rS-13-820 20 ES-16-19-13A 20 ES-S16-19-138 TS-13-82C RCICISTEAM LEAK E 1 20 ES-10-145A

-1 20 ES-10.1--43 1 20 PR.1&19.44 1 18 EG"23ý1 _1 _18 RGSr,23-1 1 1 1 1 1 1 01 ILSB-V23-16 TS-I3-82D FAN CONT BOX B ES-16-19-13A ES-I 5-19-13E ES-10-145A ES-16-1953 PR-i6-19-44 EGM-23-1 RGSC-2,:-I LSB-V23-16 LSB-V23-19 LSB-V23-20 TS-12-1OIA TS-12-I01S TS- 12-102A TS-12-1028 TS-12-103A TS-10-I03B TS-12-106A TS-12-1068 1-1 SPRESSURE LEAKIr vOWER SUPPLY FOR PI-16-19-36A TORUS PRESSURE YES YES YES YES YES YES YES YES YES YES YES YES YES YES YE S NO YES IPCI/LOCAL STARTER BOX FOR V23-16 MOV NO APCI ,LOCAL NO NO 3-19 MOV 0 rS1-10-T2A TS-12.-t2B RWCU/LINE TEMP MONITORING RWCU!LINE TEMP MONITORING RWCU/LINE TEMP MONITORING RWCU/LINE TEMP MONITORING RWCUILINE TEMP MONITORING TWCU/LINE TEMP MONITORING NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO YES NO 1 1 S TB13i2-106B 1 0 TS-12-107A TS-12-107A 0 TS-12-1076 TS-12-107B TS-1 2-108A TS-12-108A_

I o TS-12-108B TS-12-1086 1 0 TS-12-109A TS-12-109A 1 0 7S.12-109B 76-12-109B X NO NO NO NO NO NO X I YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES NO NO NO NO NO NO NO-NO NO NO NO NO NO NO NO NO NO NO NO NO ___NO X X x X X X K x RWCUILINE TEMP MONITORING 1 1 0 ITS-12-II1A ITS-12-110A YES YESJ YES NO I I NO NO NO I x YES O NO N X YES I NO i NO X Table 9.4.1 -Base List 1 Enigneenng Report No. VrY-RPT-12-00019 Rev. I Page 16 of 24 Aflcahmenl B 3CREENI SCREEN 2 1 SCREEN A SCREEN4-4 -----------------.-

___________________________

INII SOUG CURRENT EQUIPMENT EQUIPMENT ID CLASS SSEL EQUIPMENT ID EQUIPMENT DESCRIPTION Seismic 1?Undergo Regular Configuration Inspections?

Maintains at least one of the S safety Functions Replacedl IPEEE Environment Inside/ Nigh Temh p Outside? Humidt-/?(110) (T I H)Borated systam?Reactivity Control Decay Pressure Inventory Heat Control Control Remova Containment i i 1 1 1 1 1 0 TS-12-112A 0 TS-12-i 12B 18 FIS-14-45A is FIS-14"518 18 Pý-14-44A 7S.12-112A"VVUI./LINE ITEMI MONITOIRING YES NO YES I NO NO TS-11-1128 FIS-14-45A Fl S-14-45SB PS-I14-44A PS-i4-44 YES NO YES NO NO YES NO NO NO NO N-O YES NO NO xl YES NO NO 1 1 18 PS.14.48 ,SrB" PUMP DISCHARGE PRESSURE I YES x x x 18 PF-14.4C PS-14-44C SURE YES YES YES YES YES YES YES NO NO NO NO NO YES NO NO YES IS IFIS.I-1045B

-RS-10.1488 NO NO NO NO NO NO NO NO NO NO x x x 1 08S IFSO-109-75A-I PSO-109-75A-1 q (INBD) TORUS SUPPLY PNL A 1~~1 FSO-109-75A2 B-787 8-618 B-I102 LOCAL-1 3-16 YIES NO YES YES YES YES YES 1 0 18-1102 OCAL'NO NO NO NO NO YES YES YES YES NO NO NO NO NO NO NO X X 01 04 04 04 04 LOCAL-13-16, B-862 T-AC-OP-5 DT-3 DT.E OT-iD0 RCIC;LOCAL STARTER BOX FOR VI 3-16 MOV 8-"62 OCAL TERM BOX -VI 3-16 YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO 1 I 1 I 1 DT-I 0 a DT-4 DT-4 480,240-120 VAC DIST TRANSFORMER 480,240-120 VAC DIST TRANSFORMER 480/240-120 VAC DIST TRANSFORMER 480 VAC UPS-IA MG SET 480 VAC UPS-lB MG SET 480 VAC UPS-IA CONTROL PANEL YES NO I INO YES YES YES YES YES NO NO NO NO NTO NO NO 1 20 CP-UPS-1A-P.UPS.IA 1 20 CP-UPS-lB 1 1 PT-104-20E 1 18 PS-104-120A 1 18 PS-104-120B 1 10 PS-104-120C 1 18 PS-104-1200 1 20 ES-1-156-5 1 is RK25-SI 1 18 RK25-50 1 1 RK25-TA 1 18 RK25-78 1 10 RK25-23 1 IS RK25-24 1 18 RK25-0A 1 1I RK.25-50B 1 I8 RK25-51A I IS RK25-51B 2^P-UFS-IB3 PT-154-205 PS-104-1 20A PIS-I 04-12083 PS-i 04-12 OC p5.104-1200 480 VAC UPS-lB CONTROL PANEL SW/HEADER TRANSMITTER V70-1A.B, 20 ISOLATION V70-19A.B, 20 ISOLATION V70-19A.B 20 ISOLATION V70-19A.B.

20 ISOLATION YES YES YES YES YES YES ES-1-158-5 jPOWER SUPPLY FOR LSL-t07-5B RK25-78 K(B)RECIRC PUMP A INST. RACK RECIRC PUMP B INST. RACK HPCI INST. RACK (A)HPCI INST. RACK (B)JET PUMP INST. RACK (51A)JET PUMP INST. RACK ISIS)YES YES YES YES YES YES YES YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO YES NO YES NO YES NO YES NO YES NO YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO YES x x X X x X YES I x X R1K25-518 YES YES NO YES I NO x NO X YES NO YES I NO NO NO NO 10 P 1<2-68 J1<25-;5 6 1 IS PR2-S IR<5S RCIC RM INST. RAC RHR INST. RACK (A)NO YES I~ NO I I 1* ( N{lNn 1RHR INST RACK (8) YES NO YES I Table 9.4.1- Base List Engineering Reporl No. VTY-RPT-12-00019 Rev, I Page 17 of 24 Attacnmern B-e t V nr 1~ -- -~I* --. .T t-*'t rn UNIT SQUG EQUIPMENT CLASS CURRENT EQUIPMENT ID x x 1 8 1 18 1 18 1 18 1 18A SSEL EQUIPMENT ID RK25-SA RK25-5S RK25-SA RK25-6B V70-257A V70-2578 PT-I04-20A EGR TC-13406A EQUIPMENT DESCRIPTION Seismic I?Undergo ReguLar Configuration Inspections?

Maintoina ot least one of the 5 Safety Functions Replaced?j IPEEE Environment Insidel.I High Templ Outside? H.midity?(liD0) IT I H SCREEN11 SCREEN 2 1 SCREEN 3 Borated System?SCREEN4 Decay Reactivity Pressure Inventory Heay Control Control Control Removal RE NST. RACK YES NO YES YES YES NO NO NO X NO Containment REACTOR PROT. & NSSS INST. RACK SWE-19-2A OUTLET YES NO INO 1 08A SW E- 9-28 OUTLET SW!HEADER TRANSMITTER HPCI EGR ACTUATOR ASSEMBLY (TURB SPEED CON SAC-1 TCV YES NO NO NO NO NO A'NO YES NO NO NO NO NO p.4002 SAC-I DISCHARGE TEMPERATURE YES NO 1 0 EISOUl R SAC-IA 1 21~YES YES YES YES YE-S NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO CR FIRE DAMPER CONTROL SWITCH SCH-YES INO 1 21 SC I 20 SC 1 20 SC 1 07 PCV-1.456-1073A PCV-l-15-1073A N2 1 07 PCV--156-l173B PCV-I-15-1073S N2 1 0 FIS-1-16-76 FIS-1.15&-76 N2 1 0 D-2.IA Q-2-1A N2 1 0 DF 1 0 DF 1 0 V72-890 V72-St N2 1 0 V72-89C V72-89C N2 1 21 N2 I is RK-25-66 RK-25-66 CS 1 20 SE-1 13-4002 SE-1 13-4002 SA 1 20 SE-1 13A4003 SE-113-4003 SA I1 088 SE-70,3A ISE-70-3A BA E REGULATOR PRESSURE REGULATOR ROTO METER)RC ISOLATION CHECK VALVE/RC ISOLATION CHECK VALVE CYLINDERS (18 TOTAL) AND MANIFOLD IT INST. RACK C-IA EXHAUST DAMPER CONTROL.C-1E INLET/OUTLET DAMPER CONTROL.CKWASH FLOW CONTROL YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO YES YES YES YEN NO NO NO YNO YES NO NO NO NO NO NO NO NO x x X NO NO NO NO NO NO NO NO NO NO NO NO NO H NO H NO 1 08B ISE-7-3I JSE-70-3E BA(ý O0 ELA x 1 POWER SUPPLY FOR ECCS PANEL 6 X is SNVEL Item Tsble 9.4.2- SWEL 1 Engneenrig Repot1 No. VTY.RFT-12-00019 Rev. I Page 18 of 24 Afachment B DESCRIPTION

),HYDRAULIC CONTROL UNITS /899)/SC N VALVE r VALVES 1 N 3 N N 000015.1A 213'NECR A 06 5920-2258 000033 7TB 252'EDOGR A A 1,2,3,4,5 12 Y 000044;WEL1-007)G-I-1B 252'EDGRB B 1,2,3,4,5 17 Y 000049 5WELl-008.CV-108-2A FUEL OIL/DAY TANK FILL 252'DAY TK RM A A 1,2,3.4,5 07 N 000052 SWELl-009 TK-42-1B FUEL OILDIESEL OIL DAY TANK B TB 252' DAY TK RKM 8 B 1,2.3.4,5 21 1 Y 000053 SWELl-010 TK-40-IA FUEL OILIFUEL OIL STORAGE TANK YARD 252' 1,2.3,4,5 21 0 Y 000054 SWELl-011 P-92-1A FUEL OILIFUEL OIL TRANSFER PUMP A FO 241' A 1.2,3,4,5 05 I, H Y D00060 SWELl-012 M1C3--1A 120/240V VITAL AC MG SET RB 280' 1,2,3,4,5 13 1 Y 5920-4463 000061 SWELI-013 BC-i-IA 125VDCMAIN STATION BATTERY CHARGER A ON DC-1 CB 248' SWGR WEST 1,2,3,4,5 16 1 Y 00006D SWELI-014 B-AS-2 125V DC STATION BATTERY ON BUS DC-2AS TB 252' EDGR A 1,2,3,4,5 15 1 Y 000097 SWELl-015 B-1-1B 125V DC STATION BATTERY ON DC-2 CB 262' CABLE VAULT 1,2,3,4,5 15 1 Y 5920-4411 000069 SWELl-016 DC-1 125V DC DISTR PNL DC-1 1600AMp CB 262' CABLE VAULT 1,2,3,4,5 14 1 N 200071 SWELl-017 oc-2 126V DC DISTR PNL DC-2 160DAMP CB 262, CABLE VAULT 1,2,3,4,5 14 1 N 59204835 000081 SWELl-018 DC-ECCS-, 24 VDC ECGS PNL (B) RB 303' 1,2,3,4,5 14 1 Y 59204836 000085 SWELl-019 MCG-9C 480V ESS AC MCC-c- DIESEL IA ROOM (SII) TB 252' EDG A 1,2,3,4,5 01 1 Y 000098 SWELI-020 MCC-90 480V ESS AC MCC-9D -REACTOR BLDG RB 252' 1.2,3,4,5 01i N 000090 SWELl-021 MCC-88 480V ESS AC MCC-8B- REACTOR BLDG (SI) RB 280' 1,2,3,4,5 01 Y 000092 SVVELI-022 NCC-98 480V ESS AC M CC-9B- REACTOR BLDG ($11) RB 260' 1,2,3,4,5 01 y 0o0090 SWELI-023 BUS-9 480VAC SWITCHGEAR BUS NO.9 1600AMP(SIi, CB 248' SWGR EAST 1.2,3,4,5 02 1 N 000o09 SWELI-024 BUS-3 4KV -4160V SWITCHGEAR BUS NO.3 1200AMP (SI) CB 248' SWGR WEST 1,2,3,4,5 03 1 N 000101 SWEL1-025 T-8-1A STATION SERVICE TRANS 4160/480 BUS NO.8 CB 248' SWGR WEST 1,2,3,4,5 34 1 Y 000103 SWELl-026 TK4.-IA CONDENSATE STORAGE TANK YARD 252Z 2,3 21 0 N 000116 SWELl-027 P.44-IA HPCIIHPCI PUMP RB 213' HPCl 2.3 05 1 Y 5920-0622 000125 SWELl-028 P9-23-84-1 HPCI/PUMP SUCTION PRESSURE SWITCH RB 213' HPCI 2,3 18 1 Y 000129 SWELl-029 V23.l1 HPCI/STEAM SUPPLY MOV DW 266' 2,3 08A I, T N 000130 SWELl-030 V23-16 HPCIUSTEAM SUPPLY MOV ST 251' 2,3 08A I, T N 5920-1835 000140 SWELl -031 TEF-3 00B ROOM VENTILATION/EXHAUST FAN TB 252' EDG B B 1,2.3,4,5 09 1 Y 5920-4449 002164 SWELI-032 RRU-8 SWJECCS RM COOLING RB 213' SECR 1,2,3,4,5 10 1 N 5920-4683 00o074 SWELl-033 PT-2-3-52C CS. RHR PERMSSIVE RB 252' 3 18 1 Y 5920-3055/5920-3057 000176 SWELI-034 LT-107-.A CST/LEVEL TRANSMITTER CST VALVE 252 3 18 1. H YII 000177 SWELl-035 LT-107-5B CST/LEVEL TRANSMITTER CST VALVE 252 3s 19 I, H Y 5920-6041 000178 SWELl-036 PT-10-101A OW PRESSURE ECCS RB 280' 5 1 I Y 5920-3016/5920-3017 0001D 0 SWELl-037 PT-i-wic OW PRESSURE ECCS RB 280' 5 18 1 Y 5920-3016/5920-3017 000182 SWELl-038 PT."-IEIg-29A OW PRESSURE INDICATION RB 280' 5 s I Y 5920-3016/5920-3017 o0ois SWEL1-039 PT-5-12c OW PRESSURE SCRAM RB 280' 5 18 1 Y 5920-3016/5920-3017 o00z1o SWELl -040 PT-6-1m0 DW PRESSURE SCRAM RB 280' 5 18 I Y 5920-3016/5920-3017 00018 SWELl-041 -TE-10-19-30A DW TEMP INDICATION -DW 268' 5 i9 I, T Y 000203 SWELl-042 LT-2-3-72A RV LEVEL FOR RHR. DG. HPCI, RCIC, ADS. CS R8 280' 3 18 i Y 5920-301615920-3017 O00oz0s SWELI -043 LT-2-3-72C RV LEVEL FOR RHR. DG. HPCI. RCIC, ADS, CS RB 280' 3 18 1Y 5920-3016/5920-3017 0002o9 SWELl1-044 LT-2.-3-58A RV LEVEL SCRAM & PCIS RB 280' 5 18 1Y 590-31615920-3017 000210 SWELl-045O LT-2-3-563 RV LEVEL SCRAM & PCIS RR, 280' 5 18 1 Y 5920-3016/5920-3017 000227 SWELl-046 PT-2-30SSA IRV PRESSURE ECCS RB 280' 2 18 R Y 5920-3016/5920-3017 000,15 SWELl-047 PT-.2-3-56C RV PRESSURE ECCS RB 280' 2 Is8 Y 5920.3016/5920-3017 000cm SWELl-048 -P'r-23.ssc RV PRESSURE SCRAM RE 280' 2 18 1Y 5920-3016/5920-30'17 O00mo SWELl-049 PT-2-3-s55 RV PRESSURE SCRAM RB 280' 2 18Y 5920-3016/5920-3017 0=2i1 SWELl1-050 LT-2-3-73A RV SHROUD LEVEL. CONT SPRAY PERMISSIVE RB 252' 2 8Y 592D-3055/5920-3057 0022 WL 01PS-1104.53A SWiPUMP A PRESSURE SWITCH is 1 237' SW ROOM 1,2,3,4,5 8 ,HY Table 9.4.2- SWEL 1 Engineeing Repot No. VIY.RPT-12-00019 Rev. 1 Page 19 or 24 Attachment B 000257 SWELI-054 15.2-.A 000263 SWELl-055 IRV.2.71C ALP I 000266 SWELl-056 ITK-56.-1A

ý2 AIR RECIEVER RB 303'2 N 5920-5017 000268 SWELl-057 IS-2-13A SAFETY RELIEF VALVE/NrIROGEN SUPPLY ACCUMULATOR DW 275'2 21 I. T Y 000279 SWELl-058 P-ID010 RHRID RHR PUMP RB 213' SECR B 4 06 1 N 5920-1611 000281 SWELl-059 V10-656 RHRJHEAT XC BYPASS MOV RB 232' SECR B 4 08A I N 5920-9288 000282 SWELl-060 VIO-27A RHPRLPCI INJECTION MOV RB 252' 4 08A N 5920-5564/5920-5565 000300 SWELl-061 P-S-IC RHRSW/C RHRSW PUMP RB 232' NECR A 4 05 1 Y 5920-3855/5920-3944 OD0312 SWELl-062 Vio-89A RHRSWISW SUPPLY MOV RB 232' NECR A 4 08 I N 5920-11020 000314 SWELl-063 SP-7o-3A BACKWASH FLOW CONTROL IS 237' SW ROOM A 1,2,3.4,5 07 I. H N 5920-1811 000320 SWELl-064 P.1-IC SWIC SW PUMP IS 237' SW ROOM A 1,2,3,4,5 06 I. H Y 5920-3947/5920-4602 000394 -SWELI1-065 -LCV-108-03 -FUEL OIL/HEAT BOILER TK FILL FO 241' 1,2.3r4,5 07 I, H N 000324 SWELl-066 PCV.104-28A SWiDG COOLING TB 252' EbGRA A 1,2,3,4,5 07 1 N 000335 SWELl-067 V70-20 SW/TURB SLOG ISOL MOV RB 246' 7ORUS CW 1,2.3,4,5 08A I N 000353 SWELl-068 TU-I-IA -HPCIIHPCI TURBINE RB 213' HPCI 2,3 05 1 Y 000371 SWELl-069 (3-IB-INTAKE-1

-6 DG ROOM VENTILATION/DG ROOM E LOUVERS I6 TOTAL) TB 252' EOGR B B 1,2,3,4,5 0 1 Y 5920-9096 000401 SWELI-070 ES-23-110 HPCI INST PWR SUPPLY CB 272' CONT RM 2,3 0 N 5920-2678 000402 SWELl-071 FTA.2.3-110 HPCI SORT CONV-FLOW CB 272' CONT RM 2,3 20 1 N 5920-3258 000411 SWELI-072 ES-23-94 HPCI,DC/AC INVERTER C0 272' CON" RM 2.3 20 1 N 5920-3258 000420 SWELI-073 TS-23-IDIA HPCIISTEAM LEAK DETECTOR ST 251' 2,3 0 I, T Y 000426 SWELl-074 TS-23-102A HPCESTEAM LEAK DETECTOR ST 251' 2.3 0 I. T y 000428 SWELl-075 TS-23-103A HPCIISTEAM LEAK DETECTOR ST 251' 2,3 0 I. T Y 000432 SWELl -076 TS-23.104A HPCIISTEAM LEAK DETECTOR ST 251' 2,3_0 I. T Y 000496 SWEL1-077 SE-2-88A-1 MS&OUTBOARD MSIV SOLENOID ACDC ST 251' 5 086 1, T N 000512 SWELl-078 VG-22A CAD 1lOV VENT ISOLATION (OUTBD, RB 303' 5 08A I N 000515 SWEL1-079 NG-13A CAD SOV AIR ISOLATION IINBD) INJECTION TO DW PNL A RB 222' TORUS AREA 5 088 1 N 000554 SWELl-080 SE.-IS-I-PRIMARY CONTAINMENT VENT TO SBGT ISOLATION (OUTBD) AOV RB 303' 5 07 1 N 5920.4892/5920-4901 001210 SWELl-081 CRP 9-03 CONTROL ROOM PANEL CB 272 CONTRM 2,3 20 1 Y 5920-3258 001221 SWELl-082 CRP -.19 CONTROL ROOM PANEL CB 272 CONT RM 2,3 20 I N 5920-2678 001222 SWELl-083 CRP 9.2o CONTROL ROOM PANEL CB 272' CONT RM 2,3 20 1 N 5920-3770 001242 SWELl-084 DO RM B VOLTAGE REGULATOR CAB TB 252' EDGR B B 1.2,3,4,5 20 1 N 5920-3911/5920-4592 001243 SWELl-085 DG RM A NEUTRAL TRANSFORMER CAB TB 252' EDGRA A 1,2,3,4,5 20 1 Y 5920-4593 001354 SWELl -086 L-17 G33B"RM DAMPER MOTOR TB 252' EDGR B B 1.2,3,4,5 0 1 N 001355 SWELl-087 RATS-IA DG-IA RM THERMOSTAT TB 252' EOGR A A 1.2,3.4,5 20 1 N 001375 SWEL1-088 SE-113-2022 DOG RM B DAMPER SOV TB 252' EDGR B B 1,2,3,4,5 08B I N 001387 SWELl-089 D0 RM B ENGINE CONTACTOR CAB TB 252' EDGR B B 1.2,3.4,5 20 Y 031388 SWELl-090 CG RM B ENGINE INSTR PNL TB 252' EDGR B B 1,2,3,4,5 20 Y 5920-4801/5920-4802 001389 SWELl-091 DG RM B EQUIP SKID TB 252' EDGR B B 1,2.3,4,5 17 Y 001396 SWELl-092 T-LP-IL TRANFORMER FOR LP-1L IN CONTROL ROOM CB 262' CABLEVAULT 1,2,3.4,5 04 N 001514 SWELl-093 Es---15-.5 POWER SUPPLY FOR LSL-107-5E CB 272' CONTRM 2,3 20 N 001522 SWEL1-094 RK2s5.5A HPCI INST. RACK (A) RB 213' HPCI 2,3 18 1 Y 5920-3044/5920-3045 001523 SWELI-095 RK2.5-oe HPCI INST. RACK (B) RB 213' HPCG 2,3 is I Y 5920-3044/5920-3045 001526 SWELI-096 RK25-. JET PUMP INST. RACK (52A) RB 252' 1 18 I Y 5920-3055/5920-3057 001527 SWELl.097 RK26-528 JET PUMP INST. RACK (52B) RB 252' 1 1 s1 I Y 5920-305515920-3057 001534 SWELI-098 RK2--6A REACTOR PROT. & NSSS INST. RACK RB 280' 1 8 1 _ Y 5920-301615920-3017 001535 SWELl-099 RK25-BB REACTOR PROT. & NSSS INST. RACK RB 280' 1 s IS Y 5920-3016/5920-3017 001566 SWELgL-l0 RK-25-66 csr INST. RACK CST 252' 3 18 1, H Y 5920-6041 SWELl-101

-.!POWER SUPPLY FOR ECCS PANEL B CGB 248' SWGR EAST 2,4 16 1 Y SWELI-102 CYL-72-IA ITROGEN BOTTLE FOR BACKUP SRV SUPPLY RB 252' A 2 21 I N TAble 9,4.2- SWEL 1 Engioe-~g R Ocrl No. \TIY.RPT-12-O0l51 Rev. I Page 201of24 Atachrmenl B SSEL# I SWEL1# [EQUIPMENTIDI DESCRIPTION BLDG. I ELEV. I ROOM I TRAMN SYSTEM TYPE ICLASS ENVIORNMENT1 ANC I DWG System 1 Reactivity Control 2 Pressure Control 3 Inventory Control 4 Decoy Heat Removal 5 Containment-Dudng implementation of the Seismic Walkdowns SWEL-065 was determined to be inaccessible for inspection.

This SWEL numberwas valve FCV-104-17D, SW/D TRAVELLING SCREEN CONTROL VALVE. It was replaced with Valve LCV-108-3 which is located in the ouel 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.

Tnble 9.4.3- Base List 2 Engneering Repori No. VrY.RPT-12-00019 Re. I Page 21 of 24 AafChrnenl B to x ft x x BL2# EQUIPMENT ID DESCRIPTION BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT N/R 2001 ES-19-82B.

Power Supply (CAD PNL A) CAB 272' Control Room 5FPC 20 2002 N-19g-8113 Pressure indicator (CAD PNL A) CARB 272' Control Room SFPC 18 2003 T;.19-73B ITemperature indicator (CAD PN L A) CARB 272' Control Room SFPC 18 2004 dP1-19-76A Differential Pressure Indicator (CAD PNL AB CRB 272' Control Room SFPC 18 2005 ES-19-76A Power Supply (CAD PNL A) CAR 272' Control Room SFPC 20 2006 ES-19_8_A Power Suppy (CAD PNL B) CAB 1272' Control Room SFPC 20 2007 Pi-19.81A Pressure indicator (CAD PNL B) CAB 272' Control Room SFPC is 2008 TI-19-73A Ternperature indicator (CAD PN L B) CAB 272' Control Room 5FPC 18 2009 dPl-19-76A Differential Pressure Indicator (CAD PNL B) CAB 272' Cont.rol Room SFPC 18 2010 ESo19-76A

Power Supply (CAD PNL B) CAB 272' Control Room SFPC 20 2011 RK___A__, Rack _B 303' _FPC 18 7012 PI,19-82.A Pressure Indicator (RK-10AA)

RB 303' SFPC 18 2013 dPT-19-76A Differential Pressure Transmitter IRK-10AA)

RB 303' SPPC 18 2014 PT-19-81A Pressure Transmitter (RK-IOAA) 303' SFPC 18 2015 PI-19-83A Pressure Indicator (RK-10AA)

RB 303' SFPC 18.026 PS-19-0A Pressure Switch (RK-10AA) 303" SFPC 18 2017 PI_19-84A Pressure.

Indicator

_RK-!0AA_

_B 303' SFPC 18 2018 RK,_ __A_ Rick :B 303' SFPC 18 2019 P1.19-828 Pressure Indicator (RK-10AB)

R8 303' SFPC 18 2020 dPT-19-76R DifferentBl Pressure Transmitter (RK-IOAB_

AS 303' PFPC 18 2021 PT-19-818 Pressure Transmitter (RK-10AB)

RB 303' SFPC 18 2022 PI-19-838 Pressure Indicator (RK-ROAB)

B 303' SFPC 18 2023 PS-19.80B.

Pressure Switch (RK-1OAB)

AS 303' IEFPC is 2024 PI-19,84D Pres'sure Indicator (RK-10AB)

RB 303' !SFFC 18 2025 TI-19.72 Temperature tndicator 303' PP Hx Room SFPC 0 2026 TE-V9-73A Temperature Element RB 303' PP Hx Room SFPC 19 2027 TE-19-73B Temperature Element RB 303' PP Hx Room SFPC 19 2028 PE.19-73 Flow Element RB 303' FP Hx Room SFPC _0 2029 FI,19-73 Flow Indicator RB .303' FP Hx Room SFPC 0 2030 Ti.104-60 Temperature indicator RB 303' 5FPC 0 2031 TI,104,61 Temperature indicator ASB 3g03' SFPC 0 2032 V70-2$TA SW MOV SFPC Ax Outle 0 33' FP Hx Am SFPC RA 2033 V70-257B SW MOV SFPC Hx outlet AS 303' FP Hx Am 5FPC SA6.2,034 IP-19-2A SPPC Pump ASB 303' I-P Hx Am 5FPC 1 5 to Yt it 0 2035 P.19-23 SFPC Pump 303'PP Hx Rm 5FPC 5 202' 1ý ý12' Ispp;135 E '9 .3281 JSFPC t__________________________

B 13__ 03' I__PP Ho An, 1SPPC ____ 21 _________ B _33 _I xA JFC 12 2038 CAD PanelA Panel'RB 272'2ontrol Room iFPC/FPC 20 2039 CAD Panel B Panel jCRB 1272' !control Room SFPC/FPC-.3 2040 IRK-iD 303'2041 TI-19-1 Temperature indicator (RK-10i) _B 3ý03'2042 IPSL-19-69A Pressure Switch IRK-10l 303'2043 PSL-19-683

(-I0 2044:PC 18:PC 18 303':PC 18:RB 272'"ontrol Room:PC 18 Temperature Indicator (CAD PNL A):RB 272':ontrol Room:PC 18 Level Indicator (CAAD PNL B)'RB 272'-ontrol Room:PC 18 Table 9.4.3- Base List 2 Enspneering Report No. V-Y-RPT-12-00019 Rev. I Page 22 o 24 Ahachnmevt B BL-29 EQUIPMENT ID DESCRIPTION BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT N/R 2051 TI-19.71A Temperature indicator (CAD PNL B) CR8 272' Control Room FPC is 2052 TE-19-70A Temperature Element RB 303' FP Hx Room FPC 19 2053 TE-19-708 Temperature Element RB 303' FP Hx Room FPC 19 2054 TE-19.70C Temperature Element RB 303' FP Hx Room FPC 19 2055 TE-19.-A Temperature n lement RB 303' FP Hx Room FPC 19 205G TE-19-IB Temperature Element Re 303' FP Hx Room FPC 19 2057 PS-19.68A Pressure Switch RB 303' mFP Hx Room FPC 0 2058 PS119-683 Pressure Switch RB 303' FP Hx Room FPC 0 2059 TE-19-71A Temperature Element RaB 345' FPC 19 2060 TE-19-718

.P. Temperature Element R8 345' FPC 19 2061 LT-19-63A LevP STrank mimer RB 345' FPC 0 2062 LT-19-638 Level Transmitter RtB 345' FPC 0 2063 PI-19-65A Pressure Indicator RB 318' FPC 0 2064 P1.19.658 Pressure Indicator RS 318' FPC 0 2365 PM-19-.6A PreCsurC Indicator RB 3180' Skim Puma Rm_ _PC O 2066 P1,19-66$

Pressure REB 318" Skim Pump Rm FPC 0 2067 V19-220 FPC sytem suction isolation MOV RWB 303' FP Hx Rm FFC SA 2068 V19-221 FPC system su5ion isolation MOV RW8 303' FP Hx Rm FPC BA 2069 P-82-IA FPC Skimmer Pump Re :318' Skim Pump Rm FPC S 2070 P-82.113 FPC Skimmer Pump REB 318ý Skim Pump Rm FPC 5 2071 P-9-1A FPC Pump RB 203' FP Hx Rm FPC 5 2072 P-9,1B FPC Pump RB 2303' FP Hx Rm FPC 5 2073 E-9.1A FPC Heat Exchanger REB 303' FP Ax Rm FPC 21 2074 E-9-188 PC Heat Exchanger RB 2 30' PP Hx Rm FPC 21 2075 FC.104-80B Flow Transmitter (RK-10A__

_ RB 303' SW 18 2076) PI-104-180B Flow Indicator (CAD PNL A) SW to SFPC Hx CRB 272' Control Room SW is 5077 ES-104-808 Power Supply (CAD PNL A1 SW toSFPC Hx CRB 272' Central Room SW 20 2078 FI-104-80A Flow Indicator (CAD PNL B) SW to SFPC Hx CRB 272' Control Room SW 18 2079 ES.104-80A Power Supply (CAD PNL 8)} SW to SFPC Hx CRB) 272' Control Room SW20 i080 P1-104-93A Pressure indicator (RK-10AA1 RB 1303' 5W 18 2081 FT-104-80A Flow Transmitter (RK-10AA)

RB 303' SW 18 2082 Pi-10,-939 Pressure Indic.ator (RK-10AB)

RE; 303' SW is 2083 MVCC.6A MCC RB 280' 480A -1 2{084 MCC-6c M cc RWEt 252' Control Room 48)0A 1 F085- -MCC-6D MCC RWB 2S2' Control Room 480A 1 2086 MICC-TA M4CC REB 28e)0 480A1 2087 MCC-E) B MCC RB 28)0r 480OAMACC-9B MCC RB 28(Y' 48)0A I 2089 M4CC-SE MCC !RB 2S' DA i X x is SWEL Item Table 9.4.4- Rapid Drain-Down Altoohmvern B Engneering Report No. VTY-RPT-12-00019 Rev. I Page 23 of 249,4,4- Rapid Drain-Down RDD# DESCRIPTION BASIS FOR INCLUSIONIEXCLUSION RDD No Rapid Drain-Down items were identified durng the development of the SWEL 2.

Table 9.4.5- SWEL 2 Engneering Report No. VTY-RPT-12.00019 Rev. 1 Page 24 of 24 Aflachmenl B SWEL 2# EQUIPMENT ID DESCRIPTION BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT N/R RDD SWEL2-001 RK.10AA Rack RB 303' 4 18 SWEL2-002 dPT,19-76A Differential Pressure Transmitter (RK-10AAI RB 303' 4 18 SWEL2-003 PT-19-B1A Pressure Transmitter (RK-10AA)

RB 303' 4 18 SWEL2-004 PS-19-80A Pressure Switch (RK-10AA)

RB 303' 4 18 SWEL2-005 PI,19.84A Pressure Indicator (RKlt0AA)

RB 303' 4 18 SWEL2-006 P1I19-73 Flow indicator RB 303' FP Hx Room 4 0 SWEL2-007 V70-257B IW MOV SFPC Hx outlet RB 303' FP Hx Rm B 4 8A SWEL2-008 P-*9.2A SFPC Pump RB 303' PHx Rm A 4 5 SWEL2-009 E-19-2A SPPC Heat Eohanger PB 303' PP HO RO A 4 21 SWEL2-010 CAD Panel B lPanel CRB 272' Control Room B 4 20 SWEL2-011 IFTrO.04.80A Plow Transmitter (RK-10AA)

RB 303' 4 18 System 1 Reactivity Control 2 Pressure Control 3 Inventory Control 4 Decay Heat Removal 5 Containment Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 1 of 505 Attachment C Attachment C Seismic Walkdown Checklists (SWCs)

Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 2 of 505 Attachment C SWEL1# EQUIPMENT ID DESCRIPTION PAGE SWELl-001 CRD/HYDRAULIC CONTROL UNITS (89) 5 SWELI-002 LCV-3-33C CRD/SCRAM DISCHARGE VOLUME DRAIN VALVE 10 SWELl-003 PCV-3-32B CRD/SCRAM DISCHARGE VOLUME VENT VALVES 15 SWELl-004 CV-3-126-CRD/SCRAM VALVES (89) INLET 20 SWELI-005 P-46-IA CS/"A" CORE SPRAY PUMP 25 SWELl-006 C-3-1A DG START AIR/COMPRESSOR A 30 SWELI-007 DG-1B DIESEL GENERATOR B 35 SWELI-008 LCV-108-2A FUEL OIL/DAY TANK FILL 40 SWELI-009 TK-42-1B FUEL OIL/DIESEL OIL DAY TANK B 45 SWELl-010 TK-40-IA 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 SWELI-013 BC-i-IA 125V DC MAIN STATION BATTERY CHARGER A ON DC-1 65 SWELI-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 SWELl-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 (S11) 110 SWELl-023 BUS-9 480V AC SWITCHGEAR BUS NO.9 1600AMP (SII) 115 SWELl-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 SWELl-027 P-44-1A HPCI/HPCI PUMP 135 SWELl-028 PS-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 SWELl-033 PT-2-3-52C CS, RHR PERMISSIVE 155 SWELl-034 LT-I07-5A CST/LEVEL TRANSMITTER 160 SWELl-035 LT-107-5B CST/LEVEL TRANSMITTER 165 SWELl-036 PT-iO-IOIA DW PRESSURE ECCS 170 SWELl-037 PT-10-101C DW PRESSURE ECCS 175 SWELl-038 PT-16-19-29A DW PRESSURE INDICATION 180 SWELI-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-S6A RV PRESSURE ECCS 215 SWELl-047 PT-2-3-56C RV PRESSURE ECCS 220 SWEL1-048 PT-2-3-55C RV PRESSURE SCRAM 225 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 3 of 505 Attachment C 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-OS1 PS-104-53A SW/PUMP A PRESSURE SWITCH 240 SWELl-056 TK-55-1A N2 AIR RECIEVER 245 SWELl-058 P-1O-1D 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 SWELl-062 V10-89A 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 LCV-108-3 FUEL OIL TANK VALVE 285 SWELl-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 SWELl-078 VG-22A CAD MOV VENT ISOLATION (OUTBD) 325 SWELl-079 NG-13A CAD SOV AIR ISOLATION (INBD) INJECTION TO DW PNL A 330 SWELl-080 SB-16-19-6 PRIMARY CONTAINMENT VENT TO SBGT ISOLATION 335 (OUTBD) AOV SWELl-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 SWELl-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 SWELI-087 RATS-lA DG-1A RM THERMOSTAT 370 SWELl-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 SWELl-093 ES-1-156-5 POWER SUPPLY FOR LSL-107-5B 400 SWELl-094 RK25-SOA HPCI INST. RACK (A) 405 SWELl-095 RK2S-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-100 RK-25-66 CST INST. RACK 435 SWELI-101 ES-24DC-2 POWER SUPPLY FOR ECCS PANEL B 440 SWELl-102 CYL-71-1A NITROGEN BOTTLE FOR BACKUP SRV SUPPLY 445 I Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 4 of 505 Attachment C SWEL1# EQUIPMENT ID DESCRIPTION PAGE SWEL2-001 RK-10AA Rack 450 SWEL2-002 dPT-19-76A Differential Pressure Transmitter (RK-1OAA) 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-1O4-80A Flow Transmitter (RK-1OAA) 500 Items Differed to RFO 30 (March 2013) 505 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 5 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y0 NEI U[]Seismic WalkdowrChecklist (SWC) SWELl- 001 Equipment ID No. Equip. Class 1 0 Equipment Description CRD/HYDRAULIC CONTROL UNITS (89)Location:

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

YD NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?YZ N--] U[] N/A["I YZ N[- UI" N/A-'YZ Ni] Ut] N/Ar]zo- bcs7jo: I- -C-6 I P"-eý~SkAy~t fe-25-I' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 6 of 505 Attachment C ATTACHMeNT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YV NEI UL Seismic Walkdown Checklist (SWC) SWEL1- 001 Equipment ID No. Equip. Class 1 0 1 a --b 3r-Equipment Description CRD/IYDRAUrIC CONTROL UNITS (89)5. Is the anchorage configuration consistent with plant documentation?

YEI NEI] UI N/A0 (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 YS N] UF"I potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?Y" N-3 U0 N/AD YZ NE] U[-] N/AD YZ NIl Ur- N/AD 10. Based on the above seismic interaction evaluations, Is equipment free YZ ND UD of potentially adverse seismic interaction effects?EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 7 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y0 N-' Ur" Seismic Walkdown Checklist SWELl- 001 Equipment ID No/-Fý ý 17 Equip. Class 0 Equipment Description CRD/HYDRAULIC CONTROL UNITS (89)Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Yj@ N['] 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.Reference Documents:

A46/IPEEE

-SSEL Line No. 000002 Evaluated by; Kifit Parikh Date: 10/16/2012

-w -Rad Stephens R "J~~ 101~&~~.IL]t&

b4-Z-10/16/2012 EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 8 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YED NFL UI-Seismic Walkdow? Checklist (SWC) SWELl- 001 Equipment ID No. rzanwWW A Equip. Class' 0 Equipment Description CRDAHYDRAULIC CONTROL UNITS (89)Photographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 9 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YN NOJ U-Seismic Walkdown Checklist (SWC SWELl- C Equipment ID No. Equip. Class'Equipment Description CRDI-IYDRAULIC CONTROL UP EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 10 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORM Sheet I of 5 Status: YZ NEL UO'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.Anchoraoe 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

YrI NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?YEI] NEI] UI N/A0 YE] NEJ u-- N/AZ YE] N[-E U- NWAS I Enter the equipment class name from EPRi 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 11 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ N[-I U-I Seismic Walkdown Checklist (SWC) SWELl- 002 Equipment ID No. LCV-3-33C Equip. Class 1 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME DRAIN VALVE 5. Is the anchorage configuration consistent with plant documentation?

Y-I NI UE] N/AS (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 NI] U[-]potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 NO- Ur-] N/Ar-YN N[] u-] N/A[" YZ Nr"] UL[ N/AQ-YO NEI url EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 12 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YO NEI U1" Seismic Walkdown Checklist (SWC) SWELl- 002 Equipment ID No. LCV-3-33C Equip. Class 1 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 YO NI] U[]adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Marcus Hecht.NielserL Date: 10-04-2012 Ra.mond Twork I 10-04-2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 13 of 505 Attachment C ATTACHMENT 9.6 SEISMic WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0 NEI U[I Seismic Walkdown Checklist (SWC) SWELl- 002 Equipment ID No. LCV-3-33C Equip. Class 1 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME DRAIN VALVE Photographs NO PHOTO Note: Note: LCV-3-33C EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 14 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: NU- Ui--Seismic Walkdown Checklist (SWC) SWELl- 002 Equipment ID No. LCV-3-33C

.Equip. Class 1 07 Equipment Description CRDISCRAM DISCHARGE VOLUME DRAIN VALVE NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 15 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YZ NI] U[]Seismic Walkdown Checklist (SWC) SWELl- 003 Equipment ID No. PCV-3-32B Equip. Class 1 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VALVES Location:

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

YD NO 2. Is the anchorage free of bent, broken, missing or loose hardware?In-line valve, no anchorage.

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?YEI NEI UE- N/AS Y-I N"] U[-] N/AN Y[N U NEI UEIN/AS'Enter the equipment class name from EPRI 1025286. Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 16 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKIUST FORM Sheet 2 of 5 Status: YZ NEI UO-Seismic Walkdown Checklist (SWC) SWELl- 003 Equipment ID No. PCV-3-32B Equip. Class' 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VALVES 5. Is the anchorage configuration consistent with plant documentation?

YO! NrO Ur- 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 YED NO- UE-potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 NEI uE-! N/AF-YN NE! uE- N/AE YZ NEI U[-l N/A--YZ NEI U--EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 17 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 3 of 5 Status: YE0 NEI Ur 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[O 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 bv: Kirit Parikh..........

j Randy Steghens ~Q-b ~1 LC i~2 L Date: 10/04/2012 10/04/2012 EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 18 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 4 of 5 Status: YZ NM] Ur Seismic Walkdown Checklist (SWC) SWELl- 003 Equipment ID No. PCV-3-32B Equip. Class 1 07 Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VALVES Photographs Note: Looking up at valve '#EN-DC-168 REV 0 Engineering Report No. VJTY-RPT-1 2-00019 Rev. 1 Page 19 of 505 Attachment C ATTACHMENT 9.6 Sheet 5 of 5 SEISMIC WALKDOWN CHECKLIST FORM Seismic Walkdown Checklist (SWC) SWELl- 003 Equipment ID No. PCV-3-32B Equip. Class' 07 Equipment Description CRDISCRAM DISCHARGE VOLUME VENT VALVES Status: Yv NEI Uf-EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 20 of 505 Attachment C ATTACHMEI Sheet 1 of 5T 9.6 SEISMIC WALKDOWN CHECKLIST FORM 5 Status: YZ N[O] U-]Seismic Walkdown Checklist (SWC) SWELl- 004 Equipment ID No. CV-3-126-Equip. Class 1 07 Equipment Description CRD/SCRAM VALVES (89) INLET Location:

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

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?Y[D ND] ur: N/Ar']Y[0 NE] U[D N/A[]Y0 N[3 U[] N/A[']' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 21 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORM Sheet 2 of 5 Status: YZ NO3 Ul]Seismic Walkdown Checklist (SWC) SWELl- 004 Equipment ID No. CV-3-126-Equip. Class 1 07 Equipment Description CRD/SCRAM VALVES (89) INLET 5. Is the anchorage configuration consistent with plant documentation?

YE[I NEI U[] 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 YZ N[] UE]potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic Interaction effects?Y0 NIl Ur- N/A-]YED NE] U]- N/A--YZ NI] Ur] N/A-]YZ NEI U-'EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 22 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y[0 NiL ur-J 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 YZ NI[] 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-3-126-10-27associated with HCU 10-27(north bank) at the bonnet and yoke interface (see photos page 5). This surface corrosion does not pose an adverse seismic condition.

See CR- VTY-2012-05099.

Reference Documents:

A46/IPEEE

-SSEL Line No. 000011 k2V V-C, jolISIZ019-EJZAý-Evaluated by: Ktrit Parlkh Date: 10/16/2012 Ranc* &M&Les P' ILZO-~10/16/2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 23 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NEI UC-1 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 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 24 of 505 Attachment C ATTACHmENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Shoot 5 of 5 Status: Yv NC] uM Seismic Walkdown Checklist (SWC) SWEL1- C Equipment ID No. CV-3-126-Equip. Class 1 Equipment Description CRD/SCRAM VAL VES (89) INLE T showing surface corrosion.

companson.

EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 25 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y0 ND ULI Seismic Walkdown Checklist (SWC) SWELl- 005 Equipment ID No. P-46-1A Equip. Class' 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.AnchoraAe 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

Y9 NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Y0 ND UD N/AD YZ N- UI-- N/A-Y[D ND UD N/AD"]' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 26 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRM Sheet 2 of 5 Status: YO NO UO-]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?

YO NEI U[O N/AO (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 YZ NEI U-]potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Yv NEI ur- N/Ar-NOI UO N/A[Yv NrJ U[-] N/A[-]YO NOI UE-EN-DC-168 REV 0 Attachment C Engineerinf ATTAcHMENT 9.6 Si Sheet 3 of 5 Seismic Walkdown Checklist (SWC) SWELl- 005 Equipment ID No. P4-6-1A Equip. Class 1 06 Equipment Description CSI"A" CORE SPRAY PUMP Other Adverse Conditions

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

Report No. VTY-RPT-12-00019 Rev. 1 Page 27 of 505 EISMIC WALKDOWN CHEcKusT FORM Status: Y0 NO UOI Y0 NEI U(: 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/IPEEE

-SSEL Line No. 000015 Evaluated by: Kirit Parikh r _ 1 i 11t g" I ZO I_. Date: 10/17/2012 Randy SteDhens IQI% ¶C- 4( ('Jl 10/117/2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 28 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y10 NO U-" Seismic Walkdown Checklist (SWC) SWELl- 005 Equipment ID No. P-46-1A Equip. Class 1 06 Equipment Description CS/"A" CORE SPRAY PUMP Photographs

-1 NO PHOTO Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 29 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: N1J UE'-Seismic Walkdown Checklist (SWC) SWELl- 005 Equipment ID No. P-46-1A Equip. Class 1 06 Equipment Description CSP"A" CORE SPRAY PUMP NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 V Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 30 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YZ NEI UE-Seismic Walkdown Checklist (SWC) SWELl- 006 Equipment ID No. C-3-1A Equip. Class' 12- AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR A Location:

Bldg. TS Floor El. 252 Room, Area EDGR A 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 of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?Y19 NE] Ur' N/A[-YN NI-] U-] N/A[]Y0@ N["] U"] N/AEl' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 31 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Yo NE] 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?

YZ NE] U] ] N/A[](Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See A46/PEEE -SSEL Line No. 000033 6. Based on the above anchorage evaluations, is the anchorage free of YZI NEI U-]potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?There is a rigid connection but seismically they will move together and are acceptable based on engineering judgment.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 NEI ur] N/A[]YZ NE] UI] N/Al]YZ NE] UI- N/Al]YV NEI UE]EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 32 of 505 Attachment C ATTACHMEN Sheet 3 of T 9.6 SEISMIC WALKDOWN CHECKUST FORM 5 Status: YZ NEL UL-Seismic Walkdown Checklist (SWC) SWELl- 006 Equipment ID No. C-3-1A Equip. Class 1 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 adversely affect the safety functions of the equipment?

YO NO UU Comments (Additional pages may be added as necessary)

Reference Documents:

A464PEEE -SSEL Line No. 000033 Evaluated by: Marcus Hecht-Nielsen S Date: 10-01-2012 Raymond Tworek C j12=e~ to/ I!-10-01-2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 33 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRM Sheet 4 of 5 Status: YA NI] Ul]Seismic Walkdown Checklist (SWC) SWELl- 006 Equipment ID No. C-3-1A Equip. Class' 12- AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR A Photographs I I EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 34 of 505 Attachment C ATTACHMENT 9.6 SEISMC WALKOOWN CHECKuST FORM Sheet 5 of 5 Status: Y0 NI] UE-Seismic Walkdown Checklist (SWC) SWELl- 006 Equipment ID No. C-3-1A Equip. Class 1 12 -AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR A NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 35 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: Y0 NEI UM-Seismic Walkdown C-ecklist (SWC) SWELl- 007 Equipment ID No. ea u~ qp.Ia")I2ssý 17 Equipment Description DIESEL GENERA OR B' ° " " Location:

Bldg. TB Floor El. 252' Room, Area EDOGR 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.Anchoraqe 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?Steel structure, no concrete.# C72-2.ee~)

1PV F lb YZ NEI U[] NIAQ: YZ NEj UEJ N/AEJ YQ: NEfl U1 WlAS ICA Il' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 36 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NI: UL]Seismic Walkdown Checklist (S ) SWEL- 007 b ~~-t -I 1 -Jt, 171,'Equipment ID No. 0 A/ Equip. Class' 17 Equipment Description DIESEL GENERATOR B 5. Is the anchorage configuration consistent with plant documentation?

Y0 NEI Ur- N/ArO](Note: This question only applies If the Item is one of the 50% for which anchorage configuration verification is required.)

The diesel generator comes attached to the skid. The skid is properly attached to the foundation (see Swel 1-091 and VYEM-olo7) and the generator is attached to the skid with 8-1 W" diameter bolts. Thus, the generator falls under the rule of the box. Seismically acceptable by engineering Judgment.6. Based on the above anchorage evaluations, is the anchorage free of YZI N[3 U[-potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NOt UOl N/AO YZ NOI ur'] N/A[--Y0 NOi Ur] N/ADl YZ N[l U--EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 37 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ NEI U[:-Seismic Walkdown Checklist (S C SW ELi- 007 Equipment ID No. Equip. Class' 17 Equipment Description DIESEL G-ENERATOR/B 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?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawing 5920-399 1, G- 191566, and VYEM-0 107 A46/IPEEE

-Screening Evaluation Work Sheet, SSEL Line No. 000044 Evaluated by: Marcus e Date: 10-03-2012 Raymond Tworak 10-O032012 Ramond Tworek f EN-DC-168 REV 0 Engineering Report No. VTY-RPT-1 2-00019 Rev. 1 Page 38 of 505 Attachment C ATTACHMENT 9.6 SESMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0 NL] Ur]Seismic Walkdown Checklist (SWC) SWEL1- 007 Equipment ID No. Z p / Equip. Class' 17 Equipment Description DIESEL GENERATOR B Photographs EN-DC-168 REV 0 Attachment C ATTACHMENT 9.6 Sheet 5 of 5 Seismic Walkdown 1 Equipment ID No.Equipment Description Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 39 of 505 SEsmmc WALKDOWN CHECKLIST FORM Status: YN NEI U" EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 40 of 505 Attachment C ATrACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YN NO U-Seismic Walkdown Checklist (SWC) SWELl- 008 Equipment ID No. LCV-108-2A Equip. Class 1 07- FLUID OPERATED VALVES Equipment Description FUEL OIUDAY TANK FILLVALVE Location:

Bldg. TB Floor El. 252' Room, Area DAYTKRMA Manufacturer, Model, Etc. (optional but recommended)

ACF #70-14-Z-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 item one of the 50% of SWEL items requiring such verification)?

YlI NO 2. Is the anchorage free of bent, broken, missing or loose hardware?In-line valve, no anchorage.

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?YEI NEI UEr N/AO YE- N[3 U' N/AS YE" NEI UCI N/AO' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 41 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y[ NEI U--Seismic Walkdown Checklist (SWC) SWELl- 008 Equipment ID No. LCV-1O8-2A Equip. Class' 07- FLUID OPERATED VALVES Equipment Description FUEL OIL/DAY TANK FILLVALVE 5. Is the anchorage configuration consistent with plant documentation?

YEI NE uI I 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 Y[0 NE] u[]potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?No attached lines exist.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 NE] ul] N/AE]YO NEI UE] N/A[]YE] NE] uE] N/AZ YONE] uD EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Attachment C Page 42 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 3 of 5 Status: YZ NE] U-'Seismic Walkdown Checklist (SWC) SWELl- 008 Equipment ID No. LCV-108-2A Equip. Class 1 07- FLUID OPERATED VALVES Equipment Description FUEL OIL/DAY TANK FILLVALVE Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YO NEI uQ-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: KiritParlkh t -P-...- Io Ig2z0l 2- Date: 10/02/2012 Randy Stephenls L Z- 10/0212012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 43 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 4 of 5 Status: Y0 Nn] U-]Seismic Walkdown Checklist (SWC) SWELl- 008 Equipment ID No. LCV-108-2A Equip. Class 1 07- FLUID OPERATED VALVES Equipment Description FUEL OIL/DAY TANK FILL VALVE Photographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 44 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NO- UJ-Seismic Walkdown Checklist (SWC) SWELl- 008 Equipment ID No. LCV-I08-2A Equip. Class 1 07- FLUID OPERATED VALVES Eauioment DescnDtlon FUEL OIL/DAY TANK FILLVALVE NO PHOTO Note: EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 45 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YV NEI U[]Seismic Walkdown Checklist (SWC) SWELl- 009 Equipment ID No. TK-42-IB Equip. Class' 21- TANKS & HEAT EXCHANGERS Equipment Description FUEL OILUDIESEL OIL DAY TANK B Location:

Bldg. TB Floor El. = 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 of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?Two grout pads on the east side of the tank are slightly damaged, but do not effect seismic performance or reliability.

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

YO NE] UE] N/AE-Y0 N[3 Ur- N/A"]YZ NEI ur- N/AE]EN-DC-168 REV 0

'i AV, Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 46 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI UrI 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?

YO NEI] Ur N/AI (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

See A464IPEEE

-SSEL Line No. 000052 6. Based on the above anchorage evaluations, is the anchorage free of Y0 Ni] U[].potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NI] UI] N/AI]YN NII UI] N/AE]Y[ NI] U[I] N/AI]Y NiEUI'-]EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 47 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y[ NI] U[-Seismic Walkdown Checklist (SWC) SWELl- 009 Equipment ID No. TK-42-1B Equip. Class 1 21- TANKS & HEAT EXCHANGERS Equipment Description FUEL OIlUDIESEL OIL DAY TANK B Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 NEI 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 10-03-2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 48 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 4 of 5 Status: Y0 NI UMI Seismic Walkdown Checklist (SWC) SWELl- 009 Equipment ID No. TK-42-IB Equip. Class 1 21- TANKS & HEAT EXCHANGERS Equipment Description FUEL OIUDIESEL OIL DAY TANK B Photographs NO PHOTO Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 49 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y; NE] U]'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 NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 50 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YZ NEI UJ-Seismic Walkdown Checklist (SWC) SWELl- 010 Equipment ID No. TK-40-lA 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 of the 50% of SWEL items requiring such verification)?

YO NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?A small hairline crack is seen near North-East bolt, seismically insignificant by engineering judgment since only small area has this crack. A# other areas are without any cracks.Y ] NEI ur- N/A"]YC9 NE] U["] N/A[D YZ NEI Ul] N/A[' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 51 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 2 of 5 Status: YZ No Ur]Seismic Walkdown Checklist (SWC) SWELl- 010 Equipment ID No. TK-40-1A Equip. Class' 21 Equipment Description FUEL OIL/FUEL OIL STORAGE TANK (FOST)5. Is the anchorage configuration consistent with plant documentation?

YZ N] U[] N/A[](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 YO( No uO potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?No flexible items connected 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO NO ul] N/Al]Yv NM] U[] N/Al-]Y[] NE] ul] N/AZ YO NEI U EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 52 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y0 NEI U[" Seismic Walkdown Checklist (SWC) SWELl- 010 Equipment ID No. TK-40-1A Equip. Class 1 21 Equipment Description FUEL OIL/FUEL OIL STORAGE TANK (FOST)Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YO NE] U[]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/IPEEE

-Screening Evaluation Work Sheet, SSEL Line No. 00053 Evaluated by: Kirit Parikh 10 1 l&Il 2 12-Date: 10/03/12 RandyStehens 1, 4 KfqJZa i 4L 10/03/12 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 53 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YS NEI U-l Seismic Walkdown Checklist (SWC) SWELl- 010 Equipment ID No. TK-40-1A Equip. Class 1 21 Equipment Description FUEL OILIFUEL OIL STORAGE TANK (FOST)Photographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 54 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YV NO U[-Seismic Walkdown Checklist (SWC) SWELl- 010 Equipment ID No. TK-40-IA Equip. Class' 2 1 Equipment Description FUEL OIL/FUEL OIL STORAGE TANK (FOST)EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 55 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet I of 5 Status: YO NEI uE'Seismic Walkdown Checklist (SWC) SWELl- 011 Equipment ID No. P-92-1A Equip. Class' 05 Equipment Description FUEL ILUFUEL OIL TRANSFER PUMP A 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 of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?YZ NEI UD] N/A[-]YZ NEI UD" N/AD]Y0 NEI ur] N/Ar-I Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 56 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FoRM Sheet 2 of 5 Status: YN NO] UO Seismic Walkdown Checklist (SWC) SWELl- 011 Equipment ID No. P-92-1A Equip. Class 1 05 Equipment Description FUEL QIUFUEL OIL TRANSFER PUMP A 5. Is the anchorage configuration consistent with plant documentation?

YJ9 NE] ur' N/A[](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 associated anchorage calculation.

6. Based on the above anchorage evaluations, is the anchorage free of YV NE] U[]potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y; NE] U'- NIArI YN NE] uE] N/AEr YZ NE] UE N/A[-]YU NO] U-]EN-DC-1 68 REV 0 Attachment C Engineerin~

ATTACHMENT 9.6 Si Sheet 3 of 5 Seismic Walkdown Checklist (SWC) SWELl- 011 Equipment ID No. P-92-IA Equip. Class 1 05 Equipment Description FUEL OIL/FUEL OIL TRANSFER PUMP A Other Adverse Conditions

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

g Report No. VTY-RPT-12-00019 Rev. 1 Page 57 of 505 EISMIC WALKDOWN CHECKLIST FORM Status: Y[ NEI] Ur]YO NEI UE Comments (Additional pages may be added as necessary)

Referenced Documents:

A46/IPEEE

-Screening Evaluation Work Sheet, SSEL Line No. 00054 Evaluated by: Kirit Parikh ED.I= L. (o'(6Ito12.

Date: 10/03/2012 Randy Stewhens S'O)A _J L l4 J -I I Ii- 10/03/2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 58 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORM Shoot 4 of 5 Status: YN NI: UE-Seismic Walkdown Checklist (SWC) SWELl- 011 Equipment ID No. P-92-IA Equip. Class' 05 Equipment Description FUEL OILIFUEL OIL TRANSFER PUMP A Photographs NO PHOTO Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 59 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 5 of 5 Status: Y@ NE] UL-'Seismic Walkdown Checklist (SWC) SWELl- 011 Equipment ID No. P-92-1A Equip. Class' 05 Equipment Description FUEL OILUFUEL OIL TRANSFER PUMP A NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 60 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y0 NEI U[-Seismic Walkdown Checklist (SWC) SWELl- 012 Equipment ID No. MG-2-1A Equip. Class' 13 Equipment Description 120/240V VITAL AC MG SET Location:

Bldg. H .B 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.Anchoraae 1. Is the anchorage configuration verification required (i.e., is the item one YCD N-]of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?YN N["] UE] N/A[Y0 NEI U-' N/Ar" Y0 NEI U[- N/AD' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 r.Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 61 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NI] UL-Seismic Walkdown Checklist (SWC) SWELl- 012 Equipment ID No. MG-2-1A Equip. Class' 13 Equipment Description 1201240V VITAL AC MG SET 5. Is the anchorage configuration consistent with plant documentation?

YO NEI uDl N/All (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 YER NC] Ur-potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO N[:] urD N/AED YO NI] Ur- N/AD" YN NI] uD] N/AD Y19 NI] U!]EN-DC-168 REV 0 01 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 62 of 505 Attachment C ATTACHMENT 9.6 Sheet 3 of 5 SEISMIC WALKDOWN CHECKUST FORM Status: Y] NEI U0-Seismic Walkdown Checklist (SWC) SWELl- 012 Equipment ID No. MG-2-1A Equip. Class 1 13 Equipment Description 120/240V VITAL AC MG SET Other Adverse Conditions

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

Y NO U--Comments (Additional pages may be added as necessary)

Reference Documents:

Drawing 5920-4463, Sheet 1, Rev.0 and 5920-12739 A46/IPEEE

-Screening Evaluation Work Sheet, SSEL Line No. 000060 Evaluated by: Marcus Date: 10-09-2012 Ravmond Tworek to/I 6 1 L2-10-09-2012 EN-DC-168 REV 0 l Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 63 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ( NEI UM Seismic Walkdown Checklist (SWC) SWELl- 012 Equipment ID No. MG-2-1A Equip. Class 1 13 Equipment Description 120/240V VITAL AC MG SET Photographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 64 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NEI ur-Seismic Walkdown Checklist (SWC) SWELl- 012 Equipment ID No. MG 1A Equip. Class 1 13 Equipment Description 120/240V VITAL AC MG SET NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 65 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YE] NEI U--Seismic Walkdown Checklist (SWC) SWELl- 013 Equipment ID No. BC-1-1A Equip. Class 1 16 Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-1 Location:

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

YO NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Yv NO Ur N/AQ YO N[ UE- N/A-Y"0 NEI U[] N/A[-IEnter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 66 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 2 of 5 Status: YN NEI UE]Seismic Walkdown Checklist (SWC) SWELl- 013 Equipment ID No. BC-1-IA Equip. Class 1 16 Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-1 5. Is the anchorage configuration consistent with plant documentation?

Y0 ND- UD] N/AD (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 YO NDI U-]potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic Interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO ND] U["D N/AD Y0 NDI U- N/AD" Y0 NDI UD N/AD--YZ NEI UD EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 67 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 3 of 5 Status: Yv NEI UMI Seismic Walkdown Checklist (SWC) SWELl- 013 Equipment ID No. BC-1-1A Equip. Class' 16 Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-1 Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Reference Documents:

Drawing 5920-10849, Sheet 1, Rev. 1 A46/IPEEE

-Screening Evaluation Work Sheet, SSEL Line No. 000061 Evaluated by: Marcus Hecht-Nielsen a:ý,ý/.Raymond Tworek -_ o !I i/I Date: 10-09-2012 10-09-2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 68 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ N[3 UO]Seismic Walkdown Checklist (SWC) SWELl- 013 Equipment ID No. BC-1-1A Equip. Class 1 16 Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-1 Photographs Note: B NO PHOTO Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 69 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 5 of 5 Status: Nil UiL Seismic Walkdown Checklist (SWC) SWELl- 013 Equipment ID No. BC-i-1A Equip. Class' 16 Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-1 NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 I.Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 70 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: Y0 NEI UM Seismic Walkdown Checklist (SWC) SWELl- 014 Equipment ID No. B-AS-2 Equip. Class 1 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.Anchora-qe

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

YZ NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Y[@ NO] U' N/AD Y0 NE] UD N/Ar Y0 NEI u["] N/A[]' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 71 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 NED U--Seismic Walkdown Checklist (SWC) SWELl- 014 Equipment ID No. B-AS-2 Equip. Class 1 15 -BATTERIES ON RACKS Equipment Description 125V DC STATION BATTERY ON BUS DC-2AS 5. Is the anchorage configuration consistent with plant documentation?

YZ NEI UO- N/A['](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 YO NOI UO-potentially adverse seismic conditions?

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

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

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?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NOI Ur NIAO YZ NEI UO- N/Ar" YZ NOI UO N/A[-Y[ NO U-]EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 72 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 3 of 5 Status: YO N[] Ur-Seismic Walkdown Checklist (SWC) SWELl- 014 Equipment ID No. B-AS-2 Equip. Class 1 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 YZ 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. 000065 See SSEL# 000328, TK-67-1A, and EDCR 82-12 Drawings G-191572 & 5920-11085 Evaluated by: Marcus Hecht-Nielsen RavmondTworek ( ,. -A J , , L '-Date: 10-01-2012 10-01-2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 73 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0 N-] UC1 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 vwww,-.7 P 46"W90-. O-Ao" VW&b'l EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Attachment C Page 74 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORM Sheet 5 of 5 Status: YO NE] Ur" Seismic Walkdown Checklist (SWC) SWELl- 014 Equipment ID No. B-AS-2 Equip. Class 1 15- BATTERIES ON RACKS Equipment Description 125VDC STATION BATTERY ON BUS DC-2AS NO PHOTO Note: EN-DC-168 REV 0 U.Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 75 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet I of 5 Status: YZ NE] U--Seismic Walkdown Checklist (SWC) SWELl- 015 Equipment ID No. B-1-1B Equip. Class 1 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.Anchoraae 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks In the concrete near the anchors?YZ NOI UQ- N/AE'Y[O NO-] UEO N/AO-YO N[: U'- N/A[I Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 I/Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 76 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YO Nr3 UE-Seismic Walkdown Checklist (SWC) SWELl- 015 Equipment ID No. B-1-1B Equip. Class 1 15 Equipment Description 125V DC STATION BATTERY ON DC-2 5. Is the anchorage configuration consistent with plant documentation?

YN NO] U[ N/AE (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- 1-1B 6. Based on the above anchorage evaluations, is the anchorage free of Yo NO UO potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 NO U[-] N/A-YN NEI ur- N/A[J YZ N] U-] N/Ar]Yv NO u[]EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 77 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ N] UL-]Seismic Walkdown Checklist (SWC) SWELl- 015 Equipment ID No. B-1-1B Equip. Class 1 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 YZ N["] Ur-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Reference Documents:

Drawing 5920-4411, C&D BATTERIES, Sheet 1 Drawing 5920-11884, Duke Engineering

& Services, Sheets 1-4 Drawings B- I-1A and B- I- 1B A46/IPEEE

-Screening Evaluation Work Sheet, SSEL Line No. 000067 Evaluated by: Marcus

' Date: 10-09-2012 Ra-mond Tworek LOW'-.i 10-09-2012 EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 78 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0 NO' UL-Seismic Walkdown Checklist (SWC) SWELl- 015 Equipment ID No. B-I-1B Equip. Class 1 15 Equipment Description 125V DC STATION BATTERY ON DC-2 Photographs Note: B-1-1E EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 83 of 505 Attachment C ATTACHMENT 9.6 Sheet 4 of 5 SEISMIC WALKDOWN CHEcKusT FORM Status: YNI NEI Ur-L Seismic Walkdown Checklist (SWC) SWELl- 016 Equipment ID No. DC-I Equip. Class' 14 Equipment Description 125VDC DISTR PNL DC-1 1600AMP Photoaraphs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 84 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 5 of 5 Status: YN NEI UEJ Seismic Walkdown Checklist (SWC) SWELl- (Equipment ID No. DC-1 Equip. Class 1 Equipment Description 125VDC DISTR PNL DC-1 1600 NO PHOTO Note: Note: 125VDC Distr. PnL DC-1 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 89 of 505 Attachment C ASTAcHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ NEL U[I Seismic Walkdown Checklist (SWC) SWELl- (Equipment ID No. DC-2 Equip. Class', Equipment Description 125V DC DISTR PNL DC-2 1600 EN.DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 90 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y0 NEl UE1 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)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 Y[@ NEI of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?Y0 NE] UDI N/AD]YZ NEI] U- N/AE]YZ NEI U[3 N/AQ I Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 91 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI UO 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)5. Is the anchorage configuration consistent with plant documentation?

Y0 NO UO-] N/AO (Note: This question only applies If the Item is one of the 50% for which anchorage configuration verification is required.)

See SSEL Line No. 0008 1(attachment A).6. Based on the above anchorage evaluations, Is the anchorage free of Yo NO U1-potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO NOI UO N/AO Y0 NOI UEr N/AO Y0 NO ur N/AO YS NEI UO EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 92 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORM Sheet 3 of 5 Status: Y N N l U[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 YNI NE] UE]adversely affect the safety functions of the equipment?

I -3/8" nut (right upper in cabinet-see attached photo) 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-VVTY-2012-05021

/ 05007 generated to fix the engagement.

Comments (Additional pages may be added as necessary)

Note: Original inspection 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. 00008 1 (attachment A)kle'D I 11ý 10 Evaluated bv: Kirit Parikh Date: 10/11/2012 Randy SteDhens I c31~~/2brL 10/11/2012 I V EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 93 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Yv NE] U[3 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)Photographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 94 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 5 of 5 Status: YZ NO Ur-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)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 0 f Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 95 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y[0 N[] UM Seismic Walkdown Checklist (SWC) SWELl- 019 Equipment ID No. MCC-9C Equip. Class' 01 -Motor Control Centers Equipment Description 480V ESS AC MCC-9C -DIESEL 1A ROOM (SI)Location:

Bldg. TB Floor El. 252 Room, Area EDG A Manufacturer, Model, Etc. (optional but recommended)

Westinohouse.

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

Y[ NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?On October 11, 2012 revisited the unit and removed upper and lower panels. With upper panel removed was able to verify attachment of angle to unit.3. Is the anchorage free of corrosion that is more than mild surface oxidation?

On October 11, 2012 revisited the unit and removed upper and lower panels. With upper panel removed was able to verify attachment of angle to unit.4. Is the anchorage free of visible cracks in the concrete near the anchors?Crack on eastside of the floor. The crack goes thru the grout pad and the comer of house pad (SE Comer). By engineering judgment 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, Appendix B: Classes oa Equipment.

Y0 N-I uE- N/A[]Y[ NF- U"-O N/A[-'I YO N[O U[3 N/AO EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 96 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 2 of 5 Status: YN NEI U--Seismic Walkdown Checklist (SWC) SWELl- 019 Equipment ID No. MCC-9C Equip. Class 1 01 -Motor Control Centers Equipment Description 480V ESS AC MCC-9C -DIESEL 1A ROOM (SII)5. Is the anchorage configuration consistent with plant documentation?

YN NEI Ur] N/A[](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 Yo NOI U[3 potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NOI U0 N/A[]YZ NO- UL N/AC YZ NEI UC- N/AC1 YZ NEI Iu-I EN-DC-168 REV 0 Engineering Report No. VTY-RPT-1 2-00019 Rev. 1 Page 97 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORM Sheet 3 of 5 Status: YO N[-] U-Seismic Walkdown Checklist (SWC) SWELl- 019 Equipment ID No. McC-9C Equip. Class' 01 -Motor Control Centers Equipment Description 480V ESS AC MCC-9C -DIESEL 1A ROOM (Sil)Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ N[] u[]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 attachment and given the number and the weight of the cabinet door the system is acceptable.

See CR- VTY-2012-04816 for corrective action.Reference Documents:

A46/IPEEE

-SSEL Line No. 000085 Evaluated by: Marcus Hecht-Nielsen Raymond Tworek iav f '- i /12" Date: 10-11-12 10-11-12 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 98 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 4 of 5 Status: Y0 N[] uLI Seismic Walkdown Checklist (SWC) SWELl- 019 Equipment ID No. MCC-9C Equip. Class' 01 -Motor Control Centers Equipment Description 480V ESS AC MCC-9C -DIESEL 1A ROOM (SI/)Photographs NO PHOTO Note: Note: EN-DG-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 99 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKOOWN CHECKLIST FORM Sheet 5 of 5 Status: Yv NEI UI-Seismic Walkdown Checklist (SWC) SWELl- 019 Equipment ID No. MCC-9C Equip. Class' 01 -Motor Control Centers Equipment Description 480V ESS AC MCC-9C -DIESEL 1A ROOM (SIlD NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 100 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 1 of 5 Status: YN NEI Ul'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 Buildino Manufacturer, Model, Etc. (optional but recommended)

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

Y-I NO 2. Is the anchorage free of bent, broken, missing or loose hardware?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 oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?YO NF- UE] N/A"]YO NEI ul] N/A[-YO N[--] UE- N/A[-I' Ener the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 101 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 2 of 5 Status: NE] 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 5. Is the anchorage configuration consistent with plant documentation?

YE] NF[" UE] 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 Yo Ni] 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?

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NE] U-' N/A[-'YZ NEi U-] N/A["]Y0 NE-] U[D N/ADl Y[ NEI UD-1 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 102 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y; NM UM Seismic Walkdown Checklist (SWC) SWELl- 020 Equipment ID No. MCC-9D Equip. Class' 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 YO N[] U[]adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Note: Original inspection completed 10/04/2012.

Re-inspected 10/11/2012 when cabinet panels were opened by qualified plant personnel exposing the anchorage connections.

Reference Documents:

A46/IPEEE

-SSEL Line No. 000088 Evaluated by: Kirit Parikh IO i4'I 2-- Date: 10/11/2012 Randy Stephens Ro- L46t4kAJ I t I te 12O017--10/11/2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 103 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheot 4 of 5 Status: YO NO] UL-Seismic Walkdown Checklist (SWC) SWELl- 020 Equipment ID No. MCC-9D Equip. Class 1 01 Equipment Description 480V E$S AC MCC-9D -REACTOR BLDG Photoaranha 4.Note: MCC-9D is located on the right.Note: MCC-9D top anchorage (south end).EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 104 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YO N1J Ur-Seismic Walkdown Checklist (SWC) SWELl- 020 Equipment ID No. MCC-9D Equip. Class' 101 Equipment Description 480V ESS AC MCC-9D -REACTOR BLDG I i Note: Two small screws are missing from the South end of MCC-9D.See item I comment on page 1.EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 105 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 1 of 5 Status: YZ N[] UL-1 Seismic Walkdown Checklist (SWC) SWELl- 021 Equipment ID No. MCC-8B Equip. Class' 01 Equipment Description 480V ESS AC MCC-8B -REACTOR BLDG (Si)Location:

Bldg. RB Floor El. 280' Room, Area Manufacturer, Model, Etc. (optional but recommended)

Westinghouse.

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

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

See comments.4. Is the anchorage free of visible cracks in the concrete near the anchors?YN NO UQ] N/A'-YO Ni uEr N/AE-Yv NO U[-' N/A[-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 engineering judgment.Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 106 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 2 of 5 Status: YED NO UI" Seismic Walkdown Checklist (SWC) SWELl- 021 Equipment ID No. MCC-8B Equip. Class' 01 Equipment Description 480V ESS AC MCC-BB -REACTOR BLDG (SI)5. Is the anchorage configuration consistent with plant documentation?

Y0 NF[- U[i N/A-O (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 Y0 NOI UrI potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 NEI UI- N/AD-Y10 NEi U[-] N/A[-]YO NFI U-If N/Afl YN NEI UE1 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 107 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YN NC U[1-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)Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ NOI UO]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 anchorage on 10-09-2012.

Returned on 10-11-2012 and removed the bottom panels at locations 1M, 4M, 6M, and 9M and top panels at IC, 5C, 6B, and 1OBL, as well as, the vertical panel 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 RayondTw rek P-~o-LMA Lp ll 1 Date: 10-11-2012 10-11-2012 EN-DC-168 REV 0

°/Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 108 of 505 Attachment C ATTACHMENT 9.6 SEiSMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0 NO1 U[-]Seismic Walkdown Checklist (SWC) SWELl- 021 Equipment ID No. MCC-8B Equip. Class' 01 Equipment Description 480V ESS AC MCC-88 -REACTOR BLDG (SD)Photographs EN-DC-168 REV 0 e/w Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 109 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 5 of 5 Status: YO Nfl" UL-Seismic Walkdown Checklist (SWC) SWELl- 021 Equipment ID No. MCC-SB Equip. Class 1 01 Equipment Description 480V ESS AC MCC-B8 -REACTOR BLDG (SI)EN-DC-168 REV 0 V Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 110 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKIDOWN CHECKLIST FORM Sheet I of 5 Status: Y0 NEI UL Seismic Walkdown Checklist (SWC) SWELl- 022 Equipment ID No. MCC-gB Equip. Class' 01 Equipment Description 480V ESS AC MCC-9B -REACTOR BLDG (SiI)Location:

Bldg. RB Roor 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 of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?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 engineering judgment.'Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

YO NC" UCI N/ACr YZ NM UCr N/A[]YZ NCI UCr N/AC" EN-DC-168 REV 0 Engineering Report No. VTY-RPT-1 2-00019 Rev. 1 Page 111 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 NEI UO]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 NEI U[-] N/A[l (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 YV NE] U[]potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 NE] u[-] N/Ar-Y[ N[3 UE] N/Ar Yv NE] uE] N/A]YZ Ni: UE]EN-DC-168 REV 0 4-Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 112 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ NO U'Seismic Walkdown Checklist (SWC) SWELl- 022 Equipment ID No. MCC-9B Equip. Class' 01 Equipment Description 480V ESS AC MCC-9B -REACTOR BLDG (S11)Other Adverse Conditions

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

Loose screws between rows 1C to 1M 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 anchorage on 10-09-2012.

Returned on 10-11-2012 and removed the bottom panels at locations IM, 5M, 8M, 9M, and 11M and top panels at 2C, 5C, 7C, and 10B, as well as, the vertical panel between MCC 6 and MCC 9 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. 000092 Evaluated by: Marcus Hecht-Nielsen Date: 10-11-2012 Qý*.--) q,9.0-ý 10 1 1 g I I U-Ravmond Tworek 10-11-2012

...........

r " .- TT ... .. .. I l EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 113 of 505 Attachment C ATTACHUEp Sheet 4 of 5T9.6 SEISMIC WALKDOWN CHECKLIST FORM 5 Status: YN NEI U--Seismic Walkdown Checklist (SWC) SWEL1- 022 Equipment ID No. MCC-98 Equip. Class'.01 Equipment Description 480V ESS AC MCC-9B -REACTOR BLDG (SII)Photographs EN-DC-168 REV 0 I

• Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 114 of 505 Attachment C ATTACHMENT 9.6 Sheet 5 of 5 SEISMIC WALKDOWN CHECKUiST FORM Status: YZ N[] UE Seismic Walkdown Checklist (SWC) SWELl- 022 Equipment ID No. MCC-9B Equip. Class 1 01 Equipment Description 480V ESS AC MCC-9B -REACTOR BLDG (SII)EN-DC-168 REV 0 9 I Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 115 of 505 Attachment C ATTACHMEI Sheet I of 5T 9.6 SEISMIC WALKDOWN CHECKLIST FoRM 5 Status: YN NEI U[Seismic Walkdown Checklist (SWC) SWELl- 023 Equipment ID No. BUS-9 Equip. Class 1 02 Equipment Description 480VAC SWITCHGEAR BUS NO.9 1600AMP (SII)Location:

Bldg. CB Floor El. 248' Room, Area SWGR EAST Manufacturer, Model, Etc. (optional but recommended)

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

Yr- NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?YE[ NEI U[- NWAS Y[-I NEI U E] N/A0 Y[-] NEI U- NWAS' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment-EN-DC-1 68 REV 0 9 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 116 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 2 of 5 Status: YZ NrO Ur-Seismic Walkdown Checklist (SWC) SWELl- 023 Equipment ID No. BUS-9 Equip. Class 1 02 Equipment Description 480VAC SWITCHGEAR BUS NO.9 1600AMP (SII)5. Is the anchorage configuration consistent with plant documentation?

YE] NO] ur] N/AS (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 NO] UO potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NE] UE] N/Ar YZ NE] UE] N/AE]YZ NO UO N/Ar YZ NEI U(']EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 117 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKOOWN CHECKLIST FORM Sheet 3 of 5 Status: Y0 NEI UL-Seismic Walkdown Checklist (SWC) SWELl- 023 Equipment ID No. BUS-9 Equip. Class' 02 Equipment Description 480VAC SWITCHGEAR BUS NO.9 1600AMP (Sit)Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Marcus Hecht-Nielsen Date: 10-09-2012 Rlaymond Tworek ~tlvr 10-09-2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 118 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRM Sheet 4 of 5 Status: Y0 NE] U-Seismic Walkdown Checklist (SWC) SWELl- 023 Equipment ID No. BUS--9 Equip. Class 1 02 Equipment Description 480VAC SWITCHGEAR BUS NO.9 1600AMP (SII Photographs NO PHOTO Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. I Page 119 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 5 of 5 Status: Y0] NL-J UE'-Seismic Walkdown Checklist (SWC) SWELl- 023 Equipment ID No. BUS-9 Equip. Class 1 02 Equipment Description 480VAC SWITCHGEAR BUS NO.9 1600AMP (SII)NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 IF Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 120 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y0 NI] U"]Seismic Walkdown Checklist (SWC) SWELl- 024 Equipment ID No. BUS-3 Equip. Class 1 03 Equipment Description 4KV- 4160V SWITCHGEAR BUS NO.3 1200AMP (SI)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 of the 50% of SWEL items requiring such verification)?

YI] NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Y['] NE] urI N/AS YI] N[] U[] N]AS YDI NEI u[] N/AO' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 V.f Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 121 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI U-Seismic Walkdown Checklist (SWC) SWELl- 024 Equipment ID No. BUS-3 Equip. Class 1 03 Equipment Description 4KV- 4160V SWITCHGEAR BUS NO.3 1200AMP (SI)5. Is the anchorage configuration consistent with plant documentation?

YE] NEI Ur" 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 YO N[] U-potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO NEI UFJ N/A[-]YZ NEI U[- N/Ar-YZ NQ UC- NIAQ-YO NO-1 UO-]EN-DC-168 REV 0 0/Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 122 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Nil uF-J Seismic Walkdown Checklist (SWC) SWELl- 024 Equipment ID No. BUS-3 Equip. Class' 03 Equipment 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 YN N(3 U[]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 RavmondTworek

~(u/'10-09-2012 EN-DC-168 REV 0 f Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 123 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: NI'] ul-]Seismic Walkdown Checklist (SWC) SWELl- 024 Equipment ID No. BUS-S Equip. Class 1 03 Equipment Description 4KV-416OV SWITCHGEAR BUS NO.3 1200AMP (SI)Photographs Note: Bus -j NO PHOTO Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 124 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NE] Ul]Seismic Walkdown Checklist (SWC) SWELl- 024 Equipment ID No. BUS-3 Equip. Class' 03 Equipment Description 4KV- 4160V SWITCHGEAR BUS NO.3 1200AMP (Sl)NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 A h*Attachment C Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 125 of 505 ATrACHMENT 9.6 SEiSMiC WALKOOWN CHECKuST FORM Sheet I of 5 Status: YN N[l U']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 Location:

Bldg. CB Floor El. 248' Room, Area SWGR WEST Manufacturer, Model, Etc. (optional but recommended)

ASEA BROWN BOVERI # PAL2721. 3 phase. ye 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 of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?YN NO UI- N/AD-]Y[O NEI UD- N/A[-D YZ NO ur N/AD]I Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 126 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 NI] 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 5. Is the anchorage configuration consistent with plant documentation?

YZ NOI UE N/AO (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 YV NF-] u]potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y"0 NI] Ur N/A-Nil U[-I N/AO--YV NEI U- N/Ar YO N[I] UrNA EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. .1 Page 127 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y0 NEI ur-I 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 Y[@ NE] Ur]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 Calculation VYC -1046 Evaluated by: Marcus Hecht-Nielsen Date: 10-09-2012 Raymond Tworek ." "/ '" 10-09-2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 128 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORM Sheet 4 of 5 Status: Y0 NO UL-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 Photographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 129 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRM Sheet 5 of 5 Status: Y[ NOI ULiM Seismic Walkdown Checklist (SWC) SWELl- 025 Equipment ID No. T-8-1A Equip. Class 1 04 Equipment Descdption STATION SERVICE TRANS 4160/480 BUS NO.8 NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 130 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Shoot I of 5 Status: YZ N[I Ur1 Seismic Walkdown Checklist (SWC) SWELl- 026 Equipment ID No. TK-4-1A Equip. Class 1 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.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

Yr] NO 2. Is the anchorage free of bent, broken, missing or loose hardware?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 anchorage is free of bent, broken, missing or loose hardware.3. Is the anchorage free of corrosion that is more than mild surface oxidation?

Same as above 4. Is the anchorage free of visible cracks in the concrete near the anchors?No cracks in the concrete base.Y9 N['] U-i N/AE" YO NEI U[- N/A['YO NEI Ur] N/AE-I Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 131 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NO! Ur]Seismic Walkdown Checklist (SWC) SWELl- 026 Equipment ID No. TK-4-1A Equip. Class' 21 Equipment Description CONDENSATE STORAGE TANK 5. Is the anchorage configuration consistent with plant documentation?

YE! NEI Ur] N/AS (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 Urn 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 surrounding the anchorage, it Is our engineering judgment 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?

No soft target found.8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YEI NEI UE! NWAS YS NE! u[:1 N/AE!Y0 NE"] uEr N/A[]YS N3 U[-]A EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 132 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y0 NEI U"-Seismic Walkdown Checklist (SWC) SWELl- 026 Equipment ID No. TK-4-1A Equip. Class' 21 Equipment Description CONDENSATE STORAGE TANK Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YO NOi U[]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 A46IIPEEE

-Screening Evaluation Work Sheet, SSEL Line No. 000103 j~~kL- lOC2e/L Evaluated by: KirOt Parlkh Date: 102/022012 RadStephens

/0/W41J 4.S.4 Ia/i -2 10/0212012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 133 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0 N[] U-I]Seismic Walkdown Checklist (SWC) SWELl- 026 Equipment ID No. TK-4-1A Equip. Class 1 21 Equipment Description CONDENSATE STORAGE TANK Photographs Note: Condensate Storage Tank -Anchorage covered by insulation.

No visible cracks around the tank foundation EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 134 of 505 Attachment C ATTACHMEI Sheet 5 of NT 9.6 SEISMIC WALKDOWN CHECKUST FORM 5 Status: YZ Nr-] Ui-Seismic Walkdown Checklist (SWC) SWELl- 026 Equipment ID No. TK-4-1A Equip. Class 1 21 Equipment Description CONDENSATE STORAGE TANK EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 135 of 505 Attachment C ATrACHMENT 9.6 SEISMIC WALKOOWN CHECKLIST FORM Sheet I of 5 Status: YZ NEI UO-Seismic Walkdown Checklist (SWC) SWELl- 027 Equipment ID No. P.44-1A Equip. Class 1 0-5 HORIZONTAL PUMPS Equipment Description HPCI/HPCI PUMP 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.Anchorane 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?Yv NEI UE- N/A[-Y[9 NO UC N/AC YO NEI Ur N/A-' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 136 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 N[-' U']Seismic Walkdown Checklist (SWC) SWELl- 027 Equipment ID No. P-44-1A Equip. Class 1 0-5 HORIZONTAL PUMPS Equipment Description HPCI/HPCI PUMP 5. Is the anchorage configuration consistent with plant documentation?

YN Nr] Ut] N/Ar](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 (and associated calculation) and drawing No. 5920-0622.

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

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 N-I UtJ N/At]YZ NEI Ut] N/At]Y0 NEI Ut] N/At]YYN U--u EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 137 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y[9 NI] U--Seismic Walkdown Checklist (SWC) SWELl- 027 Equipment ID No. P-44-IA Equip. Class' 0-5 HORIZONTAL PUMPS Equipment Description HPCI/HPCI PUMP Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YO Ni[] Ur 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: Kirit Parikh tZpav6ý1C4-tol 110 to I I.Randy Steohenn 2 w U33J~t-)-2-O kd (ate: 10/09/2012 1 W0/09/2012

ýj EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 138 of 505 Attachment C ATTACHmENT 9.6 SEISIuC WALKDOWN CHECKLST FoRM Sheet 4 of 5 Status: YZ N-- U'-Seismic Walkdown Checklist (SWC) SWELl- 027 Equipment ID No. P-44-IA Equip. Class' 0-5 HORIZONTAL PUMPS Equipment Descriptlon HPCL/HPCI PUMP Photographs NO PHOTO Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 139 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORM Sheet 5 of 5 Status: Y0 NCl U-I Seismic Walkdown Checklist (SWC) SWELl- 027 Equipment ID No. P-44-1A Equip. Class 1 0-5 HORIZONTAL PUMPS Equipment Description HPCI/HPCI PUMP NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 140 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: YZ NO UO Seismic Walkdown Checklist (SWC) SWELl- 020 Equipment ID No. PS-23-84-1 Equip. Class 1 18- INSTRUMENTS ON THE RACK Equipment Description HPCI/PUMPSUCTION PRESSURE SWITCH 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.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YZ NO of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?Y0 NOI UD N/AO"]YED NO UO N/AO YZ NEI UrD N/A-' Enter the equipment class name from EPRI 1025286. Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-1 2-00019 Rev. 1 Page 141 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 NO U'-Seismic Walkdown Checklist (SWC) SWELl- 028 Equipment ID No. PS-23-84-1 Equip. Class 1 18- INSTRUMENTS ON THE RACK Equipment Description HPCI/PUMPSUCTION PRESSURE SWITCH 5. Is the anchorage configuration consistent with plant documentation?

YN NEI UF"D N/AD1 (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(@ N[] UED potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 NOj Un N/AD YN NDI U"] N/ADI YN NO] u[1 N/A[D]YN NEI U-]EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 142 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 3 of 5 Status: Y0 NEJ' UL-J Seismic Walkdown Checklist (SWC) SWELl- 028 Equipment ID No. PS-23-84-1 Equip. Class 1 18- INSTRUMENTS ON THE RACK Equipment Description HPCI/PUMPSUCTION PRESSURE SWITCH Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 NEI U[J 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: Kirit Parikh toile 12.012-Da w Ran&y SteohensIC.4wRJQ-

~t4((02 te: 10/09/2012 10/09/2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 143 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YZ NEl UI-Seismic Walkdown Checklist (SWC) SWELl- 028 Equipment ID No. PS-23-84-1 Equip. Class 1 18- INSTRUMENTS ON THE RACK Equipment Description HPCIIPUMPSUCTION PRESSURE SWITCH Photographs NO PHOTO Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 144 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NEL U[-]Seismic Walkdown Checklist (SWC) SWELl- 028 Equipment ID No. PS-23-84-1 Equip. Class' 18- INSTRUMENTS ON THE RACK Equipment Description HPCI/PUMPSUCTION PRESSURE SWITCH NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-1 2-00019 Rev. 1 Page 145 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: Y0D N[--] UE-Seismic Walkdown Checklist (SWC) .SWELl- 031 Equipment ID No. TEF-3 Equip. Class 1 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.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one Y19 NE]of the 50% of SWEL items requiring such verification)?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?There is a hairline crack in the upper right hand corner. No seismic concern by engineering judgment.Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment-Y0 NEI U-] N/A--Y0 NE] ur N/A[']Y0 NO Ur N/A--EN-DC-168 REV 0 P 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 146 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 N[5 U'-Seismic Walkdown Checklist (SWC) SWELl- 031 Equipment ID No. TEF-3 Equip. Class 1 09 Equipment Description DG B ROOM VENTILA TION/EXAUST FAN 5. Is the anchorage configuration consistent with plant documentation?

YC9 NO UO N/A-(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 UC-]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?

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO NC U- N/ACNCI UC N/AC Yr" NC UC N/A0 YZ NEI UM EN-DC-168 REV 0 P Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 147 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 3 of 5 Status: YE0 NOI UoI Seismic Walkdown Checklist (SWC) SWELl- 031 Equipment ID No. TEF-3 Equip. Class' 09 Equipment Description DG B ROOM VENTILA TION!EXAUST FAN Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YV No U']adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Referenced Documents:

Drawing 5920-4449 A46/IPEEE

-Screening Evaluation Work Sheet, SSEL Line No. ooo145 Evaluated by: Marcus Hecht-Nielsen

.iJ i, Date: 10-03-2012 Raymond Tworek aot/--10-03-2012 EN-DC-168 REV 0 10, Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 148 of 505 Attachment C ATTAcHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y( NI] UE'Seismic Walkdown Checklist (SWC) SWELl- 031 Equipment ID No. TEF-.I Equip. Class 1 09 Equipment Descrption DG B ROOM VENTILATION/EXAUST FAN Photographs EN-DC-168 REV 0

.P Engineering Report No. VTY-RPT-12-00019 Rev. 1 Attachment C Page 149 of 505 ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ NEI UO-Seismic Walkdown Checklist (SWC) SWELl- 031 Equipment ID No. TrEF-3 Equip. Class' 09 Equipment Description DG BROOM VENTILA TION/EXAUST FAN No Photo No Photo Note: Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 150 of 505 Attachment C ATrACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YI NCI UL'Seismic Walkdown Checklist (SWC) SWELl- 032 Equipment ID No. RRU-8 Equip. Class 1 10 Equipment Description SW/ECCS RM COOLING Location:

Bldg. RB Floor El. 213' Room, Area SECR Manufacturer, Model, Etc. (optional but recommended)

HKPORTER-MARLO COIL WORKS. Model# 41-5,23-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 of the 50% of SWEL items requiring such verification)?

YD NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?YO NC] U[- N/AC Y0 NCI UC- N/A-YO NCI ur N/ACT'Enter the equipment class name from EPRi 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 151 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORM Sheet 2 of 5 Status: Y0 N[] U[3 Seismic Walkdown Checklist (SWC) SWELl- 032 Equipment ID No. RRU-8 Equip. Class 1 10 Equipment Description SWIECCS RM COOLING 5. Is the anchorage configuration consistent with plant documentation?

Y-I NOI U-' N/A0R (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 YO NOI U[]potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO NOI UO- N/AO" Y1Z NOl U[3 N/AO YZ NOI uO" N/AO YZ Nr-I U EN-DC-168 REV 0 Attachment C Engineering ATTACHMENT 9.6 S Shoot 3 of 5 Seismic Walkdown Checklist (SWC) SWELl- 032 Equipment ID No. RRU-8 Equip. Class 1 10 Equipment Description SW/ECCS RM COOLING Other Adverse Conditions

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

Report No. VTY-RPT-12-00019 Rev. 1 Page 152 of 505 EISMIC WALKDOWN CHECKLIST FORM Status: YZ N-] U0 YO NEI UO Comments (Additional pages may be added as necessary)

Reference Documents:

A46/1PEEE

-SSEL Line No. 000164 Evaluated by: Kirit Parikh 1 011---o I l0 I-RandyStenhens o'-4 I C ( ZI 1L-Date: 10/11/2012 10/11/2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-1 2-00019 Rev. 1 Page 153 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Yv NE- UE-Seismic Walkdown Checklist (SWC) SWELl- 032 Equipment ID No. RRU-8 Equip. Class 1 10 Equipment Description SW/ECCS RM COOLING Photographs I I EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 154 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRM Sheet 5 of 5 Status: Y[ NEL UM-Seismic Walkdown Checklist (SWC) SWELl- 032 Equipment ID No. RRU-8 Equip. Class' 10 Equipment Description SW/ECCS RM COOLING NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 155 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKOOWN CHECKLIST FORM Sheet 1 of 5 Status: YZ NEI UEJ 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.Anchora-ge

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

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?Equipment has a steel attachment.

YED NEI UDi N/AD YN N[: UEr N/AD-Y-I Ni- UD- N/A]' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.

EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 156 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: Y0 NEI U'-Seismic Walkdown Checklist (SWC) SWELl- 033 Equipment ID No. PT-2-3-52C Equip. Class 1 18 Equipment Description CS, RHR PERMISSIVE

5. Is the anchorage configuration consistent with plant documentation?

YZ NE] ur] N/AEI (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[9 N[: U[]potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NEI UD" N/AD-]Y0 ND'l U'- N/AD-Y0 ND'- UD-] N/AD]YN NEI DU[r EN-DC-168 REV 0 44 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 157 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y0 NC] UL]Seismic Walkdown Checklist (SWC) SWELl- 033 Equipment ID No. PT-2-3-5C_

Equip. Class 1 18 Equipment Description CS. RHR PERMISSIVE Other Adverse Conditions

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

.09,9/) Date: 10-04-2012 R qW 'mnnri Tw nr...kF CD" Raymond Twnrak 10-04-2012

• ,

• m *

• I EN-DC-168 REV 0 A Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 158 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Y0 N[] U[]Seismic Walkdown Checklist (SWC) SWELl- 033 Equipment ID No. PT-2-3-52C Equip. Class 1 18 Equipment Description CS. RHR PERMISSIVE Photographs NO PHOTO Note: EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1 Page 159 of 505 Attachment C ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: Y0 NE] Ur-L Seismic Walkdown Checklist (SWC) SWELl- 033 Equipment ID No. PT-2-3-52C Equip. Class 1 18 Equipment Description CS, RHR PERMISSIVE NO PHOTO NO PHOTO Note: Note: EN-DC-168 REV 0