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| issue date = 06/20/2013
| issue date = 06/20/2013
| title = 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
| title = 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
| author name = Buckley S M
| author name = Buckley S
| author affiliation = Entergy Nuclear Operations, Inc
| author affiliation = Entergy Nuclear Operations, Inc
| addressee name =  
| addressee name =  
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| document type = Report, Technical
| document type = Report, Technical
| page count = 210
| page count = 210
| project =
| stage = Other
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{{#Wiki_filter:Engineering Report No. VY-RPT-12-00019 Rev IPage 1 of 33~Enter"yENTERGY NUCLEAREngineering Report Cover SheetEngineering Report Title:VERMONT YANKEESeismic Walkdown Submittal Reportfor Resolution of Fukushima Near-Term Task Force Recommendation 2.3: SeismicEngineering Report Type:New rl Revision ED Cancelled MlSuperseded Superseded by:Applicable Site(s)IPI ElANOI ElEC No. 44934IP2 ElANO2IP3 ElECH ElJAF ElGGNS ElPNPS ElRBS ElVYWWF3 ElWPOPLPElE]Report Origin:0 Entergy El VendorVendor Document No.: N/AQuality-Related:
{{#Wiki_filter:}}
El Yes0 NoPrepared by:fSteen 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- 12-00019Rev. 1Page 2 of 33Report Number VY-RPT-12-00019 Rev qPage I of 28*EnteENTERGY NUCLEAREngineering Report Cover SheetEngineering Report Title:VERMONT YANKEESeismic Walkdown Submittal Reportfor Resolution of Fukushima Near-Term Task Force Recommendation 2.3: SeismicEngineering Report Type:New 0 Revision C]Cancelled
[I Superseded
[]Superseded by-Applicable Site(s)'p 1 1IP2 01 1P3 C1 Jj&.F 01 PP~S 0Vy 0 WPO 11ANOI []AN02 [ECH [I GGNS [IRBS [E WF3 0l PLP ElEC No. 40647Report Origin:[E Entergy 0 VendorVendor Document No.: 1N-AQuality-Related:
NoPrepared by-Reviewed by:Reviewed by:Reviewed by:Approved by:Jeffrey Horton P.E (ENERCON)
/ A "OtherJuan Vizcaya (ENERCoN)
IPeer RLiewerSteven M Buckley al "Scott D Goodwin /....-./{7Y.,y-L.)
_vfSuperviwsr ManagerDate: /-2o ',/2Date: _ -_ '_Date: 114042Date: ll-20-ZOiZ Date- __ECi___
Engineering Report No. VY-RPT- 12-00019Rev. 1Page 3 of 33Revision Recordao f on0 Initial issue.Revision 0 Report was revised to incorporate inspection of the deferred itemsduring Refueling Outage (RFO 30) in March of 2013.-Retained Revision 0 Cover Sheet and signatures as page 2 to provide arecord of the personnel responsible for the Revision 0 content.-Revised Table of Contents, Table 4-1, Table 4-2, and other text revisions oradditions required to reflect deferred inspections as denoted by revision bars.-Minor editorial formatting changes only in Section 6.4 table with no Revision 0information changes.-Attachment C, page 3 of 505, Table of Contents was updated to match theEquipment 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 wasplaced above the Steam Tunnel table to match the format of the table ofcontents 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- 12-00019Rev. 1Page 4 of 33TABLE OF CONTENTSSection Description Page1.0 SCO PE AND O BJECTIVE
.......................................................................................................
52.0 SEISMIC LICENSING BASIS SUMMARY .................................................................................
62.1 Safe Shutdown Earthquake
....................................................................................................
62.2 Design Codes, Standards and M ethods ...................................................................................
73.0 SEISMIC WALKDOWN PROGRAM IMPLEMENTATION APPROACH
..........................
84.0 PERSO NNEL Q UALIFICATIO NS .............................................................................................
84.1 Equipment Selection Personnel
.............................................................................................
124.2 Seism ic W alkdown Engineers
...............................................................................................
124.3 Licensing Basis Reviewers
....................................................................................................
124.4 IPEEE Reviewers
.......................................................................................................................
124.5 Peer Review Team .....................................................................................................................
135.0 IPEEE VULNERABILITIES REPORTING
..............................................................................
156.0 SEISMIC WALKDOWN EQUIPMENT LIST DEVELOPMENT
.........................................
156.1 Base List .....................................................................................................................................
166.2 SW EL I ......................................................................................................................................
166.3 Spent Fuel Pool Item s ............................................................................................................
186.4 Deferred, Inaccessible Item s on SW EL .................................................................................
207.0 SEISMIC WALKDOWNS AND AREA WALK-BYS
...............................................................
217.1 Seism ic W alkdowns
...............................................................................................................
218.0 LICENSING BASIS EVALUATIO NS ........................................................................................
238.1 Licensing Basis Evaluations
..................................................................................................
238.2 Corrective Action Program Entries ........................................................................................
248.3 Plant Changes .............................................................................................................................
259.0 PEER REVIEW .................................................................................................................................
269.1 Peer Review Process ..................................................................................................................
269.2 Peer Review Results Sum m ary ..............................................................................................
26
 
==10.0 REFERENCES==
 
...................................................................................................................................
3211.0 ATTACH M ENTS ..............................................................................................................................
33 Engineering Report No. VY-RPT-12-00019 Rev. 1Page 5 of 281.0 SCOPE AND OBJECTIVE The Great Tohoku Earthquake of March 11, 2011 and the resulting tsunami caused an accident at theFukushima 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 asystematic and methodical review of NRC processes and regulations and determining if the agencyshould make additional improvements to its regulatory system. On March 12, 2012 the NRC issued a1OCFR50.54(f) letter (Ref. 10.1) requesting information from all licensees to support the NRC staffsevaluation 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 theplant related to degraded, non-conforming, or unanalyzed conditions with respect to its current seismiclicensing basis.The Electric Power Research Institute (EPRI), with support and direction from the Nuclear EnergyInstitute (NED, published industry guidance for conducting and documenting the seismic walkdowns which represented the results of extensive interaction between NRC, NEI, and other stakeholders.
Thisindustry 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 PowerStation (VYNPS) has committed to using this NRC-endorsed guidance as the basis for conducting anddocumenting 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 forresolution of the Fukushima Near Term Task Force (NTTF) Recommendation 2.3, Seismic.This report summarizes the basis, planning, preparation, execution and findings of the seismicwalkdowns and constitutes the "Submittal Report" as described in Section 8 of the Guidance dated June2012. The objective of the walkdown effort was to provide responses to the 10 CFR 50.54(f) letterissued by the NRC on 3/12/12 (Ref. 10.1). This included walkdowns of a sample of components andwalk-bys of associated areas of the plant to identify potentially adverse seismic conditions within theparameters provided in EPRI Report 1025286 (Ref. 10.2). Adverse seismic conditions included thosethat 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. Thiscomponent sample constituted the Seismic Walkdown Equipment List (SWEL) which satisfies therequirements for sampling as outlined in EPRI Report 1025286.Using the SWEL, walkdown teams consisting of two Seismic Walkdown Engineers (SWEs) per teamwalked down the subject components.
Results of the walkdowns were recorded on Seismic WalkdownChecklists (SWCs). All accessible items on the SWEL were walked down. Inaccessible items arelisted 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 plantcontaining a component listed in the SWEL. Results of the area walk-bys were recorded on AreaWalk-by Checklists (AWCs).
Engineering Report No. VY-RPT- 12-00019Rev. 1Page 6 of 28Area Walk-bys supplemented the seismic walkdowns and provided for inspections of general areas inthe vicinities of the subject equipment.
This eliminated tunnel-vision and allowed a vehicle to reportother potentially adverse conditions.
In cases where multiple SWEL items were located in the sameroom/area of the plant, a single AWB was conducted.
Plant rooms/areas were generally found to besufficiently 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 ofapproximately 35 feet around the component on the SWEL. The limits of the walk-by for these casesare defined on the Area Walk-by Checklist.
The intent of the walkdowns/walk-bys was to identify potentially adverse seismic conditions with afocus on anchorage and seismic spatial interactions.
Potentially adverse seismic conditions were notedon 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 fieldinspections.
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 wereinitiated to document potentially adverse seismic conditions.
The results of the LBEs are discussed inSection 8.0 and additional information is provided in Attachment F.2.0 SEISMIC LICENSING BASIS SUMMARYVermont 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 VYNPSbegan commercial operation in November of 1972, and is currently rated at 1912 MWt power. Thissection summarizes the seismic licensing basis of structures, systems and components (SSCs) atVYNPS 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 NaturalPhenomena",
of 10 CFR 50, Appendix A, structures,
: systems, and components important tosafety are designed to withstand the effects of natural phenomena such as earthquakes withoutloss 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 FinalSafety 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 largesthistorical earthquake in the region applied at the closest known location of faulting.
It isspecifically 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 groundacceleration (Ref. 10.14).The damping factors used in the dynamic seismic analysis are given in the Updated FinalSafety Analysis Report (UFSAR).
Engineering Report No. VY-RPT- 12-00019Rev. 1Page 7 of 28Additionally, 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 aseismic standpoint.
From these studies the design earthquake has been established at 0.07ghorizontal ground acceleration and the maximum hypothetical earthquake at 0.14g horizontal ground acceleration.
The seismic evaluation consisted of a review of historical data from theNew England area, an analysis of instrument and historical records for the Vermont area, and astudy of earthquake intensity attenuation with distance for the northeast United States."2.2 Design Codes, Standards and MethodsSeismic 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 asthose structures, equipment, and components whose failure or malfunction might cause orincrease the severity of an accident which would endanger the public health and safety. Thiscategory includes those structures, equipment, and components required for safe shutdown andisolation 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 otherapplicable 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 Programinclude the Reactor Building, Control Building, Intake Structure and Emergency DieselGenerator Rooms including day tank enclosures located in the Turbine Building.
Seismicdesign of Class I SSCs is in accordance with Section 12.2 of the UFSAR and Topical DesignBasis 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 ofequipment supports.
Appendix C to the UFSAR provides the Seismic Class I criteria forequipment and piping design. Appendix A to the UFSAR provides the description, scope anddesign 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 toverify 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 seismicdesign is provided in the VYNPS UFSAR. A summary of the more relevant references for thedesign of Seismic Category I structures, systems and components is provided here.2.2.1 ASME Boiler and Pressure Vessel Code, various sections2.2.2 American Concrete Institute (ACI) Building Code Requirements for Reinforced Concrete
.Engineering Report No. VY-RPT- 12-00019Rev. 1Page 8 of 282.2.3 American Welding Society (AWS) Standard Code for Arc and Gas Welding inBuilding 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 APPROACHEntergy VYNPS has committed to conduct and document seismic walkdowns for resolution of NTTFRecommendation 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 2.3Seismic Walk-down Procedure" (Ref. 10.13), outlining the guidelines, processes and requireddocumentation 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 theIndividual 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 seismiclicensing 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 provideengineering and project management resources to supplement and assist each individual site. VYNPShad 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 withvarious responsibilities.
This section identifies the project team members and their projectresponsibilities, and provides brief experience summaries for each person. Training certificates of thosequalified as Seismic Walkdown Engineers are included in Attachment H.The following table summarizes the names and responsibilities of personnel used to conduct the seismicwalkdowns.
Experience summaries of each person follow.
Engineering Report No. VY-RPT- 12-00019Rev. 1Page 9 of 33Table 4-1Equipment Seismic Licensing IPEEEName Selection Walkdown Basis ReviewerPersonnel Engineer ReviewerSteven Buckley (Vermont Yankee) X2 x2,3 x3 XMark Palionis (Vermont Yankee) X XEd Harms (Vermont Yankee) X'Scott Goodwin (Vermont Yankee) X3Marcus Hecht-Nielsen (ENERCON/ARES)
XRandall Stephens (ENERCON/ARES)
XRaymond Tworek (ENERCON/ARES)
XKirit Parikh (ENERCON)
XMichael Rose (Vermont Yankee) x3David Grimes (Vermont Yankee) XNotes:II1.2.3.Plant Operations representative Designated lead SWEDeferred walkdown SWEL items and Revision 0 responsibilities for SWEL itemsMr. Steven BuckleyMr. Buckley is a Professional Engineer (Structural) with over 25 years of seismic design experience inthe 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 "SQUGWalkdown Screening and Seismic Evaluation" training course. He was part of a two man team thatperformed all the walkdowns required by the USI-A46 and Seismic IPEEE programs at VermontYankee 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 dutiesat Vermont Yankee include technical oversight of contracted design projects and serving as lead designengineer for civil/structural/mechanical projects developed in-house.
He has performed design relatedwork 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 Seismicwalkdowns and was the lead engineer responsible for addressing issues documented in the CorrectAction Program.
Engineering Report No. VY-RPT-12-00019 Rev. 1Page 10 of 28Mr. Mark PalionisMr. Palionis is an engineer with over 30 years of experience in the nuclear power industry.
He holds aBachelor of Science degree in Mechanical Engineering from the Polytechnic Institute of Brooklyn, aswell 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. Hisprimary duties include maintenance and update of the Vermont Yankee PRA model, providing riskassessments as required in support of licensing initiatives (e.g., Tech Spec amendments for changes insystem 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 YankeeSystem 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 forthe installation and servicing of GE/Boiling Water Reactors and of GE/Large Steam Turbines andGenerators, with principal work experience in the areas of installation and repair of RPV internals andNSS systems for GE/BWRs.Mr. Ed HarmsMr. 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 theOperation Department as an Assistant Ops Manager.
He has a Senior Reactor Operator license since2003. 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 GoodwinMr. 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 numerousutilities, 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 theparticipating representative to the SQUG organization for development of resolution of USI A-46 underGL 87-02. He has completed the "SQUG Walkdown Screening and Seismic Evaluation" trainingcourse. Mr. Goodwin was the manager for implementation of Vermont Yankee's SQUG program andthe seismic portion of the IPEEE program.
Engineering Report No. VY-RPT-12-00019 Rev. 1Page 11 of 28Marcus Hecht-Nielsen Mr. Marcus Hecht-Nielsen is a licensed professional engineer with over 7 years experience.
He has aB.S degree in Structural Engineering from University of California at San Diego and an M.S inStructural Engineering also from University of California at San Diego. He is a qualified SeismicWalkdown Engineer who is trained to EPRI Near-Term Task Force (NTTF) 2.3 requirements forperforming seismic verification walkdowns of equipment and distribution systems at nuclear powerplants and facilities.
He is employed by Tobolski Watkins Engineering and has provided seismicqualifications for the US Mixed Oxide Fuel Fabrication Facility for Flanders Corporation.
Hisexperience includes many other structural design related projects.
Randall StephensMr. Randy Stephens is a degreed mechanical engineer with nuclear design experience.
He is aqualified Seismic Walkdown Engineer who is trained to EPRI Near-Term Task Force (NTTF) 2.3requirements for performing seismic verification walkdowns of equipment and distribution systems atnuclear power plants and facilities.
His experience includes supporting design tasks and specialengineering efforts associated with general mechanical systems and components.
This includespreparing and/or assisting in the preparation of design drawings, specifications and calculations, andparticipating on design teams for projects involving the design of equipment,
: systems, buildings, andfacilities.
Raymond TworekMr. Ray Tworek is a degreed mechanical engineer and a qualified Seismic Walkdown Engineer trainedto 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 supportsmechanical design activities related to both facilities and specialty hardware for ARES' clients acrossthe United States. This support encompasses engineering, design, analysis, fabrication, and testing ofstructures,
: systems, and components in the energy, aerospace, and oil & gas industries.
Kirit ParikhMr. Kirit Parikh is a degreed Mechanical Engineer with over 30 years experience, most in the nuclearfield. He has successfully completed EPRI Training on Near Term Task Force Recommendation 2.3Plant Walkdowns.
He has worked for various companies including many nuclear utilities in UnitedStates and abroad. His experience includes pipe support design, plant modifications, as well as homeoffice and field assignments.
David F. GrimesMr. Grimes is a Civil engineer with over 29 years of experience in the nuclear power industry.
Heholds 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 DesignEngineer for Vermont Yankee. His primary duties at Vermont Yankee include technical oversight ofcontracted design projects and serving as design engineer for Civil/Structural/Mechanical projectsdeveloped in-house.
He has performed design related work for Vermont Yankee Nuclear Power Stationfor more than 25 years. He is also responsible for the programmatic monitoring of structures to meetthe 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 atwo man team.
Engineering Report No. VY-RPT- 12-00019Rev. 1Page 12 of 28Michael RoseMr. 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 aCivil/Structural/Mechanical Design Engineer for Vermont Yankee. Major tasks while at VermontYankee have included Seismic scaffold package preparation and inspections, Structural portions ofEngineering
: Changes, and calculation preparation.
For this project Mr. Rose assisted in preparation of the Base Lists and SWELs, provided projectoversight for the walkdown teams, and completed walkdowns for the Spent Fuel Pool SWEL 2 items aspart 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 BasisReviewers.
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 supportfrom Mark Palionas (PRA Group), both from Vermont Yankee.
Engineering Report No. VY-RPT- 12-00019Rev. 1Page 13 of 334.5 Peer Review TeamTable 4.2 summarizes the names and responsibilities of personnel used to conduct peer reviewsof the seismic walkdown program.
Experience summaries of each person follow.Table 4-2SWEL Walkdown Submittal Name Peer Peer Report PeerReviewer Reviewer ReviewerJulien Abramovici (ENERCON)
X_ XlJuan Vizcaya (ENERCON)
X X2Laura Maclay (ENERCON)
XJeffrey Horton (ENERCON)
XScott Goodwin (Vermont Yankee) x4 x4David Grimes (Vermont Yankee) X3  x3Notes:1. SWEL and Walkdown Peer Review Team Leader2. Submittal Peer Review Team Leader3. Peer Review for the deferred SWEL items and Submittal Report4. Peer Review Team Leader for deferred SWEL itemsPeer Review Team LeaderMr. Julien Abramovici P.E. has over 39 years of nuclear power plant experience.
He held various positions such ascomponent
: 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 adequacyof components and structures, such as IEB 80-11, component seismic qualifications, 3rd partyreviews 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 CauseEvaluations.
Engineering Report No. VY-RPT-12-00019 Rev. 1Page 14 of 33SWEL Peer ReviewerLaura MaclayMs. Maclay has over three years of experience as a structural engineer with Enercon Servicesand holds a Bachelor's degree in Structural Engineering from Drexel University.
Her taskshave ranged from assisting with the development and preparation of design change packages toperforming design calculations and markups, comment resolutions, and drawing revisions.
Shespent a year on site at Turkey Point Nuclear Plant preparing structural evaluations of SSC's foran Extended Power Uprate (EPU). She designed safety related supports for computer andelectrical equipment for the Turbine Digital Controls Upgrade package and other similarpackages.
Her responsibilities also included the review of calculations, drawings and vendordocumentation for the seismic evaluation of the Unit 3 Palfinger Crane inside containment andnew platforms in the High Pressure Turbine enclosure.
Recent work includes Fukushima flooding walkdowns at Limerick Generating Station andseismic 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 adverseconditions.
Walkdown Peer ReviewerMr. Juan VizcayaMr. Vizcaya has over 30 years of structural engineering and design experience.
He hassignificant experience being the structural lead engineer on ISFSI projects and overall nuclearplant modifications and has a wide range of design/engineering experience.
Projects rangefrom the seismic analysis and design of concrete and steel structures and concrete pads to theanalysis 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 designprocess, and at the practical design of mechanical components, along with concrete and steelstructures.
He leads a group structural staff on issues involving structures, stress analysis, andsite 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 ReviewerMr. Jeffrey Horton P.EMr. 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. Heholds a B. S. in Aerospace Engineering from Parks College of St Louis University in Missouriand a M. S. in Material Science specializing in Solid Mechanics from Rutgers University inNew 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. 1Page 15 of 335.0 IPEEE VULNERABILITIES REPORTING During the IPEEE program in response to NRC Generic Letter 88-20 (Ref. 10.3), plant-specific seismicvulnerabilities 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 itemsdetermined to present a seismic vulnerability.
The IPEEE Reviewers then reviewed additional plantdocumentation to identify the eventual resolutions to those seismic vulnerabilities not resolved whenthe IPEEE report was submitted.
The seismic vulnerabilities identified for VYNPS during the IPEEE program are reported inAttachment 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 theseequipment 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 SeismicWalkdown Equipment List (SWEL) in accordance with Section 3 of the Guidance.
A team ofequipment selection personnel with extensive knowledge of plant systems and components was selectedto 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 tomaintain containment integrity (i.e., supporting the five safety functions)
* SWEL 2 consists of items related to the safety related spent fuel pool systemThe final SWEL is the combination of SWEL I and SWEL 2. The development of these two groups isdescribed 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. 1Page 16 of 33Maintaining 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 issummarized in Figure 1-1 of the Guidance.
Figure 1-1 of the Guidance provides a screening methodfor selecting SSCs, starting with all of the plant SSCs and reducing the number based on a series ofscreening criteria.
The equipment coming out of Screen #3 and entering Screen #4 is defined as BaseList 1. The equipment coming out of Screen #4 is the first Seismic Walkdown Equipment List, orSWEL 1. Development of these lists is described separately in the following sections:
6.1 Base ListA spreadsheet was developed to tabulate the total number of equipment for each of the twentytwo (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 developthe 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 ofSeismic Category (SC) I equipment or systems that support the five safety functions.
TheIPEEE program was intended to address the seismic margin of SSCs associated with each ofthe five safety functions.
At Vermont Yankee Nuclear Station, the EPRI Seismic MarginAssessment (EPRI SMA) method was used to complete the seismic IPEEE program, based onEPRI Report NP-6041 titled "A Methodology for assessment of Nuclear Power Plant SeismicMargin."
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 onepreferred and one alternate "success path" capable of achieving and maintaining a safeshutdown condition for at least seventy-two hours following a SSE event. This equipment listof SSCs on the success paths is consistent with the requirements of Screens #1 through #3 ofthe Guidance.
Therefore, the IPEEE equipment list of SSCs on the success paths is used as astarting 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 1Based on the target of 105 items, each equipment class total was factored down by 15% toobtain an idealized number of equipment in each equipment class to be selected to maintain thesame equipment diversity as the original A46/IPEEE equipment list.In parallel with the above, a risk ranking assessment was performed to determine the most risksignificant 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 wassorted 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 Ilist. This risk ranking fulfills the requirement to select equipment that supports the 5 requiredsafety functions Engineering Report No. VY-RPT- 12-00019Rev. 1Page 17 of 33The resultant risk ranking listing contained redundant trains of multiple systems.
Eachequipment type on the risk ranking list was selected to cover the maximum amount of buildingareas where the system are located.
For example, both A & B EDG components were selectedto cover all areas of each room and any unique features such as the EDG B penthouse louverslocated on the roof of the EDG B room. The RHR equipment in the corner rooms of theReactor Building was selected to minimize dose exposure for the walkdown personnel and haveequipment on each level of each corner room. Once the risk significant equipment wasrepresented the "Sample Considerations screen was applied.
Throughout the application of thisscreen, dose surveys for the equipment areas were reviewed to ensure equipment in the lowerdose areas were selected if there was an option.During application of the above screens the overall GIP equipment class percentages weremaintained 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 selectedwhenever possible to complete the target number in each equipment classification.
Thesemodifications were designed to IPEEE seismic levels and thereby are considered an IPEEEenhancement.
In addition, two new components were added that were not on the originalA46/IPEEE lists. One component is a new inverter that replaces a battery & charger system andthe 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 adequaterepresentation from various environments.
Specifically, Based on Figure 1-1 and Section 3 ofthe 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 thecontribution to risk for the SSCs. Equipment Selection Personnel developed SWEL 1 using aniterative 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 onSWEL 1 was given to items that are accessible and have visible anchorage while stillmaintaining 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 SystemsItems were selected from Base List 1 ensuring that each of the five safety functions was wellrepresented.
Additionally, components from a variety of frontline and support systems, aslisted in Appendix E of the Guidance, were selected.
The system type of each item on SWEL 1is 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 BaseList 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 1in Table 9.4.1 of Attachment B. A robust sampling of these items is represented on SWEL 1.
Engineering Report No. VY-RPT- 12-00019Rev. 1Page 18 of 33Variety of Equipment TypesAccording 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 fromeach class was determined.
Items were then selected from Base List 1 ensuring that each of theequipment classes represented there was also represented on SWEL 1 in approximately thesame ratios. The equipment class of each item on SWEL 1 is listed on Table 9.4.2 ofAttachment 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 ashaving high temperature and/or elevated humidity and within containment.
The location andenvironment 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 onBase List I which were enhanced as a result of seismic vulnerabilities identified during theIPEEE program.
These items are designated as such on Base List I in Table 9.4.1 ofAttachment 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 withhigher risk significance was chosen.6.3 Spent Fuel Pool ItemsThe 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 theGuidance.
The equipment coming out of Screen #2 and entering Screen #3 is defined as BaseList 2. The items coming out of Screen #4 are the items that could potentially cause the SFP todrain rapidly.
The items coming out of either Screen #3 or Screen #4 are the second SeismicWalkdown Equipment List, or SWEL 2. Development of these lists is described separately inthe 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- 12-00019Rev. 1Page 19 of 336.3.1 Base List 2The 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 DownA review of spent fuel pool drawings was performed to assess any potential rapid drain downpaths. 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 reviewconfirmed 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 floodedreactor cavity there is a potential drain path from the reactor cavity drain lines.Yankee Atomic Electric Company (YAEC) Report #1493, "Vermont Yankee Nuclear PowerPlant Evaluation of Potential Failures of the Spent Fuel Pool Storage System",
was prepared inresponse to IE Bulletin 84-03, "Refueling Cavity Water Seal". This report evaluates thepotential for, and consequences of, a cavity seal failure.
It considered the potential drain pathsthrough 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 adequateand the failure of the non-seismic piping is considered a "very unlikely scenario andconservative 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 thisconnected piping failure would drain the top 6 feet of the SPF in 54 minutes with no Operatoraction and the makeup capacity exceeds the leak rate capacity6.3.3 SWEL 2The first screen of Seismic Category I (SCI) equipment limits the scope to the Standby FuelPool Cooling System and associated SCI support equipment.
A review of G-191173 flowdiagrams provided the source for the identification of SCI equipment.
Using sampling Engineering Report No. VY-RPT- 12-00019Rev. 1Page 20 of 33considerations defined in Reference 10.2, the resulting equipment is a pump, valve, heatexchanger, control panel and instrument rack and associated indicating instruments.
A total ofeleven (11) components were selected.
SWEL 2 is presented in Table 9.4.5 of Attachment B.6.4 Deferred, Inaccessible Items on SWELEach item on the SWEL shall be walked down as part of the NTTF 2.3 Seismic Walkdownprogram.
In order to perform the seismic walkdowns of these items, it is necessary to haveaccess to them and to be able to view their anchorage.
In some cases, it was not feasible to gainaccess to the equipment or view its anchorage because Vermont Yankee Nuclear Station was atpower during the entire 180-day response period of Enclosure 3 to the 50.54(f) letter. For thesecases, walkdowns of these items have been deferred until the next refueling outage (RFO 30) inMarch of 2013. An updated submittal report incorporating these deferred walkdowns will beprovided 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 lackof access (high radiation areas). Eight (8) items are in the Steam Tunnel and five (5) items arein the Drywell.SWEL# Equipment ID Description Location ReasonSWELI-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 VALVE275'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- 12-00019Rev. 1Page 21 of 336.4.1 During the March 2013 Refueling Outage (RFO 30), the deferred equipment defined inthis Section 6.4 was walked down as part of the NTTF 2.3 Seismic WalkdownProgram.
The walkdowns were conducted in accordance with the Guidance asdescribed within Section 7.0.7.0 SEISMIC WALKDOWNS AND AREA WALK-BYSThe NTTF 2.3 Seismic Walkdown
: Program, conducted in accordance with the Guidance, involves twoprimary walkdown activities:
Seismic Walkdowns and Area Walk-Bys.
These activities wereconducted at VYNPS by teams of two trained and qualified Seismic Walkdown Engineers (SWEs) (seeSection 4.0). Each team included one engineer with at least several years of experience in seismicdesign and qualification of power plant SSCs. A total of three SWE teams were used. Each walkdownteam 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 Octoberof 2012. Each morning, a pre-job brief with all personnel involved was conducted.
This pre-job briefwas used to outline the components and areas that would be walked down that day, to ensureconsistency between the teams, to reinforce expectations, to identifying potential personnel safetyissues specific to that day, and to allow team members to ask questions and share lessons learned in thefield. The SWE teams brought cameras, tape measures, flashlights and, mirrors, as well as the requiredforms 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 itemson the SWEL (SWEL 1 plus SWEL 2), except for those determined to be inaccessible anddeferred.
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 eachitem. 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 thatwas identified to be inaccessible on these "scouting" walkdowns was a valve covered ininsulation.
After discussion with the Equipment Selection Personnel, the valve was replacedwith another valve in similar environment while ensuring that the overall integrity of the finalSWEL was not compromised.
Prior to performance of the walkdowns, documentation packages were developed thatcontained the pre-filled SWC and other pertinent information including the location
: drawings, response spectra information, previous A-46 and IPEEE seismic walkdown documentation, andanchorage drawings where applicable.
These documentation packages were brought with theSWE teams into the plant during the seismic walkdowns.
Walkdown inspections focused on anchorages and seismic spatial interactions, but alsoincluded inspections for other potentially adverse seismic conditions.
Anchorage, in all cases,was considered to specifically mean anchorage of the component to the structure.
This includedanchor bolts to concrete walls or floors, structural bolts to structural steel and welds to Engineering Report No. VY-RPT-12-00019 Rev. 1Page 22 of 33structural steel or embedded plates. For welds, the walkdown team looked for cracks andcorrosion 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, theattachment 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 oroperational hazards were opened during the walkdown.
This allowed visual observation ofinternal anchorage to the structure (where present),
as well as inspection for "other adverseseismic conditions" related to internal components if it could be observed without breaking theplane 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 requiredconfirmation that the anchorage configuration was consistent with plant documentation.
Of the100 SWEL items inspected, 53 anchorage inspections were conducted and documented whichis greater than the 50% requirement.
When anchorage configuration verification wasconducted, 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 inAttachment C. A total of 100 SWCs are attached; 100 with completion status marked "Y" and0 with completion status marked "N". Therefore, the 100 completed SWCs represent thecompleted 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 SteamTunnel and 5 in the Drywell) deferred to the next refueling outage due to access and ALARAconsiderations.
Seven of these 13 deferred SWEL 1 items will include an anchorage configuration verification.
There were no deferred items for SWEL 2.Area Walk-BysSeismic area walk-bys were performed in accordance with Section 4 of the Guidance for allplant areas containing items on the SWEL (SWEL 1 plus SWEL 2) except for those SWELitems 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 Guidancewas used to document the results of each area walk-by performed.
Photographs were taken ofeach area, and included on the corresponding SWC.Area walk-bys were conducted once for plant areas containing more than one SWEL item. Incases where the room or area containing a component was very large, the extent of the area Engineering Report No. VY-RPT- 12-00019Rev. 1Page 23 of 33encompassed by the area walk-by was limited to a radius of approximately 35 ft. around thesubject equipment.
The extent of the areas included in the area walk-bys is described on theAWC for that area. Because certain areas contained more than one SWEL item, there are fewertotal area walk-bys conducted than seismic walkdowns.
A total of 39 area walk-bys werenecessary 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 AWCsare 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 theDrywell and Steam Tunnel will be completed together with the deferred walkdowns for thoseinaccessible items.7.1.1 The March 2013 walkdown results for the 13 deferred SWEL items are included inAttachment K. There were 3 additional AWCs created for the areas containing the 13deferred 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 toidentify existing
: degraded, non-conforming, or unanalyzed plant conditions with respect to its currentseismic licensing basis. This section summarizes the process used to handle conditions identified, whatconditions 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 theSWC or AWC form and briefly discussed between the two SWEs to agree upon whether it was apotentially 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 wasincluded on the SWC or AWC checklist and the appropriate question was marked "Y", indicating thatno 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) Atotal 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 SeismicWalkdown
: 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 deferredSWEL item walkdowns during RFO 30.8.1 Licensing Basis Evaluations There were no Licensing Basis Evaluations required.
All unusual conditions were entered intothe CAP system immediately and dispositioned for operability, with no operability issuesidentified.
Engineering Report No. VY-RPT- 12-00019Rev. 1Page 24 of 338.2 Corrective Action Program EntriesThe 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 andone 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 paneldoor 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 Askid 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 screwsCondition:
During Fukushima seismic walkdowns in the Reactor Building 252 Elevation, theinspection 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 interiorpanel 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 wasengaged only half the depth of the nut. Requirement:
Full thread engagement of nutCR-VTY-2012-05008:
Nitrogen supply tanks CYL-72-1A and CYL-72-1B have loose nuts on mounting U-boltsCondition:
During Fukushima seismic walkdowns in the Reactor Building 252 Elevation, theinspection 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 ReactorBuilding floor elevation 213'-9",
it was identified that some of the ten anchorage locations havegrout between the bottom of the skid support (channel shaped steel attachment) and the surfaceof the foundation and some do not. Grout is not required under the channel steel per theattached Operability Recommendation.
CR-VTY-2012-5097:
During Fukushima seismic walkdowns in the Control Room, the inspection team noted 4missing panel screws on CRP-9-46 during the area walk-by.
Engineering Report No. VY-RPT-12-00019 Rev. 1Page 25 of 33CR-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 rackwas 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 15cover 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 teamnoted that the ladder support mounted on the south block wall (G-191627-22) is starting to pullaway from the wall.CR-VTY-2012-5371:
During Fukushima seismic walkdowns in the Fuel Pool Cooling Heat Exchanger Room, theinspection team noted poor housekeeping including; ladders stored on the floor that are nottagged per Procedure AP-0019, multiple bags of RAD trash, empty tool bucket, and other outof place small work tools in the room.All above CRs were evaluated immediately for operability and determined to be operable.
AllCRs 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 SeismicWalkdownThis 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.
TheCAs that are initiated ensure that the required Work Orders are properly prioritized andexecuted.
8.3 Plant ChangesThere are no changes required as a result of this effort.
Engineering Report No. VY-RPT- 12-00019Rev. 1Page 26 of 339.0 PEER REVIEWThis section summarizes the process and results of each peer review activity.
9.1 Peer Review ProcessThe peer review for the NTTF Recommendation 2.3 Seismic Walkdowns was performed inaccordance with Section 6 of the Guidance.
The peer review included an evaluation of thefollowing activities:
* review of the selection of the structures,
: systems, and components, (SSCs) that areincluded in the Seismic Walkdown Equipment List (SWEL);" review of a sample of the checklists prepared for the Seismic Walkdowns and areawalk-bys;
* review of licensing basis evaluations and decisions for entering the potentially adverseconditions 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 peerreview 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 Leaderprovided oversight related to the process and technical aspects of the peer review, payingspecial attention to the interface between peer review activities involving different members ofthe peer review team.9.2 Peer Review Results Summary9.2.1 Seismic Walkdown Equipment List Development The selection of items for the SWEL underwent peer review according to the guidance inSection 3 of the Guidance.
The SSCs to be evaluated during the seismic walkdown wereselected as described in Section 6.0. The list of components was provided to the members ofthe peer review team listed in Section 4.5. The peer review members independently providedcomments to the personnel who selected the components.
All comments were addressed andthe peer review team reviewed the changes made to the SWEL and the final SWEL, to ensureall recommendations from the Guidance were met. Specific considerations for the peer reviewprocess 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 ofthe equipment required to perform the following five safety functions, as specified in theGuidance:
* 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. 1Page 27 of 33For 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 safetyfunctions 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 theGuidance, except for cases where there are no Safety Related components at the plant that fallinto that specific equipment class. The list contains major new and replacement items, anditems enhanced based on the IPEEE as well as equipment located in various environments andareas of the plant. All major safety related systems are represented and risk factors wereconsidered in development of the list.For SWEL 2, the peer review team determined that the process to select spent fuel pool relateditems complied with the Guidance.
Portions of the spent fuel pool cooling system at VermontYankee 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 rapiddrain down of the Spent Fuel Pool for Vermont Yankee were identified.
Therefore, SWEL 2does not contain any components associated with potential rapid drain down of the pool. Thepeer review team concluded that the bases for including/excluding items associated with thespent 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 bythe team that prepared the SWELs. The resolutions were reviewed by the peer review team andit was determined that all comments were adequately addressed.
9.2.2 Seismic Walkdowns and Area Walk-BysPeer 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 tonuclear power plants. One of the peer reviewers participated in the seismic walkdown programfor a different utility.
The peer reviews were conducted at the VYNPS concurrent with theconduct of walkdowns, at approximately 50% completion.
The peer review was performed asfollows:The peer review team reviewed the walkdown packages (including checklists, photos,drawings, etc.) for SWEL items already completed to ensure that the checklists werecompleted in accordance with the Guidance.
A total 19 SWC and 11 AWC forms werereviewed, each representing approximately 20% of their respective totals. In thecontext of the Guidance, the peer review team considered the number of walkdownpackages reviewed to be appropriate.
The packages reviewed represent a variety of Engineering Report No. VY-RPT- 12-00019Rev. 1Page 28 of 33equipment types in various plant areas. While reviewing the walkdown
: packages, thepeer reviewers conducted informal interviews of the SWEs and asked clarifying questions to verify that they were conducting walkdowns and area walk-bys inaccordance with the Guidance.
* The peer review team held a meeting with the SWE teams to provide feedback on thewalkdown and walk-by packages reviewed and the informal interviews, and discusspotential modifications to the documentation packages in the context of the Guidance.
* Each peer reviewer accompanied each SWE team into the field and observed themperform a walkdown of a SWEL component and its associated area walk-by.
Duringthese observations, the peer reviewers asked clarifying questions to verify thewalkdown 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. Theassociated area walk-bys performed under the observation of a peer reviewer are listedbelow.* The peer review team held a meeting with the SWE teams to provide feedback on thewalkdown and walk-by observations, and discuss how lessons learned from review ofthe walkdown packages had been incorporated into the walkdown process.As a result of the peer review activities, the SWE teams modified their documentation processto 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 feltthese modifications would be of benefit for future reviews of checklists incorporated into thefinal report. These modifications were recommended following review of the walkdown andarea walk-by packages, and the observation walkdowns and area walk-bys demonstrated thatthe SWEs understood the recommendations and were incorporating them into the walkdownand area walk-by process.
Previously completed checklists were revised to reflect lessonslearned from the peer review process.Based on completion of the walkdown and walk-by peer review activities described, the peerreview team concludes that the SWE teams are familiar with and followed the process forconducting seismic walkdowns and area walk-bys in accordance with the Guidance.
The SWEteams adequately demonstrated their ability to identify potentially adverse seismic conditions such as adverse anchorage, adverse spatial interaction, and other adverse conditions related toanchorage, and perform anchorage configuration verifications, where applicable.
The SWEsalso demonstrated the ability to identify seismically-induced flooding interactions andseismically-induced fire interactions such as the examples described in Section 4 of theGuidance.
The SWEs demonstrated appropriate use of self-checks and peer checks. Theydiscussed their observations with a questioning
: attitude, and documented the results of theseismic 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. 1Page 29 of 33The SWEL items included the following:
: 1. SWEL-1022. SWEL-0793. SWEL-0324. SWEL-0585. SWEL-0596. SWEL-0057. SWEL-0618. SWEL-0629. SWEL-02710. SWEL-06811. SWEL-094/095
: 12. SWEL-00113. SWEL-00414. SWEL-00315. SWEL-020CYI-72-1A N2 cylinderNG-13A CAD SOVRRV-8P-10-1D RHR PumpV-10-65B RHR Bypass valveP-46-1A CS PumpP-8-1C RHRSW PumpV-10-89A RHR Supply MOVP44-lA HPCI PumpTU- 1-1A HPCI TurbineHPCI Instrument RackCRD HCU (Both banks)CV-3-26 (inlet valves)PCV-3-32B MCC-9DIn addition, as the Peer Reviewer walked to the selected SWEL, a survey of the area to therespective 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-014AWC-027AWC-029AWC-030AWC-034AWC-032AWC-007AWC-009AWC-031AWC-003AWC--013In 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. 1Page 30 of 33A 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-BysThe original walk down scope and schedule identified a subset of components thatwere deferred due to inaccessibility at the time of initial walk downs. This deferred listis 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 MainSteam Tunnel (MST). All deferred components were walked down during the Springrefueling outage (RFO 30) that was recently completed when plant conditions allowedaccess to these areas. For the deferred walk downs, the peer reviewer performed areview of all completed seismic walk down checklists (SWCs) and area walk bychecklists (AWCs) for deferred components (refer to Attachment K and L). The peerreviewer also accompanied the Lead Seismic Walkdown Engineer (SWE) into theDW and independently inspected the five (5) deferred items in this area and also thetwo (2) AWCs related to deferred DW equipment inspections.
The peer reviewerconcluded that the SWC and AWC checklists were accurate,
: thorough, and complete.
There were no Licensing Basis Evaluations (LBEs) required to be performed as a resultof the deferred walk down scope.9.2.3 Licensing Basis Evaluations There were no Licensing Basis Evaluations required.
Operability determinations wereperformed as part of the CAP process.The method used to perform Licensing Bases Evaluations (LBEs) for the Vermont Yankeeeffort was more conservative than recommended in the Walkdown Guidance document.
TheGuidance discussed performing an LBE to first determine if a reported condition complies withthe plant licensing bases prior to entering the condition in the plant CAP. Then, if the LBEconcluded the condition was in compliance with plant licensing bases, it would be sodocumented and no further effort would be required.
: Instead, all potentially adverse seismic conditions identified during the walkdowns and AWBswere 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 theCRs.This approach was preferred by Vermont Yankee since it provided immediate notification tothe Main Control Room of all potential adverse impacts.
This was reasonable and justifiable Engineering Report No. VY-RPT-12-00019 Rev. 1Page 31 of 33since the Vermont Yankee CAP requires immediate assessment of potentially adverseconditions for plant operability, which by definition, required review and understanding of thedesign and licensing bases of the subject components.
9.2.4 Submittal ReportThe 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 ofEnclosure 3 to the 50.54(f)
Letter, and documented the NTTF 2.3 Seismic Walkdown programperformed in accordance with the Guidance.
The peer review team provided the results ofreview activities to the SWE team for consideration.
The SWE team satisfactorily addressed allpeer review comments in the final version of the submittal report. The signature of the PeerReview 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- 12-00019Rev. 1Page 32 of 33
 
==10.0 REFERENCES==
 
10.1 10CFR50.54(f)
Letter, Request for Information Pursuant to Title 10 of the Code of FederalRegulations 50.54(f)
Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term TaskForce Review of Insights from the Fukushima Dai-Ichi
: Accident, dated March 12, 201210.2 EPRI 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term TaskForce Recommendation 2.3: Seismic, June 201210.3 Generic Letter No. 88-20, Supplement 4, "Individual Plant Examination of External Events(IPEEE) for Severe Accident Vulnerabilities
-1OCFR50.54(f)",
June 199110.4 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, December200110.6 USNRC NUREG 1407 "Procedural and Submittal Guidance for Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities" June 199110.7 EPRI NP-6041-SL Rev.1, "A Methodology for Assessment of Nuclear Power Plant SeismicMargin (Revision 1)", August 199110.8 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 NuclearPower 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 YankeeNuclear 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 NuclearPower Station License No. DPR-28 (Docket No. 50-271),
IPEEE Staff Evaluation ReportComments" 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 EventsRev. 510.16 Vermont Yankee Letter to NRC, BVY 12-080, dated November 27, 2012, Vermont YankeeNuclear Power Station License No. DPR-28 (Docket No. 50-271),
"Seismic WalkdownReport" Engineering Report No. VY-RPT-12-00019 Rev. 1Page 33 of 3311.0 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 TABLESEISMIC WALKDOWN EQUIPMENT LISTSSEISMIC WALKDOWN CHECKLISTS (SWCs)AREA WALK-BY CHECKLISTS (AWCs)POTENTIALLY ADVERSE SEISMIC CONDITIONS LICENSING BASIS EVALUATION FORMSPEER REVIEW CHECKLIST FOR SWELSEISMIC WALKDOWN ENGINEER TRAINING CERTIFICATES PEER REVIEW COMMENTS FOR SWCs AND AWCsSWELl RISK RANKING PROCESSDEFERRED SEISMIC WALKDOWN CHECKLISTS (SWCs)DEFERRED AREA WALK-BY CHECKLISTS (AWCs)
Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 1 of 2Attachment AAttachment AIPEEE Vulnerabilities Table Engineering Report No. VTY.RPT-12-00019 Rev. 1Page 2 of 2Attachment AATTACHMENT 9.3IPEEE VULNERABILITIES TABLE FORM AND INSTRUCTIONS
* ~ ~ 4 RESA-46 Program outliers.
Complete A-46 program and resolve all outliers.
Modifications designed to IPEEE seismic levels. IPEEE submittal Table 3.4,1defined modifications made for A46 and IPE:EE. Table 3.4.2documented 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 arereferenced within these documents.
Per NRC Letter NVY 01-023. dated March 22, 2001, all A461 IPEEEoutliers described in Table 3.4.2 have been resolved to meet 46criteria and to assure a HCLPF > 0.3g.'1~NRC Letter NVY01-023, datedMarch 22, 2001Condensate Storage Tank (CST) has a HCLPF of 0.25g.To further evaluate for possible modification or upgrade of seismiccapacity, and its associated risk to total COF using PRA methods.YVermont Yankee concluded that no simple cost effective enhancement could be identified that would improve CST seismiccapaciy.Accepted perconclusions presented in NVY01-023, datedMarch 22. 2001Vermont YankeeWork Order 99-011585-000; Complete7/14/2000 V-03Diesel Fire Il=unp Fuel Tank is weak at the tank shell to saddleinterface and potential seismic loads could cause crimping of thefuel supply lubing. Also a potential seismic interaction with anadjacent masonry wall.Tubing will be rerouted to accommodate span flexibility to accountfor seismic displacement of the tank relative to the saddle supports.
Review seismic capacity of the wall.Tubing reroute eliminated the potential crimping concern during aseismic event. The adjacent masonry wall reviewed in comparison the masonry wall sampling that was performed for the IPElEprogram and determined to be enveloped by the seismic capacity ofthe masonry wall evaluated and documented in Table 3.2.4 of theVY IPEEE submittal.
YV-04The support of the fire system northwest standpipe in the ReactorBuilding requires more robust support.Proposed improvements to enhance the support of the fire systemnorthwest standpipe in the Reactor Building.
Vermont Yankee calculation, VYC-2136, documents the design ofenhanced deadweight supports and additional lateral supports forthe Reactor Building northwest standpipe.
yMinorModification (MM) 2000-27implemented themodification; Complete11/21/2000 VnY Accepted perV-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 NVYI 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. 1Page 1 of 24Attachment BAttachment BSeismic Walkdown Equipment List Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 2 of 24Attachment BATTACHMENT 9.4SEISMIC 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 Re&#xfd;iewerDate: 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 similarGIP 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 theoriginal SWEL approval prior to Seismic Walkdowns.
Table 9.4.1. Base ListEngineeing Report No. VTY.RPT-12-00019 Rev. IPeg. 3 of 24Aflaccnrrent BxxxSCREEN1 SCREEN 2 SCREEN3 SCREEN 4SQUG CURRENT UndergoReactivity Pressure Inventory_
neovyJNIE 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 ControlInspections?
Functions O)tside H Systeon?tI 10) (TI H1 0 HCU- CRI/1HYDRAULIC CONTROL UNITS /89) YES NO YES NO I NO X1 21 CRDiNORTH SDV INSTRUMENT VOLUME YES NO YES NO I NO X1 07 LCV-3-33A LCV-3-33A CRDiSCRAM DISCHARGE VOLUME DRAIN VALVE YES NO YES NO I NO X1 07 LCV-3-336 LCV-3-338 CRDiSCRAM DISCHARGE VOLUME DRAIN VALVE YES NO YES NO I NO X1 07 LCV-3-33C LCV-3-33C CRDSCRAM DISCHARGE VOLUME DRAIN VALVE YES NO YES NO I NO X1 07 LCV-3-330 LCV-3-330 CR0iSCRAM DISCHARGE VOLUME DRAIN VALVE YES NO YES NO I NO X1 07 PCV-3-32A PCV-3-32A CR0/SCRAM DISCHARGE VOLUME VENT VALVE YES NO YES NO I NO X1 07 PCV-3-32B PCV-3-32B CR0/SCRAM DISCHARGE VOLUME VENT VALVES YES NO YES NO I NO X1 07 CV-3-12E-CV-3-126-CRDiSCRAM VALVES (9,) INLET YES NO YES NO I NO X1 07 CV-3-1.7-CV-3-127-CRDSCRAM VALVES tI5S OUTLET YES NO YES NO I NO X1 21 CRD/SOUTH SDV INSTRUMENT VOLUME YES NO YES NO I NO X1 06 P-46-1A P.465-A CSi"A COPE SPRAY PUMP YES NO YES NO I NO X1 06 P-,5-tB P-46-1B CSrECORSPAYPUMP YES NO YES NO I NO XI 0SA VI,-llA VI4-11A CS/CS INJECTION MOV YES NO YES NO I NO X1 0SA V14-118 V14-11E CSCS INJECTION MDV YES NO YES NO I NO X1 0EA V14-12A VI 4-12A CS/CS INJECTION MOV YES NO YES NO I NO X1 08A V1.-1'E V14-128 CSCS INJECTION MOV YES NO YES NO I NO X1 0MA V14-26A V14-26A CS/FULL FLOW TEST MOV YES NO YES NO I NO X1 08A V14-26E V1,-266 CS/PULL FLOW TEST MOV YES NO YES NO I NO X1 08A V14-5A VI-5A CSiMIN-FLOW MOV YES NO YES NO I NO X1 03A V14-SB Vi4-SE C./MIN-FLOW MOV YES NO YES NO I NO X1 03A V1&-TA VI4-7A CS/PUMP SUCTION MOV YES NO YES NO I NO X1 08A V14-/B VI -/7B CS/PUMP SUCTION MOV YES NO YES NO I NO X1 21 TK-8.-IA TK-80-1A DG START AIR/AIR RECEIVER TANK A YES NO NO NO YES I NO1 21 TK-58-B1 TK.80-1B DG START AIR/AIR RECEIVER TANK 5 YES NO NO NO YES I NO1 21 TK-8I-IC TK-80-1C DG START AIR/AIR RECEIVER TANK C YES NO NO NO YES I NO1 21 TK.8S-1D TK-80-1D DG START AJR/AJR RECEIVER TANK D YES NO NO NO YES I NO1 18 PS-24-IA PS.24-IA DG START AJR/COMP CONT YES NO NO NO I NO1 18 PS-24-1 PS-24-1 8G START AIPRCOMP CONT YES NO NO NO I NO1 12 C-3.1A C-3-1A DG START AIR/COMPRESSOR A YES NO NO NO I NO1 12 C-3.18 C-3-1B DG START AiRCOMPRESSOR B YES NO NO NO I NO1 SEB AS.24-IA
.S.2,-IA DGSTARTAIR/DGAJRSUPPLY YES NO NO NO I NO1 036 AS-24-tB AS-2.1-lB DG START AIR/DG A R SUPPLY YES NO NO NO I NO1 0SiB AS-24-2A AS-24-2A DG START AIRDGAIR SUPPLY YES NO NO NO I NO1 086 AS-24-28 AS-24-2E DG START AIR/DG AIR SUPPLY YES NO NO NO I NO1 1 PFl-d2-SAP-lA Pt-24-SAP-1A DG START AIR/PRESS BOUND YES NO NO NO I NOI 18 PI-24-SAP-lB PI-24-SAP-lBI DG START AIR/PRESS BOUND YES NO NO NO I r NO1 1l PS-24-APLA-IA PS-24-APLA-IA DOG START AIR/PRESS BOUND YES NO NO NO I NO1 18 PS-24-APLA-1 PS-24-APLA-1B DG START AIR/PRESSBOUND YES NO NO NO I NO1 17 0G-1A DG-IA DIESEL GENERATOR A YES NO NO NO I NO1 17 DOG-B Do-is DIESEL GENERATOR 8 YES NO NO NO I NO1 18 LSH-108-2A LSH-I1082A FUEL OIL/DAY TANK A HIGHIPRESS S YES NO NO NO I NO1 18 LSL-100-3A LEL.108-3A FUEL OIL/DAY TANK A LOW/PRESS B YES NO NO NO I NO1 1 LSH-1--2E LSH-108-2B FUEL OIL/DAY TANK B HIGH/PRESS 5 YES NO NO NO I NO1 18 LSL-1S-38E LSL-108-3B FUEL OILUDAYTANK B LOW/PRESS E YES NO NO NO I NO1 07 LCV-104-2A LCV-108-2A FUEL OILiDAY TANK FILL YES NO NO NO I ND1 07 LCV-108-2E LCVA103-2E FUEL OILDAY TANK FILL YES NO NO NO I NO21 TK-42-IATK-42-IAFUEL OIL/DIESEL OIL DAY TANK AYESNONONO I YES I INOxTK-42-1BNO NO NONO NO NOTK-AS-lA Table 9A4.1- Base List 1Enoneerirtg Reporl No. VTY-RPT-12-00019 Rev. IPage 24Allahmrenl Br I T ~ 1 I .. -eUNITSCREEN11 SCREEN 2 1 SCREEN 3SCREEN4CURRENTEQUIPMENT I SSEL EQUIPMENT ID... EQUIPMENT IDEQUIPMENT DESCRIPTION Seismic1?UndergoRegularConfiguration Inspections?
Maintains atleast one ofthe S safetyFunctions Replacedai IPEEEEnvironment Insidel [igh TampiOutside?
Humidity?
(1/0) 'tH)BoratedSystem?Reactivity Pressure Inventory DecayControl Control Control ReatRemovelNO1 07 LCV-108-3 LC%-I 08-3T TK BOILER TANK RLLNONONONONONONONO-H NO1 14VAC-AVA C-A120 VAC VAC-A VITAL SUBPANEL 100AMPYES III IN 5 I I A I I{] N U&#xa3;% I R WIL YESAC INSTRUMENTATION DISTR PNL 200AMP -&#xfd;O- --&#xfd;-o NOV/IC-1VAC-1lGf-2-IABC-I-IABC-I-I BBC-AS-2120,240V UNINTERRUPTIBLE CVITAILl AC DISTR PNL 225AMP120i,40V VITAL AC MG SET125V DC MAIN STATION BATTERY CHARGER A ON DC-I125V DC MAIN STATION BATTERY CHARGER B ON DC-2125V DC NORMAL BATTERY CHARGER ON BUS DC-2ASYESNONONONO1 &#xb6;-~~~-t------1-----t r-~---t p-I- i--aSC-1-1YESYESYESYESYESNONONONONONONO YES INO NO I1NO16SC-AS-2NONONONONOxx1 16 SC-AS-2-1 1 15 B-AS-21 15 S-I-11 15 B-1-16+1t4&#xfd; OC-3BC-AS-2.1 125V DC ALTERNATE BATTERY CHARGER ON BUS DC-2ASNO5 DC-2ASYESYESYESYESYESNONONONONONONODC-3 1125V DC DISTRPNL DC-3 60AMPNONONONONONO YES INO1 14 DC-I1 14 0C-1C1 14 DC-21 14 0C-2AS1 14 0C-2C1 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.-1125V DC DISTRPNL DC-I 1600AMPc-1 CDC-2DC-2ASDC-2CMCC-DC-2A 125V DC DISTR PNL DC-1C 1WAMPYESNONO I YES IINOINO125V OC INONONONONONO YES II-NONO125V DC MCC OC-ZA 600/AMPYES NOMCC-DC-IA MCC-DC-1B DC-ECCS-A DC-ECCS-B B-UPS-lA125V DC MCC DC-lA (HPCI) 600AMPYES NONO I YES I INOIYES NONONONONONO0NO YES INONONOI is3-UPS-lAJPS-1A BATTERY BANK1YESIisB-UPS-lBIICO-SAmCC-SC11CC-SCVCC-SEB-UPS-1BJPS-lB BATTERY BANKYESNOYESNONONONONONONO YES INONO NO YES I01MCC-BE 480V ESS AC MCC-BE -REACTOR ELDGNONONONONOVCC-SDMCC-9Ds80V ESS AC MCC-SD -REACTOR BLDGYESNO NO YESTOR BLDG (SI)1101 11CC-gB1 01 JMCC-SAMCC-SBMCC-SABUS-8BUS-SBUS-3BUS-4CP;2-2T-8-IA480V 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 (SI4KV -4160V SWITCHGEAR BUS NO.4 1200AMP (SIALTERNATE SHUTDOWN PANELYESYESYES7ESYESYESYESYESYESNONONONONONONONONONONONONONONONONONONONONONONO YES INONONONONONONONO1 031 201 041 041 211 071 07U S-4-8.2-2r-8-1ANONONONONONONO-TNOITRANS 41601480 BUS NO.9YES j NOYES NO#NNONONO0XCV-23m39LCV-23-39 IHPCICOND PUMP TO RWXXXItXIt-t--------
1~ I~~2 --- --I 18 ILS-23-98 LUV-42-41 LS-23-98HPCIiEXHAlPUMT STEAM DRAINVVHPCIIEXHAUST STEAM DRAIN POT LEVEL SWITCH/LSO-23-54' YESYESNONOYESYESNONOX1 08A :V23-21 V23-21 HPCI/FULL FLOW TEST MOV YES NO YES NI N 1NO x X Table 9.4.1- Base List 1Enpnearing Report No. VrY-RPT-12-00019 Re,. 1Page 5 of 24Aglachment 8SCREEN11 SCREEN 2 I SCREEN 3SCREEN4UNITSQUGEQUIPMENT EQU ENTCLASSI 08A IV23-24I1 09 F -IA1 18 DPIS-23&#xfd;7(
18 DPIS23-7&#xfd; 1 0 LSH-25.1SSEL EQUIPMENT IDV23-24--18-IAFN.2.IADPIS-23-76 EQUIPMENT DESCRIPTION HPCliFULL FLOW TEST MOVHPCI/GLAND SEAL CONDENSER HPCI!GLAND SEAL EXHAUSTER Seismic1?YESYESYESYESUndergoRegularConfiguration Inspections?
NONONONOMaintains atleast one ofthe 5 safetyFunctions Replaced?I IPEEEEnvironment Insidel High TempiOutside?
Hamidity?
(liD) (TIH)BoratedSystem,?Reactivity ControlDeacyPressure Inventory HeatControl CorlmRo onContainment YES NOYES NOYES NOYES NOYES NoINOXxXXXxXXHPCI/HIGH STEAM FLOW TRIPDPIS-23-77 HPCI/HIGH STEAM FLOW TRIPYESYESYESYESNONOP.44-1A AHI/HPLI PUI/PPCV-23-50 HIPCOLO COOLINGNONONONONOYES NONOXX1 07 IV23-50Aq23-5DAHPCIhLOiGS COOLINGYESYES NO INO XXI 21E-l9-IA17)17A 1&#xfd;1"&#xfd;2-25
.1 71 18 !FT-23-82 08A V23.19E-IS-IAV23-25V23-17Fr-23-82V23-191 08A IV23-20x 1 18 PS-23-84.1 I MA V23m571 08A V,3-581 08A V23-14I 08A V23-ISx I 08A V23&#xfd;15HPCILUBE OIL COOLERHPCIIMIN-FLOW MOVHPCI/PUMP CST SUCTION MOVHPCI/PUMP DISCHARGE FLOW TRANSMITTER HPCI/PUMP DISCHARGE MOVHPCI/PUMP DISCHARGE MOVHPCI/PUMP SUCTION PRESSURE SWITCHHPCIIPUMP TORUS SUCTION MOVHPCIPUMP TORUS SUCTION MOVHPCIUSTEAM SUPPLY MOVIPCI/STEAM SUPPLY MOVHPCI/STEAM SUPPLY MOVHPCI/TURBINE DRAJNPOTHPCIITURBINE EXHAUST PRESSURE SWITCHHPCOrTUPRINE EXHAUST PRESSURE SW'ICHYESYESYESYESYESNONONONONOYESNONOXYESNONONONONONOX X-- T ~ NOXXYESYESYESYESYESNOYESNOXXNONONONOYES NO INONONONONOX XcOO-tO023-15YESYESYES7ESYESNOYESNO IX xNONONONOSAC-IA1I 10 SAC-IACRHVAC/SAC-1
/CRHVAC/SAC-1/
UNIT/FAN1 I 09 S SAC-B ISAC-1E.,RHVACtCHILLER MASTER UNIT1 I 11 ISCH-25CH-2^,RHVAC/CHILLi R UNITJ~EL109 ITEF-2DO A ROOM VENTILATION]EXHAUST FANUS ITEF7xx109 T3EF-3rTl-.3ILiT FANYESYESYESYESY7ESYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESNONONONONONONONONONONONONONONONONONONONONONOYESYESYESYESNONONONONONONONONONONONONONONONONONONONONONONO INO INONO INO INo INONONO INONONO INO INO INO INO INO INO ITNONONONONONONONONONONONO.1 -1 10 RRU-5x XNONONONONONONORRUOR COCT-3-231A111111 ILT-3-231A 3W/ECCS RM COOLING_RD/SDV LEVEL TRANStR0/SDV LEVEL TRANStR (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)NONONONONOI NO INONOIS~~~ ~~~ 3 GIS LT-T&#xfd;!P 11 3-2118I PT2S -2 JPT-2 52CNO NO I NOYES NO I I NO Table 9.4.1- Base List 1Engneering Report No. VTY-RPT-12-00019 Reo. IPage 6 of 24Atahnhent BSCREENI SCREEN 2 SCREEN 3SCREEN4____ t 4 ~-e---. -UNIISOUGSOG CURRENTEQUIPMENT EQUIPMENT IDCLASSSSEL EQUIPMENT IDEQUIPMENT DESCRIPTION Seismic1?UndergoRegularConfiguration Inspections?
Maintains atleast one ofthe 5 safetyFunctions Replacedl Ip=EEEnvironment Insidel High TempiOutside?
Humidty?(110) Ir/H)BoratedSystma?DecayReactivity Pressure Inventory HeatControl Control Conrol0 ~Remoinal Containment I .~ 0 1 I-~---t4--i f.....~...-j I --1 1 18 PT-2-3-52D PT-2-3-520 CS. IYESNOYESNONOxLT-1IYESNONONONONOYESNOHNOX1 18s IT-Olt ItT106S~
IDW PRESSURE ECCSYESNONONONONONONONONOHNONONONONOx1 1I PT.-0 I0tCPT-I11 0 COW PRESSURE ECCSYESIPT.I0-10tD YESNOINONONONONONONONONON17ONONONONONONONONONONO18 PT-5-128P'T-5-12B I YES1 18 IPT-5-12C 1 13 PT-5-1201 19 7E.1&1--30A 1 ' 9 !TE-16-196308 1 20 TIA6.19-308 PrT-5-t2C YESPT-5-1YESYESYESYESYESNONONONONONONONO1"-1-6-19-308 OW TEMP. IND.NONONONONOTNONONONONO1 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 BP5-23-A SCP5S-23-550 aBSt2-12DW TEMP. FHPCI/PCIS CHPCI!PCIS CHPCI/PCIS CHPCIIPCIS CYESYESYESYESYESNONONONONOYESxXYESNONONONONONONONONONOxX1 1 8PS-2-128B R INTERLOCK aPS-2-128A
'S-2-t 28A:T-2-11 OA'T2. 11 SC:T.2.1100 R IIYESYESYESYESYESNONO1 t8 FT-2-1 IOCNONONONONONONONOYESNONONONONONONONONO1 I 18 IFT.2-1100 REACTOR RECIRC FLOW FOR RPSl 1 18 1LT.2-3 2AT.2.3-72A RV LEVEL FOR RHR. DGO HPCI, RCIC, ADS, CSRV LEVEL FOR RHR. DG. HPCI. RCIC, ADS, CSRV LEVEL FOR RHR. DG, HPCI. RCIC, ADS. CSRV LEVEL FOR RHR, QG. HPCI. RCIC. ADS. CSRV LEVEL SCRAM & PCISYESYESYESYESYESNONONONOI118 ILT-2-3-57A 1 18 ILT-2-3-57B 1120 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 6Aat. 2-3-5166aT..53- 56 -IT-2.3-560
'T-2-3-55A IT-4,2155A IT-23-355C RV LEVEL SCRAM & PCISRV LEVEL SCRAM & PEESRV LEVEL SCRAM & PCISRV PRESS. IND.RV PRESS. IND.RV PRESSURE ECCSRV PRESSURE ECCSRV PRESSURE ECCSRV PRESSURE ECCSRV PRESSURE SCRAMRV PRESSURE SCRAMYESYESYESYESYESYESYESYESYESYESYESYESNONONONONONONONONONONONOYESYESYESYESYESYESYESNONONONONONONONONONONONONONONONONONONONONONONONONONONONONONONONO-NONONONONONONONONONONONONONONOxxNOxxjYES j NOIRV WTR LEVEL IND., 3-91E RV WTR LEVEL IND.YES NONONO---- a~...a ______ J .L...~.O......-I.
____ L.....L ______ L-..--O.--L
_____ L ____ll].;,*b3p,tJn3A YES NO NO NONO-i TRble 9.4.1- Base List 1Engneering Report No. VIY-RPT-12-00019 Rea. IPage 7 0A 24AgOchmerr Br I r t,-r~~r-----------I T --- V T 7 r1SCREEN11 SCREEN 2 1 SCREEN 3SCREEN4UNITSQUG CURRENTEQUPMNEQUIPMENT 1OCLASSSSEL EQUIPMENT IDEQUIPMENT DESCRIPTION Seismic1?UndergoRegularConfiguration Inspections?
Maintains atleast on0 ofthe 5 safetyFunctions ReplacedP IPEEEEnvironment InsideI High TempiOutside?
Humidity?
(1IO) (T I H)BoratedSyst em?S In r DecayReactii~tp Pressure iInventory HeetControl Cotral Con Re eatContainment 118 IPS-104-538 PS-1 04-538SWITCH1118PS-104-53C PS-1 04-53CP1.I1-19-36A PI-16-19-368
-YES NOYES NOYES NOYES NOYES NONONONONONONONONONONOHNO-16-19-368 TORUS PRESSURE INDICATION NO1- -,-~-~--118 PTisPT-16-9.36A PT-i 5-1 D-36ATOUSU PRESURE INC[;YES NONONO1 t1 PT-16-19.368 IJPT-&#xfd;1-9-3118 TORUS PRESSURE INCNONO NO INONONONONOTORUS WTR. LEVELI YES I NO118 ILT-16-19-10E LT-IP6-1.5110E R. LEVELYES NONONONO1 20 LI-PI-16-19-12 ILI.PI.16-19-12I 1 9 TE-16-19-33C TE-1619 33C1 2C TI-16-19-33A T1IF t6-1-33A1 20 TI-16-10-33C T 16-19-33C 1 08A V2-74 V2-7,U,YES NONONONONOYESNONONONONONO ------ --NONOMAIN STEAIWDRAIN VALVE MOVYESNOTNOX1 1 08A IV2-77V2.77E MOVV2-SCAYESYESYESYESYESNONONONONOYESNONONONONONOXMAIN STEAM/lNBOARD MSIVYESNOX1I 21 1S-2-SAS.-25AMAIN STEAM/INBOARD MSIV NITROGEN SUPPLY ACCUMULATOR YESNOYESNOTNOX1 21 S-2-5B S-2-sE MAIN STEAM1ANEOARD MSIV NITROGEN SUPPLY ACCUMULATOR YES [ NO YES NO I T NO X1 1 21 IS-2-SCS-2-SCMAIN STEAMANBOARD MSEV NITROGEN SUPPLY ACCUMULATOR YESNOYESNOTNOX11 21 jS-2-5D11 07 IVU-6ADI MAIN STEAM/INBOARD MSIV NITROGEN SUPPLY ACCUMULATOR YES NO YES NO I T NO XA'MAIN STEAM/OUTBOARD MSIVYESNOYESNOTNOx1 07 IV2.86EV2-.66YESNOYESNOTNOX1 j 07 IV2C-6C JV2C-6CA/CIS-2-ScAm,xxMAIN STEAM'RELIEF VALVEYESNOYES NOTNOX1 I 07 IRV-2-710 RV-2-710MAIN STEAM;RELIEF VALVEYESNOYESNO1 O S 6E-o0C-3E-1000-3TK-55.IAPCV-1.15S-2-13AS-2-13EMAKE-NONONONONONOXX7XXSAFETY RELIEF VALVE/NITROGEN SUPPLY ACCUMULATOR YES NO YES NOT1 21 &S2-13BSAFETY RELIEF VALVEINITROGEN SUPPLY ACCUMULATOR YESNOYESNONOx1I 21 S-2-13CS-2-t 3CS-C-I1CO"-1D.1AV10-26ASAFETY RELIIYESYESYESYESYESNONONONONOYESYESYESYESYESNONONONOTNO XORHR/E RHR HEAT EXCHANGER NOX1 MA IVIO-26A1 1 8A VIt 0..26C EVI-26TSPRAY MOV YES NO YES NO I NO xSPRAY MOV YES NO YES NO I NO X Table 9.4.1- Base List 1Enpneenng Report No. VTY.RPT-12-00019 Rev. IPage 8 of 24Afchrroent BI -r t ~ 0 T -TSCREEN1I SCREEN2 1 SCREEN3SCREEN4____ + + r-.UNITSQIJG CURRENTEQ~tMNEQUIPMENT IDCLASSSSEL EQUIPMENT IDEQUIPMENT DESCRIPTION Undergo Maintains atSeismic Regular least one of1? Configuration the 5 afeatyInspections?
Functions IPEEEEnvironment Inside) High Temp/Outside?
Humoidity?
(110) TrIH)BoratedSystem?Reactivity Pressre Inventory DecayCent Containment oy "ureConrolRemovel
_______ _____ ______xx08OA JV1031ANI 08A V 1031 a1 06 P-IS-ICI 01A VIO-65A1 08A 0l-656VIO-31AYESNOYES I NONO0-316YESYESYESYESYESNONONONONOYESNONOXXYESIVI0-658 RHRIHEAT XC BYPASS MOVNONONONONONONONONONO1 08A V I-27AXV1 0-27ARHRLPCI INJECTION MOVXXXXV10-278LI10-16AJIO-15AVIO-15CYESNOYESI 0UANONONONONOYESYESYESYESYESNONONONONONONONONONO1 rSAVto-f C[RHRIRECIRC SUCTION MOV-1 YESx7XXI 2SA V10-158 VI-tU580SA VU-1so VIt0-150U 08A VIU-34A V10-34A1 08A VIt-348 Vt1-3461 08A V1D-39A VIG-39A1 0A V1D-398 VII-3981 08A VID-38A V1U-38A1 03A VtU-38B VIO-336I 08A VIt-13A VIt-13A1 U8A VI-130 1 VIU-13007 PCV-1U.-69A PC'V'.tU0,6A I .a7 PCV,-104-696 IPCV-104-696 1 06 P,.8-1A >,,8-1A1 06 P,.8-1B P-8-1 61 00 jP-f&#xfd;lC P-8-1tC1-L 06 1P.8.1D [P-6-1DYESYESYESYESYESYESNONONONONOYESNONONO IRHR(TORUS COOLING MOVNONONONONOXx7x7XSG MOVYESYESYESYESYESYESNONONONONOYESNOYESYESYESNONONONONONONONONONONONOE CONTROL VALVEXSXE CONTROL VALVEYESNOYVESNOxYESYESYESYESYESNONONONORHRSWD RHRSW PUMPNOYESX7Lx71 1 088VIO-89A/1 O-S9AYESNONOLYESNONONONONOYESNONONONO-NONOI H NOUS P-7-1ASW/A SW PUMPYES--.......-
S -.-~1 1 f 07 IFV-104-17A F.7- I O4-17A'SW/A TRAU-VE:LLIING3 SCREEIN CO N VALVE:YESNO I H NON-1-ISIYESYESYESYESYESNONONONONONONONONONONONO I H NOH NO1 1 07 IFCV-104-17C FCV-104-17C
_L DC P-7-1D [P-7-1D1 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.67-1A1 21 TK-67-il.
TK-67-1 SSWID SW PUMPSW/D TRAVELLING SCREENSWIDG COOLINGSWIDG COOLINGSW/OG-A EXPANSION TrANKSW/DG-B EXPANSION TANKIL VALVEYESYESYESYESYESYESNONO0H NONONONONONONONONONONONONONONONONOI 07FCV-10t-17E IFCV-*04-17E LING SCREEN CONTROL VALVENOH NONOYES NOYES NOYES NOYES NOYES NO1 11210-3-1B G--1IBDG START A3 MOTORNO I NONO1 [I p 1AJ I I pJ WJI" I L I 77- --5 YES NO Tgble 9.4.1- BFse List 1Engineervg Report No. VTY-RPT-12-O0019 Rev. 1Page 9 of 24AN1,hment BSCREEN1 SCREEN 2 1 SCREEN 3SCREEN4SOUG CURRENTUNIT EQUIPMENT SSEL EQUIPMENT IDEQUIPMENT ICCLASSEQUIPMENT DESCRIPTION HPCliAUX OIL PUMPHPCICOND DRAIN TO CONDHPCI'CONDENSATE PUMPSeismnic1?UndergoRegularConfiguration Inspections?
Maintains atleant ene ofthe 5 safetyFunctions Replaced?
IPEEEEnvironment Inside/ High Tempi BtratedOutaide?
Hmidity?
System?(1/0) (T I HI mReoctivity Pressure Inventory ecatControl Control Control HeatI I ReMOvaContainment 1 05p-.NOYES NOI I NOX x1A11-1ArU-- 1IAHPCIHPCI TURBINEYES NONOx1 071dPC ITUI1 07CRHVAC/LOW AMBIENT TEMP CONCRHVACILOW AMBIENT TEMP CONCRHVAC/SAC-1A COOLING COILCRHVACISAC-1A FILTER SECTIONYESYESYESYESYESYESYESYESNOYES NONOxNONONONONONONOYES NONO NONO _ NO_NO NNOXNO1CRHVAC/SAC-1A HEATING COILDG ROOM VENTILATIONIDG ROCNONO11 01 01 10DG-A-INTAKE POS.113-20 11Pos1 13-20XXXDG-IE-INTAKE-X RRUL5 FANRRU-5 MOTORRRUB AFANG--IA4NTAKE LOUVERYESNOjEOS-1 13-2011-IRRU S MOTORNOYES NO NO INO I I I I I NO INONOOTAL) YESNONONONOTN-NONONONONONONO:kRU-, FAN1 10SWJRR U-5 MOTORSWfRRU-6 FANSW!RRU-6 MOTOR FANSWiRRU-7 MOTORSWRRU-8 FANYESNO NOYES1 10 RRU-8 MOTOR RRU-8 MOTOR1 06 P.8-1A COOL COIL F-8-lA COOL COIL1 06 P-8.1B COOL COIL P-8-18 COOL COIL1 06 P.8-tC COOL COIL P-0-1C COOL COIL1 06 P-S-1D COOL COIL P-81-D COOL COIL1 088 SE-3,31A SE-3-31A1 088 SE-34318 E.-3-3181 08E SO-3-117-XX-XX SO-3-117-XX-XX 1 088 SO-3-118-XX-XX SO1 -X-XX-X1 085 LSO-108-2A LSO6-10-2A 1 088 LSO-108-2B LSO-108-2E SWIRRU-8 MOTORYESYESYESYESYESYESYESYESYESYESYESRHRSWIP-8-1D MOTOR COOLING COILCRD/SCRAM DISCHARGE VOLUME VENTIDRAIN SOVFUEL OIIjDG DAY TK FILLFUEL OILIDG DAY TK FILLFUEL OILIHEAT BOILER TKNONONONONONONONONONONONONONONONONONONONONONONONONONONONO NOYES NO IIIYES NO IYES NO IYES NO INO NO INO NO INO NO IYES NO INO NOYES NOYES NONONONONONONONONONONONONONONONONONONONONONONONONONONONOX iX11 08B ILSO-108-3 1 088 SE-25-5I 08B LSO-23-5d 1 20 FIC-23-108 20 F623,008m!
1 088 LSO&#xfd;23-40 SO-108-3:1-23-10?,I HPCI FLOW CONHPCI FLOW INDqPCI GOS. CONDYESYESYESYESYESYESYESYESYES____ YES____ YESYES11 088 ILSO-23-39 ILSO-25-39
_HYES NOYES NOYES NOYES NOYES NOYES NOYES NOYES NOXxx7x7x SXSXX7XXXXXX7X1 1 08B 1ISE-3-15-,23-94 IHPCIlDCIAC INVERTERiE-23-tI 1 0 ITS23-101A
-TSr23-101A HPCIlREMOTE TURBINE TRIPHPCI/STEAM LEAK DETECTORHPCI,STEAM LEAK DETECTORHPCIiSTEAM LEAK DETECTORHPCItSTEAM LEAK DETECTORT3-1010iTS-23-1 6BDI-WO [501-1JOB rlIIOIAM NAKUICUUM YS INO3-1028T.-23-1028
'HF'CISTEAM LEAK DETECTORYESI NO I Engineering Report No. VIY-RPr-12-O0019 Rev, Ipage 1l0of 24Allaonmerd BUNIISQUGEQUIPMENT CLASSSCREEN1I SCREEN 2 1 SCREEN 3-I4 n-CURN SSEL EQUIPMENT IDEQUIPMENT IGEQUIPMENT DESCRIPTION Seismnic1?UndergoRegularConfiguration Inspections?
Maintains atleast One Ofthe 8 safetyFunctions IPEEESCREEN4Environment Insidel High TempiOutside?
Humidity?
(I/O) ( /H)BoratedSystemnReactivity Pressure Inventory Control Control Control1 IOITS 102A ITS.23.102A 4 -- 4--11t-&#xfd;Alvl LEAK DETECTORYES NOYESNO INOXxxxAM IYES NOYESNO ITNOXXNOYESTS-23-103B IHPCI/STEAM LEAK DETECTORNONONONONONONONONONOX X0 ITS-23-103C TS--1A03C HPCI/STEAM LEAK DETECTORYESNO1 1 0 17S-23-1030 ITS-2a-1030
<DETECTOR
,1 04AYESYESYESYESYESYESNOYESXXNONONONONOYESYESYESYESYESNONONONONOTNONONONONOXX1TS-.23-O4D HPCI,STEAM LEAK DETECTORCSTILEVEL SWITCHES1 20SL-10/-SA LSL-107-SA S1 20TULEVEL IYESNOYESNONOXNOsE.2-s 08.1INBOARD MSIV SOLENOID AC/DCYESYESYESYESYESNONONONONONONONONONOI x1 8OE ISE-2450.-r SE-2-80C-I 1 08E ISE-2-80D-1 SE-2-8SM-1 NBOARD MSIV SOLENOID ACIDCINBOARD MSIV SOLENOID AC/DCRECIRCiSAMPLE LINE INBOARD ISOLA'RECIRC/SAMPLE LINE OUTBOARD ISOlMS SAFETY/RELIEF VALVE SOLENOIDMS SAFETY/REUEF VALVE SOLENOIDYES NOYES NOTXNOYESYESYESYESYESNONONONONOTTTTNONONONONOxxxxx088SE-2-71BYES NO1 0853E.2-71C1 088 SE-2-71 D1 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 C96-2-7IDSE-2-86A-I SE-2-866-1 SE.2-tt C-iSE-2-86D-1 FCV-IO-160 FSO-11 0-180F60.104-1/A FDO-l0.1 lBFSO-t54-1
/0MS 0YESNOYESYESYESYESYESYESMSIOUTBOARD MSIV SOLENOID AC/DCSWiB TRAVELLING SCREEN FLOW SOLENOID FCV-104-17B 108E 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 SOLENCCAC SOV AIR ISOLATION (INBD) INJECTION 1-17C-1 7DYESYESYESYESYESYESYESYESYESYESNONONONONONONONONONONONONONONONONONONONONONONONDNONOYESYES NOYES N3YES NO 1NOTTTTTHHHHHNONONONONONONOXxXNONONOxNO NOY1 1 0881 08BFSO.104.17E 1I1 088E NG-12BFSO-104-28B FSO-104-1IE NO-lOBVG-22AVG-22BNO-1AFL-17ES PNL BNONONONONONONONONONONONONONONONOICAD SOV AIR ISOLATION (OUTED) COMPR DISCHARGE PNL AYES NOYES NOYES NOYES NOYES NOYES NOYES NOSxxxxxxx085 NG-13ACAD SOV AIR ISOLATION (INBD) INJICAD SOV AIR ISOLATION (INBD) INJITO DW PNL ASTO DW PNL 8I 088 ING-13B ING-138YESYESYESYESYESYES Table 9.4.1- Base List 1Erlgineering Report No. VIY-RPT-12-00019 Rev. IPage 11 of 24Attachmnent BI 7 r ,~e -*eSCREEN1 SCREEN 2 SCREEN 3SCREEN4-t + +r -UNITQSO2U" CURRENTEQUIPMENTEQUIPMENT IDCLASSSSEL EQUIPMENT IDEQUIPMENT DESCRIPTION Undergo Maintains atSeismic Regular least one of1? Configuration the 5 safetyInspections?
Functions Replaced7l IPEEEEnLironment Inside/ High TempiOutside?
Humidity?
(110) (TIH)BoratedSystem?DecayReuctivity Pressure Inenltcry Heat Containment Control Control Control ReRemoval___ ___ -- -t -- t--t-t---t 1-1 t ~ -t --S 081E FSO-109.75A4 FSO-109-75A-4 1 LISE VG-SE VG.5I 08B VI-. A VT-,A1 08B FSO-109.76A PSO-10S-75A 1 088 FSO-109-765 PSO-109-76E E ISOLATION YESNOYESNONOIYESNONONONONOYESYESYESYESYESNONONONONONONONONONOxSAMPLE SYSTEM ISOLATION (OUTED) CAM RETURN TO TORUS YESxXXXX1 07 V20-94V20-94DRYWELL EQUIPMENT DRAINS ISOLATION (INBD)AOV YESDRYWELL I)AOVYESYESYESYESYESNONONONONOYESYESYESYESYESYESNONONONONONONOx107 IV72-38A-V72-33ACAC SUCTION AOVxxKx107 IV72-368V72-388CAC SUCTION AOV156-11q (INED)YESNONO-NOI 07SE-"YESYESYESYESNONONONONONONONONONOX1 07FCV-2-39;CV-2-391 07 FCV-2-40CCV-2.40RECIRCiSAMPLE 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 NOxXKX-XYESNO-- NO1YESYESYESYESYESNONONONONONONONONONO107 ISE-16-19-68 KXKKXI 07 SE-1.-19-9 55-I 9-IS-S,IR PURGE)AOVYES NOVi&-20-22A YESYESYESYESNO1YESYESYESYESYESNONO I NONO1 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 ,V70-117I 08A V13-1b V13-151 08A V13-16 V13-1S1 OaA V10-57 V`I -571 O8A Vyb-66 V1 0-.6I 08A V10-17 V1;-171 08A Vi1-IS V10-181 0A V12-15 V1t-151 08A V12-18 V12-1I1 211 0 VV-SNA v2-g6A1 0 V2.-7A V2-27A1 0 V2-28A V'2-28AYESNONO I I I INON2 PURGE SUPPLY ISOLATION (OUTED) AOVYES NODN(OUTBO)AOV YES NOON(OUTBD)AOV YES NOYES NOYESYESYESYESYESYESYESYESNONONONONONOKxNONONONONONONOXRCICJSTEAM SUPPLY MOVIYES"'. I-4 .. .:U Vq 1LV-. -XvRHRXMOV TO RWRHRJMOV TO RWRHR/SDC VALVERHRJSDC VALVEYESNO4YES NOYES NfYES NOYES NOCYES 0NOYESNONOx INO I NOxYES NO I T NOYESNONOYESYESYESYESYESYESYESNONONONONONONONO XxFDW/INSOARD CHECK VALVEYES NOYES NO1I0 V2-20EIi TNONOiRAYES I NOKXNO -is DOPT-2-116D DPT.2-1160 IlSISTEAM DIFF PRESSURE TRANSMITTER AYES Table 9.4,1- Base List 1Engneering Rupod No. VTY-RPT-12-00019 Rev. 1Page 12 of 24Attnhmerd BSCREEN11 SCREEN 2 SCREEN 3SCREEN4UNITCURRENTEQUIMNEU E EQUIPMENT 10CLASSSSEL EQUIPMENT IDEQUIPMENT DESCRIPTION Seismic1?UndergoRegularConfiguration Inspections?
Maintains atleast one ofthe 5 safetyFunctions YESYESYESReplaced?j IPEEEEnvironment Inside./
High T!mplOutside?
Humidity?
(110) I I/H)BeratedSystem?NONOI I DecayReactivity Pressure Inventory HeatControl Control Control Removal1 18 OPT-2-117A DPT-2-117A 1 18 DPT-2.117C OPT-2-1178 1 18 0PT-2-117C DPT&#xfd;-2117C 1 18 OPT-2-117C DPT.2-1t7D 1 18 OPT-2-118A DPT.2-11I AI _i8 OPT-2-11813 OPI"-.-11I8a 1 M8 0PT-2-118C DPT.2-11I8C B YES NOB YES NOContainment xXxxYESNONOIYESNONONONONOYESYESYESYESYESNONONONONONO118 DPT-2-118D DPT-2-t OPT-2m-1 19AVpT-T-115E9 DPT-2wl iSCOPT-2.t119D V70013IMSJSTEAM 0lFF PRESSURE TRANSMITTER CMSISTEAM DIFF PRESSURE TRANSMITTER CMSISTEAM DIFF PRESSURE TRANSMITTER 0MSISTEAM DIFF PRESSURE TRANSMITTER DMSISTEAM D0FF PRESSURE TRANSMITTER DMSJSTEAM 01FF PRESSURE TRANSMITTER DRBCCWiRC ISOLATION CHECK VALVEYESNOIxxxxxYESYESYESYESYESNOYESNONONONONONO1 1 18 I DPT-2-1190 YESYESYESYESNONONONONONONONONONO1 0xV70- 1.1xxx_xxPS-13-ITA PS-1.3-37A PS-13-81C P.1-1-870)
TS-13-79A RCIC/LOW 8YESYESYESYESYESYE-SNONONONONONOYESYESYESNONONONONONO1 1 0 ITS-I3-79A 1 0 ITS-13mBOA 2 imilE2:21 l, I 11ZA_1 0 IFI.104.,DA_
1 0 FI-10&#xfd;7013 TS-13-80A TS.13-81A TS-13-82A PI-104-7 TAPI-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 NOxX_xXxYESYESYESYESYESNOYESNOTNONO YESNONONONONONONONONONOx1x1 Iffli""1 0 IFI-104-IOC 1 0_L _03A &#xfd;,naI 08A IVIO-1831 0 lFm24-16FI.104-70C RHRSWJPUMP C COOLIR FLOW INDICATOR NOFI-1T4-7TO 1/10-133LP. lAH-IMP 0 COOLIR FLCYESYESYESYESYESNOYESNO YESNONONONONONOX1 I 14 ILP-IAHDG "A" LIGHTING PNLNO IT-LP1A1-H
&#xfd;P-IAJT-LP.IAJAC-OP-S771-LRP-.9AR FOR LP-1AH DG "A"YESNONONO1 14 AC-OP.S1 14 LP.IL1 14 PP.gA1 14 CP-82-11 14 CP-82.31 20 CRP 9031 2) CRP 9-041 20 CRP 9M51 20 CRP 9.061 20 CRP 9-071 20 CRP 90aI 20 CRP 9-101 20 CRP 9-121 20 CRP 9-141 20 CRP 9-15I 20 CRP 9.171 20: ORP9Ei11 20 CRP 9-20LIGHTING PNL-I20V AC240;12 TAC POWER PANEL AT MCC-9A FOR SEGTALTERNATE SHUTDOWN PANELALTERNATE SHUTDOWN PANELCONTROL ROOM PANELCONTROL ROOM PANELCONTROL ROOM PANELCONTROL ROOM PANELYESYESYESYESYESYESYESYESYESYESYESNONONONONONONONONONONONONONONONONONONO INONONONONONONONONONO NO^RP 9-01^RP 9-07;RP 9-08TRP 9-10-RP 9-12TRP 9-14^RP 9-15TRP 9-17TAP 9-laTRP 9-20NONONO NO NONONONONONONONONONOCONTROL ROOM PANELCONTROLI"_L_YESYESIYESNONONONONONONO NOCONTROL ROOM PANEL,ONTROL ROOM PANEL Table 9.4.1- Base ListEngineenng Report No. VTY-RPT-12-00019 RPe .IPage 13 of 24Alachment 8SCREENI SCREEN 2 SCREEN 3 SCREEN4SQUG CURRENT Undergo Maintains at Environment Rea tory DecayUNIT 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?
RemovalInspections?
Functions (I a O) (iT y H) System?1 20 CRP 9.22 CRP 9-22 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9-25 CRP 9.25 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9.26 CRP 9-26 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9-27 CRP 9-27 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9-30 CRP 9-30 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9-32 CRP 9.32 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9.33 CRP 9-33 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9.39 CRP 9-39 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9.41 CRP 9-41 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9-42 CRP 9-42 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9.45 CRP 9.45 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9-46 CRP 9.46 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CRP 9-L47 CRP 9-47 CONTROL ROOM PANEL YES NO NO NO I NO1 20 CAI PNL A CAD PNL A CONTROL ROOM PANEL YES NO NO NO I NO1 20 CAD PNL B CAD PNL E CONTROL ROOM PANEL YES NO NO NO I NO1 20 PPP-A-1 PPP.A.I RPS PVAR PROTECTION PNL PNL A-1 YES NO YES NO I NO X1 20 PPP-A-2 PPP-A.2 RPS PWR PROTECTION PNL PNL A-2 YES NO YES NO I NO X1 20 PPPR-B- PPP.B.1 RPS PWR PROTECTION PNL PNL B-I YES NO YES NO I NO X1 20 PPP-E-2 PPP-B-2 RPS PWR PROTECTION PNL PNL-B-2 YES NO YES NO I NO X1 20 DOG VOLT REQ CAB DO RMS VOLTAGE REGULATOR CAB YES NO NO NO YES I NO1 20 NEUTRAL TRANSCAB DRMANEUTRAL TRANSFORMER CAB YES NO NO NO YES I NO11112020201718CONTBOARD
)G RM A CONTROL BOARDYESYESYESYESYESNONONONONONONONONONONONONONONOYESNOO.SL.10B-13A ILSL-108-13A DIESEL FUEL OIL TRANSFER PUMP STARTNOI19SL-100-13B LSL-108-13A DIESEL FUEL OIL 13-12ALSVI-108-12A L OILYESYESYESYESYESNONONONONONONONONONONONONO18 ILSH-23-90
-PCIIMS COND DRAIN POT LCV-23-53 CONTROLYES I NO Ixx1089181118IS;SO-10-161 FSO-10-t61 RHRISYS PROCESS SAMPLE-S-2-I w4PS-2-134A JIS LINE PRESSYESYESYESYESYESNOYES NOYESI NO IJINONONONONOxx.S-2-.4S LINE PRESSNO YES NOIC18'S-2-1 IAPS-2-t1A1 18 1 PS-2-1 16 fps-2-ils 1 18 PS-2-1 I C PS-2-11C1 18 PS-2mi 10 P&2w!!D18 PSwi0w1D5A PS-10-1175A 1 18 PS-10-IDBB PSi0wi05S 1 18 PS-10-105C
-PS-10-105C ONDENSER VACUUM.ONDENSER VACUUM3ONDENSER VACUUM3ONDENSER VACUUMkHR PP A DISCH PRESS INTERLOCK OHR PP B DISCH PRESS INTERLOCK YESNOYES NONOXYESYESYESYESYESNONONONONO0YES NONOXYES NONOxDISCH F1 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 YESYESYESYESYESNOYES NONO YES NONONONONONOxxxx1NO YES NO I118 IPS-1AG10-SH PSI.-109i HR PP D DISCH PRYESNOYES NONO1 1 08B j S E.1-9A 99-1-129-SB SB-9 SOV1 08B ISE-1-15g SEI12,9 EB- SOVY___IY B YS I NO YES JNNO YEIO________
__YES__ I_ _ I _ NO_ YESNxx Table 9.4.1- Base ListEngneering Report No. VTY-RPT-12-00019 Re,. IPage 14 of 24Airachmerd Br.-z-tzr,
--a * --, , -SQUGUNITI EQUIPMENT CLASSCURRENTEQUIPMENT IDSCREEN11 SCREEN 2 I SCREEN 3t 4-, -SCREEN4SSEL EQUIPMENT IDEQUIPMENT DESCRIPTION Seismic17UndergoRegularConfiguration Inspections?
Maintains atleast one ofthe 5 safetyFunctions IPEEEReplaced.
Environment Inside! High Temp)Outside?
Humidity?
(1IO) (TIH)eoratedSystem.Reactivity Pressure Inventory Hecaty otimnControl Control Control e Continment Control RemovalSE-tSB&#xfd;9 SOVYEOYESYESYESYESNOYESNONOXNOUSB ISE.1-125.iOC I SE-. 1251kC ISE-I0SsOy YESYESYESYESYESNONONONONONONONONOTNOxxI USE ISE'1-125.1 1ASE- '1 ,1 1 ASBEI1 SOVNOXxXXSE-t-t 25-118I USESE-I-1I DB3SE-1-125-12C ISE.1-125-120 SB-1I SOVSB-I SOVSBA-2 SOVSBE-2 SOVSBE 12 SOVRWCU/FLOW TRANSMITTER RWCU/FLOW TRANSMITTER TORUS VACUUM W CONTROLTORUS VACUUM W CONTROLTEF-2 DG EXH FAN CONTROLSYESYESYESYESYESNOYESNONONONONONOINOYESNOINOX1 18 JFT.12-IA 1 18 FT-12-IS1 18 OPIS-16-1!
1 18 OPIS.16-v
^10 B-1093FT-I12-IA NO YESYESYESYESYESYESNOYESNOX-NOE-1098YESYESNONONONONONONO7-NTONONONONONOXX20 E6-1099B.1099rEF-2 DG EXH FAN CONTROLSNOBA 100B-1101B-I92B-1052TEF-3 DO EXH FYESNO20 IsmiUS?105MCC-SC LNONONONONONONOYESYESNONONONONONONONONONORWCUIHI TEMP ISOL SYS TB BOXYES 1B5-106013-i 0618-10625-I1013s-tU0.:LIYESYESRWCUVNONONONONOYESYESYESYESYESNONONONONO-NO01 0B-1064XRWCU/HI TEMP ISOL SYS TE BOXYES INONONONONOXB-1065B-1066HVSGP-AHVSGP-BHVFRP-AHVAC PNL 2B-1 0658-1066IIVSGP-AHVSGP-SHVFRP-AHVAC PNL 2RWCU/HI TEMP ISOL IRWCU/HI TrEMP ISOL IRRU 5.6.7.8 SWITCH BRRU 5.6.7.8 SWITCH BHVAC "A" CONT PNLHVAC PNL -SAC-IYESYES1 20NONONONONONOYESNONONONONONONONONONONOXI 141 0 L-1I1 20 RATS-lA1 20 RATS-1B1 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 25-5A1 20 25-5BL&17RATS.IARATFS-18TSE.113..4001 F&#xfd;S.113..4001 F $.,113-4005 SE-`113-2007 SE-113-2021 DG "B RM DAMPER MOTORDO-lA RM THERMOSTAT DO-iB RM THERMOSTAT SAC-1 FREEZESTAT SWITCHSP-I DISCH FLOW SWITCHSP-2 DISCH FLOW SWITCHDOG RM A DAMPER SOVDG RM 8 DAMPER SOVDOG RM B DAMPER SOVDO RM B DAMPER SOVANALOG CABINETANALOG CABINETANALOG CABINETYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESNO NONO NONONONONONONONONONONONONONONONONONONONONONONONONO NONONONONONONO NONO________________
YES NO NO N ___ I ___ I.N i___ I___ ___ __
Table 9.4.1- Base ListEngineering Report No. VTY.RPT-12-00019 Rev. IPage 15 of 24Attachment Br r rT .. r tCREEN11 SCREEN 2 1 SCREEN3SCREEN4UNInCURRENTEQUIPMENTEQUIPMENT CLASS7SSEL EQUIPMENT IDR5-56BONL-VAC-MG-2-tA
-ONT BOARD1IEQUIPMENT DESCRIPTION ANALOG CABINETCONTROL PANEL FOR VITAL AC MG-2-IADG RM B CONTROL BOARDDG RM B ENGINE CONTACTOR CABDG RM B ENGINE INSTR PNLDG RM B EQUIP SKIDDG RM B NEUTRAL TRANSFORMER CABDG RM A VOLTAGE REGULATOR CABSeismic1?YESYESYESYESUndergoRegularConfiguration Inspections?
Maintains atleant one ofthe 5 safetyFunctions ReplacedI IPEEEEnvironment Inside/ : High Temp/Outside?
I Humidity?
(1/0) (T/H)NONONONONONONOBoratedSystem?Reactivity Pressure I Inventory He C o nControl Control Control Remofol IRemovalxxt2020172020:NG CONTACTOR CABNO NOYESYESYESYESYESNONONO13 CABNONONONOYESNONONONONONONONONONO104T-LP-ILr-LP.ILTRANFORMER FOR LP-1L IN CONTROL ROOMNOTB.i3.75B TS.1-W9CTB-I13-790 TS-13-80E TS-13-80C LEAK [YESNOYESYESYESYESYESNONONONONOYESYESYESYESYESNONONONONONONONONONOX0TS-13-80C RCIC/STEAM LEAK DETECTION XxXX10 TS,-13-SM TS-11-800 TB-13-SDTS-13-81C TS-13-8ID TS-13-82B LEAKYESYESYESYESYESNONONONONOYESNONOYESYESYESYES10 ITS-13-82B RCICOSTEAM LEAK DETECTION NONONONONONOXX11I170- tE,-13-,82C 0 rS-13-820 20 ES-16-19-13A 20 ES-S16-19-138 TS-13-82C RCICISTEAM LEAK E1 20 ES-10-145A
-1 20 ES-10.1--43 1 20 PR.1&19.44 1 18 EG"23&#xfd;1 _1 _18 RGSr,23-1 11111101 ILSB-V23-16 TS-I3-82D FAN CONT BOX BES-16-19-13A ES-I 5-19-13EES-10-145A ES-16-1953 PR-i6-19-44 EGM-23-1RGSC-2,:-I LSB-V23-16 LSB-V23-19 LSB-V23-20 TS-12-1OIA TS-12-I01S TS- 12-102ATS-12-1028 TS-12-103A TS-10-I03B TS-12-106A TS-12-1068 1-1SPRESSURE LEAKIrvOWER SUPPLY FOR PI-16-19-36A TORUS PRESSUREYESYESYESYESYESYESYESYESYESYESYESYESYESYESYE SNOYESIPCI/LOCAL STARTER BOX FOR V23-16 MOVNOAPCI ,LOCALNO NO3-19 MOV0rS1-10-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 NONONONONONONONONONONONONONONONONONONONONONONONONONOYESYESYESYESYESNONONONONONONONONONONOYES NO11S 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 XNONONONONONOX IYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESNONONONONONONO-NONONONONONONONONONONONONO ___NOXXxXXXKxRWCUILINE TEMP MONITORING 110 ITS-12-II1A ITS-12-110A YESYESJYESNO I I NONONOI xYES O NO N XYES I NO i NO X Table 9.4.1 -Base List 1Enigneenng Report No. VrY-RPT-12-00019 Rev. IPage 16 of 24Aflcahmenl B3CREENI SCREEN 2 1 SCREEN ASCREEN4-4 -----------------.-
___________________________
INIISOUGCURRENTEQUIPMENT EQUIPMENT IDCLASSSSEL EQUIPMENT IDEQUIPMENT DESCRIPTION Seismic1?UndergoRegularConfiguration Inspections?
Maintains atleast one ofthe S safetyFunctions Replacedl IPEEEEnvironment Inside/ Nigh Temh pOutside?
Humidt-/?
(110) (T I H)Boratedsystam?Reactivity ControlDecayPressure Inventory HeatControl ControlRemovaContainment i i111110 TS-12-112A 0 TS-12-i 12B18 FIS-14-45A is FIS-14"518 18 P&#xfd;-14-44A 7S.12-112A "VVUI./LINE ITEMI MONITOIRING YESNOYES I NONOTS-11-1128 FIS-14-45A Fl S-14-45SB PS-I14-44A PS-i4-44YESNOYES NONOYESNONONONON-OYES NONOxlYES NONO1118PS.14.48,SrB" PUMP DISCHARGE PRESSUREI YESxxx18PF-14.4CPS-14-44C SUREYESYESYESYESYESYESYESNONONONONOYESNONOYESIS IFIS.I-1045B
-RS-10.1488 NONONONONONONONONONOxxx1 08S IFSO-109-75A-I PSO-109-75A-1 q (INBD) TORUS SUPPLY PNL A1~~1FSO-109-75A2 B-7878-618B-I102LOCAL-1 3-16YIESNOYESYESYESYESYES10 18-1102OCAL'NONONONONOYESYESYESYESNONONONONONONOXX0104040404LOCAL-13-16, B-862T-AC-OP-5 DT-3DT.EOT-iD0RCIC;LOCAL STARTER BOX FOR VI 3-16 MOV8-"62OCAL TERM BOX -VI 3-16YESYESYESYESYESNONONONONONONONONONONO1I1I1DT-I 0aDT-4DT-4480,240-120 VAC DIST TRANSFORMER 480,240-120 VAC DIST TRANSFORMER 480/240-120 VAC DIST TRANSFORMER 480 VAC UPS-IA MG SET480 VAC UPS-lB MG SET480 VAC UPS-IA CONTROL PANELYESNO IINOYESYESYESYESYESNONONONONTONONO120 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-SI1 18 RK25-501 1 RK25-TA1 18 RK25-781 10 RK25-231 IS RK25-241 18 RK25-0A1 1I RK.25-50B 1 I8 RK25-51AI IS RK25-51B2^P-UFS-IB3 PT-154-205 PS-104-1 20APIS-I 04-12083PS-i 04-12 OCp5.104-1200 480 VAC UPS-lB CONTROL PANELSW/HEADER TRANSMITTER V70-1A.B, 20 ISOLATION V70-19A.B, 20 ISOLATION V70-19A.B 20 ISOLATION V70-19A.B.
20 ISOLATION YESYESYESYESYESYESES-1-158-5 jPOWER SUPPLY FOR LSL-t07-5B RK25-78K(B)RECIRC PUMP A INST. RACKRECIRC PUMP B INST. RACKHPCI INST. RACK (A)HPCI INST. RACK (B)JET PUMP INST. RACK (51A)JET PUMP INST. RACK ISIS)YESYESYESYESYESYESYESYESYESYESYESYESNONONONONONONONONONONONONONONONONONONONONOYES NOYES NOYES NOYES NOYES NOYES NONONONONONONONONONONONONONONONONONONONONONONONONONONONONONOYESx xXXxXYES IxXR1K25-518 YESYESNO YES INO xNO XYES NO YES INO NONO NO10 P 1<2-68 J1<25-;5 61 IS PR2-S IR<5SRCIC RM INST. RACRHR INST. RACK (A)NOYES I~ NO I I1* ( N{lNn1RHR INST RACK (8) YES NO YESI Table 9.4.1- Base ListEngineering Reporl No. VTY-RPT-12-00019 Rev, IPage 17 of 24Attacnmern B-e tV nr 1~ -- -~I* --. .T t-*'t rnUNITSQUGEQUIPMENT CLASSCURRENTEQUIPMENT IDxx1 81 181 181 181 18ASSEL EQUIPMENT IDRK25-SARK25-5SRK25-SARK25-6BV70-257AV70-2578PT-I04-20A EGRTC-13406A EQUIPMENT DESCRIPTION SeismicI?UndergoReguLarConfiguration Inspections?
Maintoina otleast one ofthe 5 SafetyFunctions Replaced?j IPEEEEnvironment Insidel.I High TemplOutside?
H.midity?
(liD0) IT I HSCREEN11 SCREEN 2 1 SCREEN 3BoratedSystem?SCREEN4DecayReactivity Pressure Inventory HeayControl Control ControlRemovalRENST. RACKYESNOYESYESYESNONONO XNOContainment REACTOR PROT. & NSSS INST. RACKSWE-19-2A OUTLETYES NOINO1 08ASW E- 9-28 OUTLETSW!HEADER TRANSMITTER HPCI EGR ACTUATOR ASSEMBLY (TURB SPEED CONSAC-1 TCVYES NONONONONOA'NOYESNONONONONOp.4002SAC-I DISCHARGE TEMPERATURE YES NO1 0EISOUlR SAC-IA1 21~YESYESYESYESYE-SNONONONONONONONONONONONO NONO NONO NONO NOCR FIRE DAMPER CONTROL SWITCHSCH-YESINO1 21 SCI 20 SC1 20 SC1 07 PCV-1.456-1073A PCV-l-15-1073A N21 07 PCV--156-l173B PCV-I-15-1073S N21 0 FIS-1-16-76 FIS-1.15&-76 N21 0 D-2.IA Q-2-1A N21 0 DF1 0 DF1 0 V72-890 V72-St N21 0 V72-89C V72-89C N21 21 N2I is RK-25-66 RK-25-66 CS1 20 SE-1 13-4002 SE-1 13-4002 SA1 20 SE-1 13A4003 SE-113-4003 SAI1 088 SE-70,3A ISE-70-3A BAE REGULATOR PRESSURE REGULATOR ROTO METER)RC ISOLATION CHECK VALVE/RC ISOLATION CHECK VALVECYLINDERS (18 TOTAL) AND MANIFOLDIT INST. RACKC-IA EXHAUST DAMPER CONTROL.C-1E INLET/OUTLET DAMPER CONTROL.CKWASH FLOW CONTROLYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESYESNONONONONONONONONONONONONONONONONONONONOYESYESYESYENNONONOYNOYESNONONONONONONONOxxXNONONONONONONONONONONONONOH NOH NO1 08B ISE-7-3I JSE-70-3E BA(&#xfd; O0ELAx 1POWER SUPPLY FOR ECCS PANEL 6X is SNVEL Item Tsble 9.4.2- SWEL 1Engneenrig Repot1 No. VTY.RFT-12-00019 Rev. IPage 18 of 24Afachment BDESCRIPTION
),HYDRAULIC CONTROL UNITS /899)/SCN VALVEr VALVES1N3NN000015.1A213'NECRA065920-2258 0000337TB252'EDOGR AA1,2,3,4,5 12Y000044;WEL1-007
)G-I-1B252'EDGRBB1,2,3,4,5 17Y0000495WELl-008
.CV-108-2A FUEL OIL/DAY TANK FILL252'DAY TK RM AA1,2,3.4,5 07N000052 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 Y000053 SWELl-010 TK-40-IA FUEL OILIFUEL OIL STORAGE TANK YARD 252' 1,2.3,4,5 21 0 Y000054 SWELl-011 P-92-1A FUEL OILIFUEL OIL TRANSFER PUMP A FO 241' A 1.2,3,4,5 05 I, H YD00060 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 Y00006D SWELI-014 B-AS-2 125V DC STATION BATTERY ON BUS DC-2AS TB 252' EDGR A 1,2,3,4,5 15 1 Y000097 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 N200071 SWELl-017 oc-2 126V DC DISTR PNL DC-2 160DAMP CB 262, CABLE VAULT 1,2,3,4,5 14 1 N 59204835000081 SWELl-018 DC-ECCS-,
24 VDC ECGS PNL (B) RB 303' 1,2,3,4,5 14 1 Y 59204836000085 SWELl-019 MCG-9C 480V ESS AC MCC-c- DIESEL IA ROOM (SII) TB 252' EDG A 1,2,3,4,5 01 1 Y000098 SWELI-020 MCC-90 480V ESS AC MCC-9D -REACTOR BLDG RB 252' 1.2,3,4,5 01i N000090 SWELl-021 MCC-88 480V ESS AC MCC-8B- REACTOR BLDG (SI) RB 280' 1,2,3,4,5 01 Y000092 SVVELI-022 NCC-98 480V ESS AC M CC-9B- REACTOR BLDG ($11) RB 260' 1,2,3,4,5 01 y0o0090 SWELI-023 BUS-9 480VAC SWITCHGEAR BUS NO.9 1600AMP(SIi, CB 248' SWGR EAST 1.2,3,4,5 02 1 N000o09 SWELI-024 BUS-3 4KV -4160V SWITCHGEAR BUS NO.3 1200AMP (SI) CB 248' SWGR WEST 1,2,3,4,5 03 1 N000101 SWEL1-025 T-8-1A STATION SERVICE TRANS 4160/480 BUS NO.8 CB 248' SWGR WEST 1,2,3,4,5 34 1 Y000103 SWELl-026 TK4.-IA CONDENSATE STORAGE TANK YARD 252Z 2,3 21 0 N000116 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 Y000129 SWELl-029 V23.l1 HPCI/STEAM SUPPLY MOV DW 266' 2,3 08A I, T N000130 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 YII000177 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 Y000203 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 1Engineeing Repot No. VIY.RPT-12-00019 Rev. 1Page 19 or 24Attachment B000257SWELI-054 15.2-.A000263 SWELl-055 IRV.2.71C ALPI000266SWELl-056 ITK-56.-1A
&#xfd;2 AIR RECIEVERRB303'2N5920-5017 000268SWELl-057 IS-2-13ASAFETY RELIEF VALVE/NrIROGEN SUPPLY ACCUMULATOR DW275'221I. TY000279 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 N000324 SWELl-066 PCV.104-28A SWiDG COOLING TB 252' EbGRA A 1,2,3,4,5 07 1 N000335 SWELl-067 V70-20 SW/TURB SLOG ISOL MOV RB 246' 7ORUS CW 1,2.3,4,5 08A I N000353 SWELl-068 TU-I-IA -HPCIIHPCI TURBINE RB 213' HPCI 2,3 05 1 Y000371 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 Y000426 SWELl-074 TS-23-102A HPCESTEAM LEAK DETECTOR ST 251' 2.3 0 I. T y000428 SWELl-075 TS-23-103A HPCIISTEAM LEAK DETECTOR ST 251' 2,3 0 I. T Y000432 SWELl -076 TS-23.104A HPCIISTEAM LEAK DETECTOR ST 251' 2,3_0 I. T Y000496 SWEL1-077 SE-2-88A-1 MS&OUTBOARD MSIV SOLENOID ACDC ST 251' 5 086 1, T N000512 SWELl-078 VG-22A CAD 1lOV VENT ISOLATION (OUTBD, RB 303' 5 08A I N000515 SWEL1-079 NG-13A CAD SOV AIR ISOLATION IINBD) INJECTION TO DW PNL A RB 222' TORUS AREA 5 088 1 N000554 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 N001355 SWELl-087 RATS-IA DG-IA RM THERMOSTAT TB 252' EOGR A A 1.2,3.4,5 20 1 N001375 SWEL1-088 SE-113-2022 DOG RM B DAMPER SOV TB 252' EDGR B B 1,2,3,4,5 08B I N001387 SWELl-089 D0 RM B ENGINE CONTACTOR CAB TB 252' EDGR B B 1.2,3.4,5 20 Y031388 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 Y001396 SWELl-092 T-LP-IL TRANFORMER FOR LP-1L IN CONTROL ROOM CB 262' CABLEVAULT 1,2,3.4,5 04 N001514 SWELl-093 Es---15-.5 POWER SUPPLY FOR LSL-107-5E CB 272' CONTRM 2,3 20 N001522 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 YSWELI-102 CYL-72-IA ITROGEN BOTTLE FOR BACKUP SRV SUPPLY RB 252' A 2 21 I N TAble 9,4.2- SWEL 1Engioe-~g R Ocrl No. \TIY.RPT-12-O0l51 Rev. IPage 201of24Atachrmenl BSSEL# I SWEL1# [EQUIPMENTIDI DESCRIPTION BLDG. I ELEV. I ROOM I TRAMN SYSTEM TYPE ICLASS ENVIORNMENT1 ANC I DWGSystem1 Reactivity Control2 Pressure Control3 Inventory Control4 Decoy Heat Removal5 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 priorto Seismic Walkdowns.
Tnble 9.4.3- Base List 2Engneering Repori No. VrY.RPT-12-00019 Re. IPage 21 of 24AafChrnenl BtoxftxxBL2# EQUIPMENT ID DESCRIPTION BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT N/R2001 ES-19-82B.
Power Supply (CAD PNL A) CAB 272' Control Room 5FPC 202002 N-19g-8113 Pressure indicator (CAD PNL A) CARB 272' Control Room SFPC 182003 T;.19-73B ITemperature indicator (CAD PN L A) CARB 272' Control Room SFPC 182004 dP1-19-76A Differential Pressure Indicator (CAD PNL AB CRB 272' Control Room SFPC 182005 ES-19-76A Power Supply (CAD PNL A) CAR 272' Control Room SFPC 202006 ES-19_8_A Power Suppy (CAD PNL B) CAB 1272' Control Room SFPC 202007 Pi-19.81A Pressure indicator (CAD PNL B) CAB 272' Control Room SFPC is2008 TI-19-73A Ternperature indicator (CAD PN L B) CAB 272' Control Room 5FPC 182009 dPl-19-76A Differential Pressure Indicator (CAD PNL B) CAB 272' Cont.rol Room SFPC 182010 ESo19-76A
:Power Supply (CAD PNL B) CAB 272' Control Room SFPC 202011 RK___A__,
Rack _B 303' _FPC 187012 PI,19-82.A Pressure Indicator (RK-10AA)
RB 303' SFPC 182013 dPT-19-76A Differential Pressure Transmitter IRK-10AA)
RB 303' SPPC 182014 PT-19-81A Pressure Transmitter (RK-IOAA) 303' SFPC 182015 PI-19-83A Pressure Indicator (RK-10AA)
RB 303' SFPC 18.026 PS-19-0A Pressure Switch (RK-10AA) 303" SFPC 182017 PI_19-84A Pressure.
Indicator
_RK-!0AA_
_B 303' SFPC 182018 RK,_ __A_ Rick :B 303' SFPC 182019 P1.19-828 Pressure Indicator (RK-10AB)
R8 303' SFPC 182020 dPT-19-76R DifferentBl Pressure Transmitter (RK-IOAB_
AS 303' PFPC 182021 PT-19-818 Pressure Transmitter (RK-10AB)
RB 303' SFPC 182022 PI-19-838 Pressure Indicator (RK-ROAB)
:B 303' SFPC 182023 PS-19.80B.
Pressure Switch (RK-1OAB)
:AS 303' IEFPC is2024 PI-19,84D Pres'sure Indicator (RK-10AB)
RB 303' !SFFC 182025 TI-19.72 Temperature tndicator 303' PP Hx Room SFPC 02026 TE-V9-73A Temperature Element RB 303' PP Hx Room SFPC 192027 TE-19-73B Temperature Element RB 303' PP Hx Room SFPC 192028 PE.19-73 Flow Element RB 303' FP Hx Room SFPC _02029 FI,19-73 Flow Indicator RB .303' FP Hx Room SFPC 02030 Ti.104-60 Temperature indicator RB 303' 5FPC 02031 TI,104,61 Temperature indicator ASB 3g03' SFPC 02032 V70-2$TA SW MOV SFPC Ax Outle 0 33' FP Hx Am SFPC RA2033 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 5toYtit02035 P.19-23SFPC Pump303'PP Hx Rm5FPC5202' 1&#xfd; &#xfd;12' Ispp;135 E '9 .3281 JSFPCt__________________________
B 13__ 03' I__PP Ho An, 1SPPC ____ 21 _________ B _33 _I xA JFC 122038 CAD PanelAPanel'RB272'2ontrol RoomiFPC/FPC202039 CAD Panel B Panel jCRB 1272' !control Room SFPC/FPC-.32040 IRK-iD303'2041 TI-19-1 Temperature indicator (RK-10i)
_B 3&#xfd;03'2042 IPSL-19-69A Pressure Switch IRK-10l303'2043PSL-19-683
(-I02044:PC18:PC18303':PC18:RB272'"ontrol Room:PC18Temperature Indicator (CAD PNL A):RB272':ontrol Room:PC18Level Indicator (CAAD PNL B)'RB272'-ontrol Room:PC18 Table 9.4.3- Base List 2Enspneering Report No. V-Y-RPT-12-00019 Rev. IPage 22 o 24Ahachnmevt BBL-29 EQUIPMENT ID DESCRIPTION BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT N/R2051 TI-19.71A Temperature indicator (CAD PNL B) CR8 272' Control Room FPC is2052 TE-19-70A Temperature Element RB 303' FP Hx Room FPC 192053 TE-19-708 Temperature Element RB 303' FP Hx Room FPC 192054 TE-19.70C Temperature Element RB 303' FP Hx Room FPC 192055 TE-19.-A Temperature n lement RB 303' FP Hx Room FPC 19205G TE-19-IB Temperature Element Re 303' FP Hx Room FPC 192057 PS-19.68A Pressure Switch RB 303' mFP Hx Room FPC 02058 PS119-683 Pressure Switch RB 303' FP Hx Room FPC 02059 TE-19-71A Temperature Element RaB 345' FPC 192060 TE-19-718
.P. Temperature Element R8 345' FPC 192061 LT-19-63A LevP STrank mimer RB 345' FPC 02062 LT-19-638 Level Transmitter RtB 345' FPC 02063 PI-19-65A Pressure Indicator RB 318' FPC 02064 P1.19.658 Pressure Indicator RS 318' FPC 02365 PM-19-.6A PreCsurC Indicator RB 3180' Skim Puma Rm_ _PC O2066 P1,19-66$
Pressure REB 318" Skim Pump Rm FPC 02067 V19-220 FPC sytem suction isolation MOV RWB 303' FP Hx Rm FFC SA2068 V19-221 FPC system su5ion isolation MOV RW8 303' FP Hx Rm FPC BA2069 P-82-IA FPC Skimmer Pump Re :318' Skim Pump Rm FPC S2070 P-82.113 FPC Skimmer Pump REB 318&#xfd; Skim Pump Rm FPC 52071 P-9-1A FPC Pump RB 203' FP Hx Rm FPC 52072 P-9,1B FPC Pump RB 2303' FP Hx Rm FPC 52073 E-9.1A FPC Heat Exchanger REB 303' FP Ax Rm FPC 212074 E-9-188 PC Heat Exchanger RB 2 30' PP Hx Rm FPC 212075 FC.104-80B Flow Transmitter (RK-10A__
_ RB 303' SW 182076) PI-104-180B Flow Indicator (CAD PNL A) SW to SFPC Hx CRB 272' Control Room SW is5077 ES-104-808 Power Supply (CAD PNL A1 SW toSFPC Hx CRB 272' Central Room SW 202078 FI-104-80A Flow Indicator (CAD PNL B) SW to SFPC Hx CRB 272' Control Room SW 182079 ES.104-80A Power Supply (CAD PNL 8)} SW to SFPC Hx CRB) 272' Control Room SW20i080 P1-104-93A Pressure indicator (RK-10AA1 RB 1303' 5W 182081 FT-104-80A Flow Transmitter (RK-10AA)
RB 303' SW 182082 Pi-10,-939 Pressure Indic.ator (RK-10AB)
RE; 303' SW is2083 MVCC.6A MCC RB 280' 480A -12{084 MCC-6c M cc RWEt 252' Control Room 48)0A 1F085- -MCC-6D MCC RWB 2S2' Control Room 480A 12086 MICC-TA M4CC REB 28e)0 480A12087 MCC-E) B MCC RB 28)0r 480OAMACC-9B MCC RB 28(Y' 48)0A I2089 M4CC-SE MCC !RB 2S' DA iXx is SWEL Item Table 9.4.4- Rapid Drain-Down Altoohmvern BEngneering Report No. VTY-RPT-12-00019 Rev. IPage 23 of 249,4,4- Rapid Drain-Down RDD# DESCRIPTION BASIS FOR INCLUSIONIEXCLUSION RDDNo Rapid Drain-Down items were identified durng the development of the SWEL 2.
Table 9.4.5- SWEL 2Engneering Report No. VTY-RPT-12.00019 Rev. 1Page 24 of 24Aflachmenl BSWEL 2# EQUIPMENT ID DESCRIPTION BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT N/R RDDSWEL2-001 RK.10AA Rack RB 303' 4 18SWEL2-002 dPT,19-76A Differential Pressure Transmitter (RK-10AAI RB 303' 4 18SWEL2-003 PT-19-B1A Pressure Transmitter (RK-10AA)
RB 303' 4 18SWEL2-004 PS-19-80A Pressure Switch (RK-10AA)
RB 303' 4 18SWEL2-005 PI,19.84A Pressure Indicator (RKlt0AA)
RB 303' 4 18SWEL2-006 P1I19-73 Flow indicator RB 303' FP Hx Room 4 0SWEL2-007 V70-257B IW MOV SFPC Hx outlet RB 303' FP Hx Rm B 4 8ASWEL2-008 P-*9.2A SFPC Pump RB 303' PHx Rm A 4 5SWEL2-009 E-19-2A SPPC Heat Eohanger PB 303' PP HO RO A 4 21SWEL2-010 CAD Panel B lPanel CRB 272' Control Room B 4 20SWEL2-011 IFTrO.04.80A Plow Transmitter (RK-10AA)
RB 303' 4 18System1 Reactivity Control2 Pressure Control3 Inventory Control4 Decay Heat Removal5 Containment Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 1 of 505Attachment CAttachment CSeismic Walkdown Checklists (SWCs)
Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 2 of 505Attachment CSWEL1# EQUIPMENT ID DESCRIPTION PAGESWELl-001 CRD/HYDRAULIC CONTROL UNITS (89) 5SWELI-002 LCV-3-33C CRD/SCRAM DISCHARGE VOLUME DRAIN VALVE 10SWELl-003 PCV-3-32B CRD/SCRAM DISCHARGE VOLUME VENT VALVES 15SWELl-004 CV-3-126-CRD/SCRAM VALVES (89) INLET 20SWELI-005 P-46-IA CS/"A" CORE SPRAY PUMP 25SWELl-006 C-3-1A DG START AIR/COMPRESSOR A 30SWELI-007 DG-1B DIESEL GENERATOR B 35SWELI-008 LCV-108-2A FUEL OIL/DAY TANK FILL 40SWELI-009 TK-42-1B FUEL OIL/DIESEL OIL DAY TANK B 45SWELl-010 TK-40-IA FUEL OIL/FUEL OIL STORAGE TANK 50SWELl-011 P-92-1A FUEL OIL/FUEL OIL TRANSFER PUMP A 55SWELI-012 MG-2-1A 120/240V VITAL AC MG SET 60SWELI-013 BC-i-IA 125V DC MAIN STATION BATTERY CHARGER A ON DC-1 65SWELI-014 B-AS-2 125V DC STATION BATTERY ON BUS DC-2AS 70SWELl-015 B-I-lB 125V DC STATION BATTERY ON DC-2 75SWELl-016 DC-1 125V DC DISTR PNL DC-1 1600AMP 80SWELI-017 DC-2 125V DC DISTR PNL DC-2 1600AMP 85SWELl-018 DC-ECCS-B 24 VDC ECCS PNL (B) 90SWELl-019 MCC-9C 480V ESS AC MCC-9C -DIESEL 1A ROOM (SII) 95SWELl-020 MCC-9D 480V ESS AC MCC-9D -REACTOR BLDG 100SWELl-021 MCC-8B 480V ESS AC MCC-8B -REACTOR BLDG (SI) 105SWELl-022 MCC-9B 480V ESS AC MCC-9B -REACTOR BLDG (S11) 110SWELl-023 BUS-9 480V AC SWITCHGEAR BUS NO.9 1600AMP (SII) 115SWELl-024 BUS-3 4KV -4160V SWITCHGEAR BUS NO.3 1200AMP (SI) 120SWELl-025 T-8-1A STATION SERVICE TRANS 4160/480 BUS NO.8 125SWELl-026 TK-4-1A CONDENSATE STORAGE TANK 130SWELl-027 P-44-1A HPCI/HPCI PUMP 135SWELl-028 PS-23-84-1 HPCI/PUMP SUCTION PRESSURE SWITCH 140SWELl-031 TEF-3 DG B ROOM VENTILATION/EXHAUST FAN 145SWELl-032 RRU-8 SW/ECCS RM COOLING 150SWELl-033 PT-2-3-52C CS, RHR PERMISSIVE 155SWELl-034 LT-I07-5A CST/LEVEL TRANSMITTER 160SWELl-035 LT-107-5B CST/LEVEL TRANSMITTER 165SWELl-036 PT-iO-IOIA DW PRESSURE ECCS 170SWELl-037 PT-10-101C DW PRESSURE ECCS 175SWELl-038 PT-16-19-29A DW PRESSURE INDICATION 180SWELI-039 PT-5-12C DW PRESSURE SCRAM 185SWELl-040 PT-5-12D DW PRESSURE SCRAM 190SWELl-042 LT-2-3-72A RV LEVEL FOR RHR, DG, HPCI, RCIC, ADS, CS 195SWELl-043 LT-2-3-72C RV LEVEL FOR RHR, DG, HPCI, RCIC, ADS, CS 200SWELl-044 LT-2-3-58A RV LEVEL SCRAM & PCIS 205SWELl-045 LT-2-3-58B RV LEVEL SCRAM & PCIS 210SWELl-046 PT-2-3-S6A RV PRESSURE ECCS 215SWELl-047 PT-2-3-56C RV PRESSURE ECCS 220SWEL1-048 PT-2-3-55C RV PRESSURE SCRAM 225 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 3 of 505Attachment CSWEL1# EQUIPMENT ID DESCRIPTION PAGESWELl-049 PT-2-3-55D RV PRESSURE SCRAM 230SWELl-050 LT-2-3-73A RV SHROUD LEVEL, CONT SPRAY PERMISSIVE 235SWELl-OS1 PS-104-53A SW/PUMP A PRESSURE SWITCH 240SWELl-056 TK-55-1A N2 AIR RECIEVER 245SWELl-058 P-1O-1D RHR/D RHR PUMP 250SWELl-059 V10-65B RHR/HEAT XC BYPASS MOV 255SWELl-060 V10-27A RHR/LPCI INJECTION MOV 260SWELl-061 P-8-1C RHRSW/C RHRSW PUMP 265SWELl-062 V10-89A RHRSW/SW SUPPLY MOV 270SWELl-063 SP-70-3A BACKWASH FLOW CONTROL 275SWELl-064 P-7-1C SW/C SW PUMP 280SWELl-065 LCV-108-3 FUEL OIL TANK VALVE 285SWELl-066 FCV-104-28A SW/DG COOLING 290SWELl-067 V70-20 SW/TURB BLDG ISOL MOV 295SWELl-068 TU-1-1A HPCI/HPCI TURBINE 300SWELl-069 DG-1B-INTAKE-X DG ROOM VENTILATION/DG ROOM B LOUVERS (6 TOTAL) 305SWELl-070 ES-23-110 HPCI INST PWR SUPPLY 310SWELl-071 FTA-23-118 HPCI SQ RT CONV-FLOW 315SWELl-072 ES-23-94 HPCI/DC/AC INVERTER 320SWELl-078 VG-22A CAD MOV VENT ISOLATION (OUTBD) 325SWELl-079 NG-13A CAD SOV AIR ISOLATION (INBD) INJECTION TO DW PNL A 330SWELl-080 SB-16-19-6 PRIMARY CONTAINMENT VENT TO SBGT ISOLATION 335(OUTBD) AOVSWELl-081 CRP 9-03 CONTROL ROOM PANEL 340SWELl-082 CRP 9-19 CONTROL ROOM PANEL 345SWELl-083 CRP 9-20 CONTROL ROOM PANEL 350SWELl-084 DG RM B VOLTAGE REGULATOR CAB 355SWELl-085 DG RM A NEUTRAL TRANSFORMER CAB 360SWELl-086 L-17 DG "B" RM DAMPER MOTOR 365SWELI-087 RATS-lA DG-1A RM THERMOSTAT 370SWELl-088 SE-113-2022 DG RM B DAMPER SOV 375SWELl-089 DG RM B ENGINE CONTACTOR CAB 380SWELl-090 DG RM B ENGINE INSTR PNL 385SWELl-091 DG RM B EQUIP SKID 390SWELl-092 T-LP-1L TRANFORMER FOR LP-1L IN CONTROL ROOM 395SWELl-093 ES-1-156-5 POWER SUPPLY FOR LSL-107-5B 400SWELl-094 RK25-SOA HPCI INST. RACK (A) 405SWELl-095 RK2S-50B HPCI INST. RACK (B) 410SWELl-096 RK25-52A JET PUMP INST. RACK (52A) 415SWELl-097 RK25-52B JET PUMP INST. RACK (52B) 420SWELl-098 RK25-6A REACTOR PROT. & NSSS INST. RACK 425SWELl-099 RK25-6B REACTOR PROT. & NSSS INST. RACK 430SWELl-100 RK-25-66 CST INST. RACK 435SWELI-101 ES-24DC-2 POWER SUPPLY FOR ECCS PANEL B 440SWELl-102 CYL-71-1A NITROGEN BOTTLE FOR BACKUP SRV SUPPLY 445I Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 4 of 505Attachment CSWEL1# EQUIPMENT ID DESCRIPTION PAGESWEL2-001 RK-10AA Rack 450SWEL2-002 dPT-19-76A Differential Pressure Transmitter (RK-1OAA) 455SWEL2-003 PT-19-81A Pressure Transmitter (RK-10AA) 460SWEL2-004 PS-19-80A Pressure Switch (RK-10AA) 465SWEL2-005 PI-19-84A Pressure Indicator (RK-10AA) 470SWEL2-006 FI-19-73 Flow Indicator 475SWEL2-007 V70-257B SW MOV SFPC Hx outlet 480SWEL2-008 P-19-2A SFPC Pump 485SWEL2-009 E-19-2A SFPC Heat Exchanger 490SWEL2-010 CAD Panel B Panel 495SWEL2-011 FT-1O4-80A Flow Transmitter (RK-1OAA) 500Items Differed to RFO 30 (March 2013) 505 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 5 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: Y0 NEI U[]Seismic WalkdowrChecklist (SWC) SWELl- 001Equipment ID No. Equip. Class1 0Equipment Description CRD/HYDRAULIC CONTROL UNITS (89)Location:
Bldg. RB Floor El. 252' Room, Area SOUTH AND NORTH BANKSManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YD NO2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?YZ N--] U[] N/A["IYZ N[- UI" N/A-'YZ Ni] Ut] N/Ar]zo- bcs7jo: I- -C-6 I P"-e&#xfd;~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. 1Page 6 of 505Attachment CATTACHMeNT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: YV NEI ULSeismic Walkdown Checklist (SWC) SWEL1- 001Equipment ID No. Equip. Class1 01 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 whichan anchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of YS N] UF"Ipotentially adverse seismic conditions?
Interaction Effects7. 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/ADYZ NE] U[-] N/ADYZ NIl Ur- N/AD10. Based on the above seismic interaction evaluations, Is equipment free YZ ND UDof potentially adverse seismic interaction effects?EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 7 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: Y0 N-' Ur"Seismic Walkdown Checklist SWELl- 001Equipment ID No/-F&#xfd; &#xfd; 17 Equip. Class 0Equipment 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. 000002Evaluated by; Kifit ParikhDate: 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. 1Page 8 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: YED NFL UI-Seismic Walkdow?
Checklist (SWC) SWELl- 001Equipment ID No. rzanwWW A Equip. Class' 0Equipment Description CRDAHYDRAULIC CONTROL UNITS (89)Photographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 9 of 505Attachment CATTACHMENT 9.6SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: YN NOJ U-Seismic Walkdown Checklist (SWC SWELl- CEquipment ID No. Equip. Class'Equipment Description CRDI-IYDRAULIC CONTROL UPEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 10 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORMSheet I of 5Status: YZ NEL UO'Seismic Walkdown Checklist (SWC) SWELl- 002Equipment ID No. LCV-3-33C Equip. Class1 07Equipment Description CRD/SCRAM DISCHARGE VOLUME DRAIN VALVELocation:
Bldg. RB Floor El. 252' Room, AreaManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YrI NO2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?YEI] NEI] UI N/A0YE] NEJ u-- N/AZYE] N[-E U- NWASI 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. 1Page 11 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: YZ N[-I U-ISeismic Walkdown Checklist (SWC) SWELl- 002Equipment ID No. LCV-3-33C Equip. Class1 07Equipment Description CRD/SCRAM DISCHARGE VOLUME DRAIN VALVE5. 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 whichanchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of YZ NI] U[-]potentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?Y0 NO- Ur-] N/Ar-YN N[] u-] N/A["YZ Nr"] UL[ N/AQ-YO NEI urlEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 12 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: YO NEI U1"Seismic Walkdown Checklist (SWC) SWELl- 002Equipment ID No. LCV-3-33C Equip. Class1 07Equipment Description CRD/SCRAM DISCHARGE VOLUME DRAIN VALVEOther 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 TworkI10-04-2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 13 of 505Attachment CATTACHMENT 9.6 SEISMic WALKDOWN CHECKLIST FORMSheet 4 of 5Status: Y0 NEI U[ISeismic Walkdown Checklist (SWC) SWELl- 002Equipment ID No. LCV-3-33C Equip. Class1 07Equipment Description CRD/SCRAM DISCHARGE VOLUME DRAIN VALVEPhotographs NO PHOTONote:Note: LCV-3-33C EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 14 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: NU- Ui--Seismic Walkdown Checklist (SWC) SWELl- 002Equipment ID No. LCV-3-33C
.Equip. Class1 07Equipment Description CRDISCRAM DISCHARGE VOLUME DRAIN VALVENO PHOTO NO PHOTONote:Note:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 15 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: YZ NI] U[]Seismic Walkdown Checklist (SWC) SWELl- 003Equipment ID No. PCV-3-32B Equip. Class1 07Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VALVESLocation:
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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YD NO2. 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 surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?YEI NEI UE- N/ASY-I N"] U[-] N/ANY[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. 1Page 16 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKIUST FORMSheet 2 of 5Status: YZ NEI UO-Seismic Walkdown Checklist (SWC) SWELl- 003Equipment ID No. PCV-3-32B Equip. Class' 07Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VALVES5. 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 whichan 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 Effects7. 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 freeof potentially adverse seismic interaction effects?Y0 NEI uE-! N/AF-YN NE! uE- N/AEYZ NEI U[-l N/A--YZ NEI U--EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 17 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 3 of 5Status: YE0 NEI UrSeismic Walkdown Checklist (SWC) SWELl- 003Equipment ID No. PCV-3-32B Equip. Class' 07Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VALVESOther Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could YN NEI U[Oadversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Reference Documents:
A46/IPEEE-SSEL Line No. 000010Evaluated bv: Kirit Parikh..........
jRandy Steghens
~Q-b ~1LC i~2 LDate: 10/04/2012 10/04/2012 EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 18 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 4 of 5Status: YZ NM] UrSeismic Walkdown Checklist (SWC) SWELl- 003Equipment ID No. PCV-3-32B Equip. Class1 07Equipment Description CRD/SCRAM DISCHARGE VOLUME VENT VALVESPhotographs Note: Looking up at valve '#EN-DC-168 REV 0 Engineering Report No. VJTY-RPT-1 2-00019Rev. 1Page 19 of 505Attachment CATTACHMENT 9.6Sheet 5 of 5SEISMIC WALKDOWN CHECKLIST FORMSeismic Walkdown Checklist (SWC) SWELl- 003Equipment ID No. PCV-3-32B Equip. Class' 07Equipment Description CRDISCRAM DISCHARGE VOLUME VENT VALVESStatus: Yv NEI Uf-EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 20 of 505Attachment CATTACHMEI Sheet 1 of5T 9.6SEISMIC WALKDOWN CHECKLIST FORM5Status: YZ N[O] U-]Seismic Walkdown Checklist (SWC) SWELl- 004Equipment ID No. CV-3-126-Equip. Class1 07Equipment Description CRD/SCRAM VALVES (89) INLETLocation:
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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
Yr- NZ2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?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. 1Page 21 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORMSheet 2 of 5Status: YZ NO3 Ul]Seismic Walkdown Checklist (SWC) SWELl- 004Equipment ID No. CV-3-126-Equip. Class1 07Equipment Description CRD/SCRAM VALVES (89) INLET5. 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 whichan 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 Effects7. 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 freeof 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. 1Page 22 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: Y[0 NiL ur-JSeismic Walkdown Checklist (SWC) SWELl- 004Equipment ID No. CV-3-126-Equip. Class' 07Equipment Description CRD/SCRAM VALVES (89) INLETOther 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 posean adverse seismic condition.
See CR- VTY-2012-05099.
Reference Documents:
A46/IPEEE
-SSEL Line No. 000011k2V V-C, jolISIZ019-EJZA&#xfd;-Evaluated by: Ktrit ParlkhDate: 10/16/2012 Ranc* &M&Les P' ILZO-~10/16/2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 23 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: YZ NEI UC-1Seismic Walkdown Checklist (SWC) SWELl- 004Equipment ID No. CV-3-126-Equip. Class1 07Equipment Description CRD/SCRAM VALVES (89) INLETPhotographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 24 of 505Attachment CATTACHmENT 9.6SEISMIC WALKDOWN CHECKUST FORMShoot 5 of 5Status: Yv NC] uMSeismic Walkdown Checklist (SWC) SWEL1- CEquipment ID No. CV-3-126-Equip. Class1Equipment Description CRD/SCRAM VAL VES (89) INLETshowing surface corrosion.
companson.
EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 25 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: Y0 ND ULISeismic Walkdown Checklist (SWC) SWELl- 005Equipment ID No. P-46-1A Equip. Class' 06Equipment Description CS'A" CORE SPRAY PUMPLocation:
Bldg. RB Floor El. 213' Room, Area NECRManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
Y9 NO2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?Y0 ND UD N/ADYZ 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. 1Page 26 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRMSheet 2 of 5Status: YO NO UO-]Seismic Walkdown Checklist (SWC) SWELl- 005Equipment ID No. P-46-1A Equip. Class' 06Equipment Description CS/A" CORE SPRAY PUMP5. 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 whichanchorage 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 Effects7. 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 freeof 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 CEngineerinf ATTAcHMENT 9.6 SiSheet 3 of 5Seismic Walkdown Checklist (SWC) SWELl- 005Equipment ID No. P4-6-1A Equip. Class1 06Equipment Description CSI"A" CORE SPRAY PUMPOther Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that couldadversely affect the safety functions of the equipment?
Report No. VTY-RPT-12-00019 Rev. 1Page 27 of 505EISMIC WALKDOWN CHEcKusT FORMStatus: Y0 NO UOIY0 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 tookanother picture.Reference Documents:
Drawing 5920-2258 A46/IPEEE
-SSEL Line No. 000015Evaluated by: Kirit Parikh r _ 1 i 11t g" I ZO I_. Date: 10/17/2012 Randy SteDhens IQI% &#xb6;C- 4( ('Jl 10/117/2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 28 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: Y10 NO U-"Seismic Walkdown Checklist (SWC) SWELl- 005Equipment ID No. P-46-1A Equip. Class1 06Equipment Description CS/"A" CORE SPRAY PUMPPhotographs
-1NO PHOTONote:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 29 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: N1J UE'-Seismic Walkdown Checklist (SWC) SWELl- 005Equipment ID No. P-46-1A Equip. Class1 06Equipment Description CSP"A" CORE SPRAY PUMPNO PHOTO NO PHOTONote:Note:EN-DC-168 REV 0 VEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 30 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: YZ NEI UE-Seismic Walkdown Checklist (SWC) SWELl- 006Equipment ID No. C-3-1A Equip. Class' 12- AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR ALocation:
Bldg. TS Floor El. 252 Room, Area EDGR AManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YZ NEI2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?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. 1Page 31 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: Yo NE] UM-'Seismic Walkdown Checklist (SWC) SWELl- 006Equipment ID No. C-3-1A Equip. Class' 12 -AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR A5. 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 whichanchorage configuration verification is required.)
See A46/PEEE
-SSEL Line No. 0000336. Based on the above anchorage evaluations, is the anchorage free of YZI NEI U-]potentially adverse seismic conditions?
Interaction Effects7. 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 andare acceptable based on engineering judgment.
: 10. Based on the above seismic interaction evaluations, is equipment freeof 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. 1Page 32 of 505Attachment CATTACHMEN Sheet 3 ofT 9.6SEISMIC WALKDOWN CHECKUST FORM5Status: YZ NEL UL-Seismic Walkdown Checklist (SWC) SWELl- 006Equipment ID No. C-3-1A Equip. Class1 12 -AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR AOther Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that couldadversely affect the safety functions of the equipment?
YO NO UUComments (Additional pages may be added as necessary)
Reference Documents:
A464PEEE
-SSEL Line No. 000033Evaluated 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. 1Page 33 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRMSheet 4 of 5Status: YA NI] Ul]Seismic Walkdown Checklist (SWC) SWELl- 006Equipment ID No. C-3-1A Equip. Class' 12- AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR APhotographs I IEN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 34 of 505Attachment CATTACHMENT 9.6 SEISMC WALKOOWN CHECKuST FORMSheet 5 of 5Status: Y0 NI] UE-Seismic Walkdown Checklist (SWC) SWELl- 006Equipment ID No. C-3-1A Equip. Class1 12 -AIR COMPRESSORS Equipment Description DG START AIR/COMPRESSOR ANO PHOTO NO PHOTONote:Note:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 35 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 1 of 5Status: Y0 NEI UM-Seismic Walkdown C-ecklist (SWC) SWELl- 007Equipment ID No. ea u~ qp.Ia")I2ss&#xfd; 17Equipment Description DIESEL GENERA OR B' &deg; " "Location:
Bldg. TB Floor El. 252' Room, Area EDOGR BManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
Y[D NEI2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?Steel structure, no concrete.
# C72-2.ee~)
1PV F lbYZ NEI U[] NIAQ:YZ NEj UEJ N/AEJYQ: NEfl U1 WlASICA 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. 1Page 36 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: YZ NI: UL]Seismic Walkdown Checklist (S ) SWEL- 007b ~~-t -I 1 -Jt, 171,'Equipment ID No. 0 A/ Equip. Class' 17Equipment Description DIESEL GENERATOR B5. 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 whichanchorage configuration verification is required.)
The diesel generator comes attached to the skid. The skid is properlyattached to the foundation (see Swel 1-091 and VYEM-olo7) and thegenerator is attached to the skid with 8-1 W" diameter bolts. Thus, thegenerator falls under the rule of the box. Seismically acceptable byengineering Judgment.
: 6. Based on the above anchorage evaluations, is the anchorage free of YZI N[3 U[-potentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?YZ NOt UOl N/AOYZ NOI ur'] N/A[--Y0 NOi Ur] N/ADlYZ N[l U--EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 37 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: YZ NEI U[:-Seismic Walkdown Checklist (S C SW ELi- 007Equipment ID No. Equip. Class' 17Equipment 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 107A46/IPEEE
-Screening Evaluation Work Sheet, SSEL Line No. 000044Evaluated by: Marcus e Date: 10-03-2012 Raymond Tworak10-O032012 Ramond TworekfEN-DC-168 REV 0 Engineering Report No. VTY-RPT-1 2-00019Rev. 1Page 38 of 505Attachment CATTACHMENT 9.6 SESMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: Y0 NL] Ur]Seismic Walkdown Checklist (SWC) SWEL1- 007Equipment ID No. Z p / Equip. Class' 17Equipment Description DIESEL GENERATOR BPhotographs EN-DC-168 REV 0 Attachment CATTACHMENT 9.6Sheet 5 of 5Seismic Walkdown 1Equipment ID No.Equipment Description Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 39 of 505SEsmmc WALKDOWN CHECKLIST FORMStatus: YN NEI U"EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 40 of 505Attachment CATrACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: YN NO U-Seismic Walkdown Checklist (SWC) SWELl- 008Equipment ID No. LCV-108-2A Equip. Class1 07- FLUID OPERATED VALVESEquipment Description FUEL OIUDAY TANK FILLVALVE Location:
Bldg. TB Floor El. 252' Room, Area DAYTKRMAManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YlI NO2. 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 surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?YEI NEI UEr N/AOYE- N[3 U' N/ASYE" 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. 1Page 41 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: Y[ NEI U--Seismic Walkdown Checklist (SWC) SWELl- 008Equipment ID No. LCV-1O8-2A Equip. Class' 07- FLUID OPERATED VALVESEquipment 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 whichan 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 Effects7. 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 freeof potentially adverse seismic interaction effects?Y0 NE] ul] N/AE]YO NEI UE] N/A[]YE] NE] uE] N/AZYONE] uDEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Attachment C Page 42 of 505ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 3 of 5Status: YZ NE] U-'Seismic Walkdown Checklist (SWC) SWELl- 008Equipment ID No. LCV-108-2A Equip. Class1 07- FLUID OPERATED VALVESEquipment 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. 000049Evaluated 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. 1Page 43 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 4 of 5Status: Y0 Nn] U-]Seismic Walkdown Checklist (SWC) SWELl- 008Equipment ID No. LCV-108-2A Equip. Class1 07- FLUID OPERATED VALVESEquipment Description FUEL OIL/DAY TANK FILL VALVEPhotographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 44 of 505Attachment CATTACHMENT 9.6SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: Y0 NO- UJ-Seismic Walkdown Checklist (SWC) SWELl- 008Equipment ID No. LCV-I08-2A Equip. Class1 07- FLUID OPERATED VALVESEauioment DescnDtlon FUEL OIL/DAY TANK FILLVALVE NO PHOTONote:EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 45 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 1 of 5Status: YV NEI U[]Seismic Walkdown Checklist (SWC) SWELl- 009Equipment ID No. TK-42-IB Equip. Class' 21- TANKS & HEAT EXCHANGERS Equipment Description FUEL OILUDIESEL OIL DAY TANK BLocation:
Bldg. TB Floor El. = Room, Area DAY TK RM BManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof 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 surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?Two grout pads on the east side of the tank are slightly
: damaged, butdo 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
'iAV,Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 46 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: YZ NEI UrISeismic Walkdown Checklist (SWC) SWELl- 009Equipment ID No. TK-42-1B Equip. Class' 21- TANKS & HEAT EXCHANGERS Equipment Description FUEL OIL/DIESEL OIL DAY TANK B5. 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 whichanchorage configuration verification is required.)
See A464IPEEE
-SSEL Line No. 0000526. Based on the above anchorage evaluations, is the anchorage free of Y0 Ni] U[].potentially adverse seismic conditions?
Interaction Effects7. 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 freeof 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. 1Page 47 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: Y[ NI] U[-Seismic Walkdown Checklist (SWC) SWELl- 009Equipment ID No. TK-42-1B Equip. Class1 21- TANKS & HEAT EXCHANGERS Equipment Description FUEL OIlUDIESEL OIL DAY TANK BOther Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could Y0 NEI U'iadversely affect the safety functions of the equipment?
Comments (Additional pages may be added as necessary)
Reference Documents:
A46/IPEEE
-SSEL Line No. 000052Drawing 5920-4047 and B-191261, sheet 54.Modification MM 99-021Calculation VYC- 1891Evaluated 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. 1Page 48 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 4 of 5Status: Y0 NI UMISeismic Walkdown Checklist (SWC) SWELl- 009Equipment ID No. TK-42-IB Equip. Class1 21- TANKS & HEAT EXCHANGERS Equipment Description FUEL OIUDIESEL OIL DAY TANK BPhotographs NO PHOTONote:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 49 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: Y; NE] U]'Seismic Walkdown Checklist (SWC) SWELl- 009Equipment ID No. TK-42-1B Equip. Class' 21 -TANKS & HEAT EXCHANGERS Equipment Description FUEL OIL/DIESEL OIL DAY TANK BNO PHOTO NO PHOTONote: Note:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 50 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 1 of 5Status: YZ NEI UJ-Seismic Walkdown Checklist (SWC) SWELl- 010Equipment ID No. TK-40-lA Equip. Class' 21Equipment Description FUEL OIUFUEL OIL STORAGE TANK (FOST)Location:
Bldg. YARD Floor El. 252' Room, Area YARDManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YO NO2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?A small hairline crack is seen near North-East bolt, seismically insignificant by engineering judgment since only small area has thiscrack. A# other areas are without any cracks.Y ] NEI ur- N/A"]YC9 NE] U["] N/A[DYZ 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. 1Page 51 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 2 of 5Status: YZ No Ur]Seismic Walkdown Checklist (SWC) SWELl- 010Equipment ID No. TK-40-1A Equip. Class' 21Equipment 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 whichan 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 uOpotentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?YO NO ul] N/Al]Yv NM] U[] N/Al-]Y[] NE] ul] N/AZYO NEI UEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 52 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: Y0 NEI U["Seismic Walkdown Checklist (SWC) SWELl- 010Equipment ID No. TK-40-1A Equip. Class1 21Equipment 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-191606Calculation VYC-1469A46/IPEEE
-Screening Evaluation Work Sheet, SSEL Line No. 00053Evaluated by: Kirit Parikh10 1 l&Il 2 12-Date: 10/03/12RandyStehens 1, 4KfqJZa i 4L10/03/12EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 53 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: YS NEI U-lSeismic Walkdown Checklist (SWC) SWELl- 010Equipment ID No. TK-40-1A Equip. Class1 21Equipment Description FUEL OILIFUEL OIL STORAGE TANK (FOST)Photographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 54 of 505Attachment CATTACHMENT 9.6SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: YV NO U[-Seismic Walkdown Checklist (SWC) SWELl- 010Equipment ID No. TK-40-IA Equip. Class' 21Equipment Description FUEL OIL/FUEL OIL STORAGE TANK (FOST)EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 55 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet I of 5Status: YO NEI uE'Seismic Walkdown Checklist (SWC) SWELl- 011Equipment ID No. P-92-1A Equip. Class' 05Equipment Description FUEL ILUFUEL OIL TRANSFER PUMP ALocation:
Bldg. FO Floor El. 241' Room, Area SWCRManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YO NEI2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?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. 1Page 56 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FoRMSheet 2 of 5Status: YN NO] UOSeismic Walkdown Checklist (SWC) SWELl- 011Equipment ID No. P-92-1A Equip. Class1 05Equipment Description FUEL QIUFUEL OIL TRANSFER PUMP A5. 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 whichan 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 Effects7. 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 freeof potentially adverse seismic interaction effects?Y; NE] U'- NIArIYN NE] uE] N/AErYZ NE] UE N/A[-]YU NO] U-]EN-DC-1 68 REV 0 Attachment CEngineerin~
ATTACHMENT 9.6 SiSheet 3 of 5Seismic Walkdown Checklist (SWC) SWELl- 011Equipment ID No. P-92-IA Equip. Class1 05Equipment Description FUEL OIL/FUEL OIL TRANSFER PUMP AOther Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that couldadversely affect the safety functions of the equipment?
g Report No. VTY-RPT-12-00019 Rev. 1Page 57 of 505EISMIC WALKDOWN CHECKLIST FORMStatus: Y[ NEI] Ur]YO NEI UEComments (Additional pages may be added as necessary)
Referenced Documents:
A46/IPEEE
-Screening Evaluation Work Sheet, SSEL Line No. 00054Evaluated 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. 1Page 58 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORMShoot 4 of 5Status: YN NI: UE-Seismic Walkdown Checklist (SWC) SWELl- 011Equipment ID No. P-92-IA Equip. Class' 05Equipment Description FUEL OILIFUEL OIL TRANSFER PUMP APhotographs NO PHOTONote:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 59 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 5 of 5Status: Y@ NE] UL-'Seismic Walkdown Checklist (SWC) SWELl- 011Equipment ID No. P-92-1A Equip. Class' 05Equipment Description FUEL OILUFUEL OIL TRANSFER PUMP ANO PHOTO NO PHOTONote: Note:EN-DC-168 REV 0 0Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 60 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: Y0 NEI U[-Seismic Walkdown Checklist (SWC) SWELl- 012Equipment ID No. MG-2-1A Equip. Class' 13Equipment Description 120/240V VITAL AC MG SETLocation:
Bldg. H .B Floor El. 280' Room, AreaManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?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. 1Page 61 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: YZ NI] UL-Seismic Walkdown Checklist (SWC) SWELl- 012Equipment ID No. MG-2-1A Equip. Class' 13Equipment Description 1201240V VITAL AC MG SET5. 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 whichan 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 Effects7. 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 freeof potentially adverse seismic interaction effects?YO N[:] urD N/AEDYO NI] Ur- N/AD"YN NI] uD] N/ADY19 NI] U!]EN-DC-168 REV 0 01Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 62 of 505Attachment CATTACHMENT 9.6Sheet 3 of 5SEISMIC WALKDOWN CHECKUST FORMStatus: Y] NEI U0-Seismic Walkdown Checklist (SWC) SWELl- 012Equipment ID No. MG-2-1A Equip. Class1 13Equipment Description 120/240V VITAL AC MG SETOther Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that couldadversely 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. 000060Evaluated by: Marcus Date: 10-09-2012 Ravmond Tworekto/I 61L2-10-09-2012 EN-DC-168 REV 0 lEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 63 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: YZ( NEI UMSeismic Walkdown Checklist (SWC) SWELl- 012Equipment ID No. MG-2-1A Equip. Class1 13Equipment Description 120/240V VITAL AC MG SETPhotographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 64 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: Y0 NEI ur-Seismic Walkdown Checklist (SWC) SWELl- 012Equipment ID No. MG 1A Equip. Class1 13Equipment Description 120/240V VITAL AC MG SETNO PHOTO NO PHOTONote: Note:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 65 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: YE] NEI U--Seismic Walkdown Checklist (SWC) SWELl- 013Equipment ID No. BC-1-1A Equip. Class1 16Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-1Location:
Bldg. CB Floor El. 248' Room, Area SWGR WESTManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YO NO2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?Yv NO Ur N/AQYO 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. 1Page 66 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 2 of 5Status: YN NEI UE]Seismic Walkdown Checklist (SWC) SWELl- 013Equipment ID No. BC-1-IA Equip. Class1 16Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-15. 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 whichanchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of YO NDI U-]potentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?YO ND] U["D N/ADY0 NDI U- N/AD"Y0 NDI UD N/AD--YZ NEI UDEN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 67 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 3 of 5Status: Yv NEI UMISeismic Walkdown Checklist (SWC) SWELl- 013Equipment ID No. BC-1-1A Equip. Class' 16Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-1Other 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. 1A46/IPEEE
-Screening Evaluation Work Sheet, SSEL Line No. 000061Evaluated by: Marcus Hecht-Nielsen a:&#xfd;,&#xfd;/.Raymond Tworek -_ o !I i/IDate: 10-09-2012 10-09-2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 68 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: YZ N[3 UO]Seismic Walkdown Checklist (SWC) SWELl- 013Equipment ID No. BC-1-1A Equip. Class1 16Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-1Photographs Note: BNO PHOTONote:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 69 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 5 of 5Status: Nil UiLSeismic Walkdown Checklist (SWC) SWELl- 013Equipment ID No. BC-i-1A Equip. Class' 16Equipment Description 125V DC MAIN STATION BATTERY CHARGER A ON DC-1NO PHOTO NO PHOTONote:Note:EN-DC-168 REV 0 I.Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 70 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 1 of 5Status: Y0 NEI UMSeismic Walkdown Checklist (SWC) SWELl- 014Equipment ID No. B-AS-2 Equip. Class1 15 -BATTERIES ON RACKSEquipment Description 125V DC STATION BATTERY ON BUS DC-2ASLocation:
Bldg. TB Floor El. 252 Room, Area EDGR AManufacturer, Model, Etc. (optional but recommended)
CID. KC-9. 59 cells, flat plateInstructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on theSWEL. The space below each of the following questions may be used to record the results of Judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YZ NO2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?Y[@ NO] U' N/ADY0 NE] UD N/ArY0 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. 1Page 71 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: Y0 NED U--Seismic Walkdown Checklist (SWC) SWELl- 014Equipment ID No. B-AS-2 Equip. Class1 15 -BATTERIES ON RACKSEquipment Description 125V DC STATION BATTERY ON BUS DC-2AS5. 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 whichanchorage configuration verification Is required.)
See drawing G-1915726. Based on the above anchorage evaluations, is the anchorage free of YO NOI UO-potentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?YZ NOI Ur NIAOYZ 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. 1Page 72 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 3 of 5Status: YO N[] Ur-Seismic Walkdown Checklist (SWC) SWELl- 014Equipment ID No. B-AS-2 Equip. Class1 15- BATTERIES ON RACKSEquipment Description 125V DC STATION BATTERY ON BUS DC-2ASOther 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. 000065See SSEL# 000328, TK-67-1A, and EDCR 82-12Drawings 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. 1Page 73 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: Y0 N-] UC1Seismic Walkdown Checklist (SWC) SWELl- 014Equipment ID No. B-AS--2 Equip. Class' 15 -BATTERIES ON RACKSEquipment Description 125V DC STATION BATTERY ON BUS DC-2ASPhotographs vwww,-.7P 46"W90-. O-Ao" VW&b'lEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Attachment C Page 74 of 505ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORMSheet 5 of 5Status: YO NE] Ur"Seismic Walkdown Checklist (SWC) SWELl- 014Equipment ID No. B-AS-2 Equip. Class1 15- BATTERIES ON RACKSEquipment Description 125VDC STATION BATTERY ON BUS DC-2ASNO PHOTONote:EN-DC-168 REV 0 U.Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 75 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet I of 5Status: YZ NE] U--Seismic Walkdown Checklist (SWC) SWELl- 015Equipment ID No. B-1-1B Equip. Class1 15Equipment Description 125V DC STATION BATTERY ON DC-2Location:
Bldg. CB Floor El. 262' Room, Area CABLE VAULTManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YO NEI2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks In the concrete near theanchors?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. 1Page 76 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: YO Nr3 UE-Seismic Walkdown Checklist (SWC) SWELl- 015Equipment ID No. B-1-1B Equip. Class1 15Equipment Description 125V DC STATION BATTERY ON DC-25. 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 whichanchorage configuration verification is required.)
See drawings B- I- 1A and B- 1-1B6. Based on the above anchorage evaluations, is the anchorage free of Yo NO UOpotentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?Y0 NO U[-] N/A-YN NEI ur- N/A[JYZ N] U-] N/Ar]Yv NO u[]EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 77 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: YZ N] UL-]Seismic Walkdown Checklist (SWC) SWELl- 015Equipment ID No. B-1-1B Equip. Class1 15Equipment Description 125V DC STATION BATTERY ON DC-2Other 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 1Drawing 5920-11884, Duke Engineering
& Services, Sheets 1-4Drawings B- I-1A and B- I- 1BA46/IPEEE
-Screening Evaluation Work Sheet, SSEL Line No. 000067Evaluated by: Marcus
' Date: 10-09-2012 Ra-mond TworekLOW'-.i10-09-2012 EN-DC-1 68 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 78 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: Y0 NO' UL-Seismic Walkdown Checklist (SWC) SWELl- 015Equipment ID No. B-I-1B Equip. Class1 15Equipment Description 125V DC STATION BATTERY ON DC-2Photographs Note: B-1-1EEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 83 of 505Attachment CATTACHMENT 9.6Sheet 4 of 5SEISMIC WALKDOWN CHEcKusT FORMStatus: YNI NEI Ur-LSeismic Walkdown Checklist (SWC) SWELl- 016Equipment ID No. DC-I Equip. Class' 14Equipment Description 125VDC DISTR PNL DC-1 1600AMPPhotoaraphs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 84 of 505Attachment CATTACHMENT 9.6SEISMIC WALKDOWN CHECKUST FORMSheet 5 of 5Status: YN NEI UEJSeismic Walkdown Checklist (SWC) SWELl- (Equipment ID No. DC-1 Equip. Class1Equipment Description 125VDC DISTR PNL DC-1 1600NO PHOTONote:Note: 125VDC Distr. PnL DC-1EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 89 of 505Attachment CASTAcHMENT 9.6SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: YZ NEL U[ISeismic Walkdown Checklist (SWC) SWELl- (Equipment ID No. DC-2 Equip. Class',Equipment Description 125V DC DISTR PNL DC-2 1600EN.DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 90 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: Y0 NEl UE1Seismic Walkdown Checklist (SWC) SWELl- 018Equipment ID No. DC-ECCS-B Equip. Class1 14 -DISTRIBUTION PANELSEquipment Description 24 VDC ECCS PNL (B)Location:
Bldg. RB Floor El. 303' Room, Area EASTManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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[@ NEIof 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 surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?Y0 NE] UDI N/AD]YZ NEI] U- N/AE]YZ NEI U[3 N/AQI 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. 1Page 91 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: YZ NEI UOSeismic Walkdown Checklist (SWC) SWELl- 018Equipment ID No. DC-ECCS-B Equip. Class1 14- DISTRIBUTION PANELSEquipment 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 whichanchorage 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 Effects7. 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 freeof potentially adverse seismic interaction effects?YO NOI UO N/AOY0 NOI UEr N/AOY0 NO ur N/AOYS NEI UOEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 92 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORMSheet 3 of 5Status: Y N N l U[Seismic Walkdown Checklist (SWC) SWELl- 018Equipment ID No. DC-ECCS-B Equip. Class1 14 -DISTRIBUTION PANELSEquipment 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 fullyengaged.
About 50% of the nut is engaged.
Remaining nuts are fullyengaged.
With this observation the panel is secured and will not beimpacted 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 wasopened by qualified plant personnel.
Reference Documents:
A46/IPEEE
-SSEL Line No. 000081.A46/IPEEE
-SSEL Line No. 00008 1 (attachment A)kle'D I11&#xfd; 10Evaluated bv: Kirit ParikhDate: 10/11/2012 Randy SteDhensI c31~~/2brL 10/11/2012 I VEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 93 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: Yv NE] U[3Seismic Walkdown Checklist (SWC) SWELl- 018Equipment ID No. DC-ECCS-B Equip. Class1 14- DISTRIBUTION PANELSEquipment Description 24 VDC ECCS PNL (B)Photographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 94 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 5 of 5Status: YZ NO Ur-Seismic Walkdown Checklist (SWC) SWELl- 018Equipment ID No. DC-ECCS-B Equip. Class1 14 -DISTRIBUTION PANELSEquipment 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 fullyengaged.EN-DC-168 REV 0 0fEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 95 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: Y[0 N[] UMSeismic Walkdown Checklist (SWC) SWELl- 019Equipment ID No. MCC-9C Equip. Class' 01 -Motor Control CentersEquipment Description 480V ESS AC MCC-9C -DIESEL 1A ROOM (SI)Location:
Bldg. TB Floor El. 252 Room, Area EDG AManufacturer, Model, Etc. (optional but recommended)
Westinohouse.
Tvne WInstructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an Item of equipment on theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
Y[ NEI2. Is the anchorage free of bent, broken, missing or loose hardware?
On October 11, 2012 revisited the unit and removed upper and lowerpanels. With upper panel removed was able to verify attachment ofangle to unit.3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
On October 11, 2012 revisited the unit and removed upper and lowerpanels. With upper panel removed was able to verify attachment ofangle to unit.4. Is the anchorage free of visible cracks in the concrete near theanchors?Crack on eastside of the floor. The crack goes thru the grout pad andthe comer of house pad (SE Comer). By engineering judgment thecrack, hairline, is not a seismic issue. No photos of crack includedbecause 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[-'IYO N[O U[3 N/AOEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 96 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 2 of 5Status: YN NEI U--Seismic Walkdown Checklist (SWC) SWELl- 019Equipment ID No. MCC-9C Equip. Class1 01 -Motor Control CentersEquipment 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 whichanchorage configuration verification is required.)
See SK92403-06-A
: 6. Based on the above anchorage evaluations, is the anchorage free of Yo NOI U[3potentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?YZ NOI U0 N/A[]YZ NO- UL N/ACYZ NEI UC- N/AC1YZ NEI Iu-IEN-DC-168 REV 0 Engineering Report No. VTY-RPT-1 2-00019Rev. 1Page 97 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORMSheet 3 of 5Status: YO N[-] U-Seismic Walkdown Checklist (SWC) SWELl- 019Equipment ID No. McC-9C Equip. Class' 01 -Motor Control CentersEquipment 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 giventhe 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. 000085Evaluated by: Marcus Hecht-Nielsen Raymond Tworek iav f '- i /12"Date: 10-11-1210-11-12EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 98 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 4 of 5Status: Y0 N[] uLISeismic Walkdown Checklist (SWC) SWELl- 019Equipment ID No. MCC-9C Equip. Class' 01 -Motor Control CentersEquipment Description 480V ESS AC MCC-9C -DIESEL 1A ROOM (SI/)Photographs NO PHOTONote:Note:EN-DG-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 99 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKOOWN CHECKLIST FORMSheet 5 of 5Status: Yv NEI UI-Seismic Walkdown Checklist (SWC) SWELl- 019Equipment ID No. MCC-9C Equip. Class' 01 -Motor Control CentersEquipment Description 480V ESS AC MCC-9C -DIESEL 1A ROOM (SIlDNO PHOTO NO PHOTONote:Note:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 100 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 1 of 5Status: YN NEI Ul'Seismic Walkdown Checklist (SWC) SWELl- 020Equipment ID No. MCC-9D Equip. Class1 01Equipment Description 480V ESS AC MCC-9D -REACTOR BLDGLocation:
Bldg. RB Floor El. 252' Room, Area Reactor BuildinoManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
Y-I NO2. Is the anchorage free of bent, broken, missing or loose hardware?
Two small screws used to attach the South end panel are missing.
Seephoto 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 thefasteners (2 screws) clamping force. The end panel is securelyfastened.
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?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. 1Page 101 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 2 of 5Status: NE] UE-]Seismic Walkdown Checklist (SWC) SWELl- 020Equipment ID No. MCC-9D Equip. Class1 01Equipment Description 480V ESS AC MCC-9D -REACTOR BLDG5. 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 whichan 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 concernswith internal components.
Anchorage is secure at the boltedconnections.
No adverse seismic condition.
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?YZ NE] U-' N/A[-'YZ NEi U-] N/A["]Y0 NE-] U[D N/ADlY[ NEI UD-1EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 102 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: Y; NM UMSeismic Walkdown Checklist (SWC) SWELl- 020Equipment ID No. MCC-9D Equip. Class' 01Equipment Description 480V ESS AC MCC-9D -REACTOR BLDGOther 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 wereopened by qualified plant personnel exposing the anchorage connections.
Reference Documents:
A46/IPEEE
-SSEL Line No. 000088Evaluated by: Kirit ParikhIO 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. 1Page 103 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheot 4 of 5Status: YO NO] UL-Seismic Walkdown Checklist (SWC) SWELl- 020Equipment ID No. MCC-9D Equip. Class1 01Equipment Description 480V E$S AC MCC-9D -REACTOR BLDGPhotoaranha 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. 1Page 104 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: YO N1J Ur-Seismic Walkdown Checklist (SWC) SWELl- 020Equipment ID No. MCC-9D Equip. Class' 101Equipment Description 480V ESS AC MCC-9D -REACTOR BLDGIiNote: Two small screws are missing from theSouth end of MCC-9D.See item I comment onpage 1.EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 105 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 1 of 5Status: YZ N[] UL-1Seismic Walkdown Checklist (SWC) SWELl- 021Equipment ID No. MCC-8B Equip. Class' 01Equipment Description 480V ESS AC MCC-8B -REACTOR BLDG (Si)Location:
Bldg. RB Floor El. 280' Room, AreaManufacturer, Model, Etc. (optional but recommended)
Westinghouse.
Tvye WInstructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YZ NEI2. 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 surfaceoxidation?
See comments.
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?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 notvisible.
: However, the protective cover shows no signs of stress orcracking 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. 1Page 106 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 2 of 5Status: YED NO UI"Seismic Walkdown Checklist (SWC) SWELl- 021Equipment ID No. MCC-8B Equip. Class' 01Equipment 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 whichanchorage configuration verification is required.)
See drawing 5920-11776
: 6. Based on the above anchorage evaluations, is the anchorage free of Y0 NOI UrIpotentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?Y0 NEI UI- N/AD-Y10 NEi U[-] N/A[-]YO NFI U-If N/AflYN NEI UE1EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 107 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: YN NC U[1-Seismic Walkdown Checklist (SWC) SWELl- 021Equipment ID No. MCC-8B Equip. Class1 01Equipment 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 ascrew missing on panel 8M. Neither issue is a seismic concern, see CR-VTY-2012-04979 forcorrective action.2. Was unable to view anchorage on 10-09-2012.
Returned on 10-11-2012 and removed thebottom panels at locations 1M, 4M, 6M, and 9M and top panels at IC, 5C, 6B, and 1OBL, aswell as, the vertical panel between MCC 7A and MCC 8B come together.
With the aid of aflashlight and a telescopic inspection mirror was able to verify anchorage.
Reference Documents:
Drawing 5920-11776, Sheets 1-2, Rev.0A46/IPEEE
-Screening Evaluation Work Sheet, SSEL Line No. 000090Evaluated by: Marcus Hecht-Nielsen RayondTw rek P-~o-LMA Lp ll 1Date: 10-11-2012 10-11-2012 EN-DC-168 REV 0
&deg;/Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 108 of 505Attachment CATTACHMENT 9.6 SEiSMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: Y0 NO1 U[-]Seismic Walkdown Checklist (SWC) SWELl- 021Equipment ID No. MCC-8B Equip. Class' 01Equipment Description 480V ESS AC MCC-88 -REACTOR BLDG (SD)Photographs EN-DC-168 REV 0 e/wEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 109 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 5 of 5Status: YO Nfl" UL-Seismic Walkdown Checklist (SWC) SWELl- 021Equipment ID No. MCC-SB Equip. Class1 01Equipment Description 480V ESS AC MCC-B8 -REACTOR BLDG (SI)EN-DC-168 REV 0 VEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 110 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKIDOWN CHECKLIST FORMSheet I of 5Status: Y0 NEI ULSeismic Walkdown Checklist (SWC) SWELl- 022Equipment ID No. MCC-gB Equip. Class' 01Equipment Description 480V ESS AC MCC-9B -REACTOR BLDG (SiI)Location:
Bldg. RB Roor El. 280' Room, AreaManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YO NEI2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?There is a protective cover on the concrete and the concrete Is notvisible.
: However, the protective cover shows no signs of stress orcracking and Is seismically okay by engineering judgment.
'Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.
YO NC" UCI N/ACrYZ NM UCr N/A[]YZ NCI UCr N/AC"EN-DC-168 REV 0 Engineering Report No. VTY-RPT-1 2-00019Rev. 1Page 111 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: Y0 NEI UO]Seismic Walkdown Checklist (SWC) SWELl- 022Equipment ID No. MCC-9B Equip. Class1 01Equipment 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 whichanchorage 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 Effects7. 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 freeof potentially adverse seismic interaction effects?Y0 NE] u[-] N/Ar-Y[ N[3 UE] N/ArYv NE] uE] N/A]YZ Ni: UE]EN-DC-168 REV 0 4-Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 112 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: YZ NO U'Seismic Walkdown Checklist (SWC) SWELl- 022Equipment ID No. MCC-9B Equip. Class' 01Equipment 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 Wentto verify that the electrician tightened all the screw (on 10-11-2012 while we were opening the panels to verify anchorage) and all screwsare 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 thebottom 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 aflashlight and a telescopic inspection mirror was able to verify anchorage.
Reference Documents:
Drawing 5920-11776, Sheets 1-2, Rev.0A46/IPEEE
-Screening Evaluation Work Sheet, SSEL Line No. 000092Evaluated by: Marcus Hecht-Nielsen Date: 10-11-2012 Q&#xfd;*.--) q,9.0-&#xfd; 10 1 1 g I I U-Ravmond Tworek10-11-2012
...........
r " .- TT ... .. .. I lEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 113 of 505Attachment CATTACHUEp Sheet 4 of5T9.6SEISMIC WALKDOWN CHECKLIST FORM5Status: YN NEI U--Seismic Walkdown Checklist (SWC) SWEL1- 022Equipment ID No. MCC-98 Equip. Class'.01 Equipment Description 480V ESS AC MCC-9B -REACTOR BLDG (SII)Photographs EN-DC-168 REV 0I
*Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 114 of 505Attachment CATTACHMENT 9.6Sheet 5 of 5SEISMIC WALKDOWN CHECKUiST FORMStatus: YZ N[] UESeismic Walkdown Checklist (SWC) SWELl- 022Equipment ID No. MCC-9B Equip. Class1 01Equipment Description 480V ESS AC MCC-9B -REACTOR BLDG (SII)EN-DC-168 REV 0 9IEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 115 of 505Attachment CATTACHMEI Sheet I of5T 9.6SEISMIC WALKDOWN CHECKLIST FoRM5Status: YN NEI U[Seismic Walkdown Checklist (SWC) SWELl- 023Equipment ID No. BUS-9 Equip. Class1 02Equipment Description 480VAC SWITCHGEAR BUS NO.9 1600AMP (SII)Location:
Bldg. CB Floor El. 248' Room, Area SWGR EASTManufacturer, Model, Etc. (optional but recommended)
GE AKD-5Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
Yr- NO2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?YE[ NEI U[- NWASY[-I NEI U E] N/A0Y[-] NEI U- NWAS' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment-EN-DC-1 68 REV 0 9Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 116 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 2 of 5Status: YZ NrO Ur-Seismic Walkdown Checklist (SWC) SWELl- 023Equipment ID No. BUS-9 Equip. Class1 02Equipment 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 whichanchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of YZ NO] UOpotentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?YZ NE] UE] N/ArYZ NE] UE] N/AE]YZ NO UO N/ArYZ NEI U(']EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 117 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKOOWN CHECKLIST FORMSheet 3 of 5Status: Y0 NEI UL-Seismic Walkdown Checklist (SWC) SWELl- 023Equipment ID No. BUS-9 Equip. Class' 02Equipment 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 ~tlvr10-09-2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 118 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRMSheet 4 of 5Status: Y0 NE] U-Seismic Walkdown Checklist (SWC) SWELl- 023Equipment ID No. BUS--9 Equip. Class1 02Equipment Description 480VAC SWITCHGEAR BUS NO.9 1600AMP (SIIPhotographs NO PHOTONote:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. IPage 119 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 5 of 5Status: Y0] NL-J UE'-Seismic Walkdown Checklist (SWC) SWELl- 023Equipment ID No. BUS-9 Equip. Class1 02Equipment Description 480VAC SWITCHGEAR BUS NO.9 1600AMP (SII)NO PHOTO NO PHOTONote: Note:EN-DC-168 REV 0 IFEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 120 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: Y0 NI] U"]Seismic Walkdown Checklist (SWC) SWELl- 024Equipment ID No. BUS-3 Equip. Class1 03Equipment Description 4KV- 4160V SWITCHGEAR BUS NO.3 1200AMP (SI)Location:
Bldg. CB Floor El. 248' Room, Area SWGR WESTManufacturer, Model, Etc. (optional but recommended)
GEInstructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YI] NO2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?Y['] NE] urI N/ASYI] N[] U[] N]ASYDI NEI u[] N/AO' Enter the equipment class name from EPRI 1025286, Appendix B: Classes of Equipment.
EN-DC-168 REV 0 V.fEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 121 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: YZ NEI U-Seismic Walkdown Checklist (SWC) SWELl- 024Equipment ID No. BUS-3 Equip. Class1 03Equipment 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 whichanchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of YO N[] U-potentially adverse seismic conditions?
Interaction Effects7. 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 freeof 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. 1Page 122 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: Nil uF-JSeismic Walkdown Checklist (SWC) SWELl- 024Equipment ID No. BUS-3 Equip. Class' 03Equipment 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. 000096Evaluated by: Marcus Hecht-Nielsen Date: 10-09-2012 RavmondTworek
~(u/'10-09-2012 EN-DC-168 REV 0 fEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 123 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: NI'] ul-]Seismic Walkdown Checklist (SWC) SWELl- 024Equipment ID No. BUS-S Equip. Class1 03Equipment Description 4KV-416OV SWITCHGEAR BUS NO.3 1200AMP (SI)Photographs Note: Bus -jNO PHOTONote:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 124 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: Y0 NE] Ul]Seismic Walkdown Checklist (SWC) SWELl- 024Equipment ID No. BUS-3 Equip. Class' 03Equipment Description 4KV- 4160V SWITCHGEAR BUS NO.3 1200AMP (Sl)NO PHOTO NO PHOTONote:Note:EN-DC-168 REV 0 A h*Attachment CEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 125 of 505ATrACHMENT 9.6 SEiSMiC WALKOOWN CHECKuST FORMSheet I of 5Status: YN N[l U']Seismic Walkdown Checklist (SWC) SWELl- 025Equipment ID No. T-8-1A Equip. Class1 04Equipment Description STATION SERVICE TRANS 4160/480 BUS NO.8Location:
Bldg. CB Floor El. 248' Room, Area SWGR WESTManufacturer, Model, Etc. (optional but recommended)
ASEA BROWN BOVERI # PAL2721.
3 phase. yeRSLInstructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YZ NEI2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?YN NO UI- N/AD-]Y[O NEI UD- N/A[-DYZ 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. 1Page 126 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: Y0 NI] UMSeismic Walkdown Checklist (SWC) SWELl- 025Equipment ID No. T-8-1A Equip. Class' 04Equipment Description STATION SERVICE TRANS 4160/480 BUS NO.85. 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 whichanchorage configuration verification is required.)
See calculation VYC- 10466. Based on the above anchorage evaluations, is the anchorage free of YV NF-] u]potentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?Y"0 NI] Ur N/A-Nil U[-I N/AO--YV NEI U- N/ArYO N[I] UrNAEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. .1Page 127 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: Y0 NEI ur-ISeismic Walkdown Checklist (SWC) SWELl- 025Equipment ID No. T-8-1A Equip. Class' 04Equipment Description STATION SERVICE TRANS 4160/480 BUS NO.8Other 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. 000101Calculation VYC -1046Evaluated 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. 1Page 128 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORMSheet 4 of 5Status: Y0 NO UL-Seismic Walkdown Checklist (SWC) SWELl- 025Equipment ID No. T-8-1A Equip. Class1 04Equipment Description STATION SERVICE TRANS 4160/480 BUS NO.8Photographs EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 129 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRMSheet 5 of 5Status: Y[ NOI ULiMSeismic Walkdown Checklist (SWC) SWELl- 025Equipment ID No. T-8-1A Equip. Class1 04Equipment Descdption STATION SERVICE TRANS 4160/480 BUS NO.8NO PHOTONO PHOTONote: Note:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 130 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMShoot I of 5Status: YZ N[I Ur1Seismic Walkdown Checklist (SWC) SWELl- 026Equipment ID No. TK-4-1A Equip. Class1 21Equipment Description CONDENSATE STORAGE TANKLocation:
Bldg. YARD Floor El. 252' Room, Area OUTSIDEManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
Yr] NO2. Is the anchorage free of bent, broken, missing or loose hardware?
Entire tank covered with Insulation.
Anchorage is not visible.
Cannot bedetermined that these are true but evidence of visual inspection aroundthe 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 surfaceoxidation?
Same as above4. Is the anchorage free of visible cracks in the concrete near theanchors?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. 1Page 131 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: YZ NO! Ur]Seismic Walkdown Checklist (SWC) SWELl- 026Equipment ID No. TK-4-1A Equip. Class' 21Equipment Description CONDENSATE STORAGE TANK5. 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 whichanchorage configuration verification is required.)
: 6. Based on the above anchorage evaluations, is the anchorage free of YZ NEI Urnpotentially adverse seismic conditions?
Entire tank covered with insulation.
Anchorage Is not visible.However, based on reviewing equipment documentation (seereference page 3) and seeing no modifications surrounding theanchorage, it Is our engineering judgment through area walkdownand visual inspections that no adverse seismic condition exists.Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?YEI NEI UE! NWASYS NE! u[:1 N/AE!Y0 NE"] uEr N/A[]YS N3 U[-]AEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 132 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: Y0 NEI U"-Seismic Walkdown Checklist (SWC) SWELl- 026Equipment ID No. TK-4-1A Equip. Class' 21Equipment Description CONDENSATE STORAGE TANKOther 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. 000103j~~kL- lOC2e/LEvaluated by: KirOt ParlkhDate: 102/022012 RadStephens
/0/W41J 4.S.4Ia/i -210/0212012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 133 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: Y0 N[] U-I]Seismic Walkdown Checklist (SWC) SWELl- 026Equipment ID No. TK-4-1A Equip. Class1 21Equipment Description CONDENSATE STORAGE TANKPhotographs Note: Condensate Storage Tank -Anchorage covered by insulation.
No visible cracks around thetank foundation EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 134 of 505Attachment CATTACHMEI Sheet 5 ofNT 9.6SEISMIC WALKDOWN CHECKUST FORM5Status: YZ Nr-] Ui-Seismic Walkdown Checklist (SWC) SWELl- 026Equipment ID No. TK-4-1A Equip. Class1 21Equipment Description CONDENSATE STORAGE TANKEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 135 of 505Attachment CATrACHMENT 9.6 SEISMIC WALKOOWN CHECKLIST FORMSheet I of 5Status: YZ NEI UO-Seismic Walkdown Checklist (SWC) SWELl- 027Equipment ID No. P.44-1A Equip. Class1 0-5 HORIZONTAL PUMPSEquipment Description HPCI/HPCI PUMPLocation:
Bldg. RB Floor El. 213' Room, Area HPCIManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YO NEI2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?Yv NEI UE- N/A[-Y[9 NO UC N/ACYO 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. 1Page 136 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: Y0 N[-' U']Seismic Walkdown Checklist (SWC) SWELl- 027Equipment ID No. P-44-1A Equip. Class1 0-5 HORIZONTAL PUMPSEquipment Description HPCI/HPCI PUMP5. 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 whichanchorage configuration verification is required.)
See SSEL Line No. 000116 (and associated calculation) and drawingNo. 5920-0622.
: 6. Based on the above anchorage evaluations, is the anchorage free of YZ NEI uit]potentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?Y0 N-I UtJ N/At]YZ NEI Ut] N/At]Y0 NEI Ut] N/At]YYN U--uEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 137 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: Y[9 NI] U--Seismic Walkdown Checklist (SWC) SWELl- 027Equipment ID No. P-44-IA Equip. Class' 0-5 HORIZONTAL PUMPSEquipment Description HPCI/HPCI PUMPOther Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could YO Ni[] Uradversely 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. 000116Drawing No. 5920-0622 Evaluated by: Kirit ParikhtZpav6&#xfd;1C4-tol 110 to I I.Randy Steohenn 2 w U33J~t-)-2-O kd (ate: 10/09/2012 1 W0/09/2012
&#xfd;jEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 138 of 505Attachment CATTACHmENT 9.6 SEISIuC WALKDOWN CHECKLST FoRMSheet 4 of 5Status: YZ N-- U'-Seismic Walkdown Checklist (SWC) SWELl- 027Equipment ID No. P-44-IA Equip. Class' 0-5 HORIZONTAL PUMPSEquipment Descriptlon HPCL/HPCI PUMPPhotographs NO PHOTONote:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 139 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKuST FORMSheet 5 of 5Status: Y0 NCl U-ISeismic Walkdown Checklist (SWC) SWELl- 027Equipment ID No. P-44-1A Equip. Class1 0-5 HORIZONTAL PUMPSEquipment Description HPCI/HPCI PUMPNO PHOTO NO PHOTONote: Note:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 140 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 1 of 5Status: YZ NO UOSeismic Walkdown Checklist (SWC) SWELl- 020Equipment ID No. PS-23-84-1 Equip. Class1 18- INSTRUMENTS ON THE RACKEquipment Description HPCI/PUMPSUCTION PRESSURE SWITCHLocation:
Bldg. RB Floor El. 213' Room, Area HPCIManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 NOof 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 surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?Y0 NOI UD N/AO"]YED NO UO N/AOYZ 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 2-00019Rev. 1Page 141 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: Y0 NO U'-Seismic Walkdown Checklist (SWC) SWELl- 028Equipment ID No. PS-23-84-1 Equip. Class1 18- INSTRUMENTS ON THE RACKEquipment Description HPCI/PUMPSUCTION PRESSURE SWITCH5. 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 whichanchorage configuration verification is required.)
See SQUG, November 9-13, 1992, Section VB7, Equipment Category7 Instruments on Racks6. Based on the above anchorage evaluations, is the anchorage free of Y(@ N[] UEDpotentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?Y0 NOj Un N/ADYN NDI U"] N/ADIYN NO] u[1 N/A[D]YN NEI U-]EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 142 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 3 of 5Status: Y0 NEJ' UL-JSeismic Walkdown Checklist (SWC) SWELl- 028Equipment ID No. PS-23-84-1 Equip. Class1 18- INSTRUMENTS ON THE RACKEquipment Description HPCI/PUMPSUCTION PRESSURE SWITCHOther Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that could Y0 NEI U[Jadversely 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. 000125SQUG, November 9-13, 1992, Section VB7, Equipment Category 7 Instruments on RacksEvaluated by: Kirit Parikhtoile 12.012-DawRan&y SteohensIC.4wRJQ-
~t4((02te: 10/09/2012 10/09/2012 EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 143 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: YZ NEl UI-Seismic Walkdown Checklist (SWC) SWELl- 028Equipment ID No. PS-23-84-1 Equip. Class1 18- INSTRUMENTS ON THE RACKEquipment Description HPCIIPUMPSUCTION PRESSURE SWITCHPhotographs NO PHOTONote:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 144 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: Y0 NEL U[-]Seismic Walkdown Checklist (SWC) SWELl- 028Equipment ID No. PS-23-84-1 Equip. Class' 18- INSTRUMENTS ON THE RACKEquipment Description HPCI/PUMPSUCTION PRESSURE SWITCHNO PHOTO NO PHOTONote: Note:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-1 2-00019Rev. 1Page 145 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: Y0D N[--] UE-Seismic Walkdown Checklist (SWC) .SWELl- 031Equipment ID No. TEF-3 Equip. Class1 09Equipment Description DG B ROOM VENTILATION/EXAUST FANLocation:
Bldg. TB Floor El. 252' Room, Area EDGR BManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?There is a hairline crack in the upper right hand corner. No seismicconcern 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 P0Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 146 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: Y0 N[5 U'-Seismic Walkdown Checklist (SWC) SWELl- 031Equipment ID No. TEF-3 Equip. Class1 09Equipment Description DG B ROOM VENTILA TION/EXAUST FAN5. 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 whichanchorage configuration verification is required.)
See A46/IPEEE
-Screening Evaluation Work Sheet, SSEL Line No.0001456. 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 Effects7. 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 freeof potentially adverse seismic interaction effects?YO NC U- N/ACNCI UC N/ACYr" NC UC N/A0YZ NEI UMEN-DC-168 REV 0 PEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 147 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 3 of 5Status: YE0 NOI UoISeismic Walkdown Checklist (SWC) SWELl- 031Equipment ID No. TEF-3 Equip. Class' 09Equipment Description DG B ROOM VENTILA TION!EXAUST FANOther 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. ooo145Evaluated 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. 1Page 148 of 505Attachment CATTAcHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: Y( NI] UE'Seismic Walkdown Checklist (SWC) SWELl- 031Equipment ID No. TEF-.I Equip. Class1 09Equipment Descrption DG B ROOM VENTILATION/EXAUST FANPhotographs EN-DC-168 REV 0
.PEngineering Report No. VTY-RPT-12-00019 Rev. 1Attachment C Page 149 of 505ATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: YZ NEI UO-Seismic Walkdown Checklist (SWC) SWELl- 031Equipment ID No. TrEF-3 Equip. Class' 09Equipment Description DG BROOM VENTILA TION/EXAUST FANNo Photo No PhotoNote: Note:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 150 of 505Attachment CATrACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet I of 5Status: YI NCI UL'Seismic Walkdown Checklist (SWC) SWELl- 032Equipment ID No. RRU-8 Equip. Class1 10Equipment Description SW/ECCS RM COOLINGLocation:
Bldg. RB Floor El. 213' Room, Area SECRManufacturer, Model, Etc. (optional but recommended)
HKPORTER-MARLO COIL WORKS. Model# 41-5,23-HInstructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YD NO2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?YO NC] U[- N/ACY0 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. 1Page 151 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKUST FORMSheet 2 of 5Status: Y0 N[] U[3Seismic Walkdown Checklist (SWC) SWELl- 032Equipment ID No. RRU-8 Equip. Class1 10Equipment Description SWIECCS RM COOLING5. 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 whichan 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 Effects7. 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 freeof potentially adverse seismic interaction effects?YO NOI UO- N/AO"Y1Z NOl U[3 N/AOYZ NOI uO" N/AOYZ Nr-I UEN-DC-168 REV 0 Attachment CEngineering ATTACHMENT 9.6 SShoot 3 of 5Seismic Walkdown Checklist (SWC) SWELl- 032Equipment ID No. RRU-8 Equip. Class1 10Equipment Description SW/ECCS RM COOLINGOther Adverse Conditions
: 11. Have you looked for and found no other seismic conditions that couldadversely affect the safety functions of the equipment?
Report No. VTY-RPT-12-00019 Rev. 1Page 152 of 505EISMIC WALKDOWN CHECKLIST FORMStatus: YZ N-] U0YO NEI UOComments (Additional pages may be added as necessary)
Reference Documents:
A46/1PEEE
-SSEL Line No. 000164Evaluated 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 2-00019Rev. 1Page 153 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: Yv NE- UE-Seismic Walkdown Checklist (SWC) SWELl- 032Equipment ID No. RRU-8 Equip. Class1 10Equipment Description SW/ECCS RM COOLINGPhotographs I IEN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 154 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FoRMSheet 5 of 5Status: Y[ NEL UM-Seismic Walkdown Checklist (SWC) SWELl- 032Equipment ID No. RRU-8 Equip. Class' 10Equipment Description SW/ECCS RM COOLINGNO PHOTO NO PHOTONote:Note:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 155 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKOOWN CHECKLIST FORMSheet 1 of 5Status: YZ NEI UEJSeismic Walkdown Checklist (SWC) SWELl- 033Equipment ID No. PT-2-3-52C Equip. Class1 18Equipment Description CS, RHR PERMISSIVE Location:
Bldg. RB Floor El. 252' Room, AreaManufacturer, 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 theSWEL. The space below each of the following questions may be used to record the results of judgments andfindings.
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 oneof the 50% of SWEL items requiring such verification)?
YO NEI2. Is the anchorage free of bent, broken, missing or loose hardware?
: 3. Is the anchorage free of corrosion that is more than mild surfaceoxidation?
: 4. Is the anchorage free of visible cracks in the concrete near theanchors?Equipment has a steel attachment.
YED NEI UDi N/ADYN 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. 1Page 156 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 2 of 5Status: Y0 NEI U'-Seismic Walkdown Checklist (SWC) SWELl- 033Equipment ID No. PT-2-3-52C Equip. Class1 18Equipment 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 whichan anchorage configuration verification is required.)
See SQUG, November 9-13, 1992, Section VB7, Equipment Category7 Instruments on Racks.6. Based on the above anchorage evaluations, is the anchorage free of Y[9 N[: U[]potentially adverse seismic conditions?
Interaction Effects7. 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 freeof potentially adverse seismic interaction effects?YZ NEI UD" N/AD-]Y0 ND'l U'- N/AD-Y0 ND'- UD-] N/AD]YN NEI DU[rEN-DC-168 REV 0 44Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 157 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 3 of 5Status: Y0 NC] UL]Seismic Walkdown Checklist (SWC) SWELl- 033Equipment ID No. PT-2-3-5C_
Equip. Class1 18Equipment 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. 0A46/IPEEE
-Screening Evaluation Work Sheet, SSEL Line No. 000174SQUG, 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...kFCD"Raymond Twnrak10-04-2012
* ,
* m *
* IEN-DC-168 REV 0 AEngineering Report No. VTY-RPT-12-00019 Rev. 1Page 158 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 4 of 5Status: Y0 N[] U[]Seismic Walkdown Checklist (SWC) SWELl- 033Equipment ID No. PT-2-3-52C Equip. Class1 18Equipment Description CS. RHR PERMISSIVE Photographs NO PHOTONote:EN-DC-168 REV 0 Engineering Report No. VTY-RPT-12-00019 Rev. 1Page 159 of 505Attachment CATTACHMENT 9.6 SEISMIC WALKDOWN CHECKLIST FORMSheet 5 of 5Status: Y0 NE] Ur-LSeismic Walkdown Checklist (SWC) SWELl- 033Equipment ID No. PT-2-3-52C Equip. Class1 18Equipment Description CS, RHR PERMISSIVE NO PHOTO NO PHOTONote:Note:EN-DC-168 REV 0}}

Latest revision as of 06:42, 11 January 2025

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