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Sequoyah, Unit 2, Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report
	ML13282A233
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Site:	Sequoyah
Issue date:	09/26/2013
From:	; WorleyParsons Ltd
To:	; Office of Nuclear Reactor Regulation
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SEQUOYAH NUCLEAR PLANT -UNIT 2FUKUSHIMA NEAR-TERM TASK FORCERECOMMENDATION 2.3: SEISMICRESPONSE REPORTI 26-September-2013 WorleyParsons 633 ChestnUt St. Suite 400Chattanooga TN, 37450Tel: 423-757-8020 Fax: 423-757-5869 www.worleyparsons.com WorleyParsons Services Pty LtdABN 61 001 279812© Copyright 2013 WorleyParsons Services Pty Ltd NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2REV DESCRIPTION ORIG REVIEW WORLEY- DATE CUENT DATEPARSONS AP OVAL1 SON Unit 2Simic 4 -a 6Ls A f.J. EdgarWalkdown Repon L.Titlinaltis 4^&zmmers JEdgarI2 REVISION LOGTitle: Sequoyah Nuclear Plant -Unit 2 Fukushima Near-Term Task ForceRecommendation 2.3: Seismic Response ReportRevision DESCRIPTION OF REVISION DateNo. Approved01Initial IssueRevised to add additional references and incorporate lessons learned from self-assessment internal audit and U.S. Nuclear Regulatory Commission auditAdded Sections:

Revision Loa (pages 2A-2C)* 4.3 SWEL Finalization (page 19): added section to explain finalization ofSeismic Walkdown Equipment Lists (SWELs).Revised Sections:

Title Page: Revised issue date* Signature Page: Updated name of originator and revised issue date* Table of Contents (page 3): Updated page numbering for entire report bodyto accommodate the revisions outlined below -report body length increased from 23 pages to 34 pages; updated page references for the appendices toreflect revised page numbering scheme12-Nov-2012 26-Sep-2013

1. Executive'Summary (page 4): made minor wording changes in the firstand second paragraphs

2.3 Structures (pages 7-8): added references from Sequoyah Nuclear PlantLiving Final Safety Analysis Report (FSAR)* 3.1 Equipment Selection Personnel (page 9): expanded descriptions of theapplicable experience of equipment selection personnel

3.2 Seismic Walkdown Engineers (pages 9-10): expanded descriptions ofthe applicable experience of seismic walkdown engineers (SWEs); addedexplanatory notes about training of SWEs* 3.3 Licensing Basis Reviewers (page 10): expanded descriptions of theapplicable experience of the Licensing Basis Reviewers

3.4 IPEEE Vulnerability Incorporation Personnel (pages 10-11): revisedsection title, made minor wording change, and added explanatory notesabout the IPEEE vulnerability incorporation process0 3.5 Peer Review Team (page 11): expanded descriptions of experience ofmembers of the Peer Review Team and added notes about calculation ofHCLPF capacities

4. Selection of Structures, Systems and Components (page 12): made minorwording changes and condensed the two existing paragraphs to one* 4.1 SWEL 1 Selection (pages 12-17): added descriptive notes about SWEL1 selection

process, as well as Figure 2 (SWEL 1 Selection Process)Table 2(IPEEE Enhancements),

Table 3 (CDF Risk Rankings),

and Table 4 (LERFRisk Rankings)

4.2 SWEL 2 Selection (pages 17-18): added descriptive notes about SWEL2 selection

process, as well as Figure 3 (SWEL 2 Selection Process)0 5. Seismic Walkdowns and Area Walk-Bys (page 20): revised wording insecond paragraph and added explanatory notes about Service Requests(SRs) generated during the course of the walkdowns which were not relatedto potentially adverse seismic conditions

__________

.1 £TVA 10534 [8-1995]2A REVISION LOGTitle: Sequoyah Nuclear Plant -Unit 2 Fukushima Near-Term Task ForceRecommendation 2.3: Seismic Response ReportRevision DESCRIPTION OF REVISION DateNo. Approved.5.1 Seismic Walkdown Procedure (page 21): revised explanation ofanchorage configuration count and added explanatory notes aboutanchorage for cabinets and panels* 5.2 SWC & AWC Summary (pages 21): corrected UNID in the bulleted listfor Potentially Adverse Seismic Condition 3* 6.1 Licensing Basis Calculations (pages 23-25): deleted note (second to lastsentence) in the first paragraph, added descriptive notes about the CAPprogram, and added Table 5 (Corrective Action Program Entries)0 7.1 IPEEE Description (page 28): made minor wording change (substitution of acronym) in first0 7.2 IPEEE Findings and Vulnerabilities (page 29): added resolution documentation references and associated dates to Table 6 (IPEEE Issuesand Resolutions, previously indentified as Table 2 in Report Revision 0)* 7.4 Response to IPEEE Review (pages 29-30): added explanatory notesand added applicable dates and calculation references to Table 7 (RevisedHCLPF Equipment)

8. Peer Review (pages 31-32): added notes to the bulleted list of peerreview interaction with SWEs, added Table 8 (Peer Review Team Activities),

and added explanatory notes to the summary of the peer review process0 9. References (page 33): revised description of reference

4 and addedreferences 7-110 Appendix A:o revised pagination from pages 24-59 to pages Al -A45o added explanatory note about the name shown on the EPRITraining Certificate for Karen Carboni)o minor revisions to the resume of Joshua Best, as noted on page A6(formerly page 30)o 9 pages added to document training records* Appendix B: revised pagination from pages 60-82 to pages B1 -B23; nopages added* Appendix C: revised pagination from pages 83-89 to pages Cl -C7; no pagesadded* Appendix D:o revised pagination from pages 90-96 to pages D1 -D7o minor revision to listed UNID for item #12, as shown on page D2(formerly page 91)o minor revision to listed UNID for item #13, as shown on page D2(formerly page 91)o minor revision to listed UNID for item #45, as shown on page D3(formerly page 92)o minor revision to listed UNID for item #51, as shown on page D3(formerly page 92)o minor revision to listed Description for item #66, as shown on pageD3 (formerly page 92)TVA 10534 [8-1995]2B REVISION LOGTitle: Sequoyah Nuclear Plant -Unit 2 Fukushima Near-Term Task ForceRecommendation 2.3: Seismic Response ReportRevision DESCRIPTION OF REVISION DateNo. Approved" minor revision to listed Description for item. #67, as shown on pageD3 (formerly page 92)o minor revision to listed UNID for item #74, as shown on page D3(formerly page 92)o no pages addedAppendix E:o revised pagination from pages97-335 to pages El -E239;o Seismic Walkdown Checklist (SWC) for item #23: 'Room, Area' fieldrevised from '35 -SI Pump Room 2A' to '26 -SI Pump Room 2A',as noted on page E46 (formerly page 142)o SWC for item #72: revised item description, as noted on pagesE144-E145 (formerly pages 240-241)o no pages added* Appendix F: revised pagination from pages 336-436 to pages F1-F101; nopages added" Appendix G: revised pagination from pages 437T444 to pages G1 -G8; nopages added______________

L ______________

TVA 10534 [8-1995]2C NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2Table of Contents1. Executive Sum m ary .......................................................................................................

42. Seism ic Licensing Basis ....................................................................................................

52.1. General Plant Description

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

52.2. G round Response Spectra ...........................................................................................

52.3. Structures

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

72.4. Equipm ent and System s .............................................................................................

83. Personnel Q ualifications

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

93.1. Equipm ent Selection Personnel

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

93.2, Seism ic W alkdown Engineers

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

93.3. Licensing Basis Reviewers

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

103.4. IPEEE Vulnerability Incorporation Personnel

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

103.5. Peer Review Team ....................................................................................................

114. Selection of Structures, System s and Com ponents ...........................................................

124.1, SW EL Selection

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

124.2, SW EL 2 Selection

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

174.3, SW EL Finalization

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

195. Seism ic W alkdowns and Area W alk-Bys ...........................................................................

205.1, Seism ic W alkdown Procedure

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

205.2, SW C & AW C Sum m ary .............................................................................................

216. Licensing Basis Evaluations

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

236.1. Licensing Basis Calculations

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

236.2, Potential Seism ically Adverse Conditions

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

267. IPEEE Vulnerabilities Resolution Report ...........................................................................

287.1, IPEEE Description

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

287.2, IPEEE Findings and Vulnerabilities

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

287.3, NRC IPEEE Review ..................................................................................................

297.4, Response to IPEEE Review ......................................................................................

298. Peer Review .........................................................................................................................

319. References

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

3310. Appendices

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

34Appendix A: Resum es and Training Records ...................................................................

AlAppendix B: Base List 1 ........................................................................................................

B1Appendix C: Base List 2 .................................................................................................

C 1Appendix D: SW ELs and Area List .................................................................................

D1Appendix E: SW Cs ...............................................................................................................

ElAppendix F: AW Cs .......................................................................................................

F1Appendix G : Peer Review Report ....................................................................................

G 13 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 21. Executive SummaryAs a result of the Fukushima Daiichi Nuclear Power Plant accident, the U.S. NuclearRegulatory Commission (NRC) required all US nuclear power plants to perform seismicwalkdowns to identify and address degraded, non-conforming or unanalyzed conditions and to verify the current plant configuration with the current seismic licensing basis.The NRC Near-Term Task Force (NTTF) issued a report (Reference

1) that made aseries of recommendations.

Subsequently, the NRC issued a 50.54(f)

Letter(Reference

2) that requests information to assure that these recommendations areaddressed by all U.S. nuclear power plants. This report provides guidance forconducting a seismic walkdown as required in the 50.54(f)

Letter, Enclosure 3,Recommendation 2.3: Seismic.In support of conducting the NTTF-2.3 Seismic Walkdowns, the Electrical PowerResearch Institute (EPRI) issued a report entitled Seismic Walkdown Guidance forResolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic(Reference 3 -hereafter "EPRI Seismic Walkdown Guidance")

to provide instruction foruniform seismic walkdowns of all U.S. nuclear power plants. This document alsoincludes guidance for reporting the findings of the required walkdowns.

At Unit 2 of the Sequoyah Nuclear Power Plant, a total of 119 general Seismic CategoryI equipment items were selected from the original Individual Plant Examination forExternal Events (IPEEE) Safe Shutdown Equipment List (SSEL) to fulfill therequirements of the NTTF-2.3 Seismic Walkdowns.

The selected items were located invarious environments and included many different types of equipment from multiplesafety systems.

A total of 50 areas were included for area walk-bys.

The equipment walkdowns and area walk-bys were performed by two teams, each consisting of twoseismic engineers and operations personnel, between July 13, 2012 and November 9,2012.All 119 equipment items in the Seismic Walkdown Equipment List (SWEL) werecompleted during the walkdown phase. Ten potentially adverse seismic conditions were found and addressed through the TVA Corrective Action Program.4 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 22. Seismic Licensing BasisThe seismic licensing basis for the Sequoyah Nuclear Power Plant is derived fromReference 4 -Sequoyah Nuclear Plant Living Final Safety Analysis Report Amendment 24.2.1. General Plant Description The Sequoyah Nuclear Power Plant site is located near the geographical center ofHamilton County, Tennessee, on a peninsula on the western shore of Chickamauga Lake at Tennessee River mile (TRM) 484.5. The Sequoyah site is approximately 7.5miles northeast of the nearest city limit of Chattanooga, Tennessee, 14 miles west-northwest of Cleveland, Tennessee, and approximately 31 miles south-southwest ofTVA's Watts Bar Nuclear Power Plant. The plant has been designed, built, and isoperated by TVA and contains two identical units. Each of the two units employs aPressurized Water Reactor Nuclear Steam Supply System with four coolant loops,furnished by Westinghouse Electric Corporation.

Unit 2 began commercial operation onJune 1, 1982.2.2. Ground Response SpectraThe seismic design basis for Sequoyah Nuclear Power Plant is the 0.18g horizontal peak ground acceleration represented by the modified Housner-shape spectrum forSafe Shutdown Earthquake (SSE). Operating Basis Earthquake (OBE) is one-half ofSSE ground acceleration.

Vertical ground acceleration is two-thirds of the horizontal ground acceleration.

Figure 1 illustrates the relationship between the 5% damped minimum design responsespectra and the actual site seismic design response spectra for the SSE used in thedesign of rock-supported structures.

5 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2I..40Y4 I20~a.04.0z .04 .06 .09 .1PER~IOD (SECS) *4 I IICFigure 1. -Comparison of Response Spectra for Safe Shutdown Earthquake, 5% damping6 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 22.3. Structures The design of all Class I structures and facilities conformed to the applicable generalcodes or specifications including:

American Concrete Institute (ACI)o ACI 214-77 Recommended Practice for Evaluation of Strength Results ofConcreteo ACI 315-65 Manual of Standard Practice for Detailing Reinforced Concrete Structures o ACI 318-63 Building Code Requirements for Reinforced Concreteo ACI 318-71 Building Code Requirements for Reinforced Concreteo ACI 318-77 Building Code Requirements for Reinforced Concreteo ACI 347-68 Recommended Practice for Concrete Formworko ACI 305-72 Recommended Practice for Hot Weather Concreting o ACI 211.1-70 Recommended Practice for Selecting Proportions forNormal Weight Concreteo ACI 304-73 Recommended Practice for Measuring, Mixing, Transporting, and Placing Concrete" American Society for Testing and Materials (ASTM)o 1971 ASTM Standards

" American Society of Civil Engineers (ASCE)o Paper Number 3269, "Wind Forces on Structures,"

1961" American Institute of Steel Construction (AISC)o "Specification for the Design, Fabrication, and Erection of Structural Steelfor Buildings,"

February 12, 1969* American Welding Society (AWS):o "Code for Welding in Building Construction,"

AWS D1.0-69 as modified byTVA General Construction Specification G-29C.o "Structural Welding Code," AWS D1.1-72 as modified by TVA GeneralConstruction Specification G-29C.o "Recommended Practice for Welding Reinforcing Steel, Metal Inserts, andConnections in Reinforced Concrete Connections,"

AWS D12.1-61.

Uniform Building Code, International Conference of Building Officials, LosAngeles, 1970 edition* Southern Standard Building Code, 1969 edition, 1971 revision* "Nuclear Reactors and Earthquakes,"

USAEC Report TID-7024, August 1963* Code of Federal Regulations, Title 29, Chapter XVII, Part 1910, "Occupational Safety and Health Standards"

TVA Construction Specifications:

7 ENTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2o G-2 -TVA General Construction Specification for Plain and Reinforced Concrete.

o G-29 -TVA General Construction Specification

-Process Specification forWelding and Heat Treatment.

o G-30 -TVA General Construction Specification

-Fly Ash for Use as anAdmixture in Concrete.

o G-32 -TVA General Construction Specification

-Bolt Anchors Set inHardened Concrete.

o G-34 -TVA General Construction Specification

-Repair of Concrete.

" TVA Reportso CEB 86-12 -Study of Long-Term Concrete Strength at Sequoyah andWatts Bar Nuclear Plant.o CEB 86-19-C -Concrete Quality Evaluation.

NRC Regulatory Guides:o Number 1.12 Instrumentation for Earthquakes o Number 1.31 Control of Stainless Steel Welding2.4. Equipment and SystemsNuclear Steam Supply System (NSSS) components and equipment supplied byWestinghouse have been qualified in accordance with the applicable seismicqualification requirements.

Seismic qualification requirements for Seismic Category Isystems and components are consistent with Institute of Electrical and Electronics Engineers (IEEE) Standard 344-1971.

Seismic Category I mechanical equipment hasbeen qualified in accordance with the applicable seismic qualification requirements contained in Reference 4.Class I equipment and safety related piping were designed such that stress anddeformation behavior were maintained within the allowable limits when subjected tonormal operating conditions combined with the seismic effects resulting from theresponse to the OBE. In addition, the stresses that resulted from normal loadscombined with the response to the SSE were limited so that no loss of function

occurred, and the capability of making a safe and orderly plant shutdown was maintained.

Theallowable limits are defined in appropriate design standards including:

American Society of Mechanical Engineers (ASME) Boiler and Pressure VesselCode, 1986" American National Standards Institute (ANSI) Code for Pressure Piping ANSIB31.1.0, Power Piping, 1967* AISC Specification for the Design, Fabrication and Erection of Structural Steel forBuildings, February 12, 19698 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 23. Personnel Qualifications The personnel qualification for all individuals involved in the execution of the Fukushima Near-Term Task Force Recommendation 2.3: Seismic can be found in this section.

Fullresumes for the listed individuals can be found in Appendix A of this document.

3.1. Equipment Selection Personnel The personnel who performed equipment selection and review are:* David Moore, Sequoyah Outage Management, Operations

Assessor, HumanPerformance

Manager, Operations Work Control Planning and Scheduling Manager,and Shift Manager for 35 years.* Larry Chandler, Sequoyah Reactor Operator and Senior Reactor Operator for 32years.* Phillip York, Associate Structural Engineer with 5 years of engineering experience, including seismic design for structural components and systems.

Experience includes 2 years in the nuclear power industry.

3.2. Seismic Walkdown Engineers The personnel who performed the seismic walkdowns are:* Steven Summers, B.S. Civil Engineering Technology:

Professional Engineer in thestate of Pennsylvania with 8 years of engineering experience, including seismicdesign and general condition assessment for multiple structural component typesand systems.

Experience includes 3 years in the nuclear power industry.

" Robert Malone, B.S. Civil Engineering:

Professional Engineer in the state ofPennsylvania with 7 years of engineering experience, including seismic design andgeneral condition assessment for multiple structural component types and systems.Experience includes 2 years in the nuclear power industry.

Isaac Antanaitis, B.S. Engineering:

Civil: Structural Engineering associate with fouryears of experience in structural design for various power generating applications, including seismic design and general condition assessment for multiple structural component types and systems." Phillip York, (credentials outlined in Section 3.1 above)" James Edgar, B.S. Civil Engineering:

Professional Engineer in the state ofTennessee with 11 years of engineering experience, including seismic design andgeneral condition assessment for multiple structural component types and systems.Experience includes 2 years in the nuclear power industry.

To prepare for the seismic walkdowns, Mr. Malone and Mr. Antanaitis completed theNTTF 2.3 Seismic Walkdown Training Course developed by EPRI. This course was9 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2held at MPR Associates, Inc. in Alexandria, VA. It is noted in Frequently AskedQuestions on Seismic Walkdown

Guidance, Reference 8, that completion of this coursequalifies those in attendance to facilitate presentation of course material in subsequent training sessions for others. Mr. Summers, Mr. York, and Mr. Edgar completed thecourse in a subsequent training session held at TVA's office complex in Chattanooga, TN. This subsequent training session was conducted by Steve Eder and John Dizon,subject-matter experts (personnel qualifications outlined in Section 3.5 below) who alsocompleted the EPRI course in Virginia.

In addition to the walkdown training course developed by EPRI, all seismic walkdownengineers attended Sequoyah site-specific training before the walkdown process began.John Dizon facilitated the site-specific training by presenting explanations of licensing basis documents, IPEEE results and associated

outliers, and seismically-related issueshistorically experienced at Sequoyah Nuclear Plant. The site-specific training alsoprovided overviews of established seismic programs, which address the following:

Equipment anchorage and reaction load validation

" Seismic category I(L) piping hazards (11/I failure,

falling, and spray issues)" Distribution and suspended systems" Concrete

/ masonry wall and embedded plates* Structural platforms All training records can be found in Appendix A.3.3. Licensing Basis Reviewers The personnel who performed the licensing basis reviews:* Karen Carboni, Site Civil Engineer at Sequoyah with over seven years of experience in seismic equipment qualification and piping seismic analysis.

" Glynna Wilson, Site Civil Engineer at Sequoyah with over four years of experience instructural

analysis, including seismic equipment qualification.

I 3.4. IPEEE Vulnerability Incorporation Personnel I The personnel who incorporated IPEEE vulnerabilities are:* Joshua Best, Project Mechanical Engineer with 5 years engineering experience, including 4 years in the nuclear power industry.

" Phillip York, (credentials outlined in Section 3.1 above)To ensure that IPEEE vulnerabilities were given proper consideration in thedevelopment of the equipment sample, the individuals listed above reviewed the IPEEE10 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2submittal report and the subsequent Request for Additional Information (RAI), identified appropriate

outliers, and extracted the SSEL which became the basis for SWELdevelopment.

The results of this process were reviewed by the Peer Review Teammembers, whose applicable IPEEE-related experience is outlined in Section 3.5 below.3.5. Peer Review TeamThe personnel involved in the peer review process are:* John Dizon, Professional Engineer with over 30 years of experience in the field ofcivil and structural engineering,-earthquake engineering, risk assessment andproject management.

e Steve Eder, Professional Engineer with over 30 years of experience in the field ofcivil and structural engineering, project management, seismic engineering, and riskmanagement.

John Dizon is the Peer Review Team Leader. Through years of experience assisting TVA at SQN (since 1986), Mr. Dizon and Mr. Eder are familiar with the SQN plantdesign, plant operations, plant documentation, and associated SSCs. Past experience at SQN includes seismic design criteria development, verification of Seismic CategoryI(L) piping, and assistance on seismic qualification of cable trays, conduit, and othermiscellaneous equipment and replacement parts. Mr. Dizon and Eder have supported TVA seismic qualification projects not only at SQN, but also at BFN, BLN, and WBN.Mr. Dizon and Mr. Eder provided calculation CDQ-000-999-2012-000034 (Reference 9),which determines seismic HCLPF capacities for the governing SSC's from the seismicIPEEE, for control motion re-defined at rock outcrop.I11 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 24. Selection of Structures, Systems and Components The selection of SSCs for the Recommendation 2.3 Seismic walkdowns followed theguidelines provided in the EPRI Seismic Walkdown Guidance.

The combined SWEL forSequoyah Unit 2, which consists of 119 items of equipment, adequately addresses allrequired selection criteria.

These criteria include a distribution of environments,

systems, safety functions, and classes of equipment.

The SWEL 1 and 2 selection process is outlined in the following sections.

4.1. SWEL Selection The SWEL 1 selection screening process was performed in accordance with the EPRISeismic Walkdown Guidance.

A schematic of the screening process taken directly fromthe EPRI Walkdown Guidance is shown below -Figure 2: SWEL 1 Selection ProcessScreens #1 through #3 -The development of SWEL 1 began with the SSEL that was developed as part of theIPEEE implementation at Sequoyah, found in Reference 5 -Seismic Capability 12 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2Walkdown for IPEEE. This list fulfills the requirements of Screens #1 through #3 shownabove.It should be noted that an additional safety function "0 -Support Function" was addedto the five safety functions listed in the EPRI guidance document to categorize equipment that does not perform one particular safety function but does support all fivesafety functions.

The expanded safety function list is shown below:0. Support function1. Reactor reactivity control2. Reactor coolant pressure confrol3. Reactor coolant inventory control4. Decay heat removal5. Containment functionThe SSEL with assigned safety functions are presented in Appendix B as Base List 1.Screen #4 -From Base List 1, equipment meeting three of the five screen requirements (system,equipment type, and environment) was identified.

The systems and equipment typeswere chosen based on the criteria provided by EPRI Seismic Walkdown Guidance.

Theequipment environments selected for screen #4, which were not explicitly defined byEPRI, are listed below -" Control Building* Auxiliary Building* Reactor Building" Diesel Generator Building" Emergency Raw Cooling Water Pump Station.It should be noted that some of the equipment classes listed in the EPRI SeismicWalkdown Guidance were not represented in the original IPEEE SSEL, and therefore are not present in Base List 1. To ensure that all of the equipment classes identified inthe EPRI Seismic Walkdown Guidance were represented in SWEL 1, the scope ofselection was expanded to include SSCs which are not in the IPEEE SSEL but meet allscreening criteria.

For the new or replacement equipment requirement, the walkdown team consulted withplant operations to identify system enhancements resulting in new or replacedequipment.

Because the following equipment met all other requirements of the EPRIscreening and was installed or modified as a result of recent projects, it was added toSWEL 1.13 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2UNID Description SQN-2-INVB-250-QU-G 120V AC VITAL INVERTER 2-IVSQN-0-AHU-311-0023 MAIN CONTROL ROOM AHU B-BTable 1: New and Improved Equipment For IPEEE Enhancements, the walkdown team referenced IPEEE resolution calculations SCG-5M-0012 (Reference

5) and CDQ-000-999-2012-000034 (Reference 9). The following equipment met all other requirements of the EPRI screening and wereselected to represent IPEEE enhancements to SWEL 1.14 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2UNID Description SQN-2-BDC-201-FL-A 480V ERCW MCC 2A-ASQN-2-BDC-201-FN-B 480V ERCW MCC 2B-BSQN-2-HEX-074-0015 RESIDUAL HEAT EXCHANGER 2ASQN-2-HEX-074-0027 RESIDUAL HEAT EXCHANGER 2BSQN-0-CHGB-250-QJ-G 125V DC VITAL BATTERY CHARGER IVSQN-0-CHGB-250-QK-S 125V DC VITAL BATTERY CHARGER 2-SPARESQN-2-OXF-202-2A-A 480V SHUTDOWN TRANSFORMER 2A1 -ASQN-2-OXF-202-2B-B SD XFMR 2B-BSQN-2-OXF-202-DN-A 480V SHUTDOWN TRANSFORMER 2A-ASQN-2-OXF-202-DQ-B SD XFMR 2B2-BSQN-2-BDB-201

-DO-A 480V SHUTDOWN BD 2A2-ASQN-2-BDB-201-DP-B 480V SHUTDOWN BD 2B1-BSQN-2-BDB-201

-DQ-B 480V SHUTDOWN BD 2B2-BSQN-2-BDA-202-CO 6900V SHUTDOWN BOARD 2A-ASQN-2-BDB-202-CP 6900V SHUTDOWN BOARD 2B-BSQN-2-BDC-201-FQ-A 480V DIESEL AUXILIARY BOARD 2A1-ASQN-2-BDC-201-FU-B 480V DIESEL AUXILIARY BOARD 2B1-BSQN-2-BDC-201

-GM-A 480V REACTOR MOV BD 2A2-ASQN-2-BDC-201-GN-B 480V REACTOR MOV BD 2B1-BSQN-2-BDC-201

-JK-A 480V CONT & AUX BLDG VENT BD 2A2-ASQN-2-INVB-250-QU-G 120V AC VITAL INVERTER 2-IVTable 2: IPEEE Enhancements Risk Contribution In accordance with the EPRI guidance, SWEL 1 includes consideration of theimportance of the contribution of risk for the SSCs. SWELl was compared to the CoreDamage Frequency (CDF) and Large Early Release Frequency (LERF) Rankings, andany shared equipment was noted.The seventeen SWEL items in the following two tables address the high risk criteria, using CDF and LERF Rankings for Sequoyah Unit 2. Risk rankings and scores aretaken from SQN-SQS2-0162 (Reference 10).15 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2RAW RAW RRW RRWRank Score Rank Score1 SQN-0-CMP-032-0086-B NA NA 1.007815 132 SQN-2-PMP-070-0059-A NA NA 1.006481 193 1SQN-2-HEX-074-0027 4.912712 144 NA NA4 SQN-2-HEX-074-0015 2.215445 210 NA NA5 SQN-2-INVB-250-QU-G 4.9017 147 NA NA6 SQN-2-TNK-070-0063 1070.13 1 1.006407 207 SQN-2-BDC-201-GM-A 3.116802 188 NA NA8 SQN-2-BDC-201

-GN-B 5.601521 120 NA NA9 SQN-2-BDB-201

-DO-A 3.132869 186 NA NA10 SQN-2-BDB-201-DP-B 62.03357 9 NA NA11 SQN-2-BDB-201-DQ-B 41.25348 14 NA NA12 SQN-2-OXF-202-DN-A 22.51848 39 NA NA13 SQN-2-OXF-202-DQ-B 41.25348 15 NA NA14 SQN-2-BDE-250-NF-E 9.258878 74 NA NA15 SQN-2-BDE-250-NK-G 4.266348 158 NA NA16 SQN-0-CHGB-250-QJ-G 37.73672 16 NA NA17 SQN-2-PMP-003-0128 3.531878 181 1.005187 22Table 3: CDF Risk Rankings16 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2RAW RAW RRW RRWRank Score Rank Score1 SQN-2-FAN-030-0462-B 2.819112 150 NA NA2 SQN-0-CMP-032-0086-B 2.063044 222 1.007815 133 SQN-2-PMP-070-0059-A NA NA 1.006481 194 SQN-2-HEX-074-0027 3.20909 138 NA NA5 SQN-2-INVB-250-QU-G 5.013082 98 NA NA6 SQN-2-TNK-070-0063 587.0313 1 1.006407 207 SQN-2-BDC-201

-GM-A 2.178098 189 NA NA8 SQN-2-BDC-201

-GN-B 4.619392 100 NA NA9 SQN-2-BDB-201

-DO-A 2.178531 187 NA NA10 SQN-2-BDB-201

-DP-B 43.48617 6 NA NA11 SQN-2-BDB-201-DQ-B 23.3485 12 NA NA12 SQN-2-OXF-202-DN-A 22.77888 16 NA NA13 SQN-2-OXF-202-DQ-B 23.3485 13 NA NA14 SQN-2-BDE-250-NF-E 5.511841 93 NA NA15 SQN-2-BDE-250-NK-G 3.717315 126 NA NA16 SQN-0-CHGB-250-QJ-G 17.12208 19 NA NA17 SQN-2-PMP-003-0128 2.239433 183 1.005187 22Table 4: LERF Risk Rankings4.2. SWEL 2 Selection The SWEL 2 selection screening process was performed in accordance with the EPRIguidance

document, Seismic Walkdown Guidance.

A schematic of the screening process taken directly from the EPRI Seismic Walkdown Guidance is shown below:17 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2Figure 3: SWEL 2 Selection ProcessScreens #1 through #2The Master Equipment List for Sequoyah Nuclear Plant was utilized to retrieve acomplete list of all Seismic Category 1 spent fuel pool systems and equipment.

This listis presented in Appendix C as Base List 2.Screen #3The Spent Fuel Pool System at Sequoyah was limited to a single environment and asingle system with no new or replacement equipment since the IPEEE analysis.

Therefore the only screen #3 requirement that could be met was that of varyingequipment type. Two items of differing equipment types were selected from Base List 2.Screen #4After reviewing spent fuel pool layout drawings and consulting with plant personnel, itwas determined that there are no spent fuel pool penetrations below (approximately) tenfeet above the top of the fuel assemblies.

Therefore, no rapid drain-down items wereadded to SWEL 2.18 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 24.3. SWEL Finalization Once equipment was selected from Base Lists 1 and 2 that qualifies for seismicwalkdowns, the equipment was reviewed by the site operations representative and thePeer Review Team. This review resulted in the addition of equipment (Medium VoltageSwitchgear) that had not previously been considered to fulfill the Screen #4 for SWEL 1required equipment types.SWEL's 1 and 2 can be found in Appendix D.19 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 25. Seismic Walkdowns and Area Walk-BysGuidance for performing the walkdowns and walk-bys required for Fukushima NTTFRecommendation 2.3 can be found in the Seismic Walkdown Guidance.

The walkdowns and walk-bys were conducted in accordance with this guideline andeach was given a final status. If no potential seismically adverse conditions were notedduring a walkdown or walk-by, a YES status was given to the selected piece ofequipment or area. If a potentially adverse seismic condition was noted, a NO statuswas given and a Corrective Action Program (CAP) entry was written.

If any equipment was inaccessible, or if a portion of an item of equipment was unobservable, anUNKNOWN status was given. It is noted that there were no inaccessible SWEL items atSequoyah Unit 2.It should also be noted that, during the course of performing the walkdowns and walk-bys, five (5) Service Requests (SRs) were generated to address general housekeeping issues which did not present potentially adverse seismic conditions (per the criteriaestablished in the Seismic Walkdown Guidance).

Notes were taken regarding theseminor housekeeping issues based on general observations made during the course ofperforming walkdowns and walk-bys.

5.1. Seismic Walkdown Procedure One hundred and nineteen (119) Seismic Walkdowns Checklists (SWCs) werecompleted at Sequoyah Unit 2. These checklists can be found in Appendix E of thisdocument.

The primary types of potentially adverse seismic conditions that wereaddressed during these walkdowns include:" Bent, broken missing, or loose hardware" Corrosion that is more than moderate" Visible cracks in surrounding concrete* Impact of soft targets* Collapsing equipment

" Inadequate line flexibility Fifty (50) Area Walk-by Checklists (AWCs) were completed at Sequoyah Unit 2. Thesechecklists can be found in Appendix F of this document.

The primary areas ofobservation for potentially adverse seismic conditions that were considered during thesewalk-bys include:* Anchorage of equipment

Cable/conduit raceways and HVAC ducts* Spatial interactions between equipment 0 Flooding/Spray hazardsI20 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2" Fire hazards" Housekeeping and temporary equipment Of the one hundred nineteen (119) SWEL items, there were seven (7) pneumatic valves(equipment class 7) and nine (9) motor-operated valves (equipment class 8) for whichanchorage configuration verification is not applicable.

Anchorage configuration verification for fifty-five (55) out of the one hundred three (103) applicable SWEL itemswas verified by drawings and/or calculations.

For cabinets and panels that were selected for walkdown, NRC guidance was followedto determine which could and could not be opened for internal inspection.

An excerptfrom the guidance

document, Reference 7- FAQ Clarification on Cabinets Walkdown 9-18-12 is shown below-"Cabinets on the SWEL with undue safety or operational hazards can beconsidered inaccessible and opening of the cabinet can be deferred in accordance with the 50.54(f) letter. For those cabinets that are not to be opened, and will notbe placed on the inaccessible list for later inspection (e.g., extensive disassembly is required),

licensees should document the justification for not opening the cabineton the walkdown check sheet."All cabinets meeting the above were documented in the individual walkdowns.

5.2. SWC & AWC SummaryThe results documented by the SWCs and AWCs for Sequoyah Unit 2 is summarized below:* 111 SWCs and 39 AWCs resulted in a YES status* 8 SWCs and 11 AWCs resulted in a NO statuso Potentially Adverse Seismic Condition 1a Area 32- Surge Tank B Areao Potentially Adverse Seismic Condition 20 SQN-2-BDC-201

-GM-A -480V Reactor MOV Board 2A2-Ao Potentially Adverse Seismic Condition 3* SQN-0-BATB-250-QY-G (1-20) -125V Vital Batt. Rm IV Batteries

SQN-0-BATB-250-QY-G (21-40) -125V Vital Batt. Rm IV Batteries

SQN-2-INVB-250-QU-G

-120V AC Vital Inverter 2-IV* SQN-0-CHGB-250-QJ-G

-125V DC Vital Battery Charger IV* Area 21 -125V Battery Room IV* Area 22 -480V Board Room 2Bo Potentially Adverse Seismic Condition 4* SQN-2-LOCL-500-0222B

-Floor Panel Auxiliary Building* Area 25 -RHR Pump Area21 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2* Area 38 -Auxiliary Feedwater Pump B Area* Area 43 -SI Pump Areao Potentially Adverse Seismic Condition 50 Area 20 -125V Vital Battery Room IIIo Potentially Adverse Seismic Condition 6* SQN-2-GEND-085-DH/3B

-Control Rod Drive Generator 2B* Area 30- CRDM Roomo Potentially Adverse Seismic Condition 70 Area 36 -6.9kV Shutdown Board Room Bo Potentially Adverse Seismic Condition 80 Area 7- 2A Pump Roomo Potentially Adverse Seismic Condition 9m Area 37- Control Bldg. 669 Mechanical Roomo Potentially Adverse Seismic Condition 100 SQN-2-AHU-030-0088

-Control Rod Drive Cooling Unit C-A22 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 26. Licensing Basis Evaluations 6.1. Licensing Basis Calculations When a potentially adverse seismic condition was identified at SQN, the condition wasentered into the corrective action program.

No licensing basis evaluations wereperformed by the walkdown team per TVA expectations to communicate any potential operability concerns as soon as they were identified.

All licensing basis determinations were performed by SQN engineering on each CAP entry.The CAP Process at TVA is defined in TVA NPG Standard Program and Processes 22.300 -Corrective Action Program (Reference 11). The CAP program at all TVANuclear Facilities consists of five key phases:* Initiation

Screening

" Analysis" Implementation

" Monitoring Multiple CAP entries were generated during the seismic walkdown process at SequoyahUnit 2. There were a total of ten CAP entries that were considered potentially adverseseismic conditions and elevated to a Problem Evaluation Report (PER) status. TheseCAP entries are summarized in Table 5 on the following pages. All PERs related to thiseffort are now closed. No conditions outside the licensing basis were found during thecourse of this walkdown process.23 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2No. Location Potentially Adverse PER Potential Action Status StatusSeismic Condition(s)

Consequence Taken DateSingle attachment A telecommunications does not provide The cabinet wascabinet used by the sufficient stabilization secured bySurge Rad Con Control point to eliminate the providing anTank B 593116 possibility of the attachment at a 8/10/12 CLOSEDArea is secured (by chain) at cabinet making second point toonly one point ) contact with the Aux meet procedure Air Compressor during compliance.

a seismic event.The slack in theTemporary mobile chains must becooling fans adjacent eliminated if the fansto the 480V Boards remain in this location The fans were re-SQN were secured with to mitigate the risk of located and2 BDC-201 -chains that had 590084 the fans impacting the properly secured 8/3/12 CLOSEDGM-A sufficient slack to allow 480V Boards during a prop eureseismic event and to to meet procedure the fans to contact one meet the requirements compliance.

of the 480V Boards in a of th-reu-emn-seismic event. of 0-TI-DXX-000-013.0 (Temporary Equipment Control).

Existing condition was evaluated perNear the connection to The condition of the review of125V the ceiling, there is a block wall needs to be structural Battery crack in the south structurally evaluated

drawing, acceptedRoom IV & masonry wall shared 585201 to determine if it would as-is, and added 9/18/13 CLOSED480V by 125V Vital Battery pose a threat to to maintenance Board Room IV and 480V adjacent equipment rule structures Room 2B Board Room 2B. during a seismic monitoring (TI-7event. Attachment 44and Calculation SCG 1 S596).1. Aux Bldg EL 690(near Aux Feedwater Pump Area): Three (3) Per 0-TI-DXX-000-The unrestrained unrestrained 55-gal 013.0 (Section

3) and drums wereSI Pump drums behind 2-LOCL- NPG-SPP-09.17, the relocated toRoom Area 500-0222B drums are unstable eliminate the4 & 2 Aux Bldg EL 653 606982 and should be seismically 9/10/12 CLOSEDRHR Pump restrained to mitigate adverse condition Room Area (outside RHR Pump the risk of impact to and to meetRooms): One (1) the referenced procedu reunrestrained 55-gal equipment.

compliance.

drum next to safety-related instrument rackThe existingThe utility sink and arrangement wascabinet in this room is If the sink / counter previously 125V not attached to the wall were to break loose identified inBattery in a manner that is 598032 from the wall during a CAOR 8/20/12 CLOSEDRoom III consistent with a seismic event, the SQP900319, seismically qualified water line could cause evaluated inrestraintc a spray hazard Calculation SCG1 S0366, andaccepted as-is.24 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 26SQN-2-GEND-085-DH/3B There is one anchorbolt missing (of four)from an ABGTS ducthanger supportbaseplate above 2-GEND-085-DH, ControlRod Drive Generator 2B.742486Visual inspection ofthe arrangement shows that thereshould be four anchorbolts for the baseplate in question.

Adequacy of thesupport with themissing anchor boltneeds verification.

Immediate feedback (beforecompletion ofPER initiation) clarified that theexisting condition was addressed byCalculation SCG2S89141 (inresponse toCAQRSQT870843).

This condition isan anomaly whichfalls within thebounds evaluated and accepted as-is by the HVACduct and ductsupport samplingprogramdocumented inthe referenced calculation.

8/3/12CLOSEDScaffolding requires Another tie-offanother tie-off point point was addedScaffolding in front of opposite the existing opposite the6.9kV 6.9kV Shutdown Board tie-off point to prevent existing tie-off7 Shtdwn Bd compartments 10 & 11 596884 tipping and potentially point to mitigate 8/17/12 CLOSEDRm B is only secured in one making contact with the potential forlocation, the 6.9kV Shutdown tipping and meetBoard during a procedure seismic event, compliance.

A flammable material During a seismic A hasp and lockcabinet in the area (but event the door could were installed toERCW 2A not close enough for open and flammable prevent the8 Pump seismic spatial 610433 material could fall out flammable 10/12/12 CLOSEDRoom interaction) was not and present a fire materials cabinetanchored and the latch hazard to equipment from opening toon the door was and personnel in the meet procedure broken. area. compliance.

A bolt and nut are not Nut for this hanger The bolt wasEL 669 fully engaged on a support must be appropriately 9 Mechanical System 26 (Fire 591635 tightened to ensure tightened to 8/14/12 CLOSEDEquip Protection) pipe proper engagement of restore to fullhanger. the bolt. qualification.

This is conservatively SQN One bolt (of six) which noted as a potentially New anchor bolt10 AHU-030-anchors the equipment adverse seismic was installed to 3/8/13 CLOSEDto the steelsupport 642337 condition since it is an restore to full0088 frame is missing.

apparent deviation qualification.

from the design basis.Table 5: Corrective Action Program Entries25 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 26.2. Potential Seismically Adverse Conditions The potentially seismically adverse seismic conditions summarized above are described in more detail below.6.2.1. Potentially Adverse Seismic Condition 1During the walk-by for the Surge Tank B Area, a Radiation Control Cabinet was foundchained at a single point to a steel column. To prevent sliding or tipping into the aircompressor, it was recommended that the cabinet be anchored in a second location.

6.2.2. Potentially Adverse Seismic Condition 2A temporary cooling fan was noted to be improperly restrained in the 480V Board Room2A. This fan was secured with a chain to an appropriate structure, but the restraint wasin a location that would allow the fan to move and tip in a manner that could cause it tostrike a nearby electrical

cabinet, 2-BDC-201

-GM-A. Since many of the relayscontained in this cabinet are sensitive, this condition was considered to be potentially seismically adverse.6.2.3. Potentially Adverse Seismic Condition 3During the walkdown for equipment in the 125V Vital Battery Room IV and the 480VBoard Room 2B, a crack was noted in a common masonry block wall. The crack wasobserved at the top of the wall, directly beneath the steel angle used to connect the wallto the ceiling.

The crack is approximately 6' long and was visible on both sides of themasonry wall. This crack was judged to pose a potentially adverse seismic condition tothree different items of equipment including the 120V AC Vital Inverter 2-IV and 125VDC Vital Battery Charger IV in the 480V Board Room and battery racks 1-20 and 21-40inthe 125V Vital Battery Room IV.6.2.4. Potentially Adverse Seismic Condition 4During the equipment walkdown for SQN-2-LOCL-500-0222B and the area walk-bys forArea 25 -RHR Pump Area, Area 38 -Auxiliary Feed water Pump B Area, and Area 43 -SI Pump Area, it was noted that 55-gallon drums in the vicinity of the equipment werenot properly restrained.

Per TVA Procedure, the geometry of these drums requireseismic restraint.

6.2.5. Potentially Adverse Seismic Condition 5During the area walk-by associated with 125V Battery Room Ill, it was observed that thesink cabinet in this room was not restrained.

During a seismic.event, the cabinet couldmove away from the wall, causing the water supply line to rupture and cause a sprayhazard onto the battery racks.6.2.6. Potentially Adverse Seismic Condition 6An anchor bolt was noted to be missing from a duct support above the Control RodDrive Generator 2B (2-GEND-085-DH/3B) in the Control Rod Drive Mechanism Room.I26 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2The duct support with the missing bolt is a frame support, cantilevered from the wall,with two baseplates connecting it to the concrete.

These baseplates have four boltholes each, one of which is missing a bolt in the top plate.6.2.7. Potentially Adverse Seismic Condition 7A scaffold with potentially inadequate restraint was noted in the 6.9kV Shutdown BoardRoom B. This scaffolding was found in front of compartments 10 and 11 of the Unit 26900V Shutdown Board (2-BDB-202-CP) and was observed to be anchored at only onepoint by a loosely hung chain and could tip into overhead lighting and the shutdownboard.6.2.8. Potentially Adverse Seismic Condition 8During the area walk-by of the ECRW Pump Room 2A-A, a flammable materials cabinetwas noted to have a broken latch on its door. It was also not anchored to the floor orwall. During a seismic event, the door could open or the cabinet could tip, causing theenclosed flammable material to spill from the cabinet.

This would present a potential fire hazard in the area.6.2.9. Potentially Adverse Seismic Condition 9While performing the walk-by for the Control Building El. 669 Mechanical Room, a boltand nut were observed to be not fully engaged on a System 26 Fire Protection pipehanger. The hanger is located 12 feet above the floor, on the east side, between the Aand B EBR AHU's, just above the cross connection between the AHU's, closer to the AAHU.6.2.10. Potentially Adverse Seismic Condition 10While performing the walkdown for the Rod Drive Cooling Unit C-A, SQN-2-AHU-030-0088, a missing bolt was observed that connects the cooling unit to the steel supportframe.27 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 27. IPEEE Vulnerabilities Resolution ReportInformation for the IPEEE Vulnerabilities Resolution Report is derived from Reference 5-Seismic Capability Walkdown for IPEEE and Reference 6 -Sequoyah Nuclear Plant(SON) -Units 1 and 2 -Response to Request for Additional Information on theIndividual Plant Examination of External Events.7.1. IPEEE Description In Generic Letter 88-20, Supplement 4, the US NRC requested that the utilities for allactive nuclear power plants in the United States perform an evaluation of their nuclearpower generating facilities to identify any vulnerabilities associated with the occurrence of several plant-specific external events, and to access the impact of thesevulnerabilities on the potential for plant core damage or radioactive material release.This program, designated the Individual Plant Examination of External Events (IPEEE),is a corollary program to the Individual Plant Examination (IPE) which focused on thevulnerabilities associated with the occurrence of external events.After NRC review of the Sequoyah IPEEE Report, it was found that the review levelearthquake (RLE) was characterized in a manner that was inconsistent with NUREG-1407, the governing document for IPEEE seismic events. The intent of NUREG-1 407 isthat the RLE control motion for SQN (which is predominantly a rock site) should bespecified at rock outcrop as the NUREG/CR-0098 median 5% damped spectral shapefor rock, anchored to a PGA of 0.30g at rock outcrop.

The SQN IPEEE appropriately specified the RLE spectral shape as the NUREG/CR-0098 median rock spectrum atrock outcrop, but inappropriately specified the RLE PGA of 0.30g as occurring at thefree-field soil surface.7.2. IPEEE Findings and Vulnerabilities The IPEEE Report for the Sequoyah Nuclear Plant addressed multiple vulnerabilities that were identified during the original IPEEE walkdown process.

A full list of thesevulnerabilities can be found in Reference 5 -Seismic Capability Walkdown for IPEEE.A sample of this list was selected for Recommendation 2.3 walkdowns, and thisequipment was added to the SWEL for Sequoyah Unit 2. These selected items ofequipment, the issues noted, and the resolutions can be found in Table 6.28 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2UNID Description Resolution DateSQN-2-BDC-201

-FL-A Inadequate Anchorage

/ DCN M9858A 7/20/1993 Interaction SQN-2-BDC-201

-FN-B Inadequate Anchorage DCN M9858A 7/20/1993 SQN-2-BDC-201-FU-B 1 of 4 bolts missing:

2 of Calc SCG-4M- 6/16/1997 7 bays 0169SQN-2-CLR-030-0178 2 of 6 anchor bolts DCN Si 1 135A 1/5/1995missingSQN-2-INVB-250-QU-G Weak way bending Calc SCG-5M- 10/18/2012 channels for inverters 0035SQN-2-HEX-074-0015 Support frame tabs to DCN M1 1308A 10/4/1994 anchor plates for HXSQN-2-HEX-074-0027 Support frame tabs to DCN M 1308A 10/4/1994 anchor plates for HXTable 6: IPEEE Issues and Resolutions 7.3. NRC IPEEE ReviewSubsequent to these original SQN high confidence low probability of failure (HCLPF)capacity bounding evaluations and during the NRC Request for Additional Information (RAI) process related to the definition of RLE control motion, the SQN IPEEE RLE wasredefined from the free-field soil surface to rock outcrop.

As a result, all of the HCLPFcapacities as determined by the conservative bounding evaluations were scaled downby a factor of 0.75. Due to this scaling, the HCLPF capacity for many items dropped tobelow 0.30g (for RLE defined at rock outcrop).

However, at that time no additional effortwas expended to review in more detail and improve (increase) these HCLPF capacities, especially by eliminating some of the simplifying conservative approximations as usedin the original bounding evaluations.

A full list of these items can be found in Reference 6 -Sequoyah Nuclear Plant (SQN) -Units 1 and 2 -Response to Request for Additional Information on the Individual PlantExamination of External Events. A sample of this list was selected for Recommendation 2.3 walkdowns, and this equipment was added to the SWEL 1 for Sequoyah Unit 2.7.4. Response to IPEEE ReviewThe table on the following page shows the items that were identified as IPEEE outliersafter the NRC RAI. Subsequent to the NRC Safety Evaluation Report (SER), actionwas taken to address identified outliers.

For outliers which could not be reconciled through more in-depth seismic analysis, physical modifications and / or replacements were performed, as outlined in the table.I229 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2IItem Equipment Description*

Re-calculated HCLPF1 RHR Heat Exchangers (modified 9/28/1995) 2 Main Control Room AHUs3 Ice Condenser 4 125V Vital Battery Chargers5 480 V Shutdown Transformers (minormodification

-anchorage replaced 12/25/2012) 6 480 V Shutdown Boards7 6.9 kV Shutdown Boards Resolved by TVA Calculation 8 Regenerative Heat Exchangers CDQ-000-999-2012-000034 480 V Diesel Aux Boards Dated 10/18/12480 V Reactor MOV Boards480V Control & Aux Bldg. Vent Boards480V Reactor Vent Boards10 RHR Pumps120 VAC Vital Inverters (modified 7/12/1999) 120 VAC Vital Inverters (replaced 7/12/1999) 12 Pipe Chase Coolers (repaired)

TVA Calculation CDQ-000-999-2012-000034 utilizes descriptions and does not include UNIDsTable 7: Revised HCLPF Equipment The statuses of all IPEEE outliers which were not corrected through physicalmodification were resolved through refined calculation of the appropriate HCLPFcapacities in TVA calculation CDQ-000-999-2012-000034.

All IPEEE outliers are nowresolved and have minimum HCLPF Capacities above 0.3g.30 rii NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 28. Peer ReviewA peer review was performed in accordance with References 2 and 3. The peer reviewprocess involved considerable interaction with the review teams, and was performed throughout all phases of the effort including the following:

SWE Training (as outlined in Section 3.2)* Consultation for selection of the SSCs included on the SWEL* In-plant walkdown observations and completed checklists for the SeismicWalkdowns and Area Walk-Bys* Review of potentially adverse seismic conditions, utilization of the CAP process,and associated licensing basis review considerations

Review of submittal reportA summary of the activities performed by the Peer Review Team is shown in Table 8below. The listed functions are taken from Section 6 of the Seismic WalkdownGuidance.

Activity Activity Performed Action by Peer Review Notes / CommentsDescription Team? (YES/NO)As noted in the Peer Review Report, thepeer review team evaluated the SWEL toensure a diverse sample of theequipment required to perform the fiveReview the safety functions outlined in Section 4.1,Selection of the YES including items previously identified asSSCs included on IPEEE outliers.

The peer review teamthe SWEL also provided needed clarification regarding equipment class designation forSWEL items (regarding instrument racks,temperature

sensors, distribution panels,and medium voltage switchgear).

Review a sample As noted in the Peer Review Report, inof the checklists total, the peer review team performed (10% to 25% documentation review for over 50% of therequired) prepared YES checklists completed by the SWEs.for the Seismic Review of the SWCs and AWCs includedWalkdowns and substantial interface with the SWEs,Area Walk-Bys observation of the SWEs duringperformance of walkdowns

/ walk-bys, 31 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 2and independent field investigation ofindividual equipment components.

Peerreview team efforts related to this activityare summarized in the Peer ReviewReport.As noted in the Peer Review Report, allReview the potentially adverse seismic conditions licensing basis YES were reviewed in detail to addressevaluations seismic licensing basis and operability issues.As noted in the Peer Review Report, allReview the potentially adverse seismic conditions decisions for were reviewed in detail to addressentering the YES seismic licensing basis and operability potentially adverse issues. The peer review team is in fullconditions into the concurrence with the entry of confirmed CAP process potentially adverse seismic conditions into the CAP.As noted in the Peer Review Report, theReview the YES peer review team reviewed the submittal submittal report report and is in full concurrence with thedocumented observations and findings.

Summarize theresults of the peer YES Results of the peer review process arereview process in summarized in the Peer Review Reportthe submittal reportTable 8: Peer Review Team Activities In summary, the peer review results are confirmatory and fully supportive of theevaluations and findings as described in this report. The peer review met the intent ofthe Seismic Walkdown Guidance and was effective in providing technical oversight andreview of all required aspects of the process herein described.

The completed peerreview report is included as Appendix G to this report.32 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 29. References Reference Document Title Document PreparerNo. Number1 Recommendations for Enhancing Reactor N/A United StatesSafety in the 21st Century NuclearRegulatory Commission 2 Letter: Request for Information Pursuant N/A United Statesto Title 10 of the Code of Federal NuclearRegulations 50.54 (f) Regarding Regulatory Recommendations 2.1, 2.3, and 9.3, of Commission the Near-Term Task Force Review ofInsights from the Fukushima DaiichiAccident3 Seismic Walkdown Guidance for EPRI Electric PowerResolution of Fukushima Near-Term Task Report ResearchForce Recommendation 2.3: Seismic 1025286 Institute 4 Sequoyah Nuclear Plant Living Final SQN-1 9 Tennessee Safety Analysis Report Amendment 24 Valley(Control Copy 001437-001)

Authority 5 Seismic Capability Walkdown for IPEEE SCG-5M- Tennessee 0012 ValleyAuthority 6 Sequoyah Nuclear Plant (SQN) -Units 1 N/A Tennessee and 2 -Response to Request for ValleyAdditional Information on the Individual Authority Plant Examination of External Events(IPEEE) (TAC NOS. M83674 andM83675)7 FAQ Clarification on Cabinets Walkdown N/A United States9-18-12 NuclearRegulatory Commission 8 Frequently Asked Questions on Seismic NA NuclearWalkdown Guidance EnergyInstitute 9 Resolution of SQN Seismic IPEEE CDQ-000-Tennessee Outliers 999-2012-Valley000034 Authority 10 Determination of Risk Rankings for SQN- Tennessee Systems and Components for SQS2-0162 Valley1OCFR50.65 Authority 11 Correction Action Program NPG-SPP-Tennessee 22.300 ValleyAuthority 33 NTTF Recommendation 2.3: Seismic Response ReportSequoyah Unit 210. Appendices 34 Appendix A: Resumes and Training RecordsResumes included in this Appendix are alphabetized by last name.* Isaac Antanaitis

-Walkdown Engineer* Joshua Best -Fukushima Project Engineer* Karen Carboni -Site Engineer* Larry Chandler

-Retired SRO* John Dizon -Facility Risk Consultants

Steve Eder -Facility Risk Consultants

James Edgar -Lead Technical Engineer* Robert Malone -Unit 2 Team Leader* David Moore -Retired SRO* Steven Summers -Lead Engineer

& Unit 1 Team LeaderGlynna Wilson -Site Engineer* Phillip York -Walkdown EngineerTraining Record included in this Appendix:

Virginia EPRI Training Certificates (Course Completion Certificate lists KarenCarboni as Karen Tracy -name change is noted on page A45)" TVA/EPRI Training" SQN site-specific trainingAl l WorleyParsons Isaac Antanaitis, E.I.T.resources energy Structural Engineer-in-Training ResumeSUMMARYStructural Engineer-in-Training with four years of experience with WodeyParsons in analysis anddesign of structural steel, ductwork, buckstays, selective catalytic reduction (SCR) reactors, andstructural concrete.

Experience includes using STAAD models, as well as using other softwareincluding Microsoft Excel and MathCAD to assist in the design process.

Familiar with 9h,13t',

and14th Ed. AISC Steel Manuals, ACI 318, ACI 301, ACI 350, ASME BTH-1-2005, Design of WeldedStructures (Blodgett),

ASCE 7, U.S. Core of Engineer Design Guides for water-containing structures, and various AISC Design Guides. Experience also includes responsible engineering roles, projectintegration engineering (work-share facilitation),

and assisting in business development related tosubcontracting efforts with qualified small, minority, and woman-owned businesses.

EXPERIENCE 2008 -Present Structural Engineer-in-Training, WorleyParsons, Chattanooga, Tennessee Arizona Public Service (APS) -Four Corners 2013 Capital Budget Items (CBI) Development.

Primary responsibilities include coordination with APS plant personnel and prospective vendors todevelop complete CBI packages (including scope, schedule, and budget for start to finish execution of capital projects) for submission to APS approval board.APS -Cholla 2013 Capital Budget Items (CBI) Development.

Primary responsibilities includecoordination with APS plant personnel and prospective vendors to develop complete CB1 packages(including scope, schedule, and budget for start to finish execution of capital projects) for submission to APS approval board.Tennessee Valley Authority (TVA) -Kingston Fossil Plant (KIF) Unit Isolation DampersProject.

Primary responsibilities include performing the responsible engineering role for the plant-funded tasks associated with this project.

This includes the development of the DCN (DesignChange Notification)

package, maintaining the project schedule, leading project status and designreview meetings, and coordinating with plant personnel,

vendors, and TVA Fossil Engineering Design(FED).2011 TVA -KIF Coal Unloader Project.

Primary responsibilities include the development of a STAADmodel of the concrete coal building for use in the overall structural analyses performed for theproject.

Responsibilities also include developing the final deliverable DCN (Design ChangeNotification) package.APS -Redhawk Cooling Tower Inspection.

Primary responsibilities include assisting in theinspection and condition assessment of the structural components of the cooling tower for Units 1and 2.TVA -KIF Unit 6 Condenser Cooling Water (CCW) Tunnel Inspections.

Primary responsibilities include preparation for and execution of cooling water intake and discharge tunnel inspections, preparation of job safety analysis, and origination of tunnel inspection reportsAmerican Electric Power (AEP) Rockport Duct Inspection.

Primary responsibilities includeassisting in the inspection of various runs of back-end flue-gas ductwork in support of the Phase Iengineering study for the Unit 1 SCR and FGD Retrofit Project.TVA -Paradise Fossil Plant (PAF) Limestone Scales Project.

Primary responsibilities includethe design of reinforcement for existing limestone conveyor support steelto meet vendorrequirements for new limestone scales. Responsibilities also include coordination with construction personnel.

Design work includes delivering calculations and detailed engineering sketches.

002-000-CPF-016 (007848)

HRF-0033 Corporate Base Page 1Rev 6 (03-Feb-09)

EcoNomics A2

WorleyParsons resources

& energyIsaac Antanaitis, E.I.T.Structural Engineer-in-Training 2010-2011 2010ResumeTVA -Colbert Fossil Plant (COF) ADEM Consent Order Project.

Primary responsibilities includethe design of a concrete sump structure and associated support steel for the required chopper pumpand access platforms.

Responsibilities also include the design of a concrete foundation for electrical equipment, and coordination with construction personnel.

Design work includes delivering calculations and detailed engineering sketches.

U.S. Steel -Pro-Tec Annealing Line. Primary responsibilities include preliminary design of theconcrete post-finishing pit for the development of construction bid drawings.

TVA -Cumberland Fossil Plant (CUF) Unit I Bottom Ash Hopper Replacement Project.Primary responsibilities include the development of engineering estimates, project planningdocuments, and construction bid work scoping documents, as well as the design of: 1) post-installed epoxy anchors for hopper columns,

2) support steel for hopper platforms and piping, and 3)evaluation of sump pit support steel for demolition and construction loads. Design work includesdelivering calculations and detailed engineering sketches.

U.S. Steel -Fairfield Works Fall Protection.

Primary responsibilities included providing engineering recommendations in the development of design drawings documenting requiredinstallation of fall protection system components.

Responsibilities included performing field walk-downs of 44 overhead cranes in the hot strip mill, sheet mill, dual line mill, and cold mill at Fairfield Works.TVA -Bull Run Fossil Plant (BRF) CCW Inspection.

Primary responsibilities included preparation for and execution of cooling water discharge tunnel inspection, including preparation of job safetyanalysis and origination of tunnel inspection report.TVA -Gallatin Fossil Plant (GAF) and KIF CCW Inspections.

Primary responsibilities includedpreparation for and execution of cooling water intake and discharge tunnel inspections.

For KIFtunnel inspections, primary responsibilities also included preparation of job safety analysis andorigination of tunnel inspection reports.Dominion

-Mount Storm Project Engineering.

Primary responsibilities included design of stoplogs and cooling water intake structure.

Design work included delivering calculations and detailedengineering sketches.

The design of each stop log included considerations to accommodate drymaintenance of spillway gates, including:

structural steel design (with corrosion allowance) forapplicable load from pressure head, rubber seal selection and arrangement, and construction splicing scheme for shipping and field erection purposes.

Primary intake structure responsibilities included developing design loads, performing stability

analysis, creating and analyzing STAADmodels, and designing the geometry and reinforcement for the walls and foundation of the concretestructure.

Project responsibilities also include work related to the preparation and development ofspecifications and engineering requisition documents.

Southern Company -Plant Scherer Units 1-4 Pressure Upgrade.

Primary responsibilities included updating existing drawings with new load data, and providing connection modifications forexisting precipitator steel vertical bracing (Units 3 and 4)..TVA -CUF Unit 2 Bottom Ash Hopper Replacement Project.

Primary responsibilities includeddesign of post-installed epoxy anchors for hopper columns, and steel to support hopper platforms and piping. Responsibilities also included providing engineering support for hopper installation andremoval plans, as well as for construction phase field adjustments.

2009-2010 2009TVA -John Sevier Fossil Plant (JSF) and GAF Stack Platform Extension As-built FieldVerification.

Primary responsibilities included providing verification of as-built information forchimney platform modification work by aiding in platform safety inspection, measuring and002 nnn UT-016 1007848 HRF--Rev 6 (03-Peb-09) orporate aseEcoNomics A3 WorleyParsons Isaac Antanaitis, E.I.T.resources

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.;.. ...... ... R esdocumenting dimensions of platforms and instruments, and creating sketch amendments forstructural designers.

TVA -BRF Lifting Device Qualification.

Primary responsibilities included rating the capacities ofvarious lifting devices (including monorails, below the hook lifting beams, and a forklift liftingattachment),

providing a maximum load rating for mezzanine storage floors, and performing a craneuprate qualification.

The crane uprate qualification included calculation of the maximum capacities ofthe pulverizer lifting crane and corresponding support steel.TVA -CUF Unit 2 SCR Field Weld Inspection and Qualification.

Primary responsibilities includedvisually inspecting beam connection welds inside SCR box, determining structural condition of thesewelds, and documenting and reporting assessments to responsible plant personnel.

CPS Energy -Deely Unit 2 SCR Proposal.

Primary responsibilities included providing ductworkand steel material estimates.

Responsibilities also included creating and analyzing STAAD modelsto verify foundation modification design loads.TVA -JSF and PAF Stack Platform Extensions.

Primary responsibilities included providing baseline information for chimney platform modification work by aiding in platform safety inspection, measuring and documenting dimensions of platforms and instruments, and creating sketchamendments for structural designers.

2008 -2009 R.C. Cape May Holdings

-B.L. England Unit 2 SCR Project Engineering.

SCR reactor primaryresponsibilities included creating and analyzing STAAD models for SCR reactor box. Structural steelprimary responsibilities included submitting calculations and engineering sketches for base plates,anchor bolts, and column splices.

Responsibilities also included submitting support steel calculations and sketches for platforms and stair towers.2008 Alstom -Keyspan Northport Project Engineering.

Ductwork primary responsibilities includedcreating and analyzing STAAD models which integrate new ductwork and existing support steel,delivering detailed design sketches, and submitting hand calculation packages.

Structural steelprimary responsibilities included analyzing existing support steel and recommending specificmodifications to accommodate the new ductwork, delivering detailed design sketches, and submitting hand calculation packages.

Buckstays primary responsibilities included analyzing existing buckstays and designing new buckstays for the addition of new separated over-fire air ducts.Alstom -Pacificorp Project Engineering.

Ductwork primary responsibilities included creating andanalyzing STAAD models for ductwork (both existing ducts and modifications of existing ducts),delivering detailed design sketches, submitting hand calculation

packages, and writing sections of thedesign modification report pertaining to the aforementioned ductwork.

PPL Global -Sunbury Project, Phase II Engineering.

Ductwork primary responsibilities includecreating and analyzing STAAD models for new ductwork, delivering detailed design sketches, andsubmitting hand calculation packages.

Structural steel primary responsibilities included

creating, integrating, and analyzing STAAD models for new support steel, delivering detailed design sketches, and submitting hand calculation packages.

2007 -2008 Civil Engineering Intern, J. Farrow, P. E. & Associates, Collegedale, Tennessee Labrador Heights (Development).

Provided site design layouts, roadway designs, grading plans,and construction plan setup for the project.

Developed the storm water pollution prevention plan andthe aquatic resource alteration permit submittals.

London Lane (Development).

Provided site design layouts, roadway designs, grading plans, andconstruction plan setup for the project.

Created bid estimation computational tool for the project.002-000-CPF-016 (007848)

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& energyIsaac Antanaitis, E.I.T.Structural Engineer-in-Training 20062004-2005

....":" .. .i.. i:, x '. .. ..w :

... ,'eL m ;ResumneStonegate (Development).

Performed site plan revisions and general drafting tasks as directed bysupervising engineers.

Engineering Intern, Tennessee Valley Authority, Chattanooga, Tennessee River System Operations

-Water Resource Cataloguing System. Provided support forengineers in the analysis of water resource records from regions throughout the Tennessee ValleyWatershed.

Aided in the further development of the organizational system by which water resourcerecords are tracked and cataloged.

Field S~rvice Technician, Vibration Control Engineering, Nashville, Tennessee Nashville Courthouse

-Underground Parking Lot. Installed,

serviced, and retrieved data fromdigital and analog seismographs through computer interface and manual documentation.

Reportedseismic data to responsible engineers and blasting contractors.

Wolf Chase (Development).

Provided documentation of structural damage to engineers through theuse of field sketches, notes, and digital photography.

Initiated direct interaction with property ownerspotentially affected by the construction project.Hicks Road -Sewer Line Installation.

Set up meeting times and coordinated pre-blast precautionary measures with construction industry representatives.

Provided documentation ofstructural damage to engineers through the use of field sketches, notes, and digital photography.

EDUCATION B.S., Engineering:

Civil, University of Tennessee, Chattanooga, Tennessee, 2008B.S., Mathematics:

Technology, Bryan College, 2004REGISTRATIONS/AFFILIATIONS Engineering Intern (E.I.T.),

Tennessee No. 26439, 2007Vice-President

-Chattanooga Chapter of Engineers Without BordersSPECIFIC TECHNICAL EXPERTISE/SPECIALIST COURSESComputer Skills:STAAD.Pro 2006, 2007, and V8iSmartPlant Microsoft OfficeAutoCAD 2004, 2006, and 2008MathCADRISA Baseplate Lerporate I3002-000-CPF-016 (007848)

HRF-0033ReV 6 (03-Feb-09)

Corporate BaseEcoNomics A5 Joshua H. BestTVA Fukushima Response Team Project Engineer

-Civil DesignExperience S&L, LLC TVA Fukushima Response Team Project Engineer

-Civil Design Dec. 2011 -Present-Primary technical lead for NRC's request for information under 10 CFR 50.54(oRecommendations 2.1 -Seismic and Flooding Re-evaluations and 2.3 -Seismic and Flooding walkdowns including developing project strategy, project scoping, developing and maintaining projectschedules and budgets, participating in industry meetings and teleconferences, and contractor oversight.

-Responsible for supporting all civil design functions associated with response to NRC "OrderModifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design BasisExternal Events" as required under EA-12-049.

S&L, LLC. Mechanical Senior Associate

-Pipe Stress Analyst June 2008 to Nov. 2011" ASME Class 2 and 3 and B31.1 piping and component qualification using TVA TPIPE pipinganalysis software and hand calculations

" Knowledge of AMSE B31.1 and ASME Section III and VIII code requirements

" Responsible for Minimum Wall Calculations (FAC Evaluations),

Component Qualifications (valvesand nozzles),

Commodity Clearance Evaluations, Temporary Shielding Requests (pipe stressqualification),

and Functional Evaluations for Plant Operability

Task Manager for numerous design change packages at Browns Ferry, Watts Bar and Sequoyahnuclear plants including responsibility for scoping and maintaining project schedule, budget, andinterdisciplinary work flowTennessee Valley Authority, Fossil Power Group, Intern June 2007 -May2008Technical Support Services (Metallurgy and Welding)Memberships

Licensed Engineering Intern in Tennessee (Passed Fundamentals of Engineering Exam (October2007))*Member of American Society of Heating, Refrigerating, and Air-Conditioning Engineers (ASHRAE)-Member of American Society of Mechanical Engineers (ASME)Education BSME, Mechanical Engineering:

May 2008University of Tennessee at Chattanooga, Chattanooga, TNFocus: Energy SystemsRelated Course Work: Thermodynamics, Thermal Component Design, Advanced Fluids, EnergyConversion Bachelor of Arts, Natural Science:

May 2008Covenant

College, Lookout Mountain, GARelated course work: Physics, Chemistry, and Mathematics A6 Karen CarboniSUMMARYCivil Engineer with 7 years of experience in design engineering with the Tennessee Valley Authority.

JobExperience includes designing piping modifications with plant system, equipment seismic qualification, piping seismic analysis, development of design change packages, performing functional evaluations andother various roles of a Civil Engineer.

Familiar with ASME Section III and B31.1 for piping. Proficient with design software including and TVA-PIPE and MathCAD.EXPERIENCE Tennessee Valley Authority-Served as a Civil Engineer within the Civil Engineering Design Group atChattanooga Office Complex from September 2005 to October 2006 and at Sequoyah Nuclear Plantsince October 2006. Is qualified in Equipment Seismic Qualification and performed numerousevaluations of equipment during the procurement process.

Qualified in piping analysis and evaluatemodifications to piping systems to address plant needs. Responsible for piping analysis anddevelopment of design change documentation.

Familiar with the TVA CAP process and how it is used forproblem identification and resolution.

Other responsibilities include field support, design changepackages, verification of others work, functional evaluations, and interface with other departments within and outside of the Engineering Organization.

EDUCATION B.S., Mechanical Engineering, University of Tennessee, Chattanooga, Tennessee, 2005A7 William L. ChandlerProfessional Experience I was employed by TVA from 1980 until 2012. I was a Reactor Operator from 1989 to 1998. From 1998thru 2012 I held the position of Senior Reactor Operator/

Unit Supervisor.

I was responsible for the safeoperation of a nuclear unit reactor, oversight of the Unit operators, review of weekly work schedules, approval of all unit work and coordination between crafts for inspections and ongoing work.A8 JOHN 0. DIZON, P.E.PROFESSIONAL HISTORYFacility Risk Consultants, Inc., Huntsville,

Alabama, President, 2002-present ABS Consulting (formerly EQE International),

Oakland, California, Director andVice President of Facility Risk Division, 2000-2002 EQE International,

Oakland, California, Vice President, 1998-2000; Associate, 1991-1998; Senior Engineer, 1986-1991 Engineering Decision Analysis

Company, Cupertino, California, Senior Engineer, 1984-1986 General Electric

Company, San Jose, California, Senior Engineer, 1984URS/John A. Bluine & Associates, San Francisco, California, Senior Engineer, 1982-1984; Associate

Engineer, 1977-1980 Structural Systems Engineering, Inc., Lafayette, California, Senior Engineer, 1980-1982 Stanford University, John A. Blume Earthquake Engineering Center, Palo Alto, California, Teaching and Research Assistant, 1975-1977 PROFESSIONAL EXPERIENCE Mr. Dizon has over 30 years of experience in the field of civil and structural engineering, earthquake engineering, risk assessment and project management.

He has extensive knowledge in the areas of seismic analyses and design assessments of primary structures andpiping systems, seismic upgrade and retrofit design, seismic qualification of mechanical andelectrical systems and components, and technical development of seismic evaluation criteriaand programs for various industries, including power, oil and gas, petrochemical, and hightech process and manufacturing facilities.

Mr. Dizon has undertaken and managed a widevariety of seismic projects, ranging from traditional structural engineering design andseismic retrofits to complex nuclear power plant and DOE facilities' seismic verification projects.

He is also a guest instructor for the ASME Continuing Education Institute onseismic design and retrofit of piping systems and mechanical equipment.

At present, Mr. Dizon is primarily involved with Tennessee Valley Authority (TVA), under asubcontract with Bechtel Power Corporation, in providing engineering consulting servicesfor various structural and seismic-related civil issues in support of Watts Bar Nuclear PowerPlant Unit 2 Completion Project.

He also provides seismic consulting services to otherindustries, including defense contractors and commercial equipment manufacturers, amongothers.As President of Facility Risk Consultants, Mr. Dizon is responsible for business development and project management activities, including managing all associated tasks under asubcontract with Bechtel Power Corporation for seismic-related civil issues associated withthe recently completed Browns Ferry Unit 1 Restart Project for Tennessee Valley Authority.

The seismic works included USI A-46/IPEEE implementation

programs, seismic II/I sprayhazard evaluations, new cable routing utilizing the SQUG/GIP methodology, MSIV seismicruggedness verification, among others. Furthermore, he was also actively involved in thedevelopment of seismic II/I design criteria for distribution systems and equipment for1 FACILITY RISK CONSULTANTS, Inc.A9 JOHN 0. DIZON, P.E.DOE's PDCF project, under a subcontract with the Washington Group, Inc.; and in theseismic qualification of various essential equipment for DoD's GMD project, under asubcontract with Bechtel National, Inc. and its vendors.

In addition, Mr. Dizon hasparticipated as a subject matter expert witness in a litigation project for a large foreigncompany in the area of seismic performance of structures, piping systems and associated equipment associated with earthquake damges in a coal-fired power plant located in SouthAmerica.As EQE Project Manager for various seismic programs associated with the restart of BrownsFerry Units 2 and 3, Mr. Dizon was responsible for all engineering activities associated withUSI A-46 resolution and seismic IPEEE implementation; seismic proximity and II/I sprayinteraction evaluations; MSIV seismic ruggedness verification; cable tray and conduitraceway and supports; and HVAC support evaluation programs.

These activities consisted of seismic criteria development, seismic walkdown assessments and mitigation of findings, including retrofit designs and plant upgrades.

He was also responsible for the A-46 seismicevaluation program for major equipment items at Davis-Besse, Duane Arnold and H.B.Robinson power plants. Mr. Dizon also served as Project Manager for the HVAC seismicverification program at Salem Nuclear Plant, MSIV seismic projects at Hope Creek andBrunswick plants, and participated in a number of related seismic evaluation projects atSequoyah, Watts Bar, Bellefonte, Pickering A, Bruce A, Forsmark, Liebstadt, among others.As Managing Director of EQE's Hsinchu, Taiwan project office following the 1999 Chi-Chiearthquake, he was in charge of the region's business development and project management.

Mr. Dizon managed a number of seismic risk assessment and structural upgrade projects forthe high tech industry, including seismic consultation on a number of projects for TaiwanSemiconductor Manufacturing Co., seismic strengthening projects for UnitedMicroelectronics, Applied Materials, Winbond Electronics and Macronix International inTaiwan. In addition, he also managed the seismic upgrades for the Cypress Semiconductor and Amkor facilities and seismic design review project for IBM in the Philippines, seismicrisk assessment for AMP facilities in Japan, and seismic assessment of structural and non-structural components of clean room facilities at several Intel fab plants in the Northwest region in U.S., among others.As Group Manager for EQE at the US Department of Energy Savannah River Site, Mr. Dizonwas responsible for the seismic verification program of safety-related mechanical andelectrical systems and components.

His tasks included developing seismic evaluation criteriaand proceddres for restart and long-term seismic programs; managing the seismic walkdownand evaluation efforts; providing technical support in resolving seismic issues; and servingas an interface with the client. Mr. Dizon was also responsible for the seismic walkdown andevaluation of various distribution systems and critical equipment at the Pantex Facilities, including developing the walkdown screening criteria and evaluation acceptance criteria.

Mr. Dizon has participated in the seismic evaluation of the High Flux Isotope Reactor at OakRidge National Laboratory.

This project involved performing seismic analyses and upgradesfor the primary coolant piping system and related equipment, and the reactor and controlbuildings.

Other DOE facilities he has involvement with included Los Alamos, Livermore and Hanford sites. Mr. Dizon has also been involved in a number of risk assessment programs for petrochemical plants and refineries, including seismic walkdowns at the2 FACILITY RISK CONSULTANTS, Inc.A10 JOHN 0. DIZON, P.E.Imperial West Chemical plants in Pittsburg and Antioch, CA; Tosco Refinery in Avon, CA;and Dupont Chemical plant in Antioch, CA, among others.At EDAC, Mr. Dizon was responsible for the development and verification of a pipe supportoptimization program (OPTPIPE) and was involved in a number of snubber reduction pilotprojects.

Other areas of his involvement consisted of finite element analyses of the MX-missile launch tube components and systems for thermal and pressure loads, equipment qualification of major mechanical and electrical components, and seismic evaluation ofcooling towers.With General Electric

Company, Mr. Dizon was responsible for stress analysis and codeconformation of main steam and recirculation piping systems for generic BWR plants. Hewas also involved in the developmental phase of an in-house pipe support optimization program.At URS/Blume

& Associates, Mr. Dizon was responsible for the development andmaintenance of in-house computer programs for both linear and nonlinear analyses ofstructural and piping systems.

He was also involved in the linear and nonlinear dynamicanalyses, finite element modeling, and generation of floor response spectra for severalnuclear power plants. He helped develop a soil-structure interaction computer programusing a three-dimensional finite element technique to evaluate the dynamic response ofstructures due to arbitrary plane body and surface wave excitations.

He performed aresearch study involving soil-structure interaction analysis using the finite element FLUSHprogram to investigate the dynamic response of typical containment structures due tounderground blast excitations.

Mr. Dizon worked as a consultant to Bechtel Power Corporation with Structural SystemsEngineering, Inc. He performed structural analyses and design assessments of the primarycontainment structure and the reactor/control buildings of several BWR plants for thevarious types of hydrodynamic loads. He was involved in a BWR in-plant test procedures, data reduction and correlation study to determine the dynamic response, including soil-structure interaction of the reactor/control buildings during GE Mark II reactorhydrodynamic load actuation in the primary containment.

At Stanford University, Mr. Dizon performed statistical analyses of earthquake accelerograms and various response parameters, as part of his research work under Professor Haresh Shah. He also conducted seismic risk analyses and formulated seismic design criteriafor Nicaragua.

In addition, he was involved in the dynamic testing, of structural models andequipment.

EDUCATION STANFORD UNIVERSITY, Palo Alto, California:

Engineer Degree, 1977STANFORD UNIVERSITY, Palo Alto, California:

M.S. Structural Engineering, 1975MAPUA INSTITUTE OF TECHNOLOGY, Manila, Philippines:

B.S. Civil Engineering, 19733 FACILITY RISK CONSULTANTS, Inc.All JOHN 0. DIZON, P.E.AFFILIATIONS AND AWARDSMultidisciplinary Center for Earthquake Engineering Research (MCEER),

Strategic PartnerPhilippine Board Examination for Civil Engineers, Fifth Place, 1973Philippine Association of Civil Engineers, Certificate of Merit, 1974REGISTRATION California:

Civil EngineerPhilippines:

Civil EngineerSELECTED PUBLICATIONS With S. J. Eder, 2007. "Seismic Qualification Case Study for a New Inverter."

SMiRT-19Conference,

Toronto, Canada, August 12-17, 2007.With S. J. Eder, 2006. "Use of Earthquake Experience Data for Seismic Qualification ofEquipment."

Prepared for Multidisciplinary Center for Earthquake Engineering Research(MCEER).

June 22, 2006.With S. J. Eder, 2005. "Seismic Qualification Case Study." Prepared for Electric PowerResearch Institute and Seismic Qualification Utility Group. December 2005.With S. J. Eder, and R. D. Cutsinger.

2003. "Browns Ferry Cable Tray Evaluations."

Presented to the SQUG/SEQUAL Annual Meeting, San Antonio, TX, December 10-12, 2003.With S. J. Eder. 2003. "Technical Position Paper for Seismic II/I Design of Cable TrayRaceway Systems at PDCF." Presented to Washington Group, Inc., December 2003.With S. J. Eder, W. H. Tong, and E. H. Wong, 1999. "Chichi, Taiwan Earthquake ofSeptember 21, 1999 (M7.6). An EQE Briefing.

Oakland, CA. October, 1999.With S. J. Eder. 1998. "Risk Management for Power and Industrial Facilities

-- Focus onBusiness Interruption".

Second Biennial Federation of Asian Pacific & African RiskManagement Organization.

Manila, Philippines.

October, 1998.With F. R. Beigi. 1995. "Application of Seismic Experience Based Criteria for Safety RelatedHVAC Duct System Evaluation."

Fifth DOE Natural Phenomena Hazards Mitigation Symposium, Denver, Colorado, November 13-14, 1995.With S. J. Eder, J. F. Glova, and R. L. Koch. 1994. "Seismic Adequacy Verification of HVACDuct Systems and Supports for an USI A-46 Nuclear Power Plant." Fifth Symposium onCurrent Issues Related to Nuclear Power Plant Structures, Equipment and Piping, Orlando,Florida, December 14-16, 1994.4 FACILITY RISK CONSULTANTS, Inc.A12 JOHN 0. DIZON, P.E.With E. J. Frevold and P. D. Osborne.

1993. "Seismic Qualification of Safety-related HVACDuct Systems and Supports."

ASME Pressure Vessel and Piping Division Conference, Denver, Colorado, July 1993.With S. J. Eder. 1991. "Advancement in Design Standards for Raceway Supports and ItsApplicability to Piping Systems."

ASME Pressure Vessel and Piping Division Conference, San Diego, California, June 1991.With R. D. Campbell and L. W. Tiong. 1990. "Response Predictions for Piping SystemsWhich Have Experienced Strong Motion Earthquakes."

ASME Pressure Vessel and PipingConference, Nashville, Tennessee, June 17-21, 1990.With S. P. Harris, R. S. Hashimoto, and R. L. Stover. 1989. "Seismic, High Wind, andProbabilistic Risk Assessments of the High Flux Isotope Reactor."

Second DOE NaturalPhenomena Hazards Mitigation Conference.

With D. Ray and A. Kabir. 1979. "A 3-D Seismic Analysis for Arbitrary Plane Body andSurface Wave Excitations."

American Society of Civil Engineers Nuclear Specialty Conference, Boston, Massachusetts.

With D. Ray and A. Zebarjadian.

1978. "Dynamic Response of Surface and Embedded DiskFoundations for SH, SV, P and Rayleigh Wave Excitations."

Sixth Indian Symposium onEarthquake Engineering,

Roorkee, India."A Statistical Analysis of Earthquake Acclerograms and Response Parameters."

1977. Thesis,Stanford University, Palo Alto, California, With H. Shah, T. Zsutty, H. Krawinkler, and L. Padilla.

1977. "A Seismic Design Procedure for Nicaragua."

Paper presented at the Sixth World Conference on Earthquake Engineering, New Delhi, India.With H. Shah, T. Zsutty, H. Krawinkler, C. P. Mortgat, and A. Kiremidjian.

1976. "A Studyof Seismic Risk for Nicaragua, Part II, Summary and Commentary."

John A. BlumeEarthquake Engineering Center, Report No. 12A and 12B. Stanford University, Palo Alto,California.

5 FACILITY RISK CONSULTANTS, Inc.A13 STEPHEN J. EDERPROFESSIONAL HISTORYFacility Risk Consultants, Huntsville,

Alabama, Chief Executive

Officer, 2003-present ABS Consulting,

Houston, Texas, Vice President, North Asia Pacific Region, 2001-2003 EQE International, San Francisco, California, Senior Vice President, 1985-2001 (ABS Purchased EQE in 2000).URS/John A. Blume & Associates, Engineers, San Francisco, California, 1982-1985 J1 G. Bouwkamp, Inc., Structural Engineers,

Berkeley, California, 1981-1982 PROFESSIONAL EXPERIENCE Mr. Stephen J. Eder provides senior engineering and management consultant

services, licensing

support, and expert testimony in the fields of natural hazards risk assessment, seismic analysis, structural performance evaluation, and retrofit design. His background includes projectmanagement, engineering, risk management, and planning for domestic and multinational corporations, insurance and financial institutions, construction companies, utilities, and thegovernment.

Mr. Eder is based in Madison, Alabama.Prior to Facility Risk Consultants, Mr. Eder was stationed in Tokyo, Japan for 8 years and led alloperations for ABS Consulting Inc. (formerly EQE International, Inc.) in Japan, China, Koreaand Taiwan -- including risk consulting, structural engineering and design, probabilistic financial loss estimation, and the development and maintenance of management systems.Mr. Eder has performed many post-earthquake reconnaissance studies -- most notably he ledinvestigations of the M8.4 earthquake in Arequipa, Peru of June 2001; the M7.6 earthquake inChichi, Taiwan of September 1999; and he was lead investigator of the M8.1 earthquake inMexico of September 1985, for the US Electrical Power Research Institute (EPRI).Prior to his assignment in Japan, Mr. Eder focused primarily in the seismic risk evaluation andseismic retrofit design of critical equipment and systems.

Mr. Eder pioneered the development of many seismic risk evaluation procedures and criteria for the US and European nuclear powerindustry, the Seismic Qualification Utilities Group (SQUG), and the US Department of Energy(DOE). This included conducting a series of week-long seismic evaluation training courses for atotal of about 500 engineers, and serving as subject matter expert and technical liason forindustry groups.Mr. Eder served as project manager or project consultant for the seismic risk surveys of criticalequipment and systems at about 60 nuclear power plants in the US and Europe, and many DOEfacilities.

He performed research for and supported many U.S. industry and professional groups, to advance the state-of-the-art of seismic risk assessment techniques and seismic designguidelines.

1 FACILITY RISK CONSULTANTS, Inc.A14 STEPHEN J. EDEREDUCATION UNIVERSITY OF CALIFORNIA, Berkeley:

M.Eng., Structural Engineering and Structural Mechanics, 1982CLARKSON COLLEGE OF TECHNOLOGY,

Potsdam, New York: B.S., Magna Cum Laude, Civil andEnvironmental Engineering, 1980REGISTRATION California:

Civil Engineer, 1985Alabama:

Civil Engineer, 2003PROFESSIONAL AND BUSINESS AFFILIATIONS American Society of Civil Engineers Earthquake Engineering Research Institute Structural Engineers Association of Northern California Applied Technology CouncilTau Beta Pi National Engineering Honor SocietyPhi Kappa Phi National Honor SocietyAmerican and British Chambers of Commerce in JapanCOMMITTEES

-- PAST EXPERIENCE

-Electric Power Research Institute

-Post Earthquake Investigation Team -Leader-U.S. Department of Energy -Tiger Team Member -Natural Hazards Risk Analysis-U.S. Department of Energy -Steering Committee on Natural Hazards -Technical Liason -Mechanical and Eletrical Equipment Evaluation and Design-Seismic Qualification Utility Group -Equipment Seismic Evaluation Training

-LeadInstructor and Subject Matter Expert-Joint American Society of Mechanical Engineers and Institute of Electrical and Electronics Engineers

-Special Seismic Qualification Working Group -CoChairman

-National Center for Earthquake Engineering Research

-Critical Equipment Seismic RiskAnalysis

-Chief Researcher

-National Fire Protection Association (NFPA) -Seismic Technical Committee Member, NFPA-13.-Building Seismic Safety Council -Seismic Rehabilitation Advisory Panel Member -Mechanical Equipment.

NEHRP, FEMA 273.-American Society of Civil Engineers

-Electrical Raceway and HVAC Duct Seismic Design -Working Groups-Structural Engineers Association of California

-Seismology Subcommittee

-Non-Building Structures and Equipment 2 FACILITY RISK CONSULTANTS, Inc.A15 STEPHEN J. EDERSELECTED PUBLICATIONS

& PRESENTATIONS With J. 0. Dizon, 2007. "Seismic Qualification Case Study for a New Inverter."

SMiRT-19Conference,

Toronto, Canada, August 12-17, 2007.With J. 0. Dizon, 2006. "Use of Earthquake Experience Data for Seismic Qualification ofEquipment."

Prepared for Multidisciplinary Center for Earthquake Engineering Research(MCEER).

June 22, 2006.With J. 0. Dizon, 2005. "Seismic Qualification Case Study." Prepared for Electric PowerResearch Institute and Seismic Qualification Utility Group. December 2005.With J. 0. Dizon, and R. D. Cutsinger.

2003. " Browns Ferry Cable Tray Evaluations."

Presented to the SQUG/SEQUAL Annual Meeting, San Antonio, TX, December 10-12, 2003.With J. 0. Dizon. 2003. " Technical Position Paper for Seismic 1I/I Design of Cable TrayRaceway Systems at PDCF." Presented to Washington Group, Inc., December 2003."Analysis of Ilo2 Plant Components Affected by the June 23, 2001 Mw 8.4 Arequipa, PeruEarthquake".

Prepared for Hitachi Corporation.

December 2002. Presented in London, U.K."The Use of Modeling and Natural Risk Analysis for Power Plants".

Presented at SecondInternational Conference on Mitigating Your Risks in Energy. February 2002. Singapore.

"Using Risk Based Inspection Techniques to Assess Maintenance of Power Plants".

2002.Presented at Second International Conference on Mitigating Your Risks in Energy. February2002. Singapore.

"Preparing Your Properties for Major Earthquakes".

2001. Prepared for Architecture, Construction, and Engineering Subcomittee, American Chamber of Commerce in Japan.December 2001. Tokyo."Earthquake Hazards and Earthquake Risks in Tokyo". 2001. TELS-Setagaya, Earthquake Disaster Information and Preparedness Seminar.

October 2001. Tokyo."Geographic Information Systems".

2000. Prepared for Non-Life Insurance Institute, ISJAdvanced Course 2000 Program, Natural Hazards and Underwriting Capacity.

November2000. Tokyo.With J. 0. Dizon, W. H. Tong, and E. R. Wong, 1999. "Chichi, Taiwan Earthquake of September 21, 1999 (M7.6). An EQE Briefing.

Oakland, CA. October, 1999.With G.S. Johnson, R.E. Sheppard, M.D. Quilici, and C.R. Scawthorn, 1999. "Seismic Reliability Assessment of Critical Facilities:

A Handbook, Supporting Documentation, and Model CodeProvisions."

Technical Report MCEER-99-0008.

Multidisciplinary Center for Earthquake Engineering

Research, Buffalo, NY."Earthquake Risk of Independent Power Producer Stations",

1999. Prepared for Lloyd's JapanPower Seminar.

June 1999. Tokyo.3 FACILITY RISK CONSULTANTS, Inc.A16 STEPHEN J. EDERWith J. 0. Dizon. "Risk Management for Power and Industrial Facilities

-- Focus on BusinessInterruption".

Second Biennial Federation of Asian Pacific & African Risk Management Organization.

Manilla, Philippines.

October, 1998."3 Years After the Hanshin-Kobe Earthquake, Earthquake Risk Management, DamageAssessment and Mitigation".

1998. High Pressure Gase Safety Association of Japan. Vol. 35,No. 2 (1998). Tokyo.With G. S. Johnson, R.E. Sheppard, and S.P. Harris. 1998. "A Method to Assess and Improvethe Operational Reliability of. Critical Systems Following Earthquakes."

Presented at the 6thU.S. National Conference on Earthquake Engineering,

Seattle, WA, June 1998.With G. S. Johnson, R.E. Sheppard, and S.P. Harris. 1998. "The Development of Model CodeProvisions to Address System Reliability Following Earthquakes."

Presented at the ATC-29-1Seminar on Seismic Design, Retrofit, and Performance of Nonstructural Components, SanFrancisco, CA, January 1998.With D. W. Jones, M. K. Ravindra, C. R. Scawthorn, and K. lida. 1996. "Earthquake RiskManagement for Process Industries".

High Pressure Gas Safety Institute of Japan. Vol. 35, No.5 (1996). Tokyo.With G. A. Antaki. 1994. "Recommended Provisions for Equipment Seismic Qualification Consistent with IEEE and ASME Criteria for Use of Experience."

ASME 1994, PVP-Vol.

275-2,Seismic Engineering, Volume 2.With P. J. Butler and R. P. Kassawara.

1994. "Application of the Generic Implementation Procedure Methodology to Demonstrate Seismic Adequacy of New and Replacement Equipment and Parts in USI A-46 Plants."

ASME 1994, PVP-Vol.

275-2, Seismic Engineering

-Volume 2. Proceedings American Power Conference, Illinois Institute of Technology, April1994, Chicago, Illinois.

With N. P. Smith and R. P. Kassawara.

1994. "Future Direction for the Use of Earthquake Experience Data." Proceedings American Power Conference, Illinois Institute of Technology, April 1994, Chicago, Illinois.

With M. W. Eli and M. W. Salmon. November 1993. "Walkthrough Screening Evaluation FieldGuide, Natural Phenomena Hazards at Department of Energy Facilities."

UCRL-ID-115714, Revision

2. Lawrence Livermore National Laboratory.

"Seismic Design of Important Systems and Components--Functionality Considerations."

1993.Structural Engineers Association of Northern California, 1993 Fall Seminar, Nonstructural Components:

Design and Detailing.

San Francisco, California.

With C. Scawthorn, M. Zadeh, and G. Johnson.

1993. "Economic Impacts of Earthquake Damage to Nonstructural Components."

40th North American Meetings of the RegionalSciences Association International,

Houston, Texas.With M. W. Barlow, R. J. Budnitz, and M. W. Eli. 1993. "Use of Experience Data for DOESeismic Evaluations."

4th DOE Natural Phenomena Hazards Mitigation Conference, Atlanta,Georgia.With K. Porter, G. S. Johnson, M. M. Zadeh, and C. Scawthorn.

1993. "Seismic Vulnerability ofEquipment in Critical Facilities:

Life-safety and Operational Consequences."

Technical; ReportNCEER-93-0022.

National Center for Earthquake Engineering Research.

4 FACILITY RISK CONSULTANTS, Itc.A17 STEPHEN J. EDERWith J. K. Arros. 1993. "Applications of Experience-based Methods for Seismic Qualification ofDistribution Systems."

Prepared for Advanced Reactor Corporation FOAKE ALWR SeismicQualification Project.With MPR Associates and Winston and Strawn. 1993. "Verifying the Seismic Adequacy ofNew and Replacement Equipment and Parts." Prepared for the SQUG Management Guidelines Document.

With Lawrence Livermore National Laboratory.

1992. "Program Plan for the Evaluation ofSystems and Components in Existing DOE Facilities Subject to Nataral Phenonema Hazards."

Prepared for the U.S. Department of Energy.With J. 0. Dizon, P. D. Baughman, and G. S. Johnson.

1992. "Peer Review of the Watts BarNuclear Plant Integrated Interaction Program Suspended Systems Proximity Task." Preparedfor Tennessee Valley Authority.

With G. S. Hardy, G. S. Johnson, and R. W. Cushing of EQE; MPR; S&A; and URS. 1992."Walkdown Screening and Seismic Evaluation Training Course."

Prepared for SeismicQualification Utility Group.With M. W. Salmon. 1992. "Technical Safety Appraisal of the Idaho Chemical Processing Plant,NPH Discipline."

Prepared for the U.S. Department of Energy.With M. W. Eli. 1992. "NPH Walkdown Evaluation Summary Report -Paducah GaseousDiffusion Plant." Prepared for the U.S. Department of Energy.With G. S. Johnson, R. H. Kincaid, and G. S. Hardy. 1992. "High-rise Building CriticalEquipment Study." Prepared for National Center for Earthquake Engineering Research.

With K. E. Smith. 1992. "Seismic Performance of Standby and Emergency Power EngineGenerator Systems."

Prepared for National Center for Earthquake Engineering Research.

With M. W. Eli. 1991. "Use of Earthquake Experience Data." Prepared for the Third DOENatural Phenomena Hazards Mitigation Conference, St. Louis, Missouri.

With J. 0. Dizon. 1991. "Advancement in Design Standards for Raceway Supports and ItsApplicability to Piping systems."

PVP-Volume 210-1, Codes and Standards and Applications for Design and Analysis of Pressure Vessel and Piping Components.

ASME 1991."Cable Tray and Conduit System Seismic Evaluation Guidelines."

March 1991. EPRI ReportNP-7151.

Prepared for the Electric Power Research Institute.

San Francisco, CA: EQEInternational.

With G. S. Johnson.

March 1991. "The Performance of Raceway Systems in Strong-motion Earthquakes."

EPRI Report NP-7150.

Prepared for the Electric Power Research Institute.

SanFrancisco, CA: EQE International.

With G. S. Johnson.

March 1991. "Longitudinal Load Resistance in Seismic Experience DataBase Raceway Systems."

EPRI Report NP-7153.

Prepared for the Electric Power ResearchInstitute.

San Francisco, CA: EQE International.

With J. P. Conoscente and B. N. Sumodobila.

March 1991. "Seismic Evaluation of Rod HangerSupports for Electrical Raceway Systems."

EPRI Report NP-7152.

Prepared for the ElectricPower Research Institute.

San Francisco, CA: EQE International.

5 FACILITY RISK CONSULTANTS, Inc.A18 STEPHEN J. EDERWith Winston & Strawn, MPR Associates, Inc., etal. June 1991. "Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment."

Revision

2. Prepared forthe Seismic Qualification Utility Group.With M. W. Eli and L. J. Bragagnolo.

1991. "Walkthrough Screening Evaluation Field Guide,Natural Phenomena Hazards at Department of Energy Facilities."

Special Release for 3rd DOENatural Phenomena Hazard Mitigation Conference, October 1991, St. Louis, Missouri.

With L. J. Bragagnolo and J. P. Conoscente.

1990. "A Proposed Methodology for the SeismicDesign of Rectangular Duct Systems."

Applied Technology Center (ATC) Seminar on SeismicDesign and Performance of Equipment and Nonstructural Elements in Building and Industrial Structures, Irvine, California.

ATC-29.With J. J. Johnson and N. P. Smith. 1990. "Developments of the Seismic Qualification UtilityGroup." Applied Technology Center (ATC) Seminar on Seismic Design and Performance ofEquipment and Nonstructural Elements in Building and Industrial Structures, Irvine,California.

ATC-29.With W. Djordjevic, J. Eidinger, and F. Hettinger.

1990. "American Society of Civil Engineers Activities on Seismic Design of Electrical Raceways."

Current Issues Related of Nuclear PowerPlant Structures, Equipment, and Piping. Proceedings of the Third Symposium, Orlando,Florida, December 1990.With H. L. Williams.

1990. "Qualification of Cable Tray Supports by Earthquake Experience Data: Application at H. B. Robinson Plant" Current Issues Related of Nuclear Power PlantStructures, Equipment, and Piping. Proceedings of the Third Symposium,

Orlando, Florida,December 1990.With R. P. Kennedy, J. D. Stevenson, J. J. Johnson, W. R. Schmidt, and K. Collins.

June 1990."Watts Bar Civil Program Review."

Prepared for Tennessee Valley Authority.

With J. P. Conoscente, B. N. Sumodobila, and S. P. Harris. 1989. "Seismic Fatigue Evaluation ofRod Hung Systems."

Prepared for the Tenth Conference on Structural Mechanics in ReactorTechnology, (SMiRT).With P. D. Smith and J. P. Conoscente.

December 1988. "SQUG Cable Tray and ConduitEvaluation Procedure."

Paper presented at the Second Symposium on Current Issues Related toNuclear Power Plant Structures, Equipment and Piping, Orlando, FL.With P. I. Yanev. 1988. "Evaluation of Cable Tray and Conduit Systems Using the SeismicExperience Data Base." Nuclear Engineering and Design (North-Holland, Amsterdam) 107: 149-153.With S. P. Harris, P. D. Smith, and J. E. Hoekendijk.

October 1988. "Performance of Condensers and Main Steam Piping in Past Earthquakes."

Report prepared for General Electric NuclearEnergy Boiling Water Reactor Owners Group. San Francisco:

EQE Engineering.

With J. J. Johnson, G. S. Hardy, N. G. Horstman, G. Rigamonti, M. R. Reyne, and D. R. Ketcham.August 1988. "Technical Basis, Procedures and Guidelines for Seismic Characterization ofSavannah River Plant Reactors."

E. I. Dupont De Nemours & Co, Aiken, South Carolina.

6 FACILITY RISK CONSULTANTS, Inc.A19 STEPHEN J. EDERWith S. P. Harris, P. S. Hashimoto, J. 0. Dizon, B. Sumodobila, G. M. Zaharoff, and L. J.Bragagnolo.

March 1988. "Seismic Evaluation of the High Flux Isotope Reactor PrimaryContainment System."

Report prepared for Martin Marietta Energy Systems, Inc. SanFrancisco:

EQE Engineering.

With S. W. Swan, "Summary of the Effects of the 1985 Mexico Earthquake to Power andIndustrial Facilities."

Proceedings of the American Society of Civil Engineers International Conference on the 1985 Mexico Earthquake, Factors Involved and Lessons Learned, MexicoCity, Mexico, September 1986.With A. F. Kabir and S. Bolourchi, "Seismic Response of Pipes Supported on Complex FramingSystems."

Proceedings of the American Society of Civil Engineers Structures

Congress, NewOrleans, Louisiana, September 1986.With S. W. Swan, "The Mexico Earthquake of September 19, 1985; Performance of Power andIndustrial Facilities,"

Proceedings of the Third U. S. National Conference on Earthquake Engineering, Charleston, South Carolina, August 1986."Performance of Industrial Facilities in the Mexican Earthquake of September 19, 1985," ElectricPower Research Institute Report No. NP-4605, Project 1707-30 Final Report, Palo Alto,California, June 1986, also presented at the IEEE Power Engineering Society Summer Meeting,Mexico City, Mexico, July 1986."Earthquake Response Analysis of a Braced Offshore Platform,"

University of California, Berkeley (June 1982), also American Petroleum Institute, October 1982, San Francisco, California.

7FACILITY RISK CONSULTANTS, Inc.A20 I 'IWorleyParsons James P. Edgar, P.Eresources

& energy Chief Civil/Structural Engineer.-----.ResumneSUMMARYProject Manager with over 10 years of project retrofit, design, and management experience withWorleyParsons.

Primary responsibilities included the project management, project engineering, andthe overall structural engineering and design, coordination, and estimating for all types of retrofit anddesign projects.

Tasks included structural steel design and inspection, engineering man-hour andmaterial cost estimating, scheduling, and fabrication/erection technical support and construction fieldsupport.

Responsibilities include performing as the engineering task lead for structural steel formulti-million dollar/large scale structural retrofit projects.

In addition, tasks include managing thestructural condition assessment services performed by the WorleyParsons' Chattanooga office.EXPERIENCE 2009 -Present Project Manager, WorleyParsons, Chattanooga, Tennessee Tennessee Valley Authority (IVA). Oversee multi-discipline projects.

Responsibilities includedevelopment, management, and execution of the project scope, schedule and budget. Typicalproject responsibilities include management of several concurrent projects from proposaldevelopment, to the conceptual study phase, through design implementation, and construction.

support.2006 -2009 Principal Structural

Engineer, WorleyParsons, Chattanooga, Tennessee Alstom ECS/ Kansas City Power & Light (KCPL) -latan Generating Station Selective Catalytic Reduction (SCR) Project, Alstom Project Partnership.

Task lead overseeing engineering anddesign of ductwork, new support structures and the reinforcement of the existing support structure toaccommodate the SCR retrofit project.

Responsibilities include originating and reviewing calculations for structural steel, ductwork, foundations and other miscellaneous structural projectsassociated with the SCR project.

Responsible for overseeing other structural engineers andstructural designers in order to facilitate the design drawings with respect to the budgeted man hoursand schedule.

Review and approval shop fabrication and detailed drawings for structural steel andductwork.

Facilitate all communications between the Chattanooga and Knoxville offices as well asprovide estimating and scheduling for all current and future projects, optional design arrangements, and engineering studies.

Conduct several site visits to determine the construction feasibility ofpresent and future projects as well as to investigate and propose alternative arrangement options forthe support of the SCR system.Alstom Performance Projects

-Miscellaneous Projects.

Task lead overseeing engineering anddesign of several'miscellaneous structural steel, ductwork, and fossil projects.

Responsibilities include originating and reviewing calculations for structural steel, ductwork, and other structural projects associated with fossil sites. Responsible for overseeing other structural engineers andstructural designers in order to facilitate the design drawings with respect to the budgeted manhoursand schedule.

Projects include:Lamma Low NOx Ductwork Installation and Structural Steel Modifications Desota Low NOx Ductwork Installation Dominion Generation Chesterfield Station Furnace Buckstay Upgrade Study2007 -Present Condition Assessment Services Team Leader, WorleyParsons, Chattanooga, Tennessee In addition to senior structural engineering activities, additional responsibilities include coordinating and leading condition assessment inspections at fossil power plants. The Chattanooga inspection 002-000-CPF-016 (007848)

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EcoNomics A21 WorleyParsons James P. Edgar, P.Eresources

& energy Chief Civil/Structural EngineerResume~... .... ,, .. ... .. ... ' .. ". .... ... .. .. ... ..... .. ...... ..... ..group consists of 16 civil/structural engineers who performed condition assessment inspections throughout the U.S. for several different utility companies.

Coordinating responsibilities include estimating and scheduling

manpower, developing a detailedinspection

criteria, also evaluating and documenting the existing conditions of the respective component during the inspection.

Post-inspection responsibilities include formalizing inspection

findings, formulating necessary modifications and reinforcements, outlining future recommendations and inspection plans, reviewing the findings of team members, and executing any subsequent structural engineering tasks or engineering studies.Typical inspections include:Air and flue gas ductwork (internal and external)

Circulating cooling water tunnelsCoal handling bins,Chimneys and stacks, complete interior and exterior inspection Boiler internals and pressurevessels Furnace stiffening systemsMiscellaneous structural systems at a typical fossil siteResponsible

Engineer, TVA Project Partnership Tennessee Valley Authority (TVA) -Project Partnership.

Project lead overseeing multi-discipline projects.

Responsibilities include role as the technical lead for the multi-discipline effort as well asthe point of contact between all engineers, designers,

vendors, suppliers, and TVA management.

Tasks include technical review of engineering and design, perform documentation of modifications, monitor allocation and utilization of estimated budget, and presentation of design proposals,

progress, and construction planning to plant and construction management.

Projects include:Cumberland Fossil SCR Hopper and LPA Screen Installation and Existing Steel Modifications Multi-site TVA Chimney Structural Review and Reinforcement ProjectTVA Fossil Power Plants Condition Assessment Inspections CPS Energy -Braunig Peaker Project (Combustion Turbine).

Responsibilities include the designof several new and retrofitted structures and new equipment foundations.

Duties focus on designing the structural integrity, support measures, and serviceability of the new structures and foundations associated with the new combustion turbine project.2005 -2006 Structural

Engineer, WorleyParsons, Chattanooga, Tennessee Progress Energy Carolinas (PGNC) -Roxboro Flue Gas Desulfurization (FGD). Responsibilities include the design of large ductwork and their support structures.

Duties focus on designing thestructural integrity, support measures, and thermal expansion characteristics for large ductworkassociated with the new FGD system. In addition, responsibilities include designing the support steeland foundations for the FGD ductwork support structures.

Progress Energy Carolinas (PGNC) -Mayo Flue Gas Desulfurization (FGD). In anticipation offuture FGD project, conducted internal duct inspection for the Unit 1 ductwork at PGNC's Mayo plantsite and provided report evaluating the condition of the ductwork and its structural components andrecommending repairs.Alstom (Chattanooga)

-TXU Oak Grove Hot Air Duct to Mills (New Boiler).

Structural engineerfor the design of the Hot Air Duct to the Mills for a new boiler construction project.

Performed structural analysis of ductwork and support measures in addition to specifying metal expansion 002-000-CPF-016 (007848)

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EcoNomics A22 i WorleyParsons James P. Edgar, P.Eresources

& energy Chief Civil/Structural Engineer~, (',Resume:

joints. Provided subcontracted consulting engineering firm with ductwork-applied loading drawings tofacilitate the structural steel and foundation design effort.TVA. Responsible for several miscellaneous structural engineering projects involving structural steeldesign, duct design and analysis and design of retaining wall structures for both fossil and hydropower plants. Other responsibilities included providing technical support and temporary structure design to help facilitate construction efforts during plant modification projects.

In addition, responsibilities include internal structural inspections for circulating cooling water tunnel systems.2001 -2005 Structural

Engineer, Alstom Power, Chattanooga, Tennessee East Kentucky Power -Spurlock No. 1, SCR Project.

Responsibilities included the structural design of SCR ductwork, specification of fabric expansion joints, and slide gate and louver dampers.Provided subcontracted consulting engineering firm with ductwork-applied loading drawings tofacilitate the structural steel and foundation design effort.Tucson Electric

-Springerville Units I and 2 LowNOx Retrofit Project.

Responsible for overalllayout and design of ductwork, structural steel, SOFA, air registers, access platforms, andmodifications to the'existing ductwork.

In addition, preformed structural analysis of existing supportsteel and provided details to reinforce the structure.

Performed same responsiblities for projects withcustomers including Platte River, Lower River Colorado Authorities, TXU, PacificCorp, and KentuckyUtilities.

Mobile Energy Service Corporation

-Power Boiler No. 9, Furnace Explosion Rehabilitation Project.

Structural engineer for the inspection of damaged boiler structural steel, access platforms, and furnace stiffeners.

Produced inspection

reports, design sketches, condition assessments, andmaterial estimates to customer for required modifications/reinforcement and/or replacement ofdamaged steel.Dominion Generation

-Chesterfield Unit 5, Secondary Air Duct Modifications.

Structural engineer for the design of modifications to the secondary air duct stiffener

framing, supports, andguides to accommodate the installation of new duct openings and new expansion joint placement.

Specified new fabric expansion joints and provided detailed sketches for construction.

ProvidedOEM with ductwork applied loading drawings to facilitate the structural steel and foundation designeffort.Dominion Generation

-Chesterfield No. 6, Ductwork and Furnace Upgrade Study. Conducted structural analysis of existing boiler framing and flue gas ductwork systems for FD/ID fan pressureupgrades.

Additional responsibilities included secondary site inspections to determine theconstruction sequencing and identify potential design changes of new ductwork/boiler framingmodifications.

Performed same responsiblities for projects with customers including TXU, Exelon,and Indianapolis Power and Light.Dominion Generation

-Chesterfield No. 6, Ash Handling Tank Support Steel. Designed newsupport structure for an ash handling tank and equipment for the Economizer hopper. Evaluated theexisting structural steel and provided detailed modifications to reinforce the existing structure effected by the new steel and equipment.

EDUCATION B.S., Civil Engineering, University of Tennessee, Knoxville, Tennessee, 2001Pursuing a Masters in Civil Engineering, University of Tennessee, Knoxville, Tennessee, 2003 -Present002-000-CPF-016 (0078481 HRF-0033 Corporate Base Page 3Rev 6 (03-Feb-09)

EcoNomics A23 WorleyParsons James P. Edgar, P.Eresources

& energy Chief Civil/Structural Engineer~Resume~ ~ ~ ~ ~ ~ ~ ~ -- -: ----- ...... .: ... : i .. .., : % i:' ?IT ' '. ;.. .REGISTRATIONS/AFFILIATIONS Registered Professional Engineer

-Tennessee, No.112009, 2008One Way Element Leader, Element 9 Management of ChangeMember, AISC, ASCEConfined Space and Fall Protection TrainedMember, STAAD User GroupWood Design CED Certified PUBLICATIONS/PRESENTATIONS ASCE Duct Design 2008 Structural Department Presentation Duct Inspection Procedures 2008 Structural Department Presentation Beam and Column Reinforcing Procedures 2008 Group Presentation ASCE Wind Design Structures and Ducts 2007 Group Presentation SCR Systems 2005 Structural Department Rresentation SPECIFIC TECHNICAL EXPERTISE/SPECIALIST COURSESDoer-Seller Account Planning, 2010Frontline Leadership

Program, 2009Prestressing Concrete (UTK) -Properties of prestressing materials; methods of pre-tensioning andpost-tensioning; and analysis and design of simple and continuous beams and slabsBehavior of Steel Structures (UTK) -Focused on the design of beams, columns, beam-columns, connections,

bracing, tension members, and the interpretation of the ASD and LRFD specifications.

Statically Indeterminate Structures (UTC) -Analysis of frames, trusses,

columns, and continuous beams by force methods and slope deflection.

Analysis of Plates and Shells (UTC) -Bending and buckling of plates and shells and non-linear analysis of cables and cable roof structures.

Computer Skills:STAADPro 2004 AutoCAD 2000, 2004MicroStation Frameworks MathCAD Microsoft OfficeAWARDSNominee for- Eastern Operations People Development Award 2010Eastern Operations Civil/Structural Engineer of the Year, 2008002-O00-CPF-016 (007848)

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WorleyParsons resources

& energyRobert D. Malone, P.E.Structural EngineerResumeSUMMARYStructural Engineer with over seven years of experience with WorleyParsons in structural engineering.

Tasks include analysis and design of flue gas desulfurization (FGD) and selective catalytic reduction (SCR) ductwork, support steel, foundations, minor/major modifications to existingstructural steel/ductwork, and evaluations of existing steel. Design of miscellaneous steel/duct components including platforms, stair towers, turning vanes, and large particle ash (LPA) screens.Field experience includes ductwork inspections (miscellaneous

ductwork, precipitators, economizers, SCRs) for damage/wear assessment and general inspection for pre-bid evaluation, condenser inspections, elevator shaft inspection, and site visits for steel/ductwork layout evaluations.

Responsibilities include performing as lead for various projects, providing man-hour estimates, general project management, and task supervision of junior engineers.

Additional experience includes approximately one year of nuclear experience in modular design of equipment support steel.EXPERIENCE 2005 -Present2011 -Present2011 -2012Structural

Engineer, WorleyParsons, Chattanooga, Tennessee Arizona Public Service (APS) -Cooling Tower Assessment.

Provided structural assisgment ofthe existing cooling towers for the Redhawk, Cholla, Ocotillo, and West Phoenix power plants.General duties consisted of the following:

i Performed structural inspections of both wooden and FRP cooling towers.Performed "Repair vs. Replace" economic assessments.Provided inspection reports.American Electric Power (AEP) -Clifty Creek Power Plant, Unit Six SCR Addition.

Providedstructural assistance in the analysis of the existing unit six turbine and boiler build steel for increased loading caused by the addition of a new SCR mounted on top of the existing turbine building.

General duties consisted of the following:

0, Modeled the existing turbine and boiler building.

io Designed the new SCR support steel located on top of the existing turbine building.

Tennessee Valley Authority (TVA) -Kingston Steam Plant, Isolation Damper Project.Performed the structural analysis of the existing steel and ductwork for the additional equipment loadings related to the new isolation dampers and seal air fan additions to units one through nine.General duties consisted of the following:

1 Provided onsite support for construction.

o Performed structural calculations for existing steel modifications.

t Provided support to the structural design team.TVA -Kingston Steam Plant, Steel Remediation.

Performed the structural analysis of existingsteel damaged due to faulty orginal design. General duties consisted of the following:

P- Provided root cause analysis of the damaged duct support steel.t' Provided structural calculations for the repair of the damaged duct support steel.Provided support to the structural design team.002-OO0-CPF-016 (007848)

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& energy Structural EngineerResumeTVA -Kingston Steam Plant, Condenser Cooling Water (CCW), Tunnel Inspections.

Performed as task lead for the CCW tunnel inspections for units one though nine. General dutiesconsisted of the follwing:

0, Performed CCW tunnel inspections.

1ý Provided CCW tunnel assessment reports.0- Scheduled and staffed the inspections.

2010 -2011 Westinghouse

-Staff Augmentation at the Chattanooga, Tennessee Westinghouse Office.Provided structural engineering support for the design of nuclear equipment module support steel.General duties consisted of the following:

SPerformed structural analysis on modular units supporting equipment related to various AP1000nuclear systems for loads induced by three boundary conditions:

transportation,

lifting, andoperation.

SPerformed reviews/audits of calculations performed by Westinghouse employees as well asexternal contractors.

SProvided assistance to design team to resolve/identify any constructability issues.SPerformed calculation revisions resulting from design modifications.

SProvided technical guidance of junior engineers.

2010 Tennessee Valley Authority (TVA) -Allen Fossil Plant, EDTA Boiler Cleaning Project.

Providedstructural engineering required for the switchover from the present HCI acid cleaning system to anew forced circulation EDTA boiler cleaning system. General duties consisted of the following:

SProvided pump foundation modification P- Prepared pipe support designs- Prepared platform modification 1' Provided man-hour estimates SPrepared assistance for the Task Work Scope documentSProvided the structural portion of the project planning documentSAttended site walkdowns for pipe routing and for meetings at the site2007 -2010 Southern Company -Scherer Plant, Mercury Baghouse Project.

General responsibilities consistof dluctwork/steel layout and design, material

takeoff, duct work and steel inspection, and generalduties as a task lead. Tasks Include:h~Requests for Information responses SUnit 2 existing steel modification for new dluctwork SUnit 4 duct support steel layout/configuration SUnit 4 duct support steel design and management of designSUnit 4 dluctwork layoutSUnit 4 ductwork design and management of designSOn-going construction support2010 TVA -Colbert Fossil Plant, Reheat/Super Heat Attemperator Replacement.

Provided structural analysis of existing steel for the removal of the Unit 2 reheat attemperator and instalation ofreplacment reheat attemperator.

Provided review of current monorail scheme already in place forUnit 3 super heat attemperator removal/replacement to assure it is suitable for all Units 1 through 4.General duties consist of the following:

b, Rigging designP, Support steel reinforcement

'Design drawing reviewSPlant personnel coordination 002-000-CPF-016 (007848)

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& energy Structural Engineer.... .: * ..:, .,, * .... ... *. .. ...:: ........: :. ..: ..., ........ .. ..... ....ResumeSite trip to identify field interferences TVA -Widows Creek Steam Plant, Ammonia Vaporizer Replacment.

Provided rigging plan andsupplementary steel for the ammonia vaporizer removal and installation.

TVA -Shawnee Fossil Plant, Unit 8 Turbine Fire Inspection.

Performed inspection of the turbineroom roof, floor, and concrete turbine support frames. In addition to the above, also inspected thecrane runway, girders, and rails in the immediate area of the fire. Provided structural repairrecommendations.

TVA -Kingston Steam Plant, Condensor Inspection.

Performed inspection of the Unit 6condensor.

TVA requested the inspection after the plate wall failed during a leak test. To performthe leak test, the condenser was filled with water. It is believed that after years of fatigue stressbuilding up in the wall as well as poor craftsmanship, the additional hydrostatic pressure caused ahorizontal fracture in the plate wall.TVA -Kingston Steam Plant, Condensor Inspection.

Performed inspection of the Unit 5condensor.

A re-occurring crack in the side wall of the condensor caused pressure loss. Previousattempts by field personal to weld up the crack failed. Per TVA's request, a 3' x 5' section was cutout of the sidewall and replaced with a new plate.TVA -Cumberland Fossil Plant, Boiler Tie Modification.

Provided calculation review as well asengineering for the boiler tie modifications for the Unit 2 boiler. Also performed walkdown to insurethat no interferences would be encountered.

TVA -Cumberland Fossil Plant, Soot Blower Replacement Procedure Review. Per TVA'srequest, performed a safety evaluation of the current soot blower replacement procedure.

Thisevaluation was spurred on by an accident in which a 60' blower lance fell from the 10th floor to the 8thfloor. Recommended modifcations to the platform lab/outs on floors 9, 10, and 11. Thesemodifications mostly consisted of platform widening to allow larger turning radiuses for the 60' sootblowers.TVA -Cumberland Fossil Plant, Convection Pass Waterwall Replacement.

Provided calculation review for the waterwall replacement, as well as a walkdown to insure that there would be nointerferences for the construction procedures.

2009 -2010 TVA -Lagoon Creek Combined Cycle Plant. Providing services as the owner's engineer of thestructural engineering portion for a steam turbine generator addition.

Tasks Include:k Reviewing various calculations (turbine building steel and foundations, pipe racks, electrical buildings, steam turbine generator foundations, etc.).-Reviewing various documents (drawings, bid analysis, vendor surveillance report, and technical specifications).

2009 Florida Power and Light -Putnam Plant. Provide structural input for a circulating water pipeupgrade proposal.

Responsible for pipe support steel layout as well as steel estimate and pileestimate.

TVA -SCR inspections projects include:P- Cumberland Steam Plant -Provided condition assessment of the catalyst support beam.connections.

Provided immediate field repair recommendations.

Responsible for guidinglaborers in a manner that insured their safety as they performed their jobs. Responsible for dailyupdates on inspection progress to the customer.

P- Bull Run Steam Plant -Provided condition assessment of the catalyst support beamconnections.

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WorleyParsons resources

& energyRobert D. Malone, P.E.Structural Engineer2008-2009 20082007-2008 ResumeTVA -Widows Creek Steam Plant. Inspection of the Unit 7 scrubber elevator shaft for condition assessment.

Provided detailed report of the inspection.

TVA -Cumberland Steam Plant, Limestone Scale Project.

Provide structural engineering required for the conveyor modification for the installation of limestone scales. Provide strctural inputat weekly meetings as well as provide input for design change notification preperation.

Consumers Energy -D.E. Karn Fossil Plant, Pulse Jet Fabric Filter Project.

GeneralResponsibilities consisted of the following.

i, Analysis and design of the duct support structure for the return ducts 8, 9, 10A, 10B, and thesupply ducts 4 and 5 for Unit 2v, Pipe support steel for Unit 20 Cable tray support steel for Unit 2P- Platform design for Unit 2Sunbury Generation LP -Sunbury Station Wet FGD Retrofit Project.

Responsibilities consisted of the analysis and design of the limestone building as well as duct support structures.

TVA -Cumberland Steam Plant LPA Screen Project.

Performed the Phase 1 study, andperformed duties as the task lead for the Phase 2 study. The study consisted of an LPA screen andhopper row addition in the SCR inlet ducts of Units 1 and 2. The addition of these components affected the existing ductwork as well as the support steel to the extent that rework of the structural bracing was required.

Performed plant walkdowns for interface with screen vendor. Providedsupport for numerous update meetings as well as design review meetings at the plant with the TVAresident engineer.

Responsible for man-hour estimates of the Phase 2 study.TVA -Kingston Fossil Plant Condenser Cooling Water Tunnel Inspection.

Performed inspection of the inlet and discharge condenser cooling water tunnels.TVA -Cumberland Internal Duct Inspection Study. Conducted internal duct inspection for theUnit 1 ductwork, and provided report evaluating the condition of the ductwork and its structural components, and recommended repairs.

The Cumberland inspection consists of the evaluation ofthe boiler outlet duct, SCR ductwork, and the precipitator box including its inlet and outlet duct trains.Nebraska Public Power District.

Performed solo pre-bid general duct inspection and provided areport on the overall structural integrity of the existing ductwork.

Alstom Power -Kansas City Power & Light, latan Generation Station.

Performed design ofSCR ductwork, existing steel modifications, existing steel/foundation evaluations for increased loads,pressure upgrade study for existing

ductwork, and miscellaneous steel design (platforms, LPAscreen).

Other responsibilities included working with designers to convey engineering design andreview of shop drawings.

Attended walkdowns for interface with constructors.

Progress Energy Carolinas (PGNC) -Roxboro FGD. Responsibilities included design of ductworkand related support structures, as well as furnishing calculation packages detailing the designs.Checked other engineers' calculations to ensure correctness.

Other responsibilities includedproviding detailed sketches for designers, as well as checking finished drawings to insure correctstructural configurations.

Also provided support for plant walkdowns.

Work included:

Miscellaneous tasks included the design of various platforms, connections, base plates, anchor bolts,and stair towers.20072006-2007 2005-2006 n oýnurata casRev 6 (03-Feb-09)

C.orporate BaseEcoNomics A28 WorleyParsons Robert D. Malone, P.E.resources

& energy Structural Engineer EDUCATION B.S., Civil Engineering, Emphasis in Structural, Tennessee Technological University, 2005REGISTRATIONS/AFFILIATIONS Registered Professional Engineer

-Pennsylvania, 2009Engineer-in-Training

-Tennessee, 2005Member, Chi Epsilon Honor SocietyMember, Toastmasters, Club Number 1381870Member, Kappa Alpha OrderMember, American Institute of Steel Construction STAAD.Pro Committee Representative Chattanooga, Tennessee OfficeSPECIFIC TECHNICAL EXPERTISEISPECIALIST COURSESTennessee Valley Authority Responsible Engineer (R.E.) Training ProgramComputer Training:

AutoCAD FORTRANSmartPlant Review STAAD.Pro MathCAD MS ExcelNavisWorks GTStrudl002-000-CPF-016 (007848)

HRF-0033 Corporate Base Page 5Rev 6 (03-Feb-09)

EcoNomics A29 David W. MoorePROFESSIONAL SUMMARYThirty-five years of nuclear power plant experience most at Sequoyah Nuclear Plant. During this tenure,have held positions as, Outage Management, Operations

Assessor, Human Performance Manager,Operations Work Control Planning and Scheduling

Manager, Shift Manager and various operatorpositions.

PROFESSIONAL EXPERIENCE:

10/11 to Present -worked at Sequoyah Nuclear plant on TVA's Fukushima Japan response teamfocusing on Sequoyah site specific strategies and responses.

7/11 to 10/11- worked at Watts Bar Nuclear plant for the NEI 07 Groundwater Contamination (Tritium) environmental audit.4/11 to 6/11- worked at Sequoyah Nuclear plant for the NEI 07 Groundwater Contamination (Tritium) environmental audit.10/10 to 4/11- worked at Watts Bar Nuclear plant as a Developer for the Unit 1/Unit 2 startup and unitdifferences training for operators.

11/09 to 7/10- worked at Sequoyah Nuclear plant as a Developer for the Learning Material UpgradeProject for Operator Training.

6/09 to 11/09- worked at Sequoyah Nuclear Plant Training Center as an instructor for Operator Training.

12/08 to 5/09- worked at Prairie Island Nuclear plant as a developer for the Maintenance Rule TrainingMaterial.

9/07 to 11/08- worked at Watts Bar Nuclear plant as a Developer for the Learning Material UpgradeProject for Operator Training.

10/06 to 7/07- worked as mentor and operations manager at the Molten Salt Reactor in Oak RidgeTennessee.

9/05- Retired in from Sequoyah Nuclear Plant4/00 to 9/05 Sequoyah Nuclear Plant, Soddy-Daisy, TNShift ManagerPerform the duties of the Shift Manager.

Ensure the safe operation of SQN under all conditions.

Duringan emergency, duties include directing and controlling the actions of the operating crew and supportpersonnel, as well as placing and maintaining the plant in a safe condition.

During accident conditions serve as the Site Emergency Director until properly relieved.

Serves as the Plant Manager whenever heis offsite to ensure the necessary management functions, protective actions and notifications are carriedout.Completed the INPO Shift Managers training program at the INPO training facility.

Served a lead assessor for Sequoyah Nuclear Plant switchyard and plant electrical system reliability.

Served as a team member for the INPO mid-cycle operational readiness assessment at the ColumbiaGenerating Station.Also served a team member for the operational readiness review for the Farley Generating Station.A30I Developed and implemented a Human Performance Coaching and training program for the operations department.

Served as the Work Control Supervisor managing the work schedule, work priorities and plant criticalevolutions.

1986- 2000 Sequoyah Nuclear Plant, Soddy-Daisy, TNUnit Supervisor Obtained and maintained a Senior Reactor Operators license since 1986. .Served as a Unit Supervisor for the Plant restart effort from 1984-1986.

Responsible for the safe and reliable operation of the assignedunit and for compliance with Technical Specifications, operating license requirements, plant procedures, regulations and orders of the NRC Served as the refueling supervisor responsible for the refueling crew,maintenance group, engineering group and associated contractors.

In direct charge of the operation ofthe assigned unit. Direct and supervise licensed and non licensed operators to ensure properperformance of their duties.-

Exercise control over any action which could affect reactivity of the reactor.-

Have the authority to shutdown the unit or any equipment if conditions warrant.-

Authorize the removaland return to service of plant equipment.-

Enforce control room conduct and activities.-

Coordinate operation and surveillance testing of plant equipment and systems..

Coordinate tagging operations toinclude removal from service of all mechanical and electrical equipment.-

Assumed the control roomcommand function in the absence of the Shift Manager.

Had the responsibility for approval and review ofall radwaste releases.

1980- 1986 Sequoyah Nuclear Plant, Soddy-Daisy, TNReactor Operator, As a reactor operator participated in unit start up to 100% power and criticality of thereactor.-

Hot functional testing for the Unit 2 reactor and initial power ascension.-

Obtained a Reactoroperator license in 1981.1979-1980 Sequoyah Nuclear Plant, Soddy-Daisy, TNAssistant Unit OperatorParticipated in initial fuel loading..

Involved in low power physics testing for the initial start up.- Performed operations and alignments of plant systems during plant operation and startup testing.1977-1979 Sequoyah Nuclear Plant, Soddy-Daisy, TNNuclear Student Generating Plant Operator, Completed a two year training program learning systems,procedures and theory of the nuclear industry.

1974-1977 Gilman Paint and Varnish Chattanooga, TN.Chemical Technician, Responsible for sales, purchasing of inventory, store accounting and banking.1973-1974 Industrial Water Chemicals Chattanooga, TN.Chemical Technician Assisted in the development and the manufacture of chemicals.-

Analyzed Boiler and heat exchanger water systems-Prescribed chemical treatment programs for industrial applications Assistant Store ManagerEDUCATION 1968-1973 Tennessee Technological University Cookeville, TNBS Degree in BiologyInterests Antique automobile restoration A31 lIN WorleyParsons S. Lance Summers, P.E.resources

& energy Structural EngineerResumne... ..... ...... .. ........=== , = == = .... ...............

.. , = ... ....... ...... ....R s m .......SUMMARYStructural Engineer with over seven years of engineering experience, including four years withWorleyParsons.

Primary responsibilities included the overall structural design and coordination for alltypes of power plant design and retrofit projects.

Tasks included structural steel design, ductworkdesign, qualifying existing steel for upgraded loads/new code, foundation design, and providing erection/fabrication technical support for power generating stations.

Skilled in creating and analyzing STAAD models for ductwork, structural steel, mat foundations, as well as creatively utilizing othersoftware such as Excel, MathCAD, Smart Plant, and similar programs to expedite design. Also activein client interface with participation in project meetings and budget proposals.

In addition, responsibilities include the inspection of ductwork, structural steel, and chimneys as part of theChattanooga Condition Assesment Team. Familiar with AISC Steel Manual (ASD and LRFD), ACI318-05, IBC 2000, and ASCE 7-05.EXPERIENCE 2009 -Present Structural

Engineer, WorleyParsons, Chattanooga, Tennessee Tennessee Valley Authority (TVA) -Sequoyah Nuclear Power Plant, Soddy-Daisy, Tennessee.

Qualification of new and existing nuclear fire protection pipe supports for new loading conditions, following appropriate design criteria, code provisions, and NRC requirements.

Qualification andspecification of both existing and new pipe support components, such as struts, clamps, and anchors.Qualification and design of non-standard welded connections.

Pipe supports qualified usingcomputer

modeling, utilizing TVA supplied software.

Software includes FAPPS (ME150),BASEPLATE II (ME035),

MAPPS (ME153),

CONAN, and lAP. Creation of supporting calculation packages utilizing

MathCAD, Microsoft Excel and Word. Responsible for design input and verification of DCA (Drawing Change Authorization),

which serves as the working document for required pipesupport configurations and final support drawings to be issued into the TVA database.

Tennessee Valley Authority (TVA) -Browns Ferry Nuclear Power Plant, Athens, Alabama.Qualification of existing nuclear pipe supports for new loading conditions associated with thereplacement of motors on two minimum flow valves, following appropriate design criteria, codeprovisions, and NRC requirements.

Qualification and specification of existing pipe supportcomponents, such as struts, clamps, and anchors.

Qualification and design of non-standard weldedconnections.

Pipe supports qualified using computer

modeling, utilizing TVA supplied software.

Software includes FAPPS (ME150),

BASEPLATE II (ME035),

MAPPS (ME153),

CONAN, and lAP.Creation of supporting calculation packages utilizing

MathCAD, Microsoft Excel and Word.Responsible for design input and verification of DCA (Drawing Change Authorization),

which servesas the working document for required pipe support configurations and final support drawings to beissued into the TVA database.

Tennessee Valley Authority (TVA) -Watts Bar Nuclear (WBN) Power Plant Unit 2,1200 MWUnit, Spring City, Tennessee.

Served as a team lead for a group of five engineers supporting theWBN Unit 2 pipe support project.

Responsibilities

include, but not limited to, the qualification ofexisting nuclear pipe supports for new loading conditions following the appropriate design criteria, code provisions, and NRC requirements.

Qualification of existing and new pipe support components, such as snubbers, struts, clamps, and springs.

Qualification and design of non-standard weldedconnections.

The task utilized computer modeling via TVA-supplied software.

The software includesFAPPS (ME150),

BASEPLATE II (ME035),

MAPPS (ME153),

CONAN, and lAP. MathCAD, Excel,and Word. Software used in the creation of support calculation packages.

Responsible for thereview of Drawing Revision Authorization (DRA) to ensure accurate support drawings for issuanceinto the TVA database.

Additional responsibilities included the review and verification of pipe supportcalculations prior to issuance and coordination between multiple offices to ensure quality,completeness, and consistency.

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EcoNomics A32 WorleyParsons S. Lance Summers, P.E.resources

& energy Structural EngineerResume...... .. ..... ... ..... .... ..... .... ..R.....e....

..s..u.. .m e...... ...... ..TVA- Widows Creek Fossil Unit 8 Opacity Reduction Study. Served as the structural task leadfor a cost study of the addition of various air quality control measures (baghouse/precipitator) toWidows Creek Unit 8. The task included preliminary structural engineering of new ductwork, structural support steel, foundations, as well as the retrofit of the existing ductwork and structures.

The work involved site visits to walkdown existing structures to find ways to interface with existingequipment and route ductwork through the existing structure.

Interface with mechanical leads toprovide the necessary ductwork cross-section and to ensure an efficient flow path to achieve aminimal pressure drop. Worked closely with the estimating department in order to produce anaccurate cost estimate for four different retrofitting options.Southern Company -Scherer Unit 1-4, Flue Gas Desulphurization (FGD)/Selective Catalytic Reduction (SCR) Project, Juliet, Georgia.

Responsible for the design of an electrical utility bridgefor Units 1 and 2. The process included the layout of the utility bridge using SmartPlant Review andthe design of the structure utilizing STAAD Pro. The task included the design of anchor bolts and thedesign of spread footings to support the structure.

RC Cape May Holdings, LLC. -BL England Unit 2 Emissions Control Project, Beesley's Point,New Jersey. Primary responsibilities included the analysis and design of pile foundations to supportthe new SCR structure.

The task included using SmartPlant Review to coordinate thelayout ofaugercast piles in order to avoid existing interferences and obstructions.

STAAD Pro 2007 finiteelement analysis used to analyze the pipe cap foundation.

ACI 318-05 was utilized to provide theproper reinforcement for the pile cap as well as ensure that the anchor bolts met the requirements ofAppendix D.2007 -2009 Structural Engineer Associate, WorleyParsons, Chattanooga, Tennessee CPS Peaking -Turbine Project, Braunig Plant, Texas. Primary responsibilities included thecomputer

modeling, anlaysis, and design of soil supported mat foundations.

Analysis and design ofsmall equipment foundations including oil containment areas. Interfaced with the mechanical department in order to provide pipe supports and the associated foundations to support the chilledwater and natural gas piping systems throughout the plant.Southern Company -Scherer Unit 1-4, FGD/SCR Project, Juliet, Georgia -Primaryresponsibilities included the retrofit of existing ductwork and support structures due to increased loading caused by an upgraded pressure load associated with the addition of a mercury baghouse, FGD, and SCR. STAAD used to analyze the ductwork and support structures while PCA Column andLPile were used to evaluate the existing caissons and piers. Retrofit modifications were made toqualify the structures for the increased shear, uplift, and compressive forces that were caused by theupgraded pressure.

Mitsubishi Power Systems Americas

-Termocandelaria, Simple Cycle Plant Dual FuelConversion, Cartegena, Colombia.

Primary responsibilities included the computer

modeling, analysis, and design of soil supported mat foundations.

Analysis and design of small equipment foundations including oil containment areas. Provided pipe supports and foundations to assistmechanical/electrical engineers in the balance-of-plant design. Produced calculations for cast-in-place and post-installed equipment anchorage to concrete.

Other duties included the design ofconcrete and masonry structures that were needed due to fire rating requirements.

Work alsoincluded coordinating work with other disciplines to produce deliverables, providing project managerwith regular updates, and producing estimates and NWIs for additional work added to the Structural Engineering Scope.Southern Company -Plant Scherer Unit 3 Mercury Baghouse, Juliet, Georgia.

Primaryresponsibilities included performing the design and analysis of large ductwork and their supportstructures, as well as providing fabrication/erection support to the client. Other duties includedcreating and analyzing models for existing steel, ductwork, and working with designers to facilitate thegeneration of drawing deliverables, and meeting schedule requirements.

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EcoNomics A33

WorleyParsons resources

& energyS. Lance Summers, P.E.Structural EngineerResume2004-2007 Condition Assessment Services Team Member, WorleyParsons, Chattanooga, Tennessee In addition to structural engineering responsibilities, additional responsibilities include condition assessment inspections at fossil power plants. The tasks include traveling to the site and performing inspections, documenting the existing conditions of the respective component during the inspection, and providing a formalized post-inspection report which documents the findings and makesrecommendations on any needed modifications to the structure.

Typical inspections include air andflue gas ductwork, circulating cooling water tunnels, chimneys and stacks, and other miscellaneous structural systems.Project Engineer

-C.W. Matthews Contracting Co., Marietta, GeorgiaGDOT -McFarland Rd/SR 400 Interchange Project.

Primary responsibilities included the designand implementation of erosion control plans, traffic control plans, and staging plans. In addition, responsibilities included working with Department of Transportation (DOT) representatives toalter/change plan design in order to account for situations in the field or in order to have a minimalimpact of the traveling public. Responsibilities also included the coordination and scheduling of workand subcontractors.

GDOT -SR20/SR400 Interchange Improvement Project.

Primary responsibilities included thecoordination and scheduling of work done by subcontractors and inspection of the work uponcompletion.

In addition, responsibilities included working with DOT representatives to redesign planin order to accommodate existing field conditions and to produce a more buildable design which wassafer for the constructors as well as the traveling public. This included stormwater drainage plans,traffic control plans, and staging plans.EDUCATION B.S., Civil Engineering Technology, Southern Polytechnic State University,

Marietta, Georgia, 2003.REGISTRATIONS/AFFILIATIONS Registered Professional

Engineer, Civil, Pennsylvania, No. PE077046, 2009Member, American Institute of Steel Construction (AISC)Confined Space and Fall Protection TrainedSPECIFIC TECHNICAL EXPERTISE/SPECIALIST COURSESComputer SkillsSTAADPro V8iMathCADLPile Plus 5.0Microsoft Office Applications AutoCADSmartPlant ReviewSmartPlant Foundation PCA Column002-ooo-OPF-016 (007848)

HRF-0033Rev 6 (03.Feb-09)

Corporate BasePage 3EcoNomics A34 Glynna J WilsonCivil Design EngineerSequoyah Nuclear PlantTennessee Valley Authority SUMMARYCivil Engineer with 4.5 years of experience with the Tennessee Valley Authority at SequoyahNuclear Plant. Experience includes designing structural modifications with plant system,equipment seismic qualification, design change field implementation, and other various roles ofa Civil Engineer.

Lead Civil Engineer on Maintenance Rule, Structural Monitoring, and DamGovernance.

Also, the Site Snubber Program Engineer.

Familiar with AISC Steel Construction Manual, ACI 318 Building Code, and ASCE 7 Minimum Design Loads for buildings and otherstructures.

Proficient with current design software including AutoCAD and MathCAD.EXPERIENCE Tennessee Valley Authority-Served as a Civil Engineer within the Civil Engineering DesignGroup at Sequoyah Nuclear Plant since April 2008. Is qualified in Equipment SeismicQualification and performed numerous evaluations of equipment during the procurement process.

Responsible for field support for design change implementation.

Familiar with the TVACAP process and how it is used for problem identification and resolution.

Qualified CivilEngineer in the Maintenance Rule Program responsible for maintaining structural condition ofplant buildings and entering them into the CAP program and Maintenance Rule TrackingCalculation in order to monitor and drive resolution.

Other responsibilities include field support,design change packages, verification of others work, and interface with other departments within and outside of the Engineering Organization.

EDUCATION B.S., Civil Engineering, University of Tennessee at Chattanooga, Chattanooga, Tennessee, 2008A35

WorleyParsons resources

& energyPhillip W. York, E.I.T.Structural Engineering Associate ResumeSUMMARYStructural Engineering Associate with over three years of experience in the structural and civilengineering fields including pipe support systems analysis and structural design.EXPERIENCI 2010 -Present20112008-2009 2007-2008 EStructural Engineering Associate, WorleyParsons, Chattanooga, Tennessee Tennessee Valley Authority (TVA) -Brown's Ferry Nuclear Power Plant, Athens, Alabama.Assisted in identifying and locating electrical panels and components for cable identification in all firesafety related systems.TVA -Watts Bar Nuclear Power Plant, Spring City, Tennessee.

Conducted field walkdowns ofpiping layout and supports.

TVA- Bellefonte Nuclear Power Plant, Hollywood, Alabama.

Originated engineering analysis ofpipe support systems including baseplates, structural steel, anchor bolts, welds, vendor components, and integral attachments.

Civil Engineer, Atwell Group, Charleston, Tennessee Verified field accuracy and installation of storm sewers and sewer structures compared with designeddrawings.

Structural

Engineer, March Adams & Associates, Chattanooga, Tennessee Assisted on structural design and site planning of engineering projects including a precast concretebridge, apartment complexes, and various industrial sites.Dam Safety/River Operations Intern, TVA, Chattanooga, Tennessee Programmed proprietary database to accept decades of instrumentation data from hydroelectric plants and to calculate along predetermined parameters.

EDUCATION B.S., Engineering (Civil Concentration),

University of Tennessee, Chattanooga, Tennessee, 2008REGISTRATIONSIAFFILIATIONS Engineer-in-Training, State of Tennessee, License #26776SPECIFIC TECHNICAL EXPERTISE

AutoCAD, 2D and 3D DraftingSolidWorks, 2D and 3D DraftingSTAAD.Pro, Structural Analysis and DesignRISA, 2D and 3D Structural Analysis002-000-CPF-016 (007848)

HRF-0033 Corporate Base Page 1Rev 6 (03-Feb-09)

EcoNomics A36 Na .r 21JKCertificate of Completion Isaac Antanaitis Training on. Near TermTask ForceRecommendation 2.3-Plant Seismic Walkdowns if, lllo.June 21, 2012DateRobert K. Kassawara EPRI Manager;Structural Reliability

& Integrity A37 L~~~FI2 EFCTAWC FPOW!Rau~ra IS REEARdeCH INS1'MUTCertificate ofCompletion Joshua BestTraining on Near Term Task ForceRecommendation 2.3-Plant Seismic Walkdowns June 21, 2012DateRobert K. Kassawara EPRI Manager,Structural Reliability

& Integrity A38 FFCIRIC POMPl 1Certificate of Completion John DizonTraining on Near Term Task ForceRecommendation 2.3-Plant Seismic Walkdowns June 21, 2012.Dateif, jiilp.Robert K. Kassawara EPRI Manager.Strucural Refiabillty

& Integrity A39 ra~feI fU(ITQ;C POWERCertificate of Completion Stephen EderTraining on NearTerm Task ForceRecommendation 2.3-Plant Seismic Walkdowns June 21, 2012DateRobert K. Kassaware EPRI Manager,Strcual ReiftbIty

& Integrity A40 ELECTRIC POWERa1=0I RESEARCH INSTITUTE Certificate of Completion Robert MaloneTraining on Near Term Task ForceRecommendation 2.3-Plant Seismic Walkdowns June 21, 2012Dateif. j. 44444Robert K. Kassawara EPRI Manager,Structural Reliability

& Integrity A41 ELECTRIC POWERCertificate of Completion Karen TracyTraining on Near Term Task ForceRecommendation 2.3-Plant Seismic Walkdowns June 21, 2012DateRobert K. Kassawara EPRI Manager,Structural Reliability

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..... ... ... ...i ..... ... .'-i2tn- es II W Ae~ .. i~A45 Appendix B: Base List 1This Appendix includes the Sequoyah Unit 2 Base List 1..BI Sequoyah Unit 2UNIDO-ACCM-032-0060 0-ACCM-032-0086 0-AHU-311-0020 O-AHU-311-0023 O-AHU-311-0027 0-AHU-311-0028 0-BATB-250-QV O-BATB-250-QW 0-BATB-250-QX O-BATB-250-QY O-BDG-250-KE 0-BDG-250-KF O-BDG-250-KG O-BDG-250-KH 0-CHGB-250-QE O-CHGB-250-QF O-CHGB-250-QG O-CHGB-250-QH O-CHGB-250-QJ O-CHGB-250-QK 0-CHR-311-0126 0-CHR-311-0141 0-CHR-311-0156 0-CHR-311-0171 0-CHR-313-0303 0-CHR-313-0338 0-CLR-030-0192 0-CLR-030-0193 0-CLR-032-0065 0-CLR-032-0092 0-CMP-032-0060 0-CMP-032-0086 Base List IDescription AUX CONTROL AIR ACC AAUX CONTROL AIR ACC BMAIN CONTROL ROOM AHU A-AMAIN CONTROL ROOM AHU B-BELEC BOARD ROOM AHU A-AELEC BOARD ROOM AHU B-B125V DC VITAL BATTERY I125V DC VITAL BATTERY II125V DC VITAL BATTERY III125V DC VITAL BATTERY IV125V DC VITAL BATTERY BOARD I125V DC VITAL BATTERY BOARD II125V DC VITAL BATTERY BOARD III125V DC VITAL BATTERY BOARD IV125V DC VITAL BATTERY CHARGER I125V DC VITAL BATTERY CHARGER 1-SPARE125V DC VITAL BATTERY CHARGER II125V DC VITAL BATTERY CHARGER III125V DC VITAL BATTERY CHARGER IV125V DC VITAL BATTERY CHARGER 2-SPAREMAIN CONTROL ROOM CHILLER PKG A-AMAIN CONTROL ROOM CHILLER PKG B-BELEC BOARD ROOM CHILLER PKG A-AELEC BOARD ROOM CHILLER PKG B-BSHUTDOWN BD ROOMS A&B CHILLER PKG A-ASHUTDOWN BD ROOMS A8B CHILLER PKG 8-8SPENT FUEL PIT PMP & TB BOOSTER PMP RM COOLER A-ASPENT FUEL PIT PMP 8 TB BOOSTER PMP ROOM COOLER B-BAUX CONTROL AIR AFTERCOOLER AAUX CONTROL AIR AFTERCOOLER BAUX CONTROL AIR COMPRESSOR A-AAUX CONTROL AIR COMPRESSOR B-BSafetyFunction00000000000000000000000000550000B2 Sequoyah Unit 2UNID0-CRN-303-SJ 0-DRYA-032-0074 0-DRYA-032-0075 0-DRYA-032-0099 0-DRYA-032-0100 0-FCV-070-0001 0-FCV-070-0011 0-FCV-070-0040 0-FCV-070-0041 0-FCV-070-0193 0-FCV-070-0194 0-FCV-070-0197 0-FCV-070-0198 0-FCV-070-0206 0-FCV-070-0208 0-FLT-032-0074 0-FLT-032-0075 0-FLT-032-0082 0-FLT-032-0085 0-FSV-311-0022A 0-FSV-311-0022B 0-FSV-311-0039A 0-FSV-311-0039B 0-FSV-311-0041A 0-FSV-311-0041B 0-FSV-311-0043A 0-FSV-311-0043B 0-HEX-070-0012A 0-HEX-070-0012B 0-HEX-077-0096 0-HEX-077-0111 0-HEX-078-0017 Base List 1Description 125 TON AUX BLDG CRANEAUX BLDG AIR DRYER (NO 1) A-AAUX BLDG AIR DRYER (NO 2) A-AAUX BLDG AIR DRYER (NO 2) B-BAUX BLDG AIR DRYER (NO 1) B-BSFPCS HTX B OUTLET VLVSFPCS HTX A OUTLET VLVSFPCS HTX B INLET VLVSFPCS HTX A INLET VLVSFPCS HTX SUPPLY HEADER VLVSFPCS HTX SUPPLY HEADER VLVSFPCS HTX SUPPLY HEADER VLVSFPCS HTX SUPPLY HEADER VLVCOND DEMIN WASTE EVAL BLDF RETURN ISOL VLVCOND DEMIN WASTE EVAL BLDF SUPPLY ISOL VLVAUX CONRTOL AIR COMPRESSOR A-A PREFILTER AUX CONRTOL AIR COMPRESSOR B-B PREFILTER CONTROL AIR AFTERFILTER TO DRYERS A-ACONTROL AIR AFTERFILTER TO DRYERS B-BMAIN CONT RM AHU A-A TEMPMAIN CONT RM AHU A-A TEMPMAIN CONT RM AHU B-B TEMPMAIN CONT RM AHU B-B TEMPELECTRICAL BD RM AHU B-B TEMPELECTRICAL BD RM AHU B-B TEMPELECTRICAL BD RM AHU B-B TEMPELECTRICAL BD RM AHU B-B TEMPCOMPONENT COOLING HX 0B1COMPONENT COOLING HX 0B2WASTE GAS COMPRESSOR A HEAT EXCHANGER WASTE GAS COMPRESSOR B HEAT EXCHANGER SPENT FUEL PIT HEAT EXCHANGER BSafetyFunction00000555555555500000000000000000B3 Sequoyah Unit 2UNID0-HEX-078-0018 O-LS-018-0062A/1 0-LS-018-0062A/2 0-LS-018-0062A/3 0-LS-018-0062A/4 0-LS-018-0062B/1 0-LS-018-00621B/2 0-LS-018-0062B/3 0-LS-018-0062B/4 0-LS-018-0078A/1 0-LS-018-0078A/2 0-LS-018-0078A/3 O-LS-018-0078A/4 0-LS-018-0078B/1 0-LS-018-0078B/2 0-LS-018-0078B/3 0-LS-018-0078B/4 0-PMP-067-0432 O-PMP-067-0436 0-PMP-067-0440 0-PMP-067-0444 O-PMP-067-0452 O-PMP-067-0456 0-PMP-067-0460 0-PMP-067-0464 0-PMP-067-0470 0-PMP-067-0477 0-PMP-067-0482 0-PMP-067-0487 0-PMP-070-0051 0-PMP-313-0303 0-PMP-313-0338 Base List 1Description SPENT FUEL PIT HEAT EXCHANGER ADSL GENERATOR DAY TANK 1 LEVEL-LOW DSL GENERATOR DAY TANK 1 LEVEL-LOW DSL GENERATOR DAY TANK 1 LEVEL-LOW DSL GENERATOR DAY TANK 1 LEVEL-LOW DSL GENERATOR DAY TANK 1 LEVEL-HIDSL GENERATOR DAY TANK 1 LEVEL-HIDSL GENERATOR DAY TANK 1 LEVEL-HIDSL GENERATOR DAY TANK 1 LEVEL-HIDSL GENERATOR DAY TANK 2 LEVEL-LOW DSL GENERATOR DAY TANK 2 LEVEL-LOW DSL GENERATOR DAY TANK 2 LEVEL-LOW DSL GENERATOR DAY TANK 2 LEVEL-LOW DSL GENERATOR DAY TANK 2 LEVEL-HIDSL GENERATOR DAY TANK 2 LEVEL-HIDSL GENERATOR DAY TANK 2 LEVEL-HIDSL GENERATOR DAY TANK 2 LEVEL-HIERCW PUMP J-AERCW PUMP K-AERCW PUMP L-BERCW PUMP M-BERCW PUMP N-BERCW PUMP P-BERCW PUMP Q-AERCW PUMP R-AERCW SCREEN WASH PUMP A-AERCW SCREEN WASH PUMP B-BERCW SCREEN WASH PUMP C-BERCW SCREEN WASH PUMP D-ACCS PUMP C-SSHTDN BD RM A&B CW SYS CIRC PMPSHTDN BD RM A&B CW SYS CIRC PMPSafetyFunction04444444444444444000000000000000B4 Sequoyah Unit 2Base List 1UNID0-SGEN-311-0053 0-SGEN-311-0062 0-TCV-067-0195 0-TCV-067-0197 0-TCV-067-0199 0-TCV-067-0201 0-TNK-018-5032-1A1 0-TNK-018-5032-1A2 0-TNK-018-5032-1A3 0-TNK-018-5032-1A4 0-TNK-018-5032-1B1 0-TNK-018-5032-1B2 0-TNK-018-5032-1B3 0-TNK-018-5032-1B4 0-TNK-018-5032-2A1 0-TNK-018-5032-2A2 0-TNK-018-5032-2A3 0-TNK-018-5032-2A4 0-TNK-018-5032-2B1 0-TNK-018-5032-2B2 0-TNK-018-5032-2B3 0-TNK-018-5032-2B4 0-TNK-032-0062 0-TNK-032-0088 2-AHU-030-0080 2-AHU-030-0083 2-AHU-030-0088 2-AHU-030-0092 2-AHU-313-0262 2-AHU-313-0267 2-AHU-313-0332 2-AHU-313-0367 Description MAIN CONT RM AHU A-A STEAM GENELECT BD RM AHU A-A STEAM GENELECT RM A/C COND A SUPPLY CNTL VLVCONT BLDG A/C COND A SUPPLY CNTL VLVELECT RM A/C COND B SUPPLY CNTL VLVCONT BLDG A/C COND B SUPPLY CNTL VLVHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKHORIZONTAL DSL FUEL OIL STG TNKAUX CONTROL AIR RECVR A-AAUX CONTROL AIR RECVR B-BCONTROL ROD DRIVE COOLING UNIT D-BCONTROL ROD DRIVE COOLING UNIT A-ACONTROL ROD DRIVE COOLING UNIT C-ACONTROL ROD DRIVE COOLING UNIT B-BINCORE INST RM AHU AINCORE INST RM AHU BSHTDN BD RM B SUPPLY AHU 2A-ASHTDN BD RM B SUPPLY AHU 2B-BSafetyFunction00000000000000000000000055550000B5 Sequoyah Unit 2UNID2-AHU-313-0488 2-AHU-313-0514 2-BATB-082-UD 2-BATB-082-U E2-BDA-202-CO 2-BDB-201-DN 2-BDB-201-DO 2-BDB-201-DP 2-BDB-201-DQ 2-BDB-202-CP 2-BDC-201-FL 2-BDC-201-FN 2-BDC-201-FQ 2-BDC-201-FR 2-BDC-201-FU 2-BDC-201-FV 2-BDC-201-GL 2-BDC-201-GM 2-BDC-201-GN 2-BDC-201-GO 2-BDC-201-JJ 2-BDC-201-JK 2-BDC-201-JL 2-BDC-201-JM 2-BDC-201-JP 2-BDC-201-JQ 2-BDE-250-ND 2-BDE-250-NF 2-BDE-250-NH 2-BDE-250-NK 2-CHGB-062-TZ 2-CHGB-062-UA Base List IDescription 480V BD RM 2A SUPPLY AHU 2A-A480V BD RM 2B SUPPLY AHU 2B-BDG 2A-A BATTERYDB 2B-B BATTERY6900V SHUTDOWN BOARD 2A-A480V SHUTDOWN BD 2A1-A480V SHUTDOWN BD 2A2-A480V SHUTDOWN BD 2B1-B480V SHUTDOWN BD 2B2-B6900V SHUTDOWN BOARD 2B-B480V ERCW MCC 2A-A480V ERCW MCC 2B-B480V DIESEL AUXILIARY BOARD 2A1-A480V DIESEL AUXILIARY BOARD 2A2-A480V DIESEL AUXILIARY BOARD 2B1-B480V DIESEL AUXILIARY BOARD 2B2-B480V REACTOR MOV BOARD 2A1-A480V REACTOR MOV BOARD 2A2-A480V REACTOR MOV BOARD 2B1-B480V REACTOR MOV BOARD 2B2-B480V CONTROL & AUX BLDG VENT BOARD 2A1-A480V CONTROL & AUX BLDG VENT BOARD 2A2-A480V CONTROL & AUX BLDG VENT BOARD 2B1-B480V CONTROL & AUX BLDG VENT BOARD 2B2-B480V REACTOR VENT BOARD 2A-A480V REACTOR VENT BOARD 2B-B120V AC VITAL INST POWER BOARD 2-1120V AC VITAL INST POWER BOARD 2-11120V AC VITAL INST POWER BOARD 2-111120V AC VITAL INST POWER BOARD 2-IVDG 2A-A BATTERY CHARGERDG 2B-B BATTERY CHARGERSafetyFunction00000000000000000000000000000000B6 Sequoyah Unit 2UNID2-CHR-043-0156 2-CHR-313-0221A 2-CHR-313-0228A 2-CLR-030-0074 2-CLR-030-0075 2-CLR-030-0077 2-CLR-030-0078 2-CLR-030-0095 2-CLR-030-0097 2-CLR-030-0099 2-CLR-030-0100 2-CLR-030-0175 2-CLR-030-0176 2-CLR-030-0177 2-CLR-030-0178 2-CLR-030-0179 2-CLR-030-0180 2-CLR-030-0181 2-CLR-030-0182 2-CLR-030-0183 2-CLR-030-0184 2-CLR-030-0185 2-CLR-030-0186 2-CLR-030-0187 2-CLR-030-0194 2-CLR-030-0195 2-CLR-030-0196 2-CLR-030-0197 2-CLR-030-0201 2-CLR-030-0202 2-CLR-043-0331A 2-CLR-043-0331B Base List 1Description HOT SAMPLE ROOM CHILLERINCORE INST RMWTR CHILLER PKG AINCORE INST RMWTR CHILLER PKG BLOWER COMPT COOLING UNIT A-ALOWER COMPT COOLING UNIT C-ALOWER COMPT COOLING UNIT B-BLOWER COMPT COOLING UNIT D-BUPPER COMPT COOLING UNIT AUPPER COMPT COOLING UNIT BUPPER COMPT COOLING UNIT CUPPER COMPT COOLING UNIT DRHR PUMP RM COOLER 2A-ARHR PUMP RM COOLER 2B-BCONTAINMENT SPRAY PUMP RM COOLER 2A-ACONTAINMENT SPRAY PUMP RM COOLER 2B-BSIS PUMP RM COOLER 2B-BSIS PUMP RM COOLER 2A-ARECIP CHG PMP RM COOLER 2C-BCENTRIF CHARGING PUMP RM COOLER 2B-BCENTRIF CHARGING PUMP RM COOLER 2A-ABA XFER PMP & AUX FW PMP SP CLR A-ABA XFER PMP & AUX FW PMP SP CLR B-BPENETRATION ROOM COOLER 2A-APENETRATION ROOM COOLER 2B-BPENETRATION ROOM COOLER 2A-APENETRATION ROOM COOLER 2B-BPENETRATION ROOM COOLER 2A-APENETRATION ROOM COOLER 2B-BPIPE CHASE COOLER 2A-APIPE CHASE COOLER 2B-BPOST ACCIDENT SAMPLING COOLERS 1POST ACCIDENT SAMPLING COOLERS 2SafetyFunction50055555555555555055555555555555B7 Sequoyah Unit 2UNID2-CLR-062-0191 2-CM P-082-0240 2-CMP-082-0241 2-CMP-082-0270 2-CMP-082-0271 2-CMP-313-0483 2-CMP-313-0508 2-CND-062-0192 2-CND-062-0196 2-CND-313-2074 2-CND-313-2075 2-CRN-303-DQ 2-ENG-082-0002A1 2-ENG-082-0002A2 2-ENG-082-0002B1 2-ENG-082-0002B2 2-FAN-030-0038 2-FAN-030-0039 2-FAN-030-0246A 2-FAN-030-0246B 2-FAN-030-0246D 2-FAN-030-0246E 2-FAN-030-0250A 2-FAN-030-0250B 2-FAN-030-0316 2-FAN-030-0317 2-FAN-030-0448 2-FAN-030-0450 2-FAN-030-0452 2-FAN-030-0454 2-FAN-030-0456 2-FAN-030-0458 Base List 1Description BORIC ACID EVAP PKG B DISTILLATE COOLERDSL 2A1 STARTING AIR COMPRESSER 25.5 CFMDSL 2A2 STARTING AIR COMPRESSER 25.5 CFMDSL 2B1 STARTING AIR COMPRESSER 25.5 CFMDSL 2B2 STARTING AIR COMPRESSER 25.5 CFM480V ELECT BD RM 2A AIR RECIP COMP 2A-A480V ELECT BD RM 2B AIR RECIP COMP 2B-BBORIC ACID EVAP PKG B CONDENSER BORIC ACID EVAP PKG B VENT CONDENSER 480V ELECT BD RM 2A AIR COOLED COND 2A-A480V ELECT BD RM 2B AIR COOLED COND 2B-B175 TON POLAR CRANEDIESEL ENGINE 2A1DIESEL ENGINE 2A2DIESEL ENGINE 2B1DIESEL ENGINE 2B2CNTMT AIR RETURN FAN ACNTMT AIR RETURN FAN B480V TRANSFORMER ROOM 2B EXH FAN 2B1-A480V TRANSFORMER ROOM 2B EXH FAN 2B2-A480V TRANSFORMER ROOM 2B EXH FAN 2B3-A480V TRANSFORMER ROOM 2B EXH FAN 2B4-A480V TRANSFORMER ROOM 2A EXH FAN 2A1-B480V TRANSFORMER ROOM 2A EXH FAN 2A2-BDIESEL PANEL 2A-A VENT FANDIESEL PANEL 2B-B VENT FAND-G RM 2A-A EXHAUST FAN 1D-G RM 2B-B EXHAUST FAN 1D-G RM 2A-A EXHAUST FAN 2D-G RM 2B-B EXHAUST FAN 2DIESEL GEN ROOM 2A-A BATTERY HOOD EXHAUSTDIESEL GEN ROOM 2B-B BATTERY HOOD EXHAUSTSafetyFunction3,50000003,53,500000005555555555555555B8 Sequoyah Unit 2UNID2-FAN-030-0460 2-FAN-030-0462 2-FAN-030-250D 2-FAN-313-0496 2-FAN-313-0497 2-FAN-313-0522 2-FAN-313-0523 2-FCO-030-0250B 2-FCO-030-246A 2-FCO-030-246B 2-FCO-030-250A 2-FCO-313-0478A 2-FCO-313-0478B 2-FCO-313-0496 2-FCO-313-0497 2-FCO-313-0498 2-FCO-313-0499 2-FCO-313-0503 2-FCO-313-0510 2-FCO-313-0522 2-FCO-313-0523 2-FCO-313-0524 2-FCV-001-0004 2-FCV-001-0007 2-FCV-001-0011 2-FCV-001-0014 2-FCV-001-0015 2-FCV-001-0016 2-FCV-001-0022 2-FCV-001-0025 2-FCV-001-0029 2-FCV-001-0032 Base List IDescription DIESEL GEN 2A-A ELECT BD ROOM EXHAUST.DIESEL GEN 2B-B ELECT BD ROOM EXHAUST480V TRANSFORMER ROOM 2A EXH FAN 2A3-BBATTERY ROOM IV EXHAUST FAN 2B1-ABATTERY ROOM IV EXHAUST FAN 2B2-BBATTERY ROOM III EXHAUST FAN 2A1-ABATTERY ROOM III EXHAUST FAN 2A2-BTRANSFORMER ROOM 2A DAMPERTRANSFORMER ROOM 2B DAMPERTRANSFORMER ROOM 2B DAMPERTRANSFORMER ROOM 2A DAMPERBOARD RM CONDENSER 2A-A DAMPERBOARD RM CONDENSER 2A-A DAMPERBATTERY ROOM IV DAMPER FOR FAN Al-ABATTERY ROOM IV DAMPER FOR FAN A2-BBATTERY ROOM IV DAMPER FOR FAN A2-BBATTERY ROOM IV DAMPER FOR FAN Al-ABOARD RM CONDENSER 2B-B DAMPERBATTERY ROOM III DAMPER FOR FAN B2-BBATTERY ROOM III DAMPER FOR FAN B1-ABATTERY ROOM III DAMPER FOR FAN B2-BBATTERY ROOM III DAMPER FOR FAN Bl-ASG 1 MAIN STM HDR ISOLATION VALVEBLOWDOWN FLOW CONTROL VLV, SG-1SG 2 MAIN STM HDR ISOLATION VALVEBLOWDOWN HDR FLOW CONTROL VLV, SG-2AUX FW PMP TURB STM SUPPLY FROM SG NO 1AUX FW PMP TURB STM SUPPLY FROM SG NO 4SG 3 MAIN STM HDR ISOLATION VALVEBLOWDOWN HDR FLOW CONTROL VLV, SG-3SG 4 MAIN STM HDR ISOLATION VALVEBLOWDOWN HDR FLOW CONTROL VLV. SG-4SafetyFunction555000055550000000000055554,54,55555B9 Sequoyah Unit 2UNID2-FCV-O01-OlB1 2-FCV-001-01B2 2-FCV-O01-01B3 2-FCV-001-01B4 2-FCV-003-0033 2-FCV-003-0047 2-FCV-003-0087 2-FCV-003-O100 2-FCV-003-0126A 2-FCV-003-0136A 2-FCV-003-0166A 2-FCV-003-0166B 2-FCV-003-0179A 2-FCV-003-0179A 2-FCV-026-0240 2-FCV-026-0243 2-FCV-030-0007 2-FCV-030-0008 2-FCV-030-0009 2-FCV-030-0010 2-FCV-030-0014 2-FCV-030-0015 2-FCV-030-0016 2-FCV-030-0017 2-FCV-030-0019 2-FCV-030-0020 2-FCV-030-0037 2-FCV-030-0040 2-FCV-030-0047 2-FCV-030-0048 2-FCV-030-0050 2-FCV-030-0051 Base List 1Description BLOWDOWN ISOL VLV INSIDE CNTMT, SG-1BLOWDOWN ISOL VLV INSIDE CNTMT, SG-2BLOWDOWN ISOL VLV INSIDE CNTMT, SG-3BLOWDOWN ISOL VLV INSIDE CNTMT, SG-4SG#1 FW ISOLATION VALVESTM GEN #2 ISOLATION VALVESTM GEN #3 ISOLATION VALVESTM GEN #4 FW ISOLATION VALVEERCW HDR B ISOL VLVERCW HDR A ISOL VLVERCW HDR A ISOL VLVERCW HDR A ISOL VLVERCW HDR B ISOL VLVERCW HDR B ISOL VLVCONTAINMENT STAND PIPEREACTOR COOLANT PMP SPRAY ISOL VLVUPPER COMPT PURGE ISOLATION VALVEUPPER COMPT PURGE ISOLATION VALVEUPPER COMPT PURGE ISOLATION VALVEUPPER COMPT PURGE ISOLATION VALVELOWER COMPT PURGE ISOLATION VALVELOWER COMPT PURGE ISOLATION VALVELOWER COMPT PURGE ISOLATION VALVELOWER COMPT PURGE ISOLATION VALVEINCORE INSTR ROOM PURGE ISOLATION VALVEINCORE INSTR ROOM PURGE ISOLATION VALVELOWER COMPT PURGE CTRL VALVELOWER COMPT PURGE CTRL VALVECONTAINMENT VACUUM RELIEFCONTAINMENT VACUUM RELIEFUPPER CNTMT EXH ISOLATION VALVEUPPER CNTMT EXH ISOLATION VALVESafetyFunction44445555444444555555555555555555B10 Sequoyah Unit 2UNID2-FCV-030-0052 2-FCV-030-0053 2-FCV-030-0056 2-FCV-030-0057 2-FCV-030-0058 2-FCV-030-0059 2-FCV-032-0081 2-FCV-032-0103 2-FCV-032-0111 2-FCV-061-0096 2-FCV-061-0097 2-FCV-061-0110 2-FCV-061-0122 2-FCV-061-0191 2-FCV-061-0192 2-FCV-061-0193 2-FCV-061-0194 2-FCV-062-0009 2-FCV-062-0022 2-FCV-062-0035 2-FCV-062-0048 2-FCV-062-0061 2-FCV-062-0063 2-FCV-062-0069 2-FCV-062-0070 2-FCV-062-0072 2-FCV-062-0073 2-FCV-062-0074 2-FCV-062-0077 2-FCV-062-0085 2-FCV-063-0001 2-FCV-063-0003 Base List IDescription UPPER CNTMT EXH ISOLATION VALVEUPPER CNTMT EXH ISOLATION VALVELOWER CNTMT EXH ISOLATION VALVELOWER CNTMT EXH ISOLATION VALVEINCORE INSTR ROOM EXH ISOLATION VALVEINCORE INSTR ROOM EXH ISOLATION VALVEREACTOR BLDG UNIT 2 TRAIN A ISOL VLVREACTOR BLDG UNIT 2 TRAIN B ISOL VLVREACTOR BLDG UNIT 2 NONESNTL CNTL AIR ISOL VLVCLYCOL FLOOR SUPPLY ISOLATION VALVEINLET ISOLATION VALVE REACTOR BLDGGLYCOL FLOOR RETURN ISOLATION VALVEOUTLET ISOLATION VALVE REACTOR BLDGGLYCOL FLOOR RETURN ISOLATION VALVGLYCOL SUPPLY ISOLATION VALVEGLYCOL AIR HANDLER RETURN ISOL VALVGLYCOL RETURN ISOLATION VALVERCP 1 SEAL INJECTION ISOLATION VALVERCP 2 SEAL INJECTION ISOLATION VALVERCP 3 SEAL INJECTION ISOLATION VALVERCP 4 SEAL INJECTION ISOLATION VALVESEAL FLOW ISOLATION VALVERCP SEAL INJECTION ISOL VALVERC LOOP 3 LETDOWN FLOWRC LOOP 3 LETDOWN FLOWREGEN HT EXCH LETDOWN ISOL VLV AREGEN HT EXCH LETDOWN ISOL VLV BREGEN HT EXCH LETDOWN ISOL VLV CLETDOWN LINE ISOL VLV FLOW CONTROLNORMAL CHARGING ISOL VALVERWST TO RHR PMP FLOW CNTL VLVSIS PUMP DISCHARGE TO RWST SHUTOFF VALVESafetyFunction5555555555555555533333,53,53,53,53,53,53,53,531,3,43,4Bl Sequoyah Unit 2UNID2-FCV-063-0004 2-FCV-063-0005 2-FCV-063-0006 2-FCV-063-0007 2-FCV-063-0008 2-FCV-063-0011 2-FCV-063-0021 2-FCV-063-0022 2-FCV-063-0023 2-FCV-063-0025 2-FCV-063-0026 2-FCV-063-0039 2-FCV-063-0040 2-FCV-063-0047 2-FCV-063-0048 2-FCV-063-0064 2-FCV-063-0067 2-FCV-063-0070 2-FCV-063-0071 2-FCV-063-0072 2-FCV-063-0073 2-FCV-063-0077 2-FCV-063-0080 2-FCV-063-0084 2-FCV-063-0090 2-FCV-063-0091 2-FCV-063-0093 2-FCV-063-0094 2-FCV-063-0095 2-FCV-063-0098 2-FCV-063-0111 2-FCV-063-0112 Base List 1Description SIS PUMP A-A DISCH TO RWST SHUTOFF VALVERWST TO SIS PUMP FLOW CONTROL VALVESIS PUMP INLET TO CVCS CHARGING PUMPSIS PUMP INLET TO CVCS CHARGING PUMPRHR HTX A T CVCS CHARGING PUMPSRHR HTX B TO SIS PUMPSSIS PUMP OUTLET TO SIS TEST LINESIS PUMPS COLD LEG INJECTION CONTROL VLVSIS ACCUM FILL LINE ISOLATION VLVSIS CCP INJ TANK SHUTOFF VALVESIS BORON INJ TANK SHUTOFF VALVESIS BORON INJ TANK INLET SHUTOFF VALVESIS BORON INJ TANK INLET SHUTOFF VALVESIS PUMP A-A INLET VLVSIS PUMP B-B INLET VLVSIS ACCUM TANK N2 HDR INLET VLVSIS ACCUMULATOR TNK 4 FLOW ISOL VALVESIS ACCUM TK4 FILL VLVSIS CHECK VLV FLOW ISOLATION VLVRHR CONTAINMENT SUMP FLOW ISOL VLVRHR CONTAINMENT SUMP FLOW ISOL VLVSIS ACCUM TK3 FILL VLVSIS ACCUMULATOR TNK 3 FLOW ISOL VALVESIS CHK VLV ISOL HDR FLOW ISOLATION VLVCHARGING FLOW ISOL VLVCHARGING FLOW ISOL VLVRHR PUMP A-A DISCHARGE TO CL 2&3RHR PUMP B-B DISCHARGE TO CL 1&4SIS ACCUM TK 2 FILL VLVSIS ACCUMULATOR TNK 2 FLOW ISOL VALVESIS CHK VLV LEAK TEST ISOLATION VLVSIS CHK VLV LEAK TEST ISOLATION VLVSafetyFunction3,41,3,43,43,43,43,453,451,3,41,3,41,3,41,3,41,3,41,3,453553,4,53,4,5535551,3,41,3,45355B12 Sequoyah Unit 2UNID2-FCV-063-0115 2-FCV-063-0118 2-FCV-063-0121 2-FCV-063-0138 2-FCV-063-0152 2-FCV-063-0153 2-FCV-063-0156 2-FCV-063-0157 2-FCV-063-0164 2-FCV-063-0172 2-FCV-063-0174 2-FCV-063-0175 2-FCV.-064-0490D 2-FCV-067-0065 2-FCV-067-0066 2-FCV-067-0067 2-FCV-067-0068 2-FCV-067-0083 2-FCV-067-0087 2-FCV-067-0088 2-FCV-067-0089 2-FCV-067-0090 2-FCV-067-0091 2-FCV-067-0095 2-FCV-067-0096 2-FCV-067-0099 2-FCV-067-0103 2-FCV-067-0104 2-FCV-067-0105 2-FCV-067-0106 2-FCV-067-0107 2-FCV-067-0111 Base List 1Description SIS ACCUM TK 1 FILL VLVSiS ACCUMULATOR TNK 1 FLOW ISOL VALVESIS FLOW TO CL CHECK VLV TESTEMERGENCY BORATION FLOW CONT VLVSIS PUMP A-A OUTLET FLOW CONTROL VALVESIS PUMP B-B OUTLET FLOW CONTROL VALVESIS PUMP OUTLET TO RCS LP 1&3 HLSIS PUMP OUTLET TO RCS LP 2&4 HLSIS PUMP OUT TEST LINERHR INJECTION OR RECIRC AFTER LOCASIS TEST LINE CHECK VLV TESTSIS PUMP B-B DISCH TO RWST SHUTOFF VLVERCW HEADER B STRAINER FLUSHOUT VALVEEMERG DSL HTXS Bl&B2 SUP VLV FROM HDR AEMERG DSL HTXS Al&A2 SUP VLV FROM HDR AEMERG DSL HTXS B1&B2 SUP VLV FROM HDR BEMERG DSL HTXS A1&A2 SUP VLV FROM HDR BLOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVELOWER CNTMT D COOLERS SUPPLY ISOL VALVESafetyFunction5353.1,3,41,3,41,3,41,3,453,453,400000555555555555555B13 Sequoyah Unit 2UNID2-FCV-067-0112 2-FCV-067-0123 2-FCV-067-0124 2-FCV-067-0125 2-FCV-067-0126 2-FCV-067-0130 2-FCV-067-0131 2-FCV-067-0133 2-FCV-067-0134 2-FCV-067-0138 2-FCV-067-0139 2-FCV-067-0141 2-FCV-067-0142 2-FCV-067-0146 2-FCV-067-0176 2-FCV-067-0182 2-FCV-067-0184 2-FCV-067-0186 2-FCV-067-0295 2-FCV-067-0296 2-FCV-067-0297 2-FCV-067-0298 2-FCV-067-0490A 2-FCV-067-0491A 2-FCV-067-0491D 2-FCV-068-0305 2-FCV-068-0307 2-FCV-068-0308 2-FCV-068-0332 2-FCV-068-0333 2-FCV-070-0066 2-FCV-070-0085 Base List 1Description LOWER CNTMT D COOLERS SUPPLY ISOL VALVECNTMT SPRAY HTX B SUPPLY CONTROL VALVECONTAINMENT SPRAY HTX B SUPPLY CONTROL VALVECNTMT SPRAY HTX A SUPPLY CONTROL VALVECONTAINMENT SPRAY HTX A DISCHARGE VALVEUPPER CNTMT VENT CLR A SUPPLY ISOL VLVUPPER CNTMT VENT CLR A DISCH LSOL VLVUPPER CNTMT VENT CLR C SUPPLY ISOL VLVUPPER CNTMT VENT CLR C DISCH ISOL VLVUPPER CNTMT VENT CLR B SUPPLY ISOL VLVUPPER CNTMT VENT CLR B DISCH ISOL VLVUPPER CNTMT VENT CLR D SUPPLY ISOL VLVUPPER CNTMT VENT CLR D SDISCH ISOL VLVCCS HTX 1A1/A12 DISCH CONTROL VLVSIS PUMP RM CLR-30-180 SUPPLY CNTL VLVSIS PUMP RM CLR-30-179 SUPPLY CNTL VLVCS PUMP RM CLR-30-177 SUPPLY CNTL VLVCS PUMP RM CLR-30-178 SUPPLY CNTL VLVUPPER CNTMT VENT CLR A DISCH ISOL VLVUPPER CNTMT VENT CLR C DISCH ISOL VLVUPPER CNTMT VENT CLR B DISCH ISOL VLVUPPER CNTMT VENT CLR D DISCH ISOL VLVERCW HEADER B STRAINER BACKWASH VALVEERCW HEADER A STRAINER BACKWASH VALVEERCW HEADER A STRAINER FLUSHOUT VALVERCS FLOW CNTL VLV WDS N2 MAAN TO PRTRCS FLOW CNTL VLV WDS GA TO PRTRCS FLOW CNTL VLV WDS GA TO PRTRCS PRESSURIZER FELIEF FLOW CTRL VALVERCS PRESSURIZER FELIEF FLOW CTRL VALVECCS SURGE TNK VENT VLVEXCESS LETON HTX OUTLET VLVSafetyFunction50000555555550000055550005552205B14 Sequoyah Unit 2UNID2-FCV-070-0087 2-FCV-070-0089 2-FCV-070-0090 2-FCV-070-0092 2-FCV-070-0133 2-FCV-070-0134 2-FCV-070-0139 2-FCV-070-0140 2-FCV-070-0141 2-FCV-070-0143 2-FCV-070-0153 2-FCV-070-0156 2-FCV-070-0168 2-FCV-070-0183 2-FCV-070-0207 2-FCV-072-0002 2-FCV-072-0020 2-FCV-072-0021 2-FCV-072-0022 2-FCV-072-0023 2-FCV-072-0039 2-FCV-072-0040 2-FCV-072-0041 2-FCV-074-O001 2-FCV-074-0002 2-FCV-074-0003 2-FCV-074-0012 2-FCV-074-0016 2-FCV-074-0021 2-FCV-074-0024 2-FCV-074-0028 2-FCV-074-0033 Base List 1Description RC PMP THERM BARRIER RET CNTNMT ISOL VLVRC PMP OIL CLR RET CNTNMT ISOL VLVRC PMP THERM BARRIER RET CNTNMT ISOL VLVRC PMP OIL CLR RET CNTNMT ISOL VLVRC PMP THERM BARRIER CONT ISOL VLVRC PMP THERM BARRIER CONT ISOL VLVRC PMP OIL CLR HDR CONT ISOL VLVRC PMP OIL CLR HDR CONT ISOL VLVRC PMP OIL CLR HDR CONT ISOL VLVEXCESS LETDOWN HTX CONT INLET ISOL VLVRHR HTX B CUTLET VALVERHR HTX A CUTLER VALVEBA GAS STPR EVAP PKG B FLOW CONT VLVSAMPLE HTX HDR OUTLET VLVCOND DEMIN WASTE EVAP BLDG SUPPLYCONTAINMENT SPRAY HDR B ISOLATION VALVECNTMT SUMP SPRAY HDR B FLOW CONTROL VLVRWST TO SPRAY HDR B FLOW CONTROL VALVERWST TO SPRAY HDR A FLOW CONTROL VALVECNTMT SUMP SPRAY HDR A FLOW CONTROL VLVCONTAINMENT SPRAY HDR A ISOLATION VALVERHR SPRAY HEADER A ISOLATION VALVERHR SPRAY HEADER B ISOLATION VALVERHR SYSTEM ISOLATION VALVERHR SYSTEM ISOLATION VALVERHR PUMP 2A-A INLET FLOW CONTROL VALVERHR PUMP 2A-A MINIMUM FLOW VALVERHR HT EX A OUTLET FLOW CONTROL VLVRHR PUMP 2B-1B INLET FLOW CONTROL VALVERHR PUMP 2B-B MINIMUM FLOW VALVERHR HT EX B OUT FLOW CONTROL VLVRHR HT EX A BYPASSSafetyFunction55555555554450555555555441,3,41,3,41,3,41,3,41,3,41,3,43,4B15 Sequoyah Unit 2UNID2-FCV-074-0035 2-FCV-077-0009 2-FCV-077-0010 2-FCV-077-0018 2-FCV-077-0019 2-FCV-077-0020 2-FCV-077-0127 2-FCV-077-0128 2-FCV-084-0012 2-FCV-090-0107 2-FCV-090-0108 2-FCV-090-0109 2-FCV-090-0110 2-FCV-090-0111 2-FCV-090-0113 2-FCV-090-0114 2-FCV-090-0115 2-FCV-090-0116 2-FCV-090-0117 2-FCV-313-0222 2-FCV-313-0223 2-FCV-313-0224 2-FCV-313-0225 2-FCV-313-0229 2-FCV-313-0230 2-FCV-313-0231 2-FCV-313-0232 2-FI-074-0012 2-FI-074-0024 2-FLT-062-0065 2-FLT-062-0096 2-FLT-062-0100 Base List 1Description RHR HT EX B BYPASSREACT COOLANT DRAIN TNK FLOW CNTL VLVREACT COOLANT DRAIN TNK FLOW CNTL VLVREACT COOLANT DRN TNK TO VENT HDR ISOL VLVREACT COOLANT DRN TNK TO VENT HDR ISOL VLVREACT COOLANT DRN TNK N2 SUPPLY FLOW CNTL VLVRAECT BLDG SUMP DISCH FLOW CNTL VLVREACT BLDG SUMP DISCH FLOW CNTL VLVPW RCS PRESS RELF TNK & RCP STANDPIPES CNTNMT BLDG LWR COMPT MON ISOL VLVCNTNMT BLDG LWR COMPT MON ISOL VLVCNTNMT BLDG LWR COMPT MON ISOL VLVCNTNMT BLDG LWR COMPT MON ISOL VLVCNTNMT BLDG LWR COMPT MON ISOL VLVCNTNMT BLDG UPR COMPT MON ISOL VLVCNTNMT BLDG UPR COMPT MON ISOL VLVCNTNMT BLDG UPR COMPT MON ISOL VLVCNTNMT BLDG UPR COMPT MON ISOL VLVCNTNMT BLDG UPR COMPT MON ISOL VLVANNULUS ISOL VLVINSTRUMENT RM ISOL VLVANNULUS ISOL VLVINSTRUMENT RM ISOL VLVANNULUS ISOL VLVINSTRUMENT RM ISOL VLVANNULUS ISOL VLVINSTRUMENT RM ISOL VLVRHR FLOW INDICATOR, TRAIN ARHR FLOW INDICATOR, TRAIN BSEAL WATER FILTERSEAL WATER INJECTION FILTERSREACTOR COOLANT FILTERSafetyFunction3,4555555555555555555505050503,43,4333B16 Sequoyah Unit 2UNID2-FSV-032-0087 2-FSV-068-0394 2-FSV-068-0395 2-FSV-068-0396 2-FSV-068-0397 2-FT-062-0001 2-FT-062-0014 2-FT-062-0027 2-FT-062-0040 2-FV-030-0046 2-GENB-082-0002A 2-GENB-082-0002B 2-HEX-062-0055 2-HEX-062-0066 2-HEX-062-0077 2-HEX-062-0090 2-HEX-070-0015A 2-HEX-070-0015B 2-HEX-072-0007 2-HEX-072-0030 2-HEX-074-0010 2-HEX-074-0015 2-HEX-074-0020 2-HEX-074-0027 2-INVB-250-QM 2-INVB-250-QP 2-INVB-250-QS 2-INVB-250-QU 2-LCV-003-0148 2-LCV-003-0156 2-LCV-003-0164 2-LCV-003-0171 Base List 1Description AUX AIR COMPR B-B COOLING WTR INLETREACTOR HEAD VENT ISOLATION VALVEREACTOR HEAD VENT ISOLATION VALVEREACTOR HEAD VENT ISOLATION VALVEREACTOR HEAD VENT ISOLATION VALVERCP NO. 1 SEAL WATER FLOWRCP NO. 2 SEAL WATER FLOWRCP NO. 3 SEAL WATER FLOWRCP NO. 4 SEAL WATER FLOWCONTAINMENT VACUUM RELIEFDIESEL GEN. 2A-ADIESEL GEN. 2B-BEXCESS LETDOWN HEAT EXCHANGER SEAL WATER HEAT EXCHANGER LETDOWN HEAT EXCHANGER REGENERATIVE HEAT EXCHANGER COMPONENT COOLING HX 2A1COMPONENT COOLING HX 2A2CONTAINMENT SPRAY HEAT EXCHANGER 2BCONTAINMENT SPRAY HEAT EXCHANGER 2ARHR PUMP 2A-A SEAL HEAT EXCHANGER RHR HEAT EXCHANGER 2ARHR PUMP 2B-B SEAL HEAT EXCHANGER RHR HEAT EXCHANGER 2B120V AC VITAL INVERTER 2-1120V AC VITAL INVERTER 2-11120V AC VITAL INVERTER 2-111120V AC VITAL INVERTER 2-VISTM GEN #3 LEVEL CONTROL VALVESTM GEN #2 LEVEL CONTROL VALVESTM GEN #1 LEVEL CONTROL VALVESTM GEN #4 LEVEL CONTROL VALVESafetyFunction544443333500033300551,3,41,3,41,3,41,3,400004,54,54,54,5B17 Sequoyah Unit 2UNID2-LCV-003-0172 2-LCV-003-0173 2-LCV-003-0174 2-LCV-003-0175 2-LCV-062-0132 2-LCV-062-0133 2-LCV-062-0135 2-LCV-062-0136 2-LCV-070-0063 2-LOCL-099-ROO1 2-LOCL-099-RO02 2-LOCL-099-RO03 2-LOCL-099-RO04 2-LOCL-099-RO05 2-LOCL-099-RO06 2-LOCL-099-RO07 2-LOCL-099-RO08 2-LOCL-099-RO09 2-LOCL-099-RO1O 2-LOCL-099-R011 2-LOCL-099-R012 2-LOCL-099-R013 2-LOCL-099-R046 2-LOCL-099-R047 2-LOCL-099-R048 2-LOCL-099-R049 2-LOCL-099-R050 2-LOCL-099-R051 2-LOCL-099-R052 2-LOCL-099-R053 2-LOCL-099-R054 2-LOCL-099-R055 Base List 1Description STM GEN #3 LEVEL CONTROL VALVESTM GEN #2 LEVEL CONTROL VALVESTM GEN #1 LEVEL CONTROL VALVESTM GEN #4 LEVEL CONTROL VALVEVCT OUTLET ISOLATION VALVE LEVEL CONTROLVCT OUTLET ISOLATION VALVE LEVEL CONTROLCHARGING PUMP FLOW -RWSTCHARGING PUMP FLOW -RWSTCCS SURGE TNK DEMIN WATER INLET VLVREACTOR PROTECTION SET 1REACTOR PROTECTION SET 1REACTOR PROTECTION SET 1REACTOR PROTECTION SET 1REACTOR PROTECTION SET 2REACTOR PROTECTION SET 2REACTOR PROTECTION SET 2REACTOR PROTECTION SET 2REACTOR PROTECTION SET 3REACTOR PROTECTION SET 3REACTOR PROTECTION SET 3REACTOR PROTECTION SET 4REACTOR PROTECTION SET 4SOLID STATE PROTECTION TRAIN ASOLID STATE PROTECTION TRAIN ASOLID STATE PROTECTION TRAIN ASOLID STATE PROTECTION TRAIN BSOLID STATE PROTECTION TRAIN BSOLID STATE PROTECTION TRAIN BTEST PANEL ATEST PANEL BNSSS AUXILIARY RELAY PANEL ANSSS AUXILIARY RELAY PANEL BSafetyFunction4,54,54,5.4,5333,53,5000000000000000000000000B18 Sequoyah Unit 2UNID2-LOCL-099-R058 2-LT-003-0038 2-LT-003-0039 2-LT-003-0042 2-LT-003-0043 2-LT-003-0051 2-LT-003-0052 2-LT-003-0055 2-LT-003-0056 2-LT-003-0093 2-LT-003-0094 2-LT-003-0097 2-LT-003-0098 2-LT-003-0106 2-LT-003-0107 2-LT-003-0110 2-LT-003-0111 2-LT-062-0129A 2-LT-062-0129C 2-LT-062-0130A 2-LT-062-0130C 2-LT-068-0320 2-LT-068-0335 2-LT-068-0339 2-PCV-001-0005 2-PCV-OO1-0012 2-PCV-001-0023 2-PCV-001-0030 2-PCV-062-0081 2-PCV-068-0334 2-PCV-068-0340A 2-PDT-030-0044 Base List 1Description NSSS AUXILIARY RELAY PANEL COMMONSTM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)STM GEN 1 LEVEL XMTR (NR)VOLUME CONTROL TANK LEVEL XMITTERVOLUME CONTROL TANK LEVEL XMITTERVOLUME CONTROL TANK LEVEL XMITTERVOLUME CONTROL TANK LEVEL XMITTERRCS PRESSURIZER LEVEL TRANSMITTER RCS PRESSURIZER LEVEL TRANSMITTER RCS PRESSURIZER LEVEL TRANSMITTER SG1 MAIN STM HDR PWR RELIEF CONTROL VLVSG2 MAIN STM HDR PWR RELIEF CONTROL VLVSG3 MAIN STM HDR PWR RELIEF CONTROL VLVSG4 MAIN STM HDR PWR RELIEF CONTROL VLVLETDOWN HEAT EXCH PRESS CONTRCS PRESSURIZER POWER RELIEF VALVERCS PRESSURIZER POWER RELIEF VALVECONTAINMENT PRESSURE TRANSMITTER SafetyFunction0444444444444444433333334,54,54,54,532,42,45B19 Sequoyah Unit 2UNID2-PDT-062-0008 2-PDT-062-0021 2-PDT-062-0034 2-PDT-062-0047 2-PMP-003-0118 2-PMP-003-0128 2-PM P-018-054/4 2-PMP-018-064/3 2-PMP-018-065/3 2-PMP-018-065/4 2-PM P-062-0104 2-PMP-062-0108 2-PMP-063-0010 2-PMP-063-0015 2-PMP-068-0008 2-PMP-068-0031 2-PM P-068-0050 2-PMP-068-0073 2-PMP-070-0033 2-PMP-070-0059 2-PMP-070-0130 2-PMP-070-0131 2-PMP-072-0010 2-PMP-072-0027 2-PMP-074-0010 2-PMP-074-0020 2-PNLA-082-TV 2-PNLA-082-TW 2-PNLB-202-SC 2-PNLB-202-SD 2-PRS-068-0320 2-PT-030-0310 Base List 1Description RCP NO 1 DP ACROSS NO 1 SEALRCP NO 2 DP ACROSS NO 1 SEALRCP NO 3 DP ACROSS NO 1 SEALRCP NO 4 DP ACROSS NO 1 SEALMOTOR DRIVEN AUX FEEDWATER PUMP 2A-AMOTOR DRIVEN AUX FEEDWATER PUMP 2B-BDSL 2B2 DAY TNK FUEL XFER PUMPDSL 2A2 DAY TNK FUEL XFER PUMPDSL 2A1 DAY TNK FUEL XFER PUMPDSL 2B1 DAY TNK FUEL XFER PUMPCENTRIFUGAL CHARGING PUMP 2B-BCENTRIFUGAL CHARGING PUMP 2A-ASIS PUMP 2A-ASIS PUMP 2B-BREACTOR COOLANT PUMP 1REACTOR COOLANT PUMP 2REACTOR COOLANT PUMP 3REACTOR COOLANT PUMP 4CCS PUMP 2B-BCCS PUMP 2A-ACCS THERMAL BARRIER BOOSTER PUMP 2B-BCCS THERMAL BARRIER BOOSTER PUMP 2A-ACONTAINMENT SPRAY PUMP 2B-BCONTAINMENT SPRAY PUMP 2A-ARHR PUMP 2A-ARHR PUMP 2B-BDG 2A-A DISTRIBUTION AND CONTROL BOARDDG 2B-B DISTRIBUTION AND CONTROL BOARD6900V LOGIC RELAY PANEL 2A6900V LOGIC RELAY PANEL 2BPRESSURIZER CONTAINMENT PRESSURE TRANSMITTER SafetyFunction3,53,53,53,5444444331,3,41,3,422220000551,3,41,3,400002,35B20 Sequoyah Unit 2UNID2-PT-030-0311 2-PT-068-0062 2-PT-068-0069 2-PT-068-0323 2-PT-068-0334 2-PT-068-0340 2-RCK-250-RCRD 2-RPV-068-0100 2-SGEN-068-0101 2-SGEN-068-0102 2-SGEN-068-0103 2-SGEN-068-0104 2-STN-067-0490 2-STN-067-0491 2-TCV-062-0079 2-TE-068-0001 2-TE-068-0024 2-TE-068-0043 2-TE-068-0065 2-TNK-018-061/3 2-TNK-018-061/4 2-TNK-018-076/3 2-TNK-018-076/4 2-TNK-062-0129 2-TNK-0623-0044 2-TNK-063-0037 2-TNK-063-0060 2-TNK-063-0081 2-TNK-063-0099 2-TN K-063-0119 2-TNK-068-0300 2-TNK-070-0063 Base List 1Description CONTAINMENT PRESSURE TRANSMITTER RCS WIDE RANGE PRESSURE LOOP 4 HOT LEGRCS WIDE RANGE PRESSURE LOOP 1 HOT LEGRCS PRESSURIZER PRESSURE TRANSMITTER RCS PRESSURIZER PRESSURE TRANSMITTER RCS PRESSURIZER PRESSURE TRANSMITTER 120V AC INST PWR TRANSFER RACK (2-M-7)REACTOR VESSELSTEAM GENERATOR 1STEAM GENERATOR 2STEAM GENERATOR 3STEAM GENERATOR 4ERCW STRAINER B2B-BERCW STRAINER A2A-ALETDOWN FLOW TEMP DIVERSION CONT VLVRCS LOOP 1 HOT LEG TEMPRCS LOOP 2 HOT LEG TEMPRCS LOOP 3 HOT LEG TEMPRCS LOOP 4 HOT LEG TEMPENGINE 2A1 DAY TANK 550 GALENGINE 2B1 DAY TANK 550 GALENGINE 2A2 DAY TANK 550 GALENGINE 2B2 DAY TANK 550 GALVOLUME CONTROL TANK LEVEL XMITTERREFUELING WATER STORAGE TANKBORON INJECTION TANK 1A (CCP INJ TNK)SIS ACCUMULATOR TANK NO 4SIS ACCUMULATOR TANK NO 3SIS ACCUMULATOR TANK NO 2SIS ACCUMULATOR TANK NO 1PRESSURIZER RELIEF TANKCOMPONENT COOLING WATER SURGE TANKSafetyFunction52,42,42220222220032,42,42,42,4444431,3,41,3,41,31,31,31,32,40B21 Sequoyah Unit 2Base List IUNID2-TNK-082-0224 2-TNK-082-0225 2-TNK-082-0234 2-TNK-082-0235 2-TNK-082-0254 2-TNK-082-0255 2-TNK-082-0264 2-TNK-082-0265 2-VLV-001-0512/0531 2-VLV-001-0513 2-VLV-001-0514 2-VLV-001-0515 2-VLV-001-0516 2-VLV-001-0517 2-VLV-001-0518 2-VLV-001-0519 2-VLV-001-0520 2-VLV-001-0521 2-VLV-001-0522 2-VLV-001-0523 2-VLV-001-0524 2-VLV-001-0525 2-VLV-001-0526 2-VLV-001-0527 2-VLV-001-0528 2-VLV-001-0529 2-VLV-001-0530 2-VLV-001-0539 2-XCT-250-QC2A 2-XCT-250-QC2B 2-XFA-202-0312 2-XFA-202-0313 Description DSL 2A1 STARTING AIR TANK A 35 CFDSL 2A2 STARTING AIT TANK A 35 CFDSL 2A1 STARTING AIT TANK B 35 CFDSL 2A2 STARTING AIR TANK B 35 CFDSL 2B1 STARTING AIR TANK A 35 CFDSL 2B2 STARTING AIR TANK A 35 CFDSL 2B1 STARTING AIR TANK B 35 CFDSL 2B2 STARTING AIR TANK B 35 CFMAIN STEAM SAFETY VALVES, SG-3MAIN STEAM SAFETY VALVES, SG-3MAIN STEAM SAFETY VALVES, SG-3MAIN STEAM SAFETY VALVES, SG-3MAIN STEAM SAFETY VALVES, SG-3MAIN STEAM SAFETY VALVES, SG-2MAIN STEAM SAFETY VALVES, SG-2MAIN STEAM SAFETY VALVES, SG-2MAIN STEAM SAFETY VALVES, SG-2MAIN STEAM SAFETY VALVES, SG-2MAIN STEAM SAFETY VALVES, SG-1MAIN STEAM SAFETY VALVES, SG-1MAIN STEAM SAFETY VALVES, SG-1MAIN STEAM SAFETY VALVES, SG-1MAIN STEAM SAFETY VALVES, SG-1MAIN STEAM SAFETY VALVES, SG-4MAIN STEAM SAFETY VALVES, SG-4MAIN STEAM SAFETY VALVES, SG-4MAIN STEAM SAFETY VALVES, SG-4CCS SURGE TNK VACUUM RELIEF480/240 -120V AC INST PNL TRANFRMR 2A480/240 -120V AC INST PWR TRANSFRMR 2BERCW TRANSFORMER 2A-A480V SHUTDOWN TRANSFORMER 2A2-ASafetyFunction00000000444444444444444444400000B22 Sequoyah Unit 2UNID2-XFA-202-0314 2-XFA-202-0315 2-XFA-202-0316 2-XFA-202-0317 2-XFA-202-0318 2-XFA-202-0319 Base List 1Description 480V SHUTDOWN TRANSFORMER 2A-A480V SHUTDOWN TRANSFORMER 2A1-AERCW TRANSFORMER 2B-B480V SHUTDOWN TRANSFORMER 2B2-B480V SHUTDOWN TRANSFORMER 2B-B480V SHUTDOWN TRANSFORMER 2B1-BSafetyFunction000000B23 Appendix C: Base List 2This Appendix includes the Sequoyah Unit 2 Base List 2.Cl Sequoyah Unit 2Base List 2UNIDSQN-O-BCTB-078-0009-B SQN-O-BCTB-078-0012-A SQN-O-BCTB-078-0035-A SQN-0-BCTB-078-0035-B SQN-O-BCTC-078-O001 SQN-0-BCTD-078-0019-A SQN-O-BCTD-078-0020-B SQN-O-H EX-078-0017 SQN-0-HEX-078-0018 SQN-O-ISIV-078-0204C SQN-O-ISIV-078-0206C SQN-0-ISIV-078-0209B SQN-0-1SIV-078-0210B SQN-0-ISIV-078-0211C SQN-0-ISIV-078-0212C SQN-O-ISIV-078-0213C SQN-0-ISIV-078-0214C SQN-0-ISIV-078-0230B SQN-O-ISIV-078-0231B SQN-O-ISIV-078-0232B SQN-O-ISIV-078-0233B SQN-O-MTRB-078-0001 SQN-O-MTRB-078-0009-B SQN-O-MTRB-078-0012-A SQN-O-MTRB-078-0019-A SQN-0-MTRB-078-0020-B SQN-O-MTRB-078-0035-S SQN-O-PMP-078-0001 SQN-0-PMP-078-0009-B SQN-0-PMP-078-0012-A SQN-O-PMP-078-0019 SQN-O-PMP-078-0020 SQN-O-PMP-078-0035-S SQN-O-PMP-07S-0042 SQN-O-TA-078-0004A SQN-O-TE-078-0004 SQN-O-TI-078-0005 SQN-O-TI-078-0006 SQN-O-TI-078-0017 SQN-O-TI-078-0018 SQN-0-TIS-078-0004 SQN-0-TW-078-0005 SQN-O-TW-078-0006 Description SPENT FUEL PIT PUMP B-B 45N779-4SPENT FUEL PIT PUMP A-A 45N779-4SPENT FUEL PIT BACK-UP PUMP C-S (NORMAL SUP)SPENT FUEL PIT BACK-UP PUMP C-S (ALT SUP)SPENT FUEL PIT SKIMMER PUMPREFUELING WATER PURIFICATION PUMP AREFUELING WATER PURIFICATION PUMP BSPENT FUEL PIT HEAT EXCHANGER BSPENT FUEL PIT HEAT EXCHANGER APNL ISOL VLV TO PI-78-10PNL ISOL VLV TO PI-78-13HIGH SIDE PANEL ISOLATION VALVE FOR FI-78-16LOW SIDE PANEL ISOLATION VALVE FOR FI-78-16PNL ISOL VLV FOR O-PI-78-21 PNL ISOL VLV FOR O-PI-78-22 PNL ISOL VLV FOR 0-PI-78-23 PNL ISOL VLV FOR O-PI-78-24 HIGH SIDE ISOLATION VALVE FOR 0-FI-078-0039 LOWSIDE ISOLATION VALVE FOR 0-FI-078-0039 HIGH SIDE ISOLATION VALVE FOR 0-FI-078-0040 LOW SIDE ISOLATION VALVE FOR 0-FI-078-0040 SPENT FUEL PIT SKIMMER PUMPSPENT FUEL PIT PUMP B-B 45N779-4SPENT FUEL PIT PUMP A-A 45N779-4REFUELING WATER PURIFICATION PUMP A MOTORREFUELING WATER PURIFICATION PUMP MOTOR BSPENT FUEL PIT C-S (NOR & ALT PWR SUPPLY)SPENT FUEL PIT SKIMMER PUMPSPENT FUEL PIT.PUMP BSPENT FUEL PIT PUMP AREF WTR PUR PUMP A-AREF WTR PUR PUMP B-BSFP COOLING BACK-UP PUMP C-SSGLWHT TRANSFER PUMP TO TRANSFER CANAL OR SFPSPENT FUEL PIT WATER TEMP HISPENT FUEL PIT WATER TEMPSFPCS HT EX A INLET TEMPSFPCS HT EX B INLET TEMPSFPCS HT EX B OUTLET TEMPSFPCS HT EX A OUTLET TEMPSPENT FUEL PIT WATER TEMP HISFPCS HT EX A INLET TEMPSFPCS HT EX B INLET TEMPC2 Sequoyah Unit 2Base List 2UNIDSQN-0-TW-078-0017 SQN-0-TW-078-0018 SQN-0-VLV-078-0201A SQN-0-VLV-078-0202A SQN-0-VLV-078-0203A SQN-0-VLV-078-0204A SQN-0-VLV-078-0205A SQN-0-VLV-078-0206A SQN-0-VLV-078-0207A SQN-0-VLV-078-0208A SQN-0-VLV-078-0209A SQN-0-VLV-078-0210A SQN-0-VLV-078-0211A SQN-0-VLV-078-0211B SQN-0-VLV-078-0212A SQN-0-VLV-078-0212B SQN-0-VLV-078-0213A SQN-0-VLV-078-0213B SQN-0-VLV-078-0214A SQN-0-VLV-078-0214B SQN-0-VLV-078-0215A SQN-0-VLV-078-0216A SQN-0-VLV-078-0217A SQN-0-VLV-078-0218A SQN-0-VLV-078-0219A SQN-0-VLV-078-0220A SQN-0-VLV-078-0221A SQN-0-VLV-078-0222A SQN-0-VLV-078-0223A SQN-0-VLV-078-0224A SQN-0-VLV-078-0230A SQN-0-VLV-078-0231A SQN-0-VLV-078-0232A SQN-0-VLV-078-0233A SQN-0-VLV-078-0501 SQN-0-VLV-078-0502 SQN-0-VLV-078-0503 SQN-0-VLV-078-0504 SQN-O-VLV-078-0505 SQN-0-VLV-078-0506 SQN-0-VLV-078-0507 SQN-0-VLV-078-0508 SQN-0-VLV-078-0509 Description SFPCS HT EX B OUTLET TEMPSFPCS HT EX A OUTLET TEMPRT VLV TO PI-78-2RT VLV TO PI-78-7RT VLV TO PI-78-8RT VLV TO PI 10RT VLV TO PI-78-11RT VLV TO PI-78-13RT VLV TO PI-78-14RT VLV TO P1-78-15RT VLV TO FI-78-16RT VLV TO FI-78-16RT VLV TO PI-78-21VENT VALVE FOR 0-PI-78-21 RT VLV TO PI-78-22VENT VALVE FOR 0-PI-78-22 RT VLV TO PI-78-23VENT VALVE FOR 0-PI-78-23 RT VLV TO PI-78-24VENT VALVE FOR 0-PI-78-24 RT VLV TO PI-78-25RT VLV TO PI-78-26RT VLV TO PI-78-27RT VLV TO PI-78-29RT VLV TO PDI-78-30 RT VLV TO PDI-78-30 SF PMP A-A PRESS TESTSF PMP B-B PRESS TESTRT VLV TO PI-78-37RT VLV TO PI-78-38RT VLV TO FI-78-39RT VLV TO FI-78-39RT VLV TO FI-78-40RT VLV TO FI-78-40SFP PUMP A-A SUCTIONSFP PUMP B-B SUCTIONSFP PUMP A-A SYS DRSFP PUMP B-B SYS DRSFP PUMP A-A CAS DRSFP PUMP B-B CAS DRSFP PUMP A-A CAS VTSFP PUMP B-B CAS VTSFP PUMP A-A CHECKC3 Sequoyah Unit 2Base List2UNIDSQN-O-VLV-078-0510 SQN-O-VLV-078-0511 SQN-0-VLV-078-0512 SQN-O-VLV-078-0513 SQN-O-VLV-078-0514 SQN-O-VLV-078-0515 SQN-O-VLV-078-0516 SQN-O-VLV-078-0517 SQN-0-VLV-078-0518 SQN-O-VLV-078-0519 SQN-O-VLV-078-0521 SQN-O-VLV-078-0522 SQN-0-VLV-078-0523 SQN-O-VLV-078-0524 SQN-O-VLV-078-0525 SQN-O-VLV-078-0526 SQN-O-VLV-078-0527 SQN-0-VLV-078-0528 SQN-O-VLV-078-0529 SQN-O-VLV-078-0530 SQN-O-VLV-078-0531 SQN-O-VLV-078-0532 SQN-O-VLV-078-0533 SQN-O-VLV-078-0534 SQN-O-VLV-078-0535 SQN-0-VLV-078-0536 SQN-O-VLV-078-0537 SQN-O-VLV-078-0538 SQN-O-VLV-078-0539 SQN-0-VLV-078-0540 SQN-0-VLV-078-0541 SQN-O-VLV-078-0542 SQN-0-VLV-078-0543 SQN-0-VLV-078-0544 SQN-O-VLV-078-0545 SQN-0-VLV-078-0546 SQN-O-VLV-078-0547 SQN-O-VLV-078-0548 SQN-O-VLV-078-0549 SQN-O-VLV-078-0550 SQN-O-VLV-078-0551 SQN-O-VLV-078-0552 SQN-O-VLV-078-0553 Description SFP PUMP B-B CHECKHX A DISCHHX B DISCHCOOL LOOP SOVDEM WATER MAKE-UP SOVFROM SFP FILTER SOVCOOL LP CASK LOAD SOVSOV TO SFP FILTERSOV TO SFP FILTERSFP PUMP DISCH TO HUTSFP SOV TO SFP FILTERPRIMARY WATER-SFP SOVDEM SOV TO SFP FILTERSFP FILTER ISOL-INLET SFP FILTER ISOL-DISCH SFP SOV TO DEMSFP DEM INLET CHECK VLVFROM RESIN TK SOVSFP DEM VENTTO WDS SRST SOVSFP DEM DRDEM SOV FROM RWPPDEM SOV TO RWPFDEM CHECK TO RWPFRWPP TO RWPF SOVRWPF B ISOL-INLET RWPF A ISOL-INLET RWPF B VENTRWPF A VENTRWPF B DRRWPF A DRRWPF B ISOL-DISCH RWPF A ISOL-DISCH RWPF TO CVCS HLDUP TKSAMPLING CONN VALVETO REF CAVITY CHECKTO TRAN CANAL SOVSAMPLING CONN VALVERWPP B ISOL-DISCH RWPP A ISOL-DISCH RWPP B CHECKRWPP A CHECKRWPP B CASING DRC-4 Sequoyah Unit 2UNIDSQN-O-VLV-078-0554 SQN-O-VLV-078-0555 SQN-O-VLV-078-0556 SQN-O-VLV-078-0563 SQN-O-VLV-078-0564 SQN-0-VLV-078-0565 SQN-O-VLV-078-0568 SQN-0-VLV-078-0569 SQN-0-VLV-078-0570 SQN-O-VLV-078-0571 SQN-O-VLV-078-0572 SQN-O-VLV-078-0573 SO.N-0-VLV-078-0574 SQN-0-VLV-078-0575 SQN-0-VLV-078-0576 SQN-0-VLV-078-0577 SQN-O-VLV-078-0578 SQN-0-VLV-078-0579 SQN-O-VLV-078-0581 SQN-O-VLV-078-0582 SQN-0-VLV-078-0583 SQN-0-VLV-078-0584 SQN-O-VLV-078-0585 SQN-O-VLV-078-0586 SQN-0-VLV-078-0587 SQN-0-VLV-078-0588 SQN-0-VLV-078-0589 SQN-0-VLV-078-0590 SQN-O-VLV-078-0591 SQN-O-VLV-078-0592 SQN-0-VLV-078-0593 SQN-0-VLV-078-0594 SQN-O-VLV-078-0595 SQN-O-VLV-078-0596 SQN-0-VLV-078-0597 SQN-0-VLV-078-0598 SQN-O-VLV-078-0599 SQN-O-VLV-078-0606 SQN-O-VLV-078-0607 SQN-O-VLV-078-0608' SQN-O-VLV-078-0611 SQN-O-VLV-078-0612 SQN-0-VLV-078-0613 Base List 2Description RWPP A CASING DRRWPP B SUCTION SOVRWPP A SUCTION SOVFROM TRAN CANAL CHECKFROM TRAN CANAN SOVFROM TRAN CANAL VENTFROM CVCS REC PUM SOVSFP SKIM SOVSUCT CLEAN SOVSFP SKIM STR VENTSFP SKIM STR DRSFP SKIM PUMP DRSFP SKIM FILTER ISOLSFP SKIM FILTER VENTSFP SKIM FILTER DRSFP SKIM FILTER ISOLSFP FILTER VENTSFP FILTER DRSFP PUMP C-S SUCT ASFP PUMP C-S SUCT BSFP PUMP C-S CAS VTSFP PUMP C-S SYS DRSFP PUMP C-S CAS DRSFP PUMP C-S CKSFP PUMP C-S TO TR BSFP PUMP C-S TO TR ACOOLING LOOP A LP DRCOOLING LOOP B LP DRFLOOD MODE LOOP VENTRWP FILTER PIPING DRRWP FILTER PIPING DRSFP FILTER PIPING DRHX A OUTLET DRHX B OUTLET DRHX OUTLET PIPING DRRWP PUMPS DISCH ISORWP PUMP DISCH ISOLVLVHUT TO REFUEL CANAL ISOLHUT TO REFUEL CANAL TELL-TALE DRAINHUT TO REFUEL CANAL TELL-TALE VENTSG LAYUP WATER HOLDUP TK RECIRC ISO VLVSGLWHT TRANSFER PIPING DR VLVSGLWHT RECIR DR & SAMPLE VLVC5 Sequoyah Unit 2Base List 2UNIDSQN-0-VLV-078-0614 SQN-0-VLV-078-0615 SQN-0-VLV-078-06i6 SQN-0-VLV-078-0617 SQN-0-VLV-078-0618 SQN-0-VLV-078-606 SQN-0-XFA-078-0019-A SQN-O-XFA-078-0020-B SQN-0-XS-078-0036A-S SQN-O-XS-078-0036B-S SQN-O-XSW-078-0035-S SON-1-VLV-078-0225A SQN-1-VLV-078-0226A SQN-1-VLV-078-0227A SQN-1-VLV-078-0228A SQN-1-VLV-078-0229A SQN-1-VLV-078-0557 SQN-1-VLV-078-0558 SQN-1-VLV-078-0559 SQN-1-VLV-078-0560 SQN-1-VLV-078-0561 SQN-1-VLV-078-0562 SQN-1-VLV-078-0566 SQN-1-VLV-078-0567 SQN-1-VLV-078-0600 SQN-1-VLV-078-0601 SQN-1-VLV-078-0602 SQN-1-VLV-078-0610 SQN-2-VLV-078-0225A SQN-2-VLV-078-0226A SQN-2-VLV-078-0227A SQN-2-VLV-078-0228A SQN-2-VLV-078-0229A SQN-2-VLV-078-0557 SQN-2-VLV-078-0558 SQN-2-VLV-078-0559 SQN-2-VLV-078-0560 SQN-2-VLV-078-0561 SQN-2-VLV-078-0562 SQN-2-VLV-078-0566 SQN-2-VLV-078-0567 SQN-2-VLV-078-0600 SQN-2-VLV-078-0601 Description SLGWHT TRANSFER PIPING DR VLVSGLWHT TRANSFER PIPING ISO VLVSGLWHT TRANSFER PIPING CHK VLVSGLWHT TRANSFER PIPING ISO VLVSGLWHT TRANSFER PIPING ISO VLVBLOCK VALVE HUT TO SFP TRANSFER CANALTRANSFORMER TRANSFORMER SFPCS BACK-UP PUMP C-S POWER TRANSFER SWSFPCS BACK-UP PUMP C-S POWER TRANSFER SW.SFP COOLING BACK-UP PUMP C-S XFR SWREF CAV ISO TEST CONNREF CAV ISO TEST CONNWDS ISO TEST CONNWDS ISO TEST CONNWDS ISO TEST CONNREF CAVITY ISOLREF CAVITY ISOLREF CAVITY ISOLREF CAVITY ISOLREF CAVITY ISOLFROM REF CAVITY CHECKFROM SIS RWST CHECKTO CSS RWST SOVREFUEL CAV SUPPLY BLOCKCONT ISO VENTCONT ISOL TEST CONNFUEL TRANSFER TUBE WAFER VALVEREF CAV ISO TEST CONNREF CAV ISO TEST CONNWDS ISO TEST CONNWDS ISO TEST CONNWDS ISO TEST CONNREF CAVITY ISOLREF CAVITY ISOLREF CAVITY ISOLREF CAVITY ISOLREF CAVITY ISOLFROM REF CAVITY CHECKFROM SIS RWST CHECKTO CSS RWST SOVREFUEL CAV SUPPLY BLOCKCONT ISO VENTC6 Sequoyah Unit 2UNIDSQN-2-VLV-078-0602 SQN-2-VLV-078-0610 SQN-2-ZS-078-0041A SQN-2-ZS-078-0041B Base List 2Description CONT ISO TEST CONNFUEL TRANSFER TUBE WAFER VALVEREF CNL VORTEX SUPP ZONE SWREF CNL VORTEX SUPP ZONE SW07 Appendix D: SWELs and Area ListThis Appendix includes the Sequoyah Unit 2 SWELs and Area List.DI Sequoyah Unit 2 Seismic Walkdown Equipment Ust ICreated Bjf: Approved BY: 1Risk New or 5 Safety Enhanced Area Anchorage Item # Class UNID Description System Building Elevation Significant Replaced Functions for IPEEE Walkby Verification 1 0 0-DRYA-032-0002-B Aux Control Air Dryer B-B 032 AUXILIARY 734 (RCA) 0 322 1 2-BDC-201-FL-A 480V ERCW MCC 2A-A 201 ERCW 704 0 83 1 2-BDC-201-FN-B 480V ERCW MCC 2B-B 201 ERCW 704 0 114 1 2-BDC-201-FQ-A 480V DIESEL AUXIUARY BOARD 2A1-A 201 DIESEL GEN. 740 0 Y 2 V5 1 2-BDC-201-FU-B 480V DIESEL AUXILIARY BOARD 2B1-B 201 DIESEL GEN. 740 0 Y S6 1 2-BDC-201-GM-A 480V REACTOR MOV BD 2A2-A 201 AUXILIARY 749 Y 0 Y 237 1 2-BDC-201-GN-B 480V REACTOR MOV BD 2B1-B 201 AUXILIARY 749 Y 0 Y 228 1 2-BDC-201-JK-A 480V CONT & AUX BLDG VENT BD 2A2-A 201 AUXIUARY 734 0 Y 159 2 2-BDB-201-DO-A 480V SHUTDOWN BD 2A2-A 201 AUXILIARY 734 Y 0 Y 1s10 2 2-BDB-201-DP-B 480V SHUTDOWN BD 2B1-B 201 AUXILIARY 734 Y 0 Y 16]. 2 2-BDB-201-DQ-B 480V SHUTDOWN BD 2B2-B 201 AUXILIARY 734 Y 0 Y 1712 3 2-BDA-202-CO-A 6900V SHUTDOWN BOARD 2A-A 202 AUXIUARY 734 0 Y 3113 3 2-BDB-202-CP-B 6900V SHUTDOWN BOARD 2B-B 202 AUXIUARY 734 0 Y 3614 4 2-OXF-202-2A-A 480V SHUTDOWN TRANSFORMER 2A1-A 202 AUXILIARY 749 3 Y 19 Y15 4 2-OXF-202-2B-B SD XFMR 2B-B 202 AUXILIARY 749 3 Y 18 Y16 4 2-OXF-202-DN-A 480V SHUTDOWN TRANSFORMER 2A-A 202 AUXILIARY 749 Y 3 Y 19 Y17 4 2-OXF-202-DQ-B SD XFMR 2B2-B 202 AUXILIARY 749 Y 1 3 Y 18 Y18 4 2-XFA-202-0312 ERCW TRANSFORMER 2A-A 202 ERCW 704 0 8 Y19 4 2-XFA-202-0316 ERCW TRANSFORMER 2B-B 202 ERCW 704 0 11 Y20 See SWEL 2 for Item 20.21 5 2-PMP-003-0128 MOTOR DRIVEN AUX FEEDWATER PUMP 2B-B 003 AUXILIARY 690 Y 2,4 38 Y22 S 2-PMP-062-0104 CENT. CHARGING PUMP 2B-B 062 AUXIUARY 669 3 35 Y23 5 2-PMP-063-0010 SAFETY INJECTION PUMP 2A-A 063 AUXILIARY 669 1,3,4 26 Y24 5 2-PMP-070-00s9-A CCS PUMP 2A-A 070 AUXILIARY 690 Y 0 27 Y25 6 O-PMP-067-0452 ERCW PUMP N-B 067 ERCW 720 0 10 Y26 6 O-PMP-067-0464 ERCW PUMP R-A 067 ERCW 720 0 7 Y27 6 O-PMP-067-0482-B ERCW SCREEN WASH PUMP C-B 067 ERCW 720 0 10 Y28 6 0-PMP-067-0487-A ERCW SCREEN WASH PUMP D-A 067 ERCW 720 0 7 Y29 7 0-FCV-032-0085-B AUX COMPR B-B AUX BLDG ISOL 032 AUXILIARY 734 (RCA) 0 3230 7 2-FCV-067-0176-A S.I. PUMP AND RM CLR-30-180 SUPPLY 067 AUXIUARY 669 0 4331 7 2-FCV-067-0182-B S.I. PUMP AND RM CLR-30-179 SUPPLY 067 AUXIUARY 669 0 4332 7 2-FCV-067-0190-B RHR PUMP RM CLR-30-176 SUPPLY CONTROL VLV 067 AUXILIARY 653 0 2533 7 2-FCV-067-188 RHR PUMP RM CLR-30-175 SUPPLY CONTROL VLV 067 AUXILIARY 653 0 2534 7 2-LCV-070-0063 SURGE TANK DEMIN W INLET VLV 070 AUXILIARY 734 (RCA) 0 3235 8 0-FCV-070-0040-B SFPCS HTX A INLET FCV 0-FCV-70-40 070 AUXILIARY 714 4 2936 8 2-FCV-003-0126A-B ERCW HDR B ISOL VLV 003 AUXILIARY 690 4 3837 8 2-FCV-067-0066 EMERG DSL HTXS A1&A2 SUP VLV FROM HDR A 067 DIESEL GEN. 722 0 138 8 2-FCV-067-0067 EMERG DSL HTXS B1&B2 SUP VLV FROM HDR A 067 DIESEL GEN. 722 0 439 8 2-FCV-067-0068 EMERG DSL HTXS A1&A2 SUP VLV FROM HDR B 067 DIESEL GEN. 722 0 140 8 2-FCV-067-0492 ISOL VALVE 067 ERCW 688 0 941 9 2-FAN-030-0450-B D-G RM 2B-B EXHAUST FAN 1 030 DIESEL GEN. 740 5 6 1Safety Function(s):

0 -Support Function1 -Reactivity Control2 -RCS Pressure Control3 -RCS Inventory Control4 -Decay Heat Removal5 -Containment Isolation D2 Risk New or 5 Safety Enhanced Area Anchorage Item # Class UNID Description System Building Elevation Significant Replaced Functions forIPEEE Walkby Verification 42 9 2-FAN-030-0452 D-G RM 2A-A EXHAUST FAN 2 030 DIESEL GEN. 740 5 3 Y43 9 2-FAN-030-0460 DIESEL GEN 2A-A ELECT BD ROOM EXHAUST 030 DIESEL GEN. 740 5 3 Y44 9 2-FAN-030-0462-B DIESEL GEN 2B-B ELECT BD ROOM EXHAUST 030 DIESEL GEN. 740 Y 5 6 Y45 10 0-AHU-311-0023-B MAIN CONTROL ROOM AHU B-B 311 CONTROL 732 V 0 V 1246 10 2-AHU-313-0488 480V BD RM 2A SUPPLY AHU 2A-A 313 AUXILIARY 749 0 2447 10 2-CLR-030-0178 CONTAINMENT SPRAY PUMP COOLER 2B-B 030 AUXILIARY 653 5 4448 10 2-CLR-030-180-A SIS PUMP COOLER 2A-A 030 AUXILIARY 669 5 2649 11 0-CHR-311-0126 MAIN CONTROL ROOM CHILLER PKG A-A 311 CONTROL 732 0 12 Y50 11 0-CHR-311-0171 ELEC. BD. ROOM CHILLER PKG. B-B 311 CONTROL 669 0 37 Y51 11 0-CHR-313-0338A SHUTDOWN BD RMS A & B WATER CHILLER PKG B-B 313 AUXILIARY 714 0 4052 11 2-CHR-313-0483 480V ELECT BOARD RM 2A-A 313 AUXILIARY 749 0 2453 12 0-CMP-032-0086-B AUX CONTROL AIR COMPRESSOR B-B 032 AUXILIARY 734 (RCA) Y 0 3254 12 2-CMP-082-0240 DSL 2A1 STARTING AIR COMPRESSER 25.5 CFM 082 DIESEL GEN. 722 0 1 Y55 12 2-CMP-082-0241 DSL 2A2 STARTING AIR COMPRESSOR 25.5 CFM 082 DIESEL GEN. 722 0 1 Y56 12 2-CMP-082-0271 DSL 2B2 STARTING AIR COMPRESSER 25.5 CFM 082 DIESEL GEN. 722 0 4 Y57 13 2-GEND-085-DG 4D,CONTROL ROD DRIVE GENERATOR 2A 085 AUXILIARY 759 0 30 Y58 13 2-GEND-085-DH 3B,CONTROL ROD DRIVE GENERATOR 2B 085 AUXILIARY 759 0 30 Y59 14 0-XSW-250-KL-S SPARE 480 V AC VITAL TRANSFER SW 2-S 250 AUXILIARY 749 0 22 Y60 14 0-XSW-250-KX-S 125VDC CHGR 2-S DC XFER SW TO VBB III 250 AUXILIARY 749 0 22 Y61 14 2-BDE-250-NF-E 120V AC VITAL INSTR POWER BD 2-11 250 AUXILIARY 734 Y 0 1462 14 2-BDE-250-NK-G 120V AC VITAL INSTR POWER BD 2-IV 250 AUXILIARY 734 Y 0 4563 14 2-PNLA-082-TV-A DG 2A-A 125 VOLT DC DISTRIBUTION PNL 082 DIESEL GEN. 722 0 164 14 2-XSW-082-UH-A DG 2A-A 480VTRANSFER SWITCH 082 DIESEL GEN. 722 0 165 15 0-BATB-250-OX-F 125V Vital Battery Room III Batteries 1-20 Rack 250 AUXILIARY 749 0 20 Y66 15 O-BATB-250-OX-F 125V Vital Battery Room III Batteries 21-40 Rack 250 AUXILIARY 749 0 20 Y67 15 O-BATB-250-QX-F 125V Vital Battery Room III Batteries 41-60 Rack 250 AUXILIARY 749 0 20 Y68 15 0-BATB-250-QY-G 125V Vital Battery Room IV Batteries 1-20 Rack 250 AUXILIARY 749 0 21 Y69 15 0-BATB-250-QY-G 125V Vital Battery Room IV Batteries 21-40 Rack 250 AUXILIARY 749 0 21 Y70 15 O-BATB-250-QY-G 125V Vital Battery Room IV Batteries 41-60 Rack 250 AUXILIARY 749 0 21 Y71 15 2'BATB-082-UD-A Diesel Gen. 2A-A Battery Rack 082 DIESEL GEN. 722 0 1 Y72 16 O-CHGB-250-OJ-G 125V DC VITAL BATTERY CHARGER IV 250 AUXILIARY 749 Y 0 Y 2273 16 0-CHGB-250-QK-S 125V DC VITAL BATTERY CHARGER 2-SPARE 250 AUXILIARY 749 0 Y 22 Y74 16 2-CHGB-082-TZ-A DG 2A-A BATTERY CHARGER 082 DIESEL GEN. 722 0 175 16 2-CHGB-082-UA-B D/G 2B-B BATTERY CHGR 082 DIESEL GEN. 722 0 476 16 2-INVB-250-QU-G 120V AC VITAL INVERTER 2-IV 250 AUXILIARY 749 V Y 0 Y 22 Y77 17 2-ENG-082-0002A1 ENG 2A1 082 DIESEL GEN. 722 0 1 Y78 17 2-ENG-082-0002A2 ENG 2A2 082 DIESEL GEN. 722 0 1 Y79 17 2-ENG-082-0002B1 DIESEL ENGINE 2B1 082 DIESEL GEN. 722 0 4 Y80 17 2-ENG-082-0002B2 DIESEL ENGINE 2B2 082 DIESEL GEN. 722 0 4 Y81 17 2-GENB-082-002A DIESELrGEN.

2A-A 082 DIESEL GEN. 722 0 1 Y82 17 2-GENB-082-0002B DIESEL GEN. 2B-B 082 DIESEL GEN. 722 0 4 Y83 18 0-LOCL-500-0428 FLOOR PANEL AUXILIARY BUILDING 500 AUXILIARY 734 (RCA) 0 0 3284 18 2-LOCL-500-0005 FLOOR PANEL AUXILIARY BUILDING 500 AUXILIARY 653 0 25Safety Function(s):

0 -Support Function1 -Reactivity Control2 -RCS Pressure Control3 -RCS Inventory Control4 -Decay Heat Removal5 -Containment Isolation D3 Risk New or 5 Safety Enhanced Area Anchorage Item # Class UNID Description System Building Elevation Significant Replaced Functions forIPEEE Walkby Verification 85 18 2-LOCL-500-0019 FLOOR PANEL AUXILIARY BUILDING 500 AUXILIARY 734 (RCA) 0 3286 18 2-LOCL-500-0048 FLOOR PANEL AUXILIARY BUILDING 500 AUXILIARY 690 0 2787 18 2-LOCL-500-0163 FLOOR PANEL DGB 500 DIESEL GEN. 722 0 488 18 2-LOCL-500-0222B FLOOR PANEL AUXILIARY BUILDING 500 AUXILIARY 690 0 3889 19 2-TE-300-045OA-B DIESEL GEN 2B-B EXHAUST-HIGH TEMP 300 DIESEL GEN. 740 2,4 690 19 2-TE-300-0450B-B DIESEL GEN 2B-B EXHAUST-LOW TEMP 300 DIESEL GEN. 740 2,4 691 19 2-TE-300-0452A-A DIESEL GEN 2A-A EXHAUST-HIGH TEMP 300 DIESEL GEN. 740 2,4 392 19 2-TE-300-0452B-A DIESEL GEN 2A-A EXHAUST-LOWTEMP 300 DIESEL GEN. 740 2,4 393 19 2-TS-001-0018A-B STM FLOW TO AFPT ISOL -HIGH TEMP 001 AUXILIARY 669 0 3494 19 2-TS-001-0018B-B STM FLOW TO AFPT ISOL -HIGH TEMP 001 AUXILIARY 669 0 3495 20 O-LOCL-500-MO26D DIESEL GEN CONT 500 CONTROL 732 0 13 Y96 20 2-LOCL-500-M002 TURB CONTROL 500 CONTROL 732 0 13 Y97 20 2-LOCL-500-M004 Reactor Control Panel 2-M-4 500 CONTROL 732 0 13 Y98 20 2-LOCL-500-M008 TURB SUP CONT 500 CONTROL 732 0 1399 20 2-LOCL-500-M009 VENT-ICE CONT-REACT BD 500 CONTROL 732 0 13 Y100 20 2-PNLA-082-TV

/3-A DG 2A-A CONTROL PNL 082 DIESEL GEN. 722 0 1101 See SWEL 2 for Item 101.102 21 2-HEX-072-0007 CNTMT SPRAY HT EXCH 2B 072 AUXILIARY 690 5 39 Y103 21 2-HEX-072-0030 CONTAINMENT SPRAY HEAT EXCHANGER 2A 072 AUXILIARY 690 5 42 Y104 21 2-HEX-074-0015 RESIDUAL HEAT EXCHANGER 2A 074 AUXILIARY 690 Y 1,3,4 Y 42 Y105 21 2-HEX-074-0027 RESIDUAL HEAT EXCHANGER 2B 074 AUXILIARY 690 Y 1,3,4 Y 39 Y106 21 2-TNK-070-0063 CCS SURGE TANK B 070 AUXILIARY 734 (RCA) Y "0 32 Y107 21 2-TNK-082-0224 DSL 2A1 STARTING AIR TANK A 35 CF 082 DIESEL GEN. 722 0 _1 Y108 21 2-TNK-082-0255 DSL 2B2 STARTING AIR TANK A 35 CF 082 DIESEL GEN. 722 0 4 Y109 7 2-FCV-063-0090 SIS ACCUM TK 3 FLOW ISOLATION VLV 063 REACTOR 693 5 46110 8 2-PSV-001-0013B-B SG 2 MAIN STM HDR PRESS 001 REACTOR 747 2,3 501i1 8 2-PSV-001-0024A-A SG 3 MAIN STM HDR PRESS 001 REACTOR 747 2,3 50112 8 2-FCV-063-0118 SIS ACCUM TK 1 FLOW ISOLATION VLV 063 REACTOR 693 3 48113 10 2-AHU-030-0080 CONTROL ROD DRIVE COOLING UNIT D-B 030 REACTOR 680 5 51114 10 2-AHU-030-0088 CONTROL ROD DRIVE COOLING UNIT C-A 030 REACTOR 680 5 51115 10 2-AHU-313-0262 INCORE INSTR RM AHU A 313 REACTOR 708 0 52116 10 2-CLR-030-0074 REACTOR LOWER COMPT COOLING UNIT A-A 030 REACTOR 693 5 47117 18 2-LOCL-500-0183C FLOOR PANEL REACTOR BUILDING 500 REACTOR 693 0 47118 21 2-TNK-063-0060 SIS ACCUMULATOR NO 4 063 REACTOR 693 1,3 49119 21 2-TNK-063-0119 SIS ACCUMULATOR NO 1 063 REACTOR 693 1,3 48Safety Function(s):

0 -Support Function1 -Reactivity Control2 -RCS Pressure Control3 -RCS Inventory Control4 -Decay Heat Removal5 -Containment Isolation D4 Sequoyah Unit 2 Seismic Walkdown Equipment List 2 Created By: Approved 8y: c .--A,,-,.- "-Risk Newog S Safety IEnhancedforl Area Anchorage ItemS IClassi UNID Description System I Building Elevation Significnt Replaced Functions IPEEE Walkby Verification 20 S 0,PMP.078-O012-A SPENT FUEL PITPUMPA 078 AUXIUARY 714 0 28101 21 O.HEX-078-0018 SPENT FUEL PIT HEAT EXCHANGER A 07 AUXILUARY 714 4 29 YSafety Function(s):

0 -Support Function1 -Reactivity ControlZ -RCS PreMWssu Control3 -RCS Inventry Control4 -D ecay Heat RemovalS -Contalnment Isolation D5 Sequoyah Unit 2 Area Walk-BysArea Building Elevation Description 1 Diesel Gen 722 Bay 2A2 Diesel Gen 740 2A Bd Rm3 Diesel Gen 740 2A Fan Rm4 Diesel Gen 722 Bay 2B5 Diesel Gen 740 2B Bd Rm6 Diesel Gen 740 2B Fan Rm7 ERCW Pump 720 2A Pump Rm8 ERCW Pump 704 2A Bd Rm9 ERCW Pump 688 2A Strainer Rm10 ERCW Pump 720 2B Pump Rm11 ERCW Pump 704 2B Bd Rm12 Control 732 Cont. Mech. Eqpt. Room13 Control 732 Control Room Unit 214 Auxiliary 734 125V Batt Bd Room II15 Auxiliary 734 480V Shtdwn Bd Rm 2A216 Auxiliary 734 480V Shtdwn Bd Rm 2B117 Auxiliary 734 480V Shtdwn Bd Rm 2B218 Auxiliary 749 480V XFMR Rm 2B19 Auxiliary 749 480V XFMR Rm 2A20 Auxiliary 749 125V Batt Rm III21 Auxiliary 749 125V Batt Rm IV22 Auxiliary 749 480V Bd Rm 2B23 Auxiliary 749 480V Bd Rm 2A24 Auxiliary 749 480V 2A Mech Eq Room25 Auxiliary 653 RHR Pump Area26 Auxiliary 669 SI Pump Rm 2A27 Auxiliary 690 CCS Pump Area28 Auxiliary 714 SFP Pit29 Auxiliary 714 SFP HEX Area30 Auxiliary 759 CRDM Room31 Auxiliary 734 6.9kV Shtdwn Bd Rm A32 Auxiliary 734 Surge Tnk B AreaArea 33 Omitted34 Auxiliary 669 Aux Feedwtr Pmp 2A-S35 Auxiliary 669 Chg. Pump Rm 2B36 Auxiliary 734 6.9kV Shtdwn Bd Rm B37 Control 669 669 Mech Room38 Auxiliary 690 Aux Feedwtr Pmp B Area39 Auxiliary 690 2B RHR CCS HEX Room40 Auxiliary 714 Shtdwn Bd B AreaArea 41 Omitted42 Auxiliary 690 2A RHR CCS HEX Room43 Auxiliary 669 SI Pump Area44 Auxiliary 653 CS Pump Room 2B45 Auxiliary 734 125V Batt Bd Room IVD6 Sequoyah Unit 2 Area Walk-BysArea Building Elevation Description 46 Reactor 693 Accum. Rm 347 Reactor 693 Fan Room 148 Reactor 693 Accum. Rm 149 Reactor 693 Accum. Rm 450 Reactor 747 Annulus AZ 27751 Reactor 680 Inside Polar Crane Wall52 Reactor 708 Incore Inst Room PlatformD7 Appendix E: SWCsThe following signatures are provided for the engineers responsible for the Seismic WalkdownChecklists in Sequoyah Unit 2.Name Si"nyture DateIsaac Antanaitis I/ (2./f x-James Edgar -.Robert Malone ,Steven Summers / 1Phillip York t(-I7-?6Iz El Status: YM NO UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-O-DRYA-032-0002-B Equip. Class3 0 -Other (Dryer)Equipment Description AUX CONTROL AIR DRYER B-BLocation:

Bldg. Aux Floor El. 734 Room, Area 32 -Surge Tank B 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

1. Is the anchorage configuration verification required (i.e., is the item one YEI 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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YN NEI UE N/AENE UE N/AEY23 NEI UE N/AEYE NEI UE N/AHYO NEI UE-3 Enter the equipment class name from Appendix B: Classes of Equipment E2 Equipment ID No. SQN-O-DRYA-032-0002-B Eq a0tDEquip. ClaSS3 0 -Other (Dryer)Equipment Description AUX CONTROL AIR DRYER B-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YX NEI UE- N/AE8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YX NEI Ur N/AEand 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?YM NEI UrI N/AErYZNrUEIOther Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YM NEI UE1adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MalonePhillip YorkDate: 8/8/128/8/12E3 St..~: YEK NE UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDC-201-FL-A Equip. Class3I -MCCEquipment Description 480V ERCW MCC 2A-ALocation:

Bldg. ERCW Floor El. 704 Room, Area 8 -2A Board RoomManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware?

Front panels could not be opened due to sensitive equipment that isutilized in all modes of operation.

Front kick-plates and back panelsrequired extensive disassembly to open. Weld between channel andcabinet was checked for condition only.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YX NEI UEI N/AEYCK NEI UE N/AENED UE N/AEYEl N E- U E N/A MYN NEI U-3 Enter the equipment class name from Appendix B: Classes of Equipment E4 Equipment ID No. SQN-2-BDC-201-FL-A Equip. ClaSS3 I -MCCEquipment Description 480V ERCW MCC 2A-AInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YER NEI UEr N/Ar8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NEI UE- N/AEand 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?YX NEI UE- N/AEYN NEI UI-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 7/19/12Phillio York7/19/12E5 St~t..: YCK NO UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDC-201-FN-B Equip. Class31 -MCCEquipment Description 480V ERCW MCC 2B-BLocation:

Bldg. ERCW Floor El. 704 Room, Area 11 -2B Board RoomManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware?

Front panels could not be opened due to sensitive equipment that isutilized in all modes of operation.

Front kick-plates and back panelsrequired extensive disassembly to open. Weld between channel andcabinet was checked for condition only.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YN NEI UE N/AEY 1 N E- U E- N/AEYN NE UE N/AEYO: NO--UO--VAN/[]

YE NEI UE/3 Enter the equipment class name from Appendix B: Classes of Equipment E6 Equipment ID No. SQN-2-B4 C-201-FN-B Equip. ClaSS3 I -MCCEquipment Description 480V ERCW MCC 2B-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YM NO U- N/AE8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YER NEI U- N/AOand 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 NO UEI N/AOYM NEI U0Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 7/24/12Phillip York7/24/12E7 St....: Yl NE UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDC-201-FQ-A Equip. Class3I -MCCEquipment Description 480V DIESEL AUXILIARY BOARD 2A,1-ALocation:

Bldg. DG Floor El. 740 Room, Area 2 -2A Board RoomManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

For anchorage configuration verification see calculation SCG-4M-00169. pages 17, 18A, 18B, and 18C.2. Is the anchorage free of bent, broken, missing or loose hardware?

Front kick-plates were removed and anchorage to structure wasverified.

Front panels could not be opened due to sensitive equipment that is utilized in all modes of operation.

Back panels requiredextensive disassembly to open. Weld between channel and cabinet waschecked for condition only.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YN NOYZ NE U- N/AEYER NE UE N/AEYN NE UE N/AEYN NO UE N/AEY M N E- U E]3 Enter the equipment class name from Appendix B: Classes of Equipment E8 Equipment ID No. SQN-2-BDC-201-FQ-A Equip. ClasS3 I -MCCEquipment Description 480V DIESEL AUXILIARY BOARD 2A1-AInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

Conduit from top of cabinet has minimum clear distance to cable trays.Licensing evaluation shows that seismic event would cause a movementof one-half inches. Not credible.

8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

Masonrv block wall behind cabinet seismically qualified in calculation SCG-1-86.

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?YCK NO UO N/AE[YZ NEI UEl N/AE:]YZ NEI U- N/AE3YN NEI U[Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 7/18/12Philli York7/18/12E9 St....: YO NEI UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDC-201-FU-B Equip. Class31 -MCCEquipment Description 480V DIESEL AUXILIARY BOARD 2B1-BLocation:

Bldg. DG Floor El. 740 Room, Area5 -2B Board RoomManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

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

2. Is the anchorage free of bent, broken, missing or loose hardware?

Front kick-plates were removed and anchorage to structure wasverified.

Front panels could not be opened due to sensitive equipment that is utilized in all modes of operation.

Back panels requiredextensive disassembly to open. Weld between channel and cabinet waschecked for condition only.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YZ NE UE N/AEYO NE UE N/AENE UE N/AEYE NE UE N/AZYO NE UE3 Enter the equipment class name from Appendix B: Classes of Equipment El0 Equipment ID No. SQN-2-BDC-201-FU-B Equip. ClaSS3 I -MCCEquipment Description 480V DIESEL AUXILIARY BOARD 2B1-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YZ NEI Ur N/AE-8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NO UE1 N/AEand masonry block walls not likely to collapse onto the equipment?

Masonry block wall behind cabinet seismically qualified in calculation SCG-1-86.

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 UE- N/A-YN NO UE]Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 7/24/12Phillio York7/24/12Ell

&.....: YE NO UE]Seismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDC-201-GM-A EEquipment Description 480V REACTOR MOV BD 2A2-ALocation:

Bldg. Aux Floor El. 749 Roonquip. Class31 -MCCn, Area 23 -480V Board Room 2AManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

1. Is the anchorage configuration verification required (i.e., is the item one YE No]of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware?

Front kick-plates were removed and anchorage to structure wasverified Front panels could not be opened due to sensitive equipment that is utilized in all modes of operation.

Back panels requiredextensive disassembly to open. Weld between channel and cabinet waschecked for condition only.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YN NE UE N/AEYO NE UE N/AENE UE N/AOYE NE UE- N/AMNO UEr3 Enter the equipment class name from Appendix B: Classes of Equipment E12 Equipment ID No. SQN-2-BDC-201-GM-A Equip. ClaSS3 I -MCCEquipment Description 480V REACTOR MOV BD 2A2-AInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

Floor fan is chained improperly to conduit support near cabinet.During a seismic event fan could hit cabinet.YE] NM U- N/AF8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, Y[ NO U" N/AEand 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?YM NO Ur N/AENr-U1uOther Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MalonePhillip YorkDate: 7/30/127/30/12E13 St.,...:

YN NEI U0]Seismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDC-201-GN-B Equip. Class3I -MCCEquipment Description 480V REACTOR MOV BD 2B1-BLocation:

Bldg. Aux Floor El. 749 Room, Area 22 -480V Board Room 2BManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware?

Front kick-plates were removed and anchorage to structure wasverified.

Front panels could not be opened due to sensitive equipment that is utilized in all modes of operation.

Back panels requiredextensive disassembly to open. Weld between channel and cabinet waschecked for condition only.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YER NE UE N/AE[YN NEI UE N/AEYER NE UE N/AEYE NEI UE N/ANYN NO UE3 Enter the equipment class name from Appendix B: Classes of Equipment E14 Equipment ID No. Sei N-2-B4C-201-GN-B EqiCls2B-B Equip. ClaSS3 1 -MCCEquipment Description 480V REACTOR MOV BD 281-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YN NEI UE N/AEl8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NEI U- N/A-and masonry block walls not likely to collapse onto the equipment?

Masonrt block wall seismically qualified in calculation SCG130XI 1.9. Do attached lines have adequate flexibility to avoid damage?YN NO UEI N/A-10. Based on the above seismic interaction evaluations, is equipment free YN NE U--of potentially adverse seismic interaction effects?Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YN NEI Ur1adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneJames EdgarDate: 7/26/127/26/12E15 S,.. ý.: Y Z N E UElSeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDC-201-JK-A Equip. Class3I -MCCEquipment Description 480V CONT & AUX BLDG VENT BD 2A2-ALocation:

Bldg. Aux Floor El. 734 Room, Area 15 -480V Shutdown Board Room 2A2Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist maybe 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

YONO2. Is the anchorage free of bent, broken, missing or loose hardware?

Front kick-plates were removed and anchorage to structure wasverified Front panels could not be opened due to sensitive equipment that is utilized in all modes of operation.

Back panels requiredextensive disassembly to open. Weld between channel and cabinet waschecked for condition only.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YO NEI UE- N/AEYO NE UE N/AEYO NE UE N/AE-YE NEI UE N/AOYO NEI UE-3 Enter the equipment class name from Appendix B: Classes of Equipment E16 Equipment ID No. SQN-2-BDC-201-JK-A Equip. ClaSS3 I -MCCEquipment Description 480V CONT & AUX BLDG VENT BD 2A2-AInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

Y[ NEI UE- N/AEr8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NE UE1 N/AEand 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?YN NEI U- N/AEYZ NO UFOther Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 7/30/12PhilliD York7/30/12E17 St.,..: YN NE UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDC-201-DO-A Equip. Class32 -Low VoltageEquipment Description 480V SHUTDOWN BD 2A2-ALocation:

Bldg. Aux Floor El. 734 Room, Area 15 -480V Shutdown Board Room 2A2Manufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware?

Front panels could not be opened due to the excessive safety hazard ofopening this shutdown board during any mode of operation.

Backpanels required extensive disassembly to open. Weld between channeland cabinet was checkedfor condition only.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YN NEI UE N/AENE UE N/AEY[ NE UE-I N/AEYE NEI UE N/AIKYE NO UE-13 Enter the equipment class name from Appendix B: Classes of Equipment E18 Equipment ID No. SQN-2-BDC-20 1-DO-A EiCsAL-AEquip. C1aSS3 2 -Low VoltageEquipment Description 480V SHUTDOWN BD 2A2-AInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YE NEI UEr N/AD8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YM No U0 N/AEand 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 UiE N/AEYS NEI-U-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 7/30/12PhilliD York7/30/12E19 St.t..: YN NEI UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDB-201-DP-B Equip. Class32 -Low Voltagqe Switchqear Equipment Description 480V SHUTDOWN BD 2B1-BLocation:

Bldg. Aux Floor El. 734 Room, Area 16 -480V Shutdown Board Room 2BIManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware?

Front panels could not be opened due to the excessive safety hazard ofopening this shutdown board during any mode of operation.

Backpanels required extensive disassembly to open. Weld between channeland cabinet was checked for condition only.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YN NEI U- N/A--YN NEI UE N/AEYN NEI UEI N/AEYE NE UE N/AZYIR NE UE3 Enter the equipment class name from Appendix B: Classes of Equipment E20 Equipment ID No. SQN-2-BDB-201-DP-B Equip. ClasS3 2 -Low Voltage Switch-gear Equipment Description 480V SHUTDOWN BD 2B1-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YE NO UE[ N/AE8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NEI U- N/AE'and masonry block walls not likely to collapse onto the equipment?

Masonry block wall seismically qualified in calculation SCG130X11.

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?YE NE UE N/AOYNN[UOOther Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneJames EdgarDate: 7/26/127/26/12E21 Status: Yl NEI U0Seismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDB-201-QQ-B Equip. Class32 -Low Voltage Switch-gear Equipment Description 480V SHUTDOWN BD 2B2-BLocation:

Bldg. Aux Floor El. 734 Room, Area 17- 480V Shutdown Board Room 2B2Manufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware?

Front panels could not be opened due to the excessive safety hazard ofopening this shutdown board during any mode of operation.

Backpanels required extensive disassembly to open. Weld between channeland cabinet was checked for condition only.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YX NEI UE N/AEYO NEI UE N/AENE UE N/AEYE NE UE1 N/ASYZ Ur3 Enter the equipment class name from Appendix B: Classes of Equipment E22 Equipment ID No. SQN-2-BDB-20 1-DO-B E a L t cEquip. ClasS3 2 -Low Voltat7e Switchgear Equipment Description 480V SHUTDOWN BD 2B2-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

Yl NEI UE N/Al8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, Yl NO U- N/A-and masonry block walls not likely to collapse onto the equipment?

Masonry block wall seismically qualified in calculation SCGI3OX!

1.9. 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 NO UE N/AlYI NEI UE-IOther Adverse Conditions II. Have you looked for and found no other seismic conditions that could Y[ NE UEadversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneJames EdgarDate: 7/26/127/26/12E23 Stat..: YN NEI USeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDA-202-CO-A Equip. Class33 -Medium Voltage Switchqear Equipment Description 6900V SHUTDOWN BOARD 2A-ALocation:

Bldg. Aux Floor El. 734 Room, Area 31 -6.9kV Shutdown Board Room 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

YE NZ2. Is the anchorage free of bent, broken, missing or loose hardware?

Front panels could not be opened due to the excessive safety hazard ofopening this shutdown board during any mode of operation.

Backpanels required extensive disassembli' to open.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YN NE UE N/AENE UE N/AENE UE N/AEYE NE UE N/AZYNNEU-3 Enter the equipment class name from Appendix B: Classes of Equipment E24 Equipment ID No. SQN-2-BDA-202-CO-A Equip. Class33 -Medium Voltage Switchgear Equipment Description 6900V SHUTDOWN BOARD 2A-AInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YZ NO UO N/A[]8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NEI U- N/AEand 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?YM NE U- N/AEY[ NEI UMOther Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 8/3/12Phillib York8/3/12E25 St.,..: YN NO U-Seismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-BDB-202-CP-B Equipment Description 6900V SHUTDOWN BOARILocation:

Bldg. Aux Floor El. 734Manufacturer, Model, Etc. (optional but recommend, Equip. Class3 3 -Medium Voltage Switchcqear Q 2B-BRoom, Area 36 -6.9kV Shutdown Board Room BInstructions 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware?

Front panels could not be opened due to the excessive safety hazard ofopening this shutdown board during any mode of operation.

Backpanels required extensive disassembly to open.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YZ NE UE N/AEYM NEI UE N/AEY1Z NEI UE N/AEYE NEI UE N/ANYCK NE UE3 Enter the equipment class name from Appendix B: Classes of Equipment E26 Equipment ID No. SQN-2-BDB-202-CP-B Equip. Class33 -Medium Voltagqe Switchaqear Equipment Description 6900V SHUTDOWN BOARD 2B-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YN NO] Ur N/AE-Scaffolding in front of equipment needs additional restraint to preventtipping into soft targets.

Only one restraint point was used near thebottom on the assembly.

During a seismic event, the scaffolding couldoverturn and strike the equipment.

On a later inspection, it was foundthat the scaffolding had been anchored properly from the top of theassembly.

8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YO N rU- N/Ar-and masonry block walls not likely to collapse onto the equipment?

Masonrn, block wall near equipment seismically qualified in calculation 46W405-5.

9. Do attached lines have adequate flexibility to avoid damage?YN NEI Ur N/A[l10. Based on the above seismic interaction evaluations, is equipment freeof potentially adverse seismic interaction effects?YX NEI U-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Appendix R work was being performed in the area at the same time the walkdown occurred.

Temporary equipment was prevalent in the area. Proper storage for the equipment was verified.

Evaluated by: Robert MaloneDate: 8/7/12Phillip YorkIsaac Antanaitis 8/7/12 & 8/23/128/23/12E27 St~t..: YN NO UOSeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-OXF-202-2A-A Equip. Class34 -Transformer Equipment Description 480V SHUTDOWN TRANSFORMER 2A l-ALocation:

Bldg. Aux Floor El. 749 Room, Area 19 -480V Transformer Room 2AManufacturer, 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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchora2e

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

For anchorage configuration verification see draivings 705 7025 and48N1274 Mk 2.2. 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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YS NE UE N/AEY0 NE UE N/AEYS NE U[ N/AEYN NEI UE N/AEY9 NEI UE3 Enter the equipment class name from Appendix B: Classes of Equipment E28 Equipment ID No. SQN-2-OXF-202-2A-A Equip. ClaSS3 4 -Transformer Equipment Description 480V SHUTDOWN TRANSFORMER 2A 1-AInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YM NEI UEr N/AE8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NEI UL1 N/AEand masonry block walls not likely to collapse onto the equipment?

Masonry block wall seismically qualified in drawing 46W405- 7,9.9. 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 NO UE- N/AE]YM NO UFOther Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 7/30/12Phillio York7/30/12E29 St....: YN NEI U-Seismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-OXF-202-2B-B Equip. Class34 -Transformer Equipment Description SD XFMR 2B-BLocation:

Bldg. Aux Floor El. 749 Room, Area 18 -480V Transformer Room 2BManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

For anchorage configuration verification see drawings 705 7025 and48N1274 Mk 2.2. 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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YN NEIYZ NEI U- N/AE:-YN NEI UE N/A-YX NEI UE N/A-YX NEI UE-] N/ADYZ NO U-3 Enter the equipment class name from Appendix B: Classes of Equipment E30 Equipment ID No. SQN-2-OXF-202-2B-B Equip. ClasS3 4 -Transfonner Equipment Description SD XFMR 28-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YZ NEI UE N/A-8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, Y 0 N E- U E- N/AEand masonry block walls not likely to collapse onto the equipment?

Hairline cracks were observed and should be monitored.

Masonryblock wall seismically qualified in drawing 46W405- 7,9.9. 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?YX NE UE N/AEOther Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 7/26/12James Edoar7/26/12E31 Stat,.: YN NE UE-Seismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-OXF-202-DN-A Equip. Class34 -Transformer Equipment Description 480V SHUTDOWN TRANSFORMER 2A-ALocation:

Bldg. Aux Floor El. 749 Room, Area 19 -480V Transformer Room 2AManufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist maybe 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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

For anchorage configuration verification see drawings 7057025 and48N1274 MA- 2.2. 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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YX NE UE[ N/AOYN NO UE N/AEYN NE UE N/AEYX NE U[ N/AEYN NOU113 Enter the equipment class name from Appendix B: Classes of Equipment E32 Equipment ID No. SQN-2-OXF-202-DN-A Equip. ClaSS3 4 -Transformer Equipment Description 480V SHUTDOWN TRANSFORMER 2A-AInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YM NEI ul N/AE8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YZ NE uIE N/AEand masonry block walls not likely to collapse onto the equipment?

Hairline cracks were observed and should be monitored.

Dwg46W405-8 confirms use of same size rebar throughout the length ofwall. Masonry block wall seismically qualified in drawing 46W405-7,9.9. Do attached lines have adequate flexibility to avoid damage? YX NE UE N/AE10. Based on the above seismic interaction evaluations, is equipment freeof potentially adverse seismic interaction effects?YN NEI UrOther Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MalonePhillip YorkDate: 7/30/127/30/12E33 S~t~t.: YX NEI UOSeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-OXF-202-DQ-B Equip. Class34 -Transformer Equipment Description SD XFMR 2B2-BLocation:

Bldg. Aux Floor El. 749 Room, Area 18 -480V Transformer Room 2BManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

For anchorage configuraiion verification see drawings 7057025 and48N1274 Mk 2.2. 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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

Y9 NEI U- N/AEYZ NO UE- N/A-YZ NEI UE N/A-YZ NE U- N/AEYZ NO U-3 Enter the equipment class name from Appendix B: Classes of Equipment E34 Equipment ID No. SQN-2-OXF-202-DQ-B Equip. ClaSS3 4 -Transformer Equipment Description SD XFMR 2B2-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

Y9 NEI UE- N/AO8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NEI UE1 N/AEand masonry block walls not likely to collapse onto the equipment?

Hairline cracks were observed and should be monitored.

Masonryblock wall seismically qualified in drawing 46W405-7,9.

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 UE1 N/A--YZ NEI UE-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert Malone -Date: 7/26/12James Edaar7/26/12E35 Stat..: YZ NEI UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-XFA-202-0312 Equip. Class34 -Transformer Equipment Description ERCW TRANSFORMER 2A-ALocation:

Bldg. ERCW Floor El. 704 Room, Area 8 -2A Board RoomManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchora2e

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

For anchorage configuration verification see drawings 35 W312 SectionA-A and 33N334 Section G-G.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 the anchors?.5. Is the anchorage configuration consistent with plant documentation?

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

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

YN NEINEI UE N/A-NEI UE N/AENO Ur N/AFENEI UE N/AEYN NEI UE--]3 Enter the equipment class name from Appendix B: Classes of Equipment E36 Equipment ID No. SQN-2-XFA-202-0312 Equip. ClaSS3 4 -Transformer Equipment Description ERCW TRANSFORMER 2A-AInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YN NEI UE- N/AE8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NEI UEr N/AEand 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?YN NEI U13 N/AErYX NO U-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MalonePhillip YorkDate: 7/19/127/19/12E37 Status: YN NO U0Seismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-XFA-202-0316 Equip. Class34 -Transformer Equipment Description ERCW TRANSFORMER 2B-BLocation:

Bldg. ERCW Floor El. 704 Room, Area 11 -2B Board RoomManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

For anchorage configuration verification see drmvings 35 W312 SectionA-A and 33N334 Section G-G.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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YX NEI UE1 N/AEYCK NE UE N/AEY[K NE UE N/AENE UE N/AEYN NE UE13 Enter the equipment class name from Appendix B: Classes of Equipment E38 Equipment ID No. SQN-2-XFA-202-0316 Equip. ClaSS3 4 -Transformer Equipment Description ERCW TRANSFORMER 2B-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YN NEI UE1 N/AEI8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NEI UE- N/AEland 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?YS NEI UE N/AEIYN NEI UMOther Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MalonePhillip YorkDate: 7/24/127/24/12E39 St.: YZ NEI UMSeismic Walkdown Checklist (SWC)Equipment ID No. SQN-O-PMP-078-0012-A Equip. Class35 -Horizontal PumpEquipment Description SPENT FUEL PIT PUMP ALocation:

Bldg. Aux Floor El. 714 Room, Area 28 -Spent Fuel Pool PitManufacturer, 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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

1. Is the anchorage configuration verification required (i.e., is the item one Y E 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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

6. Based-on the above anchorage evaluations, is the anchorage free ofpotentially adverse seismic conditions?

YE NO UE N/AEYZ NO UE N/AE]YE ENO UE N/AEYE NE UE N/ANY[ NO UE3 Enter the equipment class name from Appendix B: Classes of Equipment E40 Equipment ID No. SQN-0-PMP-078-0012-A Equip. ClasS3 5 -Horizontal PumpEquipment Description SPENT FUEL PIT PUMP AInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YE NEI UE N/AE8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YX NO Ur N/AEand 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?YM NE UE- N/AEYER NEI U-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 8/2112Phillip York8/2/12E41 Statt: YN NEI UE]Seismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-PMP-003-0128 Equip. Class35 -Horizontal PumpEquipment Description MOTOR DRIVEN AUX FEEDWA TER PUMP 2B-BLocation:

Bldg. Aux Floor El. 690 Room, Area 38 -Aux Feedwater Pump B 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not AppIicable Anchorage

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

For anchorage configuration verification see drawing C-55HMTA86X22-B

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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YIZ NEI UE N/A[YZ N- UE] N/AEYN NE UE1 N/A]YNl NE UE N/AEYN NO UE3 Enter the equipment class name from Appendix B: Classes of Equipment E42 Equipment ID No. SQN-2-PMP-003-0128 Equip. ClasS3 5 -Horizontal PumpEquipment Description MOTOR DRIVEN AUX FEEDWATER PUMP 2B-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YM NEI UE N/AE:8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YM NED Ur N/AEand 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?YM NEI UEr N/AOYX NO UE1Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 8/7/12Phiio York8/7/12E43 Sat,,.: Y 9 NE] UEF-Seismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-PMP-062-0104 Equip. Class35 -Horizontal PumpEquipment Description CENT. CHARGING PUMP 2B-BLocation:

Bldg. Aux Floor El. 669 Room, Area 35 -Charging Pump Room 2B-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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchoraie

1. Is the anchorage configuration verification required (i.e., is the item one Y 0 NEIof the 50% of SWEL items requiring such verification)?

For anchorage configuration verification see drawing ISJ-0476-C-01.

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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YZ NE UE N/AENEI UE N/A"NE UE N/AENE UE N/AEYN NEI UO3 Enter the equipment class name from Appendix B: Classes of Equipment E44 Equipment ID No. SQN-2-PMP-062-0104eEquiptiCla Equip. ClaSS3 5 -Horizontal PumpEquipment Description CENT. CHARGING PUMP 2B-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YS NO U3N/AEl8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NEI UI N/AE-and masonry block walls not likely to collapse onto the equipment?

A block wall used for equipment removal was near the equipment.

It isrestrained/reinforced with cross bars bolted to the concrete wall.9. Do attached lines have adequate flexibility to avoid damage?YM NEI UE- N/A-"10. Based on the above seismic interaction evaluations, is equipment free YM NE UEof potentially adverse seismic interaction effects?Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YN NEI UE1adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Flex conduit into junction box has slipped back and exposed the wires going into the box.Evaluated by: Robert MalonePhillip YorkDate: 8/6/128/6/12E45 Status: YX NO UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-PMP-063-O010 Equip. Class35 -Horizontal PumpEquipment Description SAFETY INJECTION PUMP 2A-ALocation:

Bldg. Aux Floor El. 669 Room, Area 26 -SI Pump Room 2AManufacturer, 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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage I. Is the anchorage configuration verification required (i.e., is the item one Yl NEIof the 50% of SWEL items requiring such verification)?

For anchorage configuration verification see drawing ISI-0476-C-0l.

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?

YN NE UE N/AOYtN NEI UE N/AE4. Is the anchorage free of visible cracks in the concrete near the anchors?

Y [] NE U E N/AE5. Is the anchorage configuration consistent with plant documentation?

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

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

YZ NEI UE N/AEYN NEI U-3 Enter the equipment class name from Appendix B: Classes of Equipment E46 Equipment ID No. SQN-2-PMP-063-OO1E Equipment Description SAFETY INJECTION PUMP 2A-Aquip. Class35 -Horizontal PumpInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

Y[ NEI UE1 N/AE8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, Y 0 N E- Ur1E N/AEand masonry block walls not likely to collapse onto the equipment?

A block wall used for equipment removal was near the equipment.

It isrestrained/reinforced with cross bars bolted to the concrete wall.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 UE N/AE-YN NE-I UEOther 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)

Flex conduit into junction box has slipped back and exposed the wires going into the box.Evaluated by: Robert MaloneDate: 8/6/128/6/12PhilliD YorkF47 St.tus: YN NE UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-2-PMP-070-0059-A Equip. Class35 -Horizontal PumpEquipment Description CCS PUMP 2A-ALocation:

Bldg. Aux Floor El. 690 Room, Area 27- CCS Pump 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

For anchorage configuration verification see drawing ISI-0260-C-01.

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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

Y1 NE UE N/AE]YX NO U-E N/A[YN NEI UIE N/AE-1YN NE UE N/AE[YO NEI UIE3 Enter the equipment class name from Appendix B: Classes of Equipment E48 Equipment ID No. SQN-2-PMP-070-0059-A Equip. ClaSS3 5 -Horizontal PurapEquipment Description CCS PUMP 2A-AInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YX NEIUO N/AE:8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YO NEIUE N/AE-and masonry block walls not likely to collapse onto the equipment?

There is a 10 '-12' "specialfire barrier" wall nevt to the equipment.

Itappears to be constructed of dry wall and cantileveredform the floor.During a seismic event, it was determined that the wall would notdamage the equipment if it collapsed and is therefore not considered seismically significant.

9. Do attached lines have adequate flexibility to avoid damage? YZ NEI UEI N/AE]10. Based on the above seismic interaction evaluations, is equipment freeof potentially adverse seismic interaction effects?Y 0 N I] U E]Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 8/2/12Phillib York8/2/12E49 St.tus: YZ NE UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-0-PMP-067-0452 Equip. Class36 -Vertical PumpEquipment Description ERCW PUMP N-BLocation:

Bldg. ERCW Floor El. 720 Room, Area 10 -2B Pump RoomManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

For anchorage configuration verification see TVA calculation CEB-CQS-373.2. 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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

YCK NEI UE- N/A-NEI UE N/AEY19 NEI UE N/AEYN NE UE N/AEYN NEI UE13 Enter the equipment class name from Appendix B: Classes of Equipment E50 Equipment ID No. SQN-O-PMP-067-0452 Equipment Description ERCW PUMP N-BEquip. Class36 -Vertical PumpInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

Y[ NEI Ur N/A-8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YM NO Ur N/AEand 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?YN NE UEr N/AOYZ NO UE-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MalonePhilili YorkDate: 7/24/127/24/12E51 S,.,..: YE NEI UE1Seismic Walkdown Checklist (SWC)Equipment ID No. SQN-0-PMP-067-0464 Equip. Class36 -Vertical PumpEquipment Description ERCW PUMP R-ALocation:

Bldg. ERCW Floor El. 720 Room, Area 7 -2A Pump RoomManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

For anchorage configuration verification see TVA calculation CEB-CQS-373.2. 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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

Y19 NEI UE N/AEYCK NO U[ N/A-NE UE N/AEYS NEl U E- N/A EYN NEI UE3 Enter the equipment class name from Appendix B: Classes of Equipment E52 Equipment ID No. SQN-0-PMP-067-0464 Equipment Description ERCW PUMP R-AEquip. Class36 -Vertical PumpInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YM NEI U- N/AEr8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YN NEI UEr N/AEand 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 U- N/AEYM NEI UIOther Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MaloneDate: 7/19/12Phillib York7/19/12E53 Stat.,s:

YX NO UESeismic Walkdown Checklist (SWC)Equipment ID No. SQN-0-PMP-067-0482-B Equip. Class36 -Vertical PumpEquipment Description ERCW SCREEN WASH PUMP C-BLocation:

Bldg. ERCW Floor El. 720 Room, Area 10 -2B Pump RoomManufacturer, 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 ofjudgments andfindings.

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

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

For anchorage configuration verification see drawing 31 W211-6,Section B6-B6.2. 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 the anchors?5. Is the anchorage configuration consistent with plant documentation?

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

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

Y[ NEI UE N/AE-YN NE U13 N/AOY[ NEI UE N/AEYN NE UE N/AENEI UEI3 Enter the equipment class name from Appendix B: Classes of Equipment E54 Equipment ID No. SQN-0-PMP-067-0482-B EupCas6 etEquip. ClaSS3 6 -Vertical PumpEquipment Description ERCW SCREEN WASH PUMP C-BInteraction Effects7. Are soft targets free from impact by nearby equipment or structures?

YM NEI UEI N/Ar8. Are overhead equipment, distribution

systems, ceiling tiles and lighting, YCK NEI UE1 N/AE]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?YN NED UE N/AE Other Adverse Conditions

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

Cover to electrical box attached to equipment was not closed and caulkhas pulled away from the electrical wire. Assembly is no longerwatertight.

Comments (Additional pages may be added as necessary)

Evaluated by: Robert MalonePhillip YorkDate: 7/24/127/24/12E55 St.:YN NEI U7Seismic Walkdown Checklist (SWC)Equipment ID No. SQN-0-PMP-067-0487-A Equip. Class36- Vertical PumpEquipment Description ERCW SCREEN WASH PUMP D-ALocation: