L-MT-12-103, Final Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident

Final Response to NRC Request for Information Per 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident

ML12342A025
Person / Time
Site:	Monticello
Issue date:	11/27/2012
From:	Grubb J C Northern States Power Co, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-12-103
Download: ML12342A025 (463)

Text

{{#Wiki_filter:IG NTA9*3 SUNS' -WIT 21 Le:O FR.M PU.LI. jXceIEnergys Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 November 27, 2012 L-MT-12-103 10 CFR 50.54(f)U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 MNGP Final Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident

References:

1. NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident" dated March 12, 2012, ADAMS Accession No. ML12053A340.

2. NRC Letter, "Endorsement of Electric Power Research Institute (EPRI) Draft Report 1025286, 'Seismic Walkdown Guidance,"'

dated May 31, 2012, ADAMS Accession No. ML12145A529.

3. NSPM Letter to NRC, "Monticello Nuclear Generating Plant's 120-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated July 9, 2012.On March 12, 2012, the Nuclear Regulatory Commission (NRC) Staff issued a request for information regarding Near-Term Task Force (NTTF) insights from the Fukushima Dai-ichi accident, to all NRC power reactor licensees and holders of construction permits in active or deferred status (Reference 1). Enclosure 3 of the March 12, 2012 letter contains specific Requested Actions, Requested Information, and Required Responses associated with Near-Term Task Force (NTTF) Recommendation 2.3, 12Y-4 Document Control Desk Page 2 Seismic. This letter provides the required response to the Requested Information for NTTF Recommendation 2.3, Seismic, from the Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, on behalf of the Monticello Nuclear Generating Plant (MNGP).In a letter to the NRC dated July 9, 2012 (Reference 3), NSPM confirmed that it would use EPRI Report 1025286, "Seismic Walkdown Guidance For Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic," endorsed by the NRC in Reference 2, as the basis for seismic walkdowns at the MNGP. NSPM performed walkdowns in accordance with the NRC-endorsed guidance to verify current plant configuration with the current licensing basis; verify the adequacy of current strategies and maintenance plans; and identify degraded, nonconforming, or unanalyzed conditions.

The enclosure to this letter provides the Requested Information in response to NTTF Rec-mm-enation-2.3, Seisrnic, and includes the results of the seismicwal-downsfor MNGP. The enclosure contains Sensitive Unclassified Non-Safeguards Information (SUNSI) of which the loss, issue, modification, or unauthorized access can reasonably be foreseen to harm the public interest, or the commercial or financial interests of NSPM. NSPM requests that this proprietary information be withheld under 10 CFR 2.390(d)(1). The affected pages have been marked as proprietary, and sensitive information redacted for public disclosure. If there are any questions, or if additional information is needed, please contact Ms.Jennie Eckholt, Licensing Engineer, at 612-330-5788. Summary-of Commitments -. ... ... ....... ... ...This letter makes the following new commitments and makes no revisions to existing commitments. Regulatory Commitments Due Date NSPM will complete the Seismic Walkdowns of the Refueling Outage inaccessible components listed in Appendix D, "Plan for (RFO) R26 Future Seismic Walkdown of Inaccessible Equipment," of the enclosure. NSPM will provide an updated seismic walkdown report 60 days following with the results of the walkdowns of the inaccessible the end of RFO R26 components. Document Control Desk Page 3 I declare under penalty of perjury that the foregoing is true and correct.Executed on November 27, 2012.John C. Grubb Plant Manager, Monticello Nuclear Generating Plant Northern States Power Company -Minnesota Enclosure cc:

• Ad mi-inistrator, Region lll, USNRC Director, Office of Nuclear Reactor Regulation (NRR)NRR Project Manager, MNGP, USNRC Senior Resident Inspector, MNGP, USNRC CONTAINS SUNSI -WITHHOLD FROM PUBLIC DISCLOSURE ENCLOSURE MONTICELLO NUCLEAR GENERATING PLANT NTTF RECOMMENDATION 2.3 -SEISMIC SEISMIC WALKDOWN REPORT (830 Pages Follow)

Monticello Nuclear Generating Plant Seismic Walkdown Report Contents L is t o f T a b le s ......................................................................................................... iii Executive Sum mary ............................................................................................... iv 1 Introduction .................................................................................................................. 1-1 1 .1 B a c k g ro u n d ........................................................................................................... 1 -1 1.2 Plant Overview ...................................................................................................... 1-1 1 .3 A p p ro a c h ............................................................................................................... 1 -1 2 Seism ic Licensing Basis .......................................................................................... 2-1 2 .1 O v e rv ie w ............................................................................................................... 2 -1 2.2 Safe Shutdown Earthquake (SSE) ........................................................................ 2-1 2.3 Design of Seismic Category I SSCs ...... -.u................................. 2-1 2.3.1 Sum m ary of Seism ic Design for Class I SSCs ............................................. 2-2 2.3.2 Methods of Analysis for Class 1 SSCs ......................................................... 2-2 2.3.3 Sum m ary of Codes and Standards .............................................................. 2-3 3 Personnel Qualifications .......................................................................................... 3-1 3.1 Overview ...................................................................................................... 3-1 3.2 W alkdown Personnel ............................................................................................. 3-1 3.3 Personnel Qualifications ........................................................................................ 3-2 4 Selection of SSCs .................................................................................................... 4-1 4.1 Overview ............................................. ...... 4-1 4.2 SW EL Development .............................................................................................. 4-1 4.2.1 SWEL 1 -Sample of Required Items for the Five Safety Functions ............. 4-1 4.2.2 SWEL 2 -Spent Fuel Pool Related Items ........................ 4-4 4.2.3 SW EL 2 Development Conclusion ..................... ........ ............................. 4-5 5 Seism ic W alkdowns and Area W alk-Bys ............................................................... 5-1 5 .1 O v e rv ie w ............................................................................................................... 5 -1 5.2 Seism ic W alkdowns .............................................................................................. 5-1 5.2.1 Adverse Anchorage Conditions .......................... .. ...5-2 5.2.2 Configuration Verification ............................................................................ 5-2 5.2.3 Adverse Seism ic Spatial Interactions ........................................................... 5-3 Monticello Nuclear Generating Plant Seismic Walkdown Report 5.2.4 Other Adverse Seismic Conditions ............................................................... 5-4 5.2.5 Issues Identified during Seismic W alkdowns ................................................ 5-4 5 .3 A re a W a lk-B ys ...................................................................................................... 5 -5 5.3.1 Seismically-Induced Flooding/Spray Interactions ......................................... 5-5 5.3.2 Seismically-Induced Fire Interactions ........................................................... 5-6 5.3.3 Issues Identified during Area W alk-bys ........................................................ 5-6 6 Licensing Basis Evaluations .................................................................................. 6-1 7 IPEEE Vulnerabilities Resolution Report ............................................................... 7-1 8 Peer Review .................................................................................................................. 8-1 9 References .................................................................................................................... 9-1 Appendices__ _A Equipment Lists ........................................................................................................... A-1 B Seismic Walkdown Checklists (SWCs) ................................................................. B-1 C Area Walk-By Checklists (AWCs) ............................................................................ C-1 D Plan for Future Seismic Walkdown of Inaccessible Equipment .............. D-1 E Peer Review Report ................................................................................................ E-1 F Disposition of Seismic Walkdown Observations .................................................. F-1 ii Monticello Nuclear Generating Plant Seismic Walkdown Report List of Tables Table 2-1: List of Codes, Standards, and Specifications .................................................. 2-4 T a ble 3-1: P e rso nne l R oles ......................................................................... ............. 3-1 Table 5-1: Anchorage Configuration Verification .......................................................... 5-3 Table 5-2: CAP Status for SWCs ................................................................................... 5-8 Table 5-3: CAP Status for AWCs ................................................................................... 5-9 Table 7-1: Monticello IPEEE Seismic Improvements ........................................................ 7-2 Table A-i: Monticello Base List 1 .............................................................................. A-2 Table A-2: Monticello SWEL 1 ...................................................... I ............................ A-32 Table B-1: Monticello Completed SWCs ...................................................................... B-1 Table C-1: Monticello Completed AWCs .................................................................... C-1 Table D-i: Monticello Deferred Equipment List ......................................................... D-1 Table F-i: Disposition of SWC Observations ................................................................ F-1 Table F-2: Disposition of AWC Observations ................................................................ F-5 iii Monticello Nuclear Generating Plant Seismic Walkdown Report Executive Summary Following the accident at the Fukushima Dai-ichi nuclear power plant resulting from the March 11, 2011, Great Tohoku Earthquake and subsequent tsunami, the NRC established the Near-Term Task Force (NTTF) in response to Commission direction. The NTTF Charter, dated March 30, 2011, tasked the NTTF with conducting a systematic and methodical review of NRC processes and regulations and determining if the agency should make additional improvements to its regulatory system. Ultimately, a comprehensive set of recommendations contained in a report to the Commission (dated July 12, 2011, SECY-11-0093 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML1 11861807)) was developed. On August 19, 2011, following issuance of the NTTF report, the Commission directed the NRC staff in a staff requirements memorandum (SRM) for SECY-1 1-0093 (ADAMS Accession No. ML 112310021), in part, to determine which of the recommendations could and should be implemented without unnecessary delay. On September 9, 2011, the NRC staff provided a document to the Commission (ADAMS Accession No. ML 11 245A1 58) which identified those actions from the NTTF report that should be taken without unnecessary delay.On March 12, 2012, the NRC issued a 10 CFR 50.54(f) letter that requested information to assure that these recommendations are addressed by all U.S. nuclear power plants (Reference 6). Every U.S. nuclear power plant is required to perform seismic walkdowns to identify and address degraded, non-conforming or unanalyzed conditions and to verify the current plant configuration with the current seismic licensing basis. This report documents the seismic walkdowns performed at the Monticello Nuclear Generating Plant (MNGP) as required to address, in part, the 10 CFR 50.54(f) information request issued by the NRC.The Nuclear Energy Institute (NEI) cooperated with the NRC to prepare guidance for conducting seismic walkdowns as requested in Enclosure 3 of Reference 6, titled, Recommendation 2.3: Seismic. The guidelines and procedures prepared by NEI and endorsed by the NRC were published through the Electric Power Research Institute (EPRI) as EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012 (Reference 1). The Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, confirmed that the EPRI seismic walkdown guidance would be used as the basis for conducting the seismic walkdowns and developing the needed information at the MNGP in a letter dated July 9, 2012 (Reference 3).iv Monticello Nuclear Generating Plant Seismic Walkdown Report The EPRI Seismic Walkdown Guidance was used for the engineering walkdowns and evaluations described in this report. In accordance with the EPRI Seismic Walkdown Guidance, the following topics are addressed in the subsequent sections of this report: " Seismic Licensing Basis* Personnel Qualifications

• Selection of Systems, Structures, and Components (SSC)* Seismic Walkdowns and Area Walk-Bys* Seismic Licensing Basis Evaluations
• IPEEE Vulnerabilities Resolution Report* Peer Reviews This report documents any discrepancies or potential seismic issues identified as a result of the seismic walkdowns completed at the MNGP. No adverse seismic conditions were identified at the MNGP. Corrective Action Program Action Requests (CAPs) were entered into the site's 10 CFR 50 Appendix B qualified corrective action program.v Monticello Nuclear Generating Plant Seismic Walkdown Report I Introduction

1.1 BACKGROUND

In response to Near-Term Task Force (NTTF) Recommendation 2.3, the Nuclear Regulatory Commission (NRC) issued a 10 CFR 50.54(f) letter on March 12, 2012 requesting that all licensees perform seismic walkdowns to identify and address plant-specific degraded, nonconforming, or unanalyzed conditions (through the corrective action program) and verify the adequacy of monitoring and maintenance for protective features, and inform the NRC staff of the results of the walkdowns and corrective actions taken or planned. The Nuclear Energy Institute (NEI), with the Electric Power Research Institute (EPRI), prepared industry guidance to assist licensees in responding to this NRC request. The industry guidance document, EPRI Technical Report 1025286, Seismic Walkdown Guidanc6efor Resolufion of Fukushima N6ar-Term Task Force Recommendation 2.3: Seismic, dated June 2012 (Reference 1), was endorsed by the NRC on May 31, 2012 (Reference 4). NSPM confirmed that the EPRI seismic walkdown guidance would be used as the basis for conducting the seismic walkdowns and developing the needed information at the MNGP in a letter dated July 9, 2012 (Reference 3).1.2 PLANT OVERVIEW The Monticello Nuclear Generating Plant (MNGP) is located within the city limits of Monticello, Minnesota on the south bank of the Mississippi River. The plant and approximately 2150 acres of land at the plant site are owned by NSPM. NSPM is a wholly owned utility operating subsidiary of Xcel Energy Corporation (Xcel Energy). The current MNGP renewed operating license (Renewed Facility Operating License No.DPR-22) expires at midnight on September 8, 2030.1.3 APPROACH The EPRI Seismic Walkdown Guidance (Reference

1) was used for the MNGP engineering walkdowns and evaluations described in this report. In accordance with Reference 1, the following topics are addressed in the subsequent sections of this report:* Seismic Licensing Basis (Section 2)* Personnel Qualifications (Section 3)* Selection of SSCs (Section 4)* Seismic Walkdowns and Area Walk-Bys (Section 5)* Licensing Basis Evaluations (Section 6)* IPEEE Vulnerabilities Resolution Report (Section 7)* Peer Review (Section 8)Section 1.0 -Introduction 1-1 Monticello Nuclear Generating Plant Seismic Walkdown Report 2 Seismic Licensing Basis 2.1 OVERVIEW This section of the report summarizes the seismic licensing basis for the Monticello Nuclear Generating Plant. The safe shutdown earthquake and a summary of the codes, standards, and methods used in the design of Seismic Category I structures, systems, and components (SSC) are presented.

This section does not establish or change the seismic licensing basis of the facility and is intended to provide a fundamental understanding of the seismic licensing basis of the facility.2.2 SAFE SHUTDOWN EARTHQUAKE (SSE)The maximum horizontal ground acceleration at the foundation level is 0.12g for the safe shutdown earthquake (SSE). (Reference 2, Section 1.3.1.6) The vertical acceleration is 0.08g for the SSE. (Reference 2, Section 12.2.2.9)2.3 DESIGN OF SEISMIC CATEGORY I SSCS A full description of the SSE along with the codes, standards, and methods used in the design of the Seismic Category I SSCs for meeting the seismic licensing basis requirements is provided in the following MNGP Updated Safety Analysis Report (USAR) (Reference

2) sections: " USAR Section 1.3.1.6, Seismology and Design Response Spectra" USAR Section 2.5, Geology and Soil Investigation

• USAR Section 2.6, Seismology
• USAR Section 7.10, Seismic and Transient Performance Instrumentation Systems* USAR Section 12.2, Plant Principal Structures and Foundations
• USAR Appendix A, Seismic Design Criteria* USAR Appendix F, Containment Vessel Design Summary Design These USAR sections should be referred to for a detailed understanding of the seismic licensing basis.Section 2.0 -Seismic Licensing Basis 2-1 Monticello Nuclear Generating Plant Seismic Walkdown Report 2.3.1 Summary of Seismic Design for Class I SSCs The seismic design for critical structures and equipment for this plant is based on dynamic analysis of acceleration or velocity response spectrum curves which are based on a horizontal ground acceleration of 0.06 g (Reference 2, Section 1.3.1.6).The natural periods of vibration are calculated for buildings and equipment which are vital to the safety of the plant. Damping factors are based upon the materials and methods of construction used. Earthquake design is based on ordinary allowable stress as set forth in the applicable codes and is very conservative because the usual one-third increase in allowable working stresses due to loadings from the operating basis earthquake is not used. As an additional requirement, the design is such that a safe shutdown can be made following a safe shutdown earthquake assuming a horizontal ground acceleration of 0.12 g (Reference 2, Section 1.3.1.6).The 0.12 g design criteria are for critical items only; that is, for Class I items. (Reference 2, Section 1.3.1.6) For the design of Class I structures and equipment the maximum horizontal acceleration and the maximum vertical acceleration were considered simultaneously.

Where applicable, the resulting seismic stresses for the two motions-were-combined linearly (Reference -2,Section 12.2:.1:9). All Class-I structures and equipment were analyzed to assure that a safe shutdown can be made during horizontal ground accelerations of 0.06 g (operating basis earthquake) and 0.12 g (design basis or maximum earthquake) (Reference 2, Section 12.2.1.4. Seismic loads were based upon the seismic investigation and data developed by John A. Blume & Associates, Engineers. The design earthquake established for this site is the North 690 West Component of the 1952 Taft earthquake, normalized to a maximum ground acceleration of 0.06 gravity (Reference 2, Section 12.2.1.9). 2.3.2 Methods of Analysis for Class 1 SSCs A. Equipment All rigid Class I equipment was analyzed using accelerations derived from the results of the analysis for the supporting structure at the appropriate elevation. Amplification factors were applied for the seismic analysis of non-rigidly mounted equipment. Typical amplification factors were 2.7 for the Reactor Pressure Vessel and 1.5 for the Recirculating Pump. The amplification factors were determined by using the results of the dynamic analysis; i.e., referring to Sheet No. 4, Earthquake Analysis, Reactor Pressure Vessel, in USAR Appendix A of Reference 2, the maximum acceleration of the top of the reactor vessel is 0.16 g, since ground acceleration is 0.06 g, the amplification factor is 2.7. The other amplification factors were calculated in a similar manner.(Reference 2, Section 12.2.1.9)B. Piping Class I piping seismic analyses were performed for both operating basis and design basis (maximum) earthquakes as follows:.Mode superposition using a floor response spectra.Section 2.0 -Seismic Licensing Basis 2-2 Monticello Nuclear Generating Plant Seismic Walkdown Report A static analysis was made using conservative static seismic coefficients. These static coefficients were determined in the following manner: 1. Horizontal static coefficients were determined by using the average of the peak values from the unsmoothed ground spectral curve of the normalized earthquake.

2. This average acceleration was then multiplied by the ratio of the building response acceleration at the installed elevation of the piping to maximum ground acceleration.

• A vertical coefficient was taken at a constant value equal to two-thirds of the maximum base ground acceleration or 0.04 g.For the response spectrum analysis of piping systems, the floor spectra near the points of pipe lateral restraint were considered.

The spectrum usually selected to be used in the analysis was the one located nearest the point of lateral support of the majority of the mass of the pipe. For the recirculation lines, the spectrum used was the one occurring just above the elevation of the header, or about half way between the upper and lower elevation of the pipe. Most of the seismic restraints fall below this elevation, and the-selection of the-point was considered to-be-realistic-for the seismic-analysis. When a static analysis was made, all piping systems above the 935 foot elevation used a horizontal static coefficient, 0.82g, and below this elevation a value of 0.53g was used.These values represent an amplification factor of 13 and 9, respectively (Reference 2, Section 12.2.1.10). C. Devices All types of Class I devices (relays, switches, amplifiers, power supplies, sensors, etc.)which make up the Class I systems were tested for proper performance under the simulated seismic accelerations of the Design Basis Earthquake. Each device tested is energized and, as applicable, has a simulated input signal applied; and has its output monitored during and after the test. (Reference 2, Section 7.10.1.4)D. Racks and Panels Class I racks and panels complete with all internal wiring and devices mounted were vibrated at low accelerations over the DBE frequency range and measurements made to determine the presence of resonances. If resonances were present which affect Class I devices, steps were taken to shift their frequencies out of the band of interest or dampen them to an acceptable level. Once this was accomplished, the panel can be considered a rigid body and analyzed statically. (Reference 2, Section 7.10.1.4)Addition of new systems or re-evaluation of existing systems is done using current methods of analysis and component qualification. See Section 12.2.1.10 of Reference 2.2.3.3 Summary of Codes and Standards This section summarizes the codes, specifications, standards of practice, and other accepted industry guidelines, which are adopted to the extent applicable, in the design and construction of the Seismic Category I SSCs for meeting the plant-specific seismic Section 2.0 -Seismic Licensing Basis 2-3 Monticello Nuclear Generating Plant Seismic Walkdown Report licensing basis requirements. All of the applicable codes, standards, and specifications for Seismic Category I SSCs are listed in Table 2-1 below. These codes, standards, and specifications are also described in MNGP USAR Section 12.2.,,Table 2-1: List of Codes ,Standards, and Specifications Specification or Standard Title.~~Title :, Designation American Concrete Institute Building Code Requirements for Reinforced (ACI)-318 Concrete American Institute of Steel Specification for the Design, Fabrication and Construction (AISC) Erection of Structural Steel for Buildings -Sixth Edition American Welding Society Standard Code for Arc and Gas Welding in Building (AWS) D1.0 Construction American Society of Mechanical Boiler & Pressure Vessel Code, Section III, VIII, IX, Engineers (ASME) and X I American Petroleum Institute, Recommended Rules for Design and Construction of Specification No. 620 Large, Welded, Low Pressure Storage Tanks ACI 505-54 Specification for the Design and Construction of Reinforced Concrete Chimneys USA Standard Code for Power Piping Pressure Piping, USAS B31.1.0 -1967 American National Standard Power Piping Code, ANSI B31.1 -1977 American Society of Civil Wind Forces on Structures Engineers (ASCE) Transactions, Paper 3269 Section 2.0 -Seismic Licensing Basis 2-4 Monticello Nuclear Generating Plant Seismic Walkdown Report 3 Personnel Qualifications 3.1 OVERVIEW This section of the report identifies the personnel that participated in the NTTF Recommendation 2.3 Seismic Walkdown efforts. This section also describes the qualifications of these personnel. A description of the responsibilities and minimum qualifications of each Seismic Walkdown participant's role(s) is provided in Section 2, Personnel Qualifications, of Reference 1.3.2 WALKDOWN PERSONNEL Table 3-1 below summarizes the names and corresponding roles of personnel who participated in the NTTF Recommendation 2.3 Seismic Walkdown effort.Table 3-1:P1ersonnel Roles Seismic Licensing Name Equipment Plant Walikdown Basis IPEEE Peer Selection operations Engineer Reviewer Reviewer Reviewer (SWE)B. Lory X X W. Djordjevic X D. Zercher X** X S. Kaas X S. Luckiesh X J. Kindred X X*R. Walstrom X X T. Parker X X D. Moore X reer Review I earn Leader.**No licensing basis evaluations were performed. Section 3.0 -Personnel Qualifications 3-1 Monticello Nuclear Generating Plant Seismic Walkdown Report 3.3 PERSONNEL QUALIFICATIONS Summarized below are the qualifications for the personnel who participated in the NTTF Recommendation 2.3 Seismic Walkdown efforts. The personnel qualifications include applicable seismic training, education, and professional experience. Bruce M. Lory" Activities Performed: Equipment Selection, SWE" Seismic Training Completed: Instructor for the Fundamentals of Equipment Seismic Qualification Training and EPRI NTTF Recommendation 2.3 -Plant Seismic Walkdowns Training" Education: Bachelors of Science in Mechanical Engineering from the State University of New York at Buffalo Professional Experience: 30+ years experience in the commercial nuclear industry.Worked 18+ years in Seismic Qualification of equipment and components, and 15+ years of Environmental Qualification experience, in consulting services and in utility positions. Currently works as a senior consultant for Stevenson and Associates with specialization in Seismic and Environmental Qualification, as well as Single Failure-Proof crane design verification. Walter (Wally) Diordievic" Activities Performed: SWE" Seismic Training Completed: EPRI SQUG training and EPRI NTTF Recommendation 2.3-Plant Seismic Walkdowns Training" Education: Masters of Science in Structural Engineering from the Massachusetts Institute of Technology" Professional Experience: 37+ years of seismic experience serving the nuclear industry.Managed and led seismic walkdowns and fragility analyses of structures and components for use in probabilistic risk assessments. Performed more than twenty USI A-46 and IPEEE projects in response to the requirements of Generic Letters 87-02 and 88-20.Currently works as a senior Consultant and serves as President of Stevenson and Associates with specialization in the dynamic analysis and design of structures and equipment for seismic, blast, fluid, and wind loads.Dennis Zercher" Activities Performed: Licensing Basis Reviewer, Peer Reviewer" Seismic Training Completed: EPRI SQUG Training and Seismic Evaluation Training Course" Education: Bachelors of Science in Civil Engineering from Michigan Technological University Section 3.0 -Personnel Qualifications 3-2 Monticello Nuclear Generating Plant Seismic Walkdown Report Professional Experience: 28+ years of experience in the commercial nuclear industry. A registered Professional Engineer in Minnesota and Wisconsin. Worked as a Structural Engineer at FluiDyne Engineering and PaR Systems. Currently works at the MNGP as a Design Engineer.Steve Kaas" Activities Performed: SWE" Seismic Training Completed: EPRI NTTF Recommendation 2.3 -Plant Seismic Walkdowns Training" Education: Bachelors of Science in Civil Engineering from North Dakota State University" Professional Experience: A registered Professional Engineer in Minnesota, Iowa, and Michigan. Currently works as a Senior Civil Engineer at NSPM. President of Kaas Technical Services, Inc., Previously worked as Engineering Manager of Hanson Structural Precast, and a Field Engineer at Wells Concrete Products Company.Scott Luckiesh" Activities Performed: SWE" Seismic Training Completed: EPRI NTTF Recommendation 2.3 -Plant Seismic Walkdowns Training" Education: Bachelors of Science in Architectural Engineering from Oklahoma State University, and a Masters of Science in Structural Engineering from University of Texas -Austin.Professional Experience: A registered Professional Engineer in Minnesota, and was formerly a registered Professional Engineer in Wisconsin, Oklahoma, and Florida. 17+years of experience with structural engineering at various companies. Currently works as a Design Engineer for NSPM at MNGP, in the areas of external flooding and structural/seismic design.Jason Kindred" Activities Performed: Peer Reviewer, Plant Operations [ Seismic Training Completed: N/A[ Education: Bachelors of Science in Mechanical Engineering from University of Wisconsin-Madison" Professional Experience: 12+ years of experience in the commercial nuclear industry.Spent 11+ years in the United States Navy as a Naval Nuclear Officer. Started in the commercial nuclear industry at the MNGP. Obtained Senior Reactor Operator (SRO)license at the MNGP. Worked as a Shift Support Specialist, Control Room Supervisor, Operations Department Training Supervisor, Operations Shift Manager, and Operations Support Manager. Currently works as the Engineering Plant and Systems Manager at MNGP.Section 3.0 -Personnel Qualifications 3-3 Monticello Nuclear Generating Plant Seismic Walkdown Report Robert (Bob) Walstrom" Activities Performed: Equipment Selection, Plant Operations" Seismic Training Completed: N/A* Education: Bachelors of Science in Physics from Winona State University Professional Experience: 34+ years in Plant Operations at the MNGP. Maintained continuous active Reactor Operator (RO) or SRO license for 30 years. Worked as a non-licensed operator, a control room operator, shift supervisor and shift manager/shift technical advisor. Two years temporary assignment as Initial License Training class mentor/supervisor. Currently retired and supporting Fukushima lessons learned activities. Thomas (Tom) Parker" Activities Performed: Equipment Selection, Plant Operations" Seismic Training Completed: N/A" Education: Masters of Science in Nuclear Engineering from Iowa State University" Professional Experience: 34+ years of experience working in the nuclear industry. Spent four years in the United States Navy as a teacher at the Nuclear Power School. Started in the commercial nuclear industry at Zion nuclear plant. After five years at Zion nuclear plant, started working for NSPM and has spent the remainder of career with NSPM at the corporate offices and MNGP. Obtained SRO at the MNGP and was also an RO at the UTR-10 reactor at Iowa State University. Currently retired and supporting Fukushima lessons learned activities. David L. Moore" Activities Performed: IPEEE Reviewer" Seismic Training Completed: EPRI SQUG Training and Seismic Evaluation Training Course" Education: Bachelor of Science in Physics from University of Texas; Masters of Science in Civil/Structural Engineering from University of Washington" Professional Experience: 30+ years of seismic PRA and SMA experience for the nuclear industry and NRC. Manager, Systems Task Leader, or Peer Reviewer for over 30 seismic PRAs, SMAs, or USI A-46 assessments. Tasks included development of seismic success paths and seismic equipment lists, performance of seismic walkdowns, quantification of seismic CDF and LERF, and performance of uncertainty and sensitivity analyses.Currently works as a Consultant for several seismic PRA projects, including NRC sponsored research project on treatment of seismic correlation. Section 3.0 -Personnel Qualifications 3-4 Monticello Nuclear Generating Plant Seismic Walkdown Report 4 Selection of SSCs 4.1 OVERVIEW This section of the report describes the process used to select SSCs that were included in the Seismic Walkdown Equipment List (SWEL). The actual equipment lists that were developed in this process are found in Appendix A of this report and are as follows:* Table A-i, Monticello Base List 1* Table A-2, Monticello SWEL 1 4.2 SWEL DEVELOPMENT The selection of SSCs process described in EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012 (Reference 1), was utilized to develop the SWEL for the MNGP.The SWEL is comprised of two groups of items: " SWEL 1 is a sample of items required to safely shut down the reactor and maintain containment integrity.

• SWEL 2 is a list of spent fuel pool related items.4.2.1 SWEL 1 -Sample of Required Items for the Five Safety Functions The process for selecting a sample of SSCs for shutting down the reactor and maintaining containment integrity began with the safe shutdown equipment list (SSEL)utilized for the Seismic Qualification Utility Group (SQUG) effort completed as part of resolution of USI A-46 (Reference 12). The SQUG SSEL was then subjected to the following four screenings to identify the items to be included on the Seismic Walkdown Equipment List 1 (SWEL 1): 1. Screen #1 -Seismic Category 1 As described in Section 3 of Reference 1, Screen #1 narrows the scope of SSCs in the plant to those that are classified as Seismic Category (SC) I, because only such items have a defined seismic licensing basis against which to evaluate the as-installed configuration.

Each item on the MNGP SQUG equipment list was reviewed to determine if it had a defined seismic licensing basis. All items identified as Safety Class 1, as defined in Section 12 of the MNGP USAR (Reference 2), were identified as being SC I. Electrical enclosures containing Class 1 E devices were identified as SC 1.Section 4.0 -Selection of SSCs 4-1 Monticello Nuclear Generating Plant Seismic Walkdown Report 2. Screen #2 -Equipment or Systems As described in Section 3 of Reference 1, this screen narrowed the scope of items to include only those that do not regularly undergo inspections to confirm that their configuration is consistent with the plant licensing basis. This screen further reduced the SWEL 1 by screening out any Safety Related SC I structures, containment penetrations, SC I piping systems, cable/conduit raceways and HVAC ductwork.3. Screen #3 -Support for the 5 Safety Functions This screen narrowed the scope of items included on the SWEL 1 to only those associated with maintaining the following five safety functions: A. Reactor Reactivity Control B. Reactor Coolant Pressure Control C. Reactor Coolant Inventory Control D. Decay Heat Removal E. Containment Function These five safety functions were defined in Section 3 of Reference

1. The first four functions are associated with bringing the reactor to a safe shutdown condition.

The fifth function is associated with maintaining containment integrity. Utilizing the information in Appendix E of Reference 1, the safety function for each item on the SQUG SSEL was identified. Equipment that did not serve or support one of the five safety functions listed above were excluded from the SWEL 1. Plant Operations staff was involved with the development of SWEL 1, and identified additional systems not included on the SQUG SSEL which were associated with maintaining the five safety functions above. Based on the reviews by Plant Operations, equipment for the Standby Liquid Control, Primary Containment Hard Pipe Vent, Control Room Ventilation, and Emergency Filtration Train systems were added to SWEL 1. The results of this screen are provided in Appendix A of this report as Table A-1.4. Screen #4 -Sample Considerations This screen is intended to result in a SWEL 1 that sufficiently represents a broad population of plant Seismic Category 1 equipment and systems to meet the objectives of the NRC 10 CFR 50.54(f) Letter (Reference 6). The final SWEL 1 for MNGP is presented in Appendix A of this report as Table A-2. The following attributes were considered in the selection process for items included on SWEL 1: A. A variety of types of systems Section 4.0 -Selection of SSCs 4-2 Monticello Nuclear Generating Plant Seismic Walkdown Report The system is identified for each item on SWEL 1. The equipment included on SWEL 1 is a representative sample of 29 systems in the plant that perform one or multiple safety functions. B. Major new and replacement equipment The equipment included on SWEL 1 includes several items that have been modified or replaced over the past several years. Each item on SWEL 1 that is new or replaced is identified. C. A variety of types of equipment The equipment class is identified for each item on SWEL 1. The equipment included on SWEL 1 is a representative sample from 19 of the 21 classes of equipment listed in Appendix B, Classes of Equipment, of Reference

1. Where appropriate, at least one piece of equipment from each class is included on SWEL 1.Screens #1, #2, and #3 resulted in no equipment in equipment class number 13 for motor generators and class number 2 for low voltage switchgear and breaker panels. There were no motor generators in the plant which performed one of the five safety functions defined in Reference

1. As for the low voltage switchgear, no planned out-of-service is scheduled in the next refueling outage for Class I load centers to allow inspection.

D. A variety of environments The equipment included on SWEL 1 is a representative sample from a variety of environments (locations) in the station. To ensure an adequate sampling of equipment was selected to represent the Reactor Core Isolation Cooling (RCIC), and High Pressure Coolant Injection (HPCI) systems, additional equipment from these systems was added to the SWEL 1.Equipment was also reviewed for accessibility. Equipment that is inaccessible without the use of scaffolding or portable ladders was excluded from SWEL 1.Also, equipment located in high radiation areas was also excluded from SWEL 1 with the exception of three components in the Steam Chase and the Dry Well. These items are listed in Table D-1 in Appendix D of this report, and will be walked down during a refueling outage.E. Equipment enhanced due to vulnerabilities identified during the IPEEE program The equipment included on SWEL I includes items that were enhanced as a result of the IPEEE program. Each item on SWEL 1 that was enhanced to correct a vulnerability from IPEEE is identified. F. Contribution to risk To determine the relative risk significance of equipment for inclusion on SWEL 1, the Risk Achievement Worth (RAW) and Fussell-Vesely importance Section 4.0 -Selection of SSCs 4-3 Monticello Nuclear Generating Plant Seismic Walkdown Report from the internal plant Probabilistic Risk Assessment (PRA) models were used to create a list of the top forty risk-significant components. Initiating events, maintenance events and human error events were not considered in the generation of this list.In selecting equipment for SWEL 1 that met the above attributes, the equipment in the draft SWEL 1 had to first pass through Screens 1 through 4 before being assessed for being risk significant. Then risk significant equipment was identified based on the above criteria, and a subset of the more risk-significant equipment was selected to be on the final SWEL 1.Additionally, the list of risk-significant equipment from internal plant PRA was compared with the draft SWEL 1 to confirm that a reasonable sample of risk-significant equipment (relevant for a seismic event) was included on SWEL 1.4.2.2 SWEL 2 -Spent Fuel Pool Related Items The process for selecting a sample of SSCs associated with the spent fuel pool (SFP)began with a review of the station design and licensing basis documentation for the SFP and the interconnecting SFP cooling system. The following four screens narrowed the scope of SSCs to be included on the second Seismic Walkdown Equipment List (SWEL 2): 1. Screen #1 -Seismic Category I Only those items identified as Class 1 (SC I) are to be included on SWEL 2 with exception to the SFP structure. As described in Reference 1, the adequacy of the SFP structure is assessed by analysis as a SC 1 structure. Therefore, the SFP structure is assumed to be seismically adequate for the purposes of this program and is not included in the scope of items included on SWEL 2. Within the SFP system, MNGP identified several manual valves and check valves classified as Class 1 equipment.

2. Screen #2 -Equipment or Systems This screen considers only those items associated with the SFP that are appropriate for an equipment walkdown process. Appendix B of Reference 1 lists the classes of equipment that are appropriate for the equipment walkdown process.All of the Class 1 SFP equipment identified in Screen #1 was determined not to be suitable for the seismic walkdown process. The equipment identified in Screen #1 included manual valves and check valves which are not listed as classes of equipment appropriate for the walkdowns in the EPRI Report (Reference 1).3. Screen #3 -Sample Considerations This screen is similar to Screen #4 used for SWEL 1. It represents a process that is intended to result in a SWEL 2 that sufficiently represents a broad population of SFP Seismic Category 1 equipment and systems to meet the objectives of the NRC 10 CFR 50.54(f) Letter. All of the Class 1 equipment identified for the SFP was determined not to be appropriate for an equipment walkdown process in Screen #2.Therefore, Screen #3 was not necessary for MNGP.Section 4.0 -Selection of SSCs 4-4 Monticello Nuclear Generating Plant Seismic Walkdown Report 4. Screen #4- Rapid Drain-Down This screen identifies items that could allow the spent fuel pool to drain rapidly.Consistent with Reference 1, the scope of items included in this screen is limited to the hydraulic lines connected to the SFP and the equipment connected to those lines. For the purposes of this program it is assumed the SFP gates are installed and the SFP cooling system is in its normal alignment for power operations.

The SFP gates are passive devices that are integral to the SFP. As such, they are considered capable of withstanding a design basis earthquake without failure and do not allow for a rapid drain-down of the SFP.The SSCs identified in this screen are not limited to Class 1 (SC I) items, but is limited to those items that could allow rapid drain-down of the SFP. Rapid drain-down is defined as lowering of the water level to the top of the fuel assemblies within 72 hours after the earthquake. The design and licensing basis for the SFP and its cooling system was reviewed, and it was determined that there are no penetrations below ten feet above the top of the fuel assemblies in the SFP. Additionally, the spent fuel storage pool has been designed to withstand earthquake loadings as a Class I structure. It is a reinforced concrete structure, completely lined with seam-welded, stainless steel plates welded to reinforcing members (channels, I-beams, etc.) embedded in concrete.The stainless steel liner prevents leakage even in the event the concrete develops cracks. To avoid unintentional draining of the pool, there are no penetrations that would permit the pool to be drained below a safe storage level and all lines extending below this level are equipped with valving to prevent syphon backflow.The passage between the spent fuel storage pool and the refueling cavity above the reactor vessel is provided with two double-sealed gates with a monitored drain between the gates (Reference 2, Section 10.2.1.2). Therefore, no items which could rapidly drain-down the SFP were included on SWEL 2 for MNGP.4.2.3 SWEL 2 Development Conclusion MNGP identified several manual valves and check valves within the SFP system that are classified as Class 1 equipment. However, these components are not listed in Reference 1 as classes of equipment appropriate for the walkdowns. Additionally, there are no penetrations below ten feet above the top of the fuel assemblies in the SFP which could rapidly drain-down the SFP. Therefore, no items were identified for SWEL 2 for the Monticello Nuclear Generating Plant.Section 4.0 -Selection of SSCs 4-5 Monticello Nuclear Generating Plant Seismic Walkdown Report 5 Seismic Walkdowns and Area Walk-Bys 5.1 OVERVIEW Seismic Walkdowns and Area Walk-Bys were conducted by two 2-person teams of trained Seismic Walkdown Engineers (SWE), in accordance with Reference

1. The Seismic Walkdowns and Area Walk-Bys are discussed in more detail in the following sections.Consistent with Section 4, Seismic Walkdowns and Area Walk-Bys, of Reference 1 the SWEs used their engineering judgment, based on their experience and training, to identify potentially adverse seismic conditions.

Where needed, the engineers were provided the latitude to rely upon new or existing analyses to inform their judgment.The SWEs conducted the Seismic Walkdowns and Area Walk-Bys together as a team, in accordance with Reference

1. During these evaluations, the SWEs actively discussed their observations and judgments with each other. The results of the Seismic Walkdowns and Area Walk-Bys reported herein are based on the comprehensive and consensus agreement of the SWEs.5.2 SEISMIC WALKDOWNS The Seismic Walkdowns focused on the seismic adequacy of the items in SWEL 1, provided in Table A-2 of Appendix A in this report. The Seismic Walkdowns also evaluated the potential for nearby SSCs to cause adverse seismic interactions with the SWEL items. The seismic walkdown teams focused on the following adverse seismic conditions associated with the subject item of equipment:

• Adverse anchorage conditions
• Adverse seismic spatial interactions
• Other adverse seismic conditions The results of the seismic walkdowns have been documented on the Seismic Walkdown Checklists (SWCs) and Area Walkby Checklists (AWCs) provided in Appendix C, Checklists, of Reference

1. Seismic Walkdowns were performed and a SWC completed for 78 of the 100 equipment identified on the MNGP SWEL 1. The completed SWCs for MNGP are provided in Appendix B of this report. Additionally, photos have been included with most SWCs to provide a visual record of the item along with any comments noted on the SWC. Drawings and other plant records are cited in some of the SWCs, but are not included with the SWCs because they are readily retrievable documents through the station's document management system.Section 5.0 -Seismic Walkdowns and Area Walk-Bys 5-1 Monticello Nuclear Generating Plant Seismic Walkdown Report Seismic Walkdowns are deferred for the remaining 22 items to a refueling outage or appropriate time when the equipment is accessible.

These items could not be walked down during the 180 day period following the NRC's endorsement of the EPRI Report (Reference

1) due to being inaccessible.

Inaccessibility of this equipment was either based on the location of the equipment or due to the electrical safety hazards posed while the equipment is energized. Appendix D of this report identifies the inaccessible or deferred equipment, along with the plan for future Seismic Walkdowns. The following subsections describe the approach followed by the SWEs to identify potentially adverse anchorage conditions, adverse seismic interactions, and other adverse seismic conditions during the Seismic Walkdowns. 5.2.1 Adverse Anchorage Conditions Guidance for identifying anchorage that could be degraded, non-conforming, or unanalyzed relied on visual inspections of the anchorage and verification of anchorage configuration. Details for these two types of evaluations are provided in the following two subsections. The evaluation of potentially adverse anchorage conditions described in this subsection applies to the anchorage connections that attach the identified item of equipment to the civil structure on which it is mounted. For example, the welded connections that secure the base of a Motor Control Center (MCC) to the concrete floor would be evaluated in this subsection. Evaluation of the connections that secure components within the MCC is covered later in the subsection "Other Adverse Seismic Conditions." Visual Inspections The purpose of the visual inspections was to identify whether any of the following potentially adverse anchorage conditions were present:* Bent, broken, missing, or loose hardware* Corrosion that is more than mild surface oxidation* Visible cracks in the concrete near the anchors* Other potentially adverse seismic conditions Based on the results of the visual inspection, the SWEs judged whether the anchorage was potentially degraded, non-conforming, or unanalyzed. The results of the visual inspection were documented on the SWC, as appropriate. If there was clearly no evidence of degraded, nonconforming, or unanalyzed conditions, then it was indicated on the checklist. However, if it was not possible to judge whether the anchorage was degraded, nonconforming, or unanalyzed, then the condition was evaluated and entered into the Corrective Action Program if it was determined to be a potentially adverse seismic condition. 5.2.2 Configuration Verification In addition to the visual inspections of the anchorage as described above, the configuration of the installed anchorage was verified to be consistent with existing plant Section 5.0 -Seismic Walkdowns and Area Walk-Bys 5-2 Monticello Nuclear Generating Plant Seismic Walkdown Report documentation for at least 50% of the items on the SWEL, per the guidance in Section 4 of Reference 1.Line-mounted equipment (e.g., valves mounted on pipelines without separate anchorage) were not evaluated for anchorage adequacy and were not counted in establishing the 50% sample size, per the guidance in Section 4 of Reference 1.Examples of documentation that were considered to verify that the anchorage installation configurations were consistent with the plant documentation include the following: " Design drawings" IPEEE or USI A-46 program documentation, as applicable The Table B-1 in Appendix B documents which SWCs had anchorage confirmation performed. Table B-1 in Appendix B documents which SWCs had anchorage confirmation performed. Additionally, Table 5-1 below shows the final count of the 50% anchorage configuration verifications. Table 5-1: Anchorage Configuration Verification No. of SWEL Line-Mounted Required to Anchorages SWEL Items Items Verify? Verified (A) '(B) (A-B)/2 1 100 18 41 44 (37 completed and 7 deferred)5.2.3 Adverse Seismic Spatial Interactions An adverse seismic spatial interaction is the physical interaction between the SWEL item and a nearby SSC caused by relative motion between the two during an earthquake. An inspection was performed in the area adjacent to and surrounding the SWEL item to identify any seismic interaction conditions that could adversely affect the capability of that SWEL item to perform its intended safety-related functions. The three types of seismic spatial interaction effects that were considered are as follows:* Proximity" Failure and falling of SSCs" Flexibility of attached lines and cables Detailed guidance for evaluating each of these types of seismic spatial interactions is described in Appendix D, Seismic Spatial Interaction, of Reference 1.The Seismic Walkdown Engineers exercised their judgment to identify seismic interaction hazards. Section 5.2.5 provides a summary of issues identified during the Seismic Walkdowns. Section 5.0 -Seismic Walkdowns and Area Walk-Bys 5-3 Monticello Nuclear Generating Plant Seismic Walkdown Report 5.2.4 Other Adverse Seismic Conditions In addition to adverse anchorage conditions and adverse seismic interactions, described above, other potentially adverse seismic conditions that could challenge the seismic adequacy of a SWEL item could have been present. Examples of the types of conditions that could pose potentially adverse seismic conditions include the following:

• Degraded conditions
• Loose or missing fasteners that secure internal or external components to equipment* Large, heavy components mounted on a cabinet that are not typically included by the original equipment manufacturer
• Cabinet doors or panels that are not latched or fastened* Other adverse conditions In September 2012, a revised position from the NRC Staff in regards to Seismic Walkdowns of electrical cabinets or panels was sent to all licensees by the Nuclear Energy Institute (NEI). In this document from NEI, it was communicated that it is expected that all electrical cabinets on the SWEL that can be reasonably opened without undue safety or operational hazard will be opened during the walkdown, whether or not it is necessary to look inside to check the anchorages.

The NRC Staff described the visual inspection that should be made while viewing the interior of the cabinet through the door opening as including the following checks:* Visually check whether there is evidence that internal components are not adequately secured to the cabinet,* Check whether fasteners that secure adjacent cabinets together are in place, if such fasteners are needed to prevent potentially adverse seismic interaction between the cabinets, and" Look for "Other Adverse Seismic Conditions," as described on page 4-4 of the Seismic Walkdown Guidance.Due to the timing of this communication, MNGP did not complete this internal inspection of all electrical cabinets or panels. Some inspections were deferred to a future refueling outage or an appropriate time when the equipment is accessible. The electrical cabinets and panels which still need to be internally inspected are identified in Table D-1 of Appendix D of this report. The SWCs for the equipment identified in Table D-1 that cannot be opened for internal inspections will be revised at the time of the supplemental walkdowns to indicate the results of these internal inspections. Any other adverse seismic conditions that were identified during the Seismic Walkdowns are documented on the items' SWCs in Appendix B and Table 5-2, as applicable. 5.2.5 Issues Identified during Seismic Walkdowns Table 5-2 at the end of this section provides a summary of issues identified during the equipment Seismic Walkdowns. The equipment Seismic Walkdowns resulted with a total of nine concerns identified and each of these concerns was entered into the station's CAP. All of the identified concerns were assessed for operability and it was concluded that the issue would not prevent the associated equipment from performing its safety-related function(s). The issues identified were predominantly associated with seismic Section 5.0 -Seismic Walkdowns and Area Walk-Bys 5-4 Monticello Nuclear Generating Plant Seismic Walkdown Report interaction and plant drawing discrepancies. None of the concerns identified by the SWEs during the equipment Seismic Walkdowns were judged to be potentially adverse seismic conditions that could affect the safety-related functions of equipment. 5.3 AREA WALK-BYS The purpose of the Area Walk-Bys is to identify potentially adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL items. Vicinity is generally defined as the room containing the SWEL item. If the room is very large (e.g., Turbine Hall), then the vicinity is identified based on judgment, e.g., on the order of about 35 feet from the SWEL item. This vicinity is described on the Area Walk-By Checklist (AWC), provided in Appendix C of this report. A total of 36 Area Walk-bys were performed for MNGP.The key examination factors that were considered during Area Walk-Bys include the following:

• Anchorage conditions (if visible without opening equipment)
• Significantly degraded equipment in the area* A visual assessment (from the floor) of cable/conduit raceways and HVAC ducting (e.g., condition of supports or fill conditions of cable trays)* Potentially adverse seismic interactions including those that could cause flooding, spray, and fires in the area* Other housekeeping items that could cause adverse seismic interaction (including temporary installations and equipment storage)" Scaffold construction was inspected to meet site procedure (Reference 7).* Seismic housekeeping was examined to meet site procedure (Reference 8).The Area Walk-Bys are intended to identify adverse seismic conditions that are readily identified by visual inspection, without necessarily stopping to open cabinets or taking an extended look. If a potentially adverse seismic condition was identified during the Area Walk-By, then additional time was taken, as necessary, to evaluate adequately whether there was an adverse condition and to document any findings.The results of the Area Walk-Bys are documented on the AWCs included in Appendix C of this report. A separate AWC was filled out for each area inspected.

A single AWC was completed for areas where more than one SWEL item was located.Additional details for evaluating the potential for adverse seismic interactions that could cause flooding, spray, or fire in the area are provided in the following two subsections. 5.3.1 Seismically-Induced Flooding/Spray Interactions Seismically-induced flooding/spray interactions are the effect of possible ruptures of vessels or piping systems that could spray, flood or cascade water into the area where SWEL items are located. This type of seismic interaction was considered during the IPEEE program. Those prior evaluations were considered, as applicable, as information for the Area Walk-Bys.Section 5.0 -Seismic Walkdowns and Area Walk-Bys 5-5 Monticello Nuclear Generating Plant Seismic Walkdown Report Examples where seismically-induced flooding/spray interactions could occur include the following:

• Fire protection piping with inadequate clearance around fusible-link sprinkler heads* Non-ductile mechanical and threaded piping couplings can fail and lead to flooding or spray of equipment* Long, unsupported spans of threaded fire protection piping* Flexible headers with stiffly supported branch lines* Non-Seismic Category I tanks The SWEs exercised their judgment to identify only those seismically-induced interactions that could lead to flooding or spray. Any seismically-induced flooding/spray interactions that were identified during the Area Walk-bys are documented on the AWCs in Appendix C and Table 5-3 below, as applicable.

5.3.2 Seismically-Induced Fire Interactions Seismically-induced fire interactions can occur when equipment or systems containing hazardous/flammable material fail or rupture. This type of seismic interaction was considered during the IPEEE program. Those prior evaluations were considered, as applicable, as information for the Area Walk-Bys.Examples where seismically-induced fire interactions could occur include the following:

• Hazardous/flammable material stored in inadequately anchored drums, inadequately anchored shelves, or unlocked cabinets* Natural gas lines and their attachment to equipment or buildings* Bottles containing acetylene or similar flammable chemicals* Hydrogen lines and bottles Another example where seismically-induced fire interaction could occur is when there is relative motion between a high voltage item of equipment (e.g., 4160 volt transformer) and an adjacent support structure when they have different foundations.

This relative motion can cause high voltage busbars, which pass between the two, to short out against the grounded bus duct surrounding the busbars and cause a fire.The Seismic Walkdown Engineers exercised their judgment to identify only those seismically-induced interactions that could lead to fires. Any seismically-induced fire interactions that were identified during the Area Walk-bys are documented on the AWCs in Appendix C and Table 5-3 below, as applicable. 5.3.3 Issues Identified during Area Walk-bys In total, 16 issues were identified during the Area Walk-Bys and entered into the site's CAP. Table 5-3 at the end of this section provides a summary of the issues identified during the Area Walk-Bys. All of the identified concerns were assessed for operability and it was concluded that the issue would not prevent the associated equipment from performing its safety-related function(s). None of the concerns identified by the SWEs during the Area Walk-Bys were judged to be potentially adverse seismic conditions that could affect the safety-related functions of equipment in the area.Section 5.0 -Seismic Walkdowns and Area Walk-Bys 5-6 Monticello Nuclear Generating Plant Seismic Walkdown Report Table 5-2: CAP Status for SWCs Equipment Description of Issue CAP Status ID AO-4539 SWE's noted 2G4007 conduit used as anchor 1346939 This condition was determined not point to tie other power cables using tie to be an adverse condition, wraps. Also noted electrical tape used to hold however, WR 83827 was written to up power cables at connection point on valve, re-support the cable for AO-4539.CRD HCU W CST line is in contact with CRD structural 1259196 This condition was identified in CAP column. WR 62289 was initiated as part of 1259196. This is being addressed in CAP 1259196 to address rubbing. the work order process under WR 62289 and WO 417791. It is not an adverse seismic concern.D31 Plant drawing inaccurate with installation of 1350165 The anchorage configuration was anchors. SEWS evaluation on anchors uses determined to be acceptable as correct "as found" configuration. found. The plant drawings are being revised to match the anchorage configuration. D31 Plant drawing inaccurate with installation of 1346890 The anchorage configuration was anchors. SEWS evaluation on anchors uses determined to be acceptable as correct "as found" configuration. found. The plant drawings are being revised to match the anchorage configuration. P-203A Tall scaffold is constructed above the pump. 1347002 The engineer responsible for Verify the seismic assessment of this scaffolding evaluations reviewed the scaffold. scaffold and determined it was adequately braced to prevent sliding and overturning during a seismic event.P-209 There are eight 1" CIP anchor bolts per NX- 1346272 The anchorage configuration was 8292-43 while the walkdown only found six 1" determined to be acceptable as CIP anchor bolts. found. The plant drawings are being revised to match the anchorage configuration. T-200 There is a discrepancy between Drawing 1347243 The anchorage configuration was NX7879-8-1 and what is installed in the plant. determined to be acceptable as found. The plant drawings are being revised to match the anchorage configuration. T-200 Verify the seismic assessment for the scaffold 1347002 The engineer responsible for near tank. scaffolding evaluations reviewed the scaffold and determined it was adequately braced to prevent sliding and overturning during a seismic event.Section 5.0 -Seismic Walkdowns and Area Walk-Bys 5-7 Monticello Nuclear Generating Plant Seismic Walkdown Report Table 5-2: CAP Status for SWCs 7Equipment Description of Issue CAP Status ID V-SF-9 Drawing NX-9290-3 anchor bolt configuration 1345975 As documented in the SEWs, there does not match field. Bolt pattern does match is no seismic concern, however, the 1995 SEWS. drawing will be updated to reflect field conditions. Table 5-3: C~AP Status Vfor AWCs Area Description of Issue CAP S~tatus Walk-by~ýDesignation 2 Fire station contains victaulic couplings. Station is 1346922 This line was determined to bolted to wall. FP line runs up to roof of this floor and be adequately supported. into the floor. No sign of lateral bracing. Three There is no seismic victaulic couplings are spaced closely together. Is concern.this line adequate for seismic loads? Line is charged with water. Line is also in contact with conduit N43158 and in contact with HVAC duct support.(SWEs could not see lateral support above for FP line).7 In the Intake Structure, Sodium Hypochlorite residue 1346885 This issue is being was found on valve SHC-28 as well as from the addressed by the work ceiling, indicating a leak. managementprocess. It is not a seismic concern.10 Cable tray MP404 & MP403 appears to be in contact 1345963 This issue has been with C-27. previously analyzed and was determined not to be a seismic issue.12 In the "A" RHR room, South wall, No. 11 RHR pump 1346654 This condition is being seal cooling water supply (RBCCW), line support, addressed by the work there is a U-bolt that is missing a nut and the other management process. It is nut is not fully engaged. On a second support, one not an adverse seismic nut is not fully engaged and the other nut is partially concern.missing.12 Vertical tube support (3") has two anchor bolts into 1346643 This condition is being the floor. Nuts are not tight to the base plates. addressed in the work Located next to RHR-18-1 handwheel. management process. It is not an adverse seismic concern.Section 5.0 -Seismic Walkdowns and Area Walk-Bys 5-8 Monticello Nuclear Generating Plant Seismic Walkdown Report Table 5-3: CAP Status for AWCs Area Description of Issue CAP Status Walkby Designation 14 Also compressed bottle on cart is within a few inches 1346030 Plant operations moved the of MCC-312. Wheels are locked. Does this meet cart to comply with station house keeping procedure? housekeeping procedures. It is not a seismic concern.15 Reddish deposit noted on one of two anchor bolts on 1346642 The bolts were cleaned vertical support of structural angle supporting two under WR 82134 and found pipelines. The lines are 1" diameter connecting SV- to be in good condition. It is 2849 to contaminated drain line and RCIC -(14) (2" not a seismic concern.diameter line) -"To RCIC pump suction". SWE's cannot judge condition of one anchor bolt that is covered over with corrosion deposits. Other anchor bolt is not corroded.19 Tie wrap used to anchor electrical cable to conduit 1346939 This condition was 2G401 0. determined not to be a condition adverse to quality and it is not a seismic concern. WR 83827 was initiated to re-support the extra cable length for AO-4539.20 Cable ties are fastening a flexible conduit to a cable 1346170 This condition was tray support. determined not to be a condition adverse to quality and it is not a seismic concern.25 At the SBLC pump and tank area, there is a large 1347002 The engineer responsible amount of scaffolding, some of which is one level for scaffolding evaluations (-7' high), some of which has two levels (-14' high). reviewed the scaffold and Are the lateral attachments and overturning determined it was restraints adequate to achieve 2 over 1? adequately braced to prevent sliding and overturning during a seismic event.27 Hoist is resting on LC-101 480V Load Center. It also 1349068 It was determined not to be poses an impact hazard, and has open s-hooks. an adverse seismic condition. 27 Fire extinguisher near non safety 4.16kV 4kVB-06 1349068 It was determined not to be cubicle is an interaction hazard as it can fall off hook. an adverse seismic condition.. Section 5.0 -Seismic Walkdowns and Area Walk-Bys 5-9 Monticello Nuclear Generating Plant Seismic Walkdown Report Table 5-3: CAP Status for AWCs Area Description of Issue CAP" Status Walk-by~Designation 27 Hoist restraint on non-essential LC-109 should be 1349068 It was determined not to be replaced with a restraint more appropriate than wire. an adverse seismic condition. 28 Lighting is pendant-hung and can swing into MCC- 1349068 It was determined not to be 133B. Cable trays are supported by strut systems an adverse seismic which are adequate. condition. 28 Pendant light is an interaction hazard to conduit 1349068 It was determined not to be connected to MCC-1 33A. an adverse seismic condition. 31 FP line is in contact with DO fuel line. 1345971 This condition was found to be acceptable as any potential failures would not have any negative impact on the ability of the plant to safely shutdown.Section 5.0 -Seismic Walkdowns and Area Walk-Bys 5-10 Monticello Nuclear Generating Plant Seismic Walkdown Report 6 Licensing Basis Evaluations Section 5, Seismic Licensing Basis Evaluation, of Reference 1 provides a detailed process to perform and document seismic licensing basis evaluations of SSCs identified when potentially adverse seismic conditions are identified during the equipment Seismic Walkdowns or Area Walk-Bys. The process provides a means to identify, evaluate and document how the identified potentially adverse seismic condition meets the site's seismic licensing basis without entering the condition into the site's Corrective Action Program (CAP). Further, the process directs that if a condition cannot be readily shown to meet the seismic licensing basis, then the identified condition should be entered into the station's CAP where it will be determined that the condition does or does not meet the seismic licensing basis.All potentially adverse seismic conditions that were identified during the equipment Seismic Walkdowns or Area Walk-Bys were entered into the station's CAP. Therefore, no seismic licensing basis evaluations were completed in accordance with the process documented in Section 5 of Reference

1. Tables 5-2 and 5-3 at the end of Section 5 of this report provide a summary of the issues identified in both the Seismic Walkdowns and Area Walk-Bys.Section 6.0 -Licensing Basis Evaluations 6-1 Monticello Nuclear Generating Plant Seismic Walkdown Report 7 IPEEE Vulnerabilities Resolution Report In the NRC 10 CFR 50.54(f) letter (Reference 6), the NRC requested that licensees provide a list of plant-specific vulnerabilities (including any seismic anomalies, outliers, or other findings) identified by the Individual Plant Examination of External Events (IPEEE) and a description of the actions taken to eliminate or reduce them (including their completion dates), as part of NTTF Recommendation 2.3 -Seismic.Section 7, IPEEE Vulnerabilities, of Reference 1 provides guidance for addressing and reporting the evaluations related to the Individual Plant Examination of External Events (IPEEE) program and the actions taken in response to the vulnerabilities that were identified during that program. According to the guidance in Reference 1, the submittal report should describe the actions taken to eliminate or reduce the IPEEE seismic vulnerabilities, and the date the actions were documented as complete.

Table 7-1 and the following paragraphs provide this information. NRC Generic Letter 88-20, Supplement No. 4, "Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities," dated June 28, 1991 (Reference 9), requested licensees to complete an IPEEE. The purpose of the IPEEE is to (1) develop appreciation of severe accident behavior, (2) understand the most likely severe accident sequences that occur under full power conditions, (3) gain a qualitative understanding of the overall likelihood of core damage and radioactive material release, and (4) to identify potential plant enhancements to reduce the overall likelihood of core damage and radioactive material releases. By letter dated March 1, 1995 (Reference 5), Monticello forwarded the report documenting the results of the Monticello Individual Plant Examination of External Events (IPEEE) as requested by Generic Letter 88-20. In addition to seismic events, this report addressed internal fires, high winds, floods and other credible external events. By letter dated November 20, 1995 (Reference 11), Monticello submitted revised information concerning the evaluation of internal fires as well as the seismic event evaluation. The NRC review of information for the submittals related to IPEEE determined that'no vulnerabilities associated with aspects of external events were identified and that the staff considers these issues resolved for Monticello (Reference 10). The NRC Staff made this conclusion on the basis that (1) the US1 A-46 program would upgrade the plant to the SSE level, and (2) assuming the failure of all seismic equipment list (SEL)equipment that were not screened at the review-level earthquake level, the plant would still be able to achieve safe shutdown. The following three plant improvements, which were stated by MNGP to be made as part of the US1 A-46 program, were necessary in order to make the statement that the plant would be capable of safe shutdown after an SSE:* Fastening of U-bolts on diesel generator starting air receivers.

• Eliminating the potential impact of an HVAC duct on a relay panel.* Upgrading light fixtures in the control room to have a means of anchorage independent of the T-bar supports.Section 7.0 -IPEEE Vulnerabilities Resolution Report 7-1 Monticello Nuclear Generating Plant Seismic Walkdown Report Table 7-1 below lists the resolutions for these three IPEEE plant improvements, and when these resolutions were completed.

Of the three IPEEE improvements listed in the table below, the DG 11 and DG 12 air receivers were selected for MNGP SWEL 1. The equipment tags for the air receivers are T-79D and T-80A, respectively. Anchorage configuration verifications were performed for both of these components, and no adverse seismic conditions were identified. In addition to performing Seismic Walkdowns on the 11 DG and 12 DG air receivers, an Area Walk-by was performed in the cable spreading room. No seismic issues for the C-32 relay panel were identified as a result of the Area Walk-by.Table 7-1: Monticello IPEEE Seismic Improvements Equipment Potential Failure Mode Resolution Date Description Completed Analysis determined that a torque value of 15 ft-lb would apply adequate tension to assure that friction forces DG 11 and 12 Air Sliding-induced pipe failure. Pre- would adequately restrain the tanks in December of Receivers tension of U-bolts not reliable, an axial direction. 1996 Work Order 9603068 and Work Order 9603069 applied a torque value of 15 ft-lb to the U-bolts.Work Order 9602745 and modification 96Q035, Resolution of SQUG Outliers, trimmed the flanges of the HVAC duct Relay Panel C32 Relay chatter due to impact with so that it could not make contact with December of HVAC duct behind panel. the panels. This eliminated the 1996 potential for the duct to impact the panels and cause essential relays to chatter.It was originally thought that all of the lights were not safety wired, however when trying to resolve this outlier it was found that the 2'x4' lights directly above the main control boards were supported from the ceiling by rods.Ceiling collapse. Ceiling system The other ceiling lights were not Control Room unbraced, vulnerable T-bar independently supported from the December of Ceiling connections, light fixtures not ceiling. 1996 safety-wired. Work Order 9602920 and Modification 96Q035, Resolution of SQUG Outliers, installed safety wires on all of the lights over the listed panels to assure that they are independently supported and will not be a seismic interaction hazard.Section 7.0 -IPEEE Vulnerabilities Resolution Report 7-2 Monticello Nuclear Generating Plant Seismic Walkdown Report 8 Peer Review A peer review team consisting of at least two individuals was assembled and peer reviews were performed in accordance with Section 6, Peer Review, of Reference 1.The Peer Review process included the following activities: " Review of the selection of SSCs included on the SWEL* Review of a sample of the checklists prepared for the Seismic Walkdowns and Area Walk-Bys* Review of Licensing basis evaluations, as applicable

• Review of the decisions for entering the potentially adverse conditions into the CAP process* Review of the submittal report* Provide a summary report of the peer review process in the submittal report The peer reviews were performed independently from this report. The summary Peer Review Report is provided in Appendix E of this report.Section 8.0 -Peer Review 8-1 Monticello Nuclear Generating Plant Seismic Walkdown Report 9 References

1) EPRI Technical Report 1025286, "Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic," dated June 2012.2) Monticello Nuclear Generating Plant Updated Safety Analysis Report (USAR), Revision 28.3) NSPM (M.A. Schimmel)

Letter to NRC, "Monticello Nuclear Generating Plant's 120-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding the Seismic Aspects of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated July 9, 2012.4) NRC Letter, "Endorsement of Electric Power Research Institute (EPRI) Draft Report 1025286, 'Seismic Walkdown Guidance,"' dated May 31, 2012, ADAMS Accession No. ML12145A529.

5) Northern States Power (W.J. Hill) Letter to NRC, "Submittal of Monticello Individual Plant Examination of External Events (IPEEE) Report," dated March 1, 1995.6) NRC (E Leeds and M Johnson) Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident" dated March 12, 2012, ADAMS Accession No. ML12053A340.

7) Monticello Nuclear Generating Plant procedure 4 AWI-04.02.01, Housekeeping, Revision 19.8) Monticello Nuclear Generating Plant procedure 4 AWI-04.05.10, Scaffolding Controls, Revision 8.9) Supplement 4 of Generic Letter 88-20, "Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities," issued June of 1991.10) NRC (C.F. Lyon) Letter to NSP (M.F. Hammer), "Review of Monticello Individual Plant Examination of External Events (IPEEE) Submittal (TAC No. M83644)," dated April 17, 2000.11) NSP (W.J. Hill) Letter to NRC, "Individual Plant Examination of External Events (IPEEE) Report, Revision 1; Seismic Analysis, Revision 0 and Internal Fires Analysis, Revision 1 (TAC M83644)," dated November 20, 1995.Section 9.0 -References 9-1 Monticello Nuclear Generating Plant Seismic Walkdown Report 12) NSP (W.J. Hill) Letter to NRC, "Response to Supplement 1 to Generic Letter 87-02, Submittal of USI A-46 Seismic Evaluation Report (TAC M69460)," dated November 20, 1995.Section 9.0 -References 9-2 Monticello Nuclear Generating Plant Seismic Walkdown Report A Equipment Lists Appendix A contains the equipment lists that were developed as part of the equipment selection for the SWEL. Note that MNGP did not identify any items which required walkdowns for SWEL 2, so a Base List 2 and SWEL 2 are not provided in this appendix.The following contents are found in Appendix A: T able A -i, M onticello Base List 1 ....................................................................

A -2 Table A -2, M onticello SW EL 1 ....................................................................... A -32 Appendix A -Equipment Lists A-1 Monticello Nuclear Generating Plant Seismic Walkdown Report A. 1 Equipment Selection -Base List 1 Table A-1 is a list of the equipment resulting from Screen #3 and entering Screen #4.The screens utilized for selecting equipment for the SWEL is described in Section 4 of this report. This list of initial equipment is called "Base List 1 ," per the guidance in Reference 1.Table A-I: Monticello Base List I Equipment Description Class 1 Safety M 3 Tag Function 2 System 152-503 4KV BREAKER P-202C (03) Medium Voltage 3,4,5 4KV Switchgear 152-504 4KV BREAKER P-202A (03) Medium Voltage 3,4,5 4KV Switchgear 152-505 4KV TO P-208A 11 Core Spray Pump (03) Medium Voltage 3 4KV Switchgear 152-605 4KV TO P-208B 12 Core Spray Pump (03) Medium Voltage 3 4KV Switchgear AO-2-2-1 1A 11 RECIRC PUMP SEAL LEAKOFF (07) Fluid-Operated Valves 3, 5 REC AO-2-2-11B 12 RECIRC PUMP SEAL LEAKOFF (07) Fluid-Operated Valves 3,5 REC AO-2377 ALT N2 B (21) Tanks and Heat 5 AN2 Exchangers AO-2377 DW & TORUS PURGE OTBD ISOL (07) Fluid-Operated Valves 5 PCT AO-2378 ALT N2 A (21) Tanks and Heat 5 AN2 Exchangers AO-2378 TORUS PURGE INBD ISOL (07) Fluid-Operated Valves 5 PCT AO-2379 VACUUM RELIEF DAMPER (07) Fluid-Operated Valves 5 PCT AO-2380 VACUUM RELIEF DAMPER (07) Fluid-Operated Valves 5 PCT AO-2381 ALT N2 A (21) Tanks and Heat 5 AN2 Exchangers Appendix A -Equipment Lists A-2 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class 1 Safety Tag Function 2 System 3 AO-2381 DW PURGE INBD ISOL (07) Fluid-Operated Valves 5 PCT AO-2383 ALT N2 A (21) Tanks and Heat 5 AN2 Exchangers AO-2383 TORUS PURGE EXH INBD (07) Fluid-Operated Valves 5 PCT AO-2386 DW PURGE EXH INBD (07) Fluid-Operated Valves 5 PCT AO-2386 ALT N2 A (21) Tanks and Heat 5 AN2 Exchangers AO-2387 ALT N2 B (21) Tanks and Heat 5 AN2 Exchangers AO-2387 DW OTBD VENT (07) Fluid-Operated Valves 5 PCT AO-2-80A INBOARD MSIV (07) Fluid-Operated Valves 2, 3, 5 MST AO-2-80B INBOARD MSIV (07) Fluid-Operated Valves 3, 5 MST AO-2-80C INBOARD MSIV (07) Fluid-Operated Valves 3, 5 MST AO-2-80D INBOARD MSIV (07) Fluid-Operated Valves 3, 5 MST AO-2-86A A MSIV OUTBD (07) Fluid-Operated Valves 3, 5 MST AO-2-86B B MISV OUTBD (07) Fluid-Operated Valves 3, 5 MST AO-2-86C C MSIV OUTBD (07) Fluid-Operated Valves 3, 5 MST AO-2-86D D MSIV OUTBD (07) Fluid-Operated Valves 3, 5 MST AO-2896 ALT N2 B (21) Tanks and Heat 5 AN2 Exchangers AO-2896 TORUS PURGE EXH OTBD ISOL (07) Fluid-Operated Valves 5 PCT AO-4539 HARD PIPE VENT INBOARD ISOLATION (07) Fluid-Operated Valves 5 PCT VALVE AV-3147 11 RHR SW PUMP P-1 09A AUTO AIR (07) Fluid-Operated Valves 4, 5 RSW VENT Appendix A -Equipment Lists A-3 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class' Safety System 3 Tag Functionz St 14 RHR SW PUMP P-1 09D AUTO AIR AV-3148 VENT (07) Fluid-Operated Valves 4, 5 RSW AV-3149 13 RHR SW PUMP P-109C AUTO AIR (07) Fluid-Operated Valves 4, 5 RSW VENT 12 RHR SW PUMP P-109B AUTO AIR AV-3150 VENT (07) Fluid-Operated Valves 4, 5 RSW AV-3155 11 ESW PUMP P-i IEA DISCHARGE AIR (07) Fluid-Operated Valves 3,4 ESW VENT AV-3156 12 ESWPUMP P-111B DISCHARGEAIR (07) Fluid-Operated Valves 3,4 ESW VENT 13 ESW PUMP P-ill C DISCHARGE AIR AV-4024 VENT (07) Fluid-Operated Valves 3, 4, 5 FSW AV-4026 14 ESW PUMP P-i 110 DISCHARGE AIR (07) Fluid-Operated Valves 3,4,5 FSW VENT BPM-1, Location:l 1DG DC-BOOSTER PUMP MOTOR (05) Horizontal Pumps 1, 3,4, 5 DGN BPM-1,iLocationG BPM-l, Location: DC-BOOSTER PUMP MOTOR (05) Horizontal Pumps 3, 4, 5 DGN 12 DG BPM-2, Location: DC-BOOSTER PUMP MOTOR (05) Horizontal Pumps 3, 4, 5 DGN 11 DG BPM-2, Location: DC-BOOSTER PUMP MOTOR (05) Horizontal Pumps 3, 4, 5 DGN 12 DG BUS 15 4160 SWITCHGEAR (03) Medium Voltage 1,2,3,4,5 4KV Switchgear BUS 16 4160 SWITCHGEAR (03) Medium Voltage 1, 3,4, 5 4KV Switchgear C-03 RX AND CTMT COOLING AND ISOL (20) Instrumentation and BENCH BOARD Control Panels and Cabinets 2, 3, 4, 5 MSC C-04 RWC RECIRCULATING BENCH BOARD (20) Instrumentation and Control Panels and Cabinets 1, 3 MSC C-05 REACTOR CONTROL BENCH BOARD (20) Instrumentation and Control Panels and Cabinets 1, 3 MSC Appendix A -Equipment Lists A-4 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class' Safety 2 System3 Tag Function C-06 FEEDWATER AND CONDENSATE (20) Instrumentation and NONE MSC BENCHBOARD Control Panels and Cabinets C-07 TURBINE BENCH BOARD (20) Instrumentation and NONE MSC Control Panels and Cabinets C-08 GENERATOR AUXILLARY POWER (20) Instrumentation and NONE MSC BENCH BOARD Control Panels and Cabinets C-121 JET PUMP INSTRUMENT RACK (18) Instruments on Racks 3 REC C-122 JET PUMP INSTRUMENT RACK (18) Instruments on Racks 3 REC C-129A RHR INSTRUMENT RACK (18) Instruments on Racks 3, 4, 5 RHR C-1 29B RHR INSTRUMENT RACK (18) Instruments on Racks 3, 4, 5 RHR C-15 CHANNEL A PRIMARY ISOL AND RPS (20) Instrumentation and 113,5 PPS VERTICAL BOARD Control Panels and Cabinets 3 C-17 CHANNEL B ISOL AND RPS VERTICAL (20) Instrumentation and 1,3,5 PPS BOARD Control Panels and Cabinets C-18 FEEDWATER AND RECIRCULATION (20) Instrumentation and NONE CFW Control Panels and Cabinets C-19 PROCESS INSTRUMENT VERTICAL (20) Instrumentation and NONE CMP BOARD Control Panels and Cabinets C-20 TURBINE PLANT INSTRUMENT (20) Instrumentation and NONE MSC VERTICAL BOARD Control Panels and Cabinets C-21 NUCLEAR STEAM SUPPLY (20) Instrumentation and NONE RPV TEMPERATURE RECORDING Control Panels and Cabinets C-242 EFT NON-1E PANEL (20) Instrumentation and NONE EFT Control Panels and Cabinets C-243A EFT FLOW CONTROLLERS PANEL DIV (20) Instrumentation and NONE EFT I Control Panels and Cabinets C-244B EFT FLOW CONTROLLERS PANEL DIV (20) Instrumentation and NONE EFT 4II Control Panels and Cabinets C-253A SRV Panel (20) Instrumentation and 2 APR Control Panels and Cabinets Appendix A -Equipment Lists A-5 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class' Safety , Tag Function 2 ysem C-253B SRV Panel (20) Instrumentation and 2 APR Control Panels and Cabinets C-253D DIV II LOLO SET BYPASS PANEL (20) Instrumentation and 2 APR Control Panels and Cabinets C-27 RPIS CABINET C-27 (20) Instrumentation and NONE RPI Control Panels and Cabinets C-289A SPOTMOS PANEL (20) Instrumentation and NONE PCT Control Panels and Cabinets C-289B SPOTMOS PANEL (20) Instrumentation and NONE PCT Control Panels and Cabinets C-290A SRV BLOWDOWN INST PANEL (18) Instruments on Racks 2, 3 APR C-290B SRV BLOWDOWN INST PANEL (18) Instruments on Racks 2, 3 APR C-292 ASDS BENCHBOARD (20) Instrumentation and Control Panels and Cabinets 1, 2, 3, 4, 5 ASD C-292 INSTRUMENT RACK (18) Instruments on Racks 1, 2, 3, 5 ASD C-293 ASDS RELAY PANEL (20) Instrumentation and Control Panels and Cabinets 1, 2, 3, 5 ASD C-30 RCIC CABLE SPR RM CONTROL (20) Instrumentation and 3 RCI PANEL Control Panels and Cabinets C-303A ECCS DIV I ANALOG TRIP SYSTEM (20) Instrumentation and 3 PPS Control Panels and Cabinets C-303B ECCS DIV II ANALOG TRIP SYSTEM (20) Instrumentation and 3 PPS Control Panels and Cabinets C-304A RPS-A1 AND ISOLATION ANALOG TRIP (20) Instrumentation and 1,5 PPS UNIT Control Panels and Cabinets C-304B RPS-B1 AND ISOLATION ANALOG TRIP (20) Instrumentation and 1,5 PPS UNIT Control Panels and Cabinets C-304C RPS-A2 AND ISOLATION ANALOG TRIP (20) Instrumentation and 1,5 PPS UNIT Control Panels and Cabinets C-304D RPS-B2 AND ISOLATION ANALOG TRIP (20) Instrumentation and 1,5 PPS UNIT Control Panels and Cabinets Appendix A -Equipment Lists A-6 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-1: Monticello Base List I Equipment Description Class' Safety 2 Tag Function 2 System 3 C-311 SRV BACKUP AIR SUPPLY (20) Instrumentation and Control Panels and Cabinets 2, 3 APR C-32 A RHR, CORE SPRAY, ADS CONTROL (20) Instrumentation and 2,3,5 RHR PANEL Control Panels and Cabinets C-33 B RHR, CORE SPRAY, ADS CONTROL (20) Instrumentation and 2,3,5 RHR PANEL Control Panels and Cabinets C-39 HPCI RELAY PANEL (20) Instrumentation and 3 HPC Control Panels and Cabinets C-41 INBOARD ISOLATION RELAY PANEL (20) Instrumentation and Control Panels and Cabinets 3, 5 C-42 OUTBOARD ISOLATION RELAY PANEL (20) Instrumentation and Control Panels and Cabinets 3, 5 C-55 RX LEVEL & PRESSURE RACK (18) Instruments on Racks 1, 2,3, 5 RPV C-56 RX LEVEL & PRESSURE RACK (18) Instruments on Racks 1, 2, 3, 5 RPV C-65 Fuel Pool Vent Control Panel (20) Instrumentation and NONE HTV Control Panels and Cabinets C-88 Fuel Pool Control Panel (20) Instrumentation and NONE FPC Control Panels and Cabinets C-91 11 DIESEL GEN ELECTRICAL (20) Instrumentation and Control Panels and Cabinets 1, 3, 4, 5 DGN C-92 12 DIESEL GEN ELECTRICAL (20) Instrumentation and Control Panels and Cabinets 3, 4, 5 DGN C-93 11 DIESEL GEN CONTROL (20) Instrumentation and Control Panels and Cabinets 1, 3, 4, 5 DGN C-94 12 DIESEL GEN CONTROL (20) Instrumentation and Control Panels and Cabinets 3 4, 5 DGN CRID HCU E CRD HYDRALIC CONTROL UNITS EAST (18) Instruments on Racks 1 CRD SIDE CRD HCU E FV CRD HYDRALIC CONTROL UNITS EAST (07) Fluid-Operated Valves 1 CRD SIDE Appendix A -Equipment Lists A-7 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I EqimetDescription Class 1 Safety z ytm Equipment Sft Tag Function 2 ysem CRD HYDRALIC CONTROL UNITS CR0 HCU W WEST SIDE (18) Instruments on Racks 1 CR0 CR0 HCU W FV CRD HYDRALIC CONTROL UNITS (07) Fluid-Operated Valves 1 CR0 WEST SIDE CRD16A SCRAM DISCHARGE VOLUME (21) Tanks and Heat Exchangers 1, 3 CR0 CRD16B SCRAM DISCHARGE VOLUME (21) Tanks and Heat 1,3 CR0 Exchangers CV-1728 11 RHR HX RHRSW OUTLET (07) Fluid-Operated Valves 4, 5 RSW CV-1 729 12 RHR HX RHRSW OUTLET (07) Fluid-Operated Valves 4, 5 RSW CV-1994 11 RHR PUMP MINIMUM FLOW (07) Fluid-Operated Valves 3,4, 5 RHR CV-1995 12 RHR PUMP MINIMUM FLOW (07) Fluid-Operated Valves 3, 4, 5 RHR CV-1996 13 RHR PUMP MINIMUM FLOW (07) Fluid-Operated Valves 3, 4, 5 RHR CV-1 997 14 RHR PUMP MINIMUM FLOW (07) Fluid-Operated Valves 3, 4, 5 RHR CV-2043 HPCI STEAM LINE DRAIN TRAP (07) Fluid-Operated Valves 3 HPC BYPASS CV-2046A STEAM LINE DRN TO MAIN CDSR (07) Fluid-Operated Valves 3 HPC CV-2046B STEAM LINE DRN TO MAIN CDSR (07) Fluid-Operated Valves 3 HPC CV-2369 FLANGE LEAK OFF CONTROL VALVE (07) Fluid-Operated Valves 3 RPV CV-2370 FLANGE LEAK OFF CONTROL VALVE (07) Fluid-Operated Valves 3 RPV CV-2371 REACTOR HEAD VENT TO CRW (07) Fluid-Operated Valves 3 RPV CV-3-32A WEST SDV VENT (07) Fluid-Operated Valves 1, 3 CRH CV-3-32B EAST SDV VENT (07) Fluid-Operated Valves 1, 3 CRH CV-3-32C WEST SDV VENT (07) Fluid-Operated Valves 1, 3 CRH CV-3-32D EAST SDV VENT (07) Fluid-Operated Valves 1, 3 CRH Appendix A -Equipment Lists A-8 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class' Safety 2 System3 Tag Function SCRAM DISCHARGE VOLUME DRAIN CV-3-33A LINES (07) Fluid-Operated Valves 1, 3 CRH SCRAM ISCHARESVLM RI CV-3-33B SCRAM DISCHARGE VOLUME DRAIN (07) Fluid-Operated Valves 1, 3 CRH LINES CV-3-33C WEST SDV DRAIN (07) Fluid-Operated Valves 1, 3 CRH CV-3-33D EAST SDV DRAIN (07) Fluid-Operated Valves 1, 3 CRH D1 #11 BATTERY 125VDC (15) Batteries on Racks 1,2, 3,4, 5 125 D1O 125 VDC CHARGER FOR #11 BATT (16) Battery Chargers and 1, 2, 3, 4, 5 125 Inverters D100 DIV 2 125/250 VDC DISTRIBUTION (14) Distribution Panels 1,2,3,4,5 250 PANEL D101 DIV 2 125/250 VDC ALARM SYSTEM (20) Instrumentation and PANEL Control Panels and Cabinets 3, 4, 5 250 D102 DIV 1 125/250 VDC ALARM SYSTEM (20) Instrumentation and 3,4,5 250 PANEL Control Panels and Cabinets D11 DIV I 125VDC DISTRIBUTION CENTER (14) Distribution Panels 1, 2, 3,4, 5 125 D111 DIV 11 125 VDC PANEL (14) Distribution Panels 3, 4, 5 125 D2 #12 BATTERY 125VDC (15) Batteries on Racks 3, 4, 5 125 D20 125 VDC Charger (16) Battery Chargers and 3, 4, 5 125 Inverters D21 DIV 1125 VDC DISTRIBUTION PANEL (14) Distribution Panels 3, 4, 5 125 D211 DIV II 125 VDC PANEL (14) Distribution Panels 3,4,5 125 D31 DIV 1125/250 VDC DISTRIBUTION (14) Distribution Panels 1, 2, 3,4, 5 250 PANEL D33 125 VDC DISTRIBUTION CENTER (14) Distribution Panels 3, 4, 5 125 D3A #13 (DIV 1) 125/25OVDC BATTERY "A" (15) Batteries on Racks 1, 2,3,4, 5 250 D3B #13 (DIV 1) 125/25OVDC BATTERY "B" (15) Batteries on Racks 1, 2,3,4, 5 250 Appendix A -Equipment Lists A-9 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-1: Monticello Base List 1 Equipment Description Class 1 Safety System3 Tag Function 2 D40 125 VDC Charger (16) Battery Chargers and 3, 4, 5 125 Inverters D52 CHARGER, D3A (13) BATTERY (16) Battery Chargers and 1,2,3,4,5 250 Inverters D53 CHARGER, D3B (13) BATTERY (16) Battery Chargers and 3, 4, 5 250 Inverters D54 CHARGER, SWING D3A,D3B (13) (16) Battery Chargers and 3, 4, 5 250 BATTERY Inverters D6A #16 (DIV 2) 125/25OVDC BATTERY "A" (15) Batteries on Racks 3, 4, 5 250 D6B #16 (DIV 2) 125/250VDC BATTERY "B" (15) Batteries on Racks 3,4,5 250 D70 CHARGER, D6B (16) BATTERY (16) Battery Chargers and 1, 2, 3,4, 5 250 Inverters D80 CHARGER, D6A (16) BATTERY (16) Battery Chargers and 3,4,5 250 Inverters 090 CHARGER, SWING D6A,D6B (16) Battery Chargers and 3, 4, 5 250 (16)BATTERY Inverters DM-8089A1 V-SF-9 SUPPLY DAMPER (10) Air Handlers 1, 3, 4, 5 HTV DM-8089A2 V-SF-9 SUPPLY DAMPER (10) Air Handlers 3, 4, 5 HTV DM-8089A3 V-SF-9 SUPPLY DAMPER (10) Air Handlers 3, 4, 5 HTV DM-8089B1 V-SF-9 EXHAUST DAMPER (10) Air Handlers 3, 4, 5 HTV DM-8089B2 V-SF-9 EXHAUST DAMPER (10) Air Handlers 3, 4, 5 HTV DM-8089J1 V-SF-10 SUPPLY DAMPER (10) Air Handlers 1, 3,4,5 HTV DM-8089J2 V-SF-10 SUPPLY DAMPER (10) Air Handlers 3, 4, 5 HTV DM-8089J3 V-SF-10 SUPPLY DAMPER (10) Air Handlers 3, 4, 5 HTV DM-8089K1 V-SF-10 EXHAUST DAMPER (10) Air Handlers 3, 4, 5 HTV DM-8089K2 V-SF-10 EXHAUST DAMPER (10) Air Handlers 3, 4, 5 HTV Appendix A -Equipment Lists A-10 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List 1 Equipment Description Class' Safety System3 Tag Function 2 DPT-10-91A 11 RHR HX TUBE/SHELL DP CONTROL (18) Instruments on Racks 4, 5 RSW DPT-10-91B HR HX 12 TUBE/SHELL DP CONTROL (18) Instruments on Racks 4, 5 RSW DPT-7845A RHR 11 PUMP D/P (18) Instruments on Racks NONE RHR DPT-7845C RHR 13 PUMP D/P (18) Instruments on Racks NONE RHR E-200A 11 RHR HEAT EXCHANGER (21) Tanks and Heat 45 RHR Exchangers E-200B RHR/ RHR B HXER (21) Tanks and Heat 4,5 RHR Exchangers FE-10-121C RHR PUMP 13 MIN FLOW ELEMENT (00) Other 3, 4, 5 RHR FI-1 0-1 36B FLOW INDICATOR RHR (18) Instruments on Racks NONE RHR FI-14-50B CS LOOP 12 FLOW (18) Instruments on Racks NONE CSP FI-4104 CORE SPRAY FLOW B (18) Instruments on Racks NONE CSP 14 ESW PUMP EFT-ESW HEADER FI-4295B FLOW INDICATOR (18) Instruments on Racks NONE RSW FMT-1 (DG-12) 12 DG FUEL TRANSFER PUMP #1 (05) Horizontal Pumps 3, 4, 5 ,DGN FMT-2 (DG-11) 11 DG FUEL TRANSFER PUMP #2 (05) Horizontal Pumps 3,4,5 DGN FMT-2 (DG-12) 12 DG FUEL TRANSFER PUMP #2 (05) Horizontal Pumps 3, 4, 5 DGN FT-10-109B RHRJ RHR B LPCI INJ FLOW (18) Instruments on Racks. NONE RHR FT-10-111A RHR LOOP A CONT COOLING FLOW (18) Instruments on Racks NONE RHR FT-1 0-97A RHR HX 11 SW INLET FLOW (18) Instruments on Racks NONE RSW FT-1 0-97B RHR HX 12 SW INLET FLOW (18) Instruments on Racks NONE RSW FT-14-40B CS LOOP 12 FLOW (00) Other NONE CSP FT-23-82 HPCI PUMP FLOW TRANSMITTER (18) Instruments on Racks 3 HPC FT-6-51A FW MST FLOW "A" TO LVL CONTROL (18) Instruments on Racks NONE RLC Appendix A -Equipment Lists A-1 1 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class 1 Safety S M3 Tag D i Function 2 te FT-6-51 B FW MST FLOW "B" TO LVL CONTROL (18) Instruments on Racks 3, 5 RLC FT-6-51 C FW MST FLOW "C" TO LVL CONTROL (18) Instruments on Racks 3, 5 RLC FT-6-51 D FW MST FLOW "D" TO LVL CONTROL (18) Instruments on Racks NONE RLC FY-4106 RHR CONTAINMENT COOLING FLOW (18) Instruments on Racks NONE RHR G31 #11 DG NEUTRAL GROUNDING (04) Transformers 1,3,4,5 DGN CABINET G-3A 11 EMERGENCY DIESEL GENERATOR (17) Engine-Generators 1, 3,4, 5 DGN G-3B 12 EMERGENCY DIESEL GENERATOR (17) Engine-Generators 1, 3,4, 5 DGN G41 #12 DG NEUTRAL GROUNDING (04) Transformers 3,4,5 DGN CABINET IR-5A-K30A RACK FOR 5A-K3YA & 5A-K3OB (18) Instruments on Racks 1 PPS RELAYS IR-DPT-7845A RHR 11/13 PUMP D/P RACK (18) Instruments on Racks NONE RHR IR-FS-10-121A RHR PUMP 11 MIN FLOW CONTROL (18) Instruments on Racks 3,4,5 RHR RACK IR-FS-10-121B RHR PUMP 12 MIN FLOW CONTROL RACK (18) Instruments on Racks 3, 4, 5 RHR IR-FT 1A RHR LOOP A CONT COOLING FLOW (18) Instruments on Racks NONE RHR INSTR RACK IR-LS-7428A SDV WATER LEVEL HI RACK (18) Instruments on Racks 1, 3, 5 CRH IR-LS-7428C SDV WATER LEVEL HI RACK (18) Instruments on Racks 1, 3, 5 CRH IR-PCV-4879 ALT N2 A RACK (18) Instruments on Racks 2, 5 AN2 IR-PCV-4881 ALT N2 B RACK (18) Instruments on Racks 2, 5 AN2 IR-PI-3051 TORUS INSTRUMENT RACK (18) Instruments on Racks 5 PCT IR-RB1001-01 Fuel Pool Instrument Rack (18) Instruments on Racks NONE FPC Appendix A -Equipment Lists A-12 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-1: Monticello Base List I Equipment Description Class' Safety 2 System 3 Tag Function EAST/WEST SDV VENT/DRN VLVS AIR IR-SV-3-29 SUPPLY SOL VLV RACK (18) Instruments on Racks 3, 5 CRH IR-SV-3-31C OUTBOARD VENT/AR RPS CH A RACK (18) Instruments on Racks 1, 3,5 CRH J1010 SECURITY JUNCTION BOX (14) Distribution Panels NONE SIN J1012 SECURITY JUNCTION BOX (14) Distribution Panels NONE SIN J1013 SECURITY JUNCTION BOX (14) Distribution Panels NONE SIN K-10A RHRSW AUX AIR COMP (12) Air Compressors 4,5 RSW K-10B B RHR AUX AIR COMPRESSOR (12) Air Compressors 4, 5 RSW K-8A 11 EDG ELECTRIC/DIESEL AIR (12) Air Compressors 1,3,4,5 DGN STARTER COMPRESSOR

1. 1 11 ELECTRIC AIR STARTER K-8B COMPRESSOR
2. 2 (12) Air Compressors 1, 3, 4, 5 DGN K-9A 12 ELECTRIC AIR STARTER (12) Air Compressors 3,4,5 DGN COMPRESSOR
3. 1 K-913 12 EDG ELECTRIC/DIESEL AIR (12) Air Compressors 3,4,5 DGN STARTER COMPRESSOR
4. 2 LC-1 03 480 V LOAD CENTER (02) Low Voltage Switchgear 1, 3, 4, 5 480 LC-104 480 V LOAD CENTER (02) Low Voltage Switchgear 1,3, 4, 5 480 LT-2-3-72A LO LO REACTOR LVL ECCS INITIATION (18) Instruments on Racks 2, 3 RPV LT-2-3-72B LO LO REACTOR LVL ECCS INITIATION (18) Instruments on Racks 2, 3 RPV LT-2-3-72C LO LO REACTOR LVL ECCS INITIATION (18) Instruments on Racks 2, 3 RPV LT-2-3-72D LO LO REACTOR LVL ECCS INITIATION (18) Instruments on Racks 2, 3 RPV LT-2996 TORUS WATER LEVEL (18) Instruments on Racks 5 PCT LT-7338A TORUS WIDE RANGE LEVEL (18) Instruments on Racks NONE PCT LT-7338B TORUS WIDE RANGE LEVEL (18) Instruments on Racks NONE PCT Appendix A -Equipment Lists A-13 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List 1 Equipment Description Class' Safety System3 Tag Function S MCC-133A 480 V MCC (B33A) (01) Motor Control Centers 1, 3,4, 5 480 MCC-1 33B 480V MCC (01) Motor Control Centers 1,3, 3, 5 480 MCC-134 480 V MCC (B34) (01) Motor Control Centers 1, 3, 4, 5 480 MCC-1 42A 480 V MCC (B42A) (01) Motor Control Centers 1,3, 3, 5 480 MCC-142B 480V MCC (01) Motor Control Centers NONE 480 MtCC-143A 480 V MCC (B43A) (01) Motor Control Centers 1, 3,4, 5 480 MCC-143B 480V MCC (01) Motor Control Centers 1, 3, 4, 5 480 MCC-144 480 V MCC (B44) (01) Motor Control Centers 1, 3,4, 5 480 MCC-311 DIV 1 (RCIC) 250V DC MOTOR (01) Motor Control Centers 3 250 CONTROL CENTER 311 MCC-312 DIV 2 (HPCI) 250V DC MOTOR (01) Motor Control Centers 3 250 CONTROL CENTER 312 MCC-313 DIV 1 250V DC MOTOR CONTROL (01) Motor Control Centers 2,3,5 250 CENTER 313 (08) Motor-Operated and 3 CSP MO-1741 11 CS PUMP TORUS SUCTION Solenoid-Operated Valves MO-1 742 12 CS PUMP TORUS SUCTION (08) Motor-Operated and 3 CSP Solenoid-Operated Valves MO-i 749 11 CORE SPRAY TEST LINE TO TORUS (08) Motor-Operated and 3 CSP Solenoid-Operated Valves MO-1750 12 CS TEST LINE TO TORUS (08) Motor-Operated and 3 CSP Solenoid-Operated Valves MO-1 751 11 CS INJ OUTBOARD ISOLATION VLV (08) Motor-Operated and 3 CSP Solenoid-Operated Valves MO-1 752 12 CS INJ OUTBOARD ISOLATION (08) Motor-Operated and Solenoid-Operated Valves CSP MO-1 753 11 CS INJ INBOARD ISOLATION VLV (08) Motor-Operated and 3 CSP Solenoid-Operated Valves Appendix A -Equipment Lists A-14 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List 1 Equipment Description Class' Safety 2 System3 Tag Function 2 ytm MO-1 754 12 CS INJ INBOARD ISOLATION VALVE (08) Motor-Operated and 3 CSP Solenoid-Operated Valves MO-i 986 11 RHR SUCTION FROM TORUS (08) Motor-Operated and 3,5 RHR Solenoid-Operated Valves MO-1 987 B RHR/ TORUS SUCTION (08) Motor-Operated and 3,5 RHR Solenoid-Operated Valves MO-1988 11 RHR SHUTDOWN COOLING (08) Motor-Operated and 4 RHR SUCTION Solenoid-Operated Valves MO-1 989 RHRI B SDC SUCTION (08) Motor-Operated and 4 RHR Solenoid-Operated Valves MO-2002 11 RHR HX BYPASS (08) Motor-Operated and 3 RHR Solenoid-Operated Valves MO-2003 RHR/RHR B HXER BYPASS (08) Motor-Operated and 3 RHR Solenoid-Operated Valves MO-2006 11 RHR DISCHARGE TO TORUS (08) Motor-Operated and 5 RHR Solenoid-Operated Valves MO-2007 RHR/RHR B DISCH TO TORUS (08) Motor-Operated and 5 RHR Solenoid-Operated Valves MO-2008 TORUS COOLING ISOL (08) Motor-Operated and 5 RHR Solenoid-Operated Valves MO-2009 RHR/ RHR B TORUS COOLING TEST (08) Motor-Operated and 5 RHR RTN Solenoid-Operated Valves MO-201 0 TORUS SPRAY VLV (08) Motor-Operated and 4,5 RHR Solenoid-Operated Valves MO-2011 RHR/ RHR B TORUS SPRAY INJ (08) Motor-Operated and 5 RHR Solenoid-Operated Valves MO-2012 11 RHR LPCI OUTBOARD INJECTION (08) Motor-Operated and 3,4 RHR Solenoid-Operated Valves MO-2013 RHRIRHR B LPCI INJ OUTBD (08) Motor-Operated and 3,4 RHR Solenoid-Operated Valves MO-2014 11 RHR LPCI INBOARD INJECTION (08) Motor-Operated and 3,4 RHR Solenoid-Operated Valves Appendix A -Equipment Lists A-15 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class' Safety System 3 Tag Function 2 MO-2015 RHR B LPCI INJ INBOARD (08) Motor-Operated and Solenoid-Operated Valves 3 RHR MO-2020 11 RHR CONTAINMENT SPRAY (08) Motor-Operated and 5 RHR OUTBOARD ISOLATION Solenoid-Operated Valves MO-2021 "B" RHR CTMT SPRAY OUTBD ISOL (08) Motor-Operated and 5 RHR Solenoid-Operated Valves MO-2026 RHR HEAD SPRAY OUTBOARD (08) Motor-Operated and 4 RHR ISOLATION Solenoid-Operated Valves MO-2030 RHR SHUTDOWN COOLING SUPPLY (08) Motor-Operated and 3,4 RHR OUTBOARD ISOLATION Solenoid-Operated Valves MO-2032 RHR DISCHARGE TO WASTE SURGE (08) Motor-Operated and 5 RHR TANK Solenoid-Operated Valves MO-2033 RHR LOOPS CROSSTIE (08) Motor-Operated and 3 RHR Solenoid-Operated Valves MO-2034 HPCI INBOARD STEAM SUPPLY (08) Motor-Operated and Solenoid-Operated Valves 3, 5 HPC MO-2035 HPCI OUTBOARD STEAM SUPPLY (08) Motor-Operated and 3,5 HPC ISOLATION Solenoid-Operated Valves MO-2063 HPCI CST SUCT (08) Motor-Operated and 3 HPC Solenoid-Operated Valves MO-2075 RCIC STEAM SUPPLY INBOARD (08) Motor-Operated and 3,5 RCI ISOLATION Solenoid-Operated Valves MO-2076 RCIC STEAM SUPPLY OUTBOARD (08) Motor-Operated and ISOLATION Solenoid-Operated Valves 3, 5 RCI MO-2078 RCIC TURBINE STEAM SUPPLY (08) Motor-Operated and 3 RCI Solenoid-Operated Valves MO-2106 RCIC PUMP DISCHARGE OUTBOARD (08) Motor-Operated and 3 RCI Solenoid-Operated Valves MO-2373 INBD MS LINE DRN UPSTREAM MSIVS (08) Motor-Operated and Solenoid-Operated Valves 3 5 MST MO-2374 MAIN STEAM LINE DRAIN -OUTBOARD (08) Motor-Operated and Solenoid-Operated Valves 2, 3, 5 MST Appendix A -Equipment Lists A-16 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class 1 Safety System 3 Tag Function 2 MO-2397 RWCU INLET INBOARD ISOL (08) Motor-Operated and Solenoid-Operated Valves 3 5 RWC MO-2398 RWCU INLET OUTBOARD ISOL (08) Motor-Operated and Solenoid-Operated Valves 3 RWC MO-2-43A 11 RECIRC PUMP SUCTION (08) Motor-Operated and 3 REC Solenoid-Operated Valves MO-2-43B 12 RECIRC PUMP SUCTION (08) Motor-Operated and 3 REC Solenoid-Operated Valves MO-2-53A 11 RECIRC PUMP DISCHARGE (08) Motor-Operated and 3 REC Solenoid-Operated Valves MO-2-53B 12 RECIRC PUMP DISCHARGE (08) Motor-Operated and 3 REC Solenoid-Operated Valves N3346A 11 EDG AIR CMPSR 1 (K-8A) LOCAL (20) Instrumentation and 1,3,4,5 DGN DISCONNECT SWITCH Control Panels and Cabinets 12 EDG AIR CMPSR 2 (K-gB) LOCAL (20) Instrumentation and N3346B DISCONNECT SWITCH Control Panels and Cabinets 3 4, 5 DGN N3347 MOTOR STARTER FOR K-10A (20) Instrumentation and Control Panels and Cabinets 4, 5 DGN N4301A 11 EDG AIR CMPSR 2 (K-8B) LOCAL (20) Instrumentation and 1,3,4,5 DGN DISCONNECT SWITCH Control Panels and Cabinets N4301B 12 EDG AIR CMPSR 1 (K-9A) LOCAL (20) Instrumentation and 3,4,5 DGN DISCONNECT SWITCH Control Panels and Cabinets N4454 MOTOR STARTER FOR K-10B (20) Instrumentation and Control Panels and Cabinets 3 4, 5 DGN P-1 09A 11 RHR SW PUMP (06) Vertical Pumps 4, 5 RSW P-109B 12 RHR SW PUMP (06) Vertical Pumps 4 RSW P-109C 13 RHR SW PUMP (06) Vertical Pumps 4 RSW P-109D 14 RHR SW PUMP (06) Vertical Pumps 4 RSW P-11 DIESEL OIL XFER PUMP (05) Horizontal Pumps 1, 3, 4, 5 DOL Appendix A -Equipment Lists A-17 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment, Description Class' Safety 2 system 3 Tag Function P-111A 11 ESW (EDG-ESW)

PUMP (06) Vertical Pumps 1, 3, 4, 5 ESW P-111B 12 ESW (EDG-ESW) PUMP (06) Vertical Pumps 3, 4, 5 ESW P-111C 13 ESW (EDG-ESW) PUMP (06) Vertical Pumps 3, 4, 5 FSW P-111D 14 ESW (EDG-ESW) PUMP (06) Vertical Pumps 3, 4, 5 FSW P-202A 11 RHR PUMP (06) Vertical Pumps 3, 4, 5 RHR P-202B RHR/ RHR B PUMP # 12 (06) Vertical Pumps 3, 4, 5 RHR P-202C 13 RHR PUMP (06) Vertical Pumps 3, 4, 5 RHR P-202D RHR/ RHR D PUMP # 14 (06) Vertical Pumps 3, 4, 5 RHR P-203A 11 SBLC Pump (05) Horizontal Pumps 1 SLC P-208A 11 CORE SPRAY PUMP (06) Vertical Pumps 3 CSP P-208B 12 CORE SPRAY PUMP (06) Vertical Pumps 3 CSP P-209 HPCI PUMP (05) Horizontal Pumps 3 HPC P-222A 11 DG FUEL TRANSFER PUMP #1 (05) Horizontal Pumps 1, 3, 4, 5 DGN P-73A 480V POWER PANEL (14) Distribution Panels 4, 5 480 P-88A ECCS AREA DRAIN PUMP (06) Vertical Pumps 3, 4, 5 LRW P-88B ECCS AREA DRAIN PUMP (06) Vertical Pumps 3, 4, 5 LRW P-88C ECCS AREA DRAIN PUMP (06) Vertical Pumps 3, 4, 5 LRW P-88D ECCS AREA DRAIN PUMP (06) Vertical Pumps 3, 4, 5 LRW PCV-3004 11/13 RHRWSW PUMP MOTORS COOLING WATER HEADER INLET (07) Fluid-Operated Valves 3, 4, 5 RSW PCV-3005 12/14 RHRSW PUMP MOTORS COOLING HEADER INLET (07) Fluid-Operated Valves 3, 4, 5 RSW PCV-4879 ALT N2 A (18) Instruments on Racks 2, 5 AN2 Appendix A -Equipment Lists A-18 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class' Functiony 2 Syste Tag Fucon Sytm PCV-4881 ALT N2 B (18) Instruments on Racks 2, 5 AN2 PCV-4897 ALT N2 A (18) Instruments on Racks 2, 5 AN2 PCV-4898 ALT N2 B (18) Instruments on Racks 2, 5 AN2 PCV-4903 ALT N2 A (18) Instruments on Racks 2, 5 AN2 PCV-4904 ALT N2 A (18) Instruments on Racks 2, 5 AN2 PCV-4905 ALT N2 B (18) Instruments on Racks 2, 5 AN2 PCV-4906 ALT N2 B (18) Instruments on Racks 2, 5 AN2 PS-23-97A HPCI HI TURB EXH PRESS TURB TRIP (18) Instruments on Racks 3 HPC PSX5 X PAGE 5 VOLT POWER SUPPLY RPIS (16) Battery Chargers and NONE RPI Inverters PSX6 X PAGE 6 VOLT POWER SUPPLY RPIS (16) Battery Chargers and NONE RPI Inverters PSY5 Y PAGE 5 VOLT POWER SUPPLY RPIS (16) Battery Chargers and NONE RPI Inverters PSY6 Y PAGE 6 VOLT POWER SUPPLY RPIS (16) Battery Chargers and NONE RPI Inverters PT-14-38B CS PUMP 12 DISCHARGE PRESSURE (18) Instruments on Racks 3 CSP PT-2994A DW PRESS NARROW RANGE (18) Instruments on Racks NONE PCT PT-2994B TORUS PRESSURE NARROW RANGE (18) Instruments on Racks NONE PCT PT-4022 EFT-ESW SYSTEM PRESSURE (18) Instruments on Racks NONE PCT PT-7251A DW WIDE RANGE PRES (18) Instruments on Racks NONE PCT PT-7251B DRYWELL WIDE RANGE PRESS (18) Instruments on Racks NONE PCT RV-1523 XFER PUMP DISCHARGE RELIEF (07) Fluid-Operated Valves 3, 4, 5 DOL VALVE RV-1 524 XFER PUMP DISCHARGE RELIEF (07) Fluid-Operated Valves 3, 4, 5 DOL VALVE Appendix A -Equipment Lists A-19 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class' Safety 2 Tag Function 2 ysem RV-1745 11 CS PUMP DISCH RV TO ORW (07) Fluid-Operated Valves 3 CSP RV-1 746 12 CS PUMP DISCH RV TO ORW (07) Fluid-Operated Valves 3 CSP RV-1 990 RHR 11 PUMP SUCTION RV (07) Fluid-Operated Valves 3, 4, 5 RHR RV-1991 RHR/ RHR B PUMP SUCTION RELIEF (07) Fluid-Operated Valves 3, 4, 5 RHR RV-1 992 RHR 13 PUMP SUCTION RV (07) Fluid-Operated Valves 3, 4, 5 RHR RV-1 993 RHR/ RHR D PUMP SUCTION RELIEF (07) Fluid-Operated Valves 3, 4, 5 RHR RV-2004 RHR LOOP A DISCHARGE LINE RV (07) Fluid-Operated Valves 3, 4, 5 RHR RV-2005 RHR LOOP B DISCHARGE LINE RV (07) Fluid-Operated Valves 3, 4, 5 RHR RV-2025 RHR HEAD SPRAY LINE RV (07) Fluid-Operated Valves 3, 4, 5 RHR RV-2031 SD COOLING SUCTION SUPPLY (07) Fluid-Operated Valves 4 RHR RV-2-71A A SRV (07) Fluid-Operated Valves 2 APR RV-2-71B B SRV (07) Fluid-Operated Valves 2 APR RV-2-71C C SRV (07) Fluid-Operated Valves 2 APR RV-2-71D D SRV (07) Fluid-Operated Valves 2 APR RV-2-71E E SRV (07) Fluid-Operated Valves 2 APR RV-2-71F F SRV (07) Fluid-Operated Valves 2 APR RV-2-71G G SRV (07) Fluid-Operated Valves 2 APR RV-2-71H H SRV (07) Fluid-Operated Valves 2 APR RV-3038 11 LOOP MOTOR COOLING HEADER (07) Fluid-Operated Valves 4, 5 RSW 12/14 LOOP MOTOR COOLING RV-3039 HEADER (07) Fluid-Operated Valves 4, 5 RSW RV-3202 11 HX TUBE SIDE (07) Fluid-Operated Valves 4, 5 RSW Appendix A -Equipment Lists A-20 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class 1 Safety Tag Function 2 System 3 RV-3203 12 HX TUBE SIDE (07) Fluid-Operated Valves 4, 5 RSW RV-3216 11 DG AIR TK T-79A RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3217 11 DG AIR TK T-79B RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3218 11 DG AIR TK T-79C RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3219 11 DG AIR TK T-79D RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3220 11 DG AIR TK T-79E RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3221 11 DG AIR TK T-79F RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3222 DIESEL AIR START COMPRESSOR (K- (07) Fluid-Operated Valves 3, 4, 5 DGN 8A)RV-3223 DIESEL AIR START COMPRESSOR (K- (07) Fluid-Operated Valves 3, 4, 5 DGN 8B)RV-3224 12 DG AIR TK T-80A RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3225 12 DG AIR TK T-80B RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3226 12 DG AIR TK T-80C RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3227 12 DG AIR TK T-80D RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3228 12 DG AIR TK T-80E RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3229 12 DG AIR TK T-80F RV (07) Fluid-Operated Valves 3, 4, 5 DGN RV-3230 DIESEL AIR START COMPRESSOR (K- (07) Fluid-Operated Valves 3, 4, 5 DGN 9A)RV-3231 DIESEL AIR START COMPRESSOR (K- (07) Fluid-Operated Valves 3,4,5 DGN 9B)RV-3242 A SRV DISCHARE 2 VAC RV (07) Fluid-Operated Valves 2 MST RV-3242A A SRV DISCHARGE 8 VAC RV (07) Fluid-Operated Valves 2 MST RV-3243 B SRV DISCHARGE 2" VAC RV (07) Fluid-Operated Valves 2 MST Appendix A -Equipment Lists A-21 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class, Safety 2 System3 Tag Function RV-3243A B SRV DISCHARGE 8" VAC RV (07) Fluid-Operated Valves 2 MST RV-3244 C SRV DISCHARGE 2 VAC (07) Fluid-Operated Valves 2 MST RV-3244A C SRV DISCHARGE 8 VAC (07) Fluid-Operated Valves 2 MST RV-3245 D SRV DISCHARGE 2 VAC (07) Fluid-Operated Valves 2 MST RV-3245A D SRV DISCHARGE 8 VAC (07) Fluid-Operated Valves 2 MST RV-4236 ALT N2 B RELIEF (07) Fluid-Operated Valves 2, 5 AN2 RV-4281 A RHR HX RV SHELL SIDE (07) Fluid-Operated Valves 3, 4, 5 RHR RV-4282 RHR/RHR B HXER RELIEF VALVE (07) Fluid-Operated Valves 3, 4, 5 RHR RV-4673 ALT N2 A RELIEF (07) Fluid-Operated Valves 2, 5 AN2 RV-4878 ALT N2 A RELIEF (07) Fluid-Operated Valves 2, 5 AN2 RV-4880 ALT N2 B RELIEF (07) Fluid-Operated Valves 2, 5 AN2 RV-7440 E SRV DISCHARGE 2 VAC RV (07) Fluid-Operated Valves 2 MST RV-7440A E SRV DISCHARGE 8" VAC RV (07) Fluid-Operated Valves 2 MST RV-7441 F SRV DISCHARGE 2" VAC RV (07) Fluid-Operated Valves 2 MST RV-7441A F SRV DISCHARGE 8" VAC RV (07) Fluid-Operated Valves 2 MST RV-7467 G SRV DISCHARGE 2 VAC RV (07) Fluid-Operated Valves 2 MST RV-7467A G SRV DISCHARGE 8" VAC RV (07) Fluid-Operated Valves 2 MST RV-7468 H SRV DISCHARGE 2" VAC RV (07) Fluid-Operated Valves 2 MST RV-7468A H SRV DISCHARGE 8" VAC RV (07) Fluid-Operated Valves 2 MST SV-1728 CV-1 728 (11 RHR HX RHRSW (08) Motor-Operated and 4,5 RSW OUTLET)SV Solenoid-Operated Valves SV-1729 SV FOR CV-1 729 #12 RHR HX RHRSW (08) Motor-Operated and 4,5 OUT Solenoid-Operated Valves Appendix A -Equipment Lists A-22 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class3 Safety System3 Tag Functiony SV-1 994 SV FOR CV-1 994 #11 RHR MINIMUM (08) Motor-Operated and FLOW Solenoid-Operated Valves 3, 4, 5 RHR SV-1 995 SV FOR CV-1 995 #12 RHR MIN FLOW (08) Motor-Operated and 3,4,5 RHR Solenoid-Operated Valves SV-1 996 SV FOR CV-1996 #13 RHR MINIMUM (08) Motor-Operated and 3,4,5 RHR FLOW Solenoid-Operated Valves SV-1997 SV FOR CV-1997 #14 RHR MIN FLOW (08) Motor-Operated and 3,4,5 RHR Solenoid-Operated Valves SV-2-2-1 1A 11 RECIRC PUMP SEAL LEAKOFF (08) Motor-Operated and 3 REC Solenoid-Operated Valves SV-2-2-1 1B 12 RECIRC PUMP SEAL LEAKOFF (08) Motor-Operated and 3 REC Solenoid-Operated Valves SV-2-32A A SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-32B B SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-32C C SRV BELLOWS LEAK TEST SV (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-32D D SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-32E E SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-32F F SRV BELLOWS LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-32G G SRV BELLOWS LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-32H H SRV BELLOWS LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-33A A SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-33B B SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves Appendix A -Equipment Lists A-23 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List 1 Equipment Description Class 1 Safety Tag Function 2 ytm SV-2-33C C SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-33D D SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-33E E SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-33F F SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-33G G SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-33H H SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-34A A SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-34B B SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-34C C SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-34D D SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-34E E SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-34F F SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-34G G SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-34H H SRV BELLOW LEAK TEST (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2369 FLANGE LEAK OFF CONTROL VALVE (08) Motor-Operated and 3 RPV Solenoid-Operated Valves SV-2370 FLANGE LEAK OFF CONTROL VALVE (08) Motor-Operated and 3 RPV Solenoid-Operated Valves Appendix A -Equipment Lists A-24 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class' Safety Tag Function 2 SV-2371 REACTOR HEAD VENT TO CRW (08) Motor-Operated and 3 RPV Solenoid-Operated Valves SV-2379 ALT N2 A SPLY TO AO-2379 (08) Motor-Operated and 5 PCT Solenoid-Operated Valves SV-2380 ALT N2 A SUPPLY TO AO-2380 (08) Motor-Operated and 5 PCT Solenoid-Operated Valves SV-2-71A A SRV ALT N2 A A/S (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-71 B B SRV PILOT (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-71C C SRV ALT N2 B SUPPLY (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-71 D D SRV PILOT A/S (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-71 E E SRV ALT N2 A A/S (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-71 F F SRV PILOT A/S (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-71G G SRV PILOT A/S (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-71H H SRV PILOT A/S (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-71J E SRV ALT N2 A A/S (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-71 K G SRV PILOT A/S (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-71L H SRV PILOT A/S (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-2-71 M F SRV ASDS PILOT A/S (08) Motor-Operated and 2 APR Solenoid-Operated Valves SV-3-29 EAST/WEST SDV VENT/DRN VLVS AIR (08) Motor-Operated and 1,3 CRH SUPPLY SOL VLV Solenoid-Operated Valves Appendix A -Equipment Lists A-25 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class' Safety Tag Function 2 System 3 SV-3-31A INBOARD VENT/DR RPS CH A (08) Motor-Operated and Solenoid-Operated Valves 1, 3 CRH SV-3-31 B INBOARD VENT/DR RPS CH B (08) Motor-Operated and Solenoid-Operated Valves 1, 3 CRH SV-3-31 C OUTBOARD VENT/AR RPS CH A (08) Motor-Operated and Solenoid-Operated Valves 1, 3 CRH SV-3-31D OUTBOARD VENT/DR RPS CH B (08) Motor-Operated and 1,3 CRH Solenoid-Operated Valves SV-4014A LIQ SX RETURN TO A RHR ISOL (08) Motor-Operated and NONE PAS Solenoid-Operated Valves SV-4015A A LOOP RHR SAMPLE ISOL (08) Motor-Operated and NONE PAS Solenoid-Operated Valves SV-4015B B LOOP RHR SAMPLE ISOL (08) Motor-Operated and NONE PAS Solenoid-Operated Valves SV-4033A A CGCS RECMB CLG PMP INL (08) Motor-Operated and NONE PAS Solenoid-Operated Valves SV-4033B B CGCS RECOMBINER COOLING (08) Motor-Operated and NONE CGC PUMP INLET Solenoid-Operated Valves SV-4034A AGGCS RECMB CLG PMP BYPASS (08) Motor-Operated and NONE CGC Solenoid-Operated Valves SV-4034B B CGCS RECOMBINER COOLING (08) Motor-Operated and NONE CGC PUMP BYPASS Solenoid-Operated Valves SV-4234 ALT N2 A (08) Motor-Operated and Solenoid-Operated Valves 2, 5 AN2 SV-4235 ALT N2 B MANIFOLD ISOL (08) Motor-Operated and Solenoid-Operated Valves 2, 5 AN2 SV-4541 INBOARD N2 SUPPLY TO HPV (08) Motor-Operated and 5 PCT RUPTURE DISC Solenoid-Operated Valves T-200 Standby Liquid Control Tank (21) Tanks and Heat 1 SLC Exchangers T-44 DIESEL OIL STORAGE TANK (21) Tanks and Heat 3,4,5 DOL Exchangers Appendix A -Equipment Lists A-26 Monticello Nuclear Generating Plant Seismic Walkdown Report iTable A-:1 Monticello Base List 1 Equipment S.. .afeyty Sse 3 Tagim nDescription Class Function 2 System 3 Tag ) Function ,,,... ...... ...T-45A STANDBY DIESEL GENERATOR DAY (21) Tanks and Heat 1,3,4,5 DOL TANK Exchangers T-45B STANDBY DIESEL GENERATOR DAY (21) Tanks and Heat 1, 3,4, 5 DOL TANK Exchangers T-48A Skimmer Surge Tank A (21) Tanks and Heat NONE FPC Exchangers T-48B Skimmer Surge Tank B (21) Tanks and Heat NONE FPC Exchangers T-49A A MSIV (AO-2-80A) ACCUMULATOR (21) Tanks and Heat 3,5 MST Exchangers T-49B B MSIV (AO-2-80B) ACCUMLATOR (21) Tanks and Heat 3, 5 MST Exchangers T-49C C MSIV (AO-2-80C) ACCUMULATOR (21) Tanks and Heat 3, 5 MST Exchangers T-49D D MSIV (AO-2-80D) ACCUMULATOR (21) Tanks and Heat 3,5 MST Exchangers T-57A ALT N2 ACCUMULATOR (21) Tanks and Heat 2 APR Exchangers T-57B ALT N2 ACCUMULATOR (21) Tanks and Heat 2 APR Exchangers T-57C ALT N2 ACCUMULATOR (21) Tanks and Heat 2 APR Exchangers T-57D ALT N2 ACCUMULATOR (21) Tanks and Heat 2 APR Exchangers T-57E ALT N2 ACCUMULATOR (21) Tanks and Heat 2 APR Exchangers T-57F ALT N2 ACCUMULATOR (21) Tanks and Heat 2 APR Exchangers T-57G ALT N2 ACCUMULATOR (21) Tanks and Heat 2 APR Exchangers T-57H ALT N2 ACCUMULATOR (21) Tanks and Heat 2 APR Exchangers Appendix A -Equipment Lists A-27 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Safety E ieDescription Class 1 safety 2 System Tag,: Function T-75A ACCUMULATOR FOR SV-1994 (21) Tanks and Heat 3,4,5 RHR Exchangers T-75B RHR/ RHR B PUMP MIN FLOW ACCUM (21) Tanks and Heat 3,4,5 RHR Exchangers T-75C ACCUMULATOR FOR SV-1996 (21) Tanks and Heat Exchangers 3, 4, 5 RHR T-75D RHR/ RHR D PUMP MIN FLOW ACCUM (21) Tanks and Heat 3,4,5 RHR Exchangers T-79A 11 DG AIR TKA (21) Tanks and Heat Exchangers 3, 45 DGN T-79B 11 DG AIR TK B (21) Tanks and Heat 3,4,5 DGN Exchangers T-79C 11 DG AIR TK C (21) Tanks and Heat 3,4,5 DGN Exchangers T-79D 11 DG AIR TK D (21) Tanks and Heat 1,3,4,5 DGN Exchangers T-79E 11 DG AIR TK E (21) Tanks and Heat 1,2,3,4,5 DGN Exchangers T-79F 11 DGAIRTKF (21) Tanks and Heat Exchangers 1, 2, 3,4, 5 DGN T-80A 12 DG AIR TK A (21) Tanks and Heat 1,3,4,5 DGN Exchangers T-80B 12 DG AIR TK B (21) Tanks and Heat 1,2,3,4,5 DGN Exchangers T-80C 12 DG AIR TK C (21) Tanks and Heat 1,2,3,4,5 DGN Exchangers T-80D 12 DG AIR TK D (21) Tanks and Heat 3,4,5 DGN Exchangers T-80E 12 DG AIR TK E (21) Tanks and Heat 345 DGN Exchangers T-80F 12 DG AIR TK F (21) Tanks and Heat 345 DGN Exchangers Appendix A -Equipment Lists A-28 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List I Equipment Description Class 1 Safety System 3 Tag Function T-ALTN2B ALT N2 B BOTTLE RACK (21) Tanks and Heat 2,5 AN2 Exchangers RCIC STM LINE HI AREA TS-13-79C TEMPERATURE ISOLATION (19) Temperature Sensors 2, 3, 5 RCl V-AC-4 RHR B AIR HANDLER (10) Air Handlers 3, 4, 5 HTV V-AC-5 RHR A AIR HANDLER (10) Air Handlers 3, 4, 5 HTV V-EAC-14A CRV DIV I HVAC UNIT (111) Chillers 1,2, 3,4, 5 EFT V-EAC-14B CRV DIV II HVAC UNIT (10) Air Handlers 1, 2, 3, 4, 5 EFT V-EF-40A DIV II 250VDC BATTERY ROOM (10) Air Handlers 1,2,3,4,5 EFT VENTILATION V-EF-40B DIV II 250VDC BATTERY ROOM (10) Air Handlers 1,2,3,4,5 EFT VENTILATION V-ERF-14A CRV DIV I EXHAUST RECIRC FAN (10) Air Handlers 1, 2, 3,4, 5 EFT V-FE-11 DIV 1 EFT CHARCOAL AIR FILTER UNIT (10) Air Handlers 1,2, 3, 4, 5 EFT V-SF-10 11 DIESEL ROOM VENT FAN (09) Fans 1,3, 4, 5 HTV V-SF-9 12 DIESEL ROOM VENT FAN (09) Fans 1, 3,4, 5 HTV X30 TRANSFORMER (04) Transformers 1, 3, 4, 5 480 X40 TRANSFORMER (04) Transformers 1,2, 3, 4, 5 480 11 STANDBY INTRUMENT AC Y01 TRANSFORMER (04) Transformers NONE UAC Y10 DIV 1 CLASS NON-1E UNINT INST (14) Distribution Panels NONE UAC 120VAC DIST PANEL Y20 NON- 1E INST 120VDC DIST PANEL (14) Distribution Panels NONE UAC Y21 INSTRUMENT AC TRANSFER SWITCH (14) Distribution Panels NONE UAC Y22 12 INSTRUMENT AC TRANSFORMER (04) Transformers NONE UAC Appendix A -Equipment Lists A-29 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-I: Monticello Base List 1 Equipment Description Class' Safety 2 Tag Function, ysemn DIV 2 CLASS NON-1 E UNINT 120VAC Y30 INST AC DIST PANEL (14) Distribution Panels NONE UAC Y70 DIV 1 UNINTERRUPTIBLE 120VAC CLASS 1E DIST PANEL (14) Distribution Panels 1, 2, 3,4, 5 UAC Y71 DIV 1 120VAC CLASS 1E INVERTER (16) Battery Chargers and Inverters 1,2,3,4,5 UAC Y72 120 VDC TRANSFORMER FEEDING Y73 (04) Transformers 1,2,3,4,5 UAC Y73 ALTERNATE 120VAC TO UPS (Y71) (14) Distribution Panels 1, 2, 3,4, 5 UAC FUSED DISCONNECT SWITCH TO PANEL Y10 (14) Distribution Panels NONE UAC Y75 FUSED DISCONNECT SWITCH TO (14) Distribution Panels 1,2,3,4,5 UAC PANEL Y70 Y77 120-120/240VAC TRANSFORMER TO (04) Transformers NONE UAC PANEL Y10 Y80 DIV 2 UNINTERRUPTIBLE 120VAC (14) Distribution Panels 1,2,3,4,5 UAC CLASS 1E DIST PANEL Y81 DIV 2 120VAC CLASS 1E INVERTER (16) Battery Chargers and 1,2,3,4,5 UAC Inverters Y82 DIV 2 120 VDC TRANSFORMER Y83 (04) Transformers 1,2, 3, 4, 5 UAC Y83 ALTERNATE 120VAC TO UPS (Y81) (14) Distribution Panels 1, 2, 3,4, 5 UAC Y84 FUSED DISCONNECT SWITCH TO (14) Distribution Panels NONE UAC PANEL Y30 FUSED DISCONNECT SWITCH TO Y85 PANEL Y80 (14) Distribution Panels 1, 2, 3, 4, 5 UAC Y87 120-120/240VAC TRANSFORMER TO (04) Transformers NONE UAC PANEL Y30 Appendix A -Equipment Lists A-30 Monticello Nuclear Generating Plant Seismic Walkdown Report Notes: 1) Class -Class as defined in Appendix B of Reference 1.2) Safety function -Defined as follows: 1 = Reactor Reactivity Control 2 = Reactor Coolant Pressure Control 3 = Reactor Coolant inventory Control 4 = Decay Heat Removal 5 = Containment Function 3) System -Identifies the system associated with the equipment. The abbreviations for these systems are listed below.System Description System Description

System Description

125 125 Volt DC DGN Emergency Diesel Generators PPS Plant Protection System 250 250 Volt DC DOL Diesel Oil System RCI RX Core Isolation Cooling Sys 480 480 V Station Auxiliary EFT Emergency Filtration Train REC RX Recirculation System 4KV 4.16 KV Station Auxiliary ESW Emergency Diesel Generator-RHR Residual Heat Removal iESW System AN2 Alternate N2 FPC Fuel Pool Cooling and Cleanup RLC RX Level Control APR Automatic Press Relief FSW Emergency Filtration -ESW RPI Rod Position Information Sys ASD Alternate Shutdown HPC High Press Coolant Injection RPV RX Pressure Vessel System CFW Condensate & Feedwater HTV Heating & Ventilation RSW RHR Service Water CGC Combustible Gas Control LRW Liquid Radwaste RWC RX Water Cleanup CMP Computer MSC Miscellaneous SIN Security Instrumentation CRD Control Rod Drive System MST Main Steam SLC Standby Liquid Control CRH Control Rod Drive PAS Post Accident Sampling System UAC Uninterruptible AC Hydraulic CSP Core Spray System PCT Primary Containment Appendix A -Equipment Lists A-31 Monticello Nuclear Generating Plant Seismic Walkdown Report A.2 Final SWEL 1 This section provides a list of the final equipment selected for MNGP's SWEL 1 in Table A-2 below. This table identifies which items were selected for anchorage configuration verification, as well as which items are being deferred due to inaccessibility. The comments column of this table identifies the following selection criteria which were utilized in Screen #4: "IPEEE Enhanced" identifies that this equipment was enhanced due to outliers identified during the IPEEE program.* "New or Replaced" identifies this equipment as major new or replacement equipment.

• "Risk significant" identifies this equipment as risk significant.

The equipment class, safety function, and system designations used in Table A-2 are the same as Table A-I.Table A-2: Monticello SWEL 1 Equipment Description Class Safety System Comments Verify Defer?Tag Function Anchorage? 152-505 4KV TO P-208A 11 (03) Medium Voltage 3 4KV Yes Core Spray Pump Switchgear AO-2379 VACUUM RELIEF (07) Fluid-Operated PCT DAMPER Valves AO-2-80A INBOARD MSIV (07) Fluid-Operated 2,3,5 MST Yes Valves HARD PIPE VENT (07) Fluid-Operated Risk AO-4539 INBOARD ISOLATION () lu ed PCT VLEValves Significant VALVE 11 RHR SW PUMP P- (07) Fluid-Operated New or AV-3147 109A AUTO AIR Valves 4,5 RSW Replaced VENT 13 ESW PUMP P-AV-4024 111C DISCHARGE (07) Fluid-Operated 3,4, 5 FSW AIR VENT Appendix A -Equipment Lists A-32 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-2: Monticello SWEL I Equipment cSafety Verify Tag Description Class Function System Comments Anchorage? Defer?BPM-1, DC-BOOSTER PUMP (05) Horizontal 1 3, 4, 5 DGN Location 11 MOTOR Pumps DG BUS 15 4160 SWITCHGEAR (03) Medium Voltage 1,2, 3, 4, 4KV Yes Switchgear 5 RX AND CTMT (20) Instrumentation C-03 COOLING AND ISOL and Control Panels 2, 3, 4, 5 MSC BENCH BOARD and Cabinets C-122 JET PUMP (18) Instruments on REC Yes INSTRUMENT RACK Racks C-129A RHR INSTRUMENT (18) Instruments on 3, 4, 5 RHR Yes RACK Racks C-129B RHR INSTRUMENT (18) Instruments on 3,4,5 RHR Yes RACK Racks (20) Instrumentation C-253A SRV Panel and Control Panels 2 APR Yes and Cabinets DIV II LOLO SET (20) Instrumentation Internal C-253D and Control Panels 2 APR cabinetYes BYPASS PANEL and Cabinets inspection required C-290A SRV BLOWDOWN (18) Instruments on 2, 3 APR INST PANEL Racks (20) Instrumentation 1, 2, 3, 4, C-292 ASDS BENCHBOARD and Control Panels ASD Yes-and Cabinets RCIC CABLE SPR RM (20) Instrumentation C-30 and Control Panels 3 RCI Yes CONTROL PANEL adCbnt and Cabinets ECCS DIV I ANALOG (20) Instrumentation C-303A and Control Panels 3 PPS Yes and Cabinets (20) Instrumentation C-39 HPCI RELAY PANEL and Control Panels 3 HPC Yes and Cabinets Appendix A -Equipment Lists A-33 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-2: Monticello SWEL 1 Equipment, Description Class Safety System Comments Verify Defer?Tag Function Anchorage? Dfr INBOARD ISOLATION (20) Instrumentation C-41 RELAY PANEL and Control Panels 3, 5 PPS Yes and Cabinets C-55 RX LEVEL & (18) Instruments on 1,2,3,5 RPV Yes PRESSURE RACK Racks 11 DIESEL GEN (20) Instrumentation C-91 ELECTRICAL and Control Panels 1,3,4,5 DGN Yes and Cabinets 11 DIESEL GEN (20) Instrumentation C-93 CONTROL and Control Panels 1, 3,4, 5 DGN Yes Yes and Cabinets ORID HCU CRD HYDRALIC (18) Instruments on New or C CONTROL UNITS 1Racs 1 CRD 0 ewlor Yes W WEST SIDE Racks Replaced CRD16A SCRAM DISCHARGE (21) Tanks and Heat 1,3 CR0 VOLUME Exchangers CV-1728 11 RHR HX RHRSW (07) Fluid-Operated 4, 5 RSW OUTLET Valves HPCI STEAM LINE CV-2043 DRAIN TRAP (07) Fluid-Operated 3 HPC BYPASS CV-3-32A WEST SDV VENT (07) Fluid-Operated 1,3 CRH Valves D1 #11 BATTERY (15) Batteries on 1,2,3,4, 125 Risk Yes 125VDC Racks 5 Significant DIV2 125/250VDC (14) Distribution 1,2,3,4, Risk 0100 DISTRIBUTION Panels 5 250 Significant PANEL Dll DISTRIBUTION (14) Distribution 1,2, 3,4, 125 Risk Yes CENTR Panels 5 Significant CENTER 031 DIV 1125/250 VDC (14) Distribution 1,2,3, 4, 250 Risk Yes DISTRIBUTION Panels 5 Significant PANEL Appendix A -Equipment Lists A-34 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-2: Monticello SWEL 1 Equipment D i Safety System Comments Verify, Defer Tag Description ass Function Anchorage?

1. 13 (DIV 1) (15) Batteries on 1,2,3,4, Risk D3A 125/25BVDC Racks 250 Significant Yes BA-I-ERY "A"#13 (DIV 1) (15) Batteries on 1,2,3,4, Risk D3B 125/25OVDC ( atrs o 250 Risk Yes BTEYB"Racks 5 Significant BATT-ERY "B" Risk Significant, New or 125VDC SWING (16) Battery 1, 2or D40 CHARGER FOR #11 Chargers and ' , 125 Replaced,l AND #12 BATTERIES Inverters 5 Internal cabinet inspection required Risk SWING CHARGER (16) Battery Significant, SWN HRE1)Btey 1,2, 3, 4, 5 Internal Yes Yes D54 D3A,D3B 13 Chargers and ',2,3,' 250 cabinet BATTERY Inverters inet inspection required Risk CHARGER, SWING (16) Battery Significant, CHARGERInternal D90 D6A,D6B (16) Chargers and 1,2, 3, 4, 250 Inet Yes Yes BATTERY Inverters inet inspection required DM-889A1 V-SF-9 SUPPLY DM-8089A1 DAMPER (10) Air Handlers 1, 3, 4, 5 HTV DM-8089J1 V-SF-i 0 SUPPLY (10) Air Handlers 1, 3,4,5 HTV DAMPER FT-23-82 HPCI PUMP FLOW (18) Instruments on 3 HPC TRANSMITTER Racks#11 DG NEUTRAL G31 GROUNDING (04) Transformers 1, 3,4, 5 DGN Yes CABINET G-3A 11 EMERGENCY (17) Engine- 1,3,4,5 DGN Yes DIESEL GENERATOR Generators G-3B 12 EMERGENCY (17) Engine- 1,3,4,5 DGN Yes DIESEL GENERATOR Generators Appendix A -Equipment Lists A-35 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-2: Monticello SWEL 1 Equipment Description Class Safety System Comments AhVerify Defer?Tag Function Anchorage?

RHRSW AUX AIR K-10A COMP (12) Air Compressors 4,5 RSW Yes 11 EDG ELECTRIC/DIESEL AIR STARTER (12) Air Compressors 1,3,4,5 DGN Yes COMPRESSOR

1. 1 11 ELECTRIC AIR K-8B STARTER (12) Air Compressors 1, 3,4,5 DGN Yes COMPRESSOR
2. 2 LT-2-3-72A LO LO REACTOR LVL (18) Instruments on 2,3 RPV Risk ECCS INITIATION Racks Significant LO LO REACTOR LVL (18) Instruments on 2, 3 RPV Risk LT-2-3-72C ECCS INITIATION Racks Significant LT-2996 TORUS WATER (18) Instruments on PCT LEVEL Racks 480V AC MOTOR MCC-1 33B CONTROL CENTER (01) Motor Control 1,3,4,5 480 Risk Yes 133B Significant Internal MCC-134 480 V MCC (B34) (01) Motor Control cabinet Centers 1,3,4,5 480 inspection Yes required DIV 2 (HPCI) 250V DC (01) Motor Control Risk MCC-312 MOTOR CONTROL Contro 3 250 Risk Yes CETR32Centers Significant CENTER 312 Risk DIV 1 250V DC Significant, MCC-313 MOTOR CONTROL (01) Motor Control 2,3,5 250 Internal Yes Yes CENTER 313 Centers 2 cabinet inspection required 11 CS PUMP TORUS (08) Motor-Operated MO-1741 and Solenoid-3 CSP Operated Valves (08) Motor-Operated MO-201 0 TORUS SPRAY VLV and Solenoid-4, 5 RHR Operated Valves Appendix A -Equipment Lists A-36 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-2: Monticello SWEL I Equipment Description Class Safety System Comments Verify Defer?Tag Function Anchorage?

11 RHR LPCI (08) Motor-Operated MO-2012 OUTBOARD and Solenoid-3, 4 RHR INJECTION Operated Valves RHR/RHR B LPCI INJ (08) Motor-Operated MO-2013 OUTBD and Solenoid-3, 4 RHR Operated Valves RHR SHUTDOWN COOLING SUPPLY (08) Motor-Operated MO-2030 OO ARD and Solenoid-3, 4 RHR OUTBOARD Operated Valves ISOLATION (08) Motor-Operated MO-2063 HPCI CST SUCT and Solenoid-3 HPC Operated Valves RCIC TURBINE (08) Motor-Operated Risk MO-2078 and Solenoid-3 RCI Risk STEAM SUPPLY Operated Valves Significant RCIC PUMP (08) Motor-Operated Risk MO-2106 DISCHARGE and Solenoid-3 RCI Rigk OUTBOARD Operated Valves Significant MAIN STEAM LINE (08) Motor-Operated New or MO-2374 DRAIN -OUTBOARD and Solenoid-2, 3, 5 MST Replaced Yes Operated Valves 11 EDG AIR CMPSR 1 Internal N34A (K-8A) LOCAL (20) Instrumentation N3346A and Control Panels 1,3, 4, 5 DGN cabinet Yes DISCONNECT and Cabinets inspection SWITCH required MOTOR STARTER (20) Instrumentation cabinet ernal N3347 FOR KS1A and Control Panels 4,5 RSW inspection Yes and Cabinets required 11 EDG AIR CMPSR 2 Internal (K-8B) LOCAL (20) Instrumentation N4301A (K-8CONCAL and Control Panels 1, 3, 4, 5 DGN cabinet Yes DISCONNECT and Cabinets inspection SWITCH required P-1 09A 11 RHR SW PUMP (06) Vertical Pumps 4, 5 RSW New or Yes Replaced P-1 1 DIESEL OIL XFER (05) Horizontal 1,3,4,5 DOL Yes PUMP Pumps Appendix A -Equipment Lists A-37 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-2: Monticello SWEL 1 EqimetSaeyVerify Equipment Description Class Safety Comments Verify Defer?Tag Function Anchorage? P-111A 11 ESW (EDG-ESW) (06) Vertical Pumps 1, 3, 4, 5 ESW Yes PUMP P-111c 13 ESW (EDG-ESW) (06) Vertical Pumps 3, 4, 5 FSW New or Yes PUMP Replaced P-202C 13 RHR PUMP (06) Vertical Pumps 3, 4, 5 RHR New or Yes Replaced P-203A 11 SBLC Pump (05) Horizontal 1 SLC Yes Pumps P-208A 11 CORE SPRAY (06) Vertical Pumps 3 CSP PUMP P-209 HPCI PUMP (05) Horizontal HPC Risk Yes Pumps Significant P-222A 11 DG FUEL (05) Horizontal 1, 3, 4, 5 DGN TRANSFER PUMP #1 Pumps Internal P-73A 480V POWER PANEL (14) Distribution cabinet Panels 4, 5 480 inspection Yes Yes required ECCS AREA DRAIN P-88A PUMP (06) Vertical Pumps 3, 4, 5 LRW PS-23-97A HPCI HI TURB EXH (18) Instruments on HPC Risk PRESS TURB TRIP Racks Significant RV-1990 RHR 11 PUMP (07) Fluid-Operated 3,4,5 RHR SUCTION RV Valves RV-2-71A A SRV (07) Fluid-Operated 2 APR Risk Yes Valves Significant CV-1 728 (11 RHR HX (08) Motor-Operated SV-1 728 and Solenoid-4, 5 RSW Yes RHRSW OUTLET)SV Operated Valves ALT N2 A SPLY TO (08) Motor-Operated SV-2379 and Solenoid-5 PCT Operated Valves T-200 Standby Liquid Control (21) Tanks and Heat 1 SLC Yes Tank Exchangers Appendix A -Equipment Lists A-38 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-2: Monticello SWEL I Equipment Description Class Safety System Comments Verify Defer?Tag Function Anchorage? STANDBY DIESEL T-45A GENERATOR DAY (21) Tanks and HeatDOL Yes TANK Exchangers STANDBY DIESEL T-45B GENERATOR DAY (21) Tanks and HeatDOL Yes TANK Exchangers T-75A ACCUMULATOR FOR (21) Tanks and Heat 3, 4, 5 RHR SV-1 994 Exchangers T-79D 11 DGAIRTKD (21) Tanks and Heat 1,3,4,5 DGN IPEEE Yes Exchangers Enhanced T-80A 12 DG AIR TK A (21) Tanks and Heat 1 D IPEEE Yes Exchangers 1, Enhanced T-ALTN2B ALT N2 B BOTTLE (21) Tanks and Heat RACK Exchangers 2, 5 AN2 RCIC STM LINE HI TS-13-79C AREA (19) Temperature 2, 3, 5 RCI TEMPERATURE Sensors ISOLATION V-AC-5 RHR A AIR HANDLER (10) Air Handlers 3, 4, 5 HTV Yes V-EAC-14A CRV DIV I HVAC (11) Chillers 1, 2, 3,4, EFT UNIT 5 DIV II 250VDC 1,2,3,4, New or V-EF-40A BATTERY ROOM (10) Air Handlers 5 EFT Replaced VENTILATION DIV II 250VDC 1,2,3,4 Newor V-EF-40B BATTERY ROOM (10) Air Handlers 5 EFT Replaced VENTILATION V-ERF-14A CRV DIV I EXHAUST (10) Air Handlers 1,2,3,4, EFT RECIRC FAN 5 DIV 1 EFT 1234 V-FE-11 CHARCOAL AIR (10) Air Handlers 5 EFT FILTER UNIT V-SF-1 0 11 DIESEL ROOM (09) Fans 1,3,4,5 HTV Yes VENT FAN Appendix A -Equipment Lists A-39 Monticello Nuclear Generating Plant Seismic Walkdown Report Table A-2: Monticello SWEL 1 Equipment Description Class Safety System Comments Verify Defer?Tag Function Anchorage? 12 DIESEL ROOM V-SF-9 VENT FAN (09) Fans 1, 3, 4, 5 HTV Yes X30 TRANSFORMER (04) Transformers 1, 3, 4, 5 480 120 VDC 1,2,34 Y72 TRANSFORMER (04) Transformers , , UAC Yes FEEDING Y73 Internal (16) Battery Itra Y81 DIV 2 120VAC CLASS Chargers and 1,2, 3, 4, AC cabinet Yes Yes 1E INVERTER Inverters 5 inspection required Appendix A -Equipment Lists A-40 Monticello Nuclear Generating Plant Seismic Walkdown Report B Seismic Walkdown Checklists (SWCs)This appendix provides the Seismic Walkdown Checklists (SWC) completed as of November 1, 2012 for the MNGP. Table B-1 provides a description of each item, anchorage configuration verification, and the checklist status for each SWC. If a checklist status is marked "Y," then the SWEs concluded in the field that the equipment was seismically acceptable. If a checklist status is marked as "N," then the SWEs judged there was a potential adverse condition which required additional information to determine if the equipment was seismically adequate, complied with current site procedures and met the current licensing basis requirements. None of the observations noted in the SWCs were found to be adverse seismic conditions that significantly affected or degraded safety related functions of equipment. Appendix F of this report provides the disposition of all observations noted in the SWCs.The SWCs are provided after this table, and are in the same chronological order as listed in the table.The SWCs in this appendix include information on the location of SWEL components, which is considered Sensitive Unclassified Non-Safeguards Information (SUNSI), of which the loss, issue, modification, or unauthorized access can reasonably be foreseen to harm the safe operation of the nuclear plant. Pages which contain proprietary information have been marked, and the sensitive information has been redacted.Table B-I: Monticello Completed SWCs Equipment Description Anchorage Checklist Tag Verified Status (Y/N)AO-2379 VACUUM RELIEF DAMPER Y AO-4539 HARD PIPE VENT INBOARD ISOLATION VALVE N AV-3147 11 RHR SW PUMP P-109A AUTO AIR VENT Y AV-4024 13 ESW PUMP P-1 11C DISCHARGE AIR VENT Y BPM-1, Location 11 DC-BOOSTER PUMP MOTOR Y DG Appendix B -Seismic Walkdown Checklists B-1 Monticello Nuclear Generating Plant Seismic Walkdown Report Table B-I: Monticello Completed SWCs Equipment Description Anchorage Checklist Tag Verified Status (Y/N)C-03 RX AND CTMT COOLING AND ISOL BENCH BOARD N C-122 JET PUMP INSTRUMENT RACK Yes N C-129A RHR INSTRUMENT RACK Yes Y C-129B RHR INSTRUMENT RACK Yes Y C-253A SRV Panel Yes Y C-290A SRV BLOWDOWN INST PANEL Y C-292 ASDS BENCHBOARD Yes Y C-30 RCIC CABLE SPR RM CONTROL PANEL Yes Y C-303A ECCS DIV I ANALOG TRIP SYSTEM Yes Y C-39 HPCI RELAY PANEL Yes Y C-41 INBOARD ISOLATION RELAY PANEL Yes Y C-55 RX LEVEL & PRESSURE RACK Yes Y CRD HCU CRD HYDRALIC CONTROL UNITS WEST SIDE Yes N W CRD16A SCRAM DISCHARGE VOLUME -Y CV-1728 11 RHR HX RHRSW OUTLET -Y CV-2043 HPCI STEAM LINE DRAIN TRAP BYPASS -Y CV-3-32A WEST SDV VENT -Y D1 #11 BATTERY 125VDC Yes Y D100 DIV 2 125/250 VDC DISTRIBUTION PANEL Y Appendix B -Seismic Walkdown Checklists B-2 Monticello Nuclear Generating Plant Seismic Walkdown Report Table B-1: Monticello Completed SWCs Equipment Description Anchorage Checklist Tag Verified Status (Y/N)D31 DIV 1 125/250 VDC DISTRIBUTION PANEL Yes Y D3A #13 (DIV 1) 125/25OVDC BATTERY "A" Yes Y D3B #13 (DIV 1) 125/25OVDC BATTERY "B" Yes Y DM-8089A1 V-SF-9 SUPPLY DAMPER Y DM-8089J1 V-SF-10 SUPPLY DAMPER Y FT-23-82 HPCI PUMP FLOW TRANSMITTER Y G-3A 11 EMERGENCY DIESEL GENERATOR Yes Y G-3B 12 EMERGENCY DIESEL GENERATOR Yes Y K-10A RHRSW AUX AIR COMP Yes Y K-8A 11 EDG ELECTRIC/DIESEL AIR STARTER Yes Y COMPRESSOR

1. 1 K-8B 11 ELECTRIC AIR STARTER COMPRESSOR
2. 2 Yes Y LT-2-3-72A LO LO REACTOR LVL ECCS INITIATION Y LT-2-3-72C LO LO REACTOR LVL ECCS INITIATION Y LT-2996 TORUS WATER LEVEL Y MO-1741 11 CS PUMP TORUS SUCTION Y MO-2010 TORUS SPRAY VLV Y MO-2012 11 RHR LPCI OUTBOARD INJECTION Y MO-2013 RHR/RHR B LPCI INJ OUTBD Y MO-2030 RHR SHUTDOWN COOLING SUPPLY OUTBOARD Y ISOLATION Appendix B -Seismic Walkdown Checklists B-3 Monticello Nuclear Generating Plant Seismic Walkdown Report Table B-I: Monticello Completed SWCs Equipment Description Anchorage Checklist Tag Verified Status (YIN)MO-2063 HPCI CST SUCT Y MO-2078 RCIC TURBINE STEAM SUPPLY Y MO-2106 RCIC PUMP DISCHARGE OUTBOARD Y P-109A 11 RHR SW PUMP Yes Y P-11 DIESEL OIL XFER PUMP Yes Y P-111A 11 ESW (EDG-ESW)

PUMP Yes Y P-111C 13 ESW (EDG-ESW) PUMP Yes Y P-202C 13 RHR PUMP Yes Y P-203A 11 SBLC Pump Yes N P-208A 11 CORE SPRAY PUMP Y P-209 HPCI PUMP Yes N P-222A 11 DG FUEL TRANSFER PUMP #1 -Y P-88A ECCS AREA DRAIN PUMP -N PS-23-97A HPCI HI TURB EXH PRESS TURB TRIP -Y RV-1990 RHR 11 PUMP SUCTION RV -Y SV-1 728 CV-1728 (11 RHR HX RHRSW OUTLET)SV Yes Y SV-2379 ALT N2 A SPLY TO AO-2379 Y T-200 Standby Liquid Control Tank Yes N T-45A STANDBY DIESEL GENERATOR DAY TANK Yes Y T-45B STANDBY DIESEL GENERATOR DAY TANK Yes Y Appendix B -Seismic Walkdown Checklists B-4 Monticello Nuclear Generating Plant Seismic Walkdown Report Table B-1: Monticello Completed SWCs Equipment Description Anchorage Checklist Tag Verified, Status (Y/N)T-75A ACCUMULATOR FOR SV-1994 Y T-79D 11 DGAIRTKD Yes Y T-80A 12 DG AIR TK A Yes Y T-ALTN2B ALT N2 B BOTTLE RACK Y TS-13-79C RCIC STM LINE HI AREA TEMPERATURE ISOLATION Y V-AC-5 RHR A AIR HANDLER Yes Y V-EAC-14A CRV DIV I HVAC UNIT Y V-EF-40A DIV II 250VDC BATTERY ROOM VENTILATION Y V-EF-40B DIV II 250VDC BATTERY ROOM VENTILATION Y V-ERF-14A CRV DIV I EXHAUST RECIRC FAN Y V-FE-11 DIV 1 EFT CHARCOAL AIR FILTER UNIT Y V-SF-10 11 DIESEL ROOM VENT FAN Yes Y V-SF-9 12 DIESEL ROOM VENT FAN Yes N X30 TRANSFORMER Y Y72 120 VDC TRANSFORMER FEEDING Y73 Yes Y Appendix B -Seismic Walkdown Checklists B-5 PR.PRIT..ARY INFO.RMATION WT...... .FROM PUYBLIC 'ICLOGURE Sheet i of 4 Status: YZ NE] U[[]Seismic Walkdown Checklist (SWC)Equipment ID No. A0-2379 Equip. Class, (07) Fluid-Operated Valves Equipment Description Vacuum Relief Damper Location: Bldg. RX Floor El. Room, Area Torus Catwalk Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YEI NZ 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more, than mild surface oxidation?

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

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

YEI] NEI UIE N/AN YE] NE] UD N/A[D YEI NEI UEI N/AM YE] NEI UE] N/ANUE3 I Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 4 Status: YN NZ-- U[-Seismic Walkdown Checklist (SWC)Equipment ID No. A0-2379 Equip. Class, (07) Fluid-Operated Valves Equipment Description Vacuum Relief Damper Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YO NEIl UIZ N/AE3 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YER NEI UE- N/A[-and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NEI UE N/AOl YE NEI UD Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory A Steve Kaas Date: ,, 2-/f-Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI" WITHHOLD FROM PUBIL!C DISCLOSURIRE The remaining pages are withheld from public disclosure. Sheet 1 of 6 Status: Y L-- NO UL-Seismic Walkdown Checklist (SWC)Equipment ID No. A0-4539 Equip. Class 1 (07) Fiuid-Operated Valves Equipment Description Hard Pipe Vent Inboard Isolation Valve Location: Bldg. RX Floor El. ý _ Room, Area Torus Catwalk Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of:an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE[ NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YE-1 NEI UEi N/AI YEI NEI UE' N/AO YEI NEI UE N/AZ YE NE UE N/AZ Y0 NEI UE-1 Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 6 Status: YE] NOZ U0I-Seismic Walkdown Checklist (SWC)Equipment ID No. A0-4539 Equip. Class, (07) Fluid-Operated Valves Equipment Description Hard Pipe Vent Inboard Isolation Valve Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NE] U-1 N/Al]8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO NEI U[L N/AL]and masonry block walls not likely to collapse onto the equipment? SWEs noted JB 2J4245 has 3 bolts instead of 4 anchoring it to ceiling.SWEs judge JB has adequate seismic capacity for anticipated seismic loads.9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YED NE] U-] N/AI-YN NE UEI Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could YE] NEI UFL adversely affect the safety functions of the equipment? SWEs noted 2G4007 conduit is used as anchor point to tie together other power cables using tie wraps. Also noted electrical tape used to hold up power cables at connection point on valve.Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lorv Date: -0A8 /2-Z- ' z .Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI W-ITHHOLD FROfi PUJ-B-LIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIET/ARY INFORMATION WITI 1 19OLD FRO.M P,-UBIC DISCLOSURE Sheet 1 of 5 Status: Y[Z NE] U[1 Seismic Walkdown Checklist (SWC)Equipment ID No. AV-3147 Equip. Class, (07) Fluid-Operated Valves Equipment Description 11 RHR SW Pump P-109A Auto Air Vent Location: Bldg. INTAK Floor El _ Room, Area Main Room Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Y[[ NED 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation? YO NEI Uf-S N/A[YES NEI U- N/A[D 4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YS NE US N/AN YO NOI US N/AZ YM NFO UE]I Enter the equipment class name from Appendix B: Classes of Equipment. PROPRIETARY INFO'RMATION WITI HLD 969 FROM DI CL"OURE Sheet 2 of 5 Status: YIZ N[- U[Seismic Walkdown Checklist (SWC)Equipment ID No. AV-3147 Equip. Class' (07) Fluid-Operated Valves Equipment Description 11 RHR SW Pump P-109A Auto Air Vent Interaction Effects 7. Are soft targets free 'from impact by nearby equipment or structures? Y[ NEI UiJ N/AEl 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UEL N/AEl and masonry block walls not likely to collapse onto the equipment? Fire protection spray piping is seismically supported.

9. Do attached lines have adequate flexibility to avoid damage?No attached lines.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YE] NEI Uf] N/AZ Y NE-I UEF Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) 'I __/Evaluated by: Evatlu atebie: eDat illf- ///L-9/0I a-Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet i of 4 Status: YN NM- UE-]Seismic Walkdown Checklist (SWC)Equipment ID No. AV-4024 Equip. Classi (07) Fluid-Operated Valves Equipment Description 13 ESW Pump P-111C Discharge Air Vent Location: Bldg. INTAK Floor El. ._ Room, Area Main Room Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO NN 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YE NE UE N/Aft YE NEI UE N/A[D YE NEI UE N/AN YE- NE UE N/AN YZ NE] U 1 Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 4 Status: Y[ N[-- U-Seismic Walkdown Checklist (SWC)Equipment ID No. AV-4024 Equip. Class'. (07) Fluid-Operated Valves Equipment Description 13 ESW Pump P-1 11C Discharge Air Vent Interaction Effects 7. Are soft targets .free from impact by nearby equipment or structures? YN NEI UD N/AUl 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI US- N/AEl and masonry block walls not likely to collapse onto the equipment? Fire protection spray lines above are seismically supported.

9. Do attached lines have adequate flexibility to avoid damage?No attached lines.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YI- NE USI N/Au YO NEI US Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 NEI UI1 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary) Evaluated by: Walter Diordievic z" Date: r12 -//7-Scott Luckiesh Scott Luckiesh 4 Lý-L"--l by Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBgLIC DISCLOSURE The remaining pages are withheld from public disclosure. ! tJ ' I HLI.. I I I1\IU. .. II.L U: U II ~ .L ~I Sheet 1 of 4 Status: Y[ NE] UL-Seismic Walkdown Checklist (SWC)Equipment ID No. BPM-1 Equip. Class' (05)Horizontal Pumps Equipment Description DC-Booster Pump Motor Location: Bldg. TB Floor El. Room, Area 11 DG ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This chlecklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE] NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YEO NO UrI N/AO YE] NEI UL N/A[YO] NEIl u-i N/AO YE NEI Ur N/AO YO NO UEr I Enter the equipment class name from Appendix B: Classes of Equipment. ii aji [1L1,';KY

r'P'u.3:VI;'I;U:

xvv: <. -,';U .;;,L ,,,.-L., Sheet 2 of 4 Status: NO U0I Seismic Walkdown Checklist (SWC)Equipment ID No. BPM-1 Equip. Class 1 (05)Horizontal Pumps Equipment Description DC-Booster Pump Motor Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YH NE U-I N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NO U[I- N/AD and masonry block walls not likely to collapse onto the equipment?

• Fire protection piping is seismically designed -that is, it has been engineered with lateral supports.9. Do attached lines have adequate flexibility to avoid damage?No potential for relative movement.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 ND UD N/AD YN NEI U-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated Date: Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUB-R-LIC DISCLOSURE PROPRIE=T-An IINF-RMATIGN WITHHOLD01= FROM PUBLIC DISCLOSURE Sheet 1 of 5 Status: Y-I NO UD--Seismic Walkdown Checklist (SWC)Equipment ID No. C-03 Equip. Class 1 (20) Instrumentation and Control Panels and Cabinets Equipment Description RX and CTMT Cooling.and ISOL Bench.Board Location: Bldg. Admin Floor El.ý _ Room, Area CR Manufacturer, Model, Etc. (optional but recommended) Instructions 'for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YN NO UE- N/A[YE NE] U- N/AO YN NE] U- N/AL YE] NOE U] N/A' IEnter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 5 Status: Y[-] NO u[]Seismic Walkdown Checklist (SWC)Equipment ID No. C-03 Equip. Class, (20) Instrumentation and Control Panels and Cabinets Equipment Description RX and CTMT Cooling and ISOL Bench Board Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI UL- N/All 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI U-- N/A--and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on. the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NEI Ur1 N/AU YZ NI UiU Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YEr NED UU-1 adversely affect the -safety functions of the equipment?

Door connecting front and back panels is free to swing. Door could impact C-03 in seismic event and is a seismic interaction issue.Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory Date:Oh0 2 Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUJNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure.

1:3: I ~IL I .'x: Ir:: U: :rx'. I ,ur.~I I 1111KW I ~r.1 ULALIL UI~KLU~UI

1 Sheet i of 16 Status: YE] NO U[]Seismic Walkdown Checklist (SWC)Equipment ID No. C-122 Equip. Class, (18) Instruments on Racks Equipment Description Jet Pump Instrument Rack Location:

Bldg. RX Floor El. ý _ Room, Area East Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the, results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YN NEI of the 50% of SWEL items requiring such verification)? 5 legs -1/2" bolts plus 2 legs x (2)-112" bolts.2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

Pictures were taken of each leg starting with the south end. Floor bolts are combination of 3/8" and 1/2" bolts. Anchorage does not match calculation. Also one bolt apprears not fully threaded.6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions? YN NE UE N/AE YN NEI UE N/A[YO NE UE N/A-YE NZ UE N/AE YN N- Ur I Enter the equipment class name.from Appendix B: Classes of Equipment. PRI)PRIETARY INFI-RMATIlN WITI II IOLD FrflM PrEUl PII9IlOlURE Sheet 2 of 16 Status: YE] NE UI--Seismic Walkdown Checklist (SWC)Equipment ID No. C-122 Equip. Class, (18) Instruments on Racks Equipment Description Jet Pump Instrument Rack Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI ULI N/AU 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YI NUI UU N/AUl and masonry block walls not likely to collapse onto the equipment? Noted overheadlighting all rod hung on long rods. This system will have pendulum motion -in earthquake. Lighting system higher than rack, so it will not impact rack. System has good seismic capacity.9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NUI UU N/AU YO NI UEU Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) On a concrete pad. 10 x 1/2" diameter expansion anchor bolts.Evaluated by: BruceM Lory Evalate by Brce .Ln, ate 6a 021-Az.Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report S'JNS- WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY .IFORMATION WITHI 1OLD rnFROM PUBLIC DC',OLOCURE Sheet 1 of 8 Status: YZ NE] uF]Seismic Walkdown Checklist (SWC)Equipment ID No. C-129A Equip. Class, (18) Instruments on Racks Equipment Description RHR Instrument Rack Location: Bldg. RX FloorEI. E Room, Area A RHR.ROOM Manufacturer, Model, Etc. (optional but recommended) Iiistiuctions for Completing Checldist This checklist may'be used to document the results of the Seismic Walkdown of an item of equipment on the*SWEL. The spade below each of.the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist foi documenting other commenis.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YO NO of the 50%of SWEL items requiringsuch verification)?

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

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

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

Four 1/2" diameter through bolts into platform grating. It also has a unistrut brace to wall using two bolts Into wall via unistrut.YI0 NO UO N/AD YO NE UO N/AO YO NO UQ N/ADNEI UI N/AO Yi NEUD'Enter the equipmcnt'class name from Appendix B: Classes of EquipnientL PROPRIF- TARY WITI i OLD FRrM PUBlIC IClOSURE Sheet 2 of 8 Status: YN Nil] UE]Seismic Walkdown Checklist (SWC)Equipment ID No. C-129A Equip. Class' (18) Instruments on-Racks Equipment Description RHR Instrument Rack Interaction Effects 7. Are soft-targets free from impact by nearby equipment or structures? YJA NEI U-- N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0D NEI UI" N/ADI and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YO NEI U'- N/ADl 10. Based on the above seisimic interaction evaluations, is" equipment free YO ND UDI of potentially adverse seismic interaction effects?Other Adverse Conditions

11. Have you looked, for and found no othei seismicconditions that-could Y0 NI] U0 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary) 14 Evaluated by: Bruce M. Lorv Date: , 4010 Steve Kaas A/A//Z I If Monticello Nuclear Generating Plant Seismic Walkdown Report 0I IKQl IAIIIITrUUfIl M DfI131I II 1 l% nied'I ^Oi IDr-The remaining pages are withheld from public disclosure. PROPRIETARY I'FORM,^AT',O,) WIT,-1 IOLD FROM PUBLIC DISCLOSURE Sheet 1 of 9 Status: YN NR U-Seismic Walkdown Checklist (SWC)Equipment ID No. C-129B Equip. Class' (18) Instruments on Racks Equipment Description RHR Instrument Rack Location: Bldg. RX Floor El. ý _ Room, Area B RHR Room Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Y NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

The bolt pattern depicted in calculation 99-015 matches field configuration. YED NEI ULi N/Al]YO NE] Uil N/AZ YEI NE] Uil N/A[D Y0 NEI Ur N/AL]YO NEI UEr 1 Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 9 Status: Y0 NEI UZI Seismic Walkdown Checklist (SWC)Equipment ID No. C-129B Equip. Class" (18) Instruments on Racks Equipment Description RHR Instrument Rack.Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? Y2 NE U[3 N/AU 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YIE NOi UI- N/A'-and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO NEI UEI N/AUI YE NEI UE-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) (2) -1/2" diameter thru bolts per foot. 4 bolts total per SQUG SEWS.Evaluated by: Bruce M. Lory Evaluated by: Bruce M. Lorv Date: Sz ~Steve Kaa.s Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSU-.I WITHHOLD FROM PURLIC DICLOSIURI.E The remaining pages are withheld from public disclosure. i I I ~ ~ j~.:Iu. .. 11:L ulIU H JLIti[I Sheet 1 of 4 Status: YZ NEI U[-Seismic Walkdown Checklist (SWC)Equipment ID No. C-253A Equip. Class' (20)lnstrumentation and Control Panels and Cabinets Equipment Description SRV Panel Location: Bldg. ADMIN Floor El. ý _ Room, Area CSR Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YU NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation? YO NEI U[I N/AEl YN NEI UL N/AZ 4. Is the anchorage free of visible cracks in the concrete nearthe anchors? YE NEI U- N/AO 5. IS the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

As built: four bolts anchoring panel to baseplate. Four more bolts anchoring baseplate to concrete, as-built configuration matches anchorage documented in SQUG SEWS.Y[ NEI U- N/AO YED NEI UED'Enter the equipment class name from Appendix B: Classes of Equipment. PPAPPIF-T-A P3ApI-j -(jp, ý A 4JTWW(Z)I P FPAP4 PI IR I Ir PIRr I PrýI 1PF_Sheet 2 of 4 Status: NE] UL-]Seismic Walkdown Checklist (SWC)Equipment ID No. C-253A Equip, Class' (20)Instrumentation and Control Panels and Cabinets Equipment Description SRV Panel Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? Y0 NEI UEO N/AEU 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ ND U- N/A]and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI UO N/AUI YO NI UE-Other Adverse Conditions

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

SWEs noted 1/4" gap which was the same gap as reported in SQUG project, which was determined acceptable. Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Loa Steve Kaas Date: 2 ,- Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROMA P'LIRIC DIRCLOUP.RF The remaining pages are withheld from public disclosure. Sheet 1 of 5 Status: Y0 N[" U'-Seismic Walkdown Checklist (SWC)Equipment ID No. C-290A Equip. Class, (18) Instruments on Racks Equipment Description SRV Blowdown Inst. Panel Location: Bldg. RX Floor El. Room, Area Torus Area Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YD NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

Y0 NC-- U- N/All YS NCI UC N/AC Y0 NC UC N/ACl YC NC UC N/AS YO NEI UC I Enter the equipment class name from Appendix B: Classes of Equipment. PRPRITR ARnMATIAN W!THIf RMP~lI l~iOUR Sheet 2 of 5 Status: YZ NEI U[I Seismic Walkdowt Checklist (SWC)Equipment ID No. C-290A Equip. Classi (18) Instruments on Racks Equipment Description SRV Blowdown Inst. Panel Interaction Effects.7. Are soft targets free from impact by nearby equipment or structures? Y0 NEI U[! N/Al 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0 NEI UD N/AO and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?No relative displacement of equipment and lines.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YED NEI UI" N/AD YN NEI UO Other Adverse Conditions

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

Hand cart is located near panel but it is chained/secured to structure and will not impact equipment. Comments (Additional pages may be added as necessary) Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS- WITHHOLD FROM PURBLIC DISCLOSURE The remaining pages are withheld from public disclosure.

"i

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"..i ', HHU'.LUIA If I 'UUL.I. Sheet 1 of 2 iStatus: Y[9 NE-- U[-Seismic Walkdown Checklist (SWC)Equipment ID No. C-292 Equip. Class, (20) Instrumentation and Control Panels and ,Cabinets Equipment Description ASDS Benchboard Location: Bldg. EFT Floor El. ý _ Room, Area South Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification.required (i.e., is the item one of the 50% of SWEL items requiring, such verification)? YN NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation? YN NEI U-I N/AE Y[O NEI U-1 N/AEl 4. Is the anchorage free of visible cracks in the concrete near the anchors? YO NE] UE' N/AE-5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YO NEI UE N/AE]NE UEO' Enter the equipment class name from Appendix B: Classes of Equipment. .,...I .HI T-",IARY ..i";U1(MA " 1u 'Wll HI LU I I F UM U IGULGU ,lF Sheet 2 of 2*Status: YN NEI UL-Seismic Walkdown Checklist (SWC)Equipment ID No. C-292 Equip. Class, (20) Instrumentation and Control Panels and Cabinets Equipment Description ASDS Benchboard Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YZ NEI UrI N/AZ 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ N-- UE- N/AZ and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 NOI U-- N/AZ YE NEI U-1 Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) 28" of 3/16" fillet weld. Similar mounted weld through midsection. (4) -. 5/8" Hilti bolts located on front side. This was documented in SQUG SEWS.Evaluated by: Bruce M. Lory A ,*A Steve Kaas Date: 6F-Sheet 1 of 4 Status: YE NEI U--Seismic Walkdown Checklist (SWC)Equipment ID No. C-30 Equip. Class' (20) Instrumentation and Control Panels and Cabinets Equipment Description RCIC Cable SPR RM Control Panel Location: Bldg. ADMIN Floor El. Room, Area CSR Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist, may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YN NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation? YO NEI UI- N/AZ YO NOl U[] N/AZl 4. Is the anchorage free of visible cracks in the concrete near the anchors? YZ NEI UD N/AZl 5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YO NZI U1 N/AZ YN NEI UZ' Enter the equipment class name from Appendix B: Classes of Equipment. PROPRIET-ARY I".FORMATIO,"'N WITI It OLD FROM PUBLIC DISCLOSURE Sheet 2 of 4 Status: Y[ NEI U-Seismic Walkdown Checklist (SWC)Equipment ID No. C-30 Equip. Class' (20) Instrumentation and Control Panels and Cabinets Equipment Description RCIC Cable SPR RM Control Panel Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI UE] N/AEJ 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UI--I N/AD and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?The flexible and rigid conduits are adequate for seismic loading.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YE NEI UE1 N/AEl YE NEI UI--Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory Al4ýDate: 9/02 2.Steve Kaas f --7 Y'LI. Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DSCLOSURE The remaining pages are withheld from public disclosure. PROPRIFETA.RY INFORMATION WITl 19OLD FROM PUDLI'C DIECLOCURE Sheet 1 of 5 Status: YN NEI U[-]Seismic Walkdown Checklist (SWC)Equipment ID No. C-303A Equip. Class 1 (20) Instrumentation and Control Panels and Cabinets Equipment Description ECCS Div 1 Analog Trip System Location: Bldg. ADMIN Floor El. ý _ Room, Area CSR Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipmenton the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Y NiO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YO NI] UI- N/A[l YN NEI UL N/AOl YO NEI UL N/AL]YN NEI U- N/AU YN NEI U-IEnter the equipment class name from Appendix B: Classes of Equipment. iRO1 RIETARi IP4F--RMATliO--l WITH HO iLiD -FROM PUB6lI D IICIL -URE Sheet 2 of 5 Status: Yl NEL uil-Seismic Walkdown Checklist (SWC)Equipment ID No. C-303A Equip. Class, (20) Instrumentation and Control Panels and Cabinets Equipment Description ECCS Div I Analog Trig System Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YO NEI UEI N/AE: 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEI UI- N/AL!and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?Rigid and flexible conduits are adequate.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y NEI' urn N/AFl YO NrI ur-Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YO NEI Ur1 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory/ ~Date: 0 V16 2//,z_g7 //2-.Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRE=T-ARY INFORMATION)P WIT! Qi OGLD FflOM PUOLICG PIGGCLOSRE Sheet 1 of 4 Status: YJ NEI-- U-Seismic Walkdown Checklist (SWC)Equipment ID No. C-39 Equip. Class, (20) Instrumentation and Control Panels and Cabinets Equipment Description HPCI Relay Panel Location: Bldg. Admin .Floor El. ý _ Room, Area CSR Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YZ NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

Y10 NEI U-] N/AU YE! NEI UE N/AM YE NE! U-] N/Al YIE NE! U! N/AU YN NEI U!]I Enter the equipment class name from Appendix B: Classes of Equipment. P~f~fIF~f" r~nRPTC~ WIT.HIf O RI 1 Irl flI~r! 0 0 1fF.Sheet 12 of 4 Status: YZ NE] U[-Seismic Walkdown Checklist (SWC)Equipment ID No. C-39 Equip. Class' (20) Instrumentation and Control Panels and Cabinets Equipment Description HPCI Relay Panel Interaction Effects 7. Are soft targets free from impactby nearby equipment or structures? YZ NEI Ul N/AOl 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ Nil UOi- N/Al]and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NI] UFI N/AlO YE NOL U Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y9 NEl U-1 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory J D ate f7 -Stinve Kaa.q Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBILIC DISCLO'JRE The remaining pages are withheld from public disclosure. P149PRIETARY INFOGRMATION WITI 11 OL61 FROW PUBLIC 9DIECLOSJFlE Sheet i Of 7 Status: YN N-- UEI Seismic Walkdown Checklist (SWC)Equipment ID No. C-41 Equip. Class, (20) Instrumentation and Control Panels and Cabinets Equipment Description Inboard Isolation Relay Panel Location: Bldg. ADMIN Floor El. Room, Area CSR Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YN NE 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

The as-built configuration of the anchorage shows four anchors symmetric around base, about 12" apart.'Enter the equipment class name from Appendix B: Classes of Equipment. YZ NE UEL N/AU YO NiO UE N/AD YO NEI UL1 N/AU YO NEI UE1 N/AU YE NI UUU PROPRIETARY INFORMATIO:N WITHHOLD FROM PUBLIC DISCLOSURF Sheet 2 of 7 Status: YZ NEI UIIr-Seismic Walkdown Checklist (SWC)Equipment ID No. C-41 Equip. Class' (20) Instrumentation and Control Panels and Cabinets Equipment Description Inboard Isolation Relay Panel Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? Intercom system and chair are within one foot of C-41. Intercom is not mounted. It is resting on a table fixed to Wall. Recommendation made to move chair and move or secure intercom system.YN NI] Ur] N/Ar-8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YID NI] UFJ N/A[-and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NI] U-] N/AU YU NI UF-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) SWE's notes: The drywell leak rate timer box is mounted on side of C-41. The box is adequately anchored to the side of C-41 with four bolts.~4 Evaluated by: Bruce M. Lory/Date: 6R/oz A Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSU RE The remaining pages are withheld from public disclosure. Sheet 1 of 7 Status: YN N-] U[-]Seismic Walkdown Checklist (SWC)Equipment ID No. C-55 Equip. Class" (18) Instruments on Racks Equipment Description RX Level & Pressure Rack Location: Bldg. RX Floor El.. Room, Area South Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The-space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Y[ NEI 2. Is the anchorage free of bent, broken, missing or lOose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation? Slight surface oxidation on nut. SWEjudged this as no issue.4. Is the anchorage free of visible cracks in the concrete near the anchors?No cracks -good condition.

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

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

YZ NEI UE- N/AZ YN NEI Ur1 N/An YER NEI UE N/AZ YZ NEI UE N/Ar-YE NEI Ur1 I Enter the equipment class name from Appendix B: Classes of Equipment. IIxU: AM (y 1-. ir i .U..PU .x r.( Vi -ii ..ULU : I Ib=:.a (U-UL '=t.U.b I 1 Sheet 2 of 7 Status: YZ N-I U-1 Seismic Walkdown Checklist (SWC)Equipment ID No. C-55 Equip. Class' (18) Instruments on Racks Equipment Description RX Level & Pressure Rack Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI UL- N/AZJ 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEI UI- N/AZI and masonry block walls not likely to collapse onto the equipment? Duct work is ductile. Per drawing NF-36300-1-2, Fig 3-1D all masonry block walls are safety-related and seismically evaluated. Floor drain pipe above is welded steel and is acceptable.

9. Do attached lines have adequate flexibility to avoid damage?Instrument rack is braced and rigid so no potential for relative movements.

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YE NEI UZ N/AZ YN NEI UZ Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 NEI UZ-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary) Monticello Nuclear Generating Plant Seismic Walkdown Report S'J.NSI WITHHOLD FROM PUJBLIC DISCLOSURE The remaining pages are withheld from public disclosure.

p. ~:'.~g I U~. ~ Ill ItJLU I I :up.1 UIiLItj UI~A LU';u; :L Sheet 1 of 5 Status: YEI NE UC-Seismic Walkdown Checklist (SWC)Equipment ID No. CRD HCU W Equip. Class, (18) Instruments on Racks Equipment Description CRD Hydralic Control Units West Side Location.

Bldg. RX Floor El. ý _ Room, Area West Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YER NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YE NEI Ut] N/At YZ NEI UEi N/Atl YZ NEI U[D N/At]YZ NEI Ut] N/At]YZ NEI Uil 1 Enter the equipment class name from Appendix B: Classe$ of Equipment. ',' I ','UI IL I',/' i u ',, i:' .p ' Vi,, lii, i IULU , I-uf.1 I,'UULIU Sheet 2 of 5 Status: Y--] N[o U[i-Seismic Walkdown Checklist (SWC)Equipment ID No. CRD HCU W Equip. Class, (18) Instruments on Racks Equipment Description CRD Hydralic Control Units West Side Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI UE] N/AE 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YE] No UE- N/AU and masonry block walls not likely to collapse onto the equipment? CST line is in contact wI CRD structural column. WO 62289 was initiated as part of CAP 1259196 to address rubbing.9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NE] UE1 N/AE]Y0 NEI UE]Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Two 1/2" bolts anchor each 1-1/2" diameter pipe. Four total pipes are bracing each piece of equipment. Housekeeping:

1) Tie wraps around anchors CRD 38-35 of CRD 38-35 look like 2) DuctTape on nearby CSW line.Evaluated by: Bruce M. Lory /.0 , Steve Kaas y I l Date: o o4-J Monticello Nuclear Generating Plant I Seismic Walkdown Report SUJ.S WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure.

PROPRIETARY4 INFORMATION WITHHOLDIG6 FROM PUBLIC DI$CLO$URE Sheet 1 of 5 Status: YN NiZI UL--Seismic Walkdown Checklist (SWC)Equipment ID No. CRD 16A Equip. Class' (21) Tanks and Heat Exchangers Equipment Description Scram Discharge Volume Location: Bldg. RX Floor El. ý _ Room, Area West Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is. the item one of the 50% of SWEL items requiring such verification)? YE- NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

Y0 NEI US- N/AS YE NE US N/AS1 YN NEI US- N/AS1 YE NEI US1 N/AE YN NEI UO Enter the equipment class name from Appendix B: Classes of Equipment. I .j.I I .~L .'~,.~':~IuI ~I.I:. I IUIX ..'I I: IHULU I I zur.1 I LjIiL~tj UI~..iLUtAJI ZL Sheet 2 of 5 Status: Y[ NM- U[Seismic Walkdown Checklist (SWC)Equipment ID No. CRD16A Equip. Class, (21) Tanks and Heat Exchangers Equipment Description Scram Discharge Volume Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? Y0 NEI UI1 N/AO 8. 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?

9. Do attached lines have adequate flexibility to avoid damage?Tank has no electrical connection.

Attached piping is large bore, rigid pipe. SWEs judge configuration acceptable.

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO NO UO- N/AZ YS NEI UE3 Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Housekeeping: Is it acceptable to store hose or five gallon jug underneath the tank?Evaluated by: Bruce Lorv I/-Date: ?66 Steve Kaas ~ ~ i-// Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. "II_ Ii\ y I,j- i:ut- /\v Ii IUIX' V.I, Ii I-II-IULU IU I LIIJUI ,UI Th.Sheet 1 of 5 Status: Y[Z NO- Ur-Seismic Walkdown Checklist (SWC)Equipment ID No. CV-1728 Equip. Class, (07) Fluid-Operated Valves Equipment Description II RHR HX RHRSW Outlet Location: Bldg. RX Floor El. ý _ Room, Area A RHR ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO NZ 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YE NO U- N/A[9 YE NE: UE- N/AZ YE7 NE UE N/AZ YEi NE" UE' N/AN YN NEI UE-1 Enter the equipment class name from Appendix B: Classes of Equipment.

INFRMATI-N -ITI , I-OL F, M .I.... .CLOU,.RE Sheet 2 of 5 Status: Y[ NEI- U-Seismic Walkdown Checklist (SWC)Equipment ID No. CV-1728 Equip. Classi (07) Fluid-Operated Valves Equipment Description 11 RHR HX RHRSW Outlet Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI ULI N/AE 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[D NO U13 N/A0 and masonry block walls not likely to collapse onto the equipment? Masonry block wall surrounding stairwell is seismically qualified since wall identified in this manner in Drawing NF-36300-1-2.

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI UE- N/AE YS NE UE 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: Bruce M. Lorv 4Date: 4402 .2Z -Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SU'NSSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PRO T -" "1OnMATN T O FR U C I OSURE Sheet 1 of 4 Status: YJZ NEI- UL]Seismic Walkdown Checklist (SWC)Equipment ID No. CV-2043 Equip. Class, (07) Fluid-Operated Valves Equipment Description HPCI Steam Line Drain Trap Bypass Location:, Bldg. RX" Floor El. ý .Room, Area HPCI Room Manufacturer, Model, Etc. (optional but recommended) InstruCtions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of-judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorane 1. Is the anchorage configuration verification required (i.e., is the item one YEI NED of the 50% of SWEL items requiring such verification)?

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

YO NEI UE- N/AN YE- NEI UE- N/AE 4. Is the anchorage free of visible cracks in the concrete near the anchors? YEI NEI UE1 N/A[5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

Y[3 NEl UEi N/AN YN NEI UEi I Enter the equipment class name from Appendix B: Classes of Equipment. PROiPRIETARY INFO)RMATION WITH HOLD91=9 FROM PUBLIC.. DISCLOSURE Sheet 2 of 4 Status: YZ NEI UF-L Seismic Walkdown Checklist (SWC)Equipment ID No. CV-2043 Equip. Class, Equipment Description HPCI Steam Line Drain Trap (07) Fluid-Operated Valves Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YO NO U[ N/AO 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UI--] N/Al and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NO UI- N/A[I YN N[ UD Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 NO U-adversely affect the safety functions of the equipment?

Comments (Additional.pages may be added as necessary) Evaluated by: Bruce M. Lorv Date: ofo//-Steve Kaas -D 7-I p2~ Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY ',,F"RNMATIO,"' WITHHOLD FRfOM PUBLIC DISCLOSURE Sheet 1 of 4 Status: YZJ NE] UJ--Seismic Walkdown -Checklist (SWC)Equipment ID No. CV-3-32A Equip. Class, (07) Fluid-Operated Valves Equipment Description West SDV Vent Location: Bldg. RX Floor El. ý _ Room, Area West Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YEI NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YE NE-- UE N/AO YE- NEI UE- N/AO YEI NEI UE- NWA YEI NEI UE[ N/A[YO NEI UEi Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 4 Status: YM NEI U[-Seismic Walkdown Checklist (SWC)Equipment ID No. CV-3-32A Equip. Class' (07) F/uid-Operated Valves Equipment Description West SDV Vent Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? Y0 NEI U'I N/All 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NFI UE1 N/All and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI UE" N/All YN NEI UED Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Housekeeping: A large tie wrap is fastened to CRD line near valve.Evaluated by: Bruce M. Lary 4 '.-Steve Kaas Date: 2-//2-Monticello Nuclear Generating Plant Seismic Walkdown Report S"'NSI WITHHOLD FROQM", PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 6 Status: YER N[-] UMi Seismic Walkdown Checklist (SWC)Equipment ID No, Dl Equip. Class, (15) Batteries on Racks Equipment Description

1. 11 Battery 125VDC Location:

Bldg. ADMIN Floor El. ý _ Room, Area #11 125 BA Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Configuration is different than SEWS reference

02. Configuration is bounded by D2.2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Shrinkage cracks noted but they are not a structural deficiency

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

Consistent and bounded as indicated. by D2 SEWS.6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions? YER NEI YO NEI U[L N/AZ1 YZ NEI UZ- N/A-YED NiZ UL N/AZ-YN NEI U-1 N/AZ1 YIO NO U'Enter the equipment class name from Appendix B: Classes of Equipment. PROPRIET,"ARY INFORMATION WITHHOLD FROM PUBLIC DISCLOSURE Seismic Walkdown Checklist (SWC)Sheet 2 of 6 Status: Y[ NE] UL]Equipment ID No. DI Equip. Class, (15) Batteries on Racks Equipment Description

1. 11 Battery 125 VDC Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

YO NEI UEI N/AEl 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEI UI- N/A[l and masonry block walls not likely to collapse onto the equipment? Lights -all-thread rod to unistrut acceptable. Ducts -anchored wIstraps acceptable. CMU -qualified seismic (see SEWS), so acceptable.

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO NE] U[I N/AEZ YR NEI UI-Other Adverse Conditions

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

Comments (Additional pages may be added asnecessary) Monticello Nuclear Generating Plant Seismic Walkdown Report 01 -AIITUUrI rl CDo lin DI 101 it, Ilifli rfel 10-The remaining pages are withheld from public disclosure.

IFOHlMAT-lN VITuuI OL9 FRO49M r-UBICI Sheet 1 of 3 Status: YM NE] UL" Seismic Walkdown Checklist (SWC)Equipment ID No. DIO0 Equip. Class' (14) Distribution Panels Equipment Description Div 2 125/250 VDC Distribution Panel Location: Bldg. EFT Floor El. Room, Area All Manufacturer, Model, Etc. :(optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YZ NEI U] N/Al]YO NE UL- N/AE]YE NEI U- N/ALn YO NE UE N/AO YO NE U-1'Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 3 Status: Y[Z NEI- U-]Seismic Walkdown Checklist (SWC)Equipment ID No. D100 Equip. Class' (14) Distribution Panels Equipment Description Div 2 125/250 VDC Distribution Panel Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YO NE ULI N/Al]8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YS NO UO N/AU and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?Two rigid conduit is connected to the termination box on top of the panel. This configuration is judged acceptable by the SWEs.10. Based on the above seismic interaction eValuations, is equipment free of potentially adverse seismic interaction effects?YN. NW U- N/Al]YN NE UD Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory Al Date: Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS- WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Seismic Walkdown Checklist (SWC)Sheet I of 3 Status: YN NEI U[" Equipment ID No. D31 Equip. Class' (14) Distribution Panels Equipment Description Div 1 125/250 VDC Distribution Panel Location: Bldg. ADMIN Floor El. ý _ Room, Area DIV 1 250V Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Shrinkage cracks not structural

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

Description consistent with SEWS. Plant drawing inaccurate with installation of anchors. SEWS evaluation on anchors uses correct "as found" configuration.

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

YE NEI U-- N/AUl YS NE. UU N/AU YE NE UEI N/AU YE NEI UE" N/AU YER NI UEI 1 Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 3 Status: YZ NEI UZ-I Seismic Walkdown Checklist (SWC)Equipment ID No. D31 Equip. Class' (14) Distribution Panels Equipment Description Div 1 125/250 VDC Distribution Panel Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI U[-] N/AEs 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0 NE UI-- N/A[l and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI UL N/AEl YE NEI U Other Adverse Conditions

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

HVAC duct close to top conduit P685, judged not likely to cause adverse interaction. Comments (Additional pages may be added as necessary) Evaluated by: Walter Diordievic Date: Srcott Scott Luckiesh Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUJBLIC DISCLOSURE The remaining pages are withheld from public disclosure. AL N P I '. Ik WY& (II'. uULU N u.i I'UL .LIU 'b'H.L .m U .I Sheet 1 of 7 Status: Y[ NEI u[-1 Seismic Walkdown Checklist (SWC)Equipment ID No. D3A Equip. Class 1 (15)Batteries on Racks Equipment Description

1. 13 (Div 1) 125/250 VDC Battery "A" Location:

Bldg. ADMIN Floor El. _ Room, Area 250 VDC DI Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YN NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?Center stanchion of west (wall) rack has excessive projection & 2 nd stanchion from north has excessive projection

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?Shrinkage cracks but not structural cracks 5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

No, but it is bounded by D2 anchorage evaluation in original A-46 SEWS (see sketch on photo sheet)6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions? YZ NE UE1 N/A[l YZ NE1 U- N/All YO NEI UF N/AE YN NO ULI N/Al YN NEI UI-1 1 Enter the equipment class name from AppendixB: Classes of Equipment. I(,UM ul 'A"o r VVi , IIULU ii :ur.iI UUL' U UI b;ULU s U (k=Sheet 2 of 7 Status: Y5 NEIl UI-I Seismic Walkdown Checklist (SWC)Equipment ID No. D3A Equip. Class 1 (15)Batteries on Racks Equipment Description

1. 13 (Div 1) 125/250 VDC Battery "A" Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Saline bottle partially dislodged from holder. Placed back to fully secure.Junction box 2P4000, and 1P3002, FE-4618 (2 of 4 tabs anchored); adjudged acceptable.

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?(see SEWS for block walls that are seismically qualified)

Duct strap on duct over Door109/D40 not tight. It is still capable of carrying load.9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Saline bottle restored to properly secured position YE Ni] UI- N/A[]YE NE UZI N/AEl YE NEI UF- N/AZ YE NEI U"]Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Date: 6~ '-"/z' PRGOPRIETARY IFOfRlMTIO;; WITHHOLD rn.M PUBL'.C DSCLOSUB Sheet 3 of 7 Status: YE N[E] U-Seismic Walkdown Checklist (SWC)Equipment ID No. D3A Equip. Class, (15)Batteries on Racks Equipment Description

1. 13 (Div 1) 125/250 VDC Battery "A" Side View 4- -Battery 10.5" Note: Note: Note:

Monticello Nuclear Generating Plant Seismic Walkdown Report SUNRSI WITHHOLD FROM PUBLIC DIRCLOSURE The remaining pages are withheld from public disclosure. PRGPRF1IETAF1 INF-GRMATIGN WITHI 11O01D FROM PUBLICI DIGGLOCURE Sheet 1 of 6 Status: YN NEI U-i Seismic Walkdown Checklist (SWC)Equipment ID No. 03B Equip. Class1 (15)Batteries on Racks Equipment Description

1. 13 (Div 1) 125/25OVDC Battery "B" Location:

Bldg. ADMIN Floor El. ý Room, Area 250 VDC Dl Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YE NEI Of the 50% of SWEL items requiring such verification)?

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

YN NE UD N/AE YZ NEI UD N/AOl 4. is the anchorage free of visible cracks in the concrete near the anchors? YE NEI U-1 N/AEF Shrinkage cracks, no structural cracks 5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.) Consistent with D2 SEWS anchorage, and is bounded by D2 SEWS anchorage analysis. Two outer anchor interactions installed, inner two locations open (see sketch)6. Based on the above anchorage evaluations, is the anchorage free of potentially adverseseismic conditions? YN NO U- N/A[l YE NO UD IEnter the equipment class name from Appendix B: Classes of Equipment. PROPRIETZARY INjFORMATIONP WVITHHOLD161 FROM PU)BLIC PD6ISCLOURF Seismic Walkdown Checklist (SWC)Sheet 2 of 6 Status: YN N[E] Ul--Equipment IDNo. D3B Equip. Class' (15)Batteries on Racks Equipment Description

1. 13 (Div 1) 125/25OVDC Battery "B" Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

1) 1P3002" exterior anchorage tabs not installed.

Judged acceptable.

2) FE-4818: 2 of 4 tabs installed.

Adjudged acceptable. YN NO UO N/AU 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEI U-- N/AED and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YE NEI UE N/AU YN NEI Ui Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) PIfOPlrIETARY INFORl--ATION WITHHILD FRO PUBLIC IS"l"l11-Sheet 3 of 6 Status: YM NE] UD-1 Seismic Walkdown Checklist (SWC)Equipment ID No. D3B Equip. Class' (15)Batteries on Racks Equipment Description

1. 13 (Div 1) 125/25OVDC Battery "B" Photographs 36" Side View I View: 0000 *050c Battery 30"* -Filled with anchor o -Open hole I , j --10.5" N Note: Note: Note.N Note:

Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PR9PlIET-ARY INFORiMATIO9N WIT' 11 OL61 FRGM PUJBLIC D)IGCLO8UlE Sheet 1 of 3 Status: YM NE] U-]Seismic Walkdown Checklist (SWC)Equipment ID No. DM-8089A1 Equip. Class' (10) Air Handlers Equipment Description V-SF-9 Supply Damper Location: Bldg. TB Floor El. ý _ Room, Area DG BLDG Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results .ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YEI NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YED NEI U-- N/AU-YZ NE UE] N/AU1 YE NEI U[ N/AZ YE NE1 UEi N/A[R YN Nil UD' Enter the equipment class namefrom Appendix B: Classes of Equipment. PROPRIETARY 'II-RMATIIN WITI I- FREW PUJBlIIC 9i"-LOS'6G, Sheet 2 of 3 Status: N[] Ui-Seismic Walkdown Checklist (SWC)Equipment ID No. DM-8089A1 Equip. Classi (10) Air Handlers Equipment Description V-SF-9 Supply Damper Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI UL] N/AZ 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YNJ NI] UI- N/AZ and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NI] U-] N/AZ YN NEI U Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lorv Date: Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS- WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 5 Status: YZ N1 UD--Seismic Walkdown Checklist (SWC)Equipment ID No. DM-8089J1 Equip. Class' (10) Air Handlers Equipment Description V-SF- OSupply Damper Location: Bldg. TB Floor El. Room, Area DG BLDG Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results ofthe Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Overall unit is one integral unit built into building. Anchorage of the unit is not visible; however, in any case the damper fails in the open position if the damper is dislodged because pneumatic pressure is lost.2. Is the anchorage free of bent, broken, missing or loose 'hardware?

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?Floor cracks which have no effect on damper unit anchorage.

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

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

YE-I N YZ NEI UE1 N/AE!YO NEI UE' N/A[l Y0 NEI UE] N/AE!YEI NEI UE! N/AZ YN NEI UE-Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 5 Status: YE N[-] U[L]Seismic Walkdown Checklist (SWC)Equipment ID No. DM-8089J1 Equip. Class' (10) Air Handlers Equipment Description V-SF-I Supply Damper Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI U!] N/Al]8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UEI N/AD and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y9 NDI U[] N/AI-YE NEI UD1 Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Walter Diordievic Date: Scott Luckiesh Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBILC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 4 Status: Y] NEI Uti Seismic Walkdown Checklist.(SWC) Equipment ID No. FT-23-82 Equip. Class, (18) Instruments on Racks Equipment Description HPCI Pump Flow Transmitter Location: Bldg. RX Floor El. ý _ Room, Area HPCI Room Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation? Team also looked at Rack C-120 anchorage. Team noted ground water leakage onto center rack kicker support.4. Is the anchorage free of visible cracks in the concrete near the anchors?Team looked for cracks around C-120 rack anchorage since transmitter is locally mounted on rack. No cracks were found.5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YN NEI U- N/AE YO Ni U- N/AO YO NEI UD N/AE1 YE NE UE N/AO YO NEI U-IEnter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 4 Status: YZ NEI UD--Seismic Walkdown Checklist (SWC)Equipment ID No. FT-23-82 Equip. Class 1 (18) Instruments on Racks Equipment Description HPCI Pump Flow Transmitter Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YO NEL ULI N/All 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UI-IJ N/Al]and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NEI U-] N/AE]YZ NEL UL Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory Date: O Z 2--Steve Kaas 4z/z,6 /'%-M"7 Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS- W!THHOLD FROM P'UBIC DISCLOSURE The remaining pages are withheld from public disclosure. 1-M.- ý -- .-- ý ý 1. 1 ..... .--I-A 11 -- -n ...I Seismic Walkdown Checklist (SWC)Sheet i of 7 Status: Y[ N-] U-Equipment ID No. G-3A Equip. Class' (17) EngQine7 Generators Equipment Description 11 Emergency Diesel Generator Location: Bldg. TB Floor El. ý _ Room, Area 11 DG RM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YID NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation? Surface oxidation only. SWEsjudged as acceptable.

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

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

YE NEl U[] N/AL]YN NE] UL- N/AL]YO NEI U-] N/AL]YZ NEI UE- N/A--YI NOL UL 1 Enter the equipment class name from Appendix B: Classes of Equipment. PROPRIE-TARV IIIFORMATIONPj WITH HOL9 FROM PUBICII DICrLOSURE Sheet 2 of 7 Status: YN NEI U-]Seismic Walkdown Checklist (SWC)Equipment ID No. G-3A Equip. Class' (17) Engine-Generators Equipment Description 11 Emergzency Diesel Generator Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

1) Temporary power pack (TH-3) located approximately 4'South of DG skid is not deemed a hazard but should be chained to wall hooks on south end.8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?Cast iron drain piping is laterally unrestrained but not deemed a flooding hazard or a seismic interaction hazard as it is rod supported along the horizontal run and the vertical run has two gravity supports.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?House, heating steam fan will displace less than 1" during seismic event so steam line has adequate flexibility; however, a brace to adjacent wall may be an enhancement to prevent damage to attached steam supply piping which is threaded-end piping and has high stress intensification factors.YN NEI UF- N/AF1 YO NE] U[I N/AE]YZ NEI U-1 N/AL]YED NE UE1 Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Turbine Building roof drain ends up as a 12" line connected with victaulic couples. Not deemed a seismic interaction hazard; however the mechanical couplings may pry open (deemed unlikely) so some rain water could leak out but there are two drains in EDG room that can accommodate such a leak. Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. I'ItPUIlI=AI}Y INFUGtMATIGN WviTi 11 1ELD F~lOm PU)BLIC 91GG6LOYRFl Seismic Walkdown Checklist (SWC)Sheet 1 of 5 Status: YE NE] UL--Equipment ID No. G-3B Equip.. Class' (17) Engine-Generators Equipment Description 12, Emergency Diesel Generator Location: Bldg. TB Floor El. Room, Area 12 DG ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used.to record. the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., ýis the item one of the 50% of SWEL items requiring such verification)? YER NEI 2. Is the anchorage free-of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion'that is more than mild surface oxidation? Mild rust noted on some bolts. SWEs judge them acceptable.

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

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

YN NEI UD N/AZ YO NEI UIZ N/AD1 YED NEI UL- N/AU1NEI U-1 N/AD YE NEI UF1 1Enter the equipment class name from Appendix B: Classes of Equipment. Seismic Walkdown Checklist (SWC)Sheet 2 of 5 Status: NEI u--Equipment ID No. G-3B Equip. Class' (17) Engine-Generators Equipment Description 12 Emergency Diesel Generator Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YE NO UO N/AO 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UO N/AEl and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?Tubing attached to FE-4224B and FIS-4224B (12 emergency diesel generator ESW low floor alarm) is anchored to wall with P,2010 unistrut spring nuts. The pipe the tubing is connected to has different movement from floor. SWEs judge that the spring nut will allow tubing to slide in seismic event if there is a large enough differential movement between the wall and floor.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NEI UE] N/A[-]YED NEI UE Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) (14) -1 1/4" cast in place bolts, seven bolts each side at approx 57" spacing per S & A calc # 91C2687 Evaluated by: Bruce M. Lory 124.-,~ ore 7 Date: oylo' " --Z Rthvp Kqa.q Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure.

INF-ORMATION WITH HL FROLE)FM PUrLIC DI"-lOCURE Sheet 1 of 5 Status: YN NM U-Seismic Walkdown Checklist (SWC)Equipment TD No. K-10A Equip. Class' (12) Air Compressors Equipment Description RHRSW Aux Air Comp.Location: Bldg. RX Floor El. Room, Area Southeast Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of'judgments and findings& Additional space is provided at the end of this checklist fordocumenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Y NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YZ NEI U[] N/AlD YO NE] UE- N/Al]NEI UZl N/A[]YZ NEI U[] N/Al]YZ NEI UE1 IEnter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 5 Status: YN NEI UZI Seismic Walkdown Checklist (SWC)Equipment ID No. K-10A Equip. Class 1 (12) Air Compressors Equipment Description RHRSWAux Air Coamp.Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YE NEI UE1 N/AEI 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YIE NEI UI1 N/AL!and masonry block walls not likely to collapse onto the'equipment? Masonry block is safety related and is therefore acceptable.

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI UEI N/AL!YO NE UE Other Adverse Conditions.

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

Comments (Additional pages may be added as necessary) There are four 1/2" diameter expansion anchors, which are spaced 32" wide and 19" long.Evaluated by: Bruce Lorv /.I At'(. i,. -.-Date: ,:: 2 All;ý-ýiýSteve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 5 Status: YN N[] u[-]Seismic Walkdown Checklist (SWC)Equipment ID No. K-8A Equip. Class' (12) Air Compressors Equipment Description 11 EDG Electrical/Diesel Air Starter Compressor

1. 1 Location:

Bldg. TB Floor El. ý _ Room, Area 11 DG RM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YR NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation? 4, Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YN N- UL N/AU YER NO U- N/Al YN NEI UL N/AU YZ NEI U- N/AU YE NEI UO I Enter the equipment class name from Appendix B: Classes of Equipment. Seismic Walkdown Checklist (SWC)Sheet 2 of 5 Status: Y[ NEI- U-Equipment ID No. K-8A Equip. Class' (12) Air Compressors Equipment Description 11 EDG Electrical/Diesel Air Starter Compressor

1. 1 Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

YZ NEI ULi N/AUI 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YE NEI UI- N/AU and masonry block walls not likelyto collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based.on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Starting battery-is strapped in place, and is not a seismic concern.YN NEI UD[ N/AUl YN NEI UE1 Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Walter Diordievic ate: Scott Luckiesh Monticello Nuclear Generating Plant Seismic Walkdown Report S'JNSI WITHHOLD FROM PUBgLIC DIRSCLOSJRE-The remaining pages are withheld from public disclosure. Sheet I of 4 Status: YM NO V'0 Seismic Walkdown Checklist (SWC)Equipment ID No. K-8B Equip. Class' (12) Air Compressors Equipment Description 11 Electric Air Starter Compressor

1. 2 Location:

Bldg. TB Floor El. ý _ Room, Area 11 DG ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YN NEL 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Some degradation of paint surface on SE corner but not at the anchor.No effect on anchors.5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YO ND U0 N/AEl YZ N[i U0I N/ADl YO NO UE- N/AZ-YN NEI UF] N/AZ YN NEI UEl I Enter the equipment class name from Appendix B: Classes of Equipment. Sheet,2 of 4 Status: YM Nn] U-]Seismic Walkdown Checklist (SWC)Equipment ID No. K-8B Equip. Class' (12) Air Compressors Equipment Description 11 Electric Air Starter Compressor

1. 2 Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

YS NEI UE- N/AE-8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YE NEI U0 N/AD and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?YN NEI UE' N/AEl 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Monticello Nuclear Generating Plant Seismic Walkdown Report SR'J.NIS-WITHHOLD FROM PUBRLIC DISCLOSURE The remaining pages are withheld from public disclosure. PRE)PflIETARY INjFGRNMATIN WVITHHLD G1 FflOM PU1BLIC 9ISCLOS6URE Sheet 1 of 3 Status: YN NM UM Seismic Walkdown Checklist (SWC)Equipment ID No. LT-2-3-72A Equip. Class' (18) Instruments on Racks Equipment Description LO LO Reactor LVL ECCS Initiation Location: Bldg. RX Floor El. _ Room, Area C-55 Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be usedto record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YEI NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YO NEI UE- N/AE1 YO NEI U-I N/AE]YE] NEI UE1 N/AO Y0- NEI UE- N/AO YE NEI UE]Enter the equipment class name from Appendix B: Classes of Equipment. PROPRI!T-ARY INjFOGRMATFION WITI 1IGI=E OL FlOM PUBLIC DI6CLOCURE= Sheet 2 of 3 Status: Y[ NEI[ U'--Seismic Walkdown Checklist (SWC)Equipment ID No. LT-2-3-72A Equip. Class' (18) Instruments on Racks Equipment Description LO LO Reactor LVL ECCS Initiation Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI UD N/ADI 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NDI UD1 N/AD and masonry block walls not likely to collapse onto the equipment? Per drawing NF-36300-1-2, Fig. 3-1D all masonry block walls are safety-related and seismically evaluated. Block wall is above rack/instrument location. Lighting is adequately supported.

9. Do attached lines have adequate flexibility to avoid damage?No relative movement between rack and instrument.

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NDI UD N/Al YE NEI UM Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by:/ Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 3 Status: YN Ni-] U-]Seismic Walkdown Checklist (SWC)Equipment ID No. LT-2-3-72C Equip. Class' (18) Instruments on Racks Equipment Description LO LO Reactor L VL ECCS Initiation Location: Bldg. RX Floor El. ý _ Room, Area C-55 Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing. Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments, Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YEI NE 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YZ NEI UI- N/AU YN NEI UEI N/AEl YN NEI U-- N/AE1 YE NEI UE1 N/A YN0 NE UE'Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 3 Status: YE N[-] UI Seismic Walkdown Checklist (SWC)Equipment ID No. LT-2-3-72C sEquip. Class (18) Instruments on Racks Equipment Description LO LO Reactor L VL ECCS Initiation Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YE NEI UEI N/AL]8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEI- UEL N/AEl and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI Urn N/AE]YIE NE] UE]Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) See notes for L T-2-3-72A. Identical to -72A. Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSSI WITHHOLD FROM PURBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PRPRITR INRMATIAN VVITII L O ULCDCLS Sheet 1 of 3 Status: YN NEl] ULI Seismic Walkdown Checklist (SWC)Equipment ID No. LT-2996 Equip. Class, (18) Instruments on Racks Equipment Description Torus Water Level Location: Bldg. RX Floor El. Room, Area Torus Area Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWIEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE- NO 2. Is .the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YO N['] U- N/AD YU NEI U-- N/A[YN NEI U-1 N/AZ1 YBI NBI U-- N/AN YED NEI Uil I Enter the equipment class name from Appendix'B: Classes of Equipment. Sheet 2 of 3 Status: Y] NEI- U-]Seismic Walkdown Checklist (SWC)Equipment ID No. LT-2996 Equip. Class' (18) Instruments on Racks Equipment Description Torus Water Level Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YM NEI UE) N/AEZ 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YIZ NFi ULi N/AD and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?There is no relative displacement between equipment and lines. Both are rigidly attached to same support structure.

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NEI UZI N/AZ YZ NEI U[:]Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Walter Dbrdevic ate: 7VI Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. (,-usii- AN'i /iY IP! P4 VIHuULU ,rui I'UW1L3,La U bW.LU.U,1 Sheet 1 of 4 Status: YR NE] UL-Seismic Walkdown Checklist (SWC)Equipment iD No. MO-1741 Equip. Class, (08) Motor-Operated and Solenoid-Operated Valves Equipment Description 11 CS Pump Torus Suction Location: Bldg. RX Floor El. ý _ Room, Area A RHR ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one Y[E NO of the 50% of SWEL items requiring such verification)?

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

YE- NEI UEi N/AO YE] NE UE- N/AO 4. Is the anchorage free of visible cracks in the concrete near the anchors? YEI NE UE1 N/AZ 5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YE NE UE N/AO YO NEI UE1 1 Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 4 Status: YZ NEI Ur-]Seismic Walkdown Checklist (SWC)Equipment ID No. MO-1741 Equip. Class, (08) Motor-Operated and Solenoid-Operated Valves Equipment Description II CS Pump Torus Suction Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEL UrL N/AlE 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NI UErI N/AL1 and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEl UL N/AL YN NEl UL-Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y12 NEI UL adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory Date: Oko/a2-Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS' WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 4 Status: YE N[-] U-]Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2010 Equip. Class' (08) Motor-Operated and Solenoid-Operated Valves Equipment Description Torus Spray VLV Location: Bldg. RX Floor El. Room, Area Torus Catwalk Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional. space is provided at the end of this checklist for documenting other comments, Anchorae 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE) NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YI- NE UEI N/AE YEI NEI UE N/AZ YE] NEI UE N/AZ YE NE UE N/AE YZ NEI UE1 1 Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 4 Status: YN N[-R UM-l Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2010 Equip. Classi (08) Motor-Operated and Solenoid-Operated Valves Equipment Description Torus Spray VLV Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI UEI N/AEI 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ Ni UEI1 N/AZ and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?A thin wire is used to restrain a local hoist from a conduit. This is the second instance of this configuration.

As an enhancement, the hoist should be attached to a more substantial anchor (not conduit) using chain.YN ND UDI N/AZI YN NEI UZ Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Date:~; Monticello Nuclear Generating Plant Seismic Walkdown Report SJUhSR WITHHOLD FROM PUBIR1C DIRSCLOSURE The remaining pages are withheld from public disclosure. PRfOPRIETARfY ',,FORMAT',O," WITH H1 OLD FROM PUBUC DIGSLOSURE Sheet 1 of 3 Status: YE NO] U[Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2012 Equip. Class' (08) Motor-Operated and Solenoid-Operated Valves Equipment Description 11 RHR LPCI Outboard Iniection Location: Bldg. RX Floor El. Room, Area East SD Cooling Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorag~e

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

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

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

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

YEI NEI UE' N/AE Y E NE] UZ N/AN YEI NEI UE] W/AS YEI NEI UEr N/AN YZ NE UE-Enter the equipment class name from Appendix B: Classes of Equipment. p p, R I ' .IE T ,A nY .NI.. .M A I. .N W IT H H OL... ..F R. M PU. B L IC 9 IS C , U R F=Sheet 2 of 3 Status: YN NI- ur7 Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2012 Equip. Class, (08) Motor-Operated and Solenoid-Operated Valves Equipment Description 11 RHR LPCI Outboard Iniection Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YO NEI UI N/AL 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NE Ur7 N/AL and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI UI N/ALE YE NEI Ur1 Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) A~-A A-Evaluated by: Bruce Lorv Steve Kaas / I" Date: OYd27"I Monticello Nuclear Generating Plant Seismic Walkdown Report SU.NSI- WITHHOLD FROM PUBLRIC DRSCLOSURE The remaining pages are withheld from public disclosure. M." 11-1 HE~ I : .... I R ui '"I1: U U IIzrII*tLU u~tL ~ : Sheet 1 of 4 Status: Y[ NO U[-]Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2013 Equip. Class' (08) Motor-Operated and Solenoid-Operated Valves Equipment Description RHR/RHR B LPCI INJ OUTBD Location: Bldg. RX Floor El. ý _ Room, Area West SD Cooling Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YOI NZ of the 50% of SWEL items requiring such verification)?

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

YE NE UE'q N/AE YE NE UEI N/AN 4. Is the anchorage free of visible cracks in the concrete near the anchors? YE NE UE N/A[D 5. Is the anchorage configuration consistent with plant documentation?(Note; This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YE NEI UE N/AE YO NO UE I Enter the equipment class name from Appendix B: Classes of Equipment. MI..., L ..Sheet 2 of 4 Status: YN NEI- Uli-Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2013 Equip. Class' (08) Motor-Operated and Solenoid-Operated Valves Equipment Description RHR/RHR B LPCi INJ OUTBD Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YE NO UO N/AO 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YIO NEI UI N/A-and masonry block walls not likely to collapse onto the equipment? Block walls confirmed to be seismic category I per drawing NF-36300-1-2 rev 0.9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NWI U- N/AZ YO NO UO Other Adverse Conditions

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

Comments (Additional pages may beadded as necessary) Evaluated by: Bruce M. Lory 1~Date: £2 2 2..-61Z h.Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBILIC DISCLOSUIRE The remaining pages are withheld from public disclosure. PROPRIET-ARY INFORMATION WITFHHOLD-FROMA PUBIC DIECLOURF Sheet I of 3 Status: YZ NEI U-]Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2030 Equip. Classi (08) Motor-Operated and Solenoid-Operated Valves Equipment Description RHR Shutdown Cooling Supply Outboard isolation Location: Bldg. RX Floor El. ý _ Room, Area East SD Cooling Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO- N 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YO] NEI UE N/AM YE NE UE N/AE YE NE UE N/AN YE NEI UE N/A2 YED NEI U-'Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 3 Status: YIN ND U-Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2030 Equip. Class, (08) Motor-Operated and Solenoid-Operated Valves Equipment Description RHR Shutdown Cooling Supply Outboard Isolation Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YER NEI UEr N/ADl 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YE NEI Ui N/ADl and masonry block walls not likely to collapse onto the equipment? Pendant light is within swinging distance of MO-2030 but will not adversely affect MO operation.

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI UE-- N/AE YN NEI UE-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 5 Status: YN NO] U[-]Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2063 Equip. Class' (08) Motor-Operated and Solenoid-Operated Valves Equipment Description HPCI CST SUCT Location: Bldg. RX Floor El. ý _ Room, Area HPCI ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below eachof the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO NE 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YO NEI UE N/AIU YO NE UO N/AZ YE NEI UE N/A YE NEI Ur N/A0 YZ NEI U-I Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 5 Status: YE Nr] U[]Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2063 Equip. Class' (08) Motor-Operated and Solenoid-Operated Valves Equipment Description HPCI CST SUCT Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YJZ NEI US N/AS 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YIN NS USr- N/AS and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI US N/AS Y0 NEI U[l Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory'If.Date: ýUA//.2_Steve Kaas.gl/ 1// 2-SZ ., Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. 0 u InHk 0U ANL ( I', N U I dvikx I k P .VVI I [ In Ut:9 I ourqi I 'Uk5LI b~;LUU H bu uL(k Sheet i of 3 Status: N-- UL-]Seismic Walkdown ,Checklist (SWC)Equipment ID No. MO-2078 Equip. Class' (08) Motor-Operated and Solenoid-Ogerated Valves Equipment Description RCIC Turbine Steam Supply Location: Bldg. RX Floor El. ý _ Room, Area RCIC Room Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YE] NO of the 50% of SWEL items requiring such verification)?

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

YE] NE] UEI N/AN YE] NEI UE N/AE 4. Is the anchorage free of visible cracks in the concrete near the anchors? YE:] NEI UE] N/AH 5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YEI NEI UE] N/A0 YN NEI U-I Enter the equipment class name from Appendix B: Classes of Equipment. Dor'IO ICTAD 1-IflD ATIfKlK ---rjr fl -fRtA -I I -f --ifl -l~ D Sheet 2 of 3 Status: YN NR] Ul-]Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2078 Equip. Class, (08) Motor-Operated and Solenoid-Operated Valves Equipment Description RCIC Turbine Steam Supply Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? Y[ NEI UD- N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Yll NDI U0 N/AD and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN ND UD N/AD1 YN NEI UDI Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory I Date: Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. ,r-RRIF,-TAR-INFORMATI.N WIT."^" IGHO6 FROM P-UBLIC D9',CLOSURE Sheet 1 of 3 Status: YN NF-] Ut-]Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2106 Equip. Class, (08) Motor-Operated and Solenoid-Operated Valves Equipment Description RCIC Pump Discharge Outboard Location: Bldg. RX Floor El. _ Room, Area RCIC Room Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the. end of this checklist for documenting other comments.Anchoratze

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

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

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

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

YEI NEI UE- N/AO YE NEI UEr N/AOI YEI NEI UEI N/Au YEI NE-I UE- N/AO YO NEI UE1 1 Enter the equipment class name from Appendix B: Classes of Equipment. PROPRIET"ARY INFORMATION WITIAl, HOLD FROM r Sheet 2 of 3 Status: YN NEI u--Seismic Walkdown Checklist (SWC)Equipment ID No. MO-2106 Equip. Class 1 (08) Motor-Operated and Solenoid-Operated Valves Equipment Description RCIC Pump Discharge Outboard Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN N[l UEW N/AE]8, Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NOI- UEI N/ADl and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN Nil Ul-1 N/AD Y0 NEI U[J Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) SWEs noted MO-2106 valve body cuts into piping isulation approx 1". Pipeline has nearby rod pipe hanger and additional 2 or 3 way pipe support anchored to wall. SWEs judge valve cannot rotate along pipe axis to further crush pipe insulation. SWEs judge configuration acceptable and not seismic interaction issue.Evaluated by: Bruce M. Lory 4'-~ 4.Steve Kaas f Date: 6XI-OIlz 0 Monticello Nuclear Generating Plant Seismic Walkdown Report S'.NSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIET ILIARY INFORMATIGIN WITIHFI lO FREW PUBLIC Di1sCLOBURE Seismic Walkdown Checklist (SWC)Sheet 1 of 5 Status: YM NF-- U--Equipment ID No. P-109A Equip. Class' (06) Vertical Pumps Equipment Description 11 RHR SW Pump Location: Bldg. INTAK Floor EI.._ Room, Area Main Room Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the follov~ing questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Y[Z NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation? Minimal oxidation where paint has chipped off Some oxidation on mounting flange. This is not a seismic concern.4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.) See Stevenson and Associates Calculation 9 7-336, "Outlier Evaluation of Service Water Pumps." 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions? YM NEI UD N/AD Y[ NEI U- N/AD YM NO UD N/AD YN ND UD N/A[D]Y[ ND] UFH 1 Enter the equipment class name from Appendix B: Classes of Equipment. Seismic Walkdowt Checklist (SWC)Sheet 2 of 5 Status: YE NEI U--Equipment ID No. P-109A Equip. Class, (06) Vertical Pumps Equipment Description 11 RHR SW Pump Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN Ni UUi N/AU 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN Nn UE- N/A[U and masonry blockwalls not likely to collapse onto the equipment? Fire protection spray lines above are seismically supported. Air louver well secured to ceiling and wall.9.. Do attached lines have adequate flexibility to avoid.damage?

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NOI Uil N/AU YN NEI UEI Other Adverse Conditions

11. Have you looked for and found noother seismic conditions that could YED NEI U-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary) Evaluated by: Wally Diordievic /Date: L Scott Luckiesh Monticello Nuclear Generating Plant Seismic Walkdown Report SU'NSI WITHHOLD FROM PUBILBC DISCLOSURE The remaining pages are withheld from public disclosure. .:Iuw I A):'.,, jIAL:~ UIt.LLUtUI~L Seismic Walkdown Checklist (SWC)Sheet 1 of 3 Status: YE NF] UV-]Equipment ID No. P-11 Equip. Class' (05) Horizontal Pumps Equipment Description Diesel Oil XFER Pump Location: Bldg. FO PM Floor El. Room, Area Main Room Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YN N[il of the 50% of SWEL items requiring such verification)?

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

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

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

YO NEI U-] N/Al]YN NEI ULI N/AUl YE Nil U0l N/AUl YN NE UI] N/AEl YN NEI U[E' Enter the equipment class name from Appendix B: Classes of Equipment. R:IMU -II Hit .iY A i (y I U! (Mik' U' VyI (HIUU I~ M i HLtiU UIW blU I (1=Sheet 2 Of 3 Status: YM NE] ULI1 Seismic Walkdown Checklist (SWC)Equipment ID No. P-11 Equip. Class, (05) Horizontal Pumps Equipment Description Diesel Oil XFER Pump Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YOI NEI UI M/AE 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO NO- Ur- 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 free of potentially adverse seismic interaction effects?YlZ NEIZ ULJ NIAO YZ NEI UL Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Pump anchorage consists of 3/8" diameter cast in place bolts spaced 15.5" lengthwise and 9" depthwise. Evaluated by: Bruce M. Lorv Annie-Date: 09z/o 2/?..Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI -WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY INFORMATION WITHL RMPBLCDSLCR Sheet i of 4 Status: YM N[il Uf-Seismic Walkdown Checklist (SWC)Equipment ID No. P-m11A Equip. Class, (06) Vertical Pumps Equipment Description 11 ESW (EDG-ESW) Pump Location: Bldg. iNTAK Floor El. ý _ Room, Area Main Room Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Y] NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation? Painted 4. Is the anchorage free. of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent withplant documentation?(Note: This question only applies if the item is one of the 50% for Which an anchorage configuration verification is required.) See Stevenson and Associates Calculation 97-336, "Outlier Evaluation of Service Water Pumps." 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions? YO NI] Ut] N/AU YZ NEI Ut N/AL!YZ Nin UE] N/AU YN N[] Ut] N/An YE NI U"-Enter, the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 4 Status: YZ Nn-] U--Seismic Walkdown Checklist (SWC)Equipment ID No. P-IlA Equip. Class, (06) Vertical Pumps Equipment Description 11 ESW (EDG-ESW) Pump Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YO N[I UD N/AL]8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Ys NEI UIE N/AEl and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Chain fall from SW-2-1 has remote chance of reaching P-111A but poses no credible seismic hazard.YN NEI U[] N/AL]YS NEI Ur-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) /1 -Evaluated by: Walter Diordievic 7 Date: "'2/Z/ _-P,£'citf I ,,ckip..h Scott Luckiesh Monticello Nuclear Generating Plant Seismic Walkdown Report S'JNSI WITHHOLD FROM PUBLIC DISCLOSSURE The remaining pages are withheld from public disclosure. Sheet 1 of 4 Status: YV N[-- U--Seismic Walkdown Checklist (SWC)Equipment ID No. P-111C Equip. Class 1 (06) Vertical Pumps Equipment Description 13 ESW (EDG-ESW) Pump Location: Bldg. INTAK Floor El. ý _ Room, Area Main Room Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of.SWEL items requiring such verification)? Y0 NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YN NEI UL- N/Al Y0 NEI U[] N/AE]YE NEI UL] N/AD YZ ND U-I] N/Al]Y[ Nil UEI 1 Enter the equipment class name from Appendix B: Classes of Equipment.

• U" I, Ul , VV' U:1; I..)L I U ,L't. U2',UL&U ',U; __Sheet 2 of 4 Status: YZ NE-- U--Seismic Walkdown Checklist (SWC)Equipment ID No. P-111C Equip. Class" (06) Vertical Pumps Equipment Description 13 ESW (EDG-ESW)

Pump Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NI] UD] N/AL 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Yo] N'-1 UE] N/AL and masonry block walls not likely to collapse onto the equipment? Overhead fire prot. piping is seismically supported.

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Chain fall from SW-2-1 is not well secured, however, poses no hazard to P-1C.Y0 NEI UI] N/A[]YZ NEI UE Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ Ni] UDi adversely affect the safety functions ofthe equipment?

Comments (Additional pages may be added as necessary) Monticello Nuclear Generating Plant Seismic Walkdown Report SU'NRSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PRO9PRIETARY INFOGRMATION WITI 11 'OLD) FROM PUBLIC DISCLOSU8RE ,Sheet 1 of 6 Status: Y[ NI-- UI-Seismic Walkdown Checklist (SWC)Equipment ID No. P-202C Equip. Class' (06) Vertical Pumps Equipment Description 13 RHR Pump Location: Bldg. RX Floor El. ý _ Room, Area A RHR ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

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

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

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

YZ NEI UE- N/AEI YO NEI UE- N/AEl YZ NEI UL- N/AE YZ NEi U3 N/AE-YO NEI UEi'Enter the equipment class name from Appendix B: Classes of Equipment. PR"'PRIETARY VINO'RMA:TITON WITI I- OLD FROM PUBLIC DIi-lOl iRE Sheet 2 of 6 Status: YN Nn U["I Seismic Walkdown Checklist (SWC)Equipment ID No. P-202C Equip. Class 1 (06) Vertical Pumps Equipment Description 13 RHR Pump Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YU NEI UF- N/At]8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YE NEI Ut] N/At]and masonry block walls not likely to collapse onto the equipment? Block wall is seismic category I per Drawing NF-36300-1-2.

9. Do attached lines have adequate fleXibility to avoid damage?Also looked at bearing cooling flex lines and they looked adequate.SWEsjudged bearing cooling lines have adequate flexibility.

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI Ut] N/At]YO NEI Ut]Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Pump anchored with four 1" diameter grouted in place anchors on 26" x 20" spacing pattern per S&A calculation attached to SQUG SEWS (job #91C2687)Evaluated by: Bruce M. Loa Date: 6 00/a I~ Z.Steve Kaas I-Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSal' WITHHOLD FROM PUJBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Iii'lII" 8 HIJ (~.V in' "'IH L K M UiI IL ~Sheetn of 4 Status: Y-I NZ UL-Seismic Walkdown Checklist (SWC)* Equipment ID No. P-203A Equip. Class' (05) Horizontal Pumps Equipment Description 11 SSLC Pump Location: Bldg. RX Floor El. ý Room, Area East Manufacturer, Model, Etc. (optional but recomnmended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchoraee 1. Is the anchorage configuration verification required (i.e., is the item one Y[I NI]of the 50% of SWEL items requiring such verification)?

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

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

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

YO NI] UIJ N/AO YlN NI UOI N/AD YO NEI UI] N/AD YO ND UD N/AD YO NDE UE IEnter the equipment class name from Appendix B: Classes of Equipment. Seismic Walkdown Checklist (SWC)Equipment ID No. P-203A Equip. Class' (05) Horizontal Pumps Equipment Description 11 SBLC Pump Sheet 2 of 4 Status: YEI NET UI Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? Tall scaffold is constructed above the pump. Verify the seismic assessment of this scaffold. (Same WO referenced in SWC for SLC tank)8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentia lly adverse seismic interaction effects?Final status will be dependent on outcome of scaffold seismic assessment.

YO NO U-C N/AC Yn NCI Uf N/AD YO NC UCi N/ACl YD NO UCI d Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) There are six 7Y8" diameter holes in the base, spaced 21" and 36.5" wide, and 35.5" long. There are 314" foundation bolts used in these six locations. Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI", WITHHOLD FROM PUBgLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 9 Status: YEi NEI UW-Seismic Walkdown Checklist (SWC)Equipment ID No. P-208A Equip. Class' (06) Vertical Pumps Equipment Description 11 Core Spray Pump Location: Bldg. RX Floor El. ý _ Room, Area A RHR ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YLI NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YO NEI U-1 N/AIl YZ NEI UI- N/A--YO NDL ULi N/AEl YI' NEI UE] N/A[YO1 NEI T_' Enter the equipment class name from Appendix B: Classes of Equipment. PROPRIET:ARY INFOGRMATION WITHHOLD'G6 F-ROM PUBLIC DISGCLOSUR[ Sheet 2 of 9 Status: YN Nr- U[Seismic Walkdown Checklist (SWC)Equipment ID No. P-208A Equip. Class, (06) Vertical Pumps Equipment Description 11 Core Spray Pump Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI U[I N/AZ 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[ NEI U-I N/A[-and masonry block walls not likely to collapse onto the equipment? Overhead block walls are seismically qualified per drawing NF-36300-1-2 rev 0.9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YI NZ UZ- N/AZ YED NEI UZ Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory I4/J'"'Date: 61e) 211t 16 f?Steve Kaas X Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLRC The remaining pages are withheld from public disclosure. PROPRIETARY INFORMATION WITI 1 9OLD FROM PUBLIC DISCLOSURE Seismic Walkdown Checklist (SWC)Sheet I of 13 Status: Y[-- NO UL]Equipment ID No. P-209 Equip. Class' (05) Horizontal Pumps Equipment Description HPCI PUMP Location: Bldg. RX Floor El. ý _ Room, Area HPCI ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE NE 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?1) Surface cracks noted on North end of pedestal.

They are small hairline cracks. SWEs judge no reduction in anchor bolt capacity.2) Also noted horizontal cracking in pump pedestal.5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.) There are eight 1" C/P anchor bolts per NX-8292-43 while the walkdown only found six 1" CIP anchor bolts. See CAP 1346272.6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions? YO NEI UE1 N/AE YZ NEI UIJ N/ADl YN NEI UE N/AE YE NO UE-1 N/AE YE] NO UE I Enter the equipment class name from Appendix B: Classes of Equipment. i I (U I1 I I~.: P "~IIH L ~MIUAI ~tL t I-Seismic Walkdown Checklist (SWC)Equipment ID No. P-209 Equip. Class" (05) Horizontal Pumps Equipment Description HPCI PUMP Sheet 2 of 13 Status: YI- NZ U[-I Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? Noted 6x6" TS in contact with insulation on piping to HPCI Booster pump. SWE's judged acceptable. Rigid TS will have minor deflection under seismic load.YM NEI UL N/AL 8. Ate overhead equipment, distribution systems, ceiling files and lighting, Y0 NEI UO N/All and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NEI Ul N/ALI YO NE UEi Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) 8x 1" diameter foundation bolts approximately 58" apart per NX-8292-43. Evaluated by: Bruce M. Lorv Af Date: 8 2-Steve Kaas 7-Monticello Nuclear Generating Plant Seismic Walkdown Report S'J.1hSR WITHHOLD FRO.An PUBLIC L DISCLOSURE The remaining pages are withheld from public disclosure. I ',UI, , ', U, I Ur" '.',iiI hULU PUfi UULLU Sheet I of 5 Status: Y[n NEI UM-Seismic Walkdown Checklist (SWC)Equipment ID No. P-222A Equip. Class, (05) Horizontal Pumps Equipment Description 11 DG Fuel Transfer Pump #1 Location: Bldg. TB Floor El. ý _ Room, Area 11 DG RM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings, Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YLI NO of the 50% of SWEL items requiring such verification)?

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

YE] NEI UE N/AO Y-I NEI UE1 N/AO 4. Is the anchorage free of visible cracks in the concrete near the anchors? YE NE] UE- N/AZ 5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

Fuel pumps are securely mounted to EDG skid by four 3/8" diameter bolts.YE NE UE1 N/AZ YO NEI UE1'Enter the equipment class name from Appendix B: Classes of Equipment. H"IUII l'L',',I ii'l k,.. 10'I iu.H" ! ',' .i ULU I I .H.(i, W.'U6LIU UIb.H ULU.U Hb L Sheet 2 Of 5 Status: NRE] U[-1 Seismic Walkdown Checklist (SWC)Equipment ID No. P-222A Equip. Class' (05) Horizontal Pumps Equipment Description 11 DG Fuel Transfer Pump #1 Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? HVAC drain piping above skid not deemed a seismic interaction hazard because it is laterally supported at the east and west walls which reduces the bending moments in the line to an acceptable level.YN NEI UI- N/AL 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YED NEI ULI N/AL and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?Attached fuel oil lines have flexible connections.

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI U-- N/AL YO NEI U-1 Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y9 NEL UL-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary) Evaluated by: Walter Diordievic A Date: & -Scott Luckiesh Z Monticello Nuclear Generating Plant Seismic Walkdown Report SUN.SI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 5 Status: YLI NO Ur-Seismic Walkdown Checklist (SWC)Equipment ID No. P-88A Equip. Class' (06) Vertical Pumps Equipment Description ECCS Area Drain Pump Location: Bldg. RX Floor El. Room, Area A RHR ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YI] NO of the 50% of SWEL items requiring such verification)?

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

The anchor bolts are heavily corroded YO NEI UE] N/AE]YEI] NO UE- N/AEl 4. Is the anchorage free of visible cracks in the concrete near the anchors? YZI NOi UI- N/AiI 5. Is the anchorage configuration consistent with plant documentation?(Note; This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

Based on question 3 above, the anchorage is not free of potentially adverse seismic conditions. YEI NEI UE-] N/A YEI NO UEi I Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 5 Status: Y[-l NO U-']Seismic Walkdown Checklist (SWC)Equipment ID No. P-88A Equip. Class' (06) Vertical Pumps Equipment Description ECCS Area Drain Pump Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI UE N/AEl 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YID NO UI-- N/A-and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Numerous tie wraps used to secure power cable from pump motor all the way to where the cable enters the cable wireway. The length of cable run is 15-20 feet with tie wraps. No flex or rigid conduit was used. Tie wraps bind cable to rigid conduit that serves a different function.

Is this an approved method to seismically mount safety related cables and what is the plant standard that was used?YO NE UE N/AE YE-]N[]UI-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory&' .'ýP_ &Date: 0 M/ 7/Z-Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI -WITHHOLD FROM PUB-LIC DISCLOSUJRE The remaining pages are withheld from public disclosure. PROPRIETAlRY I,'FORMATION WITHHOLD FROM PUBLIC DISCLOSURE Sheet i of 5 Status: Y[ NEI- UC--Seismic Walkdown Checklist (SWC)Equipment IID No. PS-23-97A Equip. Class' (18) Instruments on Racks Equipment Description HPCI HI TURB EXH PRESS TURB TRIP Location: Bldg. RX Floor El. Room, Area HPCI ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchoratge

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

See SWC for FT-23-82 for discussion about corrosion on anchorage of common rack C-120.Y0 NEI UE] N/AU Y0 NE] UE1 N/AE]4. Is the anchorage free of visible cracks in the concrete near the anchors? YEI NE] UE- N/AN 5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YE] NEI UE] N/AN YN NEI UE I Enter the equipment class name from Appendix B: Classes of Equipment.

[urLi I~ 'r~ i.j'~r~IltL

! U. UAIUULLL Sheet 2 of 5 Status: YN NI U[]Seismic Walkdown Checklist (SWC)Equipment ID No. PS-23-97A Equip. Class' (18) Instruments on Racks Equipment Description HPCI HI TURB EXH PRESS TURB TRIP Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? Y0 NEI UE1 N/AlI-8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEI UI- N/A-1 and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines .have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y10 NE UE N/AD3 YN NO UE1 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: Bruce M. Lorv Date: Steve Kaas A_'-z/ 2-/ Monticello Nuclear Generating Plant Seismic Walkdown Report SU.NSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY I..'NFORMATIO. WITHIHIPOLD FROM PUBLIC DISCLOSURE Sheet 1 of 3 Status: NE] UE]Seismic Walkdown Checklist (SWC)Equipment ID No. RV-1990 Equip. Class, (07) Fluid-Operated Valves Equipment Description RHR 11 Pump Suction RV Location: Bldg. RX Floor El. ý _ Room, Area A RHR ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YOJ NEI UL N/AE YO-1 NEI UF- N/AN YO] NEl UI- N/A]YO- NO U-- N/AN YO NEI UE'Enter the equipment class name from Appendix B: Classes of EquipmenL. iI ' I dI riIIz.IIIU !f iiIL U.IIU iI I§jU § : Sheet 2 of 3 Status: YN NR] UL-]Seismic Walkdown Checklist (SWC)Equipment ID No. RV-1990 Equip. Class' (07) Fluid-Operated Valves.Equipment Description RHR 11 Pump Suction RV Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YEI NEI U[" N/A]8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0 NE-1 U[1 N/AEl and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YM NEI UE- N/AE1 YZ NE UE1 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: Bruce M. Lory Evauaedby Buc M LrvDae:e5~2 V Date: 010 Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSU'RE The remaining pages are withheld from public disclosure. PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DISCLOSURE Sheet 1 of 3 Status: YN Ni[ ui-Seismic Walkdown Checklist (SWC)Equipment ID No. SV-1728 Equip. Class 1 (08) Motor-Operated and Solenoid-Operated Valves Equipment Description CV-1728 (II RHR HX RHRSW Outlet) SV Location: Bldg. RX Floor El. ý _ Room, Area A RHR ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.AnchoraPE 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YER NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?Anchorage check for whole CV-1 728 control station.3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

Four 3/8" diameter expansion anchors noted in SEWS.YN NE UL N/AL YO NEI U- N/AD YN NEI Ur- N/AL-Y[ NEI Ur- N/A-1 YE NEI UE1 I Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 3 Status: YZ NO] U[-l Seismic Walkdown Checklist (SWC)Equipment ID No. SV-1728 Equip. Class' (08) Motor-Operated and Solenoid-Operated Valves Equipment Description CV-1728 (11 RHR HX RHRSW Outlet) SV Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YE NEI ULI N/Al]8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YED NE] ULI N/AU and masonry block walls not likely to collapse onto the equipment? Masonry block wall surrounding stairwell is seismically qualified since wall identified in this manner in Drawing NF-36300-1-2.

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO NEI UD] N/Al]YZ NEI U[I Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory Evalatedby: ruc M. orv ate J Date 2L Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. i '! -1 .1- 1 1 -I 1 11 ..Sheet 1 of 3 Status: YN N[O] uZI Seismic Walkdown Checklist (SWC)Equipment ID No. SV-2379 Equip. Class' (08) Motor-Operated and Solenoid-Operated Valves Equipment Description ALT N2 A SPLY TO A0-2379 Location: Bldg. RX Floor El. m_ Room, Area Torus Catwalk Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results Of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchora2e 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE1 NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more thanmild surface oxidation?

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

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

YE] NE U[J N/AN YEI NEI UE- N/AE Y[-1 NEI UE N/A0 YE NE UE N/AS YE NEI UE'Enter the equipment class name from Appendix B: Classes of Equipment. IAL:L UILUtUKL Sheet 2 of 3 Status: YE NEI Ut]Seismic Walkdown Checklist (SWC)Equipment ID No. SV-2379 Equip. Class, (08) Motor-Operated and Solenoid-Operated Valves Equipment Description ALT N2 A SPLY TO AO-2379 Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YZ NEI UE- N/AEl 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NE" UE- N/AEl and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y9 NEI UE1 N/AE YN NEI U" Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)" /. ." /Evaluated by: Walter Diordievic (U!Date: k01- -XA/£Scott Luckiesh Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUJL£IC DISCLOSU RE The remaining pages are withheld from public disclosure. PGPILIP p,, TAWy I...w.I.il.. iL..FROm.PUBL!G.. ICDIUL... RE.Sheet i of 6 Status: YEI NO ULI Seismic Walkdown Checklist (SWC)Equipment ID No. T-200 Equip. Class' (21) Tanks and Heat Exchangers Equipment Description Standby Liquid Control Tank Location: Bldg. RX Floor El. _ Room, Area East Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments., Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?Each of four brackets has two bolts, not three bolts. Drawing NX7879-8-1 shows three holes per bracket.3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Shrinkage cracks in grout pad, not of structured concern.5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

There is a discrepancy between Drawing NX7879-8-1 and what is installed in the plant.6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions? YO NEI ULi N/AEl YO NEI U-1 N/A[YO NEI UEL N/AUl YEI NO U-- N/ALl YE NO UEU'Enter the equipment class name from Appendix B: Classes of Equipment. rRODPRI=T-AR* INjFORMATPION WITHHOLD91: FROM RUBLIG DISOLOCURE Sheet 2 of 6 Status: YE] NZ Ur-Seismic Walkdown Checklist (SWC)Equipment H) No. T-200 Equip. Class' (21) Tanks and Heat Exchangers Equipment Description Standby Liquid Control Tank Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YE NEI ULI N/AU 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEl UO1 N/AUl and masonry block walls not likely to collapse onto the equipment? Masonry block walls above and west of tank are seismically designed.9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Verify the seismic assessment for the scaffold near tank. (WO 432143, component ID RV-2470)YZ NEl UI- N/AUl Y'I NED UE-OtherAdverse Conditions

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

Comments (Additional pages may be added as necessary) Four brackets equally spaced with 1-1/8" diameter anchor bolts spaced 6" apart for each brace. Bolts attach brace to the floor and brace welded to tank.Evaluated by: Evalatedby:Date: /4-Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE PfOPfIE=T-ARY INFORMATION WITI 11 OLD9 FROM PUBLIC DICOLOSURE

---

. -----~*-**-** *.. ......... .IIF R T ...- .-* .-*-*-*. ....... .-, -. -,o, --- ,S e t Status: YE NEI- U" Seismic Walkdown Checklist (SWC)Equipment ID No. T-45A Equip. Class, (21) Tanks and Heat Exchangers Equipment Description Standby Diesel Generator Day Tank Location:

Bldg. TB Floor El. ý _ Room, Area 11.DG DAY Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on .the SWEL. The space below each .of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?One anchor nut is flush with stud, while other anchors have stud projection through nut. All anchors develop full strength.3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YE NEI U[-1 N/AL YED NEI UE- N/AL YE NEI UE- N/AL YZ NE UE1 N/AL YZ NEI UE'Enter the equipment class name from Appendix B: Classes of Equipment. ....... .ULU I I ~UM I UIjL~L JIriLLULUI JI Status: Shee 2E oF 4 Seismic Walkdown Checklist (SWC)Equipment ID No. T-45A Equip. Class' (21) Tanks and Heat Exchangers Equipment Description Standby Diesel Generator Day Tank Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YS NEI U[ N/AL[8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YER NEI UI- N/AL and masonry' block walls not likely to collapse onto the equipment? Masonry Wall is seismically designed. Roof drain is rigid. No seismic issues.9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NI UL- N/AL Y[ NEI U-1 Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSIS WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 3 Status: Y[ NI- U--]Seismic Walkdown Checklist (SWC)Equipment ID No. T-45B Equip. Class' (21) Tanks and Heat Exchangers Equipment Description STANDBY DIESEL GENERA TOR DAY TANK Location: Bldg. TB Floor El. Room, Area 12 DG DAY Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checidist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YN N[i 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YO NEI UI- N/AEl YN NF- U-- N/AZ YM NW-1 Ur1 N/AF-YN NEI U-1 N/AEZ YN NEI U[Z' Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 3 Status: YZ N-] U-]Seismic Walkdown Checklist (SWC)Equipment ID No. T-45B Equip. Class' (21) Tanks and Heat Exchangers Equipment Description STANDBY DIESEL GENERA TOR DAY TANK Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YM NEI Ur1 N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[N ND-1 UI- N/AD and masonry block walls not likely to collapse onto the equipment? Block wall check for 80-11. Wall D-105 is a safety related block wall per drawing NF-36300-1-3 rev. 0. Block wall therefore is acceptable.

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NDI UD- N/AD YN NND] UD-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory Date: 67,"-Rteve Kan.q Steve Ka~s Z$X~ ~7,4-~ Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure.

i -U!' (it i A!: r: !P11 k ~ix (MO lr OUP! WWI NI I ULi M UM (kq UUI 19MbbLUk~bI (i Sheet 1 of 3 Status: YO N[[] U-1 Seismic Walkdown Checklist (SWC)Equipment ID No. T-75A Equip. Class, (21) Tanks and Heat Exchangers Equipment Description Accumulator for SV-1994 Location:

Bldg. RX Floor El. ý _ Room, Area A RHR ROOM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO- N 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YO NEI U- N/AL YO NEI U[:- N/AU YEI NE UE- N/AO YE NE U- N/AO YM NEI U-'Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 3 Status: YZ NEI[ U-]Seismic Walkdown Checklist (SWC)Equipment ID No. T-75A Equip. Class' (21) Tanks and Heat Exchangers Equipment Description Accumulator for S V-1994 Interaction Effects 7. Are soft targets free from impact by nearby equipment orstructures? YZ N[l UlE N/AEI 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NO UE" N/AEI and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y2 NEI UE- N/AE YZ NEI UD Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Low Steve Kaas V Date: ekvz Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROMR PUJBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY 'IP'FOR.MATION WITHHOLD '069FROM PYUBIC DISCLOSURE Sheet 1 of 4 Status: YE N[-] U--Seismic Walkdown Checklist (SWC)Equipment ID No. T-79D Equip. Class, (21) Tanks and Heat Exchangers Equipment Description 11 DG Air TK D Location: Bldg. TB Floor El. Room, Area 11 DG RM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one Y0 NEI of the 50% of SWEL items requiring such verification)?

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

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

Small hairline crack on south floor anchor was judged to be small and has no significant effect on shear capacity.6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions? YN NEI UE] N/AE]YZ NE] UD N/AE]YI NE] UE1 N/AE]YZ NE] UE1 N/AE-YO NO UE]Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 4 Status: Y[ NEI ULI-Seismic Walkdown Checklist (SWC)Equipment ID No. T-79D Equip. Class, (21) Tanks and Heat Exchangers Equipment Description 11 DG Air TK D Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI UI- N/AEl 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEI U-1 N/AL]and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO NEI ULI N/All YE NEI Ul3 Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) -. -o .Evaluated by: Walter Di°rdevic -Date: Monticello Nuclear Generating Plant Seismic Walkdown Report SU'JNSI WITHHOLD FROM PUB8LIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 4 Status: Y] N[-1 U[Seismic Walkdown Checklist (SWC)Equipment ID No. T-80A Equip. Class 1 (21) Tanks and Heat Exchangers Equipment Description 12 OG AIR TK A Location: Bldg. TB Floor El. ý _ Room, Area 12 DG RM Manufacturer, Model, Etc.. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YLZ ND of the 50% of SWEL items requiring such verification)?

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

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

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

YZ NDI UD N/AD YM NEI U-'I Enter the equipment class name from Appendix B: Classes of Equipment. PROPRIEFTARY INFORIMATION WITI OLD FROM PUBLIC DISCLOSURE Sheet 2 of 4 Status: YN N[-] UM-Seismic Walkdown Checklist (SWC)Equipment ,D No. T-80A Equip. ClassW (21) Tanks and Heat Exchangers Equipment Description 12 OG AIR TK A.Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI ULI N/AZ 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NEI UI- N/AZI and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?Engineering judgment was used to determine that the rigid piping system is adequate.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NO UZ- N/AZ YE NEUFu Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) All tanks are clamped to a steel rack which is connected to the floor and ceiling. The tanks are held in place by two large U-bolts. There are four total 5/8" diameter anchors.Evaluated by: Bruce M. Lory Evlute y:BrceMZLkiDae Dae 6A.Steve. Steve Ka~s 7.,, Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM DISSCLOSURE The remaining pages are withheld from public disclosure. PrlPRIET'nRY INFORMATION WITHJ H --6 FROM UBICII iICOL-OlSRE Sheet 1 of 5 Status: YE NEI[ UI-]Seismic Walkdown Checklist (SWC)Equipment ID No. T-ALTN2B Equip. Class' (21) Tanks and Heat ExchanQers Equipment Description ALT N2 B Bottle Rack Location: Bldg. TB Floor El. ý _ Room, Area South Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YlZ NEI U[I N/AZl YE NEI Ur N/AD YO NEI UEI N/A[[YZI NEI U[3 N/AO YO NEI UFI I Enter the equipment class name from Appendix B: Classes of Equipment. It-~uIKILIgI-~' II'~I U .1g::uP.~j:nHULL I I-~UM 1UJL:.j u:1/2utu:ZL Sheet 2 of 5 Status: NE] Ui--Seismic Walkdown Checklist (SWC)Equipment ID No. T-ALTN2B Equip. Class, (21) Tanks and Heat Exchangers Equipment Description ALT N2 B Bottle Rack Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NE ULI N/All 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO NEI U- N/AU and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10, Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y10 NEI UU- N/AUI YED NI U-1 Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y0 NEI UU1 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory Steve Kees 7 6(7Z-Date: OM ..c/i I Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUN'JISI WITHHOLD FROM PUBLIC DI SCLOSURE The remaining pages are withheld from public disclosure. l'! (U 1 1 ( I b! d irQ l l (I MP Hi r 099p i HN 11 ULUE ! !u~ (U 'U LI HibUl=HbI (in Sheet 1 of 5 Status: N'- Ut-Seismic Walkdown Checklist (SWC)Equipment ID No. TS-13-79C Equip. Class, (19) Temperature Sensors Equipment Description RCIC STM Line Hi Area Temperature Isolation Location: Bldg. RX Floor El. ý _ Room, Area RCIC Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgrnents and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YF-I NO of the 50% of SWEL items requiring such verification)?

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

YZ NEI UE' N/AEl YN NEI UE' N/Al 4. Is the anchorage free of visible cracks in the concrete near the anchors? YN NEI UEi N/AUl 5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YE NEI UE- N/AN YZ NEI UEF I Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 5 Status: YE NEI- U-Seismic Walkdown Checklist (SWC)Equipment ID No. TS-13-79C Equip. Class, (19) Temperature Sensors Equipment Description RCIC STM Line Hi Area Temperature Isolation Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YZ NEI UE] N/AE]8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YiN NEI UE] N/A[l and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?Rigid conduit used is acceptable

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI UE] N/AE1 YZ NEI UE-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) Noted: Cord of I & C squak box is looped around stairwell railing. SWE's judge ok but recommend clamp or other device to secure more adequately. Evaluated by: Bruce M. Lory 4-zcV Date: OYe f.71 Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. !I aJi d! ': I~ I~." J' ..Ili U U :tr1 UiLt I§L L I~Sheet I of 5 Status: YEJ NE] UE-]Seismic Walkdown Checklist (SWC)Equipment ID No. V-AC-5 Equip. Class, (10) Air Handlers Equipment Description RHR A Air Handler Location: Bldg. RX Floor El. ý _ Room, Area A RHR RM Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YN NEI of the 50% of SWEL items requiring such verification)?

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

Mild oxidation of weld connecting isolator base to grating. SWEs judge it is acceptable. YZ NE] UE] N/AL]YU NEI UI' N/AD3 4. Is the anchorage free of visible cracks in the concrete near the anchors? YEI NE UE- N/AID Mounted on grating.5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YZ NEI UE N/A[Y0 NEI UE-I Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 5 Status: YN NEI U-Seismic Walkdown Checklist (SWC)Equipment ID No. V-AC-5 Equip. Class' (10) Air Handlers Equipment Description RHR A Air Handler Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NO U[-I N/AO 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YE NEI U- N/AOl and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y0 NEI UI N/AUI YZ NEI UD Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Four 1/2" diameter anchors on 90" x 31-1/2" pattern.Housekeeping/FME: Broken wire hanging and large tie wrap broken and should be removed.Evaluated by: Bruce M. Lory V Date: Steve Kaas. Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSUJRE The remaining pages are withheld from public disclosure. Sheet 1 Of 3 Status: YM NI UI-]Seismic Walkdown Checklist (SWC)Equipment ID No. V-EAC-14A Equip. Class, (11) Chillers Equipment Description CRV Div I HVAC Unit Location: Bldg. EFT Floor El. ý _ Room, Area EFT Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE1 NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Shrinkage cracks noted but do not adversely affect seismic capacity of anchorage.

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

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

YO NEI UE1 N/AEl YE NE- U[3 N/AEl YO NEI UI3 N/AE YEI NE] UE3 N/AZ YO NE] UEF' Enter the equipment class name from Appendix B: Classes of Equipment. PROPRIFET.AR.Y INFORMATION WIT.I O1 LD .FflOM PUBUG -'DISCO.URE,.Sheet 2 of 3 Status: YM NEI U-]Seismic Walkdown Checklist (SWC)Equipment ID No. V-EAC-14A Equip. Class, (11) Chillers Equipment Description CRV Div I HVAC Unit Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI U- N/A[l 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO NO- ULi N/AO and masonry block walls not likely to collapse onto the equipment? Noted 4" diameter piping system overhead that contains victaulic couplings. It is next to or possibly in contact with insulation on HVA C duct. HVAC duct is designed as seismic category 1. SWEs judge pipe -HVAC duct interaction minor. Piping is also anchored in numerous locations.

9. Do attached lines have adequate flexibility to avoid damage? YO NE! UE! N/AO 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YO NEI u-Other Adverse Conditions

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

Walls on either side of equipment are made of drywall. Modification

1. 79N745 (Doc. #400) documented how the drywall system in the EFT satisfies seismic II over I criteria.Comments (Additional pages may be added as necessary)

Evaluated by: Bruce M. Lorv Date: to6.Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI -WITHHOLD FROBM PULIRIC DISCLORSURE The remaining pages are withheld from public disclosure. nnn)PRnIT--AR IPFORMATI-A WIT- IT71 OL9 FROM PUBLICi Sheet 1 of 6 Status: YN NEI UL-Seismic Walkdown Checklist (SWC)Equipment ID No. V-EF-40A Equip. Class' (10) Air Handlers Equipment Description Div II 250VDC Battery Room Ventilation Location: Bldg. EFT Floor El. ý _ Room, Area EFT Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist fordocumenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Shrinkage cracks noted but does not adversely affect seismic capacity of anchorage.

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

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

YN NO UE N/AE YO NE UO N/Al YO NE U- N/AE YE NE UF N/AO YO NO UE' Enter the equipment class name from Appendix B: Classes of Equipment. PRO)PRIETARY INFO'RMATIO-. 'WITHH Ol'i-lD FROM PULI DI'c.iSURE Sheet 2 of 6 Status: Y[ NEI U[]Seismic Walkdown Checklist (SWC)Equipment ID No. V-EF-40A Equip. Class, (10) Air Handlers Equipment Description Div II 250VDC Battery Room Ventilation Interaction Effects 7. Are soft targets free from impact by nearby ,equipment or structures? YZ NEI UI N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YED NOIl UL N/AU and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NE U- N/AU YN NEI UE]Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory-~--. -Date: -g/-0-24/."-- Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report 011kl I IO ll~AII l-UUflIl 17% I0r DI IDI If' rI'klf'I flQ1 ID -The remaining pages are withheld from public disclosure. PRlPRIETlARY INFlnRMATIN WVITH HO LD6 FROM PUBLIC DIrlOlliRE Sheet i of 5 Status: YZ NE] Ut-I Seismic Walkdown Checklist (SWC)Equipment ID No. V-EF-40B Equip. Class' (10) Air Handlers Equipment Description Div 2 250 VDC Battery Room Ventilation Location: Bldg. EFT Floor El. ý _ Room, Area EFT Manufacturer, 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 the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Y-I NZ 2. Is the anchorage free of bent, broken, missing or lOose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation? Some of the anchorage welds have mild oxidation which was deemed acceptable.

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

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

YN NE! UE] N/AL YO NEI U!] N/AU YZ NF] UO] N/AF1 YEI NEI U!] N/AE YO NEI U!]'Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 5 Status: YZ NEI U[[]Seismic Walkdown Checklist (SWC)Equipment ID No. V-EF-40B Equip. Class' (10) Air Handlers Equipment Description Div 2 250 VDC Battery Room Ventilation Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? A 2" FP line in the corner above the blower is anchored to the wall using U-bolts with angle and two anchors in the wall. Judged acceptably anchored by SWEs.YEI NF' UL' N/AEl 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[E NEI UM N/ADl and masonry block walls not likely to collapse onto the equipment? Drywall next to blower. Drywall is seismically qualified for II over I per Mod #79N745 (File #D400)9. .Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YS NEI UE1 N/AE]YU NEI UE]Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lony Date: t 2-Ste-ve Kaas Steve Kaas ~; A~-~ Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI -WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. rRGPRIEITAR* INF-GlMATIIN WITHHOLDG6 F-floq PUBLICI DIGGLOSURE Sheet 1 of 3 Status: Y[ NM- Ut-]Seismic Walkdown Checklist (SWC)Equipment ID No. V-ERF-14A Equip. Class" (10) Air Handlers Equipment Description CRV Div I Exhaust Recirc Fan Location: Bldg. EFT Floor El. ý .Room, Area EFT Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YEI NO 2. Is the anchorage free of bent, broken, missing or loose hardware?3,. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

YZ NEI UEi N/ANl YE NEI UE] N/ANl YO NEI U-] N/AEl YE] NEI UEI N/AZ YE NEI UE1'Enter the equipment class name from Appendix B: Classes of Equipment. PROPRIETARY INFORMATION WITI 1i OLI FROM PUBIC1 DISC""0rloUiRE Sheet 2 of 3 Status: YE NO-- U[-Seismic Walkdown Checklist (SWC)Equipment ID No. V-ERF-14A Equip. Clas Equipment Description CRV Div I Exhaust Recirc Fan s' (10) Air Handlers Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YED NO UEJ N/Al 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI UL N/AL]and masonry block Walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YE NEI UiL N/AO YN NEI UL Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory A,

• Aýý.117 Date: Steve Kaas .-812-1)-Z-Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUB1LIC DISCLOSURE The remaining pages are withheld from public disclosure.

I I :~: II'~: U: :r.1:~ I IUI'. '.'.i Iii: ULU I Ur.1 UIALIU UI~LLULUI L Sheet I of 5 Status: Y[ NEI UF-Seismic Walkdown Checklist (SWC)Equipment ID No. V-FE-11 Equip. Class, (10) Air Handlers Equipment Description Div I EFT Charcoal Air Filter Unit Location: Bldg. EFT Floor El. ý _ Room, Area EFT Manufacturer, Model, Etc. (optional but recommended) Instructions, for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL; The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE1 NZ 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?Shrinkage cracks noted but does not adversely affect seismic capacity of anchorage.

5. Is the anchorage configuration consistent With plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YN NEI U' N/AZ1 YN NEI UE- N/AZ YO NEI UM N/AE3 YEI NEI U N/AN YN NO UE-I Enter the equipment class name from Appendix B: Classes of Equipment. PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DISCLOSURE Sheet 2 of 5 Status: YE NE-- U[-Seismic Walkdown Checklist (SWC)Equipment ID No. V-FE-11 Equip. Class' (10) Air Handlers Equipment Description Div I EFT Charcoal Air Filter Unit Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI U[] N/Al 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YD NO' U0- N/An and masonry block walls not likely to collapse onto the equipment? Drywell noted and determined that it meets seismic II over I criteria based on documentation in modification 79N745 (Doc D400).9. Do attached lines have adequate flexibility to avoid damage?Boot connecting train to blower unit has good fiexiblity. .10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEI UE] N/AE]YO NE] UED Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory ILA~Loo.Date: 2 [ *Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. !'V. HI~Lg- rIu-::u.~:n ~ ~M UiI i~ ,I~Sheet 1 of 4 Status: YE NI U-]Seismic Walkdown Checklist (SWC)Equipment ID No. V-SF-1O Equip. Class' (09) Fans Equipment Description 11 Diesel Room Vent Fan Location: Bldg. TB Floor El. Room, Area DG BLDG Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.AnchoraRe 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Drawing R-81676-1 (NX-9290-3) shows connection of fan to skid. It was not used since inspection is of skid anchorage.

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?SW motor and anchor has a hairline crack going through it. Since anchorage analysis concludes no tensile forces the crack is not a seismic issue.5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YN NEI YZ NEI UE1 N/AE YZ NEI UE1 N/AEl YN NE U-1 N/AE YI NEI UE- N/AEl YM NEI UE1 IEnter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 4 Status: YZ NEI U-]Seismic Walkdown Checklist (SWC)Equipment ID No. V-SF-i0 Equip. Class' (09) Fans Equipment Description

11. Diesel Room Vent Fan Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

Y[ NEI UE- N/AZ 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NEI U0 N/AZ and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y[ NE Un N/AZ YN NE UFI Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Walter Djordlevic Date: Scott Luckiesh Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI -WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PflOPflIETARY INjFGRMATION)P WII 1 OLD9 FROM UJBLICI 9DISCLOCWFlE Sheet I of 4 Status: YD- NO U[-Seismic Walkdown Checklist (SWC)Equipment ID No. V-SF-9 Equip. Class, (09) Fans Equipment Description 12 Diesel Room Vent Fan Location: Bldg. TB Floor El. Room, Area DG BLDG Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YO NEI 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

Drawing NX-9290-3 anchor bolt configuration does not match field. Bolt pattern does match 1995 SEWS. See CAP 1345975.6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions? YO N[-- ULI N/AZ YO NEI U] N/A[YO N[-- UE1 N/AZ YEI NO U-- N/AZ-Y[ NEI UD'Enter the equipment class name from Appendix B: Classes of Equipment. PROPRElT--ARY IIFORMATIO"N I -I 1HH=9 FROM PUBLIC ll,-ClIURE Sheet 2 of 4 Status: Y[Ii NZ U-]Seismic Walkdown Checklist (SWC)Equipment ID No. V-SF-9 Equip. Class, (09) Fans Equipment Description 12 Diesel Room Vent Fan Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YE NEI UE1 N/A[9 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YED NEI UE- N/A and masonry block walls not likely to collapse onto the equipment? Noted room heater adequately supported via (2) -1/2" diameter threaded rods.9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YZ NEi UE[ N/AE[YED NEI UEl Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Anchorage used for configuration verification is from S&A calc 91C2687. See attached calc. (10) -3/4" diameter cast in place bolts.Evaluated by: Bruce M. Lory (/Date: &92 6 ,..Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUJBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY

• INFORMATION WITI 19OLD FROM PUBLIC DISCLOSURE Sheet i of ii Status: YN N[-] u[]Seismic Walkdown Checklist (SWC)Equipment 1D No. X30 Equip. Class, (04) Transformers Equipment Description Transformer Location:

Bldg. TB Floor El. m_ Room, Area Lower 4kV Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? Four anchors on base plates for a total of (24) -3/4" diameter concrete expansion anchors.2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

Y 1NO YO NEl UE- N/A[l YZ NEI UL N/Arl YI NEI UE[ N/Anl YEI NEI U['1 N/AO YE NE UE-I Enter the equipment class name from Appendix B: Classes of Equipment. PROPR[IrTARY)I"TV INFIRIATIOI PIITHHL OMI P-- rIC'l PIS,-o,1,l Sheet 2 of 11 Status: YN NEI U-Seismic Walkdown Checklist (SWC)Equipment ID No. X30 Equip. Class' (04) Transformers Equipment Description Transformer Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? Cage is mounted to frame and frame is secured by same 24 anchors via structural members.YO NEI UEI N/AZ 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YN NO UEI N/A0 and masonry block walls not likely to collapse onto the equipment? Overhead duct and cable tray supports are ductile. Strap and light metal strut support systems are ductile.9. Do attached lines have adequate flexibility to avoid damage?Conduit has adequate flexibility.

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YlZ NE U-1 N/AZ YN NE UZ1 Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Walter Diordievic Scott Luckiesh I-Ij V-Date: ( ,2/-- Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI -WITHHOLD FROM PUBLIC DISCLOSUJRE The remaining pages are withheld from public disclosure. i-tu .0H1 M R1L P I ;i i'iu! wri.' 1 Sur. Wy 0. in Iul=H l i (H.1 i Wbk=Ib HUIL 1U isI LE Sheet 1 of 4 Status: YR NEI U--Seismic Walkdown Checklist (SWC)Equipment ID No. Y72 Equip. Classi (04) Transformers Equipment Description 120 VDC Transformer Feeding Y73 Location: Bldg. EFT Floor El. ý _ Room, Area All Manufacturer, Model, Etc. (optional but recommended) Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results ofjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)? YE NE 2. Is the anchorage free of bent, broken, missing or loose hardware?3. Is the anchorage free of corrosion that is more than mild surface oxidation?

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

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

SQUG SEWS show four 3/8" diameter anchors on 18" x 15" spacing.YO NEI U'- N/AZ YO Nil U[-] N/A[: YN NEl UZ' N/AEl YN NEI UI- N/AZ3 YN NE] U[: I Enter the equipment class name from Appendix B: Classes of Equipment. Sheet 2 of 4 Status: YN NEI U-Seismic Walkdown Checklist (SWC)Equipment ID No. Y72 Equip. Class' (04) Transformers Equipment Description 120 VDC Transformer Feeding Y73 Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures? YN NEI U- N/AUl 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO NEI Ut N/AU and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?Rigid conduit is sufficiently stiff. Connection is rigid and acceptable.

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NW U- N/AU YZ N' U-Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory L~-~ /*Date: _,,?102-1. .Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSRI -WIITHHOL D FROM PI RL IC DISCL OSRE R The remaining pages are withheld from public disclosure. Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! Withhold from Public Disrcls-re C Area Walk-By Checklists (AWCs)This appendix provides the Area Walk-By Checklists (AWC) completed as of November 9, 2012 for the MNGP. Table C-1 provides the a list of the Area Walk-By checklists, as well a list of SWEL items associated with each area, and whether or not the checklist was marked as "Y" or "N" (the checklist status). If a checklist status is marked "Y," then the SWEs concluded in the field that the equipment was seismically acceptable. If a checklist status is marked as "N," then the SWEs judged there was a potential adverse condition which required additional information to determine if the equipment was seismically adequate, complied with current site procedures and met current licensing basis requirements. None of the observations noted in the SWCs were found to be adverse seismic conditions that significantly affected or degraded safety related functions of equipment. Appendix F of this report provides the disposition of observations noted in the AWCs.The AWCs are provided after this table, and are in the same chronological order as listed in the table below.This table and the following AWCs include information on the location of SWEL components, which is considered Sensitive Unclassified Non-Safeguards Information (SUNSI), of which the loss, issue, modification, or unauthorized access can reasonably be foreseen to harm the safe operation of the nuclear plant. Pages which contain proprietary information have been marked, and the sensitive information has been redacted.Pages which contain proprietary SUNSI information have been marked.Table C-I: Monticello Completed AWCs Area Walk-By Area Walk-by Checklist Checklist AresignationEquipment Tag Status Designation (Y/N)EFT D100 1 N D90 Appendix C -Area Walk-By Checklists C-1 Monticello Nuclear Generating Plant Seismic Walkdown Report R I Im Rm'IuMIl~i .-Itni Rm WzI-'urwnic 7 uisciosur Table C-I: Monticello Completed AWCs Area Walk-By Area Walk-by Checklist Checklist Designation Equipment Tag Status (Y/N)V-EAC-14A EFT-DIV1 V-EF-40A 2 N V-ERF-14A V-FE-11 3 EFT-DIV2 V-EF-40B Y MCC-1 34 4 EFT-N-DIV1 N Y72 C-292 5 EFT N Y81 6 FUEL P-11 Y AV-3147 AV-4024 7 INTAK P-109A Y P-111A P-111C D1 8 PAB-11 BATT Y D11 Appendix C -Area Walk-By Checklists C-2 Monticello Nuclear Generating Plant Seismic Walkdown Report SRISM Withhold from Pu--blic Dicoqu-re-Table C-1 Monticello Completed AWCs-Area Walk-by Checklist Checklist Designation. Equipment Tag Status ... , YN (YIN), D31 D3A 9 PAB-13BATT D3B N D40 D54 C-253A C-30 10 PAB-CSR C-303A N C-39 C-41 C-03 11 PAB-CR N C-253D Appendix C -Area Walk-By Checklists C-3 Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI fr-oam Publicr Diaelosure Table C-I: Monticello Completed AWCs ..Area Walk-by Checklist Checklist Designation Equipment Tag Status (YIN)C-129A CV-1 728 MO-i 741 P-202C P-208A 12 RX-ARHR N P-88A RV-1 990 SV-1 728 T-75A V-AC-5 13 RX-BRHR C-129B Y CV-2043 FT-23-82 MCC-312 14 RX-HPCI N MO-2063 P-209 PS-23-97A 15 RX-RCIC MO-2078 N C-290A 16 RX-TORUS Y LT-2996 Appendix C -Area Walk-By Checklists C-4 Monticello Nuclear Generating Plant Seismic Walkdown Report f btuNbI V.".ItnoIa Trom Public wisclosure Table C-1: Monticello Completed AWCs Area Walk-By Area Walk-by Checklist Checklist Designation Equipment Tag Status (YIN)MO-2106 17 RX-RCIC N TS-1 3-79C AO-2379 18 RX-TORUSCAT-E MO-2010 Y SV-2379 19 RX-TORUSCAT-NW AO-4539 N C-122 20 RX-EAST K-10A N N3347 MO-2012 21 RX-E-SDCR Y MO-2030 CRD HCU W 22 RX-WEST CRD16A Y CV-3-32A 23 RX-W-SDCR MO-2013 Y MCC-313 24 RX-MG SET N P-73A P-203A 25 RX-SBLC N T-200 Appendix C -Area Walk-By Checklists C-5 Monticello Nuclear Generating Plant Seismic Walkdown Report burjbi vv"itnowa

rom Funlic wisclosure Table C-I

Monticello COmpleted&AWCs rea Walk-"y .Area Walk-by Checklist Checklist Dresignation Equipment Tag Status Deignation (YIN)C-55 26 RX-SOUTH LT-2-3-72A Y LT-2-3-72C 152-505 27 TB-L4KV BUS 15 N X30 28 TB-SOUTH MCC-133B N 29 TB-1 1 DG-DAY T-45A Y BPM-1, Location 11 DG C-91 C-93 G31 G-3A 30 TB-11DG-RM K-8A Y K-8B N3346A N4301A P-222A T-79D 31 TB-12DG-DAY T-45B N Appendix C -Area Walk-By Checklists C-6 Monticello Nuclear Generating Plant Seismic Walkdown Report Q!CIQMI !Aiafkk,-.I, fr^ Daikll,= Dicas Table C-I: Monticello Completed AWCs Area Walk-By Area Walk-by Checklist Checklist D .esignaion Equipment Tag Status (Y/N)G-3B 32 TB-12DG-RM N T-80A 33 TB-SOUTH T-ALTN2B N 34 TB-U4KV NA (See note below) N V-SF-10 35 TB-11DG Y DM-8089J1 V-SF-9 36 TB-12DG Y DM-8089A1 Appendix C -Area Walk-By Checklists C-7 Sheet 1 of 6 Status: YE[ NO Ul]Area Walk-By Checklist (AWC)Location:

Bldg. EFT Floor El. m_ Room, Area' Battery Charger Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YO NEI UI- N/All 2. Does anchorage of equipment in the area appear to be free of significant YO NEI UL- N/AL]degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?HVAC duct protrudes in front of MCC-144. Unistrut supporting the duct is within 3/8" from front of MCC.4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Drywall in comer -does it meet seismic 1// criteria? This is next to the D70 battery charger.YO- NO UL] N/AL]YI- NO UL- N/AL]If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETAfRY PIFORMATION WITI ^,-IOLD FROM PULI- OCrE Sheet 2 of 6 Status: YE] No U]--Area Walk-By Checklist (AWC)Location: Bldg. EFT Floor El. Room, Area' Battery Charger Room 5. Does it appear that the area is free of potentially adverse seismic YOI NO UI1 N/ADl interactions that could cause flooding or spray in the area?3/4" copper line identified with a two support rod support about 8' apart.Soldered union 3' from one support. Is this line designed for seismic category II/I, and if not, does this line present a spray problem on class I equipment if it ruptures?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?YZ NSI US- N/AS 7. 'Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YI NSI US- N/AS 8. Have you looked for and found no other seismic conditions that could YZ NE-I UO'adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lor,,- Date: O.P,4 -2//2_Steve Kaas2.,. Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 28 Status: Y-- NO UI--Area Walk-By Checklist (AWC)Location: Bldg. EFT Floor El. m_ Room, Area, Div I Instructions for Completing Checidist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YE NEI U[ N/AU 2. Does anchorage of equipment in the area appear to be free of significant YZ NEI ULI N/AU degraded c6nditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YE NE U-- N/AU YZ NEI U-- N/AU IIf the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. Sheet 2 of 28 Status: YE] NZ Ur Area Walk-By Checklist (AWC)Location: Bldg. EFT Floor El. ý _ Room, Area, Div I 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?1) 3/4" diameter copper line with soldered connection. Line appears supported in horizontal direction but not vertically. Hand valve WDW 60 one elbow within 1/16" of conduit. This elbow might contact the conduit during a seismic event, breaking a solder joint and causing spray of saftey-related equipment.

2) Fire station contains victaulic couplings.

Station is bolted to wall. FP line, runs up to roof of this floor and into the floor. No sign of lateral bracing. Three victaulic couplings are spaced closely together. Is this line adequate for seismic loads? Line is charged with water. Line is also in contact with conduit N43158 and in contact with HVAC duct support.(SWEs could not see lateral support above for FP line).3) 3" vertical pipe or conduit of unknown material has a two-bolt pipe coupling, runs floor to ceiling. It has two wall supports. The line cuts 1" into insulation on ESW line. Is this line adequate for seismic Il/I? See penetration F2-39155.4) Two 3" diameter line connected to North wall (drywall) runs 5' along wall, then 3' into EFT room, and then vertically for 6' connects to ceiling.There are five elbows that appear to be cast iron threaded onto malleable steel pipe. There are no supports. Done under mod # E-81N300 (P.O. # 051926C-42)

6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YE] NO UE1 N/A[YE NEI ULI N/A--YZ NEI UED N/AU 8. Have you looked for and found no other seismic conditions that could YO NEI UDI adversely affect the safety functions of the equipment in the area?Shrinkage cracks noted everywhere on floor. Not of concern.Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lor ,y. ' Date: 0 211. 2/Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSUIRE The remaining pages are withheld from public disclosure. PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DSCOLOSURE Sheet 1 of 4 Status: YN] NE] U[]Area Walk-By Checklist (AWC)Location: Bldg. EFT Floor m Room, Area 1 Div 2 Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YN NEI UEI N/AZ 2. Does anchorage of equipment in the area appear to be free of significant YN NEIl UL- N/AEi degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YN NEI U-1 N/AZ YE NEI UE- N/All 1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY INFfRMATION WITHHOLD FROM PUBLIC DISCLOSURE Sheet 2 of 4 Status: Y[ NEJ U-Area Walk-By Checklist (AWC)Location: Bldg. EFT Floor El. Room, Area 1 Div 2 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?1) Fire hose station anchored to wall with (4) -3/8" anchors. Fire hose station serves as anchor for fire hose stanchion. SWEs judge configuration adequate for anticipated seismic loads. This is not a flood hazard.2) Noted a 2" drain pipe with victaulic couplings. Pipe has one pipe support consisting of structural steel with U-bolt. Structural steel is anchored to wall with 2 bolts. SWEs judge piping configuration acceptable.

6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YO NEI UO N/AE3 YN NEI ULI N/AU YN NEI UrI N/AD 8. Have you looked for and found no other seismic conditions that could YO NEI UEI adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lor j&y. Date: -g Steve Kaas _ 0/Z Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DISCLOSURE Sheet 1 of 8 Status: YE] NN U[]Area Walk-By Checklist (AWC)Location: Bldg. EFT Floor El. m_ Room, Area' North Room (Div 1)Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YO N[] UE' N/AE1 2. Does anchorage of equipment in the area appear to be free of significant YO NEI ULI N/AEi degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YN NEI UE1 N/AE YN NEI UE- N/AE-I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about.35 feet from the SWEL item. --=- I r-A ---1-1. --Sheet 2 of 8 Status: Y[-] NO Ur-Area Walk-By Checklist (AWC)Location: Bldg. EFT Floor El. ý _ Room, Area' North Room (Div 1)5. Does it appear that the area is free of potentially adverse seismic YEI NED UE- N/AE!interactions that could cause flooding or spray in the area?1) 4" diameter line from south wall is connected at wall with structural steel anchored to CIP concrete. It has victaulic coupling midspan and is anchored above MCC with U-bolt/I-beam support. Concern is differential displacement of south steel beam versus north CIP wall.2) 4" diameter piping containing victaulic couplings have good structural support to CIP. SWE's deemed adequate.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?YN NE! UE! N/AE!7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YER NE! UE1 N/AE!8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?Y NEI Ur-Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory j o-,- Date: 08/02 //-Steve Kaas (. Monticello Nuclear Generating Plant Seismic Walkdown Report SUJNSI WITHHOLD FROfin PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY I.FORMATI.O." WillTiiOLD FROM PUBLI.C DISCLOURE Sheet 1 of 9 Status: YEI NO U[]Area Walk-By Checklist (AWC)Location: Bldg. EFT Floor El. Room, Area' 3r' Floor Instructions for COmpleting Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YZ NEl Ur-1 N/AEl 2. Does anchorage of equipment in the area appear to be free of significant YN NEl U0 N/A[-degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?YI NEI U[] N/AU[4. Does it appear that the area is free of potentially adverse seismic spatial Y-- NIO US N/AU interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

C-303B & C-304C are within 3/4" at top. Is this acceptable? 'If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY INFORMATION WITHHO-tt-0lD FROM PUBLIC Sheet 2 of 9 Status: YE] NO Ur-Area Walk-By Checklist (AWC)Location: Bldg. EFT Floor El. Room, Area 1 3 rd Floor 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?Roof drain system contains victaulic couplings on 2" and 6" The 2'lines are well supported with 3" angle, welded to anchor plates. Plates are bolted to wall with 3/4" anchors. Pipes are all U-bolted. 6" line uses I-beams welded to anchor plate. SWEs judge this to be acceptable.

6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?Fire hose station anchored to wall, via 4 bolts on inside.7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YE NEI UE] N/AE]YO NEI UE] N/AU YE NEI Ur- N/AU 8. Have you looked for and found no other seismic conditions that could YD- NO U-]adversely affect the safety functions of the equipment in the area?Floor to ceiling 6" roof drain has victaulic coupling 4' from top and has no bracing. Is this seismically acceptable? Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lora , J4. Date: bW62b.-Steve Kaas 90E/'5, Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBgLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPnRIETARY INFORMATION WIT' Q6OLD FROM PUBLI'C DISCLOSURE Sheet 1 of 6 Status: YN N-] uFL-Area Walk-By Checklist (AWC)Location: Bldg. Fuel I Floor El. Room, Area' Main Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

1) P-59 panel, was checked for wall anchor. SWEs found panel is screwed to the wall plus an electrical box fitting is connecting it to a wireway.2) Cresent wrench was wedged underneath P-59. Crescent wrench was removed.2. Does anchorage of equipment in the area appear to be free of significant degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Y10 Nil UD N/Al YN NIO UD N/AD YS NEI UE N/AD Y0 Nil UL- N/AO If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY INFORMATION WITHHOLD FROM PUJBIC DISCLOSURE Sheet 2 of 6 Status: Y[Z NE] U-E Area Walk-By Checklist (AWC)Location: Bldg. Fuel Floor El. Room, Area, Main Room 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? Noted: An oil rag container and a toolbox was on the floor next to P-11.However, these items were on the floor and will not affect the pump or its conduit in a seismic event.YEl NEI UI- N/AS YN NEI U0 N/AU YZ NEI ULI N/AEl 8. Have you looked for and found no other seismic conditions that could YlM NElI UD adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Noted: Oil lines going into wall had painted over section of pipe at wall.Evaluated by: Bruce M. Lory / aL 42 Date: 0/ Z-Steve Kaas "-Z/ Z_ Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBgLIC DISCLOSURE PrFPRIET-AR INFOGRMATION WIm 1 1^nTHHOL= FROM PUBLIC DIG6rLO$RE Sheet 1 of 14 Status: YN ND] Uf-Area Walk-By Checklist (AWC)Locati6n: Bldg. INTAK Fo. Oor E3l Room, Area' Main Room Ihstructionsifor Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space.below each of the following questions may be used to record the results ofjudgments and findings.Additional space is'provided at the end of this checklist for documenting other comments.L. Does anchorage of equipment inthe atea appear to be free of potentially adverse seismic conditions (if Visiblewi'thout necessarily opIeuning cabinuts)? Pager telephone bog is missing two of four anchors but not an as selsmlc~capaclty Is greater than demand and the box is not essential.

2. Does anchorageof equipment in the area appear io: be free of significant degraded conditions?

All equipment is well coated Wiih little or no oxidation evident.3. Based onA Visual inspiction from the floor, do the c6ble/oh&duit raceways and HVAC ducting to be free of poteti ally adverse-seismic conditions (eOg., condition of supports is adequate and fill conditions of Cable traysappear io be inside acceptable limits)?Ohe'strut support has.some build-up of calcium or similar materIal but'poses no~hazard to nearby components.

4. Does it appear that the area is free of potentially adverse seismicspatial interaptins

with other equipment in thearea (e.g., ceiling tiles and lighting)?

'Scaffolding near, and over P-1ID (WO 451760/4483i), and near;sdreenwash header, is unahchored Ond unbraced. It does not appear to be a credible hazard to pump or piping except for some instrumentation (e.g. FIR-4231). Staging area in SE corner of lItake sturbtuie is w611..managed in that the wheels are chocked bnd items are.chained. YO NE UDl N/AL YO NO UD N/AD Y0 ND WE N/AD YN NOI UEDN/AO'ithe room in which the SWEL Item is located is very ]arge.(e.g, Turbine Hal), the area selected sho0ld be dacribed.This selected area should be based on judgment, e.g., on the'order of abcut 35 feet from the.SWELitem. PROPRIE"lTARY INFORMATION WITHHOLD'9I FROM PUiBL" DISCLGO"URE Sheet 2 of 14 Status; Y[ NO-] U13 Area Walk-By Checklist (AWC)Location: Bldg. INTAK Floor El Room, Area' Main Room 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?All piping Is ductile (welded steel piping) or seismically supported.

6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?YIO NO U[- N/AD YO NEI UJ N/AO*1 7. Does it appear that the area is free of potentially adverse seismic YO NO" UlI N/AQI interactions associated with housekeeping practices, storage of portable equipment, and temporary installations.(e~g., scaffolding, lead shielding)?

Fire header nearsupport P-IOOC-H212 will collide with Backwash Strainer Flow and with hanger H212 which Is designated Cat 1, Class C. Theretis minimal available space to generate significant inertial forces so this situatidn Is deemed acceptable. MMCC-40 tool cart on west side has wheels chocked, so It is acceptable.

8. Have you looked for and found no other seismic'conditions that could YO NO IIU adversely affect the safety functions of the equipment in the area?House heating, steam radlatiors, while flexible, do not pose a flooding'ssde as the :are not likely to fail, and if they did, it Would Only Introduce steam to Intake structure.

Comments (Additional pages may be added as necessary) Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. M-n-A- 1KI-MRA-1-1 11 -ý -RA M1 Sheet I of 7 Status: YN NM uW Area Walk-By Checklist (AWC)Location: Bldg. PAB Floor El. m. Room, Area 1 Battery#11 (Door 110)Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items., The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting othercomments.

1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

1) Box I P3002 external anchorage not visible in tabs, connected to bus duct J512. SWEs deemed acceptable.

2) FE-4617, two of four visible tabs w/ anchors. Deemed acceptable.

2. Does anchorage of equipment in the area appear to be free of significant degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YS NE UL] N/AD Y0 Ni UO N/AD YN NE UE- N/AE YN NO UL N/AL]I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment,'e.g., on the order of about 35 feet from the SWEL item. PROPRIETAFRY INFORMATION WITI 1 9OLD FROM PUBLI'C DISCLOSURE Sheet 2 of 7 Status: YE NEI U--Area Walk-By Checklist (AWC)Location: Bldg. PAB Floor El.. Room, Area' Battery #11 (Door 110)5. Does it appear that the area is free of potentially adverse seismic YI9 NI UrL N/AW interactions that could cause flooding or spray in the area?No wet piping or fire .protection lines in the room.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YO NEI Ul] N/AL]YO NEI U-] N/AE]8. Have you looked for and found no other seismic conditions that could YO NEl UEi adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Evaluated by: Walter Dbord/evic .A XI: X/Scott Luckiesh - Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBILIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 10 Status: YE] NZ Un]Area Walk-By Checklist (AWC)Location: Bldg. PAB Floor EI. ._ Room, Area' Battev #13 (Door 109)Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided atthe end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? Check drawing details documentation for anchorage of base plate between D40 & D54.YEI NEI UE- N/AE 2. Does anchorage of equipment in the area appear to be free of significant YZ NEI UEr N/AE degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?One loose nut for duct strap anchor above Door 109 needs to be tightened..

YEI NO UE1 N/AEl 4. Does it appear that the area is free of potentially adverse seismic spatial Y10 NE] UE] N/AEl interactions with other equipment in the area (e.g., ceiling tiles and lighting)? 1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. Sheet 2 of 10 Status: Y[] NZ u--Area Walk-By Checklist (AWC)Location: Bldg. PAB Floor El. ý _ Room, Area' Battery #13 (Door 109)5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?No hazards within area (room) itself.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? Identified saline eyewash bottle not properly engaged (snapped in).This issue is tracked by Seismic Walkdown Checklist for D3A.YE NEI ULI N/AZ1 Y[ NFE U-] N/AZ YN NE UZ N/AE-8. Have you looked for and found no other seismic conditions that could YO NEI U-1 adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary)"Reset" label for D102 was found on the floor and was placed on top of D102. Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSIM WITHHOLD FROM PUBLIC DIRSCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY INFORMATION WITHIHOCLD FROM I DISCrElSUREt! Sheet I of 24 Status: YE[- N[ U-I Area Walk-By Checklist (AWC)Location: Bldg. PAB Floor El. ý _ Room, Area' Cable Spreading Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of YZ NEI U-- N/AU1 potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant YE NEI UFI N/AUl degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit YLI NZ UEU N/AUl raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?1) Cable tray GR405, GR404, and GR403 is in contact with HVAC duct registers in 4 of 5 cases.2) Cable tray MP404 & MP403 appears to be in contact wi C-27.3) Some unistrut nuts are not fully engaged to support overhead lighting.4) Some cable tray cantilever supports have two screws while others have one. The SWEs judge the cable tray connection details as acceptable for seismic loading with trays have either one or two screws in the free end of the horizontal tray supports.4. Does it appear that the area is free of potentially adverse seismic spatial YER NUi UU- N/AUl interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Overhead lighting near C-303A had two bolts for shear connection with one thru bolt additional with no bolts. SWEs judge the one thru-bolt adequate for seismic loads.'If the room in which the SWEL item is located is vely large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. Sheet 2 of 24 Status: Y-- NO U]-]Area Walk-By Checklist (AWC)Location: Bldg. PAB Floor El. ý _ Room, Area' Cable Spreading Room 5. Does it appear that the area is free of potentially adverse seismic Nil UI- N/AU interactions that could cause flooding or spray in the area?4"drain line well supported using two U-bolt vertical rod supports.SWEs judge acceptable.

6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e;g., scaffolding, lead shielding)?

Cart had wheels locked and placed off in SW corner of CSR.YO NEI UU N/AU YED ND UEI N/AU 8. Have you looked for and found no other seismic conditions that could YO NU UU-adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Noted: Single emergency light on pole is wedged between rigid conduit & HVAC duct. Not a seismic concern.Verify coupling material on drain line and that allowable stress is not exceeded.Evaluated by: Bruce M. Lory Date: Steve Kaas _/ Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE PROPRIETAFRY INFFORMATION WITHHOLD FROM PUBLIC DISCLOSURE Sheet 1 of 19 Status: YE] NO U-]Area Walk-By Checklist (AWC)Location: Bldg. PAB Floor El. ý _ Room, Area 1 Control Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

1) Confirmed C-300 is anchored to floor so it cannot tip over onto C-08.2) Hole in base angle that's midspan in C-08 with no bolt. SWEs judge panel is still seismically anchored since panel has top bracing as well as anchor bolts in base.2. Does anchorage of equipment in the area appear to be free of significant degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YO NEI UE1 N/AZ YO NE UE1 N/AEl Y[ NE UE1 N/AZ1 Y[D NEI UE N/AZ I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. M-MMI-A- IKI- RA-1-1 ý -RA Sheet 2 of 19 Status: Y[-] NN U[]Area Walk-By Checklist (AWC)Location: Bldg. PAB Floor El. ý Room, Area' Control Room 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

1) Copier is within 30" of C-08. SWEs judge copier cannot slide or tip over into C-08, so it is acceptable where it is located. Copier has low center of gravity and is on top of carpeting.

2) Emergency Equipment cabinet across the aisle in comer from C-13 and C-37, and in the comer, -is potentially unanchored.

If unanchored, then may have potential adverse seismic spatial interaction concern since it could tip over and impact C-13, which may adversely affect C-37 also.3) Plant status board is anchored to wall with two screws. If board anchorage were to fail under seismic event, it may impact C-03. Is this board adequately restrained for seismic load?8. Have you looked for and found no otherseismic conditions that could adversely affect the safety functions of the equipment 'in the area?Doors between front and back control room panels are not restrained. Doors are free to swing in seismic event and could impact side of C-02 or C-13. This is a potential seismic interaction issue.YO NEI U N/AFl YZ NEI ULI N/AE-YEi NO UE] N/A[l YEINO UO Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Loay i) , Date: Steve Kaas / Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 14 Status: YE] NZ U--Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area' RHR A Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YED NEI UEI N/AE 2. Does anchorage of equipment in the area appear to be free of significant YO NEI U[-] N/AE3 degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YN NEI UE- N/AD YN NEI UI- N/A--IIf the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. Sheet 2 of 14 Status: Y[-] NZ4 Uf]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ._ Room, Area 1 RHR A Room 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YO NO U- N/AU YE NO UE N/AO YO NE UE N/AO 8. Have you looked for and found no other seismic conditions that could YO NO U" adversely affect the safety functions of the equipment in the area?1) Vertical tube support (3') has two anchor bolts into the floor. Nuts are not tight to the base plates. Located next to RHR-18-1 handwheel.

2) In the "A" RHR room, South wall, No. 11 RHR pump seal cooling water supply (RBCCW), line support, there is a U-bolt that is missing a nut and the other nut is not fully engaged. On a second support, one nut is not fully engaged and the other nut is partially missing. Evaluate operability.

Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Loa Date: 0,16,21/2-Steve Kaas C/' i2_, Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 2 Status: YO NFI-] U[-]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý ý Room, Area 1 RHR B Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YO NiE UE- N/All 2. Does anchorage of equipment in the area appear to be free of significant YN NEI UZ- N/AZ degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HIVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?YM NEI UE[ N/AEl 4. Does it appear that the area is free of potentially adverse seismic spatial YM NEI UE1 N/AZl interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. Sheet 2 of 2 Status: YV Nn U]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. Room, Area 1 RHR B Room 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YED NE US3 N/AS YN NEil U1 N/AS YZ NEI US] N/AS 8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the .equipment in the area?YN NEI U5 Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory A 4. @ Date: 02..Steve Kaas e-L-<~ ~ ~ Sheet 1 of 13 Status: YEI NM UE3.Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. Room, Area, HPCI Room Instructions for Completing Cheeldist This checklist may be used to document the results of the.Area Walk-By near one or more SWEL items. The space below eah. of the following questions may be used to record the results ofjudgments and findings, Additional space is provided at'the end of this checklist for documenting other comments.1. Does anchorage Of equipment in the are appear to be free of potentially adverse seismic conditions (if Visible without necessarily opening cabinets)? YO, NEI UII N/AEO 2. Does anchorage of equipment in the area appear to befree of significant YIO NO] U'-I N/AO degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit-raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?small tray (tubing) system along West & South walls observed to have only one bolt per-tray cantflever&spport supports are spaced every 6'-8'. S WE 'sjudge one bolt f6r anchoring tray to support as seismically adequate since trays are only approx. 6.to 1' wide.4. Does it appear that the area is free of potentially adverse seismic spatial interactions With other equipment in the area (e.g., ceiling tiles and lighting)?

HVAC support on south end cuts into pipe insulation on line SC 16-6-ED approximately 1-318" and insulation appears to be 1-1/2'thick. Is this a saisimic spatial interaction issue?Manual 1P Valve (PS-23-106) hand wheel in contact.with ventilation duct Will the interaction between the two cause a leakage from the valve?YO NOE U NIAO YI NO UEO N/A['If the room in which the SWEL item is located is very large (e.g., TurbineHall), the area selected should be described. This selected area should be based on judgment, e-g., on the order of about 35 feet from the SWEL item. Sheet 2of 13 Status: YEF NO uDl Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El..ý Room, Ara .HPCI Room 5. Does it appear that the area is free of potentially adverse seismic YIE NEI U] N/A'-interactions that could cause flooding or spray.in the area?6. Does it appear that the area is free.of potentially adverse seismic YMI NI] U0] N/Al]interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic YE] NO Ut] N/A[]interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? Noted: Scaffolding clamped to HPCI stairwellas adequate for seismic 1) MCC-312is within zone of Influence of R-8 cabinet for chemical control storage. SWEs cannot determine If R-8 is anchored towall from Inside. Cabinet is locked. Cabinet could tip over, impacting MCC-312 If not anchored.2) Also compressed bottle on cart is within a few inches of MCC-31Z Wheels are locked. Does this meet staton house keeping procedure? .-See CAP.1346030-. S. Have you looked for and found no other seismic conditions that could YEI NEI. UM adversely affect the safety functions of the equipment in the area?'Comments (Additional pages may be added as necessary) Evaluated. by: Bruce M. Low Date: ORIN_,______-Steve Kaas,.__ _____ Monticello Nuclear Generating Plant Seismic Walkdown Report QI IIIQI I II ,UUIr'l 1"i IDf"lMI DI II Iif rICrI nQH IDr-The remaining pages are withheld from public disclosure. PROPR'IET.ARY 'IFORMATION WITHH,--uL-D FROM PUBLIC D9ISCL-o Sheet I of 8 Status: Y[-] NO u[-Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area, RCIC Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YO NEI UE] N/AEl 2. Does anchorage of equipment in the area appear to be free of significant YE] UE] N/AFl degraded conditions? Reddish deposit noted on one of two anchor bolts on vertical support of structural angle supporting two pipelines. The lines are 1" diameter connecting SV-2849 to contaminated drain line and RCIC -(14) (2" diameter line) -"To RCIC pump suction". SWE's cannot judge condition of one anchor bolt that is covered over with corrosion deposits. Other anchor bolt is not corroded.3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?YO NEI UE] N/AE]4. Does it appear that the area is free of potentially adverse seismic spatial YO NEI UE] N/AE]interactions with other equipment in the area (e.g., ceiling tiles and lighting)? If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about.35 feet from the SWEL item. I ~Sheet 2 of 8 Status: Yr-] NO U[]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. Room, Area 1 RCIC 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YO NEI U[-I N/ADi YZ NEI UL1 N/AZ1 YN NEI UI- N/AEI 8. Have you looked for and found no other seismic conditions that could YN NEI UL adversely affect the safety functions of the equipment in the area?1) Block wall surrounding door-21 (East Div I RHR & CS App. R. Cable enclosure door). Block wall confirmed to be seismic category I per Drawing 36300-2-1. Comments (Additional pages may be added as necessary)

1) Noted: Unidentified liquid deposit on floor in corner-near vicinity of RCIC-31 check valve.2) Potentially loose screw on one panel of removable wall surrounding block wall (JI 14)3) Red tape holding label onto C-128.Evaluated by: Bruce Md. LoaiA Date: Steve Kaas ~

Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI -1 IITHHOLD FROM PUILIC DIrCLOSUioRE The remaining pages are withheld from public disclosure. I I t11 I 1L I :'.; II~~I ~JI ~r.Ir. I it r. .".~i liii RJLU I I ~ur.1 I UHLItJ UILLLUtUI L Sheet 1 of 5 Status: YN N- U[-]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area 1 Torus Bottom Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YN NEI U[ N/AE 2. Does anchorage of equipment in the area appear to be free of significant YE NO UI- N/AEl degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YED NEI UL N/AL]YN NEI U[-1 N/AEl I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY INFORMATION WITHIHIOLD FROM PUBLIC DIESCLOSURE Sheet 2 of 5 Status: YZ NEJ ULII Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area' Torus Bottom 5. Does it appear that the area is free of potentially adverse seismic YEI NEI UI- N/ADl interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YN NEI UL] N/AZ1 YZ NEI U[] N/AEl 8. Have you looked for and found no other seismic conditions that could YZ NEI U1 adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added asnecessary) Monticello Nuclear Generating Plant Seismic Walkdown Report SU3.NSI WITHHOLD FROOMRA PUBLIC DISCLOSUJRE The remaining pages are withheld from public disclosure. PROPRIETA~RY INjFORMATION)P WITHHOLD96 FROM PU)BLIC DIGGCLOCRE Sheet 1 of 16 Status: YIZ- NO! UE'Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. Room, Area' RCIC Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YM NEI ULD N/AU 2. Does anchorage of equipment in the area appear to be free of significant YE NO Ui N/AU.degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YN NUI UU- N/AU YJZ NEI UU[ N/AU If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. i '! ._1 1 .1- 1 ... .1 11 ..Sheet 2 of 16 Status: Y[-] NM UIE]Area Walk-By Checklist (AWC)Locationý Bldg. RX Floor Room, Area 1 RCIC 5. Does it appear that the area is free of potentially adverse seismic YLI NO U[iI N/ADl interactions that could cause flooding or spray in the area?1) In the RCIC room, ý, there is a chain used to secure H-1 13 (gib crane) that does not restrain it from impacting the rod hanger supporting the pipe below. Is this configuration acceptable as-is or do we need to secure H-1 13 in a different way to prevent a seismic interaction issue? H-113 is within -2" of the rod hanger.2)ln the RCIC room, there is a rod hanger for the RCIC steam supply line that is in contact with a pipe. Is this acceptable? 3)ln the RCIC room, there is a rod hanger on the RCIC pump discharge that appreas to be in contact with the RCIC steam supply line. Is this acceptable?

6. Does it appear that the area is free of potentially adverse seismic YO NEI UI' N/AEI interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

In the RCIC room, there is a chain used to secure H-113 (gib grane) that does not restrain it from impacting the rod hanger supporting the pip below. Is this configuration acceptable as-is or do we need to secure H-1 13 in a different way to prevent a seismic interaction issue? H-1 13 is within -2" of the rod hanger.YE-I NO U0i N/AUl 8. Have you looked for and found no other seismic conditions that could YO NE ULi adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lor. Date: ogle _Z4 2--Steve Kaas _/ Monticello Nuclear Generating Plant Seismic Walkdown Report SUN S-I WITH HOll 1L--D F RO r Mt PUllBILIC 1 D I R" The remaining pages are withheld from public disclosure. PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DIGSCLOSURE Sheet 1 of 4 Status: YN Nn U[Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. Room, Area' Torus Catwalk East Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YZ NEI ULI N/ADl 2. Does anchorage of equipment in the area appear to be free of significant YO ND U- N/AD degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YE ND ULI N/AD YO NEI UD- N/AD 1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. I L~iJI h~IL I :-~~' ir~i cII-~r.v\ I icJr 'XI I [IIItJLU I [~1JM UtILItY UIItLU~UtIL Sheet 2 of 4 Status: Y[ NI u[]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area, Torus Catwalk East 5. Does it appear that the area is free of potentially adverse seismic YO NEI U[-I N/AU1 interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? Steel water bucket (5 gal.) on platform not secured but will not cause adverse seismic interaction. YZ NE U-- N/AUI YO NE UU N/AU 8. Have you looked for and found no other seismic conditions that could YO NU UU adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPflIETARIA INPORMATFIGN WITI 11 OLD9 FROM PUBLIC1 PISG69SURE Sheet I of 13 Status: YE] NZ U[-Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area 1 Torus Catwalk Northwest Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant degraded conditions?

1) Tie wrap used to anchor electrical cable to conduit 2G4010.2) Two boxes on ceiling appear to be unanchored and supported by nearby unistrut.

Rigid conduit from boxes to unistrut are 2G4013 &2G4014.3) Drain line (1 of 2 mentioned above) is in contact with tube tray. Is this acceptable?

4) Crack in path of anchor for ceiling support on solenoid valve S V-4541 & SV-4592.3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?YO NEI UE" N/AE YEI NO UE: N/AE3 YO NEI UE- N/A]4. Does it appear that the area is free of potentially adverse seismic spatial YO NEI UE- N/AE interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. RRGP'h1F=T-AI-U( INLULMA I UNP WIT- 11 196PL I 1-M PIJB! PUUI(2 VI 9URUL Sheet 2 of 13 Status: Y[-] N ] U[]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ._ Room, Area' Torus Catwalk Northwest 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?Floor drains in contact with each other could be potential flooding issue.It is located between Bay 6 & Bay 7 (Penetration RB609 & RB603). It is a Welded pipe and rod hung.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YE NIE UE- N/ADl YN NE UE N/AE Yl NE UE N/ADl 8. Have you looked for and found no other seismic conditions that could YEI NEI UE adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory L .. .* Date: 2-Steve Kaas 0-6 Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI W-ITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Eko Oki I ILI."I 1 Ul ~M. (ik IUI' 'i VI IIILU UM wm UUII b htAJLU='bWVEt Sheet 1 of 9 Status: YEI- NZ U[Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area' East Instructions for Completing Checklist This checklist may be used to document the results of the'Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YO NEI UE3 N/AE]2. Does anchorage of equipment in the area appear to be free of significant YO NEI UEI N/AE]degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?Cable ties are fastening a flexible conduit to a cable tray support.Initiated CAP 1346170.4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YE] NO UE] N/AE]YO NEI UE] N/AE]I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. Sheet 2 of 9 Status; YD] N Uti]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area 1 East 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YN NEI UEI N/AZ Y[ NEIl UF- N/AZ1 YE NEI UEi N/AZ 8. Have you looked for and found no other seismic conditions that could YEI NZ UE-1 adversely affect the safety functions of the equipment in the area?1) Found two pipes suspended from bent rod hangers above the HCU's (see photos attached). The rods are bent to fit around a conduit near ,the ceiling. One rod.hanger is supporting an abandoned pipe which is capped at both ends.2) The other rod hanger supports a heating steam line. This is not a seismic concern. However, is this configuration adversely affecting the conduit?Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory Date: Steve Kaas 6/2 ,1/2-Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. iiOrlIETArl-INF-irMATI-N WITHHO-LDUU96 F--RA PUBLIC DIGlGO- iRE Sheet I of 7 Status: Y[ NEI UI-Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. Room, Areal East SD Cooling Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YM NEI U-1 N/AEl 2. Does anchorage of equipment in the area appear to be free of significant YO NEI U-- N/AEl degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions, of cable trays appear to be inside acceptable limits)?YZ NOI UO'- N/AO 4. Does it appear that the area is free of potentially adverse seismic spatial YIN NO UO N/Anl interactions with other equipment in the area (e.g., ceiling tiles and lighting)?(See M02030 sheet)'If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. ., I.,i- UlH '..";. I.IN VWI IHHULU PI UI 6LLIU U '-I Sheet 2 of 7 Status: Y[ NR- ur--Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area' East SD Cooling Room 5. Does it appear that the area is free of potentially adverse seismic YIN NEI UE) N/AU interactions that could cause flooding or spray in the area?1) Piping penetration for FZ-1380 is in a seismic category I wall, deemed acceptable.

2) (2) Insulated piping lines: CST to "A" containment spray / CST supply, lines are welded steel pipe, deemed acceptable.

3) Floor drain line with welded joints adjudged acceptable.

6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?YO NEI U[] N/AU 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

Moveable ladder is in corner of area but it will not have an adverse seismic interaction as it is outside a h + I' distance.YZ NEI UEr N/Ar)8. Have you looked for and found no other seismic conditions that could NEI UD1 adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Evaluated by: Walter Diordievic Date: ILI Scott Luckiesh h/ - Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSU'RE The remaining pages are withheld from public disclosure. Sheet 1 of 7 Status: Y[ NEI U[]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area 1 West Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if Visible without necessarily opening cabinets)? Tall cabinet near C-216 is 50" tall x 24"x 24". The wheels on the cabinet are locked. Cabinet could tip over. C-216 verified as Non-Safety Related. Therefore cabinet is adjudged as not an adverse seismic interaction issue.YE NEl UL- N/All 2. Does anchorage of equipment in the area appear to be free of significant YN NE] U[:] N/Ar]degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YZ NEI U'- N/AL]YE NEI U[] N/AL]1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described, This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY-INFORMATION WITH HOLD FROM PUBLIC Sheet 2 of 7 Status: YN NO- U[-Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area 1 West 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YZ NEI UO N/AU YN NO UO N/AU YN Nn U' N/AU 8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?YN NI U-1 Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lorv L47, .,- Date: C 0/ 2.l Steve Kaas I/z Monticello Nuclear Generating Plant Seismic Walkdown Report S'JNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIET.ARY INFORMATION WITH H1 OLD FROM PUBLIC DISCLOSURE Sheet 1 of 2 Status: YZ Nn] U--Area Walk-By Checklist (AWC)Location; Bldg. RX Floor El. ý .Room, Area 1 West SD Cooling Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YED NEI U- N/AS 2. Does anchorage of equipment in the area appear to be free of significant YIE NEI US N/AS degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceilingtiles and lighting)?

YN NEI USl N/ASl YN NE] US N/A[S I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PRGPflIET-ARY INFEAMATIO!N VWiT! IGI OL FROM PUBLIC 9I8GLOSUflE Sheet 2 of 2 Status: Y[ N- U[]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. m_ Room, Area 1 West SD Cooling Room 5. Does it appear that the area is free of potentially adverse seismic YN NEI UOI N/ADl interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YZ N[-] Ur- N/AEl YE NEI UE1 N/Ar-I 8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?YE NEI Un Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory .Date: 6AY101 Steve Kaas Sheet I of 13 Status: YEI NO U[Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. .. Room, Area, MG Set Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? Y1Z NEI ULI N/AZl 2. Does anchorage of equipment in the area appear to be free of significant YE NEI- UI1 N/AZ degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?YJZ NEI UZ- N/AZ 4. Does it appear that the area is free of potentially adverse seismic spatial YN NEl UI- N/AZl interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

IIf the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY INFGRMAT-,9". WITH 11 OLD FROM PUBLIC DSLOSURE Sheet 2 of 13 Status: Y[- NI UL--Area Walk-By Che'cklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area 1 MG Set 5. Does it appear that the area is free of potentially adverse seismic YEI NZ UEI N/AL-interactions that could cause flooding or spray in the area?1) FP line 3" -4" diameter with victaulic couplings near F-20355 and F-20360. FP line has threaded couplings that might be cast iron. Some couplings are midspan.2) The line to a heat-activated-device (HAD) for FP system is in contact with Service Air Line.3) Smaller cast iron FP line has same threaded couplings as 3" -4" FP line by 12 MG Set.4) Large line with victaulic couplings (10"- 12"- Roof drain) comes from wall, takes 90" turn and enters ceiling. SWEs judge acceptable for seismic loads since relative displacements of wall and ceiling are negligible due to connection design between ceiling and wall.6. Does it appear that the area is free of potentially adverse seismic Y! NEI UE- N/AE interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YN NEI UE- N/A[]8. Haveyou looked for and found no other seismic conditions that could YN NE UE adversely affect the safety functions of the equipment in the area?1) Block wall noted around Door-73 is seismic category 1 per drawing NF-36300-1-2 (South wall).2) Electrical box for penetration F2-0350 does not have anchorage in block wall. Box is connected to conduit 1K3100. Block wall is seismic category I per drawing .NF-36300-1-2. Comments (Additional pages may be added as necessary) Housekeeping -FME (rags or paper) was identified behind C283A.In area walked by is a FP nozzle in contact with cable tray adjacent to Generator

11. Cable tray support is mounted to wall. The fire protection line is not charged since it is a deluge system for motor Generator 11.Evaluated by: Bruce M. Lorv y ).. Date: 691021L2_Steve Kaas A 2-Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure.

PRO-PRIETARY INFORMATIl." WITI I IOLD FROM PUB1IC DICL6OIURE Sheet I of 6 Status: Y0 NO U[Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ý _ Room, Area 1 SBLC Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YN NEI U0 N/AUl 2. Does anchorage of equipment in the area appear to be free of significant YE NEI UE' N/AU degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

See scaffold discussion for SLC tank T-200 and pump P-203A.YN NEI UU1 N/AUl YE- NZ UE1 N/AUl' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PRnrRIETARY INFORMATION VWIT- UI IHGL' FROM PUOLIC DISI-lOURE Sheet 2 of 6 Status: Y[- NO U[-Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. Room, Area' SBLC Room 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?Fire protection line and welded steel floor drain line are adequate. Roof drain line is mechanically coupled but well supported. If it leaks water it is collected through floor drains.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?Chemical control storage location flammables cabinet MMCC-08 is located 10' away from SLC pump. The cabinet is not anchored and contains lubricants and oil products. If this cabinet tips over, there is no viable ignition source, so the configuration is deemed adequate.7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? As an observation, the TH-4 Temporary Power Pack is unanchored and is next to MCC-1 11 (non-essential). Flammable cabinet is also not anchored. Neither of these situations poses an interaction hazard of Seismic Category I components since they are not in close proximity. YO ND U-1 N/AU YN NEI U-- N/AD YN NDI U-- N/AD.8. Have you looked for and found no other seismic condi .tions that could NE"I UE'adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Evaluated by: Walter Dbordievic Date: Scott Luckiesh___ ______ Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. I A 1.-1 11 --1-1 --- ^1. ..Sheet 1 of 8 Status: YS N[] U-]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El. ._ Room, Area' South Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? MCC 122 is top braced and anchored, so it is seismically acceptable: A TWS channel A cabinet is anchored.YN NEI UD] N/AL-2. Does anchorage of equipment in the area appear to be free of significant YN NEI U[:] N/AL]degraded conditions? Checked CS T pressurizing to B RHR Containment Spray line for straps to brackets and found them in place, so it is acceptable.

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?HVAC support straps are ductile. All piping is welded steel and ductile.Junction boxes are anchored to reinforced concrete wall.4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Cable trays are strut supported and ductile, thus acceptable. Per drawing NF-36300-1-2, Fig. 3-ID all masonry block walls are safety related and seismically evaluated. YO NEI UL N/AL]YN NEI U[] N/AL-'If the room in Which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY I'FO-GRMATIO, WITHHOLD FROM PULIGC DISCLOSURE Sheet 2 of 8 Status: Y[ N'] UM]Area Walk-By Checklist (AWC)Location: Bldg. RX Floor El._ Room, Area' South 5. Does it appear that the area is free of potentially adverse seismic YI NE UO N/AZ interactions that could cause flooding or spray in the area?FP and floor drains piping are ductile so no credible potential for rupture leading to flooding.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YO NEI UI N/AZNEI UL N/AE1 8. Have you looked for and found no other seismic conditions that could YO NHi UEH adversely affect the safety functions of the equipment in the area?Block-out on south wall is not a hazard due to arching action and no equipment is found in the area.Comments (Additional pages may be added as necessary) Evaluated by; Walter Dbordevic /Date: /Scott Luckiesh Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI -WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DISCLOSURE Sheet 1 of 20 Status: YE] NO UI-Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. ý _ Room, Area' Lower 4KV Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? Y[0 NEI UE- N/AE 2. Does anchorage of equipment in the area appear to be free of significant YED NE- U[:] N/AU degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and H-VAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?Bent rungs on cable ladder trays evaluated by NCI-89-052.

Judged acceptable.

4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

1) Hoist is resting on LC-101 480V Load Center. It also poses an impact hazard, and has open s-hooks.2) Fire extinguisher near non safety 4.16kV 4kVB-06 cubicle is an interaction hazard as it can fall off hook.3) Hoist restraint on non-essential LC-109 should be replaced with a restraint more appropriate than wire.YE NEI UE1 N/AU YEI NZ U0- N/AU I If the room in which the SWEL item is located is vely large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY INFORMATION WITI 1 OLD FROM PUBLIC DISCLOSURE Sheet 2 of 20 Status: Y[-] NZ U-Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. Room, Area, Lower 4KV Room 5. Does it appear that the area is free of potentially adverse seismic YN NEI Url N/AFl interactions that could cause flooding or spray in the area?Piping in south end of room is non-seismic piping but is not an adverse seismic interaction because the pipe is welded steel.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause afire in the area?H't2 line and oil/H 2 lines are welded steel so there are no adverse seismic interactions that could cause a fire.7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? Non-essential XFMR X-90 has missing bolts. There is an existing W 0.34875 noting this condition. YZ NEI- UL- N/AL!YED NI] U['I N/AE!8. Have you looked for and found no other seismic conditions that could YO NEI ULI adversely affect the safety functions of the equipment in the area?Junction Box NJ5220 near 2R Aux. Trans. Sudden pressure relay has no external anchorage. However, the junction box is very secure.Adjudged adequate.Comments (Additional pages may be added as necessary) Evaluated by: Walter Dbordievic Date: _____________ Scott Luckiesh 7 / , Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS1 WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. I zul IaLIgK~' :r~, ~r.::~: :u~..'~: Sheet 1 of 3 Status: Y[-] NZ uE-Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. m_ Room, Area' South Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YZ NE3 UE] N/AD]2. Does anchorage of equipment in the area appear to be free of significant YZ NEI ULI N/A[l degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and H{VAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?Lighting is pendant-hung and can swing into MCC-133B.

Cable trays are supported by strut systems which are adequate.4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)? Pendant light is an interaction hazard to conduit connected to MCC-133A.YEJ NO U0I N/All YEI NI UE- N/AE]' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRI.ETARY INFORMATIIN WITHHOLD 1 r9 FROM DIrCLOlURE Sheet 2 of 3 Status: Y[-- NM U-]Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. Room, Area' South 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? No items in room.YO NEO UE[ N/Ail YO NE UE- N/AEl YE NE UDI N/AlI 8. Have you looked for and found no other seismic conditions that could YED NEI UEI adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Evaluated by: Walter Dordevic Date: J I Scott Luckiesh /Z________ Monticello Nuclear Generating Plant Seismic Walkdown Report 01 IK11CI -AIITrUU II r% CDnR 01 I011 iftI-r'tlfI (n l ID0: The remaining pages are withheld from public disclosure. PROPRIETAR4Y 'I"- "-MATI'N WIT^,.- IOL, FRM PUBLIC ,,--LOURE Sheet 1 of 5 Status: YZ NEI UD-Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. ý _ Room, Area' 11 DG Day Tank Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YZ NO UO N/AE 2. Does anchorage of equipment in the area appear to be free of significant YZ NO UE-1 N/AU degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?Drain line is deemed acceptable given short span.YM NEI UE1 N/AU 4. Does it appear that the area is free of potentially adverse seismic spatial YLZ NE Ur N/AU interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY INFO-RMATI-N WITHHOLD, FROM PUBLIC, DISCLOSURE Sheet 2 of 5 Status: YIZ NE] Ur--Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. _ Room, Area 1 11 DG Day Tank Room 5. Does it appear that the area is free of potentially adverse seismic NO UD N/AOl interactions that could cause flooding or spray in the area?Fire protection line is seismically supported and a pre-action system.Deemed acceptable.

6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?Oil catch basin (can) is on floor but there are no ignition sources in room. Deemed acceptable.

7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

YN NO UO N/A[U YE NEI UL N/AEl 8. Have you looked for and found no other seismic conditions that could Y0 NO UI-adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Evaluated by: Walter Diordievic Date: 4.1/I 2-Scott Luckiesh LI Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS- WITHHOLD FROM. P'UBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY INFORMATION WITHH,-,-LD, FROM PIC,3[-. G DI,, LOSRE Sheet 1 of 6 Status: YE NEI- U[Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. ý _ Room, Area, 11 DG Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

1) Heater on west wall should be chained to something substaintial, not a conduit.2) TH-3 (temperary power pack) should be chained to hook on south wall.2. Does anchorage of equipment in the area appear to be free of significant degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?1) Heating steam fans should be braced. This is an enhancement and not a seismic concern.2) Drain piping with Victaulic couplings deemed acceptable.

The 12" line attached to Turbine Building roof may at worst leak through couplings but there are two drains in room to handle roof drain leakage should it occur.4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e~g., ceiling tiles and lighting)? YO NEI Ur- N/AU YO NEI U[- N/AU YO NEI UEJ- N/AE3 YN NE UD N/AU 1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. ';:' Z ;\IL I Y r"; ",r;v. , lur. v: i I HHULU I-I I'U .LLU =Sheet 2 of 6 Status: Y[ N[- U'-Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. Room, Area' 11 DG Room 5. Does it appear that the area is free of potentially adverse seismic YE NEL UL N/A[interactions that could cause flooding or spray in the area?Fire protection piping is seismically supported and is also pre-action. Discussion on piping is provided on previous page.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?DG fuel reservoir is an integral part of the skid, and not an adverse seismic interaction, 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? See discussion for TH-3 and heater blower on previous page.YO NEI UL N/AE]YZ NL UL N/A-1 8. Have you looked for and found no other seismic conditions that could Y[ NEL UL adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Evaluated by: Walter Dbordievic ANj Date: //'Scott Luckiesh X,//Z Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS. WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure.

ntlY IPFrRMATI-N WITII O ID69 FORM PUYB1I Sheet 1 of 3 Status: Y-- NO UW--Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. Room, Area, 12 DG Day Tank Room Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YE NEI UEI N/AEJ 2. Does anchorage of equipment in the area appear to be free of significant YE NEI UE- N/AEl degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YE NEI UE' N/AE1 YE NEI UE- N/AEl 1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area shouldbe based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY INFORMATION WITHHOLID FROM PUBLIC DIGCLOSURE! Sheet 2 of 3 Status: YE-' NM U[]Area Walk-By Checklist (AWC)Location: Bldg. TO Floor El. ý _ Room, Area' 12 DG Day Tank Room 5. Does it appear that the area is free of potentially adverse seismic YN NEI UD N/AU interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YO NO" U-] N/AU Y[ NO UO N/AU 8. Have you looked for and found no other seismic conditions that could YO NZ UU adversely affect the safety functions of the equipment in the area?FP line is in contact with DO fuel line. See CAP 1345971.Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory ,. , A Date: 0,Y/0 sk &2-Steve Kaas _,3 Z/ Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS1 WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 5 Status: Y[] NO U[']Area Walk-By Checklist (AWC).Location: Bldg. TB FlOor El. ý _ Room, Area, 12 DG Room Instructions for Completing Checklist This-checklist may be used to document the results of the Area Walk7By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

1) Noted: Battery on Lister diesel inspected

& confirmed battery base is screwed in from bottom with at least (2) -1/4" diameter screws.2) Main .FP station has two dead weight supports with no anchorage to floor. Additional support nearby is bolted to floor & captures FP station using 1/2" plate to capture pipe. Is this configuration acceptable considering seismic anchorage?

2. Does anchorage of equipment in the area appear to be free of significant degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?1) Heating steam fans should be braced. This is an enhancement and not a seismic concem.4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YE] NIZ Ur- N/AU YO NEI UI N/AU YO N[W] Ur- N/AU YI NEI U[-1 N/AU Iif the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY INFORMATION WITHHOLDI FROM PUBLIC DIG-ICOURE-Sheet 2 of 5 Status; YL- NZ U[-]Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. ý _ Room, Areai 12 DG Room 5.Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?FP piping branch line by engine control panel noted to be within 1" of HVAC duct. HVAC duct appears to be seismic cat 1 so relative movement of it and FP line movement judged minor in all cases. SWE's judge acceptable. Other FP lines noted within 1" of other sections of HVAC duct also judged acceptable by SWE's.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YO NI] UI- N/AEI YZ N[ U-1 N/A[]YN NEI UDI N/AEl 8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?YN NEI UEl Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lory -4 !a D, Date: _0_ _- ___Steve Kaas -z/t,- ,/ Monticello Nuclear Generating Plant Seismic Walkdown Report SU.INSI WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY INFORMATION WITI I6OLD FROM PUBUC DISCLOSURE Sheet 1 of 8 Status: YE[- NZ Uj--i Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. ý _ Room, Area 1 South Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YO NEI UD N/AO 2. Does anchorage of equipment in the area appear to be free of significant YO NEI UI' N/AU degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?HVAC has 5' free end cantilever from last support and entire HVAC run is supported from cable tray KA432. Is this configuration required to meet seismic 2/1 criteria?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YEI] NI UE] N/AE]YZ NEI UE- N/AE]' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PRGROIVE:TAR INFORMATION WIT-I OLD96 FROM PUBLIC BIGGLO2URE Sheet 2 of 8 Status: YE] NZ UrI]Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. Room, Areal South 5. Does it appear that the area is free of potentially adverse seismic YEI NEI Ur- N/AL]interactions that could cause flooding or spray in the area?Large SW line SW-1 (24" diameter line) -Pipeline was verified as meeting seismic category I requirements, as documented in calculation 08-182.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?YZ NEl UI- N/All 7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YN NO] U-] N/AL]8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?YN NEI UL]Comments (Additional pages may be added as necessary) Housekeeping: Choker was found on pipe above TB-935 scaffolding. Evaluated by: Bruce M. Lory / -t -4 n .Date: ORA Steve Kaas Z-P -7/ Monticello Nuclear Generating Plant Seismic Walkdown Report I1 IKICI l 7 I DI IDI I0 Ift' 'Il f"Cn ID -The remaining pages are withheld from public disclosure. PROPRIETARY INF-oGMATIGN WITH, 1OLD t FRoM WuBLc DISCLOSURE Sheet I of 27 Status: YE] NO Ur]Area. Walk-By Checklist (AWC)Location: Bldg. TB Floor El._ Room, Area' Upper4kV Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? YO NEI UE] N/AD 2. Does anchorage of equipment in the area appear to befree of significant YO] NEI UI1 N/AU degfaded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?1) Rod for conduit support for conduits B933A & 2 other conduits is in contact with HVAC duct. Duct is moving just due to air flow & causes rod to be moved with it. Rod appears to be bent, possibly because anchor point for rod is inside footprint of HVAC duct.2)HVAC duct above 4kV switchgear door has 4 straps holding up 30" x 18" duct section of 10' in length. Straps have one screw connecting it to duct.4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

1) Lighting is hung on a rod on the rear side of Bus 16. Itis laterally supported to prevent sway by one wire tied of grating. SWEs are concerned that there are not enough lateral supports.

Light is 21'long.2)Fire extinguisher by 4kV door has small lip holding it to wall. Need to check vertical seismic acceleration to see if uplift can occur. Fire extinguisher is 34" away from 16 Bus.YO NO UU- N/AU YI- NO UU N/AUl' If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described, This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DISCLOSURE Sheet 2 of 27 Status: YE-] NZ U[Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. Room, Area' Upper 4kV 5. Does it appear that the area is free of potentially adverse seismic NEI UI- N/AD interactions that could cause flooding or spray in the area?No FP lines or other lines containing water were seen.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?Noted: Hydrogen & oil line running vertically in back of room. Lines are well supported and go into concrete.7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

1) SWE's noted good tie off of 1/2 ton crane H-20B 2) Ladder in back of LC-102 is on sloping hook. Hooks do not have much slope.YM NEI UI-1 N/AUl YUI NO U-1 N/AU 8. Have you looked for and found no other seismic conditions that could YU NO UU adversely affect the safety functions of the equipment in the area?1) 12 DG Potential Transformer (G-3B/Pot) is above 4kV cubicle 152-602. Is this accounted for in anchorage calcPT appears to be bolted to top of cubicle with angles.2) Bus-12 Pot (although it is NSR) is on top of cubicle 152-201 SWEs cannot verify it is. anchored to top of cubicle. Could Bus-12 Pot be seismic II over I concern by impacting Bus 14 which is connected to Bus 16.Comments (Additional pages may be added as necessary)

Evaluated by: Bruce M. Lor. Date: 01?_/___-.. Steve Kaas Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI WITHHOLD FROM PUB LIC DISCLOSURE The remaining pages are withheld from public disclosure. PROPRIETARY INFORMATION WITHHOLD FROM PUBLIC DISCLOSURE Sheet 1 of 7 Status: Y[ NF- UL-Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El.. Room, Area 1 11 DG Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible withoutnecessarily opening cabinets)? YZ NEI ULI N/AD]2. Does anchorage of equipment in the area appear to be free of significant YZ NEil UI1 N/AL]degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?Drain line from roof is cast-iron but well supported so it won't fail or leak. Steam line will not fail but an enhancement would be to brace heater fan. If leakage were to occur there is a floor drain to collect water.4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YN NEI UL1 N/AL]YE NE] UE] N/AL]' If the room in which the SWEL item is located is verylarge (e.g.,Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., onthe order of about 35 feet from the SWEL item. PROPRIE=TARY INFO9RMATION WITHHOLDGI= FROMA PUBLIC DISCLOSURE= Sheet 2 of 7 Status: YZ NE] UED Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. ý _ Room, Area 1 11 DG 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?See discussion forroof drain line on previous page.6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YE NEI UL N/AU YZ NEI UU N/AD YE NEI Ur- N/AU 8. Have you looked for and found no other seismic conditions that could YZ NEI Uil adversely affect the safety functions of the equipment in the area?Comments (Additional pages may be added as necessary) Evaluated by: Walter Diordievic 1-" /*Tate: Scott Luckiesh " Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE The remaining pages are withheld from public disclosure. Sheet 1 of 3 Status: Y[ NEI U-]Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. Room, Area 1 12 DG Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results ofjudgments and findings.Additional space is provided at the end of this checklist for documenting other comments.1. Does anchorage of equipment in the area appear to be free of potentially adverse seismic conditions (if visible without necessarily opening cabinets)? Room Heater noted but adequately supported by (2) -1/2" diameter threaded rods.YE NE UE N/AE 2. Does anchorage of equipment in the area appear to be free of significant YD NEI UI- N/A-degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and HVAC ducting appear to be free of potentially adverse seismic conditions (e.g., condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?4. Does it appear that the area is free of potentially adverse seismic spatial interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

YE NEI U" N/AE YM NEI U[-E N/AU I If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described. This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item. PROPRIETARY IINFOR"M'At'qTItON~ W^ITU~"I HOLD Fr'O"-M, PU1iC) 'O1111'-Sheet 2 of 3 Status: Y[Z N-] U--I Area Walk-By Checklist (AWC)Location: Bldg. TB Floor El. ý _ Room, Area, 12 DG 5. Does it appear that the area is free of potentially adverse seismic interactions that could cause flooding or spray in the area?6. Does it appear that the area is free of potentially adverse seismic interactions that could cause a fire in the area?7. Does it appear that the area is free of potentially adverse seismic interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)? YE NEI U[L N/AU YO NEI U[-1 N/AEl YN NEI Ur N/AU 8. Have you looked for and found no other seismic conditions that could adversely affect the safety functions of the equipment in the area?YN NEIUE Comments (Additional pages may be added as necessary) Evaluated by: Bruce M. Lorv a Date: 6 O,/, Z..Steve Kaas - Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI -WITHHOLD FROM PUBLIC DISCLOSURE Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI Withheld from Public D;sc'osurc D Plan for Future Seismic Walkdown of Inaccessible Equipment This section discusses the plan for future seismic walkdowns to complete the inaccessible items from SWEL I which were deferred either for drywell entry or cabinet internal inspection. Table D-1 summarizes the reasons each item is inaccessible during normal plant operation. This table and the following AWCs contain Sensitive Unclassified Non-Safeguards Information (SUNSI), of which the loss, issue, modification, or unauthorized access can reasonably be foreseen to harm the commercial interests of NSPM. Pages which contain proprietary information have been marked.As shown in the table below, 22 items have been deferred until a refueling outage or an appropriate time when the equipment is accessible. Inaccessibility of this equipment was either based on the location of the equipment (environment that posed personnel safety concerns while the unit is operating), or due to the timing of the issuance of the clarification on internal electrical cabinet inspections and the electrical safety hazards posed while the equipment is energized. All items will be walked down by the end of Refueling Outage R26 in Spring 2013. An updated submittal report will be provided 60 days following the end of RFO R26.Table D-1: Monticello Deferred Equipment List Equipment Area Walk-By Area lk-Description By Reason'for Inaccessibility Tag

• Checklist Copeed,..Completed' 152-505 4KV TO P-208A 11 TB-L4KV Yes De-energization Required Core Spray Pump AO-2-80A INBOARD MSIV RX-DRYWELL No Drywell Entry Required BUS 15 4160 SWITCHGEAR TB-L4KV Yes De-energization Required C-253D DIV II LOLO SET PAB-CR Yes Internal Cabinet Inspection BYPASS PANEL Required C-91 11 DIESEL GEN TB-il DG-RM Yes De-energization Required ELECTRICAL Appendix D -Plan for Future Seismic Walkdown of Inaccessible Equipment D-1 Monticello Nuclear Generating Plant Seismic Walkdown Reportll lmlf=. II I II II dP StuN1 withhold from Public wisclosure Table D-1: Monticello Deferred Equipment Listr~~~~~ae .....W":K yalk-' .. .. ......Equipment Descripioo .Area Walk-By Ara W Tag Checklist By Reason for Inaccessibility

.. ... ... .Completed -...C-93 11 DIESEL GEN TB-i 1 DG-RM Yes De-energization Required CONTROL DIV I 125VDC D11 DISTRIBUTION PAB-11BATT Yes De-energization Required CENTER 125VDC SWING Internal Cabinet Inspection D40 CHARGER FOR #11 PAB-1 3BATT Yes Required AND #12 BATTERIES SWING CHARGER Internal Cabinet Inspection D54 D3A, D3B 13 PAB-13BATT Yes Required BATTERY CHARGER, SWING CHARGERB (16)G EInternal Cabinet Inspection D90 D6A, D613 (16) EFT Yes Required BATTERY#11 DG NEUTRAL G31 GROUNDING TB-11DG-RM Yes De-energization Required CABINET 480V AC MOTOR MCC-133B CONTROL CENTER TB-SOUTH Yes De-energization Required 133B MCC-134 480 V MCC (B34) EFT-N-DIV1 Yes Internal Cabinet Inspection Required DIV 2 (HPCI) 250V DC MCC-312 MOTOR CONTROL RX-HPCI Yes De-energization Required CENTER 312 DIV 1 250V DC Internal Cabinet Inspection MCC-313 MOTOR CONTROL RX-MG SET Yes Required CENTER 313 MAIN STEAM LINE MO-2374 DRAIN -OUTBOARD RX-STEAMCHASE No High Radiation during Operation 11 EDG AIR CMPSR 1 N3346A (K-8A) LOCAL TB-11DG-RM Yes Internal Cabinet Inspection DISCONNECT Required SWITCH Appendix D -Plan for Future Seismic Walkdown of Inaccessible Equipment D-2 Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! Withhold from Public ..osurn Table D-1: Monticello Deferred Equipment List ,Equipment Area Walk-By Area Walk-By Reason for Inaccessibility Tag ectCompleted N3347 MOTOR STARTER RX-EAST Yes Internal Cabinet Inspection FOR K-10A Required 11 EDG AIR CMPSR 2 Internal Cabinet Inspection N4301A (K-8B) LOCAL TB-11DG-RM Yes DISCONNECT SWITCH Required Internal Cabinet Inspection P-73A 480V POWER PANEL RX-MG SET Yes required Required RV-2-71A A SRV RX-DRYWELL No Drywell Entry Required Y81 DIV 2 120VAC CLASS EFT Yes Internal Cabinet Inspection 1EINVERTER Required Appendix D -Plan for Future Seismic Walkdown of Inaccessible Equipment D-3 Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI Information Withhold from Public DI*-Isur-E Peer Review Report This appendix includes the Peer Review Team's report, including the signed Peer Review Checklist for the SWEL from Appendix E, Checklist for Peer Review of SSC Selection, of Reference 1.Table E-1 of this appendix includes information on the location of SWEL components, which is considered SUNSI, of which the loss, issue, modification, or unauthorized access can reasonably be foreseen to harm the safe operation of the nuclear plant.Pages which contain proprietary SUNSI information have been marked, and the sensitive information has been redacted.Appendix E -Peer Review Report F-1 Peer Review Report for Near Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdown Inspection of Monticello Nuclear Generating Plant November 15, 2012 Peer Reviewers:Kindred (Team ]ýeaoder)Date/,- A/f- 7 O/Z-Date 1 Introduction Overview This report documents the independent peer review for the Near Term Task Force (NTTF) Recommendation 2.3 Seismic at the Monticello Nuclear generating Plant.The peer review addresses the following activities: Review .f the selootein of the StrUc.... , Y.tem.. , and corationents, (SSCs)that are included in the Seismic Walkdown Equipment List (SWEL).* Observation of the seismic walkdowns on August 1, 2012 and adherence to the Seismic Walkdown Guidance (SWG)l.* Review of a sample of the checklists prepared for the Seismic Walkdowns &Walk-Bys.* Review of any licensing basis evaluations. o Review of the decisions for entering the potentially adverse conditions into the plant's Corrective Action Plan (CAP).o Review of the final submittal report The peer reviewers are Jason Kindred and Dennis Zercher, both Xcel Energy employees. Jason Kindred is designated as the Peer Review Team Leader.Neither of these engineers is involved in the seismic walkdown inspection process so that they can maintain their independence from the project. Dennis Zercher is an degreed structural engineer, has over twenty five years of nuclear seismic experience and has completed the SQUG Walkdown Screening and Seismic Evaluation Training course as a Seismic Capability Engineer. Jason Kindred is degreed mechanical engineer with over twenty years of nuclear engineering experience and is a licensed Senior Reactor Operator.The SWEL development was performed by Robert Walstrom. The Peer Re£,ew team was involved in the review of SWEL I and SWEL 2. The Peer Review ensured the lists covered various systems in the plant and all five safety functions listed in Section 3 of EPRI Technical Report 1025286. All items identified by the Peer Review team were corrected prior to commencing the in-plant walkdowns. None of the issues identified were significant enough to warrant entry into the corrective action process. The completed SWEL Peer 1 EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012. Review Checklist is found in Attachment

1. The discussion for the SWEL development peer review is found in Section 2.The peer review of the seismic walkdown inspection started on August 24, 2012 with a peer check of the actual walkdowns.

Dennis Zercher joined the walkdown teams for a portion of the day's planned walkdowns to observe the conduct of walkdowns and adherence to the SWG. There were two walkdown teams.Interviews were conducted by Dennis Zercher with the various members of both the SWE inspection teams to ascertain procedural compliance with the SWG.The discussion of the sample Seismic Walkdown Checklists (SWCs) and Area Walkdown Checklists (AWCs) is provided in Section 3.No issues were identified which challenged the current licensing basis.

2. Peer Review -Selection of SSCs Purpose The purpose of this section is to describe the process to perform the peer review of the selected structures, systems, and components, (SSCs) that were included in the Seismic Walkdown Equipment List (SWEL).Selection of SSCs The guidance in EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012, Section 3: Selection of SSCs was used as the basis for this review.This peer review was based on interviews with the following individual who was directly responsible for development of the SWEL 1:* Mr. Robert Walstom, Retired SRO/Shift Manager This peer review utilized the checklist shown in the SWG, Appendix F: Checklist for Peer Review of SSC Selection.

For SWEL I development, the following actions were completed in the peer review process:* Verification that the SSCs selected represented a diverse sample of the equipment required to perform the following five safety functions: o Reactor Reactivity Control (RRC)o Reactor Coolant Pressure Control (RCPC)o Reactor Coolant Inventory Control (RCIC)o Decay Heat Removal (DHR)o Containment Function (CF)o Verification that the SSCs selected include an appropriate representation of items having the following sample selection attributes: o Various types of systems o Major new and replacement equipment o Various types of equipment o Various environments o Equipment enhanced based on the findings of the IPEEE o Risk insight consideration For SWEL 2 development, the Peer Review process verified that appropriate justification was documented for spent fuel pool related items that were not added to the SWEL 2. Peer Review Findings -Selection of SSCs This peer review found that the process for selecting SSCs that were added to the SWEL was consistent with the process outlined in the SWG Section 3: Selection of SSCs.* The SSCs selected represented a diverse sample of equipment required to perform the five safety functions* The SSCs selected included a sample of items that represents each of the desired attributes/considerations. The peer review checklist is attached to this document with additional comments that the Peer Review team provided back to the SWEL developer. All of these comments were verified by the Peer Review team to have been incorporated into the SWEL prior to the commencement of in-plant walkdowns. None of the issues identified were significant enough to warrant entry into the Corrective Action Process.Resolution of Peer Review Comments -Selection of SSCs All comments requiring resolution were incorporated prior to completion of this in-plant walkdowns. None of the issues identified were significant enough to warrant entry into the Corrective Action Process.Conclusion of Peer Review -Selection of SSCs This peer review concludes that the process for selecting SSCs to be included on the seismic walkdown equipment list appropriately followed the process outlined in the SWG, Section 3: Selection of SSCs. It is further concluded that the SWEL sufficiently represents a broad population of plant Seismic Category 1 equipment and systems to meet the objectives of the NRC 50.54(f) Letter.

3. Review of Sample Seismic Walkdown & Area Walk-Bys Checklist Overview An interview was conducted by Dennis Zercher with the SWE inspection teams in accordance with the SWG requirements.

The interviews were conducted during during field walk downs for both an equipment walk down and an area walk down. The interview with Bruce Lori and Steve Kaas of one SWE walkdown inspection team occurred on July 26, 2012. The interview with Walter Djordjevic and Scott Luckiesh of the other SWE inspection team occurred on August 1, 2012.A peer review of the sample SWCs and AWCs was performed on August 24, 2012.Peer Review Findings -Seismic and Area Walkdown Checklists The sample Checklists that were reviewed includes both Seismic Walkdown Checklists and Area Walkdown Checklists. Table 3-1 lists the SWC and AWC samples that were reviewed, which represent approximately 18% of the total Checklists. Table 3-1: Table of SWC and AWC Samnles from Seismic Walkdown Inspection Equipment Equipment Walkdown 50% Observations Identification Class (GIP) Item Anchor Verif.(Y/N)D-31 14- Div 1 Y No concerns Distribution 125/250 Panels VDC Distribution Panel D-10 16 -Battery 125 VDC Y No concerns Chargers Charger for and Inverters

1. 11 Battery CRD HCU W 18- CRD Y CST line in contact with Instrument Hydraulic column -existing CAP on Racks Control 129196 addresses Units West concern Side C-39 20- HPCI Relay Y No concerns Instrument Panel and Control Panels and Cabinets C-253A 20 -SRV Panel Y No concerns Instrument and Control Panels and D m 4 #Cabinets AO-4539 07 -Fluid- Hard Pipe N Electrical tape used t Operated Vent secure excess cable -Valves Inboard CAP 1346939 addresses Isolation this concern Valve MCC-313 01 -Motor Div 1 250 Y No concerns Control VDC Motor Centers Control Center 313 LT-2-3-72C 18 -LoLo N No concerns Instruments Reactor on Racks Level ECCS Initiation K-10A 12 -Air RHRSW Y No concerns Compressors Aux Air Compressor G-3B 17 -Engine- 12 Y No concerns Generators Emergency Diesel.Generator D-3A 15- Div I Y Excessive projection of Batteries on 125/250 anchor bolt no addressed Racks VDC -anchorage judged Battery adequate, see appendix F.V-AC-5 10 -Air RHR A Air Y No concerns Handlers Handler P-11A 06 -Vertical 11 ESW Y No concerns Pumps (EDG-ESW)Pump MO-2063 08 -Motor- HPCI CST N No concerns Operated Suction and valve Solenoid-Operated Valves Y71 16 -Battery DIV 1 Y No concerns Chargers 120VDC and Inverters Class IE Inverter Area Walkdown Observations Description Intake Structure No concerns Reactor Bldg -HPCI Bottle cart next to MCC -CAP 1346030 written to Room address concern Reactor Bldg= -RCIC Reddish deposit on anchor bolts- CAP 1346642 Room written to address concern Reactor Bldg -SBLC Potential seismic interaction from scaffold -CAP area 1347002 written to address concern TB -11 DG Day No concerns Room TB -12 DG Room No concerns Reactor Bldg M -B No concerns RHR Room TB -Lower 4KV Potential interaction hazards from hoist on load center and fire extinguisher on electrical cubicle -CAP 1349068 written to address concern.Nonessential transformer missing bolts -existing work order addressing this condition.

PAB -13 Battery Loose nut on duct strap -work request was initiated Room to correct.Evaluation of Findings -Seismic and Area Walkdown Checklists There were no findings that challenged the licensing basis. Tables 52' and 5-3 of the Seismic Walkdown Report (final submittal report) provide the lists of the issues encountered for the equipment seismic walkdowns and area walk-bys.There were very few seismic housekeeping instances found throughout the plant and it can be concluded that MNGP implements their seismic housekeeping program consistently. The Seismic Walkdown Checklists documented the details of the identified issues, the action taken and the conclusion of the SWE inspectors. The Peer Review team verified that all technical issues identified that required evaluation or resolution were entered into the Corrective Action Program.Some minor administrative issues were identified in the review and provided back to the team. These issues did not warrant entry into the CAP.The peer reviewers consider the judgments made by the SWEs to be appropriate and in concurrence with the SWG.Resolution of Peer Review Comments -Seismic and Area Walkdown Checklists The Peer Review team verified that all technical issues requiring evaluation or resolution were entered into the Corrective Action Program.Conclusion of Peer Review -Seismic and Area Walkdown Checklists This peer review concluded that Seismic and Area Walkdown checklists properly documented and dispositioned the issues identified by the engineers performing the walkdowns.

4. Review of Licensing basis Assessments Section 6 of the final submittal report was reviewed to assess Seismic Licensing Basis Evaluations.

The report documents that all potentially adverse seismic conditions that were identified during plant walkdowns were entered into the corrective action process. Therefore, no Licensing Basis Evaluations were needed.The Peer Review Team determined that while this was a conservative method to complete this portion of the evaluation, it did not violate the EPRI guidance document.Tables 5-2 and 5-3 of the Seismic Walkdown Report were reviewed by the Peer Team, and it was concluded that the completed and planned corrective actions for the issues identified were appropriate to address the conditions identified.

5. Review Final Submittal Report and Sign-Off The entire final submittal report has been reviewed by Dennis Zercher and Jason Kindred and found to meet the requirements of the EPRI 1025286 -Seismic Walkdown Guidance.The Peer Review concurs that the objectives and requirements of Enclosure 3 to 10CFR50.54(f) letter 2 are met.2 NRC Letter to All Power Reactor Licensees et al., "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3, of the Near-Term Task. Force Review of Insights from the Fukushima Dai-ichi Accident," Enclosure 3, "Recommendation 2.3: Seismic," dated March 12, 2012 Attachment 1: Peer Review Checklist for SWEL Sheet I of 5 Peer Review Checklist for SWEL #1 Instructions for Completing Checklist This, peer review checklist may be used to document the review of the Seismic Walkdown Equipment List (SWEL) in accordance with Section 6 Peer Review. The space below each question in this checklist should be used to describe any findings identified during the peer review process and how the SWEL may have changed to address those findings.

Additional space is provided at the end of this checklist for documenting other comments.1. Were the five safety functions adequately represented in the SWEL I sclection? Y9 NEI The Peer Review Team reviewed the list of selected equipment to validate the assignment of the correct safety functions to the components. The Peer Review Team agrees that the four safety functions specified in the EPRI guidance as well as the containment function are well represented. The following specific comments are provided from'this review: " Item #38 -The Peer Review Team does not agree that AV-4024(#1 3 ESW pump disch air vent valve) supports the Reactivity Control Safety Function (ESW not needed for Scram or SBLC)." Item #38, 40, 45, 93, 95, 147, 152, 182, 183, 184, 204, 205, 208, 217, 219, 273, 276, 283, 284, 296, 451, 452, 474, 477, 493, 494, 495 -The Peer Review Team does not agree that this equipment supports the Reactor Pressure Control Safety Function. Table B-2 from the EPRI guidance document lists SRV's, ADS, and MSIV's as supporting this function. AC power is not really required for these components to perform their function, The exception may be ADS, as it needs as signal showing that RHR or CS pumps are running, but this is a remote or distant relationship to the depressurization function.* Item #227 -Since MCC-313 provides power to the Main Steam Line Drain Outboard Isolation valve, it could be considered to support the Reactor Pressure Control Safety Function (similar to MSIV).2, Does SWEL I include an appropriate representation of items having the following sample selection attributes:

a. Various types of systems? YN NE The Peer Review Team reviewed the list of selected equipment to validate that a sufficient sampling of plant systems related to the safety functions was represented.

The list below shows the count of components In each of MNGP's systems, The Peer Review Team concluded that the a sufficient sampling of the various plant systems was represented. Sheet 2 of 5 Peer Review Checklist for SWEL #1 125 125 VDC 3 250 250 VDC 8 480 480 V Station Auxiliary 5 24V 24 VDC 41(V 4 KV Station Auxiliary AIR Instrument & Service Air AN2 Alternate N2 I APR Auto Pressure Relief 4 ASD Alternate Shutdown 1 CRD Control Rod Drive Mechanism 2 CRH Control Rod Drive Hydraulics System I CSP Core Spray Cooling System 3 CST Condensate Storage DAC Drywell Atmosphere Cooling DGN Diesel Generators 14 DOL Diesel Oil Storage 3 EFT CRV -EFT 5 ESW EDG Emergency Service Water 1 FSW EFT Emergency Service Water 2 HOA H2-02 Control Analyzing HPC High Pressure Coolant Injection 6 HTV Heating & Ventilation 5 LRW Liquid Radwaste 1 MST Main Steam NIP Power Range Monitors NIS Start Up Range Monitors PCS Main Steam Pressure Control PCT Primary Containment 4 PPS Plant Protection 2 RCI Reactor Core Isolallon Cooling System 3 REC Reactor Recirculatlon System 1 RHR Residual Heat Removal 9 RLC Reactor Level Control RMC Reactor Manual Control RPI Rod Position Information System RPP Reactor Protection System Power Supply RPV Reactor & Vessel Assembly 3 RSW RHR Service Water 5 RWC Reactor Water Cleanup SCT Secondary Containment SEL Security Diesel SLC Standby Liquid Control System 2 SLG Security Facility Lighting & Grounding UAC Instrument AC & Uninterruptible AC 2 b. Major new and replacement equipment? The Peer Review Team validated that the list of selected equipment contained a sufficient sampling of plant equipment that has been replaced in recent years. This Included large components such as an RHR and an RHRSW Pump.YM NEI Sheet 3 of 5 Peer Review Checklist for SWEL #1 c. Various types of equipment? Tie Peer Review Team reviewed the list of selected equipment against Appendix B (Classes of Equipment) to the EPRI Seismic Wall(down Guidance. The following is a summary of the sampling of equipment classified on the current list.0 Other 0 1 Motor Control Centers and Wall-Mounted Contactors 4 2 Low Voltage Swltchgear and Breaker Panels 1 3 Medium Voltage, Metal-Clad Swltchgear 2 4 Transformers 3 5 Horizontal Pumps 5 6 Vertical Pumps 6 7 PneumatIc Operated Valves. 9 8 Motor-Operated and Solenoid Operated Valves 10 9 Fans 2 10 Air Handlers 8 11 Chillers 0 12 Air Compressors 3 13 Motor Generators 0 14 Distribution Panels and Automallc Transfer Switches 4 15 Battery Racks 3 16 Battery Chargers and Inverters 4 17 Engine Generators 2 18 Instrument Racks 11 19 Temperature Sensors 0 20 Instrument and Control Panels 13 21 Tanks and Heat Exchangers 8 The Peer Review Team noted the following issues that require follow up:* The list did not contain any equipment from #11 (Chillers), #13 (Motor-Generators), or #19 (Temperature Sensors).o Item # 487 on the MNGP SWEL (V-EAC-14A) Is classified as an air-handler, when it may be more appropriate to classify it as a chiller.d. Various environments? The Peer Review Team reviewed the list of selected equipment against criteria for selection listed In the EPRI Seismic Wall(down Guidance. The team determined that the although a reasonable effort was made to select equipment in different locations throughout the plant, the following concerns were noted and-need to be addressed: o The MNGP SWEL lists locations for equipment, but does not make any effort to describe the environmental conditions at these locations. This could create challenges for personnel not familiar with MNGP layout when reviewing the SWEL. It is recommended YO NEl YO NEI Sheet 4 of 5 Peer Review Checklist for SWEL #1 that the SWEL Team develop some environmental descriptions for the areas listed. (Example Warm/Dry, Cool/Dry, Warm/Damp, Cool/Damp, etc.)There is only one item on the list In the Drywell and no items in the Steam Chase. These would be the most realistic "Harsh" environments for equipment at MNGP.o Item #73 on the MNGP SWEL lists its location as "ALL," e. Equipment enhanced based on the findings of the IPEEE (or equivalent) program? YO NEI The Peer Review Team noted that five items on the MNGP SWEL were classified as equipment enhanced as a result of the IPEEE program. This meets the requirement from the EPRI guidance to select "some".equipment from this program.f. Were risk insights considered in the development of SWEL 1 ? YO NEI The Peer Review Team reviewed the list of the top 20 risk significant equipment items from the MNGP PRA Engineer. 20 of the 98 equipment Items listed on the MNGP SWEL, have ties to the top 20 risk significant systems for PRA. The team felt this was a strong sample and was well documented.

3. For SWEL 2: SWEL 2 REVIEW NOT DOCUME]NTED ON THIS CIJECICLIST

a. Were spent fuel pool related items considered, and if applicable included in YEI NEI SWEL 2?b. Was an appropriate justification documented for spent ftiel pool related items not YE NE-included in SWEL2?

Sheet 5 of 5 Peer Review Checklist for SWEL #1 4. Provide any other comments related to the peer review of the SWELs.None 5. Have all peer review comments been adequately addressed in the final SWEL? YM NEI Peer Reviewer #1: Date: 2-Peer Reviewer #2 : Date: ________________/__ Monticello Nuclear Generating Plant Seismic Walkdown Report F Disposition of Seismic Walkdown Observations This appendix includes a discussion of how observations noted in the Seismic Walkdown Checklists (SWC) and Area Walk-By Checklists (AWC) were dispositioned. All observations noted in the SWCs or AWCs were reviewed by site engineering to determine whether or not the issues could be readily shown to meet the seismic licensing basis. If it was clear that the observations noted by the SWEs were not seismic concerns, then the observation was dispositioned as needing no further actions.However, if site engineering could not readily determine if the condition met the seismic licensing basis, then the observations were entered into the CAP. Table F-1 and Table F-2, below, lists the observations identified in the SWCs and AWCs, and how each observation was dispositioned. Only those observations which required additional review by site engineering are included in these tables. Comments or recommended enhancements are not included. If an observation was entered into the CAP, or into the work management system, then a status of the action requested is provided.The AWCs in this appendix include information on the location of SWEL components, which is considered SUNSI, of which the loss, issue, modification, or unauthorized access can reasonably be foreseen to harm the safe operation of the nuclear plant.Pages which contain proprietary information have been marked, and the sensitive information has been redacted.Table F-I: Disposition of SWC Observations Walkdown Question Observation Disposition Checklist No.AO-4539 11 SWEs noted 2G4007 conduit is CAP 1346939 was initiated to evaluate this used as anchor point to tie observation. This condition was determined not together other power cables to be an adverse condition, however, WR 83827 using tie wraps. Also noted was written to re-support the cable for AO-4539.electrical tape used to hold up power cables at connection point on valve.C-03 11 Door connecting front and back Due to the large differences in stiffness and panels is free to swing. Door mass between the panels and door there will be could impact C-03 in seismic very little vibration to any relays so there will not event and is a seismic be a concern with relay chatter. Therefore, it is interaction issue. not a seismic concern.Appendix F -Disposition of Seismic Walkdown Observations F-1 Monticello Nuclear Generating Plant Seismic Walkdown Report Table F-I: Disposition of SWC Observations Walkdown Question Observation Disposition Checklist No...C-122 5 Pictures were taken of each leg MNGP calculations validated the 3/8" bolt starting with the south end. Floor currently installed rack configuration meets bolts are combination of 3/8" and design load criteria. Computations used pinned 1/2" bolts. Anchorage does not bases for the rack, therefore no tension is match calculation. Also one bolt expected on the anchors, only shear load.appears not fully threaded. Shear load is resisted by bearing of the anchor rods on the concrete floor, therefore 3/4 thread engagement does not affect anchorage shear capacity. Therefore, it is not a seismic concern.CRD HCU 8 CST line is in contact w/ CRD This condition was identified in CAP 1259196.W structural column. WO 62289 This is being addressed in the work order was initiated as part of CAP process under WR 62289 and WO 417791. It is 1259196 to address rubbing. not an adverse seismic concern.CRD HCU Comment Tie-Wrap around anchors for Tie-wrap was removed. There is no seismic W s CRD 38-35 and CRD 50-31 concern.should be removed.D3A 2 Center stanchion of west (wall) Anchorage was judged adequate by SEWs.rack has excessive projection There is no seismic concern.and 2nd stanchion from north has excessive projection. D31 5 Plant drawing inaccurate with CAP 1350165 and CAP 1346890 were initiated installation of anchors. SEWS to document this observation. The anchorage evaluation on anchors uses configuration was determined to be acceptable correct "as found" configuration. as found. The plant drawings are being revised to match the anchorage configuration. D70 11 This is a potential for seismically The equipment in the room is for the Division II induced spray due to 3/4" 250VDC batteries. This equipment is not relied copper water line noted in area on for an internal flood event, therefore a break walkby checklist EFT932. of the 3/4" line will not prevent a safe shut down of the plant. It is not a seismic concern.MCC-134 7 3" diameter line entering room The piping is seismically supported by rigid from south wall has just a dead seismic supports. The threaded connections will weight support near south wall not fail. It is not a seismic concern.and then runs horizontally over to MCC. This line appears to contain cast iron threaded fittings. Concern is if this small line structurally fails in seismic event, it could impact MCC.Appendix F -Disposition of Seismic Walkdown Observations F-2 Monticello Nuclear Generating Plant Seismic Walkdown Report Table F-1: Disposition of SWC Observations Walkdown: Question Observation Disposition Checklist No.MCC-134 7 4" diameter line from south wall The displacement of the Victaulic coupling will is connected at wall with be dominated by the displacement of the pipe.structural steel anchored to CIP The support differential displacement will concrete. It has victaulic contribute an insignificant amount. Therefore, coupling midspan and is the pipe supports on the concrete wall and the anchored above MCC with U- other supports on the building steel will have an boltI-beam support. Concern is insignificant effect on the pipe and the Victaulic differential displacement of coupling in the pipe. It is not a seismic concern.south steel beam versus north CIP wall.P-203A 7 Tall scaffold is constructed CAP 1347002 was initiated to evaluate this above the pump. Verify the observation. The engineer responsible for seismic assessment of this scaffolding evaluations reviewed the scaffold scaffold. and determined it was adequately braced to prevent sliding and overturning during a seismic event.P-209 5 There are eight 1" CIP anchor CAP 1346272 was initiated to evaluate this bolts per NX-8292-43 while the observation. The anchorage configuration was walkdown only found six 1" CIP determined to be acceptable as found. The anchor bolts. plant drawings are being revised to match the anchorage configuration. P-88A 3 The anchor bolts are heavily Per plant documentation, the anchors have corroded. adequate margin in that the amount of corrosion on the anchor bolts will not affect the seismic qualification of the pump. It is not a seismic concern.T-200 5 There is a discrepancy between CAP 1347243 was initiated to evaluate this Drawing NX7879-8-1 and what observation. The anchorage configuration was is installed in the plant. determined to be acceptable as found. The plant drawings are being revised to match the anchorage configuration. T-200 10 Verify the seismic assessment CAP 1347002 was initiated to evaluate this for the scaffold near tank. observation. The engineer responsible for scaffolding evaluations reviewed the scaffold and determined it was adequately braced to prevent sliding and overturning during a seismic event.V-SF-9 5 Drawing NX-9290-3 anchor bolt CAP 1345975 was initiated to evaluate this configuration does not match observation. As documented in the SEWS, field. Bolt pattern does match there is no seismic concern, however, the 1995 SEWS. drawing will be updated to reflect field conditions. Appendix F -Disposition of Seismic Walkdown Observations F-3 Monticello Nuclear Generating Plant Seismic Walkdown Report Table F-I: Disposition of SWC Observations Walkdown Question Observation Disposition" Checklist No.Y71 8 3" or 4" diameter line has The displacement of the Victaulic coupling will victaulic couplings. It is be dominated by the displacement of the pipe.connected to north wall using The support differential displacement will structural steel and is connected contribute an insignificant amount. Therefore, to south wall with a steel beam. the pipe supports on the concrete wall and the Concern is differential other supports on the building steel will have an displacement under seismic insignificant effect on the pipe and the Victaulic loading could pull couplings coupling in the pipe. It is not a seismic concern.apart.Appendix F -Disposition of Seismic Walkdown Observations F-4 Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! Withhold from Public DiscGOsUre Table F-2: Disposition of AWC Observations Area Walkby Question Checkls No. Observation Disposition Checklist No.HVAC duct protrudes in front of MCC-144. Both MCC-144 and the duct are rigidly supported. At EFT 3 Unistrut supporting the duct is within 3/8" from maximum SSE, there will be minimal displacement of the front of MCC. duct and MCC-144. Therefore, it is not a seismic concern.Drywall in corner -does it meet seismic Il/I The drywall construction was shown in plant documentation to be able to withstand a seismic event EFT 4criteria? This is next to the 70 battery and not affect any class I equipment. Therefore, it is not charger. a seismic concern.3/4" copper line identified with a two support The equipment in the room is for the Division II 250VDC rod support about 8' apart. Soldered union 3'from one support. Is this line designed for batteries. This equipment is not relied on for an internal EFTseism onegory I s this line flood event, therefore a break of the 3/4" line will not seismic category I/l/, and if not, does this line prevent a safe shut down of the plant. It is not a seismic present a spray problem on class I equipment concern.if it ruptures?3/4" diameter copper line with soldered connection. Line appears supported in horizontal direction but not vertically. Hand Failure of the copper line may cause spray onto V-ERF-valve WDW 60 one elbow within 1/16" of 14A. However, V-ERF-14A is not required for safe conduit. This elbow might contact the conduit shutdown of the plant and is not required to be operable during a seismic event, breaking a solder joint for an internal flooding event. It is not a seismic concern.and causing spray of safety-related equipment. Fire station contains victaulic couplings. Station is bolted to wall. FP line runs up to roof of this floor and into the floor. No sign of lateral bracing. Three victaulic couplings are EFT -Div 1 5 spaced closely together. Is this line adequate This line was determined to be adequately supported as for seismic loads? Line is charged with water. part of CAP 1346922. There is no seismic concern.Line is also in contact with conduit N43158 and in contact with HVAC duct support.(SWEs could not see lateral support above for FP line).3" vertical pipe or conduit of unknown material The purpose/function of the stand pipe is a vent line from has a two-bolt pipe coupling, runs floor to the battery room (1st floor) to the roof. Failure of the pipe EFT -Div 1 5 ceiling. It has two wall supports. The line cuts is not a concern because the pipe is adeqvately 1" into insulation on ESW line. Is this line supported between the floor and the ceiling, It is not a adequate for seismic Il/1? See penetration F2- seismic concern.3915.Appendix F -Disposition of Seismic Walkdown Observations F-5 Monticello Nuclear Generating Plant Seismic Walkdown Report Am li BArn buriall VV~tnnICIi TIrun FUUNGL LUIS;IGU~.e Table F-2: Disposition of AWC Obsrvations Area Waly Question , Observation Disposition Checklist No.'4" diameter line from south wall is connected The displacement of the Victaulic coupling will be at wall with structural steel anchored to CIP dominated by the displacement of the pipe. The support concrete. It has victaulic coupling midspan differential displacement will contribute an insignificant EFT-N-Div 1 5 and is anchored above MCC with U-bolt/I-amount. Therefore, the pipe supports on the concrete beam support. Concern is differential wall and the other supports on the building steel will have displacement of south steel beam versus an insignificant effect on the pipe and the Victaulic north CIP wall. coupling in the pipe. It is not a seismic concern.These panels were reviewed as part of the SQUG C-303B & C-304C are within 3/4' at top. Is this program. Based on the SQUG analysis, the gap of 3/4" EFT 4 arepthin would be sufficient to prevent seismic interaction, and acceptable? the cabinets would not impact each other. It is not a seismic concern.Floor to ceiling 6" roof drain has victaulic EFTor 8 coling 4' frotop drain has nobracig IThis line was determined to be adequately supported as E FT 8coupling 4' from top and has no bracing .Is p r f C P 1 4 9 2 ot e ei o s i m c c n e n this seismically acceptable? part of CAP 1346922, so there is no seismic concern.In the Intake Structure, Sodium Hypochlorite This issue is being addressed by the work order process.Intake 3 residue was found on valve SHC-28 as well su is ng addessed bynterk p as from the ceiling, indicating a leak.Panel D31 was qualified as part of the SQUG program and determined to be seismically adequate in the Check drawing details documentation for existing configuration. The anchorage for the mounting 1 anchorage of base plate between D40 & D54. plate for panels D31, D52, D53 and D54 was verified against plant drawings and it was found that the anchorage for these panels is in accordance with plant drawings. No further action is required.The nut on the anchor bolt has full engagement but is PAB -13 Battery 3 One loose nut for duct strap anchor above loose and should be tightened. The duct support remains Door 109 needs to be tightened. adequate in its current configuration. WR 83099 was initiated to address this condition. PAB -13 Battery Comments "Reset" labelfor D102 was found on the floor Label was remounted by plant Operations. and was placed on top of D102.BCable tray MP404 & MP403 appears to be in CAP 1345963 concluded that this issue had been contact with C-27. previously analyzed and was determined not to be a seismic issue.Appendix F -Disposition of Seismic Walkdown Observations F-6 Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSI Withhold from Public Dr-I.-nnrc Table F-2: Disposition of AWC Observations Area Walkby Question Observation Disposition Checklist No.The connection of the vent to the main duct is s clinch Cable tray GR405, GR404, and GR403 is in lock type connection which has minimal rotational PAB-CSR 3 contact with HVAC duct registers in 4 of 5 resistance. Any interaction between the cable tray and Pca ies. the vent would move the vent without imparting any cases. significant load to the tray. Therefore, it is not a seismic concern.The line is a 4" drain line from the toilet located on the control room. The line is not pressurized or full of fluid and is not a flooding concern. A break of the line at the PAB-CSR Comments Verify coupling material on drain line and that uinw udpsil euti h no aln u ti PAB-SR ommnts alloabl stessis nt eceeed. union would possibly result in the union falling but it is not over any safety related equipment. The remainder of the line is supported and would not fall and impact any equipment. It is not a seismic concern.PAB-CSR 3 Some unistrut nuts are not fully engaged to If the light was to fall, and a circuit trip would occur, there support overhead lighting, would be minimal impact. It is not a seismic concern.Emergency Equipment cabinet across the aisle in corner from C-1 3 and C-37, and in the PAn -Control corner, is potentially unanchored. If The cabinet is anchored to the adjacent work platform to Room l unanchored, then may have potential adverse prevent the cabinet from tipping. It is not a seismic seismic spatial interaction concern since it concern.could tip over and impact C-13, which may adversely affect C-37 also.Plant status board is anchored to wall with two The status board is anchored to the contact wall with two PAB -Control screws. If board anchorage were to fail under Roomseimic ven, i mayimpct -O3.Is his anchors. The anchors are adequate for the calculated R oom seism ic event, it m ay im pact C -03. Is thisse mi lo d .I is n t a e s ic o c r .board adequately restrained for seismic load?The doors are free.to pivot about their hinges and could Doors between front and back control room impact the panels. The doors would impact the panel panels are not restrained. Doors are free to structure but would not impact any components inside PAB -Control 8 ineismieventrand could act side the panels. Due to the large differences in stiffness and Room 8 or in 13.ism ic is an ouldtima s iei mass between the panels and the hollow metal door, of C-02 or C-13. This is a potential seismic there will be minimal vibration to any relays and no concerns with relay chatter. The door is not a seismic concern.Vertical tube support (3) has two anchor bolts This condition is being addressed in the work RX -A RHR 8 into the floor. Nuts are not tight to the base management process, under WR 82181 and WO RXp-lothe fLoo uted aex t to RHRt18-1 whe base 464604. CAP 1346643 documents the observation. It is plates. Located next to RHR-18-1 handwheel.concern. Appendix F -Disposition of Seismic Walkdown Observations F-7 Monticello Nuclear Generating Plant Seismic Walkdown Report f B BB ~iuN~I ~'~itnnoi tram i'urncusour Table F-2: Disposition of AWC Observations Area Walkby Question Observation Disposition Checklist No.In the "A" RHR room, South wall, No. 11 RHR pump seal cooling water supply (RBCCW), This condition is being addressed by the work RX -A RHR 8 line support, there is a U-bolt that is missing a management process, under WR 82180 and WO nut and the other nut is not fully engaged. On 463560. CAP 1346654 documents the observation. It is a second support, one nut is not fully engaged not an adverse seismic concern.and the other nut is partially missing.HVAC support on south end cuts into pipe A 1/8" gap is estimated to exist between pipe and brace.insulation on line SC 16-8-ED approximately The 8" pipe is rigidly supported (seismic support) 5' from-4 1-3/8andinsulationolnS18 appearstoximtely 1 the brace location. Pipe movement at the brace location RX -HPCI 4 1-3/8" and insulation appears to be 1-1/2" i iia </".Teeoetepp ilntitrc thic. I thi a eismc satia ineracion is minimal (<1/8"). Therefore the pipe will not interact t ismcsp with the brace during a seismic event or thermal expansion of pipe. It is not a seismic concern.Both valve piping and duct are rigidly supported near the Manual 1" Valve (PS-23-106) hand wheel in interaction location. Due to low SSE accelerations at the contact with ventilation duct. Will the level of HPCI room (<0.02g) movement of pipe/valve and interaction between the two cause a leakage duct is minimal such that no damage to valve or duct is from the valve? expected. Operation of the valve or valve position will not be affected. It is not a seismic concern.MCC-312 is within zone of influence of R-8 Based on size of the cabinet and low SSE acceleration cabinet for chemical control storage. SWEs at the HPCI room floor, the cabinet will not tip over. If the RX -HPCI 7 cannot determine if R-8 is anchored to wall cabinet tip over (i.e., in the short direction) it will not from inside. Cabinet is locked. Cabinet could impact any safety related equipment. It is not a seismic tip over, impacting MCC-312 if not anchored. concern.Also compressed bottle on cart is within a few Plant operations moved the cart to comply with RX -HPCI 7 inches of MCC-312. Wheels are locked. Does housekeeping procedures. It is not a seismic concern.this meet station house keeping procedure? CAP 1346030 documents the condition identified. Reddish deposit noted on one of two anchor bolts on vertical support of structural angle supporting two pipelines. The lines are 1" diameter connecting SV-2849 to contaminated RX -RCIC 2 drain line and RCIC -(14) (2" diameter line) -The bolts were cleaned under WR 82134 and found to"To RCIC pump suction". SWE's cannot judge be in good condition. It is not a seismic concern. CAP condition of one anchor bolt that is covered 1346642 documents this observation. over with corrosion deposits. Other anchor bolt is not corroded.Appendix F -Disposition of Seismic Walkdown Observations F-8 Monticello Nuclear Generating Plant Seismic Walkdown Report SUNSi Withheld from Pubic Dnsilosurc Table F-2: DispoSition of AWC Observations Area Wa Qkby Question O e i Disposition Checklist No. O e ation ....ito In the RCIC room, there is a chain used to secure H-1 13 (gib crane) that does not restrain it from impacting the rod hanger H 113 has stops to prevent swinging toward rod hanger.RX- RCIC 5 and 7 supporting the pipe below. Is this configuration The chain prevents it moving away from the wall. It is not acceptable as-is or do we need to secure H- a seismit m oncern.113 in a different way to prevent a seismic a seismic concern.interaction issue? H-1 13 is within -2" of the rod hanger.In the RCIC room, there is a rod hanger for The support is PSH-108. This condition is addressed in a RX -RCIC 5 the RCIC steam supply line that is in contact MNGP calculation and is not a seismic concern.with a pipe. Is this acceptable? A calculation evaluated a similar condition with hanger In the RClC room, there is a rod hanger on PSH-1 08, which is in contact with a floor drain line. The the RCIC pump discharge that appears to be evaluation concluded that assuming a 3" total movement RX -RClC in contact with the RCIC steam supply line. Is of both lines, the impact on the rod hanger is negligible this acceptable? with respect to the additional loading on the rod hanger.This condition is bounded by this calculation. Therefore, there is no seismic concern.RX -Torus This condition was determined in CAP 1346939 not to be Catwalk -2 Tie wrap used to anchor electrical cable to a condition adverse to quality and it is not a seismic Northwest conduit 2G4010. concern. WR 83827 was initiated to re-support the extra cable length for AO-4539.sTwo boxes on ceiling appear to be Both conduits are anchored close to the junction boxes.RX -Torus Tworboxes ond ceilinpportedyearby tBased on small weight of the boxes and low seismic Catwalk -2 nanchored and supported by nearby unistrut. SSE accelerations, the conduits are capable of Northwest 2G4013 and 2G4014. supporting the junction boxes, even if the boxes are not anchored to ceiling. It is not a seismic concern.Both drain lines are supported near the tube tray. The RX -Torus Drain line (1 of 2 mentioned above) is in lies will not move vertically. Therefore, no force from the Northwest2 contact with tube tray. Is this acceptable? piping is imposed on the tube tray. Lateral movement of Northwest -piping also has no significant impact on tube tray. There is no seismic concern.The observed condition is not a crack. The gap between RX -Torus the ceiling T-beams (9" wide) was filled with concrete Catwalk -2 Crack in path of anchor for ceiling support on after the T-beams were installed. The lines along the gap Northwest solenoid valve SV-4541 and SV-4592. appear to be cracks; however, the lines are the boundary between poured concrete and pre-fabricated T-beams.There is no seismic concern.Appendix F -Disposition of Seismic Walkdown Observations F-9 Monticello Nuclear Generating Plant Seismic Walkdown Report SUNS! Withhold from Publmc DiSloSUre Table, F-2: Disposition of AWC Observations Area Wallklby Question Checlist No.Observation Disposition. Both drain lines are supported near the tube tray. The RX -Torus lines will not move vertically. Therefore, no force from the Catwalk -be potential flooding issue. It is located ping is imposed on the tube tray. Lateral movement of between Bay 6 & Bay 7 (Penetration RB609 & piping lsos n the tube tray. l emen Northwest RB603). It is a welded pipe and rod hung. piping also has no significant impact on tube tray. There is no seismic concern.Cable ties are fastening a flexible conduit to a his condition was determined in CAP 1346170 not to be RX -East 3 cable tray support. a condition adverse to quality and is not a seismic concern.In the Rx Bldg, above HCUs, there are two The conduit was identified as H158. Electrical rod hangers that are bent around conduit: One engineering determined there are no identified cables in RX -East 8 that supports an abandoned pipe, the other the conduit. Thus any local damage to the conduit will supports a heating steam line. Is this not affect any plant equipment. There is no seismic configuration adversely affecting the conduit? concern.FP line 3" -4" diameter with victaulic The line is not seismic and breaks are postulated in this RX -MG Set 5 couplings near F-20355 and F-20360. FP line line for internal flooding events. The sprinkler piping is has threaded couplings that might be cast only filled with water during a fire event, so it is not a iron. Some couplings are midspan. seismic concern.RX-MG Set 5 The line to a heat-activated-device (HAD) for The fire protection system air line is not Class 1;FP system is in contact with Service Air Line. therefore seismic interaction is not a concern.RX -MG Set 5 Smaller cast iron FP line has same threaded The fire protection system air line is not Class 1;couplings as 3" -4" FP line by 12 MG Set. therefore seismic interaction is not a concern.The pull box is not required to be supported, per plant Block wall noted around Door-73 is seismic specifications. Pull boxes that are on walls have an RX- MG Set 8 category 1 per drawing NF-36300-1-2 (South electrical fitting that goes through the wall. It is also grouted in the wall, which also provides support for the wall), box. Based on this the pull box is adequately supported, and is not a seismic concern.The pull box is not required to be supported, per plant Electrical box for penetration F2-0350 does specifications. Pull boxes that are on walls have an not have anchorage in block wall. Box is electrical fitting that goes through the wall. It is also connected to conduit 1 K31 00. Block wall is grouted in the wall, which also provides support for the seismic category 1 per drawing NF-36300-1-2. box. Based on this the pull box is adequately supported, and is not a seismic concern.RX -MG Set Comments FME (rags or paper) was identified behind V/R 83036 removed the loose material. It is not a seismi(C283A. concern.Appendix F -Disposition of Seismic Walkdown Observations F-10 Monticello Nuclear Generating Plant Seismic Walkdown Report S'J.hS! Withhold fr.m P-blibc Disclo-unre Table F-2: Disposition of AWC Observations Ar--a Wal':b";=w y Question ..Area alist Q on Observation Disposition Checklist No.See scaffold discussion for SBLC tank T-200 CAP 1347002 was initiated to evaluate this observation. and pump P-203A. (At the SBLC pump and The engineer responsible for scaffolding evaluations tank area, there is a large amount of reviewed the scaffold and determined it was adequately RX -SBLC 4 scaffolding, some of which is one level (-7' braced to prevent sliding and overturning during a high), some of which has two levels (-14' seismic event.high). Are the lateral attachments and overturning restraints adequate to achieve 2 over 1 ?)Hoist is resting on LC-101 480V Load Center. This condition was determined not to be a seismic TB -Lower 4KV 4 It also poses an impact hazard, and has open concern (CAP 1349068).s-hooks.Fire extinguisher near non safety 4.16kV This condition was determined not to be a seismic TB -Lower 4KV 4 4kVB-06 cubicle is an interaction hazard as it Tonw erm not tob9 asisi can fall off hook. concern (CAP 1349068).Hoist restraint on non-essential LC-1 09 should This condition was determined not to be a seismic TB -Lower 4KV 4 be replaced with a restraint more appropriate concern (CAP 1349068).than wire.Non-essential XFMR X-90 has missing bolts. This condition was determined not to be a seismic TB -Lower 4KV 7 There is an existing W.O. 00359194 noting concern. It is being addressed in the Work Order process this condition, under WO 359194.Lighting is pendant-hung and can swing into This condition was determined not to be a seismic TB -South 3 MCC-133B. Cable trays are supported by strut systems which are adequate. concern (CAP 1349068).Pendant light is an interaction hazard to This condition was determined not to be a seismic conduit connected to MCC-1 33A. concern (CAP 1349068).This condition was evaluated under CAP 1345971 and TB -12 DG Day 8 FP line is in contact with DO fuel line. was found to be acceptable as any potential failures Tank would not have any negative impact on the ability of the plant to safely shutdown.Main FP station has two dead weight supports with no anchorage to floor. Additional support The vertical support is modeled as a one way support, TB -12 DG Room 1 nearby is bolted to floor and captures FP per calculation. The support is as designed, and it shoulc station using 1/2" plate to capture pipe. Is this not be bolted to the floor but allowed horizontal configuration acceptable considering seismic movement. There is no seismic concern.anchorage? Appendix F -Disposition of Seismic Walkdown Observations F-1 1 Monticello Nuclear Generating Plant Seismic Walkdown ReportI ID Ku'ii OF nnnoifl a .- --1Nm i -:f" iic-T 91rciosur Table F-2: Disposition of AWC Observations Area Walkby Question Observation Disposition Checklist No.HVAC has 5' free end cantilever from last This type of support was evaluated as part of the TB -South 3 support and entire HVAC run is supported resolution of SQUG. Based on this evaluation, the tray from cable tray KA432. Is this configuration support is adequate to support the HVAC ducting. It is required to meet seismic 2/1 criteria? not a seismic concern.Rod for conduit support for conduits B933A and 2 other conduits is in contact with HVAC Any impact during a seismic event between the duct and TB -Upper 4KV 3 duct. Duct is moving just due to air flow and the rods could locally deform the HVAC duct but it would causes rod to be moved with it. Rod appears to be bent, possibly because anchor point for not cause structural failure. There is no seismic concern.rod is inside footprint of HVAC duct.Lighting is hung on a rod on the rear side of The lighting is supported by rod hangers and runs the Bus 16. It is laterally supported to prevent length of the upper 4kV room from west to east and TB -Upper 4KV 16sway by one wire tied of grating. SWEs are passes through the security barrier wall. The lighting concerned that there are not enough lateral support does not need to be restrained laterally as the concernd ta t te ae notenough l rod hangers will support the lighting without lateral supports. Light is 21' long, support. There is no seismic concern.The 12 Diesel Generator Pot Transformer was evaluated TB DG Ue Ve4kcicle 152-02sformer th Pis acutdin a calculation. The calculation added additional support TB -Upper 4KV for in anchorage calc? PT appears to be to prevent overturning and impacting equipment in the bolted to top of cubicle with angles, area. A plant drawing shows the additional anchorage for the potential transformer, so there is no seismic concern.Appendix F -Disposition of Seismic Walkdown Observations F-12}}