L-PI-14-020, Enclosure 3 - Prairie Island Nuclear Generating Plant, Unit 2 - NTTF Recommendation 2.3 - Seismic Updated Seismic Walkdown Report (Redacted)

Enclosure 3 - Prairie Island Nuclear Generating Plant, Unit 2 - NTTF Recommendation 2.3 - Seismic Updated Seismic Walkdown Report (Redacted)

ML14069A028
Person / Time
Site:	Prairie Island
Issue date:	03/04/2014
From:	Northern States Power Co, Xcel Energy
To:	Office of Nuclear Reactor Regulation
Shared Package
ML14069A024	List: L-PI-14-020, Enclosure 3 - Prairie Island Nuclear Generating Plant, Unit 2 - NTTF Recommendation 2.3 - Seismic Updated Seismic Walkdown Report (Redacted) ML14069A027
References
L-PI-14-020
Download: ML14069A028 (300)

Text

CONTAINS SUNSI- WITHHOLD FROM PUBLIC DISCLOSURE UNDER 2.390 ENCLOSURE 3 PRAIRIE ISLAND NUCLEAR GENERATING PLANT - UNIT 2 NTTF RECOMMENDATION 2.3 - SEISMIC UPDATED SEISMIC WALKDOWN REPORT (REDACTED)

(255 Pages Follow)

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table of Contents Lis t o f T a ble s ......................................................................................................... iii Executive Sum mary ............................................................................................... iv I Introduction................................................................................................................... 1-1 1 .1 Ba c kg ro u n d ........................................................................................................... 1-1 1.2 Plant Overview ...................................................................................................... 1-1 1 .3 A pp ro a c h ............................................................................................................... 1-2 2 Seism ic Licensing Basis ........................................................................................ 2-1 2 .1 O v e rv iew ............................................................................................................... 2-1 2.2 Design Basis Earthquake (DBE) ............................................................................ 2-1 2.3 Design of Seism ic Category I SSCs ....................................................................... 2-1 2.3.1 Sum mary of Seism ic Design ........................................................................ 2-2 2.3.2 Methods for Qualifying Electrical and Mechanical Equipment and Instrumentation ...................................................................................................... 2-2 2.3.3 Sum mary of Codes and Standards ............................................................... 2-3 3 PersonnelQualifications......................................................................................... 3-1 3 .1 O v e rv iew ............................................................................................................... 3-1 3.2 W alkdown Personnel ............................................................................................. 3-1 3.3 Personnel Qualifications ........................................................................................ 3-3 4 Selection of SSCs .................................................................................................... 4-1 4 .1 O v e rv iew ............................................................................................................... 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 SW EL 2 - Spent Fuel Pool Related Items .................................................... 4-4 4.3 Changes to the Final SW EL 1 ...................................................................... 4-5 5 Seism ic W alkdowns and Area Walk-Bys ................................................................ 5-1 5 .1 O v e rv iew ............................................................................................................... 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 i

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 5.2.4 Other Adverse Seism ic Conditions ............................................................... 5-3 5.2.5 Issues Identified during Seism ic W alkdowns ................................................ 5-5 5.3 Area W alk-Bys ....................................................................................................... 5-5 5.3.1 Seism ically-Induced Flooding/Spray Interactions ......................................... 5-6 5.3.2 Seism ically-Induced Fire Interactions ........................................................... 5-7 5.3.3 Issues Identified during Area W alk-Bys ........................................................ 5-7 6 Licensing Basis Evaluations.................................................................................... 6-1 7 IPEEE VulnerabilitiesResolution Report .................................................................... 7-1 8 Peer Review .................................................................................................................. 8-1 9 References .................................................................................................................... 9-1 Appendices A Equipment Lists...................................................................................................... A-1 B Deferred Seismic Walkdown Checklists (SWCs) ................................................. B-1 C DeferredArea Walk-By Checklists (AWCs) ........................................................... C-1 D Peer Review Report................................................................................................. D-1 ii

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report List of Tables Table 2-1: List of Codes, Standards and Specifications 2-4 Table 3-1: Personnel Roles - Initial Seismic Walkdown Effort 3-1 Table 3-2: Personnel Roles - Post 11/26/2012 Seismic Walkdown Effort 3-1 Table 4-1: Substituted Equipment for Revised SWEL 1 4-5 Table 5-1: Anchorage Configuration Confirmation 5-3 Table 5-2: Prairie Island Unit 2 SWC CAP Status 5-8 Table 5-3: Prairie Island Unit 2 Area Walk-By CAP Status 5-11 Table 7-1: Prairie Island IPEEE Seismic Vulnerabilities 7-2 Table A-i: Prairie Island Unit 2 - Base List 1 A-2 Table A-2: Prairie Island Unit 2 - SWEL 1 A-42 Table B-i: Prairie Island Unit 2 SWCs Completed after November 26, 2012 B-2 Table C-1: Prairie Island Unit 2 AWCs Completed after November 26, 2012 C-2 Table D-1: SWC Samples from Seismic Walkdown Inspection for Unit 2 performed after November 26, 2012 D-7 Table D-2: AWC Samples from Seismic Walkdown Inspection for Unit 2 performed after November 26, 2012 D-11 iii

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal 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-1 1-0093 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML111861807)) 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. ML112310021), 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. ML11245A158) 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 as well as to verify the current plant configuration with the current seismic licensing basis. This report documents the seismic walkdowns performed at the Prairie Island Nuclear Generating Plant (PINGP) 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 PINGP in a letter dated July 9, 2012 (Reference 10).

NSPM performed walkdowns in accordance with the EPRI Seismic Walkdown Guidance (Reference 1) and submitted a summary of the results of these walkdowns in a letter dated November 26, 2012 (Reference 13). In Appendix D of Reference 13, NSPM identified components that could not be inspected 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 (environment that posed personnel safety concerns while the unit is operating), or due to iv

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report the timing of the issuance of the clarification on internal electrical cabinet inspections and the electrical safety hazards posed while the equipment is energized. In the Reference 13 report, NSPM committed to completing these inaccessible walkdowns during Refueling Outage (RFO) 2R29 and submitting an updated Seismic Walkdown report 60 days following the end of the refueling outage in 2015.

The original schedule for completing the inaccessible walkdowns was based on the next planned refueling outage that provided an opportunity to inspect the internals of electrical equipment, considering the existing plant-specific component outage maintenance schedules. NSPM did not schedule additional unplanned equipment outages to support these cabinet interior inspections since NRC/industry guidance did not require circuits to be interrupted or disconnected to gain access to the interior portions of the cabinet.

The NRC scheduled a public conference call on May 7, 2013 to discuss NRC staff concerns regarding delayed inspection items as identified in seismic walkdown reports for a number of operating reactors (Reference 12). During the meeting, the NRC staff stated its expectation that walkdown activities should be completed as expeditiously as possible and by the next refueling outage, if possible. The NRC staff requested that licensees voluntarily submit a supplemental letter to their walkdown reports to propose an alternate approach for completing the inaccessible walkdowns by the next refueling outage. Another public conference call was scheduled on August 1, 2013 for the NRC staff to provide further clarification on the information that should be provided in the licensee's voluntary letters (Reference 42).

As requested in References 12 and 42, NSPM submitted a proposal for final disposition of the remaining NTTF Recommendation 2.3 Seismic Walkdowns for PINGP Unit 2 on September 12, 2013 (Reference 9). This letter revised the commitments made in the Reference 13 seismic walkdown report to complete the Seismic Walkdowns of the inaccessible components listed in the enclosure of Reference 9 by the end of Refueling Outage (RFO) 2R28.

Following the NRC Staffs initial review of the industry's seismic walkdown reports, regulatory site audits were conducted at a sampling of plants. Based on the seismic walkdown report reviews and site audits, the NRC Staff identified, in a letter dated November 1, 2013 (Reference 43), the additional information necessary to allow the NRC Staff to complete its assessments. NSPM submitted responses to these RAIs in a letter dated November 27, 2013 (Reference 11).

This updated Seismic Walkdown report provides the results of the deferred Seismic Walkdowns performed at PINGP after November 26, 2012. This report also documents any new discrepancies or potential seismic issues identified as a result of the deferred Seismic Walkdowns. Results from the Seismic Walkdowns completed prior to November 26, 2012, and any potential discrepancies or potential seismic issues, were submitted in the Reference 13 report. This report provides a status update of the corrective actions previously identified in Tables 5-2 and 5-3 of the Reference 13 report. No adverse seismic conditions were identified at the PINGP as a result of the initial or deferred walkdowns. Corrective Action Program Action Requests (CAPs) were entered into the site's 10 CFR 50 Appendix B qualified corrective action program.

v

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal 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 Much of the information previously provided in the Reference 13 report on the seismic licensing basis, selection of SSCs, IPEEE vulnerabilities resolution report, and the methodology used for completing the Seismic Walkdowns and Area Walk-Bys has not changed since November 26, 2012. However, this information is repeated in this report for reference, and to reiterate the process that has been used for the initial and deferred Seismic Walkdowns.

This report closes the commitments in References 9 and 13, and provides the supplemental information required for the final response to the Requested Information for NTTF Recommendation 2.3, Seismic (Reference 6). No additional Seismic Walkdowns are required for PINGP Unit 2. Additional walkdowns will be required for the next PINGP Unit 1 outage during 2014.

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Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal 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), 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 (Reference 6). 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 Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012 (Reference 1), was endorsed by the NRC on May 31, 2012 (Reference 8). NSPM confirmed that the EPRI seismic walkdown guidance would be used as the basis for conducting the seismic walkdowns and gathering the requested information at PINGP in a letter dated July 9, 2012 (Reference 10).

1.2 PLANT OVERVIEW PINGP, Units 1 and 2, are both two-loop pressurized water reactors owned by NSPM.

Westinghouse Electric Corporation designed and supplied the nuclear steam supply systems, initial reactor fuel, and the turbine-generator units. Pioneer Service and Engineering Company (PS&E) was the plant's architect-engineer. Northern States Power was the constructor.

The containment for each unit was designed by PS&E and consists of two systems:

• A primary containment consisting of a free-standing low-leakage steel vessel, including its penetrations, isolation systems and heat removal systems.

• A secondary medium leakage concrete shield building surrounding the primary containment, including special ventilation systems for its annulus and adjacent auxiliary building.

1-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 1.3 APPROACH The EPRI Seismic Walkdown Guidance (Reference 1) was used for PINGP Unit 2 engineering seismic 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) 1-2

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 2 Seismic Licensing Basis 2.1 OVERVIEW This section of the report summarizes the seismic licensing basis for PINGP Unit 1 and Unit 2. 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 (SSCs) are presented. This section does not establish or change the seismic licensing basis of the facility but is intended to provide a fundamental understanding of the seismic licensing basis of the facility.

2.2 DESIGN BASIS EARTHQUAKE (DBE)

The design basis earthquake (DBE) is based upon a maximum horizontal ground acceleration of 0.12g; the associated response spectra are given in Plate 4.6, Appendix E of Reference 2. The DBE is synonymous with the Safe Shutdown Earthquake (SSE) (Reference 2, Section 12.2.1.3.5).

2.3 DESIGN OF SEISMIC CATEGORY I SSCS Full descriptions 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 are provided in the following PINGP Updated Safety Analysis Report (USAR) (Reference 2) sections:

" USAR Section 12.2.1.1, Classificationof Structures and Components

• USAR Section 12.2.1.3.5, Seismic Loads

• USAR Section 12.2.1.4, General Design Criteriafor Structures

" USAR Section 12.2.1.4.3, Structural Design Basis

• USAR Section 12.2.1.5, Seismic Analysis of Mechanical and Electrical Equipment These USAR sections should be referred to for a detailed understanding of the seismic licensing basis.

2-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 2.3.1 Summary of Seismic Design The site Operating Basis Earthquake (OBE) and DBE ground response spectra are shown in Plates 4.5 and 4.6, respectively, in Appendix E of the PINGP USAR (Reference 2). The equivalent multi-mass mathematical model was constructed to approximate the structural system. The effect of the foundation soils is included in the model by means of equivalent springs. The spectral method was used to determine the maximum response of each mass point for each mode, using the OBE (Reference 2, Plate 4.5 in Appendix E) and damping values given in USAR Table 12.2-8 of Reference 2 as input. The total response for each point was determined by the root-mean-square (RMS) method. From this, a set of curves were developed showing the maximum translational accelerations, displacements, shears, and moments as varying with height.

The maximum horizontal and vertical ground accelerations at the ground level are 0.12g for the DBE (SSE) and 0.06g for OBE (Plates 4.5 & 4.6, Appendix E - Reference 2).

These OBE and DBE ground response spectra were plotted at 0.5%, 2% and 5%

damping (Reference 2, Plates 4.5 and 4.6 of Appendix E). The vertical ground acceleration is equal to two-thirds of the horizontal ground acceleration (Reference 2, Section 12.2.1.4.3.1.1).

2.3.2 Methods for Qualifying Electricaland Mechanical Equipment and Instrumentation Equipment and instrumentation are qualified using one or more of the following methods:

1. Qualification by analysis,

2. Qualification by test, or

3. Qualification by combination of analysis and test.

Equipment is qualified by analysis if the equipment is not too complex and can be represented in a mathematical model for performing static analysis and/or dynamic analysis.

1. Qualification by Analysis Static Analysis Static analysis is performed for an equipment item determined to be rigid. The seismic forces on each component of the equipment are obtained by concentrating the total mass at the equipment's center of gravity and multiplying the values of the mass and the appropriate floor acceleration from the seismic response spectra. The resulting forces are converted to stresses and are added to the other equipment stresses, as per the design criteria, to determine if the equipment is adequate to withstand the required load.

2-2

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Dynamic Analysis Dynamic analysis is performed for flexible equipment items. The equipment is analyzed using a response spectrum or time-history analysis. Both of these methods have been used to qualify equipment for PINGP.

2. Qualification by Test If the equipment is flexible and too complex to be represented properly by an analytical model, then the equipment is qualified by test. Testing is also performed where the equipment is required to operate during or after a seismic event for which this cannot be established analytically. Seismic tests are performed by subjecting the equipment to vibratory motion which conservatively simulates the motion at the equipment mounting location during an (or several) OBE(s), followed by the vibratory motion associated with an SSE.

3. Qualification by Combination of Test and Analysis Some electrical equipment and instrumentation are qualified by a combination of test and analysis. This qualification can be achieved through various methods such as extrapolation from similar equipment or similar seismic conditions.

2.3.3 Summary of Codes and Standards This section summarizes the codes, specifications, standards of practice, and other accepted industry guidelines to the extent applicable in the design and construction of the following:

• Containment - the applicable codes, standards, and specifications for the containment are 1 through 23 in Table 2-1 below.

" Containment Internal Structures - all of the items listed in Table 2-1 below are applicable for the containment internal structures.

• Safety-Related Structures Outside of Containment - all of the items listed in Table 2-1 below are applicable, with the exception of Items 17 and 18.

• Foundations for Seismic Category I Structures - the applicable codes, standards, and specifications are 1 through 14 and 19 through 23 in Table 2-1 below.

2-3

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table 2-1: List of Codes, Standards, and Specifications Specification SeicainStandardSpecification or Title Reference Number Stgnation Designation American Concrete Building Code Requirements for Reinforced 1 Institute (ACI) 318- Concrete (Reference 14) 71,77,83 2 ACI 301 Specifications for Structural Concrete for Buildings (Reference 15)

Recommended Practice for ANSI A145.1 Concrete Formwork (Reference 16)

Recommended Practice for Hot ANSI A170.1 Weather Concreting (Reference 17)

Recommended Practice for Selecting 5 ACI 211.1 Proportions for Normal Weight Concrete (Reference 18)

Recommended Practice for Measuring, Mixing, 6 ACI 304 Transporting, and placing concrete (Reference 19)

Manual of Standard Practice for Detailing Reinforced Concrete Structures (Reference 20)

Recommended Practice for Cold Weather Concreting (Reference 21)

Recommended Practice for Consolidation of Concrete (Reference 22)

Recommended Practice for Curing Concrete (Reference 23)

Recommended Practice for ANSI Al 46.1 11 ACI 214 Evaluation of Compression Test Results of Field (Reference 24)

Recommended Practice for Concrete Inspection (Reference 25) 13 ACI 304 Preplaced Aggregate Concrete for Structural and Mass Concrete (Reference 26) 14 Report by ACI Placing Concrete by Pumping Method Committee 304 (Reference 27)

Specification for the Design, Fabrication, and 15 AISC-69,78 Erection of Structural Steel for Building (Reference 28)

Structural Welding Code (Reference 29) 16 AWS D1.1 2-4

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table 2-1: List of Codes, Standards, and Specifications Specification SeiiainStandardSpecification or Title Reference Number Signation Designation Boiler & Pressure Vessel Code,Section III ASME (Reference 30)

ASME-1971, S73 Division 1, Subsection NE ASME-1974, S75 Division 1, Subsection NF 17 Division 2, Proposed Standard Code for ASME-1 973 Concrete Reactor Vessels and Containments Issued for Trial Use and Comments ASME-1 980 Division 2, CC 6000 ASME-1 992 1992 Addenda, Division 1,Section XI, Subsection IWL, IWE American Public Test Methods Sulphides in Water, Standard 18 Health Assoc. Methods for the Examination of Water and (APHA) Waste Water (Reference 31)

Annual Books of ASTM Standards 19 ASTM (Reference 32) 20 CRSI MSP-1 Manual of Standard Practice (Reference 33)

Proposed Supplementary Q.A. Requirements for Installation, Inspection and Testing of Structural 21 ANSI N45.2.5 Concrete and Structural Steel During Construction Phase of Nuclear Power Plants (Reference 34)

Chief of Research and Development Standards, 22 CRID Department of the Army, Handbook for Concrete and Cement Volume I and II, Corps of Engineers U.S. Army (Reference 35)

Code Requirements for Nuclear Safety Related Concrete Structures (Reference 36) 24 AISI Specification for design of cold-formed steel structural members (Reference 37) 2-5

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal 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 of the EPRI Report 1025286 (Reference 1).

3.2 WALKDOWN PERSONNEL Table 3-1 below summarizes the names and corresponding roles of personnel who participated in the initial NTTF Recommendation 2.3 Seismic Walkdown effort. The names and corresponding roles of personnel who participated in the NTTF Recommendation 2.3 Seismic Walkdown effort after November 26, 2012 are provided in Table 3-2.

T2hIn 2.1' P~rQnnnM Pnic~ - lniti2i ~kmir~ W2IIcrInwn Fffnrt Equipment eeltiomnt Plant Plant Seismic Walkdown Licensing IPEEE Peer Name Selection Basis Reiwr evwr Engineer Operations Engineer R Reviewer Reviewer B. Lory (S&A) X X W. Djordjevic (S&A) X D. Zercher (NSPM) X D. Cherlopalle (NSPM) X Xi K. Kriesel (NSPM) X X3 S. Seilhymer (NSPM) X X1 P. Valtakis (NSPM) X X x2 T. Bacon (S&A)

M. Etre (S&A) X D. Moore X Notes:

1. Peer Review Team member for SWEL review only.

2. Peer Review Team Leader.

3. No licensing basis evaluations were performed.

3-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table 3-2: Personnel Roles - Post November 26, 2012 Walkdown Effort Seismic Licensing I Equipment Plant Walkdown Basis IPEEE Peer Engineer Operations Engineer Reviewer Reviewer Reviewer (SWE)

B. Lory (S&A) X X D. Cherlopalle (NSPM) X X1 K, Kriesel (NSPM) X X3 S. Seilhymer (NSPM) X X1 M. Delaney (S&A) X2 P. Gazda (S&A) X M. Wodarcyk (S&A) X D. Moore X D, Zercher (NSPM) x B. Fauver (NSPM) X X Notes:

1. Peer Review Team member for SWEL review only.

2. Peer Review Team Leader.

3. No licensing basis evaluations were performed.

3-2

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal 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: Bachelor of Science in Mechanical Engineering from the State University of New York at Buffalo Professional Experience: 30+ years of 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: Master 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.

3-3

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Dennis Zercher

" Activities Performed: SWE

" Seismic Training Completed: EPRI SQUG Training

" Education: BSCE, Michigan Technological University

" Professional Experience: 28+ years of structural and seismic engineering in commercial nuclear industry. Performed the USI A-46 and IPEEE seismic walkdowns for Monticello Nuclear Generating Plant. A registered Professional Engineer in Minnesota and Wisconsin. He works at Stevenson & Associates as a Design Engineer. He was a Structural Engineer at FluiDyne Engineering and PaR Systems.

Dileep Cherlopalle

" Activities Performed: Equipment Selection Peer Review, SWE

" Seismic Training Completed: EPRI NTTF Recommendation 2.3 - Plant Seismic Walkdowns Training

" Education: Master of Science in Structural Engineering - University of Alaska -

Fairbanks

" Professional Experience: 4+ years of experience in commercial nuclear industry.

Currently a Design Civil/Structural Engineer at PINGP.

Kyle Kriesel

" Activities Performed: Licensing Basis Reviewer, SWE

" Seismic Training Completed: EPRI SQUG Training

" Education: Bachelor of Science in Civil Engineering from North Dakota State University

" Professional Experience: 11 + years of experience in the commercial nuclear industry. A registered Professional Engineer in Minnesota. Worked as a Plant Design Civil/Structural Engineer at Cooper Nuclear Station and PINGP including structures monitoring implementation and structures monitoring program coordinator.

3-4

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Stephen Seilhymer

" Activities Performed: Equipment Selection Peer Reviewer

" Seismic Training Completed: N/A

" Education: Bachelor of Science in Physics - Applied Nuclear Science from Winona State University

" Professional Experience: Reached rank of Electronics Technician First Class and performed as Reactor Operator and Engineering Watch Supervisor on a nuclear powered submarine in the United States Navy. Obtained Senior Reactor Operator License and has completed roles as Equipment Operator, Control Room Supervisor, Shift Manager, Assistant Operations Manager, Licensed Operator Requalification Training Supervisor, and Operations Simulator and Classroom Instructor positions at PINGP. Has a total of 30 years of nuclear experience, with 18 years of experience as a Senior Reactor Operator.

Pete Valtakis

" Activities Performed: Equipment Selection (Initial phase only)

" Seismic Training Completed: N/A

" Education: Bachelor of Science in Physics, Winona State University

" Professional Experience: Acted as a Reactor Operator on a nuclear powered submarine in the United States Navy, and was also assigned as a Leading Petty Officer of the Reactor Controls Division, an Engineering Officer of the Watch, and a Training Coordinator for the Naval Prototype Training Unit. Obtained Senior Reactor Operator License at PINGP and has completed roles as Reactor Operator, Lead Operator, Control Room Supervisor, and Shift Manager at PINGP. Participated in all phases of pre-operational testing and initial criticality of both PINGP units. Has a total of 39 years of commercial nuclear experience, with 28+ years of experience as a Senior Reactor Operator.

3-5

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Todd Bacon

" Activities Performed: Peer Review Team Leader

" Seismic Training Completed: Near Term Task Force Recommendation 2.3 -

Plant Seismic Walkdowns

" Education: Bachelor of Science in Civil Engineering from the University of Illinois

- Champaign

" Professional Experience: Mr. Bacon has thirty years of experience in the design and modification of mechanical and structural systems. His responsibilities have included serving as an Engineering Manager involving work from the conceptual design through to the installation support phases of multiple projects. Mr. Bacon has served as Project Engineer and Project Manager for numerous work scope efforts, including coordination of personnel in multiple locations. His efforts have also included significant client and/or regulatory interface, as required. These activities have also included responsibility for budgets, schedules and the technical accuracy of work performed. In addition, he has extensive experience in proposal and report development, as well as personnel training activities. Mr.

Bacon's work has involved extensive use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, including involvement with various piping system related committees.

Mark Etre

" Activities Performed: Peer Reviewer

" Seismic Training Completed: EPRI SQUG training and Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns,

" Education: Master of Science in Mechanical Engineering from the Worcester Polytechnic Institute

" Professional Experience: Mr. Etre is a Project Manager in the S&A Boston office.

He has managed and led seismic walkdowns and analyses of structures and components. Mr. Etre has more than 20 years of seismic experience serving the nuclear industry. Mr. Etre has participated in numerous USI A-46 and IPEEE projects in response to the requirements of Generic Letters 87-02 and 88-20.

3-6

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report David L. Moore

" Activities Performed: IPEEE Reviewer

" Seismic Training Completed: EPRI SQUG Systems and Relay 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.

Bruce Fauver

" Activities Performed: Equipment Selection Engineer, Plant Operations

" Seismic Training Completed: N/A

" Education: Master of Engineering Management, George Washington University

" Professional Experience: Served as a Propulsion Plant Watch Officer and Engineering Officer of the Watch on nuclear powered aircraft carriers during 20 year career in the United States Navy, and was also assigned as a Division Officer of the Reactor Electrical and Mechanical Divisions, Reactor Training Assistant and Preventive Maintenance Officer for entire aircraft carrier. Obtained Senior Reactor Operator License at PINGP and has completed roles as Control Room Supervisor and Shift Technical Assistant at PINGP. Has a total of 4 years of commercial nuclear experience, with one year of experience as a Senior Reactor Operator.

Marlene Delaney

" Activities Performed: Peer Reviewer

" Seismic Training Completed: EPRI SQUG Training, Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns

" Education: Bachelor of Science in Civil Engineering, University of Wisconsin -

Milwaukee

" Professional Experience: 30 years of experience in commercial nuclear industry.

Currently a Project (Structural) Engineer at Stevenson & Associates (S&A).

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Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Philip Gazda

" Activities Performed: Peer Reviewer

" Seismic Training Completed: EPRI SQUG Training, Near Term Task Force Recommendation 2.3 - Plant Seismic Walkdowns

" Education: Master of Science in Civil Engineering from the University of Illinois at Urbana-Champaign

" Professional Experience: 40 years of experience in commercial nuclear industry.

Currently Chicago Office General Manager at Stevenson & Associates (S&A).

Michael Wodarcyk

" Activities Performed: SWE

" Seismic Training Completed: Near Term Task Force Recommendation 2.3 -

Plant Seismic Walkdowns

" Education: Master of Science in Civil Engineering from the University of Illinois at Urbana-Champaign

" Professional Experience: 2 years of experience in commercial nuclear industry.

Currently a Staff (Structural) Engineer at Stevenson & Associates (S&A).

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Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal 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 and are as follows:

• Table A-1 is a list of the equipment coming out of Screen #2 and entering Screen #3 for the equipment selection of SWEL 1. This list of equipment is titled Base List 1.

• Table A-2 is the PINGP Unit 2 list of equipment which has gone through the screening process defined in Reference 1 and then selected by the Equipment Selection Team to be seismically inspected in accordance with Reference 1, excluding Spent Fuel Pool (SFP) equipment, which is in SWEL 2. This list of equipment is termed SWEL 1.

4.2 SWEL DEVELOPMENT The process for selection of SSCs 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 PINGP Unit 2.

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 required for safe shutdown and maintaining containment integrity began with the composite Seismic Qualification Utility Group (SQUG) Safe Shutdown Equipment List (SSEL) (Reference 3). The SQUG SSEL was then subjected to the following four screens 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, only items that have a defined seismic licensing basis (Seismic Category I) are to be included in SWEL 1. Each item on the 4-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SSEL was reviewed to determine if it had a defined seismic licensing basis. All items identified as Seismic Category I, as defined in Section 12 of the PINGP USAR (Reference 2), were identified as having a defined seismic licensing basis. Electrical enclosures containing Class 1E devices were identified as Seismic Category I.

Seismic Category I and Class 1E determination was made through a review of current design and licensing basis documentation.

2. Screen #2 - Equipment or Systems 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 - 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's 10 CFR 50.54(f) letter (Reference 6). In Section 3 of Reference 1, the screen for sample considerations is Screen #4. NSPM performed Screen #4 of Reference 1 as Screen #3. The screen for determining supports of the five safety functions (Screen #3 in Reference 1) was performed as Screen #4 for the PINGP. As a result of this change in order, the Base List 1 in Table A-1 of Appendix A of this report is a list of the equipment coming out of Screen #2. Also, this report defines Screen #3 of Reference 1 as Screen #4, and vice versa for Screen #4 of Reference 1.

The following attributes were considered in the selection process for items included on SWEL 1:

A. A variety of types of systems The system for each item on SWEL 1 is identified. The equipment included on SWEL 1 is a representative sample of several systems that perform one or multiple safety functions. Further, the systems represented include both frontline and support systems from those listed in Appendix E, Systems to Support Safety Function(s), of Reference 1.

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 for each item on SWEL 1 is identified. The equipment included on SWEL 1 is a representative sample from each of the classes of equipment listed in Reference 1 Appendix B, Classes of Equipment. Where 4-2

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 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 classes (12) Air Compressors or (13) Motor Generators.

D. A variety of environments The location for each item is identified on SWEL 1. The equipment included on SWEL 1 is a representative sample from a variety of environments (locations) in the site.

E. Equipment enhanced due to vulnerabilities identified during the IPEEE program The equipment included on SWEL 1 includes several items that were enhanced as a result of the IPEEE program. Each item on SWEL 1 that was enhanced to correct an outlier from IPEEE is identified.

F. Contribution to risk To determine the relative risk significance, the Risk Achievement Worth (RAW) and Fussell-Vesely importance from the internal plant PRA were used.

Initiating events, maintenance events and human error events were not considered in the generation of this list. The thresholds for risk significance that were used (Fussell-Vesely risk > 5.OE-3, RAW > 2) are derived from the ANS/AMSE PRA Standard. This PRA Standard was endorsed by the NRC via Regulatory Guide 1.200.

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. Screen #4 - Support for the 5 Safety Functions This screen ensured that the scope of items included on the SWEL 1 are 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 4-3

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 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.

It is noted that items on SWEL 1 with a specific safety function(s) are considered frontline systems. Items with a safety-function designation of 'Support System HVAC', 'Support System AC Power', 'Support System DC Power', Engineered Safety Features Actuation System ('ESFAS') or 'Cooling Water' may be categorized as a frontline or support system. Items with a safety function designation of 'Support System HVAC', 'Support System AC Power', 'Support System DC Power',

Engineered Safety Features Actuation System ('ESFAS') or 'Cooling Water' support at least one of the five safety functions, however, the specific safety function(s) are depicted as numbers 1-5 in SWEL 1, corresponding to the 5 safety functions mentioned in the EPRI guidance (Reference 1). SWEL 1 in Table A-2 of Appendix A contains a legend to correlate this number to a specific safety function.

4.2.2 SWEL 2 - Spent Fuel Pool Related Items The PINGP Unit 1 seismic walkdown submittal report discusses and identifies the equipment selected for SWEL 2. Therefore, this PINGP Unit 2 seismic walkdown submittal report does not contain a discussion of the SWEL 2 walkdowns or equipment selection process.

4-4

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 4.3 Changes to the Final SWEL I After the November 26, 2012 report (Reference 13), changes were made to the final SWEL 1. A description and justification for the changes made to SWEL 1 since the Reference 13 report are described in the following paragraphs.

In an effort to complete the deferred seismic walkdowns by the end of the RFO 2R28, NSPM evaluated component availability to determine opportunities where the equipment could be accessible for inspection, as well as to determine viable substitutions that could be made to allow earlier inspection (Reference 9). As a result of this evaluation, NSPM identified seven (7) components that were not out of service during 2R28 to allow for internal cabinet inspections. These seven (7) components were SWEL 1 items BUS 211, BUS 221, BUS 222, MCC 2A1, MCC 2K1, MCC 2K2, and MCC 2L2.

NSPM identified four (4) similar components that were available in the outage for inspection. For the 480V switchgear internal cabinet inspections, BUS 212 was substituted for BUS 211. SWEL 1 items BUS 221 and BUS 222 were deleted from SWEL 1, because these components were not accessible for walkdowns in the outage.

As for the 480V Motor Control Center (MCC) internal cabinet inspections, MCC 2LA1 was substituted for MCC 2A1, and MCC 2M1 was substituted for MCC 2K1. The other available 480V MCC, MCC 2X1, was added to SWEL 1 as an additional walkdown inspection. A summary of the substitutions is provided in Table 4-1.

Equipment Tag No. 274-013 (23 Containment Fan Coil Unit) was removed from the list of equipment whose anchorage required verification, due to its internal anchorage being inaccessible during RFO 2R28. However, a walkdown of the equipment was still performed.

Table 4 Substituted Equipment for Revised SWEL I Original Equipment Tag Replacement Equipment Tag BUS 211 BUS 212 MCC 2A1 MCC 2LA1 MCC 2K1 MCC 2M1 4-5

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal 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 on the SWEL 1 and SWEL 2 as provided in Table A-2 of Appendix A of 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 all 93 Seismic Walkdowns were documented on Seismic Walkdown Checklists (SWCs). The SWCs completed before November 26, 2012 were submitted in Appendix B of Reference 13. Those completed after November 26, 2012 are provided in Appendix B of this document. Photos have been included with most Seismic Walkdown Checklists to provide a visual record of the item along with any comments noted on the Seismic Walkdown Checklist. Drawings and other plant records are cited in some of the Seismic Walkdown Checklists, but are not included with the Seismic Walkdown Checklists because they are readily retrievable documents through the station's document management system.

5-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 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 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 and a licensing basis evaluation was not necessary. However, if it was not possible to judge whether the anchorage is degraded, nonconforming, or unanalyzed, then the condition was entered into the Corrective Action Program as a potentially adverse seismic condition.

5.2.2 Configuration Verification In addition to the visual inspections of the anchorage as described above, for at least 50% of applicable equipment items, the configuration of the installed anchorage was verified to be consistent with existing plant documentation.

Line-mounted equipment (e.g., valves mounted on pipelines without separate anchorage) were not be evaluated for anchorage adequacy and were not counted in establishing the 50% sample size.

Examples of documentation that is considered to verify that the anchorage installation configurations are consistent with the plant documentation include the following:

5-2

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

• Design drawings

• Seismic qualification reports of analyses or shake table tests

• IPEEE or USI A-46 program documentation, as applicable Table B-1 in Appendix B documents which deferred SWCs had anchorage configuration verification 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 SWEL Items Items Verify? Items Verified (A) (B) (A-B)/2 1 93 25 34 36 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.

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 5-3

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

• 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 and panels was sent to all licensees through the Nuclear Energy Institute (NEI). In this document, it was communicated that it was 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 was necessary to look inside to check its anchorage. 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 for evidence that internal components are or 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 Reference 1.

The internal inspections of electrical cabinets and panels were performed at PINGP to the extent allowed by personnel and operational safety. For SWEL 1 Items MCC 2K2 and MCC 2L2, NSPM completed partial inspections of the 480V MCCs. Even though internal cabinet inspections of individual compartments of the MCCs were not performed due to personnel safety issues and operational constraints, NSPM performed a visual inspection of the MCC's anchorage. Due to the fact that MCC anchorage can be accessed by removing panels at the bottom of the MCC that does not result in exposing energized conductors, these visual inspections included an assessment of the MCCs' anchorage.

For lower voltage cabinets (e.g., 120 VAC distribution panels), the panel faceplate was removed to allow visual inspection of the anchorage and internals while the component was energized. If wires or other internal components blocked the view of any anchors, they were not moved to permit inspections. The operational and personnel safety risk did not justify movement of internal components within energized equipment. NSPM's procedures on electrical safety allow qualified individuals to approach energized electrical components, if the individuals do not cross the specified approach boundary distance for the particular component. The approach boundary for low voltage cabinets allowed visual inspection of the cabinet interiors without impacting personnel safety.

Instead of re-performing the external visual inspections of the cabinets and panels for these components, the SWCs for deferred equipment which had been externally inspected prior to November 26, 2012 were modified as necessary to incorporate the results of internal inspections performed during RFO 2R28. These SWCs and the other SWCs completed for equipment deferred until RFO 2R28 can be found in Appendix B of this report.

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Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 5.2.5 Issues Identified during Seismic Walkdowns Table 5-2 at the end of this section provides a summary of issues identified during all of the equipment Seismic Walkdowns. The table includes an update on the status of the corrective actions for the concerns previously identified in the Reference 13 report, as well as a summary of the concerns identified during the RFO. Six additional observations were identified in completion of the deferred Seismic Walkdowns, as follows:

SWEL 1 Equipment Observations B25/LOAD SEQ CAB: Plastic terminal covers missing some screws BUS 26: Light fixture with open S-hook Cubicles 26-11, 26-12, 26-16, and 26-17 each have a knife BUS 26: switch anchored using 2 screws, despite there being four mounting holes. All other cubicles are mounted with four screws.

MCC 2K2: Drainage discharge tanks not restrained Duct work support in front of MCC 2KA BUS 2 missing one of eight base plate anchor nuts MCC 2L2: Piece of tie wire found under cell A5 at anchor bolts With the addition of these new concerns, the total number of concerns identified for the equipment Seismic Walkdowns is 17. In addition, two observations (associated with Control Panel B-2) identified during the seismic walkdowns are not in the site's CAP but are in the work management process for resolution, and are conservatively included in this report for tracking purposes. The new concerns identified during the outage were assessed for operability and it was concluded that the issues would not prevent the associated equipment from performing its safety-related function(s). 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. Seven Area Walk-Bys were completed after November 26, 2012. Therefore, a total of 36 Area Walk-Bys were performed for PINGP Unit 2. The Area Walk-By Checklists (AWC) completed before November 26, 2012 were submitted in Appendix C of Reference 13. The seven Area Walk-Bys completed after November 26, 2012 are provided in Appendix C of this report.

5-5

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 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 verify compliance with site procedures (Reference 38).

• General plant conditions were inspected to verify compliance with site procedures (Reference 39).

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/SprayInteractions 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.

One area of particular concern to the industry is threaded fire protection piping with long unsupported spans. If adequate seismic supports are present or there are isolation valves near the tanks or charging sources, flooding may not be a concern. Numerous failures have been observed in past earthquakes resulting from sprinkler head impact.

Less frequent but commonly observed failures have occurred due to flexible headers and stiff branch pipes, non-ductile mechanical couplings, seismic anchor motion and failed supports.

Examples where seismically-induced flooding/spray interactions could occur include the following:

• Fire protection piping with inadequate clearance around fusible-link sprinkler heads 5-6

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

• 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, as applicable. No new seismically-induced flooding/spray interactions were identified during the Area Walk-Bys completed during RFO 2R28.

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 bus bars, which pass between the two, to short out against the grounded bus duct surrounding the bus bars 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. No new seismically-induced fire interactions were identified during the Area Walk-Bys completed during RFO 2R28.

5.3.3 Issues Identified during Area Walk-Bys During the Area Walk-Bys the SWEs identified several instances where the seismic housekeeping was not in accordance with site procedures. These instances were noted on the AWCs and the issues were entered into the site CAP. Table 5-3 at the end of this section provides a summary of the issues identified during the Area Walk-Bys. The Area Walk-Bys were designated with an identifier number, as the titles for the Area Walk-Bys contain SUNSI. The designations for the Area Walk-Bys are provided in Table C-1 of Appendix C of this report. The designations for the Area Walk-Bys performed prior to November 26, 2012 were provided in Table C-1 of the Reference 13 report.

In total, 25 concerns were identified during the Area Walk-Bys and entered into the site's CAP or work management system. One concern was identified during the RFO 2R28 5-7

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report walkdowns (loose anchor on a non-safety-related HVAC duct floor support). This new concern was entered into the CAP and assessed for operability. 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.

Table 5-2: Prairie Island Unit 2 SWC CAP Status Equipment Description of Issue CAP# Status ID Closed to CAP 22DDCLP, light bar above pump has one open S-hook 1352001 and 245-392 (top part of S). Could swing down and hit pump, no 1351884 Work Request concerns for pump damage. Validate open S-hook and (WR) 83533, both write work request to correct. of which are complete.

Both of the "S" hooks holding the light fixture above the 22CC pumps are open. The power cord is taped and Closed to WR 245-122 seems to be able to support the light fixture. The light 1351916 83541, which is fixture is in contract with the "L"column and it is complete.

possible the light may break during seismic motion.

The CC Pump collection barrel is tied with rope to the Closed to WR 245-122 Unistrut. The barrel has a note attached that 1351901 83539, which is references CAP 1317022 and WO 74792. complete.

There is duct tape on the bottom of the rigging beam 245-122 above the CC pump. It is a housekeeping issue, and 1351913 Closed.

not a seismic concern.

WRs 84434, Multiple open "S" hooks for lighting fixtures were 83556, and 83533, Multiple identified request was during the Seismic initiated Walkdowns.

to track all An action of these occurrences 1352001 and are WO 465427 associated and perform an extent of condition. with this observation.

WR 84674 and There are missing cap nuts on the south side of the WO 467408 are 55320 cabinet. This is a maintenance issue and not a seismic 1356613 associated with issue. this observation, and are complete.

WR 101195 is B-2 Duct tape was identified behind Panel B-2 at about 8' N/A associated with high between the CVCS letdown and RHR labels. this observation.

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Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table 5-2: Prairie Island Unit 2 SWC CAP Status Equipment Description of Issue CAP# Status ID There is a bent back cover plate for the CVCS letdown WR 84959 and B-2 monitor. It is located at about 10' high near the CVCS N/A WO 471054 are letdown label. The cover plate is non-structural and is associated with not an adverse seismic condition. this observation.

The following housekeeping items were identified:

Duct tape was found on the side of the first monitor, Closed to WR E-2 about 8' high on the generator controls. A broken tie 1352954 83785, which is wrap is inside E-2 and pinned to a diagonal support. A complete.

tie wrap was found on the edge of a HVAC duct exhaust above E-2.

In addition to the foreign material, the pig tail of a cable WR 84837 and E-2 with a multi-pin connector was found stored on top of 1357129 WO 467495 are the box. It is not a seismic concern, but it is associated with recommended that the site evaluate the condition. this observation.

WR 83890 and EM-B2 A mounting screw was discovered missing inside the 1353340 WO 465970 are back of this panel in one of the electronic modules. associated with this observation.

WR 84626 and The rod hanger for piping below the valve is missing WO 467183 are MV-32384 one bolt. This is not a seismic issue for the valve, but 1356520 aOciate requires evaluation. this observation.

WRs 83645, 83646, and WOs PNL 22 The counterweight of the door pulley system may strike 1352343 465563, 465564 panel PNL 22. are associated with this observation.

As documented in WR 83615 and WO 465451, further walkdowns PNL 261 The upper left 3/8" diameter shell expansion anchor 1352221 confirmed the PNL 261 ~~~~has sheared off.1321 cofreth fourth anchor was present. No further actions were required.

5-9

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table 5-2: Prairie Island Unit 2 SWC CAP Status Equipment Description of Issue CAP# Status ID WR 96103 and B25/LOAD Interior of the cabinet was inspected. Itwas noted that WO 489148 are SEQ CAB some small plastic terminal covers were missing some 1401059 associated with screws. this observation.

Cubicles 26-11, 26-12, 26-16, and 26-17 have a knife switch anchored using 2 screws, despite there being 4 mounting holes. All other cubicles are mounted with 4 BUS 26 screws. Vendor review of the vendor-assembled and - 1405313 Closed.

supplied equipment determined that the two screws in the various configurations found in the field were sufficient to meet seismic requirements.

The 300 gallon tank collecting discharge from the 1" copper drain line is on the floor next to a 55 gallon MCC 2K2 barrel on the floor. These are not tied down and in a 1352563 Closed.

seismic event these may break or tip over and cause flooding in the area.

WR 83731 and There is a missing nut for one of the 8 anchors on the WO 46566 are MCC 2K2 base plate for the ductwork support in front of MCC 1352623 WO 465665 are 2KA BS 2.associated with 2KA BUS 2. this observation.

A small piece of tie wire was found under the cell A5 at MCC 2L2 the anchor bolts. It is a housekeeping concern, and not 1352321 Closed.

a seismic issue.

5-10

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table 5-3: Prairie Island Unit 2 Area Walk-by CAP Status Area Walk-by Description of Issue CAP# Status Designation One of the two floor brackets for the unistrut that supports the component cooling motor WR 83865 and WO power cables appears to be bent and the 1353327 465979 are associated anchor is loose. There is a tygon tube wedged with this observation.

under the corner.

Two drums are present under the component cooling heat exchanger to collect leak off. The Closed to WR 83853, drums are poorly tied off by rope to a small 1353280 which is complete.

copper drain line for the 11 component cooling pump unit cooler.

A top cover plate wing nut is missing from the 2RE-39 radiation monitor. There is also a WR 83571 and WO 2 loose screw on the side door cover. The 1352076 471191 are associated monitor is resting on the floor near the wall, and with this observation.

is located between the 22 component cooling pump and the stairs to the upper level.

Next to the pressure gauge P1-18249, there is a portable cord reel supported on the wall by a pin. Since the cord is free to rotate, the reel WR 83779 and WO could swing in a seismic event and potentially 1352923 465931 are associated impact the valve and tubing of the pressure with this observation.

gauge. Work request has been initiated to either secure the portable cord reel from movement or re-locate.

Radiation monitor DRM-2 is attached magnetically to electrical panel 2R1A54. The The monitor was magnetic base may not be strong enough to relocated and secured prevent the monitor from falling and impacting 1352792, under 1352792.

the pressure gauge P1-1 8249 or associated 3 tubing. Two action requests (AR) in the CAP 1352586 and The enhancements to were issued - one to evaluate long term out of 1397910 Radiation Protection service time for the radiation monitor and the guidance are currently second one to evaluate any potential trace ar 1352586.

procedures discrepancies in the deficiencies in the installation of portable radiation monitors.

5-11

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table 5-3: Prairie Island Unit 2 Area Walk-by CAP Status Area Walk-by Description of Issue CAP# Status Designation The guard cover on 22 safety injection (SI) pump coupling has two loose nuts for the bracket attached to the foundation of the SI pump. The bolts are effective to withstand 1352699 Closed to WR 83742, seismic loads. The coupling guard will remain which is complete.

in place during a seismic event. It is seismically acceptable, but the loose bolts should be tightened.

An oil can is sitting on the pipe support for MV- WR 83746 and WO 32185. There was no holder found for storing 1352727 346607 are associated the can, which is against the site's seismic with this observation.

housekeeping procedure.

A steam heating line was found tie wrapped to the line that includes the 2-RCCH-538 support. 1352959 Closed to WR 83786.

The tie wrap is a poor housekeeping practice, and should be removed.

The wrench hanging from 2MS-27-2 is a potential hazard to SOV-33266 and SV-33264. Closed to WR 83607, 9 The recommendation is to re-locate the wrench 1352195 which is complete.

to a height lower than the SOV elevation, so that is no longer a potential hazard.

Multiple open "S" hooks for lighting fixtures were identified during the Seismic Walkdowns. WRs 84434, 83556, and An action request was initiated to track all of 1352001 83533, and WO 465427 Multiple these occurrences and perform an extent of are associated with this condition. See Appendix F for all open "S" observation.

hook observations.

After further evaluation by plant engineering, it was determined that the safety classification of this indicator may not meet the requirements of the plant's equipment classification procedure.

20 PI-11979 is currently classified as non-safety 1352398 Closed to EC 20977.

related but it may need to be classified as safety related. CAP 1352398 has been initiated to evaluate the safety classification of the starting air indicator.

5-12

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table 5-3: Prairie Island Unit 2 Area Walk-by CAP Status Area Walk-by Description of Issue CAP# Status Designation The starting air indicator (PI-11979) for the 22 diesel driven cooling water pump has a bracket Closed to WR 83545 20 with provisions for four screws. However, only 1351936 and WO 466341, which two bolts are attaching the indicator to the are complete.

concrete wall.

WR 101184, 83793 and 23 The guard to belt drive on 121 instrument air 1352975 WO 466348 are (013-011) is missing two anchor bolts. associated with this observation.

WR 101183, 83796are and Chain fall for 2AF-13-1 is within eight inches of WO 465937 23 interacting with MCC 1A Bus 1. The chain fall 1352961 aO with thi needs to be restrained. observation.

The clamp of the conduit going into Panel 227 24 is loose. The clamp bolt is loosely attached to 1353370 Closed to WR 83887, the Unistrut location of the clamp, which is 6ft which is complete.

above the floor.

Closed to WR 83594 25 The 123 instrument air compressor guard is 1352154 and WO 465439, which missing a few anchors.

are complete.

The fire extinguisher (301) is on a short bent bracket. It is recommended that the bracket WR 83577 is associated gets bent back to normal (horizontal) position with this observation.

or is replaced.

WRs 83645 and 83646, The counterweight "S" hook is also open and W~s 45 and 26 or the counterweight could fall to the floorPL 1352343 465564 as d 22465564 are associated against PNL agaist 22 with this observation.

Duct tape is preventing a chain for a fluorescent light fixture from making contact WR 83605 and WO 27 with a conduit. This type of restraint is not 1352192 465449 are associated necessary and should be removed. It is a with this observation.

housekeeping issue and not a seismic concern.

5-13

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table 5-3: Prairie Island Unit 2 Area Walk-by CAP Status Area Walk-by Description of Issue CAP# Status Designation There are lighting diffusers tied off to the 29 support grid. Unit 1 and Unit 2 "C"panels have 1352209 Closed.

a fluorescent light fixture on chains too close (within 1-2") to the panel.

Unit 1 and Unit 2 "E" panels have side panels Closed to WR 83579, 29 that have slid out of position. This is a 1352102 which is complete.

housekeeping issue and not a seismic concern.

Fire extinguisher bracket 224 has a rotated 29 bracket (into the insulation) and should be N/A WR 83584 initiated.

repaired.

The filing cabinets adjacent to the main control 29 board in both Unit 1 and Unit 2 are close to the 1357683 Closed.

main control board.

The cart adjacent to the Protection Systems III 29 and the cart adjacent to cabinets RPI-1, -2, and 1357686 Closed.

-3 in Unit 1 are close to the equipment. The chain is not used to restrain the carts.

A loose anchor was identified on an HVAC duct WR 96286 and WO 2R28-2 floor support. The support was for non-safety 1401822 489992 are associated duct which would not impact other equipment. with this observation.

5-14

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal 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 plant's CAP where it will be determined whether 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 plant'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.

In Reference 11, NSPM provided additional information on the process followed for determining potential adverse seismic conditions and dispositioning observations identified as part of the seismic walkdown effort. This information was provided in response to the NRC's Requests for Additional Information from Reference 43.

6-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal 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) as well as 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 that were 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.

On October 23, 2008, the NRC Staff transmitted a Request for Additional Information (RAI) to NSPM as part of their review of PINGP plant license renewal application (Reference 5). The NRC's RAI "SAMA 3.c" requested the following information:

"As stated in the IPEEE seismic analysis, several potential seismic outliers were dispositioned through an analysis process which determined that the impacted function was not required or could be recovered, or that an alternate means for performing the associated function was available... For those outliers stated as being resolved through the closure of USI A-46 (IPEEE Section A.2.4.1.1), confirm that all corrective actions have been completed, and that their use is supported by procedures and training, as appropriate." (Reference 5)

NSPM provided a response to this RAI in a letter dated November 21, 2008 (Reference 40). In its response, NSPM stated that components listed in Section A.2.4.1.1 of PINGP IPEEE provide a summary of the SQUG outliers that pertain to the IPEEE scope. The NSPM RAI response also noted that in a letter from the NRC to Northern States Power dated August 5, 1998, Resolution of Unresolved Safety Issue (USI) A-46 for PINGP, Units 1 and 2 (TAC NOS. M69474 and M69475), the NRC issued a Safety Evaluation stating that the NRC had received notification that all outliers had been resolved, except for four equipment outliers. NSPM had notified the NRC of equipment outliers, resolution descriptions, and resolution timeline, if not already completed, in Attachment 2 of an RAI response letter sent to the NRC from NSPM dated November 17, 1997 (Reference 41). In this 1997 letter, NSPM committed to resolve the four remaining equipment outliers during PINGP Unit 2 outage in December 1998 and PINGP Unit I outage in May 1999.

Of those four remaining equipment outliers, three (3) were related to components listed in section A.2.4.1.1 of the PINGP IPEEE. The equipment included control valves CV-39409, CV-39401, and Motor Control Center MCC-2LA2. The actions taken to resolve the three outliers are described below in Table 7-1. Per the work completed as described below, all outliers identified in Section A.2.4.1.1 of PINGP IPEEE have been 7-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report resolved. Aside from this completed work, no additional procedure changes or training is required to close the identified outliers.

Table 7-1: Prairie Island IPEEE Seismic Vulnerabilities Equipment Potential Failure Mode Resolution Date Description Completed Control valve CV-39409 was The airline to valve CV-39409 was identified as an outlier because relocated such that the airline is 1 R20 refueling CV-39409 contact with surrounding conduits greater sh ttwo (2) inches from other outage in May could break the solenoid tap electrical conduits in the area. of 1999 connection.

The airline and associated solenoid valve for CV-39401 were rerouted so Control valve CV-39401 was that the airline and solenoid valve are identified as an outlier because aexisting minimum of two Also, inchestheaway from 1R20 outagerefueling in May conduits. electrical CV-39401 contact with surrounding conduits junction box associated with the of 1999 could break the solenoid tap solenoid valve for CV-39401 was relocated such that the box is greater than two inches from other electrical conduits in the area.

Motor Control Center MCC-2LA2 was identified as an outlier because New angle support braces were 2R19 refueling it was observed that the MCC installed at the base of MCC-2LA2 to outage in rocked about its weak axis when increase the structural stability of the November of bumped, making the welding at the MCC. 1998 base suspect.

7-2

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 8

Peer Review A peer review team consisting of four (4) individuals was assembled and peer reviews were performed in accordance with Section 6, PeerReviews, 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 and the summary Peer Review Report is provided in Appendix D of this report.

8-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 9

References Reference drawings related to SWEL items that were used as part of the seismic walkdown effort are provided in the Seismic Walkdown Checklists and if applicable, in the Area Walk-By Checklists.

1. EPRI Technical Report 1025286, "Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3:

Seismic," dated June 2012.

2. Prairie Island Nuclear Generating Plant Updated Safety Analysis Report (USAR), Revision 32.

3. NSP (M.D. Wadley) Letter to NRC, "Response to Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Issue (USI) A-46," dated November 20, 1995.

4. Pioneer Service & Engineering Co. Report JAB-PS-02, "Prairie Island Nuclear Generating Plant Earthquake Analysis of the Reactor-Auxiliary-Turbine Building", dated November 29, 1968. (not used)

5. NRC Letter to NSPM, "Request for Additional Information Regarding the Analysis of Severe Accident Mitigation Alternatives for Prairie Island Nuclear Generating Plant, Units 1 and 2," dated October 23, 2008, ADAMs Accession No. ML082950604.

6. 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," dated March 12, 2012, ADAMS Accession No. ML12056A046.

7. John A. Blame & Associates, Engineers, "Prairie Island Nuclear Generating Plant Earthquake Analysis: Reactor-Auxiliary-Turbine Building Response Acceleration Spectra," JAB-PS-04, February 16, 1971. (not used)

8. NRC Letter, "Endorsement of Electric Power Research Institute (EPRI) Draft Report 1025286, 'Seismic Walkdown Guidance,"' dated May 31, 2012, ADAMS Accession No. ML12145A529.

9. NSPM Letter to NRC, "PINGP Unit 2 - Proposed Resolution of the Remaining Seismic Walkdowns Associated with NRC Request for 9-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 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," dated September 12, 2013, ADAMS Accession No. ML13259A027.

10. NSPM Letter to NRC, "Prairie Island 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, ADAMS Accession No. ML12192A207.

11. NSPM Letter to NRC , "Prairie Island Nuclear Generating Plant, Units 1 and 2, Response to Requests for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns," dated November 27, 2013, ADAMS Accession No. ML13333B457.

12. NRC Memorandum, "Summary of the May 7, 2013, Public Conference Call on the Delayed Inspection Items Associated with Japan Lessons Learned Near-Term Task Force Recommendation 2.3 Seismic Walkdowns," dated June 5, 2013, ADAMS Accession No. ML13136A003.

13. NSPM Letter to NRC, "PINGP Unit 2 - 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," dated November 26, 2012, ADAMS Accession No. ML12334A470.

14. ACI 318-71, 77, 83, Building Code Requirements for Reinforced Concrete

15. ACI 301, Specifications for Structural Concrete for Buildings

16. ACI 347, Recommended Practice for ANSI A 145.1 Concrete Formwork

17. ACI 305, Recommended Practice for Hot ANSI A 170. 1 Weather Concreting

18. ACI 211.1, Recommended Practicefor Selecting Proportionsfor Normal Weight Concrete

19. ACI 304, Recommended Practice for Measuring, Mixing, Transporting,and placing concrete

20. ACI 315, Manual of StandardPracticefor DetailingReinforced Concrete Structures

21. ACI 306, Recommended Practicefor Cold Weather Concreting

22. ACI 309, Recommended Practicefor Consolidationof Concrete 9-2

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

23. ACI 308, Recommended Practicefor Curing Concrete

24. ACI 214, Recommended Practicefor ANSI A146.1 Evaluation of Compression Test Results of Field

25. ACI 311, Recommended Practicefor Concrete Inspection

26. ACI 304, PreplacedAggregate Concrete for Structuraland Mass Concrete

27. Report by ACI Committee 304, PlacingConcrete by Pumping Method

28. AISC-69,78, Specification for the Design, Fabrication,and Erection of StructuralSteel for Building

29. AWS D 1.1, Structural Welding Code

30. ASME Boiler & Pressure Vessel Code,Section III -

i.ASME-1971, S73 Division 1, Subsection NE ii. ASME-1974, S75 Division 1, Subsection NF iii.ASME-1973 Division 2, Proposed Standard Code for Concrete Reactor iv. Vessels and Containments Issued for Trial Use and Comments

v. ASME-1980 Division 2, CC 6000 vi. ASME-1992 1992 Addenda, Division 1,Section XI, Subsection IWL, IWE

31. American Public Health Assoc. (APHA) Test Methods Sulphides in Water, Standard Methods for the Examination of Water and Waste Water

32. ASTM Annual Books of ASTM Standards

33. CRSI, MSP-1, Manual of Standard Practice

34. ANSI N45.2.5, ProposedSupplementary Q.A. Requirements for Installation, Inspection and Testing of StructuralConcrete and StructuralSteel During Construction Phase of Nuclear PowerPlants

35. CRD, Chief of Research and Development Standards,Department of the Army, Handbook for Concrete and Cement Volume I and II, Corps of Engineers U.S. Army

36. ACI-349-76, 85, Code Requirements for Nuclear Safety Related Concrete Structures

37. AISI, Specification for design of cold-formed steel structuralmembers 9-3

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

38. Prairie Island Nuclear Generating Plant Maintenance Procedure D80, Rev.

27, "Scaffolding, Ladders and Cable Tray Platforms."

39. Prairie Island Nuclear Generating Plant Seismic Housekeeping Procedure H41, Rev. 13, "Control of Temporary Structures and Equipment."

40. NSPM (M.D. Wadley) Letter to NRC, "Responses to NRC Requests for Additional Information Dated October 23, 2008 Regarding Application for Renewed Operating Licenses," dated November 21, 2008, ADAMS Accession No. ML083370505.

41. NSPM (J.P. Sorensen) Letter to NRC, "Response to Request for Additional Information on the Prairie Island Nuclear Generating Plant, Units 1 and 2, Resolution of Unresolved Safety Issue A-46 (TAC Nos. M69474 and M69475)," dated November 17, 1997.

42. NRC Memorandum, "Summary of the August 1, 2013, Public Conference Call on the Delayed Inspection Items Associated with Japan Lessons Learned Near-Term Task Force Recommendation 2.3 Seismic Walkdowns,"

dated August 14, 2013, ADAMS Accession No. ML13218B361.

43. NRC Letter, "Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns," dated November 1, 2013, ADAMS Accession No. ML13304B418.

9-4

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report A

Equipment Lists Appendix A contains the equipment lists that were developed as part of theequipment selection for the SWEL. Note that the Base List 2 and SWEL 2 associated with the spent fuel pool equipment are not included in this report, since they are included as part of the PINGP Unit 1 seismic walkdown submittal report.

The following contents are found in Appendix A:

Table A-I, Prairie Island Unit 2 - Base List 1 A-2 Table A-2, Prairie Island Unit 2 - SWEL 1 A-42 A-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report A.1 Equipment Selection - Base List 1 Table A-1 is a list of the equipment coming out of Screen #2 and entering Screen #3.

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."

Table A-I: Prairie Island Unit 2 - Base List I Equipment Tag Description 17705 22 AFP LO SUCT PRESS TRIP PS 17778 21 AFP LO DISCH PRESS TRIP PS 17779 21 AFP LO SUCT PRESS TRIP PS 31060 22 AFWP MN STM THTL CV 31230 2 REAC CLNT LOOP PRZR LTDN LN ISOL CV A 31234 2 REAC CLNT LOOP PRZR PWR OPRTD RLF CV A 31279 2 REAC CLNT LOOP PRZR LTDN LN ISOL CV B 32019 LOOP A MN STM TO 22 TD AFWP MV 32020 LOOP B MN STM TO 22 TD AFWP MV 32046 21 SGB ISOL MV 32147 21 FC CLG WTR RTRN ISOL MV A 32148 21 FC CLG WTR RTRN ISOL MV B 32153 23 FC CLG WTR RTRN ISOL MV A 32154 23 FC CLG WTR RTRN ISOL MV B 32194 2 REAC EXCS LTDN LINE ISOL MV A 32210 2 REAC EXCS LTDN LINE ISOL MV B A-2

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List 1 Equipment Tag Description 32247 22 TD AUX FW TO 22 5TM GEN MV 32248 21/22 AUX FW TO 21 STM GEN ISOL MV 32249 21/22 AUX FW TO 22 STM GEN ISOL MV 32334 21 AUX BLDG CLG WTR RTRN HDR ISOL MV 32383 21 AFWP DSCH TO 21 STM GEN MV 32384 21 AFWP DSCH TO 22 STM GEN MV 32386 21 FC CLG WTR INLT ISOL MV 33251 21 REGEN HT EXGR CHG LN OUTL SV 33258 21 LOOP A MN STM HDR SV A 33259 21 LOOP A MN STM HDR SV B 33260 21 LOOP A MN STM HDR AIR EXHT SV A 33261 21 LOOP A MN STM HDR AIR EXHT SV B 33263 22 LOOP B MN STM HDR SV A 33264 22 LOOP B MN STM HDR SV B 33265 22 LOOP B MN STM HDR AIR EXHT SV A 33266 22 LOOP B MN STM HDR AIR EXHT SV B 33490 2 REAC CLNT LOOP PRZR LTDN LN ISOL SV 33491 2 REAC CLNT LOOP PRZR LTDN LN ISOL SV 2 33492 21 MD AUX FW PMP RCRC/LUBE OIL CLG SV 33493 22 TD AUX FW PMP RCRC/LUBE OIL CLG SV A-3

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List I Equipment Tag Description 33498 2 DSL GEN RM OUTS AIR B TRN DMPR SV 33695 21 CLASS I ROOF EXHT FAN DMPR SV 33696 21 SCVNG & COMTN AIR DMPR SV A 33764 2 REAC CLNT LOOP PRZR PWR OPRTD RLF VLV A SV 33829 21 SCVNG & COMBTN AIR DMPR SV B 37415 21; 23 FCU CLG WTR SUPPLY SV 37423 21; 23 FCU CLG WTR RETURN SV 50000 D5 DSL GEN BENCHBOARD 50200 D5 DSL GEN VERTICAL PANEL 55320 D5 DSL GEN ENG 1 AUX DESK 55420 D5 DSL GEN ENG 2 AUX DESK 55820 D6 DSL GEN ENG 1 AUX DESK 55920 D6 DSL GEN ENG 2 AUX DESK 60000 D6 DSL GEN BENCHBOARD 60200 D6 DSL GEN VERTICAL PANEL 70350 22 DD CLWP LCL PNL 053-322 22 COOLING WATER PUMP DIESEL OIL DAY TANK 2 CRDM/REG 5KVA SOLA REGULATOR 2 CRDM/XFMR CRDM MAIN CONTROL TRANSFORMER 201/XFMR 201 TRANSFORMER A-4

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description 202/XFMR 202 TRANSFORMER 21 AUX FW PUMP 21 AUXILIARY FEEDWATER PUMP MOTOR DRIVEN 21 BATT 21 BATTERY 21 BATT CHG 21 BATTERY CHARGER 21 BATT CHG/XFM 21 BATTERY CHARGER TRANSFORMER 21 BCM/XFMR BORON CONC MEAS TRANSFORMER 21 FUSE BOX 21 FUSE BOX 21 IBA/XFMR INTERRUPTABLE BUS AUX TRANSFORMER 21 INV 21 INVERTER 211M/XFMR 211M TRANSFORMER 211M/XFMR 211M TRANSFORMER 212M/XFMR 212M TRANSFORMER 212M/XFMR 212M TRANSFORMER 21-3/CT1 21 FW PUMP CURRENT TRANSFORMER 21-3/CT2 21 FW PUMP CURRENT TRANSFORMER 21-3/PT1 21 FW PUMP POTENTIAL TRANSFORMER 213-011 22 CL PUMP DIESEL START-UP AIR COMPRESSOR 217-111 21 AUXILIARY FEEDWATER PUMP LUBE OIL COOLER 217-112 22 AUXILIARY FEEDWATER PUMP LUBE OIL COOLER 217-121 22 CL PUMP GEAR OIL COOLER A-5

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List 1 Equipment Tag Description 217-201 D5 1A L/O COOLER 217-202 D5 1B L/O COOLER 217-203 D5 2A L/O COOLER 217-204 D5 2B L/O COOLER 217-205 D6 1A L/O COOLER 217-206 D6 1B L/O COOLER 217-207 D6 2A L/O COOLER 217-208 D6 2B L/O COOLER 217-211 D5 ENG 1 GOV OIL COOLER 217-212 D5 ENG 2 GOV OIL COOLER 217-213 D6 ENG 1 GOV OIL COOLER 217-214 D6 ENG 2 GOV OIL COOLER 21MR 21 MISCELLANEOUS RELAY RACK 21MSAR 21 MISC SYSTEMS AUXILIARY RACK 21RM RADIATION MONITORING RACK 21RM 22 BATT 22 BATTERY 22 BATT 22 BATTERY (& BATTERY RACK) 22 BATT CHG 22 BATTERY CHARGER 22 BATT CHG/XFM 22 BATTERY CHARGER TRANSFORMER 22 FUSE BOX 22 FUSE BOX A-6

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description 22 INV 22 INVERTER 221M/XFMR 221M TRANSFORMER 222M/XFMR 222M TRANSFORMER 22-3/CT1 22 FW PUMP CURRENT TRANSFORMER 22-3/CT2 22 FW PUMP CURRENT TRANSFORMER 22-3/PT1 22 FW PUMP POTENTIAL TRANSFORMER 22MR 22 MISCELLANEOUS RELAY RACK 23 INV 23 INVERTER 23-1/CT1 121 SCREENWASH PUMP CURRENT TRANSFORMER 23-1/CT2 121 SCREENWASH PUMP CURRENT TRANSFORMER 232-281 21 SCREENHOUSE ROOF EXHAUST FAN 232-291 21 SCREENHOUSE DIESEL COOLING SUPPLY FAN 232-421 21 D5 DSL RM COOLING FAN 232-422 22 D6 DSL RM COOLING FAN 232-441 21 D5 DSL GEN BLDG SPLY FAN 232-442 22 D6 DSL GEN BLDG SPLY FAN 232-443 23 D5 DSL GEN BLDG SPLY FAN 232-444 24 D6 DSL GEN BLDG SPLY FAN 232-451 21 D5 DSL GEN BLDG RETURN FAN 232-452 22 D6 DSL GEN BLDG RETURN FAN A-7

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description 232-453 23 D5 DSL GEN BLDG RETURN FAN 232-454 24 D6 DSL GEN BLDG RETURN FAN 232-461 D5 ENG 1 HT/LT RADIATOR FAN 1 232-462 D5 ENG 1 HT/LT RADIATOR FAN 2 232-463 D5 ENG 2 HT/LT RADIATOR FAN 1 232-464 D5 ENG 2 HT/LT RADIATOR FAN 2 232-465 D6 ENG 1 HT/LT RADIATOR FAN 1 232-466 D6 ENG 1 HT/LT RADIATOR FAN 2 232-467 D6 ENG 2 HT/LT RADIATOR FAN 1 232-468 D6 ENG 2 HT/LT RADIATOR FAN 2 23-3/CTI 21 CW PUMP CURRENT TRANSFORMER 23-3/CT2 21 CW PUMP CURRENT TRANSFORMER 23-3/PT1 21 CW PUMP POTENTIAL TRANSFORMER 23-4/CTl 21 CL PUMP CURRENT TRANSFORMER 23-4/CT2 21 CL PUMP CURRENT TRANSFORMER 234-031 D5 DIESEL GENERATOR 234-032 D6 DIESEL GENERATOR 234BT/PT1 234BT POTENTIAL TRANSFORMER 234BT/PT2 234BT POTENTIAL TRANSFORMER 235-081 22 CL PUMP DIESEL JACKET CLG HX A-8

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description 235-111 21 REGENERATIVE HEAT EXCHANGER 235-131 21 SEAL WATER HEAT EXCHANGER 235-201 D5 ENG 1 L/O PREHEATING HEAT EXCHANGER 235-202 D5 ENG 2 L/O PREHEATING HEAT EXCHANGER 235-203 D6 ENG 1 L/O PREHEATING HEAT EXCHANGER 235-204 D6 ENG 2 L/O PREHEATING HEAT EXCHANGER 23-6/CT1 21 HD PUMP CURRENT TRANSFORMER 23-6/CT2 21 HD PUMP CURRENT TRANSFORMER 23-7/CT1 23 HD PUMP CURRENT TRANSFORMER 23-7/CT2 23 HD PUMP CURRENT TRANSFORMER 23-8/CT1 203-205-207 STA AUX XFMR CURRENT TRANSFORMER 23-8/CT2 203-205-207 STA AUX XFMR CURRENT TRANSFORMER 23A INV/XFMR 23 INVERTER ALT SOURCE TRANSFORMER 23M INV/XFMR 23 INVERTER MAIN TRANSFORMER 23M/CT 23M CURRENT TRANSFORMER 23M/PT 23M POTENTIAL TRANSFORMER 23MR 23 MISCELLANEOUS RELAY RACK 24 INV 24 INVERTER 24-2/CT1 22 CW PUMP CURRENT TRANSFORMER 24-2/CT2 22 CW PUMP CURRENT TRANSFORMER A-9

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description 24-2/PT1 22 CW PUMP POTENTIAL TRANSFORMER 24-5/CT1 22 HD PUMP CURRENT TRANSFORMER 24-5/CT2 22 HD PUMP CURRENT TRANSFORMER 245-041 21 CHARGING PUMP 245-042 22 CHARGING PUMP 245-071 21 SI PMP 245-122 22 CC PMP 245-201 22 AUXILIARY FEEDWATER PUMP TURBINE DRIVEN 245-331 21 AUXILIARY FEEDWATER PUMP MOTOR DRIVEN 245-392 22 DD CLP 245-821 22 CL PUMP CNSTNT LUBE OIL PUMP 245-881 21 D5 FO STG TK XFER PUMP 245-882 22 D6 FO STG TK XFER PUMP 245-883 23 D5 FO STG TK XFER PUMP 245-884 24 D6 FO STG TK XFER PUMP 245-891 21 D5/D6 FO RCVG TK RECIRC PUMP 245-901 D5 ENG 1 ENG DRVN FO PUMP 245-902 D5 ENG 2 ENG DRVN FO PUMP 245-903 D6 ENG 1 ENG DRVN FO PUMP 245-904 D6 ENG 2 ENG DRVN FO PUMP A-I0

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List 1 Equipment Tag Description 245-911 D5 ENG 1 FO BACKUP PUMP 245-912 D5 ENG 2 FO BACKUP PUMP 245-913 D6 ENG 1 FO BACKUP PUMP 245-914 D6 ENG 2 FO BACKUP PUMP 245-921 D5 1A ENG DRVN L/O PUMP 245-922 D5 1B ENG DRVN L/O PUMP 245-923 D5 2A ENG DRVN L/O PUMP 245-924 D5 2B ENG DRVN L/O PUMP 245-925 D6 1B ENG DRVN L/O PUMP 245-926 D6 1B ENG DRVN L/O PUMP 245-927 D6 2A ENG DRVN L/O PUMP 245-928 D6 2B ENG DRVN L/O PUMP 245-931 D5 ENG 1 AC PRELUBE PUMP 245-932 D5 ENG 2 AC PRELUBE PUMP 245-933 D6 ENG 1 AC PRELUBE PUMP 245-934 D6 ENG 2 AC PRELUBE PUMP 245-941 D5 ENG 1 DC BU PRELUBE PUMP 245-942 D5 ENG 2 DC BU PRELUBE PUMP 245-943 D6 ENG 1 DC BU PRELUBE PUMP 245-944 D6 ENG 2 DC BU PRELUBE PUMP A-11

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List I Equipment Tag Description 245-971 D5 ENG 1 ENG DRVN HT CLNT PUMP 245-972 D5 ENG 2 ENG DRVN HT CLNT PUMP 245-973 D6 ENG 1 ENG DRVN HT CLNT PUMP 245-974 D6 ENG 2 ENG DRVN HT CLNT PUMP 245-981 D5 ENG 1 ENG DRVN LT CLNT PUMP 245-982 D5 ENG 2 ENG DRVN LT CLNT PUMP 245-983 D6 ENG 1 ENG DRVN LT CLNT PUMP 245-984 D6 ENG 2 ENG DRVN LT CLNT PUMP 245-991 D5 ENG 1 HT CLNT PREHTR CIRC PUMP 245-992 D5 ENG 2 HT CLNT PREHTR CIRC PUMP 245-993 D6 ENG 1 HT CLNT PREHTR CIRC PUMP 245-994 D6 ENG 2 HT CLNT PREHTR CIRC PUMP 24-6/CT1 204-206-209 STA AUX XFMR CURRENT TRANSFORMER 24-6/CT2 204-206-209 STA AUX XFMR CURRENT TRANSFORMER 246-011 22 CL PUMP DIESEL START-UP AIR RECEIVERS 246-031 D5 1A START AIR RECEIVER 246-032 D5 1B START AIR RECEIVER 246-033 D5 2A START AIR RECEIVER 246-034 D5 2B START AIR RECEIVER 246-035 D6 1A START AIR RECEIVER A-12

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description 246-036 D6 1B START AIR RECEIVER 246-037 D6 2A START AIR RECEIVER 246-038 D6 2B START AIR RECEIVER 24-7/CT A 21 CHILLER PH A CURRENT TRRANSFORMER 24-7/CT C 21 CHILLER PH C CURRENT TRANSFORMER 24-7/CT1 21 CHILLER CURRENT TRANSFORMER 24-7/CT2 21 CHILLER CURRENT TRANSFORMER 24-7/GND CT 21 CHILLER GND DET CURRENT TRANSFORMER 247-021 D5 ENG 1 HT CLNT PREHEATER 247-022 D5 ENG 2 HT CLNT PREHEATER 247-023 D6 ENG 1 HT CLNT PREHEATER 247-024 D6 ENG 2 HT CLNT PREHEATER 24A INV/XFMR 24 INVERTER ALT SOURCE TRANSFORMER 24M INV/XFMR 24 INVERTER MAIN TRANSFORMER 24M/CT 24M CURRENT TRANSFORMER 24M/PT 24M POTENTIAL TRANSFORMER 24MR 24 MISCELLANEOUS RELAY RACK 25 INV 25 INVERTER 25-2/CT1 202 STA AUX XFMR CURRENT TRANSFORMER 25-2/CT2 202 STA AUX XFMR CURRENT TRANSFORMER A-13

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description 25-3/CT1 22 CC PUMP CURRENT TRANSFORMER 25-3/CT2 22 CC PUMP CURRENT TRANSFORMER 253-011 21 PRESSURIZER RELIEF TANK 253-021 21 VOLUME CONTROL TANK 253-081 21 REFUELING WATER STORAGE TANK 253-331 21 D5 FO STORAGE TANK 253-332 22 D6 FO STORAGE TANK 253-333 23 D5 FO STORAGE TANK 253-334 24 D6 FO STORAGE TANK 253-361 21 D5 FO DAY TANK 253-362 22 D6 FO DAY TANK 253-371 D5 ENG 1 FO LEAKAGE TANK 253-372 D5 ENG 2 FO LEAKAGE TANK 253-373 D6 ENG 1 FO LEAKAGE TANK 253-374 D6 ENG 2 LEAKAGE TANK 253-401 D5 ENG 1 HT EXPANSION TANK 253-402 D5 ENG 2 HT EXPANSION TANK 253-403 D6 ENG 1 HT EXPANSION TANK 253-404 D6 ENG 2 HT EXPANSION TANK 253-411 D5 ENG 1 LT EXPANSION TANK A-14

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report ThhI~ A-I Pr~iri~ I~I~nd Unit 2 - Rasp List I Equipment Tag Description 253-412 D5 ENG 2 LT EXPANSION TANK 253-413 D6 ENG 1 LT EXPANSION TANK 253-414 D6 ENG 2 LT EXPANSION TANK 25-6/CT1 D2 EMERG GEN CURRENT TRANSFORMER 258-011 21 CLG WTR STRNR 26-0/CT1 21 AFW PUMP CURRENT TRANSFORMER 26-0/CT2 21 AFW PUMP CURRENT TRANSFORMER 26-2/CT1 D1 EMERG GEN CURRENT TRANSFORMER 262-441 D5 ENG 1 HT/LT RADIATOR 262-442 D5 ENG 2 HT/LT RADIATOR 262-443 D6 ENG 1 HT/LT RADIATOR 262-444 D6 ENG 2 HT/LT RADIATOR 26-5/CT1 21 CC PUMP CURRENT TRANSFORMER 26-6/CT1 201 STA AUX XFMR CURRENT TRANSFORMER 26-6/CT2 201 STA AUX XFMR CURRENT TRANSFORMER 266-011 D5 1A INBOARD AIR AFTERCOOLER 266-012 D5 1B INBOARD AIR AFTERCOOLER 266-013 D5 2A INBOARD AIR AFTERCOOLER 266-014 D5 2B INBOARD AIR AFTERCOOLER 266-015 D6 1A INBOARD AIR AFTERCOOLER A-15

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List 1 Equipment Tag Description 266-016 D6 1B INBOARD AIR AFTERCOOLER 266-017 D6 2A INBOARD AIR AFTERCOOLER 266-018 D6 2B INBOARD AIR AFTERCOOLER 266-021 D5 1A OBRD AIR AFTERCOOLER 266-022 D5 1B OBRD AIR AFTERCOOLER 266-023 D5 2A OBRD AIR AFTERCOOLER 266-024 D5 2B OBRD AIR AFTERCOOLER 266-025 D6 1A OBRD AIR AFTERCOOLER 266-026 D6 1B OBRD AIR AFTERCOOLER 266-027 D6 2A OBRD AIR AFTERCOOLER 266-028 D6 2B OBRD AIR AFTERCOOLER 269-031 21 SEAL WATER INJECTION FILTER 269-032 22 SEAL WATER INJECTION FILTER 269-061 21 SEAL WATER FILTER 269-062 22 SEAL WATER FILTER 269-301 D5 ENG 1 COMBUSTION AIR FILTER 269-302 D5 ENG 2 COMBUSTION AIR FILTER 269-303 D6 ENG 1 COMBUSTION AIR FILTER 269-304 D6 ENG 2 COMBUSTION AIR FILTER 27 INV 27 INVERTER A-16

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List 1 Equipment Tag Description 274-011 21 CONTAINMENT FAN-COIL UNIT 274-012 22 CONTAINMENT FAN-COIL UNIT 274-013 23 CONTAINMENT FAN-COIL UNIT 274-014 24 CONTAINMENT FAN-COIL UNIT 274-031 25 SAFEGUARD SWITCHGEAR FAN-COIL UNIT 274-032 26 SAFEGUARD SWITCHGEAR FAN-COIL UNIT 274-051 21 AUXILIARY FEEDWATER PUMP MOTOR FAN-COIL UNIT 274-061 21 COMPONENT COOLING PUMP MOTOR FAN-COIL UNIT 274-062 22 COMPONENT COOLING PUMP MOTOR FAN-COIL UNIT 278-011 D5 ENG 1 EXHAUST SILENCER 278-012 D5 ENG 2 EXHAUST SILENCER 278-013 D6 ENG 1 EXHAUST SILENCER 278-014 D6 ENG 2 EXHAUST SILENCER 27A INV/XFMR 27 INVERTER ALT SOURCE TRANSFORMER 27M INV/XFMR 27 INVERTER MAIN TRANSFORMER 27M/CT 27M CURRENT TRANSFORMER 27M/PT 27M POTENTIAL TRANSFORMER 28 INV 28 INVERTER 2AF-29-1 21 AUX FW PUMP SUCT RELIEF 2AF-29-2 22 AUX FW PUMP SUCT RELIEF A-17

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description 2AMR1 MISCELLANEOUS RELAY RACK 2AMR1 2ARP1 REACTOR PROTECTION RELAY RACK 2ARP1 2ARP2 REACTOR PROTECTION RELAY RACK 2ARP2 2ARP3 REACTOR PROTECTION RELAY RACK 2ARP3 2ARP4 REACTOR PROTECTION RELAY RACK 2ARP4 2ARP5 REACTOR PROTECTION RELAY RACK 2ARP5 2ASG1 SAFEGUARD RELAY RACK 2ASG1 2ASG2 SAFEGUARD RELAY RACK 2ASG2 2BI PROCESS PROTECTION RACK 2B1 2B2 PROCESS PROTECTION RACK 2B2 2BMR1 MISCELLANEOUS RELAY RACK 2BMR1 2BRP1 REACTOR PROTECTION RELAY RACK 2BRP1 2BRP2 REACTOR PROTECTION RELAY RACK 2BRP2 2BRP3 REACTOR PROTECTION RELAY RACK 2BRP3 2BRP4 REACTOR PROTECTION RELAY RACK 2BRP4 2BRP5 REACTOR PROTECTION RELAY RACK 2BRP5 2BSG1 SAFEGUARD RELAY RACK 2BSG1 2BSG2 SAFEGUARD RELAY RACK 2BSG2 2CL-25-1 22 DDCLP JACKET HX RELIEF 2CL-57-3 21 CONTAINMENT FAN COIL UNITS - RELIEF VLV A-18

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description 2CL-57-4 22 CONTAINMENT FAN COIL UNITS - RELIEF VLV 2CL-57-5 23 CONTAINMENT FAN COIL UNITS - RELIEF VLV 2CL-57-6 24 CONTAINMENT FAN COIL UNITS - RELIEF VLV 2CVC1 PROCESS CONTROL RACK 2CVC1 2CVC2 PROCESS CONTROL RACK 2CVC2 2CVCS1 PROCESS CONTROL RACK 2CVCS1 2CVCS2 PROCESS CONTROL RACK 2CVCS2 2DG-3 D2 JACKET CLNT HTR RELIEF 2EG-15-2 D5 1B START AIR RCVR RELIEF 2EMA DISTRIBUTION PANEL 2EMA 2EMB DISTRIBUTION PANEL 2EMB 2FE-115 21 REAC CLNT PMP SL WTR INJ F ORIF 2FE-116 22 REAC CLNT PMP SL WTR INJ F ORIF 2FT-115 21 REAC CLNT PMP SL WTR INJ F XMTR 2FT-116 22 REAC CLNT PMP SL WTR INJ F XMTR 2FT-464 MN STM FR 21 STM GEN CHNNL I RED F XMTR 2FW PROCESS CONTROL RACK 2FW 2HC-142 21 CHG LINE FLOW CONT STA 2HC-428A 21 CHARGING PUMP SPEED CONT STA 2HC-428B 22 CHARGING PUMP SPEED CONT STA A-19

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List I Equipment Tag Description 2HC-468 21 MN STM SAF RLF TO ATM LOOP A CONT STA 2HC-478 21 MN STM SAF RLF TO ATM LOOP B CONT STA 2HSC-428D 21 CHG PMP SPD CONT STA 2HSC-428E 22 CHG PMP SPD CONT STA 2L1-112 21 VOL CONT TNK LI 2LI-141B 21 VOL CONT TNK LI 2LQ-112 21 VOL CONT TNK LVL PWR SPLY 2LQ-141 21 VOL CONT TNK LVL PWR SPLY 2LQ-426 PRESSURIZER LVL TRANS PWR SPLY 2LQ-427 PRESSURIZER LVL TRANS PWR SUPPLY 2LQ-428 PRESSURIZER LVL TRANS PWR SPLY 2LT-112 21 VOL CONT TNK LVL XMTR 2LT-141 21 VOL CONT TNK LVL XMTR 2LT-426 2 REAC CLNT LOOP PRZR (CHNNL I-RED) LVL XMTR 2LT-427 2 REAC CLNT LOOP PRZR (CHNNL II-WHI) LVL XMTR 2LT-428 2 REAC CLNT LOOP PRZR (CHNNL III-BLU)LVL XMTR 2LT-461 21 STM GEN LOOP A CHNNL I-RED LVL XMTR 2LT-487 21 STM GEN LOOP A WR LVL XMTR 2LT-488 22 STM GEN LOOP B WR LVL XMTR 2LT-751 21 RX VSL HEAD UPPER RNG TRN A D/P XMTR A-20

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List 1 Equipment Tag Description 2LT-753 21 RX VSL HEAD DYNAMIC RNG TRN A D/P XMTR 2LT-761 22 RX VSL HEAD UPPER RNG TRN B D/P XMTR 2LT-762 U2 RVLIS HEAD FULL RANGE TRN B D/P XMTR 2LT-763 22 RX VSL HEAD DYNAMIC RNG TRN B D/P XMTR 2LT-920 21 RWST LVL XMTR 2LT-921 21 RWST LVL XMTR 2NE-51 EXCORE DETECTION TRN A DETECTOR ASSY 2NE-52 EXCORE DETECTION TRN B DETECTOR ASSY 2NI-51A EXCORE DETECTION TRN A SHUTDOWN MONITOR 2NI-52A EXCORE DETECTION TRN B SHUTDOWN MONITOR 2NM-51 EXCORE DETECTION TRN A AMPLIFIER 2NM-51A EXCORE DETECTION TRN A OPTICAL ISOLATOR 2NM-52 EXCORE DETECTION TRN B AMPLIFIER 2NR1 NUCLEAR INSTRUMENTATION RACK 2NR1 2NR2 NUCLEAR INSTRUMENTATION RACK 2NR2 2NR3 NUCLEAR INSTRUMENTATION RACK 2NR3 2NR4 NUCLEAR INSTRUMENTATION RACK 2NR4 2PQ-429 2 REAC CLNT LOOP PRZR (CHNNL 1-RED) P PWR SPLY 2PQ-430 2 REAC CLNT LOOP PRZR (CHNNL II-WHI) P PWR SPLY 2PQ-431 2 REAC CLNT LOOP PRZR (CHNNL III-BLU) P PWR SPLY A-21

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List I Equipment Tag Description 2PQ-468 STM GEN PRESS XMTR PWR SPLY 2PQ-478 STM GEN PRESS XMTR PWR SPLY 2PQ-482 STM GEN PRESS XMTR PWR SPLY 2PQ-483 STM GEN PRESS XMTR PWR SPLY 2PT-429 2 REAC CLNT LOOP PRZR (CHNNL I-RED) P XMTR 2PT-430 2 REAC CLNT LOOP PRZR (CHNNL II-WHI) P XMTR 2PT-431 2 REAC CLNT LOOP PRZR (CHNNL III-BLU) P XMTR 2PT-468 21 STM GEN MN STM HDR (CHNNL I-RED) P XMTR 2PT-469 21 STM GEN MN STM HDR (CHNL II-WHI) P XMTR 2PT-478 22 STM GEN MN STM HDR (CHNNL III-BLU) P XMTR 2PT-479 22 STM GEN MN STM HDR (CHNL IV-YEL) P XMTR 2PT-482 21 STM GEN MN STM HDR (CHNNL III-BLU) P XMTR 2PT-483 22 STM GEN MN STM HDR (CHNNL I-RED) P XMTR 2PZRHTRA/CT A 2 PRZR HTR GRP A CURRENT XFMR A 2PZRHTRA/CT C 2 PRZR HTR GRP A CURRENT XFMR C 2PZRHTRA/PT A 2 PRZR HTR GRP A POTENTIAL XFMR A 2PZRHTRA/PT C 2 PRZR HTR GRP A POTENTIAL XFMR C 2PZRHTRA/XFMR 2 PRZR HTR GRP A TRANSFORMER 2PZRHTRB/CT A 2 PRZR HTR GRP B CURRENT XFMR A 2PZRHTRB/CT C 2 PRZR HTR GRP B CURRENT XFMR C A-22

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List 1 Equipment Tag Description 2PZRHTRB/PT A 2 PRZR HTR GRP B POTENTIAL XFMR A 2PZRHTRB/PT C 2 PRZR HTR GRP B POTENTIAL XFMR C 2PZRHTRB/XFMR 2 PRZR HTR GRP B TRANSFORMER 2111 PROCESS PROTECTION RACK 2R1 2R2 PROCESS PROTECTION RACK 2R2 2RC-10-1 PRESSURIZER RELIEF VALVE 2RC-10-2 PRESSURIZER RELIEF VALVE 2RCS1 PROCESS CONTROL RACK 2RCS1 2RC52 PROCESS CONTROL RACK 2RCS2 2RH-8-1 RHR HOT LEG SUCTION RELIEF 2RM RADIATION MONITORING RACK 2RM 2RM3 U2 AREA RADIATION MONITORING RACK 2RP1 ROD POSITION INDICATOR RACK 2RP1 2RP2 ROD POSITION INDICATOR RACK 2RP2 2RP3 ROD POSITION INDICATOR RACK 2RP3 2SA PROCESS CONTROL RACK 2SA 2SC-428A 21 CHG PMP SPEED CONTR 2SC-428B 22 CHG PMP SPEED CONTR 2SD PROCESS CONTROL RACK 2SD 2SI-26-1 RHR HX TO 2 RX VESSEL LOOP B RELIEF VALVE TO PRT A-23

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List 1 Equipment Tag Description 2SPT-428A 21 CHG PMP SPEED CONT RNG EXPANDING XMTR 2SRR-428A 21 CHG PMP SPEED CONT PRESS REG 2SRR-428B 22 CHG PMP SPEED CONT PRESS REG 2ST-428A 21 CHG PMP SPEED CONT SPEED XMTR 2ST-428B 22 CHG PMP SPEED CONT SPEED XMTR 2T3/24407 21 CHILLER LOAD LIMIT XFMR 2VC-24-1 21 VOLUME CONTROL TANK RELIEF 2VC-25-1 RCP SEAL RETURN/EXCESS LETDOWN RELIEF TO PRT 2VC-25-2 LETDOWN LINE TO VCT INLET 2VC-26-1 2 REGEN HX LETDOWN LINE OUTLET RELIEF TO PRT 2VC-28-1 21 CHARGING PUMP DISCHARGE RELIEF 2VC-28-2 22 CHARGING PUMP DISCHARGE RELIEF 2W1 PROCESS PROTECTION RACK 2W1 2W2 PROCESS PROTECTION RACK 2W2 2Y1 PROCESS PROTECTION RACK 2Y1 2Y2 PROCESS PROTECTION RACK 2Y2 A CONTROL PANEL A AC21 BOP ANNUNCIATOR CABINET AC21 AC22 BOP ANNUNCIATOR CABINET AC22 AC23 BOP ANNUNCIATOR CABINET AC23 A-24

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List I Equipment Tag Description AC24 BOP ANNUNCIATOR CABINET AC24 AF-29-1 11 AUX FW PUMP SUCT RELIEF AF-29-2 12 AUX FW PUMP SUCT RELIEF AUX RELAY CAB 1203 AUX RELAY CAB 1203 B-2 CONTROL PANEL B-2 B21/SWGR BUS 21 4.16KV SWITCHGEAR B21/XFR SW 4.16 KV BUS 21 TRANSFER SWITCH B22/SWGR BUS 22 4.16KV SWITCHGEAR B22/XFR SW 4.16 KV BUS 22 TRANSFER SWITCH B23/SWGR BUS 23 4.16KV SWITCHGEAR B24/SWGR BUS 24 4.16KV SWITCHGEAR B25 LOGIC-1 BUS 25 LOGIC CAB 1 B25 LOGIC-2 BUS 25 LOGIC CAB 2 B25/AUX RELAY CAB BUS 25 AUXILIARY RELAY CABINET B25/LOAD SEQ CAB BUS 25 SAFEGUARDS LOAD SEQUENCER CABINET B25/SWGR BUS 25 4.16KV SWITCHGEAR B25/XFR SW 4.16KV SWGR BUS 25 TRANSFER SWITCH B26 LOGIC-1 BUS 26 LOGIC CAB 1 B26 LOGIC-2 BUS 26 LOGIC CAB 2 B26/AUX RELAY CAB BUS 26 AUXILIARY RELAY CABINET A-25

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List I Equipment Tag Description B26/LOAD SEQ CAB BUS 26 SAFEGUARDS LOAD SEQUENCER CABINET B26/SWGR BUS 26 4.16KV SWITCHGEAR B26/XFR SW 4.16KV SWGR BUS 26 TRANSFER SWITCH BENCH BOARD D5 BENCH BOARD D5 BENCH BOARD D6 BENCH BOARD D6 BUS 211 BUS 211 BUS 212 BUS 212 480V SWITCHGEAR BUS 221 BUS 221 BUS 222 BUS 222 480V SWITCHGEAR BUS 25 BUS 25 BUS 26 BUS 26 C-2 CONTROL PANEL C-2 CD-34080 21 FCU DISCH TO CNTMT DOME CD CD-34081 21 FCU NORM DISCH TO GAP & STRUCT CD CD-34082 22 FCU DISCH TO CNTMT DOME CD CD-34083 22 FCU NORM DISCH TO GAP & STRUCT CD CD-34084 23 FCU DISCH TO CNTMT DOME CD CD-34085 23 FCU NORM DISCH TO GAP & STRUCT CD CD-34086 24 FCU DISCH TO CNTMT DOME CD CD-34087 24 FCU NORM DISCH TO GAP & STRUCT CD A-26

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description CD-34138 21 CLASS I ROOF EXHT FAN DSCH CD CD-34139 21 SCVNG & COMBTM AIR CD CV-31060 22 TD AFW PUMP TRIP THROTTLE CV CV-31102 21 STM GEN POWER OPERATED RELIEF CV CV-31107 22 STM GEN POWER OPERATED RELIEF CV CV-31116 21 LOOP A MN STM HDR ISOL CV CV-31117 22 LOOP B MN STM HDR ISOL CV CV-31230 2 REAC CLNT LOOP PRZR LTDN LN ISOL CV A CV-31279 2 REAC CLNT LOOP PRZR LTDN LN ISOL CV B CV-31418 21 MD AUX FW PMP RCRC/LUBE OIL CLG CV CV-31419 22 TD AUX FW PMP RCRC/LUBE OIL CLG CV CV-31425 21/22 RCP SEAL BYPASS RETURN CV CV-31457 22 DDCLP JCKT CLR OUTL CV CV-31654 21 CLG WTR STRAINER BACKWASH CV CV-31655 22 CLG WTR STRNR BCKWSH CV CV-31999 22 TD AFW PMP STM BLOCK CV CV-39200 21 & 23 FCU CLG WTR RTN ORIF B-P CV CV-39202 22 & 24 FCU CLG WTR RTN ORIF B-P CV CV-39413 22/24 FCU CLG WTR SUPPLY CV CV-39414 22/24 FCU CHILLED WTR SUPPLY CV A-27

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List 1 Equipment Tag Description CV-39415 21/23 FCU CLG WTR SUPPLY CV CV-39416 21/23 FCU CHILLED WTR SUPPLY CV CV-39417 22 SHROUD CLG COILS TR A CHILLED WTR SUPPLY CV CV-39419 21 SHROUD CLG COILS TR B CHILLED WTR SUPPLY CV CV-39421 22/24 FCU CLG WTR RETURN CV CV-39423 21/23 FCU CLG WTR RETURN CV D-2 CONTROL PANEL D-2 D2 CFRP/XFMR D2 CLEAN FUEL RTRN PMP TRANSFORMER D2/CT CURRENT TRANSFORMER D2/GEN RLY PNL D2 EMERG GEN RELAY PNL D2/GND RES NEUTRAL GROUNDING RESISTOR D2/GND XFMR NEUTRAL GROUNDING TRANSFORMER D2-3 GENERATOR RELAY BOX D2-3 D5/EXC PNL D5 DSL GEN EXCITATION PANEL-SEVR D5/GND CAB D5 DSL GEN GROUND CABINET D5/RTU D5 DSL GEN REMOTE TERMINAL UNIT CABINET D5/RTV D5 DSL GEN REMOTE TRANSMITTER & VIBRATION CABINET D6/EXC PNL D6 DSL GEN EXCITATION PANEL-SEVR D6/GND CAB D6 DSL GEN GROUND CABINET D6/RTU D6 DSL GEN REMOTE TERMINAL UNIT CABINET A-28

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List 1 Equipment Tag Description D6/RTV D6 DSL GEN REMOTE TRANSMITTER & VIBRATION CABINET DG AUX DESK D5 DG AUX DESK D5 DG AUX DESK D6 DG AUX DESK D6 E-2 CONTROL PANEL E-2 EM-A2 EVENT MONITORING RACK EM-A2 EM-B2 EVENT MONITORING RACK EM-B2 ET-507/XFMR U2 CNTMT AIR SMPL LN HT TRACE XFMR F-2 CONTROL PANEL F-2 G-2 CONTROL PANEL G-2 GRD/D5 D5 DSL GEN NEUT GROUNDING TRANSFORMER GRD/D6 D6 DSL GEN NEUT GROUNDING TRANSFORMER LOOP 2H-428A 21 CHARGING PUMP SPEED CONTROL LOOP 2H-428B 22 CHARGING PUMP SPEED CONTROL LOOP 2L-112 21 VC TK LVL LOOP 2L-141 22 VC TK LVL LOOP 2L-426-RP PRZR LVL RED CHANNEL LOOP 2L-428-RP PRZR LVL BLUE CHANNEL LOOP 2P-429-RP PRZR PRESS RED CHANNEL LOOP 2P-431-RP PRZR PRESS BLUE CHANNEL LOOP 2P-482-RP 21 STM GEN PRESS BLUE CHANNEL A-29

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description LOOP 2P-483-RP 22 STM GEN PRESS RED CHANNEL MCC 2A1 MOTOR CONTROL CENTER 2A BUS 1 MCC 2A2 MOTOR CONTROL CENTER 2A BUS 2 MCC 2AA2 MOTOR CONTROL CENTER 2AA BUS 2 MCC 2AC1 MOTOR CONTROL CENTER 2AC BUS 1 MCC 2AC2 MOTOR CONTROL CENTER 2AC BUS 2 MCC 2B1 MOTOR CONTROL CENTER 2B BUS 1 MCC 2BA1 MOTOR CONTROL CENTER 2BA BUS 1 MCC 2D1 MOTOR CONTROL CENTER 2D BUS 1 MCC 2D2 MOTOR CONTROL CENTER 2D BUS 2 MCC 2DA1 MOTOR CONTROL CENTER 2DA BUS 1 MCC 2DA2 MOTOR CONTROL CENTER 2DA BUS 2 MCC 2E1 MOTOR CONTROL CENTER 2E BUS 1 MCC 2E2 MOTOR CONTROL CENTER 2E BUS 2 MCC 2EGB MOTOR CONTROL CENTER 2EGB MCC 2J1 MOTOR CONTROL CENTER 2J BUS 1 MCC 2J2 MOTOR CONTROL CENTER 2J BUS 2 MCC 2K1 MOTOR CONTROL CENTER 2K BUS 1 MCC 2K2 MOTOR CONTROL CENTER 2K BUS 2 MCC 2KA2 MOTOR CONTROL CENTER 2KA BUS 2 A-30

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List 1 Equipment Tag Description MCC 2L1 MOTOR CONTROL CENTER 2L BUS 1 MCC 2L2 MOTOR CONTROL CENTER 2L BUS 2 MCC 2LA1 MOTOR CONTROL CENTER 2LA BUS 1 MCC 2LA2 MOTOR CONTROL CENTER 2LA BUS 2 MCC 2M1 MOTOR CONTROL CENTER 2M BUS 1 MCC 2M2 MOTOR CONTROL CENTER 2M BUS 2 MCC 2P1 MOTOR CONTROL CENTER 2PBUS 1 & 2 MCC 2R1 MOTOR CONTROL CENTER 2R BUS 1 & 2 MCC 2S1 MOTOR CONTROL CENTER 2S BUS 1 MCC 2TA1 MOTOR CONTROL CENTER 2TA BUS 1 MCC 2TA2 MOTOR CONTROL CENTER 2TA BUS 2 MCC 2X1 MOTOR CONTROL CENTER 2X BUS 1 MCC 2X2 MOTOR CONTROL CENTER 2X BUS 2 MTR 121C-22 22 COOLING WATER STRAINER MTR 211K-12 21 D5 DSL GEN BLDG SPLY FAN MTR 211K-13 21 D5 DSL GEN BLDG RETURN FAN MV-32020 22 SG MS SPLY TO 22 TD AFW PMP MV MV-32026 21 MD AFW PUMP SUCT CLG WTR SUPPLY MV MV-32030 22 TD AFW PUMP SUCT CLG WTR SUPPLY MV MV-32033 2 TURB BLDG CLG WTR HDR MV A-31

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List I Equipment Tag Description MV-32048 21 MSIV BYPASS MV MV-32050 22 MSIV BYPASS MV MV-32060 RFLG WTR EM ERG MK-UP TO CHG PMPS MV MV-32062 RFLG WTR EMERG MK-UP TO CHG PMPS MV MV-32063 21 VOL CONT TNK TO CHG PMPS ISOL MV MV-32144 LOOP A/B CLG WTR HDR XOVR MV A MV-32148 21 FCU CLG WTR OUTL ISOL MV B MV-32156 24 FCU CLG WTR OUTL ISOL MV A MV-32159 LOOP A/B CLG WTR HDR XOVR MV B MV-32160 21 CC HX CLG WTR INLET MV MV-32161 22 CC HX CLG WTR INLET MV MV-32180 SUMP B TO 21 RHR PMP TRN A (OUTSIDE) MV MV-32194 2 REAC EXCS LTDN LINE ISOL MV A MV-32210 2 RCP SEAL RETURN/EXCESS LETDOWN ISOLTRN B MV MV-32246 22 TD AUX FW TO 21 STM GEN MV MV-32248 21/22 AFW TO 21 SG ISOL MV MV-32383 21 MD AFW PMP DISCH TO 21 SG MV MV-32384 21 AFWP DSCH TO 22 STM GEN MV MV-32389 24 FCU CLG WTR INLT ISOL MV PNL 21 DISTRIBUTION PANEL 21 A-32

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description PNL 211 INSTRUMENT BUS II PANEL (WHI) 211 PNL 2111 AC DISTRIBUTION PANEL (WHI) 2111 PNL 2112 AC DISTRIBUTION PANEL (RED) 2112 PNL 2113 AC DISTRIBUTION PANEL (BLU) 2113 PNL 2114 AC DISTRIBUTION PANEL (YEL) 3114 PNL 2116 AC DISTRIBUTION PANEL 2116 PNL 21-16 125 VDC PANEL 25 PNL 212 INSTRUMENT BUS I PANEL (RED) 212 PNL 212-3 PROCESS RACK 2R1 PNL 212-4 PROCESS RACK 2R2 PNL 213 INSTRUMENT BUS III PANEL (BLU) 213 PNL 213-3 PROCESS RACK 2B1 PNL 213-4 PROCESS RACK 2B2 PNL 214 INSTRUMENT BUS IV PANEL (YEL) 214 PNL 215 ROD POSITION PANEL 215 PNL 216 NON-INTERRUPTABLE PANEL 216 PNL 217 INTERRUPTABLE PANEL 217 PNL 218 AC DISTRIBUTION PANEL 218 PNL 218/REG PNL 218 SOLATRON VOLTAGE REGULATORN PNL 22 DC DISTRIBUTION PANEL 22 A-33

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List 1 Equipment Tag Description PNL 22-18 125 VDC PANEL 26 PNL 227/DISC SW DISTRIBUTION PANEL 227 DISCONNECT SWITCH PNL 228/DISC SW DISTRIBUTION PANEL 228 DISCONNECT SWITCH PNL 230 AC DISTRIBUTION PANEL 230 PNL 231 DC DISTRIBUTION PANEL 231 PNL 232 AC DISTRIBUTION PANEL 232 PNL 234 AC DISTRIBUTION PANEL 234 PNL 234/XFMR PANEL 234 TRANSFORMER PNL 235 AC DISTRIBUTION PANEL 235 PNL 235/XFMR PANEL 235 TRANSFORMER PNL 246 AC DISTRIBUTION PANEL 246 PNL 246/XFMR PANEL 246 TRANSFORMER PNL 247/XFMR PANEL 247 TRANSFORMER PNL 248/XFMR PANEL 248 TRANSFORMER PNL 25 NUCLEAR DISTRIBUTION PANEL 25 PNL 251 DC DISTRIBUTION PANEL 251 PNL 251-10 U2 TRN A RCS VENT SYS SV37091;37093;37095 PNL 25-15 125 VDC PANEL 253 PNL 25-16 125 VDC PANEL 251 PNL 25-18 125 VDC PANEL 252 A-34

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

. Table A-I: Prairie Island Unit 2 - Base List I Equipment Tag Description PNL 251-9 21 & 22 MN STM HDR ISOL CV-31116 & CV-31117 PNL 252 DC DISTRIBUTION PANEL 252 PNL 252-14 CV 39200 21 & 23 FCU CLG WTR RTRN ORIF BYPS PNL 253 DC DISTRIBUTION PANEL 253 PNL 253-34 CD 34080 21 FCU DISCH TO CNTMT DOME CD PNL 253-35 CD 34081 21 FCU DISCH TO CNTMT BSTR FAN CD PNL 26 NUCLEAR DISTRIBUTION PANEL 26 PNL 261 DC DISTRIBUTION PANEL 261 PNL 261-12 CV 31999 22 TD AUX FW PMP MN STM SUPPLY CV PNL 261-15 CV31419 22 TD AUX FW PMP RECIRC PNL 26-15 125 VDC PANEL 263 PNL 26-16 125 VDC PANEL 261 PNL 26-17 125 VDC PANEL 262 PNL 261-8 21 & 22 MN STM HDR ISOL CV-31116 & CV-31117 PNL 262 DC DISTRIBUTION PANEL 262 PNL 262-1 U2 TRN B RCS VENT SYS SV37092;37094;37096 PNL 262-6 CV 39202 22 & 24 FCU CLG WTR RTRN ORIF BYPS PNL 263 DC DISTRIBUTION PANEL 263 PNL 263-16 CD 34082 22 FCU DISCH TO CNTMT DOME CD PNL 263-18 CD 34083 22 FCU DISCH TO BOOSTER FANS CD A-35

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-I: Prairie Island Unit 2 - Base List 1 Equipment Tag Description PNL 27 DISTRIBUTION PANEL 27 PNL 28 DISTRIBUTION PANEL 28 PNL 2EM DISTRIBUTION PANEL 2EM PNL 2EMA EVENT MONITORING RACK EM-A2 PNL 2EMA/DISC DISTRIBUTION PANEL 2EMA DISCONNECT SWITCH PNL 2EM-A1 PNL 2EM-A1 PNL 2EMA-11 ICCM UNIT 2 TRAIN A MICROPROCESSOR 2LM-750 PNL 2EMA-3 EXCORE DETAMPLIFIER 2NM-51 PNL 2EMA-8 TB A1688 ICCM UNIT 2 TRAIN A PLASMA DISPLAY PNL 2EMB EVENT MONITORING RACK EM-A2 PNL 2EMB/DISC DISTRIBUTION PANEL 2EMB DISCONNECT SWITCH PNL 2EM-B1 PNL 2EM-B1 PNL 2EMB-11 ICCM UNIT 2 TRAIN B MICROPROCESSOR 2LM-760 PNL 2EMB-3 EXCORE DET AMPLIFIER 2NM-52 PNL 2EMB-8 TB 2889 ICCM UNIT 2 TRAIN B PLASMA DISPLAY PNL31 DC DISTRIBUTION PANEL 31 PT/TT1/D5 D5 DSL GEN PH A-B POT XFMR 4.16KV-120X120V PT/TT1/D6 D6 DSL GEN PH A-B POT XFMR 4.16KV-120X120V PT/TT2/D5 D5 DSL GEN PH B-C POT XFMR 4.16KV-120X120V PT/TT2/D6 D6 DSL GEN PH B-C POT XFMR 4.16KV-120X120V A-36

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description PT/TT3/D5 D5 DSL GEN PH A-B POT XFMR 4.16KV-120X120V PT/TT3/D6 D6 DSL GEN PH A-B POT XFMR 4.16KV-120X120V PT/TT4/D5 D5 DSL GEN PH B-C POT XFMR 4.16KV-120X120V PT/TT4/D6 D6 DSL GEN PH B-C POT XFMR 4.16KV-120X120V PT-1/D5 D5 AUTO VOTAGE REG MOTOR ORERATED POT PT-1/D6 D6 AUTO VOTAGE REG MOTOR ORERATED POT PT-2/D5 D5 MANUAL VOLTAGE REG MOTOR OOPERATED POT PT-2/D6 D6 MANUAL VOLTAGE REG MOTOR OOPERATED POT PWRS/24407 U2 CHILLED WTR SYS 28V PWR SPLY RS-21-11 SAFETY VALVE HEADER STM GENERATOR 21 RS-21-12 SAFETY VALVE HEADER STM GENERATOR 21 RS-21-13 SAFETY VALVE HEADER STM GENERATOR 21 RS-21-14 SAFETY VALVE HEADER STM GENERATOR 21 RS-21-15 SAFETY VALVE HEADER STM GENERATOR 21 RS-21-16 SAFETY VALVE HEADER STM GENERATOR 22 RS-21-17 SAFETY VALVE HEADER STM GENERATOR 22 RS-21-18 SAFETY VALVE HEADER STM GENERATOR 22 RS-21-19 SAFETY VALVE HEADER STM GENERATOR 22 RS-21-20 SAFETY VALVE HEADER STM GENERATOR 22 SA-56-3 22 CLG WTR PUMP - DIESEL STARTING AIR A-37

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List I Equipment Tag Description SV-33258 21 LOOP A MN STM HDR SV A SV-33259 21 LOOP A MN STM HDR SV B SV-33260 21 LOOP A MN STM HDR AIR EXHTSV A SV-33261 21 LOOP A MN STM HDR AIR EXHT SV B SV-33263 22 LOOP B MN STM HDR SV A SV-33264 22 LOOP B MN STM HDR SV B SV-33265 22 LOOP B MN STM HDR AIR EXHT SV A SV-33266 22 LOOP B MN STM HDR AIR EXHT SV B SV-33300 22 TD AFW PMP STM BLOCK SV SV-33346 22 CLG WTR STRNR BCKWSH SV SV-33389 21 FAN COIL UNIT DSCH TO CONTM DOME DMPR TRN A S SV-33390 21 FAN COIL UNIT NORM DSCH TO GAP & STRUC DMPR S SV-33391 22 FAN COIL UNIT DSCH TO CONTM DOME DMPR TRN B S SV-33392 22 FAN COIL UNIT NORM DSCH TO GAP & STRUC DMPR S SV-33393 23 FAN COIL UNIT DSCH TO CONTM DOME TRN A SV SV-33394 23 FAN COIL UNIT NORM DSCH TO GAP & STRUC DMPR S SV-33395 24 FAN COIL UNIT DSCH TO CONTM DOME TRN B SV SV-33396 24 FAN COIL UNIT NORM DSCH TO GAP & STRUC DMPR S SV-33466 22 DD CLWP AIR MTR RS SV A SV-33467 22 DD CLWP AIR MTR SV B A-38

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List 1 Equipment Tag Description SV-33490 2 REAC CLNT LOOP PRZR LTDN LN ISOL SV SV-33491 2 REAC CLNT LOOP PRZR LTDN LN ISOL SV 2 SV-33492 21 MD AUX FW PMP RCRC/LUBE OIL CLG SV SV-33493 22 TD AUX FW PMP RCRC/LUBE OIL CLG SV SV-33498 2 DSL GEN RM OUTS AIR B TRN DMPR SV SV-33565 21 AUX FW PMP MTR UNIT CLR SV SV-33695 21 CLASS I ROOF EXHT FAN DMPR SV SV-33696 21 SCVNG & COMTN AIR DMPR SV A SV-33777 22 DD CLWP DSL JCKT CLR OUTL SV SV-33829 21 SCVNG & COMBTN AIR DMPR SV B SV-37091 RCS VENT SYS PRZR VENT SV SV-37092 RCS VENT SYS PRZR VENT SV SV-37093 RCS VENT SYS REACTOR HEAD VENT SV SV-37094 RCS VENT SYS REACTOR HEAD VENT SV SV-37095 RCS VENT SYS TO PRT SV SV-37096 RCS VENT SYS TO CNTMT ATMOS SV SV-37200 21 & 23 FCU CLG WTR RTN ORIFICE B-P SV SV-37202 22 & 24 FCU CLG WTR RTN ORIF B-P SV SV-37413 22; 24 FCU CLG WTR SUPPLY SV SV-37415 21; 23 FCU CLG WTR SUPPLY SV A-39

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-1: Prairie Island Unit 2 - Base List 1 Equipment Tag Description SV-37421 22; 24 FCU CLG WTR RETURN SV SV-37423 21; 23 FCU CLG WTR RETURN SV SV-37464 UNIT 2 TRAIN A CHILL WTR/CLG WTR ISOL SV SV-37465 UNIT 2 TRAIN B CHILL WTR/CLG WTR ISOL SV SV-37466 UNIT 2 TRAIN A CHILL WTR/CLG WTR ISOL SV SV-37467 UNIT 2 TRAIN B CHILL WTR/CLG WTR ISOL SV SV-37904 D5 ENG 1 AUX DESK 1B START AIR SV TB 2209 RELAY ROOM AUX RELAY CABINET TB 2222 RELAY ROOM TERMINAL BOX TB 2229 RELAY ROOM TERMINAL BOX TB 2480 TB FOR 21 CHARGING PUMP TB 2481 TB FOR 22 CHARGING PUMP TERM CAB 2222 TERM CAB 2222 TERM CAB 2229 TERM CAB 2229 VC-25-2 LETDOWN LINE TO VOLUME CONTROL TANK INLET - RLF VERT CONT PNL D5 VERT CONT PNL D5 VERT CONT PNL D6 VERT CONT PNL D6 A-40

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report A.2 Final SWEL 1 This section provides a list of the final equipment selected for PINGP'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.

A-41

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-2: Prairie Island Unit 2 - SWEL I Equipment Description Class' Safety Verify Deferred? Comments Tag Function 2 System Anchorage?

50000 D5 DSL GEN BENCHBOARD 20 1, 2, 3, 4, 5 D5 Yes 50200 D5 DSL GEN VERTICAL PANEL 20 1, 2, 3, 4, 5 D5 Yes 55320 D5 DSL GEN ENG 1 AUX DESK 20 1, 2, 3, 4, 5 D5 Yes 70350 22 DD CLWP LCL PNL 20 1, 2, 3, 4, 5 CL Yes 053-322 22 DD CLG WTR PMP DSL OIL DAY TNK 21 1, 2, 3, 4, 5 CL Yes New or replaced, IPEEE 15 1, 2, 3, 4, 5 DC Yes enhanced 21 BATT 21 BATTERY (& BATTERY RACK) Enhanced 21 BATT 21 BATTERY CHARGER 16 1,2,3,4,5 DC Yes Yes CHG 21 INV 21 INVERTER 16 1, 2, 3, 4,5 IP Yes Yes 211M/XFMR 211M TRANSFORMER 4 1,2,3,4,5 EB Risk significant 212M/XFMR 212M TRANSFORMER 4 1, 2, 3, 4, 5 EB 217-111 21 MD AFW PMP L/O CLR 21 4 AF 22 BATT 22 BATTERY (&BATTERY RACK) 15 1, 2, 3, 4, 5 DC Yes New or replaced 22 BATT 22 BATTERY CHARGER 16 1, 2, 3, 4, 5 DC Yes CHG 221M/XFMR 221M TRANSFORMER 4 1, 2, 3, 4, 5 EB Risk significant A-42

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-2: Prairie Island Unit 2 - SWEL 1 Equipment Description Class' Safety 2 y t m3 Verify D f re ?C m e t Tag Function2 SystemsAnchorage?

23 INV 23 INVERTER 16 1, 2, 3, 4, 5 IP Yes Yes Risk significant 232-281 21 SFGDS SCRNHSE ROOF EXHT FAN 9 1, 2, 3, 4, 5 ZR Yes Yes IPEEE Enhanced 234-031 D5 DSL GEN 17 1, 2, 3, 4,5 D5 234-032 D6 DSL GEN 17 1,2, 3, 4,5 D6 235-081 22 CLG WTR PMP DSL JCKT CLG HX 21 1, 2, 3, 4, 5 CL IPEEE Enhanced 245-042 22 CHG PMP 5 1,2,3 VC Yes 245-071 21 SI PMP 5 3 SI Yes 245-122 22 CC PMP 5 2,3 CC Yes 245-201 22 TD AFW PMP 5 4 AF Yes 245-392 22 DD CLG WTR PMP 6 1, 2, 3, 4, 5 CL Yes IPEEE Enhanced 246-031 D5 1A START AIR RCVR 21 1, 2, 3, 4, 5 D5 253-361 21 D5 FO DAY TANK 21 1, 2, 3, 4,5 FO Yes 253-401 D5 ENG 1 HT EXPANSION TANK 21 1, 2, 3, 4, 5 D5 258-011 21 CLG WTR STRNR 0 1, 2, 3, 4, 5 CL Yes 274-013 23 CNTMT FCU 10 5 ZC Yes New or replaced 274-031 121 SWGR RM UNIT CLR 10 1,2, 3,4, 5 ZH 274-162 TRN B EVENT MON RM UNIT CLR 10 1, 2, 3, 4, 5 ZH A-43

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-2: Prairie Island Unit 2 - SWEL I Equipment Description Class' Safety System3 Verify Deferred? Comments Tag Function2 Anchorage?

2ASG1 SAFEGUARD RELAY RACK 2ASG1 20 1, 2, 3, 4, 5 RP Yes 2EG-15-2 D5 1B START AIR RCVR RELIEF 7 1,2,3,4,5 D5 2FT-464 MN STM FR 21 STM GEN CHNNL I RED F 18 4 RP Yes XMTR 2LT-428 2 PRZR (CHNL III-BLU)LVL XMTR 18 3 RP Yes Yes 2LT-461 21 STM GEN LOOP A CHNNL I-RED LVL XMTR 18 4 RP Yes Yes 2LT-762 U2 RVLIS HEAD FULL RANGE TRN B D/P 18 3 EM XMTR 2LT-763 22 RX VSL HEAD DYNAMIC RNG TRN B D/P 18 3 EM Yes XMTR 2LT-920 21 RWST LVL XMTR 18 1,2,3 EM Yes 2LT-921 21 RWST LVL XMTR 18 1,2,3 EM Yes 2NR3 NIS RACK III (BLU) 2NR3 20 1 NI Yes IPEEE Enhanced 2PT-469 21 STM GEN MN STM HDR (CHNL II-WHI) P 18 4 MS XMTR 2PT-479 22 STM GEN MN STM HDR (CHNL IV-YEL) P 18 4 RP XMTR 2VC-28-2 22 CHG PMP DISCH RELIEF 7 1, 2, 3 VC B-2 CONTROL PANEL B-2 20 1,2,3,5 BM IPEEE Enhanced A-44

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-2: Prairie Island Unit 2 - SWEL 1 Equipment Description Class 1 Safety System3 Verify Deferred? Comments Tag Function2 Anchorage?

B25/LOAD BUS 25 SFGDS LOAD SEQUENCER CABINET 20 1, 2, 3, 4, 5 EA Yes SEQ CAB New or replaced, Risk BUS 212 480V SWITCHGEAR 2 1, 2, 3, 4, 5 EB Yes Nificant BUS 212 significant BUS 26 BUS 26 4.16KV SWITCHGEAR 3 1, 2, 3,4, 5 EA Yes Risk significant CV-31060 22 TD AFW PMP TRIP THROTTLE CV 7 4 AF CV-31419 22 TD AFW PMP RECIRC/L-O CLG CV 7 4 AF CV-31457 22 DD CLG WTR PMP JCKT CLR OUTL CV 7 1, 2, 3, 4, 5 CL CV-39413 22/24 FCU CLG WTR SUPPLY CV 7 5 ZX CV-39417 22 CRDM SHRD CLG COIL SPLY CV 7 5 ZX Yes IPEEE Enhanced CV-39419 21 CRDM SHRD CLG COIL SPLY CV 7 5 ZX Yes IPEEE Enhanced D-2 CONTROL PANEL D-2 20 4 BM IPEEE Enhanced E-2 CONTROL PANEL E-2 20 4 BM IPEEE Enhanced EM-B2 EVENT MONITORING RACK EM-B2 20 2, 4, 5 EM Yes MCC 2LA1 MOTOR CONTROL CENTER 2LA BUS 1 1 1,2,3,4,5 EB Yes Yes MCC 2K2 MOTOR CONTROL CENTER 2K BUS 2 1 1, 2, 3, 4 EB Yes Yes Risk significant, IPEEE Enhanced MCC 2M1 MOTOR CONTROL CENTER 2M BUS 1 1 5 EB Yes Yes A-45

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-2: Prairie Island Unit 2 - SWEL I Equipment Description Class' Safety System 3 Verify Deferred? Comments Tag Function S Anchorage?

MCC 2L2 MOTOR CONTROL CENTER 2L BUS 2 1 1,3,5 EB Yes Yes MCC 2X1 MOTOR CONTROL CENTER 2X BUS 1 1 5 EB Yes MTR211K- 21 D5 DSL GEN BLDG SPLY FAN 9 1, 2, 3,4,5 EB 12 MTR 211K- 21 D5 DSL GEN BLDG RETURN FAN 9 1,2, 3, 4, 5 EB 13 MV-32020 22 SG MS SPLY TO 22 TD AFW PMP MV 8 4 MS MV-32030 22 TD AFW PMP SUCT CL SPLY MV 8 4 CL MV-32148 21 FCU CLG WTR OUTL ISOL MV B 8 5 CL MV-32156 24 FCU CLG WTR OUTL ISOL MV A 8 5 CL Yes MV-32160 21 CC HX CLG WTR INLET MV 8 3 CL MV-32180 SUMP B TO 21 RHR PMP TRN A (OUTSIDE) MV 8 3,4 SI MV-32246 22 AFW TO 21 SG MV 8 4 AF MV-32248 21/22 AFW TO 21 SG ISOL MV 8 4 AF MV-32383 21 MD AFW PMP DISCH TO 21 SG MV 8 4 AF MV-32384 21 MD AFW PMP DISCH TO 22 SG MV 8 4 AF MV-32389 24 FCU CLG WTR INLT ISOL MV 8 5 CL A-46

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-2: Prairie Island Unit 2 - SWEL 1 Equipment Description Class 1 Safety System3 Verify Deferred? Comments Tag Functionz Anchorage?

Risk significant, IPEEE DISTRIBUTION PANEL 21 14 1, 2, 3, 4, 5 DC Yes Yes Enhancd PNL 21 Enhanced PNL 211 INSTRUMENT BUS II PANEL (WHI) 211 14 1,2, 3,4, 5 IP Yes Risk significant PNL 213 INSTRUMENT BUS III PANEL (BLU) 213 14 1,2, 3, 4,5 IP Yes Risk significant PNL 22 DC DISTRIBUTION PANEL 22 14 1,2,3,4,5 DC IPEEE Enhanced PNL 234 AC DISTRIBUTION PANEL 234 14 3 EX Yes PNL 24M PANEL 234 TRANSFORMER 234/XFMR 4 3 EX PNL 235 AC DISTRIBUTION PANEL 235 14 3 EX Yes PNL 35M PANEL 235 TRANSFORMER 4 3 EX 235/XFMR PNL 253 DC DISTRIBUTION PANEL 253 14 2, 3,5 DC Yes Yes PNL 261 DC DISTRIBUTION PANEL 261 14 4, 5 DC Yes PNL 262 DC DISTRIBUTION PANEL 262 14 3, 5 DC Yes PNL 2EM DISTRIBUTION PANEL 2EM 14 1, 2, 3, 4, 5 EM Yes Yes RS-21-11 21 SG MS HDR RELIEF 7 4 MS SV-33389 21 FCU DISCH TO CNTMT DOME CD-34080 SV 8 5 ZC Yes SV-33777 22 DD CLWP DSL JCKT CLR OUTL SV 8 1, 2, 3, 4, 5 CL A-47

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Table A-2: Prairie Island Unit 2 - SWEL 1 Equipment Description Class 1 Safety System3 Verify Deferred? Comments Tag Function2 Anchorage?

SV-37464 U2 TRN A CHLD WTR/CLG WTR ISOL SV 8 5 ZX Yes SV-37466 UNIT 2 TRAIN A CHILL WTR/CLG WTR ISOL SV 8 5 ZX Yes SV-37904 D5 ENG 1 AUX DESK 1B START AIR SV 8 1, 2, 3, 4, 5 D5 A-48

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal 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.

AF AUXILIARY FEEDWATER MP MISC PLANT INSTRUMENTS AT AUX START-UP/STDBY XFMRS MS MAIN STEAM BM SITE MISCELLANEOUS NI NUCLEAR INSTRUMENTATION MAINTENANCE CC COMPONENT COOLING PI ROD POSITION INDICATION CL COOLING WATER RC REACTOR COOLANT D1 D1 EMERGENCY DIESEL RP REACTOR PROTECTION D2 D2 EMERGENCY DIESEL SA STATION & INSTRUMENT AIR D5 D5 EMERGENCY DIESEL SE STEAM EXCLUSION D6 D6 EMERGENCY DIESEL SF SPENT FUEL POOL COOLING DC DC AUXILIARIES SI SAFETY INJECTION EA 4.16KV ELECTRICAL VC CHEMICAL & VOLUME CONTROL EB 480V ELECTRICAL ZC CONTAINMENT VENT EH ELECTRO-HYDRAULIC SYSTEM ZG DIESEL ROOMS VENT EL SITE LIGHTING ZH SAFEGUARDS CHILLED WATER EM EVENT MONITORING ZR SCREENHOUSE VENT EX 240/120V MISC AUXILIARIES ZX CNTMT & AUX BLDG COOLING FO FUEL OIL FW FEEDWATER IP INSTRUMENT POWER SOURCES A-49

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE UNDER 2.390 B Deferred Seismic Walkdown Checklists (SWCs)

This appendix provides the Seismic Walkdown Checklists (SWC) completed after Reference 13 was submitted. The SWCs completed prior to November 26, 2012 were provided in Table B-1 of the Reference 13 report, and are not provided in this supplement.

In the Reference 13 report, NSPM identified 30 deferred seismic walkdowns that needed to be completed at a later date. As described in Section 4 of this report, two items were deleted from the SWEL 1 list due to their being inaccessible during RFO 2R28. In addition, three items were inaccessible during RFO 2R28 and were therefore substituted for similar components. One item was added to the SWEL 1. Finally, one item remained on the SWEL 1 but was removed from the list of equipment whose anchorage required verification, due to its internal anchorage being inaccessible during RFO 2R28. As a result of these equipment substitutions and deletions, NSPM completed 29 deferred seismic walkdowns.

The SWCs are provided after Table B-i, and are in the same chronological order as listed in the table.

The SWCs in this appendix included 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 contained SUNSI information have been marked with a header, and the sensitive information, such as the locations and photos of safety-related components, has been redacted.

B-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report RU.gI IAI'".OfLr FRO.Mi PU2RLIC DISCLOSUIRE IUNhEFR 2.920 Table B-I: Prairie Island Unit 2 SWCs Completed after November 26, 2012 Anchorage Check Equipment Description Confirmed? list Equipment Tag Status (YIN) (YIN) 50000 D5 DSL GEN BENCHBOARD N Y 21 BATT CHG 21 BATTERY CHARGER Y Y 21 INV 21 INVERTER Y Y 23 INV 23 INVERTER Y Y 232-281 21 SFGDS SCRNHSE ROOF EXHT FAN Y Y 258-011 21 CLG WTR STRNR N Y 274-013 23 CNTMT FCU N Y 2FT-464 MN STM FR 21 STM GEN CHNNL I RED F XMTR N Y 2LT-428 2 PRZR (CHNL III-BLU)LVL XMTR Y Y 2LT-461 21 STM GEN LOOP A CHNNL I-RED LVL XMTR Y Y B25/LOAD SEQ CAB BUS 25 SFGDS LOAD SEQUENCER CABINET N Y BUS 212 BUS 212 480V SWITCHGEAR N Y BUS 26 BUS 26 4.16KV SWITCHGEAR N N CV-39417 22 CRDM SHRD CLG COIL SPLY CV N Y CV-39419 21 CRDM SHRD CLG COIL SPLY CV N Y MCC 2K2 MOTOR CONTROL CENTER 2K BUS 2 Y N MCC 2L2 MOTOR CONTROL CENTER 2L BUS 2 Y Y MCC 2LA1 MOTOR CONTROL CENTER 2LA BUS 1 Y Y MCC 2M1 MOTOR CONTROL CENTER 2M BUS 1 Y Y MCC 2X1 MOTOR CONTROL CENTER 2X BUS 1 N Y MV-32156 24 FCU CLG WTR OUTL ISOL MV A N Y PNL 21 DISTRIBUTION PANEL 21 Y Y PNL 213 INSTRUMENT BUS III PANEL (BLU) 213 N Y PNL 235 AC DISTRIBUTION PANEL 235 N Y PNL 253 DC DISTRIBUTION PANEL 253 Y Y PNL 2EM DISTRIBUTION PANEL 2EM Y Y SV-33389 21 FCU DISCH TO CNTMT DOME CD-34080 SV N Y SV-37464 U2 TRN A CHLD WTR/CLG WTR ISOL SV N Y SV-37466 UNIT 2 TRAIN A CHILL WTR/CLG WTR ISOL SV N Y B-2

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT,*HIOLD FROW PUBLIC DIS-CLOSURE UNDER 2.390 Sheet 1of 3 Status: Y*J NL- UE-(SWC)

Seismic Walkdown Checklist Equipment ID No. 50000 Equip. Class' (20) Instrumentationand Control Panelsand Cabinets Equipment Description D5 DSL GEN BENCHBOARD Location: Bldg. D5/D6 Floor El. I Room, Area D5 CNTRL 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.

Anchorane I. Is the anchorage configuration verification required (i.e., is the item one YEl- NO of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YO NEl UI-] N/AE]

It is stitch welded to embedded plates in the floor with substantial welds and bolted internallyto the mounting base.

3. Is the anchorage free of corrosion that is more than mild surface YO NEl Ul] N/Al]

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YZI NEI UiZ N/AU3

5. Is the anchorage configuration consistent with plant documentation? YI- NEl ULi N/A[D (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of YZ NI UEl]

potentially adverse seismic conditions?

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

B-3

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' 11'OLD FROM PUBLIC DISCLOSURE UNDER 2.390 Sheet 2 of 3 Status: Y0 NEI Um Seismic Walkdown Checklist (SWC)

Equipment ID No. 50000 Equip. Class' (20) Instrumentationand Control Panels and Cabinets Equipment Description D5 DSL GEN BENCHBOARD Interaction Effects

7. Are soft targets free friom impact by nearby equipment or structures? YZl NEI UO] N/AE3 The light fixtures are secured to a light metal strut.

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YI NEI UEr N/AE!

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

An electricalcable is coiled on top of the annunciatorpanel 50003.

9. Do attached lines have adequate flexibility to avoid damage? YIl NEI UE- N/A-]

10. Based on the above seismic interaction evaluations, is equipment free YZI NEI Ut]

of potentially adverse seismic interaction effects?

Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could Y9 NEI Ut]

adversely affect the safety functions of the equipment?

Comments (Additional pages Inay be added as necessary)

This item was held over from the originalwalkdown to complete internalinspections. Interiorof the benchboardwas inspected and found to be free of adverse seismic conditions.

Evaluated by: Dileep Cherlopalle C -\J.-\*t;\ \ -p,.*.&, " -.. Date: \- "-L,-- ,

Q KWle Kriesel B-4

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' WIT' 11OeLD FROM PUBLIG DISCILOsUREE UNDER 2.390 Status: Y[ N[-- U[-

Seismic Walkdown Checklist (SWC)

Equipment ID No. 50000 Equip. Class:1 (20) Instrumentationand Control Panels and Cabinets Equipment Description D5 DSL GEN BENCHBOARD Photogranhs Note: D5 Diesel GeneratorBenchboard Note: Interiorof D5 Diesel GeneratorBenchboard "Jr7 Note: Interiorof D5 Diesel GeneratorBenchboard Note: Interiorof D5 Diesel GeneratorBenchboard I

B-5

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SLJP 418..1 -- VI I I1II IO-LD I I VlV IUB I.-- I S-GI O J 6L%

L-' EI JND ý-/

f;*I**""*0U {et She-UI*1" 105 Status: YZ N[-] U-I Seismic Walkdown Checklist (SWC)

Equipment ID No. 21 BATT CHG Equip. Class' (16) Battery Chargersand Inverters Equipment Description 21 BATTERY CHARGER Location: Bldg. TURB Floor El. _ Room, Area 21 BATT 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 onl 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 NEI of the 50% of SWEL items requiring such verification)?.

2. Is the anchorage free of bent, broken, missing or loose hardware? YN NE3 UF] N/AUI

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

4. Is the anchorage free of visible cracks in the concrete near the anchors? YED NEI UU] N/AUl

5. Is the anchorage configuration consistent with plant documentation? YED NEI UUl N/AU1 (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Drawings NF-38221-10 and NX-236971-1 are used.

6. Based on the above anchorage evaluations, is the anchorage fiee of YO NEI UEU potentially adverse seismic conditions?

IEnter (he equipment class name from Appendix B: Classes of Equipment.

B-6

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Seis i Check W Tc --ist')'M

, "-lkdowO- St*a tu Sheet 2 Of 5 Sau:Y E E Seismic Walkdown Checklist (SWC)

Equipment ID No. 21 BATT CHG Equip. Class', (16) Battery Chargersand Inverters Equipment Description 21 BATTERY CHARGER Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO ND UE1 N/AD

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YID N[] Ur- N/AD]

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

9. Do attached lines have adequate flexibility to avoid damage? YO ND UD N/AD

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

Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could YI NDI UD-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

This equipment was walked down as part of the originalscope, but was deferred to complete internal cabinet inspections.Interior of the cabinet was inspected and found to be free of adverse seismic conditions.

Evaluated by: Dileep Cherlonalle C-. -,,,.

\*V. X Date: \ - ;aL - Nt5-Kvle Kriesel /Zz"/Aý B-7

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS'I - WITI I .LD FROM PUBLI DISCLOSURE UNDER 2.390 Status: YZ Nr-- UD-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. 21 BATT CHG Equip. Class, (16) Battery Chargersand Inverters Equipment Description 21 BATTERY CHARGER Photographs Note: 21 Battery Charger Note: Anchorage for 21 Battery Charger Note: Anchorage for 21 Battery Charger B-8

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSI - WIT'HH OLD= FROM PUBLIC DISCLOSURE UNDER 2.390 Note: Anchorage for 21 Battery Note: Area above 21 Battery Charger Note: Area above 21 Battery Charger B-9

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSIKI'I W II-- I**IT -LD '-F-I"REW PUBIC* DIS'*f%*/* "C'LOSR Ir- DER- 2.390r-r)1*

J/

Note: Interior of 21 Battery Charger Note: Interior of 21 Battery Charger B-10

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS',., IT' 1r.- ,

W,,-.- .....

FREW-..-...r . ,U r-ER- 2.39 Sheet 1 of 4 1 Status: Y0 NE] U-'

Seismic Walkdown Checklist (SWC)

Equipment ID No. 21 INV Equip. Class, (16) Battery Chargers and Inverters Equipment Description 21 INVERTER Location: Bldg. TURB Floor El. _ Room, Area 21 BATT 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 firee of bent, broken, missing or loose hardware? Y9 NEI UrI N/A--

3. Is the anchorage free of corrosion that is more than mild surface Y10 NEI UEr N/A--

oxidation?

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

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

Plant drawing NX-19644-2, Design Change 78Y068 and 83Y415 are used for reference.

6. Based on the above anchorage evaluations, is the anchorage firee of YM NEI ]ur potentially adverse seismic conditions?

IEnter the equipment class name fi'om Appendix B: Classes of Equipment.

B-11

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report r-,CLOSURE UNDER 2.390 Sheet 2 Of 4 Status: YZ NEI U[-

Seismic Walkdown Checklist (SWC)

Equipment ID No. 21 INV Equip. Class, (16) Battery Chargersand Inverters EqUtipment Description 21 INVERTER Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YED Nil Ur] N/AU

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YZ NO U[:] N/A[U and masonry block wvalls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YED NE] Ur] N/AU

10. Based on the above seismic interaction evaluations, is equipment free Y0 NEI UE of potentially adverse seismic interaction effects?

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Initial walkdown was performed as part of originalscope. The remaining walkdown to inspect the interiorof the panel was deferred to the Outage schedule based on the need to open the panel.

Interiorof the panel was inspected and found to be free of adverse seismic conditions.

Evaluated by: Dileep Cherlopalle Date: 1i- 2__1+- 1!J; KWle Kriesel B-1 2

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSI - WIT! 1IOLID FROM PUBLIG DISCLOSUJRE UNDER 2.390 Status: Y[ N-- UD-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. 21 INV Equip. Class' (16) Battery Chargiersand Inverters Equipment Description 21 INVERTER Photo~raDhs Note: 21 Inverter Note: 21 Inverter Note: Area above 21 Inverter Note: Anchorage for 21 Inverter B-13

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report suNsI -TI I-ll1 I"LD FRM rPUaLIC DISCLOSURE UNDER 2.390 Note: Interior of 21 Inverter Note: Interiorof 21 Inverter Note: Interiorof 21 Inverter Note:

B-1 4

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' WI'ITH t i Fr-r R APUi-O i D-IC' C~l

-BL ER iF-- i2.39-'r Sheet IOf 4 Status: YN3 NEO U[-l Checklist (SWC)

Seismic Walkdown Equipment ID No. 23 INV Equip. Class, (16)Battery Chargersand Inverters Equipment Description 23 INVERTER Location: Bldg. TURB Floor El. __ Room, Area 21 BATT 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.

Anchoraie

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

2. Is the anchorage free of bent, broken, missing or loose hardware? YNl NI] U0 N/AC-

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

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y0l NCI UC1 N/ACl

5. Is the anchorage configuration consistent with plant documentation? YZ NCI UC1 N/AC1 (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Plant drawing NX-19644-2, Design Change 78Y068 and 83Y415.

Anchorage spacing and markings match those specd in above DCs

6. Based on the above anchorage evaluations, is the anchorage free of YN NEI UC]

potentially adverse seismic conditions?

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

B-1 5

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS'

, -,WT' , 'OLD

, F-ROM , ,, ,,-,',,-,,,-,,,-r-,, ,-- - Sheet 2 of 4 Status: YI* N[- U[-J Checklist (SWC)

Seismic Walkdown Equipment ID No. 23 INV Equip. Class' (16)Battery Chargersand Inverters Equipment Description 23 INVERTER Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO NEI UrO N/AO

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

9. Do attached lines have adequate flexibility to avoid damage? YZ NOI UI- N/AU1

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

Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could YO NOI Uil adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Interiorof the cabinet was inspected and found to be free of adverse seismic conditions.

Evaluated by: Dileep Cheriopalle C .v. tAe.Q~v ~ Date: 1- 2-Lt- \iý U

Kyle Kriesel We Kries B-16

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' WITI IIOLD FROM

" U1 LIr DISCLOSURE UNDER 2.390 Status: Y[ N- U[--

Seismic Walkdown Checklist (SWC)

Equipment ID No. 23 INV Equip. Class1 (16)Battery Charqersand Inverters Equipment Description 23 INVERTER Note: Area above 23 Inverter Note: Interiorof 23 Inverter Note: Interior of 23 Inverter B-1 7

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' WIT' 11'OLD FROM PUBLIC DISCLOSURE UNDER 2.390 Note: Interiorof 23 Inverter iNote: Ancnorage ror zi inverter ir*ote: Ancnorage ror z inverer B-18

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS* - WITHH

... LD FROM

.UBLI, DISCLO*LSURE UNDER 2.390 Sheet 1 of 4 Status: Y[I NE-I Ur-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. 232-281 Equip. Class' (9) Fans Equipment Description 21 SFGDS SCRNHSE ROOF EXHT FAN Location: Bldg. SSCN 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 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 NIl of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Y0 NEI ULI[N/AEl

3. Is the anchorage free of corrosion that is more than mild surface Y0 NEI Ur] N/AE!

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YI3 NEI UI- N/AFl

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

Reference SQUG SEWS data and calc ENG-CS-098.

Seismic horizontal anchorage consists of six 1/2" diameter bolts. Bolt size is not specified in plant documentation. The number and location of the bolts is consistent with plant documen'tation.

Enter the equipment class name fi'om Appendix B: Classes of Equipment.

B-1 9

Prairie Updated Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report SUN.,&., - Wi

....... ,-,- ,,,. .. . .. "R'" .. . .... .. % Sheet 2 Of 4 Status: YN N[L Ufl Seismic Walkdown Checklist (SWC)

Equipment ID No. 232-281 Equip. Class' (9) Fans Equipment Description 21 SFGDS SCRNHSE ROOF EXHT FAN

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

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YOR NEI UE] N/A-'

No equipment or structuresin vicinity.

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YE NEI U[] N/AU[

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

No overhead equipment or structures in vicinity.

9. Do attached lines have adequate flexibility to avoid damage? YO NEI UIE] N/AU Flexible conduits are connected to fan operatorand junction box.

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

of potentially adverse seismic interaction effects?

Other Adverse Conditions

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

adversely affect the safety fimnctions of the equipment?

Comments (Additional pages may be added as necessary)

B-20

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS'I - WIT IO,,LD FRO.PUBLIC DISCLO*SURE UNDER 2.390 Sheet 3 of 4 Status: YO NEIl U--

Seismic Walkdown Checklist (SWC)

Equipment ID No. 232-281 Equip. Class' (9) Fans Equipment Description 21 SFGDS SCRNHSE ROOF EXHT FAN Evaluated by: Kyle Kriesel Date: ,2 9,"

9 Michael Wodarcyk1 Y 12/2/2013 B-21

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report 1I'I W/IT!-I'ULD--Ar~P i1 i) rDlCLOSURE ir39 iiliSheet UNDER. 4 Of 4 Status: YO NE] ul-Seismic Walkdown Checklist (SWC)

Equipment ID No. 232-281 Equip. Class, (9) Fans Equipment Description 21 SFGDS SCRNHSE ROOF EXHT FAN Photographs ate: Horizontal brace attached to fan Anchorage from horizontal brace to wall Note:

B-22

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT,* *1-OLD FROM PUBLIC DISCL.OSURE UNDER 2.390 Sheet 1 of 3 Status: Y[I NEI U[-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. 258-011 Equip. Class, (0) OTHER Equipment Description 21 CLG WTR STRNR Location: Bldg. SSCN 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 I Is the anchorage configuration verification required (i.e., is the item one YUI NO of the 50% of SWEL items requiring such verification)?

2, Is the anchorage firee of bent, broken, missing or loose hardware? YO N[l UI N/AD

3. Is the anchorage free of corrosion that is more than mild surface YO NEI ULI N/A[U oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YO NEI ULI N/AUI

5. Is the anchorage configuration consistent with plant documentation? YUI NEI UUi N/AO (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 fiee of YO NEI UI-potentially adverse seismic conditions?

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

B-23

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSl -IWITI II OLD FROM I UBLI. DISC.LOSURE UNIDER 2.390 Sheet 2 of 3 Status: Y[ NEIr U[-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. 258-011 Equip. Class, (0) OTHER Equipment Description 21 CLG WTR STRNR Inter-action Effects

7. Are soft targets fi'ee fioom impact by nearby equipment or structures? YZ NEI UE- N/AEl

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

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

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

Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could YE NEI UE]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel && A Date: /, .2 5</ "

Michael Wodarcvk 12/2/2013 B-24

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS!- WIT' OLD FROM PUBLI- DISCLOSURE UNDER 2,390 Sheet 3 of3 Status: Y* NF- ur-I Checklist (SWC)

Seismic Walkdown Equipment ID No. 258-011 Equip. Class' (0) OTHER Equipment Description 21 CLG WTR STRNR Photographs Note: Nameplate Note: Baseplate m Note: Attached equipment with flexible conduits and tubing B-25

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUPii CheLD W-aWIT' FROM PUB(WGi Wl .f A N j?.~i is:

e i ,,,ER,.39,, Sheetlof4 Status: Yo NE] ULI Seismic Walkdown Checklist (SWC)

Equipment ID No. 274-013 Equip. Class' (10) Air Handlers Equipment Description 23 CNTMT FCU Location: Bldg. CNTM Floor El. __ Room, Area 2CNTM 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 offjudgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

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

Due to inaccessibilityof component's anchorage, SWEL has been revised to remove 274-013 from the list of equipment whose anchorage requires verification.

2. Is the anchorage fiee of bent, broken, missing or loose hardware? YZJ NI] Ui] N/AUl

3. Is the anchorage flee of corrosion that is more than mild surface YZ NI UL] N/All oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YI NI] U[] N/AUl

5. Is the anchorage configuration consistent with plant documentation? YFI NEI U[- N/AIN (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 firee of YIl NI] UUl potentially adverse seismic conditions?

All external anchorage mounting 274-013 to floor channels is visible.

Only portions of internal anchorageare visible.

'Enter the equlipment class namic from Appendix B: Classes of Equipmnent.

B-26

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' I,OLD - FR*OMU,LI, DISCLOSURE UNDER 2.390 Sheet 2 of 4 Status: Y[ NEIr U0 Seismic Walkdown Checklist (SWC)

Equipment ID No. 274-013 Equip. Class, (10) AirHandlers Equipment Description 23 CNTMT FCU Interaction Effects

7. Are soft targcts free fi'om impact by nearby equipment or structures? Y[1 NEI UEI N/A0 All soft targets are located within the component's motor housing and are therefore protected from impact with other items.

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO NEI UE] N/A-1 and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YZ] NEI UE1 N/AU1 Rigid attachedpiping is seismically-analyzed.

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

of potentially adverse seismic interaction effects?

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriese/ Date: ,42 11' Michael Wodarcvk 12/3/2013 B-27

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WITI "'-OLD) FROW ,UBLI DISCLO-SURE UNDER 2.390 Sheet 3 of 4 Status: YO NEI UM-Seismic Walkdown Checklist (SWC)

Equipment ID No. 274-013 Equip. Class, (10) Air Handlers Equipment Description 23 CNTMT FCU Photographs Note: Overall view of component Note: External anchorage I Note: Pipingbehind component B-28

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS'WIT! 1HOLE) FROM PIJBLC- DISC'LOSURE UNDER 2-390 Sheet 4 of 4 SNote: uomponent internalswan timited view ot internal anchorage Note: Note:

B-29

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SU,,. - WITH, iLD F,*, vPULI, D,,,.LOSURE U,_DER 2.390 Sheet 1 of 3 Status: Y] NO UJ'-

Seismic Walkdown Checklist (SWC)

Equipment ID No. 2FT-464 Equip. Class, (18) Instruments on Racks Equipment Description MN STM FR 21 STM GEN CHNNL I RED F XMTR Location: Bldg. CNTM Floor El. _ Room, Area 2CNTM 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.

Anichorage

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

2. Is the anchorage fi'ee of bent, broken, missing or loose hardware? YOI NE] UE] N/AF"

3. Is the anchorage free of corrosion that is more than mild surface YZ NEI UE] N/Al]

oxidation?

4. Is the anchorage filee of visible cracks in the concrete near the anchors? YZ NEII u-] N/AE]

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

6. Based on the above anchorage evaluations, is the anchorage free of YO NEI UE]

potentially adverse seismic conditions?

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

B-30

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS! -,WITI HOLDE*, FROM ,ULIC DISCLOSURE UNDER 2.390 Sheet 2 of3 Status: Y[ N[- U-'

Seismic Walkdown Checklist (SWC)

Equipment ID No. sEquip.

2FT-464 Class (18) Instruments on Racks Equipment Description MN STM FR 21 STM GEN CHNNL I RED F XMTR Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO NEI UEI N/AL!

Soft targets are protected by overhead walkway grating. Temporary equipment in vicinity to be removed priorto Unit 2 restart.

8. Are overhead equilment, distribution systems, ceiling tiles and lighting, YLI N[] UF- N/AO and masonry block walls not likely to collapse onto the equipment?

No permanent overhead equipment.Temporary equipment in vicinity to be removed priorto Unit 2 restart.

9. Do attached lines have adequate flexibility to avoid damage? YO NEI UL! N/AEl Flexible conduit and stainless steel tubing are attached to component.

10. Based on the above seismic interaction evaluations, is equipment fi'ee YI NEI UE of potentially adverse seismic interaction effects?

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)

Evaluated by: Kyle Kriesel Date: A .2C /1" /K Michael Wodarcyk 12/4/2013 B-31

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSO - WIT' 11'OLD FREW U,*LI, DISLOSURE UNDER 2.390 Sheet 3 of 3 Status: YN NEI U[-

Seismic Walkdown Checklist (SWC)

Equipment ID No. 2FT-464 Equip. Class, (18) Instruments on Racks Equipment Description MN STM FR 21 STM GEN CHNNL I RED F XMTR Note: Nametag Note: Overall view of item on mounting plate Note: View of 2FT-464 (along with 2LT-461) on Note: Close-up with mounting plate and anchorage mounting plate B-32

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' ... L., FROM PUBLIC DISCLOsURE UNDER 2.390 Sheet I of 3 Status: YZ NO U-Seismic Walkdown Checklist (SWC)

Equipment ID No. 2LT-428 Equip. Class, (18) Instruments on Racks Equipment Description 2 PRZR (CHNL III-BLU)LVL XMTR Location: Bldg. CNTM Floor El. __ Room, Area 2CNTM 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 NEI of the 50% of SWEL items requiring such verification)?

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

3. Is the anchorage fiee of corrosion that is more than mild surface YED NDI U-- N/A[U oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Yl NDI U--1 N/AD

5. Is the anchorage configuration consistent with plant documentation? Yl0 NDI UD N/A (Note: This question only applies if the item is one of the 50% for whiich an anchorage configuration verification is required.)

Reference:

SEWS 2LT-428

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

Enter the equipment class name from Appendix 13:Classes of Equipment.

B-33

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SU.NSI - WIT.. 'OLD)FROM PU. LI- DISC-LOsU-RE UNDER 2.390 Sheet 2 of 3 Status: YE NEI UM Seismic Walkdown Checklist (SWC)

Equipment ID No. 2LT-428 Equip. Class, (18) Instruments on Racks Equipment Description 2 PRZR (CHNL III-BLU)LVL XMTR Interaction Effects

7. Are soft targets firee friom impact by nearby equipment or structures? YS NEI UE] N/A[I

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

9. Do attached lines have adequate flexibility to avoid damage? Y0 NEI UEi N/AU Flexible conduit and stainless steel tubing are attached to component.

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

of potentially adverse seismic interaction effects?

Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could YN NEI Ur-E adversely affect the safety finctions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel Date: /4/V Michael Wodarcvk 12/3/2013 B-34

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WITHHO....LD FROM PUBLI, DISC.LO.SURE UNDER 2.390 Sheet 3 Of 3 Status: Y10 NE] U((

Seismic Walkdown Checklist (SWC)

Equipment 1.D No. 2LT-428 Equip. Class' (18) Instruments on Racks Equipment Description 2 PRZR (CHNL III-BLU)LVL XMTR Photographs Note: Component mounted to wall Note: Upper anchorage Note: Lower anchorage Note: Component attachment to mounting plate B-35

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT',, 'OLD FROM PUBLI. DISCLOsURE UNDER 2.390 Sheet I of 3 Status: YM NEI U[I Seismic Walkdown Checklist (SWC)

Equipment ID No. 2LT-461 Equip. Class' (18) Instruments on Racks Equipment Description 21 STM GEN LOOP A CHNNL I-RED LVL XMTR Location: Bldg. CNTM Floor El. _ Room, Area 2CNTM Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdowvn 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? Yi NE] UE] N/AE1

3. Is the anchorage free of corrosion that is more than mild surface Y0 NEI Ur] N/Ar-oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YN NEI UEi N/AEr

5. Is the anchorage configuration consistent with plant documentation? YIM NE] urI N/AD (Note: This question only applies if the item is one of the 50% for

\vhich an anchorage configuration verification is required.)

Reference:

CalculationENG-CS-008

6. Based on the above anchorage evaluations, is the anchorage free of YNI NEI UE]

potentially adverse seismic conditions?

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

B-36

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS, - WTI lm .OLD FR-m PUBLIC DISCLOSURE UNDER 2.390 Sheet 2 of 3 Status: Y0 No- UF-Seismic Walkdown Checklist (SWC)

Equipment ID No. 2LT-461 Equip. Class' (18) Instruments on Racks Equipment Description 21 STM GEN LOOP A CHNNL I-RED LVL XMTR Interaction Effects

7. Are soft targets free fioom impact by nearby equipment or structures? YOl NEI UEON/AEl Soft targets areprotected by overhead walkway grating. Temporary equipment in vicinity to be removed priorto Unit 2 restart.

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YHI NEI UI] N/A0 and masonry block wvalls not likely to collapse onto the equipment?

No permanent overhead equipment.Temporary equipment in vicinity to be removed priorto Unit 2 restart.

9. Do attached lines have adequate flexibility to avoid damage? YU* Nil UrL N/Afl Flexible conduit and stainless steel tubing are attached to component.

10. Based on the above seismic interaction evaluations, is equipment fiee YU NEI UEi of potentially adverse seismic interaction effects?

Other Adverse Conditions 1 I. Have you looked for and found no other seismic conditions that could YED NEI UEH adversely affect the safety functions of the equipment?

Conmments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel 74*:7~Z Date: /,, /(/

Michael Wodarcyk 12/4/2013 B-37

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUP.. - WIT' 1'OLD FROM PUBLI_ DIS..LO.SURE UNDER 2.390 Sheet 3 of 3 Status: Y0 NEI U[]

Seismic Walkdown Checklist (SWC)

Equipment ID No. 2LT-461 Equip. Class' (18) Instruments on Racks Equipment Description 21 STM GEN LOOP A CHNNL I-RED LVL XMTR Photoolaphs Note: Nametag Note: Overall view of item on mounting plate Note: View of 2LT-461 (along with 2FT-464) on Note: Close-up with mounting plate and anchorage mounting plate B-38

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS'- WIT' 1IOLD FROM PUBLIC DISCLODSURE UNDER 2.390 Sheet 1 of 5 Status: Yo NEI- UL--

Seismic Walkdown Checklist (SWC)

Equipment ID No. B25/LOAD SEQ CAB Equip. Class' (20) Instrumentation and Control Panelsand Cabinets Equipment Description BUS 25 SFGDS LOAD SEQUENCER CABINET Location: Bldg. D5/D6 Floor El. __ Room, Area 25 BUS 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.

Anchor age I. Is the anchorage configuration verification required (i.e., is tie item one YEI NID of the 50% of SWEL items requiring such verification)?

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

Stitch welded to embed plate.

3. Is the anchorage fiee of corrosion that is more than mild surface YO NEI UE- N/Al]

oxidation?

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

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

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

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

B-39

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS! - WITI 1-)LD FROMr- PUBLIC DISCLOSURE UNDER 2.39E) Sheet 2 of 5 Status: YI* Nr-- UD" Checklist (SWC)

Seismic Walkdown Equipment ID No. B25/LOAD SEQ CAB Equip. Class' (20) Instrumentationand Control Panelsand Cabinets Equipment Description BUS 25 SFGDS LOAD SEQUENCER CABINET Interaction Effects

7. Are soft targets free fi'om impact by nearby equipment or structures? YO NEI- Ur N/AQ

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

S-hooks on lighting were crimped shut.

9. Do attached lines have adequate flexibility to avoid damage? YN NEI Ur- N/Al]

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

Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could YED NEl Ui-adversely affect the safety finctions of the equipment?

Comments (Additional pages may be added as necessary)

Interiorof the cabinet was inspected. It was noted that somesmall plastic terminal covers were missing some screws. These covers were also retained by wire rings so do not represent a hazard.AR 1401059 was initiated.

Evaluated by: Kyle Kriesel Ax Date: /,.2- ý/-

Dilee pCherlopalle r-.\?.-b 1 * ,eK.o .ge A _ 1- 2~L~.-'~

B-40

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report IUI tkU;VI I "UULt1; UjIt.7LUbU;l t t*Uti ( Z.J!JU b U N0 - VVII1 111ktt Status: YZ Nn U[-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. B25/LOAD SEQ CAB Equip. Class' (20) Instrumentation and Control Panels and Cabinets Equipment Description BUS 25 SFGDS LOAD SEQUENCER CABINET Photographs Note: BUS 25/Load Sequencer Cabinet Note: BUS 25 / Load Sequencer Cabinet welded to embed plate Note: Area above BUS 25/Load Sequencer Note: Area above BUS 25/Load Sequencer Cabinet Cabinet B-41

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Note: Interiorof BUS 25 / Load Sequencer Cabinet B-42

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

'Load Sequencer Cabinetl Note: Interiorof BUS 25 / Load Sequencer Cabinet Note:

B-43

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS, -oW ITH* ,, r-,D F--R-EW .-.,or. -. oUR

-.. ..- DI , U- BE- 2.390 ,,, Sheet i of 6 Status: Y0 NE[--I U[--

Checklist (SWC)

Seismic Walkdown Equipment ID No. BUS 212 Equip. Class, (02) Low Voltage Switchgear Equipment Description BUS 212 480V SWITCHGEAR Location: Bldg. D5/D6 Floor El. _ Room, Area 211/212 BUS 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.

Anchorap_e

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

2. Is the anchorage fiee of bent, broken, missing or loose hardware? YO NEI UF] N/Al]

3. Is the anchorage fiee of corrosion that is more than mild surface YO* NEI U-] N/Ar]

oxidation?

4. Is the anchorage firee of visible cracks in the concrete near the anchors? YO NEI UE] N/AL]

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

6. Based on the above anchorage evaluations, is the anchorage free of YO NEI U]

potentially adverse seismic conditions?

Enter the equipment class name from Appendix B: Classes ofEquipment.

B-44

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' WIT' 11lE, -,M ,PUBLICDIsCLOsUR-,UNDER 2.390 Sheet 2 of 6 Status: YO NEI[ U[-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. BUS 212 Equip. Class, (02) Low Voltage Switch-gear Equipment Description BUS 212 480V SWITCHGEAR Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO NEI Ui] N/AE Equipment currently out of service for outage maintenance

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

Lighting S-hooks are crimped.

9. Do attached lines have adequate flexibility to avoid damage? YO NEI UO N/AU

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

Other Adverse Conditions 1 I. Have you looked for and found no other seismic conditions that could YO NEI Ui]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Interiorof the switchgear was inspected and found to be free of adverse seismic conditions. Fuses were not in the base of one of the cubicles, but are related to the current out of service condition for the outage. They are bagged as part of the process.

Evaaluated by: Kyle iesel Date: /I __ ____

/1 00, Dileep Cherlopalle C '. t-;\k~e 1- 2-4~- 11 B-45

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSI - WITI n rOrLD PUBLIC nROIM DISlClSURE UNDER 2.390 Status: Y[ N((1 UD--

Seismic Walkdown Checklist (SWC)

Equipment ID No. BUS 212 Equip. Class, (02) Low Voltage Switch-gear Equipment Description BUS 212 480V SWITCHGEAR Photographs Note: BUS 212 Note: Area above BUS 212 Note: Area above BUS 212 Note: Area above BUS 212 B-46

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSI WIT'HHOl-LD r Rm PUBLIC DISCLOSURE UNDER 2.390 Note: Interiorof BUS 212 B-47

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS: WITH' ILD

"- FROM -U.LI, DISCLOsURE UNDER 2.390 Note: Intenor o0 bU;3 212 Note: Interiorof BUS 212 B-48

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report UNSI - WII II I'OLD FROM IUBLI DISCLOSURE UNDER 2.390 Note: Interior of Note: Intenor ot bU, 212 Note: Interiorof BUS 212 B-49

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS!- WIT!1 IOL:D FREM PUBLIG DISCLOSURE UNDER 2.390 Sheet 1 of 5 Status: YEI- NO UI--

Seismic Walkdown Checklist (SWC)

Equipment ID No. BUS 26 Equip. Class' (03) Medium Voltagie Switch gear Equipment Description BUS 26 4.16KV SWITCHGEAR Location: Bldg. D5/D6 Floor El. ___ Room, Area 26 BUS 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 YEI NM of the 50% of SWEL items requiring such verification)?

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

3. Is the anchorage free of corrosion that is more than mild surface Y[ NEI U-I N/ALE oxidation?

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

Switchgear welded to embedded steel

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

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

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

B-50

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' -^,,T' 1 . FREW rrG. ,ULG.- .- N.DE., 2*..*..*,r*.390 Sheet 2 of 5 Status: YLI NOI UI-Seismic Walkdown Checklist (SWC)

Equipment ID No. BUS 26 Equip. Class' (03) Medium Voltagie Switch gear Equipment Description BUS 26 4.16KV SWITCHGEAR Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO* NEIlJur-- N/A[-I YD ND UEr- N/AD

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

One light fixture just West of Cubicle 26-17 has an open S-hook on one end. If vertical g levels high enough, the light fixture could come loose from that end and strike end cubicle, causing relays to trip. See CAP 1352001 (correspondingWR 83556 generated).

YL N[l U-] N/A-1

9. Do attached lines have adequate flexibility to avoid damage?

YI- NED UD-/A

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 YO NDI UD--

adversely affect the safety finctions of the equipment?

Comments (Additional pages may be added as necessary)

Internal inspection performed on 16 of 17 cubicles. Cubicle 26-13 protected by Operations.Danger tag closed; confirmed with Operations.

All cubicles bolted to each other with sufficient number of bolts so that switchgearacts as a unit.

Cubicles 26-11, 26-12, 26-16, and 26-17 have a knife switch anchored using 2 screws, despite there being 4 mounting holes. All other cubicles are mounted with 4 screws. See CAP 1405313. Vendor review of the vendor-assembled and -supplied equipment determined that the two screws in the various configurations found in the field were sufficient to meet seismic requirements.

B-51

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Sheet 3 Of 5 SUNS' -IT'VVriI11IO*LD FROM PUBLIC) DISCLOSUJRE UNDER 0-390Sheof Status: YE- NO UM Seismic Walkdown Checklist (SWC)

Equipment ID No. BUS 26 Equip. Class' (03) Medium VoltaQe Switchcqear Equipment Description BUS 26 4.16KV SWITCHGEAR Evaluated by: Dennis Zercher Date: 11/4/2013

a. =

Bruce LorV 11/4/2013 B-52

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Sheet 4 of 5 PUBLIC DISCLOSURE UNDER 2.390 , hef4O SUNS'l WITI II I1"LD FRO Status: YE] No U--

Seismic Walkdown Checklist (SWC)

Equipment ID No. BUS 26 Equip. Class' (03) Medium Voltage Switchgear Equipment Description BUS 26 4.16KV SWITCHGEAR Photographs Note: Exteriorview of Cubicle 26-1 1No0e: *nine SWlCn irnsIoe UUoile ZO- -I wlun Z oU q l4Ore:

N lypIal welu ancrjoiage mounting screws (CAP 1404924)

B-53

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Sheet 5 of 5

~!~!I II 1111 I I I I! hI~:I II ii l-I4 Note: Typical bolts connecting adjacent cubicles Note: Light fixture with open S-hook (CAP 1352001)

B-54

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSI

. - WIT' v OLD FROM

,ULI, D.S.LOS,,RE UNDER 2.390 Sheet 1 of 3 Status: Y[D NE] U-Seismic Walkdown Checklist (SWC)

Equipment ID No. CV-39417 Equip. Class, (7) Fluid-OperatedValves Equipment Description 22 CRDM SHRD CLG COIL SPLY CV Location: Bldg. CNTM Floor El. _ Room, Area 2CNTM Manufacturer, Model, Etc. (optional but recommended)

Instrnctions 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 folIlowing 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 YEI NO of the 50% of SWEL items requiring such verification)?

In-line component

2. Is the anchorage free of bent, broken, missing or loose hardware? YEI NEI Ur] N/AO

3. Is the anchorage fiee of corrosion that is more than mild surface YEI] NI U-] NWAS oxidation?

4. Is the anchorage fiee of visible cracks in the concrete near the anchors? YEI ND UE- N/AO

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

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

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

B-55

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

,., NS, - ........ ,.,ILD, ,FR.,O , PU, .... I ...... ... UNDE 2,.390

• Sheet 2 Of 3 Status: YO NEI U[

Seismic Walkdown Checklist (SWC)

Equipment ID No. CV-39417 Equip. Class' (7) Fluid-OperatedValves Equipment Description 22 CRDM SHRD CLG COIL SPLY CV Interaction Effects

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

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO NEI UiI N/AU and masonry block wvalls not likely to collapse onto the equipment?

Temporary equipment in vicinity to be removed priorto restarting Unit 2. Component is protectedfrom overhead equipment by large aux.

steel for pipe support.

9. Do attached lines have adequate flexibility to avoid damage? YO NEI UF] N/AEU Flexible conduit and stainless steel tubing are attached to component.

10. Based on the above seismic interaction evaluations, is equipment fi'ee YZ NI UUU of potentially adverse seismic interaction effects?

Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could YZ Nn- UE]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel Date:

Michael Wodarcvk 12/3/2013 B-56

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' 1,IOLD FROMPUBLIC DISCLO-SURE UNDER 2.390 Sheet 3 of 3 Status: YZ NE UL-Seismic Walkdown Checklist (SWC)

Equipment ID No. CV-39417 Equip. Class' (7) Fluid-OperatedValves Equipment Description 22 CRDM SHRD CLG COIL SPLY CV Photop-raphs Note: Overall view of valve B-57

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' IHOLD FRFOM PUBLIC, DISL.,SU -EUNDER 2.390 Sheet Iof 3 Status: YN NE] UL-Seismic Walkdown Checklist (SWC)

Equipment ID No. CV-39419 Equip. Class' (7) Fluid-OperatedValves Equipment Description 21 CRDM SHRD CLG COIL SPLY CV Location: Bldg. CNTM Floor El. __ Room, Area 2CNTM 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 I. Is the anchorage configuration verification required (i.e., is the item one YEr NED of the 50% of SWEL items requiring such verification)?

In-line component

2. Is the anchorage fi'ee of bent, broken, missing or loose hardware? YEI NE] UE] N/A[D

3. Is the anchorage fi'ee of corrosion that is more than mild surface Y[-- NEI UL] N/A[D oxidation?

4. Is the anchorage firee of visible cracks in the concrete near the anchors? YEI NEI UrL N/AIl

5. Is the anchorage configuration consistent with plant documentation? YEI NEI UE1 N/AO (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 fiee of YZ] NEI UDI potentially adverse seismic conditions?

Enter the equipment class name from Appendix B: Classes ofEquipment.

B-58

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT! ILD

. FROM

. . DISCLSURE

.ULI. UNDER 2.390 Sheet 2 of 3 Status: YE NEI U[-M Seismic Walkdown Checklist (SWC)

Equipment ID No. CV-39419 Equip. Class, (7) Fluid-OperatedValves Equipment Description 21 CRDM SHRD CLG COIL SPLY CV Interaction Effects

7. Are soft targets fiee from impact by nearby equipment or structures? YZ NEI UI] N/AI-

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO Ni] UE] N/AL!

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

9. Do attached lines have adequate flexibility to avoid damage? Y0 NEI Ut] N/AL Flexible conduit and stainless steel tubing are attached to component.

10. Based on the above seismic interaction evaluations, is equipment free Y0 NEI UE]

of potentially adverse seismic interaction effects?

Other Adverse Conditions I1. Have you looked for and found no other seismic conditions that could YED NE- Ur]

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel Date: __ / e/ _

MihelWc/rv 12/3/20 13 Michael Woda vk B-59

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS- WT' 1 'LD-FROM PU ,*,, ,,-, LO E UN,-E, 2,.390, Sheet 3 of 3 Status: Y[ NEI U["]

Seismic Walkdown Checklist (SWC)

Equipment ID No. CV-39419 Equip. Class' (7) Fluid-OperatedValves Equipment Description 21 CRDM SHRD CLG COIL SPLY CV Photogiraphs Note: Overall view of valve Note: Note:

B-60

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSI - WITI II IOLD FIR -M PUBLIC DISCL*OSURE UNDER 2.390 Sheeti of 6 Status: Y[l] NN u[]

Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2K2 Equip. Class' (01)) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2K BUS 2 Location: Bldg. AUX Floor El. __ Room, Area NORTH 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 YED NEIl of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YO NEl UEi N/All

3. Is the anchorage free of corrosion that is more than mild surface YZ NI] Ui] N/AEl oxidation?

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

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

Referenced SQUG SEWs for anchorage verification. Anchor patterns match the SEWs.

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

IEnter the equipment class name firom Appendix B: Classes or Equipment.

B-61

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SeUPll + I--L. FROM PU -' U, I, rSE-R,,

- WlIT' -,,UNDER 2.390 Sheet 2 of 6 Status: YLJ N[ U[-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2K2 Equip. Class' (01)) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2K BUS 2 Interaction Effects

7. Are soft targets fi'ee firom impact by nearby equipment or structures? YO~ NEI ULI N/Afl

8. Are overhead equilment, distribution systems, ceiling tiles and lighting, Y9 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? YZ NEI U-] N/AE]

10. Based on the above seismic interaction evaluations, is equipment fr'ce Y-I NE UE]

of potentially adverse seismic interaction effects?

A 1" copper line runningjust in front of MCC 2K BUS 2 is rod hung with no braces. It can swing during an earthquakeand touch the MCC, but the SWEs judged it would not affect the safety function of the equipment.

Plantengineering evaluated this observation, and concluded that a similarissue with MCC 2K2 was documented as a potentialoutlieras part of the resolution to USI A-46. The condition is evaluated in calculationENG-CS-098 for a drain line 4" from the MCC. As this condition is 6" from the MCC, there are no impacts to this MCC.

Other Adverse Conditions

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

B-62

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' -,WIT', ,-LD FROM PUBLI- DISLOSURr ,UNDER-2.390 Sheet3of6 Status: YE] ND UE-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2K2 Equip. Class' (01)) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2K BUS 2 Comments (Additional pages may be added as necessary)

Interiorof the MCC was inspected.

1. A 1" copper line hanger rod is touching the chilled water valve (2ZX-4-22).

Plantengineeringevaluated this observation and concluded that the configurationis acceptable.

2ZX-4-22 is not safety related and not seismically qualified. The minimal contact between the rod hanger and the valve is acceptablebecause the swaying force the hangercould produce in a design basis earthquake would be well below the force requiredto damage the valve. If during a seismic event the hangerwere to hit the valve and break, the other hangersalong the 1" copper drain line would be able to pick up the additionalload. The additionalload from the copper line would be distributed to a hanger6' to the left and 8' to the right of the hanger in question.

2. The 300 gallon tank collecting dischargefrom the 1" copperdrain line is on the floor next to a 55 gallon barrelon the floor. These are not tied down and in a seismic event these may break or tip over and cause flooding in the area.

Plant engineering evaluated this observation and concluded that it is a housekeeping concern, and not a seismic issue. CAP 1352563 was initiatedto address this condition.

3. There is a missing nut for one of the 8 anchors on the base plate for the ductwork support in front of MCC 2KA BUS 2.

CAP 1352623 was initiated to document the observation and WR 83731 was initiated to replace the nut Evaluated by: Dileep Cherlodalle c. J. tA. *..4_A*, Date: 2.-

-3 2

Bruce Lorv 9/20/2012 B-63

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUP,, ,,-,OLD

-,WITI FREW

, U- LI, DISCL.OSURE UNDER 2.390 Sheet4of6 Status: YE] NN Uf-Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2K2 Equip. Class, (01)) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2K BUS 2 Photographs Note: Front of MCC with 1" copperpipe Note: Side of MCC with 1" copperpipe Note: Side of MCC with 1" copperpipe B-64

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

.Q'NI C nim.i! .l5p IFF InF*?

WU!T-i" iC-Ifl f F-PClM PWA 1PI

-H~ 9 _oQn Sheet5of6 Note: Pipe hangertouching chilled water valve Note: Unrestrainedtank and drum 2ZX-4-22 B-65

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Sheet 6 of 6 SUP461 - WIT' 11'OLD FROM PUBLIC DISCLOSURE UNDER 2.390 Note: Duct supportbase plate with missing nut Note:

Note: Note:

B-66

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUo, I - WIT'HH,,OLD FR- ,ULI, DISCLOSURE UNDE-R 2.390 Sheet 1of 3 Status: YO N[-] U[-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2L2 Equip. Class' (01) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2L BUS 2 Location: Bldg. AUX Floor El. __ Room, Area NORTH 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 YO NEI of the 50% of SWEL items requiring such verification)?

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

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

oxidation?

There is minor surface oxidation on rearanchorunder the cell A3, B3, A5, B4, C4, and D4 for the MCC 2L BUS 2. It is not a seismic concern.

4. Is the anchorage free of visible cracks in the concrete near the anchors? YZ NEI UE] N/AUl

5. Is the anchorage configuration consistent with plant documentation? YO NEI UE] N/A[-]

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

The SWEs referenced the SQUG SEWs for anchorageverification.

The anchorbolt pattern matches with the documentation in the SEWs.

6. Based on the above anchorage evaluations, is the anchorage free of YOI N[] UE]

potentially adverse seismic conditions?

I Enter the equipment class namie from Appcndix B: Classes of Equipment.

B-67

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' ,,'OLD FROM PUBLIC DISCLOSURE UNDER 2.390 Sheet 2 of 3 Status: YO NEI UI--

Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2L2 Equip. Class' (01) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2L BUS 2 Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO ND UDJ N/AU

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO NE UD N/AU and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YO NO UD N/AD

10. Based on the above seismic interaction evaluations, is equipment free Y0 NEI U of potentially adverse seismic interaction effects?

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Interiorof the MCC was inspected.

A small piece of tie wire was found under the cell A5 at the anchorbolts. It is a housekeeping concern, and not a seismic issue.

CAP 1352321 was initiatedto evaluate the housekeeping issues identified during these walkdowns.

Evaluated by: Dileep Cherlopalle C-- V. ~Q~~\~~ Date: I- "4'! - It.

Bruce Lorv 9/20/2012 B-68

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS - FROM PUBLIC DISCLOSURE UNDER 2.390 Sheet 3 of 3 WIT' -IHOLD Status: YO Nn-] U-'

Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2L2 Equip. Class' (01) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2L BUS 2 Photoeraphs I

Note: Front of MCC B-69

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' 'OLD FRM ,PU

,- ,LI DISCLOSURE UNDER 2.390 Sheet 1 of 6 Status: YZ NE] U--

Seismic Walkdown Checklist (SWC)

Equipment IDNo. MCC 2LAI Equip. Class' (1) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2LA BUS I Location: Bldg. AUX Floor El. __ Room, Area J.2/12.5 (Aux Bldq south of stairs)

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

i. Is the anchorage configuration verification required (i.e., is the item one YED N[]

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

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

3. Is the anchorage free of corrosion that is more than mild surface YS NH! UHI N/AEU oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YED NEI UHI N/AUI Observed concrete cracking was included in SEWS data and previously evaluated.

5. Is the anchorage configuration consistent with plant documentation? YNl NHI UHI N/AHI (Note: This queslion only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Review of USI A-46 SEWS data. Plantdrawings NF-38300-1 and NF-38315-4. MCC is welded to embed steel with added anchorage by Design Change 97EB01.

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

Enter the equipment class name fiom Appendix B: Classes of Equipment.

B-70

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS WIT! ,, !OLD FROM PUBLIC DISCLOSURE UNDER 2.390 Sheet 2 of 6 Status: YZ NEI UE-Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2LAI Equip. Class, (1) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2LA BUS I Interaction Effects

7. Are soft targ*ts free from impact by nearby equipment or structures? YO ND UD- N/AD

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO NDI UD- N/AD" and masonry block walls not likely to collapse onto the equipment?

No open S-hooks were observed.

9. Do attached lines have adequate flexibility to avoid damage? YO ND UD N/AD

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

Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could YED NDI UD-adversely affect the safety finctions of the equipment?

Comments (Additional pages may be added as necessary)

Interiorof the MCC was inspected and found to be free of adverse seismic conditions.

Evaluated by: Kyle Kriesel /4ýý 4;;Z125 Date: /I ,Y, ,IK/

Dileen Cherlonalle i' -%.. t;\p%ý%, o -- %

jd B-71

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' WIT'I11OELD FROM PUBLIC DISCLOSURE UNDER 2.390 Status: YX N--- UD--

Seismic Walkdown Checklist (SWC)

EquipmentoIDhNo. MCC2LA - Equip. Class, (1) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2LA BUS 1 Photographs Note: MCC 2LA 1 Note: Interiorof MCC 2LA I Note: Interiorof MCC 2LA 1 Note: Interior of MCC 2LA 1 B-72

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT!HH OLD FROM PUBLIC DISCLOSURE UNDER 2.390 Note: Interiorof B-73

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report IA~l-l' II "\ I rr*l

"- l *r r"C*l e% i**r- I IKlr' rf- r,fir"

,-*'I

%J~h I.KIrI

%-j ji - v v I I Iii...L

'* -r-,r"r. A I I %....IV, I

' I mI WJ- I~. ~ ~ L~.t~ L. JI1~

Note: Anchorage for MCC 2LA I I

I Note: INote: MU(L ZLA 7 wetoect to emoec steei B-74

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

~JLJI '4.JE -

~uI.*lI ~

t\ -Nr I-i r~ am IS Er -NO',rC' nn V VI I I SI I~..JL.L/ I I ~'..JVI I ~JLJL.I'...i L~I~J~..jLA..~iJiJI ~L IINlk~-flfr I,

~JI '4LJS.....I~ ~.J~flJ Note: Area near MCC 2LA 1 Note: Area above/nearMCC 2LA I Note: Area above / near MCC 2LA I Note:

B-75

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SU-.SI - WIT' 1 OLD FROM-PUBLI DISCLOSURE UNDER,2.390 Sheet iof 6 Status: YZ NEI UI'I Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2M1 Equip. Class' (1) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2M BUS I Location: Bldg. AUX Floor El. __ Room, Area G. 7/13.8 (Aux Bldg near 22 SBV Exh Ftr)

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

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

3. Is the anchorage free of corrosion that is more than mild surface YN] NEI Ul- N/AD" oxidation?

4. Is the anchorage fi'ee of visible cracks in the concrete near the anchors? YO NE] UI- N/A[]

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

Plant drawingsNF-38301-1 and NF-38315-9 are used.

6. Based on the above anchorage evaluations, is the anchorage firee of YO NI- UE1 potentially adverse seismic conditions?

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

B-76

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' WIT'-, !OLD FROM r U- LIG DISCLOSU*RE UNDER 2.30o Sheet 2 of 6 Status: YO NEI U-l Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2M1 Equip. Class' (1) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2M BUS 1 Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO NEI Ur N/AU

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YO NE] UU- N/A[

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

No open S-hooks observed.

9. Do attached lines have adequate flexibility to avoid damage? YO NOI Ur N/AU

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Interiorof the MCC was inspected and found to be free of adverse seismic conditions.

i J

Evaluated by: Kyle Kriesel AV11t1--1A9X-ý A[

• p" Date: X,2,, *"

Wieep Cherlooalle c,- j.-t\ ,eg ?A- I - L B-77

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSI - VII II IOLD FROM PUBLIC DISCLOSURE UNDER 2.390 Status: YZ N[-- U[-

Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2M1 Equip. Class' (1) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2M BUS 1 Photographs Photographs Note: MCC 2M1 rNote: intenor or IVI.uLZVIVP Note: Interior of MCC 2M1 B-78

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report I l'l IA IA I II Ir'I r\ - " a M' Mu r'*l M r-"*'n r% lI -" r I I Ir" rr- ' I ,,fl"I

ý~lJIj IjI - v VI I I III.LL . I I %ýIJvI I .. Lý I. -~~lJ -- - fl-J -. I

• Note Note: Interiorof MCC 2M1 I Note: Anchorage tor Mu( ZM7 B-79

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

~~~~l~~~r~~j~~~;I~

III-I 111 - 11 P.' 1 u Ii i IIZI H IiA EZIjj I~Ii Note: Anchorage for MCC Note: Anchorage for MCC 2M1 I oee: /ncnorage ror iviuu ziviI B-80

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report Note: Area near MCC 2M1 Note: Area above MCC 2M1 Area near MUG 2M1 Note:

B-81

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

,,, , W

, IT'-- , , ,-, ,,-,,

PUBLIC) ,-, , ,- , ,,-2,3,,9,,-,-, " Sheet 1 of 5 Status: Y[* N[--] U[-

(SWC)

Seismic Walkdown Checklist Equipment ID No. MCC 2X1 Equip. Class' (1) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2X BUS 1 Location: Bldg. AUX Floor El. _ Room, Area J.3/12.8 (Aux Bldg south of stairs)

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

2. Is the anchorage firee of bent, broken, missing or loose hardware? YO NEI U[] N/AEl

3. Is the anchorage free of corrosion that is more than mild surface YI0 NI] UE] N/AL]

oxidation?

4. Is the anchorage firee of visible cracks in the concrete near the anchors? YO NEI UE- N/Al]

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

6. Based on the above anchorage evaluations, is the anchorage free of Y[D NEI UE]

potentially adverse seismic conditions?

Cabinet is anchored at the base and to adjacentcabinet.

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

B-82

e Island Nuclear Generating Plant - Unit 2 ated Seismic Walkdown Submittal Report SllNSI - WITI I-LD FROM PU. LIC DISiL OS,*RE ,N-DER2.390 Sheet 2 of 5 Status: YZ NO Ur-1 Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2X1 Equip. Class' (1) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2X BUS 1 Interaction Effects

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

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y(9 NEI Ur- N/AEl and masonry block walls not likely to collapse onto tile equipment?

Noted S-hooks on lighting fixture adjacent to the MCC cabinet were not crimped. This was previously addressedin the AWC for this area.

9. Do attached lines have adequate flexibility to avoid damage? Y0D NE UE] N/AD

10. Based on the above seismic interaction evaluations, is equipment five YO NEI UE of potentially adverse seismic interaction effects?

Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could YO NEI UQ adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Interiorof the MCC was inspected and found to be free of adverse seismic conditions.

Evaluated by: Kyle Kriesel 144"Aý Date: /,,2 Dileep Cherloalle C.V.

B-83

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS'. - VWlI IIIIH IO U IFROMV I ULIG DISC*LOSVUREL. UINDERI 2..,90 Status: Y[ NrI U --

Seismic Walkdown Checklist (SWC)

Equipment ID No. MCC 2X1 Equip. Class' (1) Motor Control Centers Equipment Description MOTOR CONTROL CENTER 2X BUS 1 Photozraphs 1w Sj Note: MCC 2X1 Note: Interiorof MCC 2X1 Note: Interiorof MCC 2X1 B-84

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - lII I IOLID FROM PUBLIC DISCILO)SURE UNDER 2.390 Note: Interior of MCC 2X1 rNote: 1-mcnorage torIVIL, L zA i Note: Anchorage for MCC 2X1 Note: Area above /near MCC2X1 B-85

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report r-1 IH5PI - X.A!ITI 1119)1 Ml r-PCflM P1 1PR1 IP. flI5W'. 9fl5 IRF 1 IA-flFP !DqQf Note: Area above / near MCC2X1 Note: Area above /near MCC2X1 Note: Note:

B-86

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' -, 'OLD FROM r U-LIC DISCLOSURE UNDER 2.390 Sheet I of 3 Status: YO N-" Ur Seismic Walkdown Checklist (SWC)

Equipment ID No. MV-32156 Equip. Class' (8) Motor-Operatedand Solenoid-Operated Valves Equipment Description 24 FCU CLG WTR OUTL ISOL MVA Location: Bldg. CNTM Floor El. _ Room, Area 2CNTM 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] NZ of the 50% of SWEL items requiring such verification)?

In-line component

2. Is the anchorage firee of bent, broken, missing or loose hardware? Y]i NOI Ul- N/A0D

3. Is the anchorage free of corrosion that is more than mild surface YEI NEI UE] N/A0 oxidation?

4. Is the anchorage firee of visible cracks in the concrete near the anchors? YI- NEI UEI N/A0

5. Is the anchorage configuration consistent with plant documentation? YEI NOI UE] N/AO (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 fi'ee of YZ NO UE]

potentially adverse seismic conditions?

I Enter the equipment class name from Appendix 13:Classes of Equipment.

B-87

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT'

,, IOLD-ULIG FROM DISLO*,SURE UNDER 2.390 Sheet 2 of 3 Seismic Walkdown Checklist (SWC) Status: YO NE] U[]

Equipment ID No. MV-32156 Equip. Class, (8) Motor-Operated and Solenoid-OperatedValves Equipment Description 24 FCU CLG WTR OUTL ISOL MV A Interaction Effects

7. Are soft targets free friom impact by nearby equipment or structures? YEO NE] U0] N/AZ All targets are robust

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

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

Overhead light fixture is conduit-mounted.

9. Do attached lines have adequate flexibility to avoid damage? YZl NEI UE] N/A--

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

of potentially adverse seismic interaction effects?

Other Adverse Conditions i1. Have you looked for and found no other seismic conditions that could YE NE] UE]

adversely affect the safety finctions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriese/ Date: 2 I/

Michael Wodarcvk 12/3/2013 B-88

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

~i- ~*- ~U r~ ii. is i~c'ri CC'lID= 1 IKflnrrl n - -

bt W11- 11 1IULLJ I- M - L.. .JI Sheet 3 of 3 Status: YM NEIr Ur-Seismic Walkdown Checklist (SWC)

Equipment ID No. MV-32156 Equip. Class, (8) Motor-Operatedand Solenoid-OperatedValves Equipment Description 24 FCU CLG WTR OUTL ISOL MV A Photo! raDhs Note: Overall view of valve Note: Note:

B-89

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT'

,1-IOLD FROM PUBLIC DISCLOSURE UNDER 2.390 Sheet 1 of 5 Status: Y* N[-- U[--

Checklist (SWC)

Seismic Walkdown Equipment ID No. PNL 21 Equip. Class' (14)DistributionPanels Equipment Description DISTRIBUTION PANEL 21 Location: Bldg. TURB Floor El. __ Room, Area 21 BATT Manufacturer, Model, Etc. (optional but recommended)

Instructions 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 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.

Anchorap-e

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y0l NHI UEi N/AlQ

3. Is the anchorage free of corrosion that is more than mild surface Y[ NHI UE] N/AE]

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y[D NEH UH] N/AE]

5. Is the anchorage configuration consistent with plant documentation? Y[9 NEI UH N/AH1 (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Referenced SQUG SEWS and verified bolts. Anchorage details in calc ENG-CS-098 also used for reference.

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

potentially adverse seismic conditions?

IEnter the equipment class name From Appendix B: Classes of Equipment.

B-90

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSI WIT,!, , ,LD FROM PUBLIC DISLOSU, E UNDER 2.390 Sheet 2 of 5 Status: YZ NEI UE]

Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 21 Equip. Class' (14)DistributionPanels Equipment Description DISTRIBUTION PANEL 21 Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y0 NE] UO N/AOZ

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Yo NEI UC- N/Al]

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

9. Do attached lines have adequate flexibility to avoid damage? Y0 NO UO N/AD

10. Based on the above seismic interaction evaluations, is equipment free YO NO U0 of potentially adverse seismic interaction effects?

Other Adverse Conditions II. Have you looked for and found no other seismic conditions that could YO NOI Ull adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Initialwalkdown was performed as part of original scope. The remaining walkdown to inspect the interiorof the panel was deferred to the Outage schedule based on the need to open the panel Interiorof the panel was inspected. There were some small adhesive cable ties which are no longer attached to the cabinet. There was no equipment for the loose cable to impact in this area of the cabinet and is acceptable.

Evaluated by:. Date: \-4 * - ".

/t .2c B-91

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SN'-WIT

........ FREW UR ,.,LI UNDE

...... 2.390 Status: YZ NFl UD--

Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 21 Equip. Class' (14)Distribution Panels Equipment Description DISTRIBUTION PANEL 21 Photographs Note: Panel 21 Note: Area above Panel 21 Note: Panel 21 Note: Panel 21 B-92

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report r'I ImIeI" IAII'II II F% Mi r=llZ IM ^1 r% ei%^ P" ei'l i r- I *I*Ir= rrn ,

Note: Interiorof Panel 21 Note: Interiorof Panel 21 Note: Interiorof Panel21 Note: Interiorof Panel 21 B-93

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WITHI 1IOLD FROM PUBLIC DISCLOSURE UNDER 2.390 Note: Interior of Panel 21 rNote: -AncnorageTor r-'anei z*i B-94

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSI - WIT'I IILI O FROM PUBLIC DISCLO*SURE UNDER 2.390 Sheet.of 3 Status: YN NEI U-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 213 Equip. Class' (14) DistributionPanels Equipment Description INSTRUMENT BUS Ill PANEL (BLU) 213 Location: Bldg. TURB Floor El. __ Room, Area RELAY 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 Y[I] NZ of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YO NE UL N/AD

3. Is the anchorage fiee of corrosion that is more than mild surface YO NE UD] N/AD oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YO NEI UE] N/AL]

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

6. Based on the above anchorage evaluations, is the anchorage free of YO NE UE1 potentially adverse seismic conditions?

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

B-95

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS,, WT,

,,,- 'OLD FR'OM- r-, ,, -,r UNDER

,r-Sheet 2,390,, 2 of 3 Status: Y0 NEI UE]

Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 213 Equip. Class, (14) DistributionPanels Equipment Description INSTRUMENT BUS Ill PANEL (BLU) 213 Interaction Effects

7. Are soft targets flee from impact by nearby equipment or structures? YO NE UD N/AD Telephone receiver to the left of panel could potentiallyfall from its cradle and strike the panel during a seismic event The panel body is robust and the phone receiver is light; the panel body and the electrical components inside would not be negatively affected by such an impact.

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

9. Do attached lines have adequate flexibility to avoid damage? YO NOI U0 N/AU

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Interiorof the panel was inspected and found to be free of adverse seismic conditions.

P110oai,,

ILJ y I;Itl l*l (,,I I,* *,l htp F,, Miton I;.5.I J.J C'hnrhnnoIMn 1.'! FtItl,,, - ' AA(MJ) .k '.A.A. K~Ztj&L A Date: 1_-1__\4 __

Michael Wodarcvk ( 10/24/2013 B-96

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUINSI - WIT'" I LD FROM PU"II ,- DISCLO,-SURE UNDER 2.390 Sheet 3 of 3 Status: YM NI] UFl Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 213 Equip. Class' (14) DistributionPanels Equipment Description INSTRUMENT BUS IlI PANEL (BLU) 213 Photographs Note: Panelexternals Note: Panel internals Note: Upper 2 anchorbolts B-97

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WITI IIlILD F*RNHNA i- ii to 0C DISCLO*URE UNDER 2.390 Sheet 1of 4 Status: YN NEI UL-Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 235 Equip. Class, (14) Distribution Panels Equipment Description AC DISTRIBUTION PANEL 235 Location: Bldg. AUX Floor El. __ . Roomn, Area NORTH WEST Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checldist This checklist may be used to document the results of the Seismic Walkdowvn 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 YEI] NOI of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YO NEI UI- N/AEl The bottom-left anchor seems to have a gap (1/8') between the wall and anchor head. In its currentconfiguration,it is not effective under seismic loading and needs to be tightened or the anchorcalculation revised to show it is seismically adequatefor three bolts.

Site engineering review determined the gap is only on one side of the nut. The anchoris installed at a slight angle and bolt is tight.

3. Is the anchorage free of corrosion that is more than mild surface YO NEI UE] N/AUI oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YOl NEI UE] N/AU]

5. Is the anchorage configuration consistent with plant documentation? YE] NEI UL] N/AO (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 firee of YZ NI UEL potentially adverse seismic conditions?

I Enter (he equipment class niame from Appendix B: Classes of Equipment.

B-98

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS, - WIT' R^!OLD FROM PUBLIC DISCLOsURE UNDER 2.390 Sheet 2 of 4 Status: YO NE] Ur-Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 235 Equip. Class, (14) DistributionPanels Equipment Description AC DISTRIBUTION PANEL 235 Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YZI NEI UD N/AD Equipment cartnext to panel is adequatelyrestrainedfrom movement duringa seismic event. Scaffold next to panel is adequatelybracedand would not adversely affect panel during a seismic event.

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YID N[] Ul- N/A[]

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

9. Do attached lines have adequate flexibility to avoid damage? YO NE UD N/AD

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Interiorof the panel was inspected and found to be free of adverse seismic conditions.

Evaluated by: Dileep Cherlopalle c. .t, ee- 11-.4-qleAslý - Date: I-!t-.--

Michael Wodarcyk _ _ _ _ _ _ _ _ _ Date: 10/24/2013 B-99

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' WT'H1 eLD FROM PUBLe- *91{*GSURE UNDR 2*-390 Sheet3of4 Status: Y[ Nil UM]

Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 235 Equip. Class' (14) Distribution Panels Equipment Description AC DISTRIBUTION PANEL 235 Photoaravhs Note: Panel external with door open Note: Panel internal Note: Properly restrainedequipment cart in vicinity Note: Properly restrainedscaffolding in vicinity of of panel panel B-100

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report IM=_I_,_

__ _[-, _ _ Sheet 4 of 4 Note: Anchor to wall Note: Anchor to wall installedat slight angle B-101

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' 1OLD FROM PUBLI, DIS-LoSURE UNDE, r 2.390 Sheet of4 Status: YM N[-] U--

Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 253 Equip. Class' (14) DistributionPanels Equipment Description DC DISTRIBUTION PANEL 253 Location: Bldg. 2CNTM Floor El. _ Room, Area CNTM 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 onl 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? YE NEI Ul] N/AU

3. Is the anchorage fi'ee of corrosion that is more than mild surface YED NEI UL] N/ADl oxidation?

4. Is the anchorage fi'ee of visible cracks in the concrete near the anchors? YE] NEI U] N/AN Panel is anchored to two Unistrutsspanning between two aux. steel columns.

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

Reference:

Calculation ENG-CS-101

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

Enter the equipmient class name fiom Appendix B: Classes of Equipment.

B-102

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WITHHO FROM

,- ,-LDPUBLIC DISCLOSURE UNDER 2.390 Sheet 2 of 4 Status: Y0 NEI U-II Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 253 Equip. Classi (14) Distribution Panels Equipment Description DC DISTRIBUTION PANEL 253 Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YE NEI Ur- N/AU Metal casing protects internalequipment from impact.

Replacement fuse in a plastic bag is hanging from a tagged-out fuse.

Fuse will be replacedand bag removed priorto Unit 2 restart.

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

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

9. Do attached lines have adequate flexibility to avoid damage? Y0 NO UO N/AUI Attached conduits are supported by a Unistrut frame along with the panel.

10. Based on the above seismic interaction evaluations, is equipment fiee Y0I NE UEI of potentially adverse seismic interaction effects?

Other Adverse Conditions I1. Have you looked for and found no other seismic conditions that could YS NEI U-1 adversely affect the safety functions of the equipment?

Small pieces of foreign material (pen, fuse, wire hook) were lying at the bottom of the panel. Bottom of panel is sufficiently far from fuses such that FME would not interactwith the fuses. Foreign materialwas removed during walkdowns by the supportingelectricians.

Comments (Additional pages may be added as necessary)

Interiorof the panel was inspected and found to be free of adverse seismic conditions.

Evaluated by: Kyle Kriesel 744~Li~LZ Date: /.2 z Michael Wodarcyk 12/3/2013 B-103

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' 'OLD,- FROM P,ULI. DISCLOSURE UNDER 2.390 Sheet 3 of 4 Status: Yo NEI U-I Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 253 Equip. Class, (14) DistributionPanels Equipment Description DC DISTRIBUTION PANEL 253 Photographs Note: Nameplate Note: Exteriorof panel Note: Interiorof panel Note: Upper intemals and anchorage B-104

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSi - WITH H'OLD FROM PUBLIC DISCILOSURE UNDER 2.390 Sheet 4 of 4 A

Note: Lower internals,anchorage,bagged Note: FM removed from bottom of panel replacement fuse, and FM Note: Typical spring nut securing panel anchorage Note:

to Unistrut B-105

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUN - WIT' 11IOLD FREM PUBLIC DISCLOSURE UN1DER 2.390 Sheet 1 of 4 Status: Y[ NE] UM Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 2EM Equip. Class' (14) Distribution Panels Equipment Description DISTRIBUTION PANEL 2EM Location: Bldg. TURB Floor El. __ Room, Area TRN B EVENT MON 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 tile item one YO NEI of the 50% of SWEL items requiring such verification)?

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

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

4. Is the anchorage frec of visible cracks in the concrete near the anchors? Y0Z NE-I U] N/Ar-

5. Is the anchorage configuration consistent with plant documentation? YOI NEI UI] N/A--

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

Reference drawings NX-19837-26 and NX-19837-27.

Anchorage (thru-bolts) verified on both sides of Safety Related Block Wall #6.

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

I Enter the equipment class nanme from Appendix B: Classes of Equipment.

B-106

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SU, S -,,,W,,T',-, ,-, F-ROM^ ,-, , DE

,-.R G - - - 2,,.

.390, Sheet 2 of 4 Status: YNI N[il UI--

Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 2EM Equip. Class' (14) Distribution Panels Equipment Description DISTRIBUTION PANEL 2EM Interaction Effects

7. Are soft targets free flom impact by nearby equipment or structures? YZ NEI UrI N/AEl

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YM N[:] UrI N/A--

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

Panel is mounted onto Safety Related Block Wall #6.

9. Do attached lines have adequate flexibility to avoid damage? YIZ NOI U'- N/Ar-

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

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YN NOl UO1 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Interior of the panel was inspected and found to be free of adverse seismic conditions.

Evaluated by: Dileep Cherlopalle C_.-\. . \e_.,,,X., Date: I %k - ) !t-Michael Wodarcyk 10/24/2013 B-107

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' 11IOLID FREW PUBLIC DISGLOSURE UNDER 2.390 Sheet3of4 Status: YM NEIl U]-

Seismic Walkdown Checklist (SWC)

Equipment ID No. PNL 2EM Equip. Class' (14) DistributionPanels Equipment Description DISTRIBUTION PANEL 2EM Photoeraphs Note: Panelexternal Note: Panel internal Note: Upper anchorage Note: Lower anchorage B-108

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report QWWQ .M~ '!iTri "I Ifir) fl IAM p1 ifl ,,-, GO-, - ,, ,, R, -2 ,*,, Sheet4 of4 Note: Panelanchorage, opposite side of Note:

Safety Related Block Wall #6 B-109

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report

-SUNSI - WIT IIHL-- FROM :  : ,, :: :.' - rDSGLOSRE - UNDER 2-390 Sheet I of 3 Status: Y[I NEI U" Seismic Walkdown Checklist (SWC)

Equipment ID No. SV-33389 Equip. Class' (8) Motor-Operatedand Solenoid-OperatedValves Equipment Description 21 FCU DISCH TO CNTMT DOME CD-34080 SV Location: Bldg. CNTM Floor El. _ Room, Area 2CNTM 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 YUI NED of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Y0 NEI UI- N/AUl One anchor bolt is several threads too long but is tightly secured with nut. Valve mounting plate overall is secured. Not a seismic concern.

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

4. Is the anchorage free of visible cracks in the concrete near the anchors? YZ NEI UE- N/AUl Minor spalling nearone anchor due to drilling to install the anchoris not a seismic concern.

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

6. Based on the above anchorage evaluations, is the anchorage firee of YO NEI UI-potentially adverse seismic conditions?

Enter the equipment class name fromn Appendix 13: Classes of Equipment.

B-110

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT.. .. OLD FROM PUBLIC DISCL.OSURE UNDER 2.390 Sheet 2 of 3 Status: YN NEI U[-

Seismic Walkdown Checklist (SWC)

Equipment ID No. SV-33389 Equip. Class, (8) Motor-Operatedand Solenoid-OperatedValves Equipment Description 21 FCU DISCH TO CNTMT DOME CD-34080 SV Interaction Effects

7. Are soft targets free firom impact by nearby equipment or structures? YED NEI U0I N/AU All nearby equipment is well-restrained.

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

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

Overhead lighting is conduit-mounted.

9. Do attached lines have adequate flexibility to avoid damage? YO NI] UI] N/A[]

Flexible conduit and copper tubing are attachedto component.

10. Based on the above seismic interaction evaluations, is equipment free Yj NiEUI-]

of potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YED NI] U-'

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel Date: A .2 "/ ,/

747~

Michael Wodarcv, r 12/4/2013 B-111

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' 11IOLD FROM PUBLIC DISCLOSURE UNDER -Z.,* Sheet3of3 Status: YNJ NEi U--

Seismic Walkdown Checklist (SWC)

Equipment ID No. SV-33389 Equip. Class' (8) Motor-Operatedand Solenoid-OperatedValves Equipment Description 21 FCU DISCH TO CNTMT DOME CD-34080 SV Photographs Note: Nametag Overall view of valve and mounting Note: Overhead equipment, including Note:

conduit-mounted light fixture B-112

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS! - H1O

.WITHFIROM -LD PUBLIC) DISCLOSURE UNDER 2.390 Sheet 1of 3 Status: YN NEI- Ur---

Seismic Walkdown Checklist (SWC)

Equipment ID No. SV-37464 Equip. Classi (08) Motor-Operatedand Solenoid-OperatedValves Equipment Description U2 TRN A CHLD WTR/CLG WVTR ISOL SV Location: Bldg. AUX Floor El. _ Room, Area NORTH WEST Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to doctmient 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] NZ of the 50% of SWEL items requiring such verification)?

2. Is the anchorage fi'ee of bent, broken, missing or loose hardware? YOl NEI UD N/AU

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

4. Is the anchorage firee of visible cracks in the concrete near the anchors?. Y9 NEI UO N/AU

5. Is the anchorage configuration consistent with plant documentation? YE NEI UE N/A[D (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 firee of YO NO] UOI]

potentially adverse seismic conditions?

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

B-113

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS' - WIT' M

,-'OLD , ,PUBLICDISCLOSURE UNDER 2.390 Sheet 2 of 3 Status: YN NEI UI-Seismic Walkdown Checklist (SWC)

Equipment ID No. SV-37464 Equip. Class' (08) Motor-Operatedand Solenoid-OperatedValves Equipment Description U2 TRN A CHLD WTR/CLG WTR ISOL SV Interaction Effects

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

Temporary Radiation Protectionpowercord to be removed priorto Unit 2 restart.All other equipment in vicinity is securely mounted.

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

Chain-hung overhead light fixture with open S-hook is prevented from impacting SV-37464 by both sufficient distance and equipment above valve, and is therefore not a seismic concern. All other overhead equipment in vicinity is securely mounted.

9. Do attached lines have adequate flexibility to avoid damage? YEI NEI UD N/AU Flexible conduit and stainless steel tubing are attached to component.

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

Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could Y0 NEI U--

adversely affect the safety finctions of the equipment?

Comninents (Additional pages may be added as necessary)

Evaluated by: Kyle Kries e Date: /, 2 K/K V

Michael Wodarcvk A 12/4/2013 B-114

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS, - WIT' H-OLE) FROM ,ULI, DISCLOSURE UNDER 2.390 Sheet 3of3 Status: Y0 N[] UE]

Seismic Walkdown Checklist (SWC)

Equipment ID No. SV-37464 Equip. Class, (08) Motor-Operatedand Solenoid-OperatedValves Equipment Description U2 TRN A CHLD WTR/CLG WTR ISOL SV Photographs Note: Valve with mounting plate Note: Chain hung overhead light fixture with open S-hook Note: Note:

B-115

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUP4, - WIT' 1uI-LD FROMr UI3LI, DISL*OSURE UNDER 2.390 Sheet 1 Of 3 Status: YN NEIr U-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. SV-37466 Equip. Class, (08) Motor-Operatedand Solenoid-OperatedValves Equipment Description UNIT 2 TRAIN A CHILL WTR/CLG WTR ISOL SV Location: Bldg. 2CNTM Floor El. . Room, Area CNTM 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 YO N0 of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Y0 NEI U] N/AO

3. Is the anchorage free of corrosion that is more than mild surface YN NEI U1 N/A]

oxidation?

4. Is the anchorage fiee of visible cracks in the concrete near the anchors? YN NEI UE N/AU

5. Is tile anchorage configuration consistent with plant documentation? YEI NE U- N/AE (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 firee of Y0 NI UU-potentially adverse seismic conditions?

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

B-116

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSI *.- WIT,', LD FROM PBLI, DISCL-OSURE UNDER 2.390 Sheet 2 of 3 Status: Yv NEI UrI Seismic Walkdown Checklist (SWC)

Equipment ID No. SV-37466 Equip. Class' (08) Motor-Operatedand Solenoid-OperatedValves Equipment Description UNIT 2 TRAIN A CHILL WTRICLG WTR ISOL SV Interaction Effects

7. Are soft targets free froin impact by nearby equipment or structures? YZJ NEI UEU N/Ar-

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y0 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? Y0 NEI Ul- N/AUl Flexible conduit and stainless steel tubing are attached to component.

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

Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could YZ NEI U--

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaliiatedc hv: Kvh.- Kri~qe ef ,iA  ;- ' Date: /,2 1,, #"

'7 f Michael Wodarcvk ~ 'Y 12/3/2013 B-117

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS'*. WIT,'.

,- L FR- PUBLIC) DISCLOSURE UNDER 2.390 Sheet 3 of 3 Status: Y[ NE] U[-

Seismic Walkdown Checklist (SWC)

Equipment ID No. SV-37466 Equip. Class, (08) Motor-Operatedand Solenoid-Operated Valves Equipment Description UNIT 2 TRAIN A CHILL WTR/CLG WTR ISOL SV Note: Overall view of valve and mounting Note:

Note: Note:

B-118

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE UNDER 2.390 C, Deferred Area Walk-By Checklists (AWCs)

This appendix provides the Area Walk-By Checklists (AWC) completed after Reference 13 was submitted. The AWCs completed prior to November 26, 2012 were provided in Table C-1 of the Reference 13 report, and are not provided in this supplement.

NSPM completed seven deferred Area Walk-Bys during RFO 2R28. Table C-1 below provides the list of the deferred AWCs that were completed, 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).

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 included 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 contained SUNSI information have been marked with a header, and the sensitive information, such as locations and pictures of safety-related components, has been redacted.

C-1

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNSI WITHHOLD FROM PUB1LIC DISCLOS'URE U,.NDER 2.290 2z2b-1 2D5-D6_ - 25 BUS B25/LOAD SEQ CAB Y 2R28-2 2AUX - NW MCC 2M1 N 2R28-3 2CNTM - 22 SG Vault CV-39417 Y 2CNTM_ - 23 CFCU 274-013 Y CV-39419 2R28-4 MV-32156 PNL 253 SV-37466 2R28-5 2CNTM_ - PRZR Vault 2LT-428 Y 2R28-6 2CNTM_ - 21 SG Vault SV-33389 Y 2CNTM_ - 21 SG Vault 2FT-464 2R28-7 2LT-461 Y C-2

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNSI WAIITHHILD FROM PUBLIC DISCLOSURE UNDER 2.,39G Sheet I of 3 Status: YO N-- UL-Area Walk-By Checklist (AWC)

Location: Bldg. D5/D6 Floor El. Room, Area, 25 BUS 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 ofjudgmnents and findings.

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

I. Does anchorage of equipment in the area appeal- to be free of Y[J NEI U-] N/AEl potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appealr to be firee of significant YO NEI Ur1 N/Ar1 degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit YED NEI Url N/AU-raceways and HVAC ducting appear to be fiee 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 fiee of potentially adverse seismic spatial YN NEI UU] N/Ar" interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Lighting suspended from heavy chain with crimped S-hooks.

' 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.

C-3

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUMSI WITHHO CLD FROM PUBLIC D;S;LOSURE IU ;DER 2.390- Sheet 2 of 3 Status: YN Nn UI-Area Walk-By Checklist (AWC)

Location: Bldg. Q5/D6 Floor El. __ Room, Area' 25 BUS

5. Does it appear that the area is free of potentially adverse seismic YO NEI UD] N/AL]

interactions that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic Y(@ Nil U1 N/AD interactions that could cause a fire in the area?

Equipmentin the area for the currentoutage which is not normally present.

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

Tagging and maintenance equipment in the area for the currentoutage.

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

Comnments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel A / /_,' Date: / 2 , /

Dileep Cherlopalle C. .'J. >\e_* *-'Ž(AA 1-2_4-C-4

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS' WITHHOLD FROM PUBLIC DISCLOSURE UNDER 2.390, Status: YZ N-] UD Area Walk-By Checklist (AWC)

Location: Bldg. D5/D6 Floor El. Room, Area, 25 BUS Photographs BU3 25 in 05/16 Building elevation Note: Area near BUS 25 in D5/D6 Building elevation Note: Area in front of Breakers in D5/D6 Building Note: Area in D5/D6 Building ' elevation elevation C-5

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNSI

, ,ITHHOLD FRO"M PUBLIC DISLeOSURE UNDER 2.390 Sheet I of 4 Status: Y[-] NM U--

Area Walk-By Checklist (AWC)

Location: Bldg. AUX Floor El. Room, Area, NORTH 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 ofjudgments and findings.

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

I. Does anchorage of equipment in the area appear to be free of YMJ NEI UEI N/AF-potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be firee of significant YEI NO UEI N/AEi degraded conditions?

A loose anchor was identified on an HVAC duct floor support. AR 1401822 and WR 96286 were initiatedfor repair.The support was for non-safety duct which would not impact other equipment.

3. Based on a visual inspection friom the floor, do the cable/conduit YOl NEI UE] N/AL]

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 firee of potentially adverse seismic spatial YN NEI UE] N/AEI interactions wvith other equipment in the area (e.g., ceiling tiles and lighting)?

Observed some open S-hooks but none would have any equipment impacts.

IIf the room in which the SWEL item is located is v'ery 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.

C-6

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNSI'I WITHHO'*I r'L~1D FBIG I r8lOl UN*I~IIIDER 2.;390 Sheet 2 of 4 Status: YE] NN ur-Area Walk-By Checklist (AWC)

Location: Bldg. AUX Floor El. ___ Room, Area, NORTH WEST

5. Does it appear that the area is free of potentially adverse seismic YO* NE UD N/AU interactions that could cause flooding or spray in the area?

Fire Protectionpiping in the area to support PAC filters. The piping is socket welded and well supportedso there is no impact.

6. Does it appear that the area is free of potentially adverse seismic YO NEI UL] N/AU interactions that coild cause a fire in the area?

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

Equipment was staged in the area for the currentoutage. No issues were observed with the staging of equipment or materials.

8. Have you looked for and found no other seismic conditions that could YO NIl Ur-adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel/ Date:

Dileep Cherlopalle C V.  !- -

C-7

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated Status: Y[-] NZ U-Area Walk-By Checklist (AWC)

Location: Bldg. AUX Floor El. __ Room, Area 1 NORTH WEST Photographs ,____

Note: Aux Building 'elevation NW area Note: Duct supports Note: Shielding supports C-8

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report,'Updated SUNS'I -VVITHHILD FROM PUBLIC DISCLOSURE UNDER 2.390 Shielding supports Shielding supports Note: Storage cabinet Note:

C-9

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUlNS! WITHHOVLD FROM PUBLIC DISCLOSURE UNDER 2.3900 Sheet 1of 4 Status: YN Nil uFE Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. Room, Area, 22 SG Vault 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.

I. Does anchorage of equipment in the area appear to be free of YO NEI UE] N/AEF potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant YED NEI UE] N/AI-degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit YN NEI UE- N/Arl 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 firee of potentially adverse seismic spatial YZ NEI UI- N/A-1 interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Numerous pieces of temporary equipment (lighting, hoses, scaffolding, etc.) to be removed prior to Unit 2 restart.

IIf the room in which the SWEL item is located is veiy3 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.

C-10

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SU NlS 'l- V I L* F R.OI M I I U B-L I J DI GU EU N DER*f 2lJ

. 3 9 0U S hee t 2 of 4 Status: YZ NE] UL-'

Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. __ Room, Area, 22 SG Vault

5. Does it appear that the area is free of potentially adverse seismic Y0 NEI U0- N/Afl interactions that could cause flooding or spray in the area?

All waterand steam lines in areaare seismically-designed.

6. Does it appear that the area is free of potentially adverse seismic Y0 NEI UH] N/AEO interactions that could cause a fire in the area?

Temporary gas bottles are adequatelyrestrained.

7. Does it appear that the area is free of potentially adverse seismic YO NO U- N/A[l interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

Numerous pieces of temporary equipment (toolboxes, ladders,etc.) to be removed priorto Unit 2 restart.

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

Comments (Additional pages may be added as necessaty)

Staged equipment limits visibility of some portions of this area. No adverse seismic conditions have been noted.

Evaluated by: Kyle Knesel /___ __ Date: 42 Michael Wodarcyk /12/32013 C-11

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS'I = ITHHOLD FROM PUBLIC DISCLO.SURE UNDER 2.390= Sheet 3 of 4 Status: YZ NEI U*

Area Walk-By Checklist (AWC)

Location: Bldg. CNTMI Floor El. Room, Area' 22 SG Vault Photographs Note: Temporarily-stagedequipment Note: Temporary scaffolding Note: Flexible tubing and conduit C-12

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS! W-TH. L. FROM PUBLIC DI-"LOSU RE U..N.DER 2.390 Sheet4of4 Note: Overhead aux. steel duct support with Note: Typical aux. steel anchorage attached flexible copper tubing Note:

Note:

C-1 3

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS' WITHHOLD FROM PUBLIC DI.CLO.SURE UNDER 2.390. Sheet I of 3 Status: YE NEI U--

Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. Room, Area' 23 CFCU Instructions for Completing Checldist 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 YID NEI UIZ N/AE]

potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant YID NEI UEi N/AUI degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit YI NEI UUI N/AE]

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 YE NEI ULI N/AUI interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

Overhead lighting is conduit-motnted.

' If the room in which the SWEL item is located is veiy 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.

C-1 4

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS' WITHHOLD FROM PUBLIC DISCLOSURE UNDER 2.39&- Sheet 2 of 3 Status: YZ NF-'] Uo-Area Walk-By Checklist (AWC)

Location: Bldg. CNAITM Floor El. __ Room, Area, 23 CFCU

5. Does it appeal that the area is free of potentially adverse seismic YE N[O UF1U N/Ar" interactions that could cause flooding or spray in the area?

Overheadfire protectionpiping in the area was noted during the walkdowns, and the USAR was consulted for guidance to determine whether the piping could be a flooding or spray concern. PerUSAR Section 5, Rev. 32, Table 5.2-1, PartB, containmentoverheadfire protection piping is isolated via a blind flange (i.e., disconnected) while Unit 2 is operating and is therefore not of flooding or spray concern.

6. Does it appear that the area is free of potentially adverse seismic YZ NEI U-I N/A[]

interactions that could cause a fire in the area?

7. Does it appear that the area is fi'ee of potentially adverse seismic Yi3 NOI UO- N/A--

interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

Numerous pieces of temporaryequipment to be removed prior to Unit 2 restart.

8. Have you looked for and found no other seismic conditions that could Y0 NOI UO-adversely affect the'safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel /** Date: *.2 Y,/F/

Michael Wodarcyk 12/3/2013 C-15

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS' WITHHOLD FR..M PUBLIC DISCLO.SURE UNDER 2.3 Sheet 3 of 3 Status: YO NEI UU Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. __ Room, Area' 23 CFCU Note: Typical aux. steel anchorage Note: Temporary extension cords Note: Wall-mounted cable trays and temporary Note: Overhead equipment (including storage cabinets conduit-mounted light fixtures)

C-16

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS' \NITHHOLD FROM PUBLIC DISCLOSSURE UNDER 2.39G- Sheet I of 3 Status: YM NEI uF Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. Room, Area' PRZR Vainli 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.

I. Does anchorage of equipment in the area appear to be free of YM NEI ULI N/AF!

potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be firee of significant YO NEI Ur1 N/Ar-degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit YN NHI UHI N/AUI 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 YO NEI UI- N/AU-interactions with other equil)ment in the area (e.g., ceiling tiles and lighting)?

Flexible conduit in contact with junction box near2PT-431 not a seismic concern due to conduit's flexibility and robustnessof junction box casing.

Proximity of overhead piping and conduits to one anothernot a seismic concern due to flexibility.

' 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.

C-1 7

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS.

.. ITHHLD FROM.PUBLIC DISCLOSURE UNDER 2.39G- Sheet 2 of 3 Status: Y[ Nr- Ur Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. __ Room, Areal PRZR Vault

5. Does it appear that the area is firee of potentially adverse seismic Yi NEI UE] N/AE]

interactions that could cause flooding or spray in the area?

6. Does it appear that the area is firee of potentially adverse seismic YID NEI UEI N/AE]

interactions that could cause a fire in the area?

Hydrogen piping is well-supported and seismically-designed.Matting on floor grating is fire-retardant.

7. Does it appear that the area is firee of potentially adverse seismic YZJ NEI UE! N/AE!

interactions associated with housekeeping practices, storage of poirable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

Temporary pail to be removed prior to Unit 2 restart.Ladder and other equipment stored in designated area.

8. Have you looked for and found no other seismic conditions that could YZ NEI U-]

adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel A /, Date: 1_2 Michael Wodarcyk 12/3/2013 C-18

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUMS. -.. IT.HHELD FROM PUBLIC DISCLOSU.RE. UNDER 2.39&.. Sheet 3 of 3 Status: Y[ NE-] UL-Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. __ Room, Area' PRZR Vault I Note: Catwalk, facing containment wall Note: Catwalk, facing pressurizervault and bioshield walls Note: Overhead equipment, including Note: Accumulator tank conduit-mounted light fixtures and hydrogen piping C-1i9

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS' W .IT.HHO.LDFROM PUBLIC DISCLOSURE UNDER 2.3.0. Sheet I of 3 Status: YO NE] UE-Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. __ Room, Area' 21 SG Vault 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 UI N/Af1 potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant YO N[-I U[] N/AU]

degraded conditions?

3. Based on a visual inspection fi'om the floor, do the cable/conduit YO NEI UO] 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)?

4. Does it appear that the area is firee of potentially adverse seismic spatial YO NEI U-1 N/AUl 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.

C-20

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS' WITHHO*LD rlFRM* PUBLIC DISCLOSURE UNDER 2.39G- Sheet 2 of 3 Status: YN NE] UZ--

Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. __ Room, Area, 21 SG Vault

5. Does it appear that the area is fiee of potentially adverse seismic YZ NEI Ur! N/A[

interactions that could cause flooding or spray in the area?

6. Does it appear that the area is firee of potentially adverse seismic YO NEl UE" N/Ar1 interactions that could cause a fire in the area?

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

Temporary equipment (cables, FME covers, etc.) to be removed priorto Unit 2 restart.

8. Have you looked for and found no other seismic conditions that could YZ NU-I UU-adversely affect the safety finctions of the equipment in the area?

Minor pipe rod hangerdeformation (supportingContainmentHeating Steam Supply line) is not a seismic concern.

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel / Date:

Michael Wodarcyk 12/4/2013 C-21

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS' W-ITHHOLD FROM PUBLIC DISCLO.SURE UNDER 2.390- Sheet 3 of 3 Status: YV N[1 U-Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. __ Room, Area, 21 SG Vault Photographs Note: Aux. steel walkway support Note: Restrainedgas bottle iNote: uverneac equipment Note: Temporary equipment and scaffolding C-22

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS' WITHHOLD FROM PUBLIC DISCLOSURE UNDER 2.390- Sheet I of 3 Status: YN N[-] uL-Area Walk-By Checklist (AWC)

Location: Bldg. CNAITM Floor El. Room, Area, 21 SG Vault Instructions for Completing Checklist This checklist may be used to documnent 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 YOI NEl Uil N/AE3 potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant YZ Ni] Uil N/All degraded conditions?

3. Based on a visual inspection firom the floor, do the cable/conduit Y9 NEI UiU 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)?

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

Overhead lighting is conduit-mounted. Temporary equipment in vicinity to be removed prior to Unit 2 restart.

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.

C-23

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS' \,AIITHHOLD FROM PUBLIC DISCLOSURE UNDER 2.394- Sheet 2 of 3 Status: YO NZ] U[

Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. Room, Area, 21 SG Vault

5. Does it appear that the area is free of potentially adverse seismic YN NEI UI' N/AO interactions that could cause flooding or spray in the area?

All water and steam lines in vicinity are seismically-designed.

6. Does it appear that the area is free of potentially adverse seismic YE3 NEI UL- N/AI7 interactions that could cause a fire in the area?

All temporary gas bottles are adequately restrained.

7. Does it appear that the area is free of potentially adverse seismic Yi0 Nil Ut- N/AU interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

Temporary equipment in vicinity (gas bottles, scaffolding, ladders, etc.)

to be removed priorto Unit 2 restart.

8. Have you looked for and found no other seismic conditions that could Y[Z NE-I ur7 adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

Evaluated by: Kyle Kriesel / Date: - /y, Michael Wodarcyk 12/4/2013 C-24

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated SUNS! WITHHOLD FROM PUBLIC DISCLO)SURE UNDER 2.39 Sheet 3 of 3 Status: Y[ NEIr U0]

Area Walk-By Checklist (AWC)

Location: Bldg. CNTM Floor El. _ Room, Area' 21 SG Vault Photographs Note: Temporary equipment Note: Overhead walkway with temporary cabies and hoses Typical overhead, conduit-mounted C-25

Prairie Island Nuclear Generating Plant - Unit 2 Updated Seismic Walkdown Submittal Report SUNS! WITHHOLD FROM PUBLIC DISCLOSURE UNDER 2.390 Peer Review Report This appendix includes the Peer Review Team's report, including the signed Peer Review Checklist for the SWEL from Appendix F, Checklist for PeerReview of SSC Selection, of Reference 1.

This appendix included 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 contained SUNSI information have been marked with a header, and the sensitive information, such as the locations and photos of safety-related components, has been redacted.

D-1

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated Peer Review Report for Near Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdown Inspection completed after November 26, 2012 of Prairie Island Nuclear Generatin2 Station Unit 2 February 5, 2014 Prepared by Peer Reviewers Marlene M Delaney, SE, PE (Team Leader)

Philip Gazda, SE, PE Dileep Cherlopalle S. Seilhymer Marlene Delaney Peer Review Team Leader Certification Signature Date: 2/5/14 D-2

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated Introduction Overview This report documents the independent peer review for the Near Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdowns performed after November 26, 2012 for Unit 2 of the Prairie Island Nuclear Generating Plant (PINGP). The peer review addresses the following activities:

• Review of the selection of the structures, systems, and components (SSCs) that are included in the Seismic Walkdown Equipment List (SWEL) specifically focusing on changes made to the SWEL after November 26, 2012.

• Review of a sample of the checklists prepared after November 26, 2012 for the Seismic Walkdowns & Area Walk-bys.

• Review of any licensing basis evaluations performed after November 26, 2012.

• Review of the decisions for entering the potentially adverse conditions identified in walkdowns performed after November 26, 2013 into the plant's Corrective Action Plan (CAP).

• Review of the final submittal report.

The peer reviewers for PINGP Unit 2 are Ms. Marlene M. Delaney and Mr. Philip Gazda of S&A, and Dileep Cherlopalle and S. Seilhymer of NSPM. Ms. Delaney is designated as the Peer Review Team Leader. Ms. Delaney and Mr. Gazda were not involved in the seismic walkdown inspection process so that they maintain their independence from that portion of the project. Ms. Delaney is a civil-structural engineer with over thirty years of nuclear engineering experience. She has received the Seismic Capability Engineer (EPRI-SQUG) and Seismic Walkdown Engineer (SWE) training. Mr. Gazda is an advanced degree structural engineer with over forty years of nuclear power plant experience. Mr. Gazda has also been trained as a Seismic Capability Engineer (EPRI-SQUG) and a Seismic Walkdown Engineer (SWE EPRI 2-day training). Mr. Cherlopalle and Mr. S. Seilhymer from the Operations department have participated in the peer review of the SWEL, while Ms. Delaney and Mr. Gazda have participated in all other phases of the peer review process for PINGP Unit 2.

Revisions to the SWEL were made for the walkdowns performed after November 26, 2012. The peer review resulted in no findings. The SWEL Peer Review checklist is found in Attachment 1. The discussion for the SWEL development peer review is contained in this peer review report.

Interviews were conducted with the SWE inspection team after review of a sample of the Unit 2 Seismic Walkdown Checklists (SWCs) and the Area Walk-by Checklists (AWCs) generated after November 26, 2012 to ascertain procedural compliance with the SWG.

The interviews were conducted by Ms. Delaney and Mr. Gazda with Messrs. Michael Wodarcyk, Kyle Kriesel, Dileep Cherlopalle, Dennis Zercher and Bruce Lory of the SWE D-3

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated inspection teams on February 4, 2014 and February 5, 2014. The discussion of the sample SWCs and AWCs is provided in this peer review report.

No issues were identified which challenged the current licensing basis.

D-4

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated 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) for walkdowns performed after November 26, 2012.

This section documents the Peer Review - Selection of SSCs performed for PINGP - Unit 2 after November 26, 2012.

Peer Review Activity - 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 individuals who were directly responsible for development of the SWEL:

Mr. P. Valtakis, Prairie Island Plant Engineer Mr. Bruce Lory, Senior Mechanical Engineer This peer review utilized the checklist shown in the SWG, Appendix F: Checklist for Peer Review of SSC Selection.

For SWEL 1 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)

This peer review determined that the SSCs selected for the seismic walkdowns represent a diverse sample of equipment required to perform the five safety functions.

" 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 (note that several risk insight consideration components were removed from the SWEL due to lack of accessibility to perform D-5

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated internal inspections however other risk insight consideration components remain on the SWEL and the overall impact was of no consequence)

This final peer review of the SWEL for SSCs walked down after November 26, 2012 determined that the SSCs selected include a sample of items that represent each attribute/consideration identified above.

Peer Review Findings - Selection of SSCs This peer review found that the process for selecting SSCs that were added/removed from the SWEL for the walkdowns performed after November 26, 2012 was consistent with the process outlined in the SWG Section 3: Selection of SSCs.

The peer review checklist dated January 16, 2014 is attached to this document.

Resolution of Peer Review Comments - Selection of SSCs All comments requiring resolution were incorporated prior to completion of this peer review.

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 after November 26, 2012 appropriately followed the process outlined in the SWG, Section 3: Selection of SSCs. It is further concluded that the final SWEL sufficiently represents a broad population of plant Design Class I equipment and systems to meet the objectives of the NRC 50.54(f) letter.

D-6

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated Review of Sample Seismic Walkdown & Area Walk-Bys Checklists Overview A peer review of the SWCs and AWCs generated after November 26, 2012 was performed after which an interview was conducted with the SWE inspection team in accordance with the Seismic Walkdown Guidance (SWG) requirements. Interviews were conducted with the SWEs on February 4, 2014 and February 5, 2014. The SWE trained walkdown engineers were Messrs. Kyle Kriesel, Dileep Cherlopalle, Michael Wodarcyk, Dennis Zercher, and Bruce Lory.

Sample Checklists Table D-1 lists the SWC and AWC samples which represent approximately 34% of the SWCs and 42% of the AWCs.

Table D-1: SWC Samples from Seismic Walkdown Inspection for Unit 2 performed after November 26, 2012 Equipment Identification Equipment Class Walkdown Item Observations A note is provided on the SWC stated that the internal cabinet inspection was held over from the original walkdown. It is not clear ifthe SWC contains all information from the original walkdown.

50000 20 D5 DSL GEN Discussion with the SWEs BENCHBOARD indicated that the information was included and validated by their signatures on the SWC.

Photos and notes on SWC indicate external inspections were performed. Concern is resolved.

D-7

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated Table D-1: SWC Samples from Seismic Walkdown Inspection for Unit 2 performed after November 26, 2012 Equipment Identification Equipment Class Walkdown Item Observations A note is provided on the SWC stated that the internal cabinet inspection was held over from the original walkdown. It is not clear ifthe SWC contains all information from the original walkdown.

21 BATT Discussion with the SWEs CHG 21 BATTERY CHARGER indicated that the information was included and validated by their signatures on the SWC.

Photos and notes on SWC indicate external inspections were performed. Concern is resolved.

A note is provided on the SWC stated that the internal cabinet inspection was held over from the original walkdown. It is not clear ifthe SWC contains all information from the original walkdown.

21 INV 16 Discussion with the SWEs 21 INVERTER indicated that the information was included and validated by their signatures on the SWC.

Photos and notes on SWC indicate external inspections were performed. Concern is resolved.

232-281 9 21 SFGDS SCRNHSE No concerns ROOF EXHT FAN 258-011 0 21 CLG WTR STRNR No concerns D-8

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated Table D-1: SWC Samples from Seismic Walkdown Inspection for Unit 2 performed after November 26, 2012 Equipment Identification Equipment Class Walkdown Item Observations Internal inspection performed on 16 of 17 cubicles. Issues were found in some cubicles however these issues were not adverse seismic conditions. The SWC should have stated a conclusion regarding the uninspected cubicle acceptability. During the interview with the SWEs, it BUS 26 3 BUS 26.4 16KV was determined that the SWITCHGEAR identified issues were non-seismic in nature and it could be considered that the 1 7 th cubicle would be acceptable. Concern resolved. Note that checklist is N based on field walkdown notes and is not revised to a Y status even though there are no seismic concerns. This is consistent for the project.

Note that checklist is N based on field walkdown notes and is not revised to MCC 2K2 1 MOTOR CONTROL a Y status even though CENTER 2K BUS 2 there are no seismic concerns. This is consistent for the project.

D-9

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated Table D-1: SWC Samples from Seismic Walkdown Inspection for Unit 2 performed after November 26, 2012 Equipment Identification Equipment Class Walkdown Item Observations A note is provided on the SWC stated that the internal cabinet inspection was held over from the original walkdown. It is not clear if the SWC contains all information from original walkdown. Discussion PNL 21 14 DISTRIBUTION PANEL 21 with the SWEs indicated that the information was included and validated by their signatures on the SWC. Photos and notes on SWC indicate external inspections were performed. Concern is resolved 21 FCU DISCH TO SV-37464 8 DOECD-TO0No 2NTMT DOME CNTMT CD-34080 concerns Sv SV-37466 8 UNIT 2 TRAIN A CHILL No concerns WTR/CLG WTR ISOL SV D-1 0

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated ouruit - vvi i i ii iituL i iKUMv j'tUL3LIt UkAtt~JLUUJ~kL UNUqtl=I  !.djtU Table D-2: AWC Samples from Seismic Walkdown Inspection for Unit 2 performed after November 26, 2012 Area Walkdown Description Observations 2R28-1 No concerns 2D5-D6_. -25 BUS 2R28- Note that checklist is N based on field walkdown notes and is not revised to a Y status even though there are no seismic

-AUXconcerns. This is consistent for the project 2R28-6 2CNTMm21 SG VAULT Noconcerns Evaluation of Findincqs There were no findings that challenged the licensing basis. Tables 5-2 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. All issues were adequately addressed on the SWCs and entered into Tables 5-2 and 5-3 as appropriate.

The scaffolding and seismic housekeeping procedures were reviewed by the SWEs in order to gain a full understanding of the plant practices in regard to those procedures.

There were no seismic concerns noted in Unit 2 with regard to scaffold erection. The scaffolds were properly tied off and braced, and properly tagged with respect to the procedure.

The peer reviewers consider the judgments made by the SWEs to be appropriate and in accordance with the SWG.

D-11

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated Review of Licensing Basis Assessments Tables 5-2 and 5-3 of the Seismic Walkdown Report provide a list of the issues encountered during the Unit 2 seismic walkdown inspections performed after November 26, 2012 for the SWEL components and how they were addressed. If a PINGP CAP request was generated it is shown in the Tables. No potentially adverse seismic conditions were identified that resulted in a seismic licensing basis evaluation. The peer reviewers concur with this outcome.

D-1 2

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated Review Final Submittal Report & Sign-off The entire final submittal report has been reviewed by Ms. Marlene Delaney and Mr. Phil Gazda and found to meet the requirements of the EPRI 1025286 - Seismic Walkdown Guidance. The Peer Review determined that the objectives and requirements of the 50.54(f) letter1 are met. Further, the efforts completed and documented within the final submittal report are in accordance with the EPRI guidance document.

1 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 D-1 3

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated Sheet I of 2 Peer Review Checklist for SWEL 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.

I. Were the five safety functions adequately represented in the SWEL I selection? YId NEI

2. Does SWEL I include an appropriate representation of items having the following sample selection attributes:

a. Various types of systems? Yrd NEI

b. Major new and replacement equipment? YVNEJ

c. Various types of equipment?

d. Various environments? YIdNrI

e. Equipment enhanced based on the findings of the IPEEE (or equivalent) program? YO NEI D-14

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report, Updated Sheet 2 of 2 Peer Review Checklist for SWEL

f. Were risk insights considered in the development of SWEL 1? Yff NlI

3. For SWEL 2:

a. Were spent fuel pool related items considered, and if applicable included in Y[f Nhi SWEL 2?

b. Was an appropriate justification documented for spent fuiel pool related items not Y[* NEl included in SWEL 2?

4. Provide any other comments related to the peer review of the SWELs.

YE*]Nr-

5. Have all peer review comments been adequately addressed in the final SWEL?

Peer Reviewer #11: -, ~ Th~\)SetL Nymcv\- Date: OI/( 1L4 Peer Reviewer #2: ct- _ cAA~g,"VALc~Pu Date: '~I 16 D-1 5

CONlTAINS SUNS IITHHOLDl FROM PUBLIC DISCLOSURE UNDER 2.390 ENCLOSURE4 REPLACEMENT PAGES FOR PINGP UNIT 2 FINAL SEISMIC WALKDOWN REPORT (REDACTED)

(43 Pages Follow)

L-PI-14-020 NSPM REPLACEMENT PAGES FOR PINGP UNIT 2 FINAL SEISMIC WALKDOWN REPORT (REDACTED)

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 2). Enclosure 3 of the March 12, 2012 letter contains specific Requested Actions, Requested Information, and Required Responses associated with NTTF Recommendation 2.3, Seismic. Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, submitted the required response to the Requested Information for NTTF Recommendation 2.3, Seismic, for Prairie Island Nuclear Generating Plant (PINGP) in a letter dated November 26, 2012 (Reference 1).

During preparations of the updated seismic walkdown report, NSPM identified items in the Reference 1 report that required correction. Replacement pages for the following sections of the Reference 1 report are provided in this enclosure.

" Section 5, Seismic Walkdowns and Area Walk-Bys

• Appendix B, Seismic Walkdown Checklists

• Appendix C, Area Walk-By Checklists

• Appendix F, Dispositionof Seismic Walkdown Observations The replacement pages provided in this enclosure correct the items identified by NSPM.

Corrections are noted in the replacement pages with either underlined text or revision bars.

These corrections do not impact the original conclusion of the Reference 1 report.

The enclosure contained information on the location of Seismic Walkdown Equipment List (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 contained SUNSI information have been marked with a header, and the sensitive information, such as locations and pictures of safety-related components, has been redacted.

References:

1. NSPM Letter to NRC, "PINGP Unit 2 - 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,"

dated November 26, 2012, ADAMS Accession No. ML12334A470.

2. 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.

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report This internal inspection of electrical cabinets and panels was performed at PINGP to the extent allowed by the plant. Any situations that posed a danger to personnel or the proper operation of the plant were deferred to a future outage and are identified in Table D-1 of Appendix D in this report. The Seismic Walkdown Checklists (SWC) for the equipment identified in Table D-1 that cannot be opened for internal inspections will be revised at the time of the supplemental walkdown to indicate the results of these internal inspections.

Any identified other adverse seismic conditions are documented on the items' SWC in Appendix B and Table 5-2, as applicable.

5.2.5 Issues Identified during Seismic Walkdowns Table 5-2 provides a summary of issues identified during the equipment Seismic Walkdowns. The equipment Seismic Walkdowns resulted with a total of 12 concerns identified and each of these was entered into the site's Corrective Action Program (CAP). There were two observations identified during the seismic walkdowns that are in the work management process for resolution, and are conservatively reported in this report for tracking purposes. All of the identified concerns were assessed and it was concluded that the anomaly or issue would not prevent the associated equipment from performing its safety-related function(s). 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 29 Area Walk-bys were performed for PINGP Unit 2.

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 verify compliance with site pprocedures (Reference 38).

5-5

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report 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 bus bars, which pass between the two, to short out against the grounded bus duct surrounding the bus bars 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 During the Area Walk-Bys, the SWEs identified several instances where the seismic housekeeping was not in accordance with site procedures. These instances were noted on the AWCs and the issues were entered into the site CAP. Table 5-3 at the end of this section provides a summary of the issues identified during the Area Walk-Bys. The issues are associated with Area Walk-By designations, which are provided in Appendix C.

In total, 23 issues were identified during the Area Walk-Bys and entered into the site's CAP. One observation identified during the Area Walk-Bys is being resolved in the work management process, and is conservatively reported in this table for tracking purposes.

No potentially adverse seismic conditions were identified that resulted in a seismic licensing basis evaluation.

5-7

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table 5-2: Prairie Island Unit 2 SWC CAP Status Equipment Description of Issue CAP# Status ID The light bar is being held by two "S" hooks. One of the "S" hooks is open. If the light bar were to swing, it Closed to CAP 245-392 might hit the pump. Although this potential seismic 1351884 1352001 and WR interaction might be credible, it is not significant since 83533.

the pump would still be able to perform its intended safety function.

Both of the "S" hooks holding the light fixture above the 22CC pumps are open. The power cord is taped 245-122 and seems to be able to support the light fixture. The 1351916 Closed to WR 83541.

light fixture is in contract with the "L"column and it is possible the light may break during seismic motion.

The CC Pump collection barrel is tied with rope to the Closed to WR 83539, 245-122 Unistrut. The barrel has a note attached that 1351901 which is complete.

references CAP 1317022 and WO 74792.

There is duct tape on the bottom of the rigging beam 245-122 above the CC pump. It is a housekeeping issue, and 1351913 Closed.

not a seismic concern.

Multiple open "S" hooks for lighting fixtures were Open - Work identified during the Seismic Walkdowns. An action Request (WR) 84434, Multiple request was initiated to track all of these occurrences 1352001 83556, and 83533 and perform an extent of condition. See Appendix F are associated with for all open "S" hook observations, this observation.

There are missing cap nuts on the south side of the Closed to WR 84674 55320 cabinet. This is a maintenance issue and not a 1356613 and WO 467408.

seismic issue.

Deleted WR 101195 is B-2 Duct tape was identified behind PanB-2 -2 at about 8' N/A associated with this high between the CVCS letdown and RHR labels. observation.

There is a bent back cover plate for the CVCS B-2 letdown monitor. It is located at about 10' high near N/A WR 84959 and WO the CVCS letdown label. The cover plate is non- 471054 initiated.

structural and is not an adverse seismic condition.

5-8

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table 5-2: Prairie Island Unit 2 SWC CAP Status Eqipmn Description of Issue CAP# Status ID The following housekeeping items were identified:

Duct tape was found on the side of the first monitor. Closed to WR 83785, E-2 about 8' high on the generator controls. A broken tie 1352954 which is complete.

wrap is inside E-2 and pinned to a diagonal support. A tie wrap was found on the edge of a HVAC duct exhaust above E-2.

In addition to the foreign material, the pig tail of a E-2 cable with a multipin connector was found stored on 1357129 Closed to WR 84837 top of the box. It is not a seismic concern, but it is and WO 467495.

recommended that the site evaluate the condition.

Open - WR 83890 EM-B2 A mounting screw was discovered missing inside the 1353340 and WO 465970 are back of this panel in one of the electronic modules. associated with this observation.

The rod hanger for piping below the valve is missing Closed to WR 84626 MV-32384 one bolt. This is not a seismic issue for the valve, but 1356520 and WO 467183.

requires evaluation.

Closed to WRs PNL 22 The counterweight of the door pulley system may 1352343 83645, 83646, and strike panel PNL 22. WOs 465563, 465564.

PNL 261 The upper left 3/8" diameter shell expansion anchor 1352221 Closed to WR 83615 has sheared off. and WO 465451.

5-9

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table 5-3: Prairie Island Unit 2 Area Walk-by CAP Status Area Walk-by Description of Issue CAP# Status Designation It appears that CS-19543 is not anchored to the wall. There are four Closed to WR 83853, external holes in the bracket for 1353327 which is complete.

fasteners but no fasteners are present.

Two drums are present under the component cooling heat exchanger to collect leak off. The drums are Closed to WR 83865 and poorly tied off by rope to a small WO 465979.

copper drain line for the 11 I component cooling pump unit cooler.

A top cover plate wing nut is missing from the 2RE-39 radiation monitor.

There is also a loose screw on the 2 side door cover. The monitor is resting on the floor near the wall, and is located between the 22 component cooling pump and the stairs to the upper level.

Next to the pressure gauge Pl-18249, there is a portable cord reel supported on the wall by a pin.

Since the cord is free to rotate, the reel could swing in a seismic event 1352923 Closed to WR 83779 and and potentially impact the valve and WO 465931.

tubing of the pressure gauge. Work request has been initiated to either secure the portable cord reel from movement or re-locate.

5-10

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table 5-3: Prairie Island Unit 2 Area Walk-by CAP Status Area Walk-by Description of Issue CAP# Status Designation Radiation monitor DRM-2 is attached magnetically to electrical panel 2R1A54. The magnetic base may not be strong enough to prevent the The monitor was relocated monitor from falling and impacting and secured under the pressure gauge P1-18249 or 1352792.

3 associated tubing. 2 CAP were 1352792,1352586 issued - one to evaluate long term and 1397910 The enhancements to out of service time for the radiation Radiation Protection monitor and the second one to guidance are tracked under evaluate any potential procedures 1352586.

deficiencies in the deficiencies in the installation of portable radiation monitors.

The guard cover on 22 safety injection (SI) pump coupling has two loose nuts for the bracket attached to the foundation of the SI pump. The 4 bolts are effective to withstand 1352699 Closed to WR 83742, seismic loads. The coupling guard which is complete.

will remain in place during a seismic event. It is seismically acceptable, but the loose bolts should be tightened.

An oil can is sitting on the pipe support for MV-32185. There was Closed to WR 83746 and 4 no holder found for storing the can, 1352727 W 346607.

which is against the site's seismic housekeeping procedure.

A steam heating line was found tie wrapped to the line that includes the 4 2-RCCH-538 support. The tie wrap is 1352959 Closed to WR 83786.

a poor housekeeping practice, and I should be removed.

The wrench hanging from 2MS-27-2 is a potential hazard to SOV-33266 and SV-33264. The recommendation 1352195 Closed to WR 83607.

is to re-locate the wrench to a height lower than the SOV elevation, so that is no longer a potential hazard.

5-11

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table 5-3: Prairie Island Unit 2 Area Walk-by CAP Status Area Walk-by Description of Issue CAP# Status Designation Deleted Multiple open "S" hooks for lighting fixtures were identified during the Seismic Walkdowns. An action Open - WR 84434, 83556, Multiple request was initiated to track all of 1352001 and 83533 are associated these occurrences and perform an with this observation.

extent of condition. See Appendix F for all open "S" hook observations.

After further evaluation by plant engineering, it was determined that the safety classification of this indicator may not meet the requirements of the plant's 20 equipment classification procedure. 1352398 Open.

PI-11979 is currently classified as non-safety related but it may need to be classified as safety related. CAP 1352398 has been initiated to evaluate the safety classification of the starting air indicator.

The starting air indicator (PI-11979) for the 22 diesel driven cooling water pump has a bracket with provisions for four screws. However, only two 20 bolts are attaching the indicator to 1351936 Closed to WR 83545 and the concrete wall. CAP 1351936 has WO 466341.

been initiated to evaluate this observation and WR 8354 was initiated off of this action request to correct the condition.

The guard to belt drive on 121 23 instrument air (013-011) is missing 1352975 Closed to WR 83793.

two anchor bolts.

Chain fall for 2AF-13-1 is within eight 23 inches of interacting with MCC 1A 1352961 Closed to WR 83796.

Bus 1. The chain fall needs to be restrained.

5-12

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table 5-3: Prairie Island Unit 2 Area Walk-by CAP Status Area Walk-by Description of Issue CAP# Status Designation The counterweight "S" hook is also Closed to WR 83645 and 26 open and the counterweight could 1352343 WR 83646.

fall to the floor or against PNL 22 The clamp of the conduit going into Panel 227 is loose. The clamp bolt Closed to WR 83887, 24 is loosely attached to the Unistrut 1353370 which is complete.

location of the clamp, which is 6ft above the floor.

25 The 123 instrument air compressor 1352154 Closed to WR 83594 and guard is missing a few anchors. WO 465439.

The fire extinguisher (301) is on a short bent bracket. It is 25 recommended that the bracket gets 1352094 Closed to WR 83577.

bent back to normal (horizontal) position or is replaced.

Duct tape is preventing a chain for a fluorescent light fixture from making WR 83605 and WO 27 contact with a conduit. This type of 1352192 465449 are associated with restraint is not necessary and should 1329 459are atith be removed. It is a housekeeping this observation.

issue and not a seismic concern.

There are lighting diffusers tied off to the support grid. Unit 1 and Unit 2 29 "C" panels have a fluorescent light 1352209 Open.

fixture on chains too close (within 1"-

2") to the panel.

Unit 1 and Unit 2 "E" panels have 29 side panels that have slid out of 1352102 Closed to WR 83579, position. This is a housekeeping which is complete.

issue and not a seismic concern.

Fire extinguisher bracket 224 has a 29 rotated bracket (into the insulation) N/A WR 83584 initiated.

and should be repaired.

5-13

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table 5-3: Prairie Island Unit 2 Area Walk-by CAP Status Area Walk-by Description of Issue CAP# Status Designation The filing cabinets adjacent to the 29 main control board in both Unit 1 and 1357683 Open.

Unit 2 are close to the main control board.

The cart adjacent to the Protection Systems III and the cart adjacent to 29 cabinets RPI-1, -2, and -3 in Unit 1 1357686 Open.

are close to the equipment. The chain is not used to restrain the carts.

5-14

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table F-1: Disposition of Seismic Walkdown Observations Walkdown Question Observation Disposition Checklist No.

The side panel is attached with a sufficient amount of There are missing cap nuts on the south side of the fasteners to prevent it from coming loose, so it is not a seismic 55320 11 cabinet. This is a maintenance issue and not a concern. However, CAP 1356613 has been initiated to seismic issue. evaluate this observation. In addition, WR 84674 was initiated to address this observation.

The "S" hooks for lighting fixtures throughout the CAP 1352001 has been initiated to evaluate the open "S" room are mostly closed, but not all of the way. The hooks on light fixtures which have been identified during these 22 BATT22 ATT1010 SWEs chain recommend links are thinthat enoughthe "S' hooks beslip to possibly fullythrough.

closed, walkdowns. In addition to this action request, WR 83556k recommend thoughanonetof them"e hover the f sers 84434, and 83533 have been initiated to address these even though none of them are over the batteries observations.

themselves.

CAP 1352001 has been initiated to evaluate the open "S" hooks on light fixtures which have been identified during these 22 BATT There are open "S hooks for lighting fixtures above walkdowns. In addition to this action request, WR 83556, CHG 8the battery charger. 84434, and 83533 have been initiated to address these observations.

There are open "S" hooks for some of the lighting It is not a seismic concern, but CAP 1352001 has been Ther

"' arhoksfor opn omeof he ighing initiated to evaluate the "S" hook observations noted during 221M/XFMR 8 fixtures, but this will not pose an interaction hazard wkwthe CAP 13201 Wuring hoof to te trnsfomerand to the transformer.these 83533 have 1352001, walkdowns. Off of CAP WR 83556 84434 been initiated.

F-2

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table F-1: Disposition of Seismic Walkdown Observations Walkdown Question Observation Disposition Checklist No.

The guard between the engine and generator is bolted to the engine. No additional fasteners are required. It would not be 234-032 11 The guard between the engine and the generator is advisable to have the guard secured at both the engine and not anchored to the floor, the pad as the vibration from the engine when running would put undue stress on the guard fasteners. It is not a seismic concern.

There are two open "S' hooks on the light fixture. It CAP 1352001 has been initiated to evaluate all of the open "S" hooks identified during these walkdowns. In addition to the zone of influencen writing this action request, WR 83556, 84434, and 83533 have been initiated to address these observations.

CAP 1352001 has been initiated to evaluate the open "S" The light fixture above 21 safety injection pump has hooks on light fixtures which have been identified during these 245-071 8 two but open is not "S" hooks. and significant SWEsthe judged safety that it is credible, injection pump is walkdowns. In addition to this action request, WR 83556, 843.ad353hvbenitaedoadrstee not adversely affected. 84434, and 83533 have been initiated to address these observations.

Both of the "S" hooks holding the light fixture above the 22 CC pumps are open. The power cord is CAP 1351916 has been initiated to evaluate this observation.

245-122 8 taped and seems to be able to support the light In addition to writing this action request, WR 83541 has been fixture. The light fixture is in contact with the column initiated to address this observation.

2 and it is possible the light may break during seismic motion.

F-3

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table F-I: Disposition of Seismic Walkdown Observations Walkdown Question Observation Disposition Checklist No.

Due to the fact that the CC pumps and heat exchangers are mounted on raised concrete pedestals, the proximity of a barrel to the pump has no adverse impact seismically.

However, such poorly secured barrels are in conflict with the 245-122 8 the C Pump collection barrel is tied with rope to requirements of the seismic housekeeping procedure and the references CAP 1317022 and WO 74792. engineering change for the CC pump leakoff collection barrels structural system. CAP 1351901 has been initiated to evaluate this observation, and WR 83539 has been generated to address this observation.

There is duct tape on the bottom of the rigging beam 245-122 8 above the CC pump. It is a housekeeping issue, and CAP 1351913 has been initiated to evaluate this observation.

not a seismic concern.

Fluorescent light located west of TD AFW pump has CAP 1352001 has been initiated to evaluate this observation.

245-201 7 open "S" hook on one chain but the other chain will In addition to the action request, WR 83556, 84434, and prevent light from falling on the pump. 83533 have been initiated to address this observation.

The light bar is being held by two "S" hooks. One of the "S" hooks is open. Ifthe light bar were to swing, CAP 1351884 has been initiated to evaluate this observation.

245-392 8 it might hit themight pump.beAlthough this potential seismic writing this action request, WR 83533 has been In addition toinitiated interaction credible, it is not significant to address this observation.

since the pump would still be able to perform its intended safety function.

F-4

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table F-1: Disposition of Seismic Walkdown Observations Walkdown Question Observation Disposition Checklist No.

The supply and return line are laterally unsupported, The piping configuration is seismically installed. The subject 274-031 11 and could potentially over stress the nozzle piping is analyzed in a plant calculation, and is shown to be (particularly the copper portion in the cooling acceptable. There is no seismic concern.

radiator).

A calculation was found which previously performed a 274-162 Supply and return lines are laterally unrestrained and determination of seismic adequacy of ZH system pressure may subject cooler nozzle to large movement, boundary in the 122 Bus Room and other locations within the plant.plant No additional review isThere documentation. required is no based on concern.

seismic the identified CAP 1352001 has been initiated to evaluate the open "S" A light fixture has three open "S' hooks. The SWE's hooks on light fixtures which have been identified during these 2LT920 8 judged that the light fixture will not impact the walkdowns. In addition to this action request, WR 83556k transmitter, so there is no seismic interaction 84434, and 83533 have been initiated to address these concern. observations.

Site Engineering discovered later that the cabinet is anchored The cabinet labeled "clean chemical handling to the wall with two small anchors, which can only be found by 2LT-921 10 equipment" (36" x 24" x 75" high) is stored about 4" opening the cabinet and moving internal contents to see them.

from the level transmitter. Therefore this observation is resolved and there is no adverse seismic condition.

Duct tape was identified behind Panel B-2 at about This observation is not a seismic concern. WR 101195 is 8' high between the CVCS letdown and RHR labels. associated with this observation.

F-5

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table F-1: Disposition of Seismic Walkdown Observations Walkdown Question Observation Disposition Checklist No.

There is a bent back cover plate for the CVCS letdown monitor. It is located at about 10' high near It is not a seismic concern, however, WR 84959 was initiated the CVCS letdown label. The cover plate is non- to correct the bent dust cover on the enunciators.

structural and is not an adverse seismic condition.

The light fixture near E-2 in the middle section has CAP 1352001 has been initiated to evaluate the open "S" one open "S" hook out of four hooks. E-2 is not in hooks on light fixtures which have been identified during these E-2 8 the zone of influence, therefore it is not a seismic walkdowns. In addition to this action request, WR 83556, concern. This light fixture was noted during the area 84434, and 83533 have been initiated to address these walkbys. observations.

The SWEs identified the following foreign materials:

1. Duct tape was found on the side of the first monitor, about 8' high on the generator controls. CAP 1352954 has been initiated to evaluate this observation.

E-2 Comments 2. A broken tie wrap is inside E-2 and pinned to a Additionally, WR 83785 has been initiated to remove the diagonal support. foreign material.

3. A tie wrap was found on the edge of a HVAC duct exhaust above E-2.

In addition to the foreign material, the pig tail of a The abandoned cable was not configured per the guidance for maeralthepi tal o a In ddiio tothefoeig abandoned cables. Therefore, CAP 1357129 has been cable with a multipin connector was found stored on indoned cumes. Therefo C n. 1357129n ha been E-2 Comments top of the box. It is not a seismic concern, but it is initiated to document this observation. In addition, WR 84837 was initiated to address this observation. There is no impact recommended that the site evaluate the conditionis not a seismic concern.

F-6

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table F-I: Disposition of Seismic Walkdown Observations Walkdown Question Observation Disposition Checklist No.

The unit remains functional with only one screw holding the card in. The one screw will ensure it does not impact other A mounting screw was discovered missing inside the equipment as well. The card does not support any safety back of this panel in one of the electronic modules. functions, therefore it is not a seismic concern. However, CAP 1353340 was initiated to document this observation, and WR 83890 was generated to correct the condition.

Based on engineering judgment the small mass on the control The train B event monitoring unit cooler CS-19144 switch box is adequately supported by the two anchor EM-B2 Comments PNL 219-1 has four bolt holes in the base plate but configuration. It is also obvious from the multiple installations only two screws are installed, that this is the as designed configuration and there has been no degradation. It is not a seismic concern.

The pipe support trapeze for the rod support of the A rigid seismic restraint prevents the rod hanger and MV-32030 turbine driven auxiliary feedwater pump discharge connected thesteel motortrapeze valve. support It is not from moving and impacting line may displace (out of the plane of the trapeze) a seismic concern.

and potentially strike MV-32030.

CAP 1352001 has been initiated to evaluate the open "S" There is an open "S" hook on the light fixture above hooks on light fixtures which have been identified during these MV-32180 8 MV-32180. It is credible, but will not impact MV- walkdowns. In addition to this action request, WR 83556, 32180. 84434, and 83533 have been initiated to address these observations.

The pipe hanger rod below the valve is missing one CAP 1356520 has been initiated to evaluate this observation.

MV-32384 Comments bolt. This is not a seismic issue for the valve, but In addition, WR 84626 was initiated to address this requires evaluation, observation.

F-7

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report Table F-I: Disposition of Seismic Walkdown Observations Walkdown Question Observation Disposition Checklist No.

The A-46 SEWs declared this panel as an outlier This was identified as an outlier for resolution during the PNL 22 6 andsubject be required a grout pad sorecommended that the bolts would not SQUG walkdowns and was evaluated.

It is not aThe condition was does to notbending.

appear toThe have been performed.resolution determined to be acceptable. seismic concern.

CAP 1352343 has been initiated to evaluate this observation.

PNL 22 The counterweight 2strikeofpanel the door PNL pulley

22. system may WR 83645 and 83646 have also been initiated to address this observation.

Both of the 'S"hooks for the light fixture in front of CAPon1352001 has been initiated to evaluate the open "S" hooks light fixtures which have been identified during these PNL 234 8 panel 234 as the panel are itopen. The light is 4' away from fixture will not the panel. It isimpact not a walkdowns. In addition to this action request, WR 83556, 843,ad353hvbenitaedoadrstee seismic concern. 84434, and 83533 have been initiated to address these observations.

The "S hooks" at both ends of a light fixture near PNL-234/XFMR are open. If light fixture unhooks at CAP 1352001 has been initiated to evaluate the open "S" both ends, its power cord will hold the fixture at one hooks on light fixtures which have been identified during these 234/FMR 8 end, and the other end will swing down. Panel 234 walkdowns. In addition to this action request, WR 83556, and the transformers are not in zone of influences so 84434, and 83533 have been initiated to address these SWEs judge light fixture falling is not an adverse observations.

seismic condition.

Plant engineering investigated this observation and determined that the fourth bolt is visible behind the spring-loaded nut holding the panel enclosure to the Unistrut. Panel PNL 261 2 The upper left 3/8" diameter shell expansion anchor 261 therefore has four mounting bolts connecting it to the concrete wall, and no concern is present. CAP 1352221 was initiated to document this observation. WR 83615 was also initiated to perform any field work required by CAP 1352221.

F-8

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report SUNS' vw ......... W*,,THHOLD FROm PUBMI= DIumu6GURE Table F-2: Disposition of Area Walk-by Observations Area Walk by Question Observation Disposition Checklist No.

A top cover plate wing nut is missing from the 2RE-39 radiation monitor. There is also a loose screw on the side The radiation monitor is not safety related. WR 83571 was initiated to AUX 12/22 Comments door cover. The monitor is resting on the floor near the replace the wing nut and tighten the loose screw. CAP 01352076 was CCPUMP wall, and is located between the 22 component cooling initiated to document the observation.

pump and the stairs to the upper level.

CAP 1352923 has been initiated to document the observation, and AUX 21/22 Next to the pressure gauge P1-18249, there is a portable WR 83779 has been initiated to either secure the portable cord reel CNTM SPRAY 4 cord reel supported on the wall by a pin. Since the cord is from movement or re-locate the portable cord reel to a more suitable free to rotate, the reel could swing in a seismic event and location.

potentially impact the valve and tubing of the pressure gauge.

The monitor was relocated and secured under 1352792.

Radiation monitor DRM-2 is attached magnetically to AUX 21/22 electrical panel 2RIA54. The magnetic base may not be The enhancements to Radiation Protection guidance are currently CNT7 SPRAY strong enough to prevent the monitor from falling and tracked under 1352586.

impacting the pressure gauge P1-18249 or associated tubing. CAP 1397910 monitors the placement of portable radiation monitoring equipment throughout the plant.

The guard cover on 22 safety injection (SI) pump coupling has two loose nuts for the bracket attached to the AUX222ontion ofothe Spum. frthe blkts AUX 21/22 foundation of the SI pump. The boltsar fctvedto to tCAP are effective 1352699 had been initiated to evaluate this observation. In adiintwrigthscioreutW834hsbenntaedo SI PUMP 1 withstand seismic loads. The coupling guard will remain in addition to writing this action request, WR 83742 has been initiated to place during a seismic event. It is seismically acceptable, re-tighten the bolts.

but the loose bolts should be tightened.

F-1 0

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report

..... - WITH[:cLD FRO.M PULiC. Bis. Le.U. E Table F-2: Disposition of Area Walk-by Observations Area Walk by Question Observation Disposition Checklist No.

There is no requirement for the attachment of flow meters. The flow meter uses the metal chain to keep it affixed to the pipe. The chain is X21/22 An ultrasonic flow meter is chained to a pipe near 2SI robust and is sufficient for supporting the weight of the meter. In a S PUMP 4 68. The pipe may not be capable of supporting this seismic event the meter would move with the pipe and no extra load seismic load. would be exerted on the chain. The seismic loads for the piping were evaluated within a plant evaluation. The configuration is acceptable, and is not a seismic concern.

AUX 21/22 An oil can is sitting on the pipe support for MV-32185. CAP 1352727 has been initiated to evaluate this observation. Off of SI PUMP 7 There wasthe against nosite's holderseismic found for storing the can, housekeeping which is procedure. his action request, WR 83746 was initiated to address the condition.

AUX 21/22 A steam heating line was found tie wrapped to the line that CAP 1352959 has been initiated to evaluate this observation. In SI PUMP 8 includes the 2-RCCH-538 housekeeping practice,support. The tie and should be wrap is a poor removed. addition, WR 83786 has been initiated to address the condition.

The light fixture to the side of the 22 charging pump has CAP 1352001 has been initiated to evaluate the open "S"hooks AUX 22 an open "S" hook. The light fixture will not fall in a seismic identified during these walkdowns. In addition to writing this action CHRG PMP 4 event, and will not impact any equipment even if it did fall. request, WR 83556. 84434. and 83533 have been initiated to address The 22 charging pump is not in the zone of influence of this observation.

the light fixture.

There are open "S" hooks for lighting fixtures throughout the area. Light fixture near charging pump 71117 and CAP 1352001 has been initiated to evaluate the open "S" hooks on 71119 is an interaction hazard if cabinet contains sensitive light fixtures which have been identified during these walkdowns. In devices. Another open "S"hook on light fixture is above addition to this action request, WR 83556, 84434, and 83533 have MCC 2K Bus 1 and above Miscellaneous Systems 21 been initiated to address these observations.

Relay Rack.

F-11

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report SUNSI - WITI"OL'.D FROM PUBLIC. . . .i. . .U.E Table F-2: Disposition of Area Walk-by Observations Area Walk by Question Observation Disposition Checklist No.

XThere are open "S"hooks at both ends at the top of the CAP 1352001 has been initiated to evaluate the open "S"hooks AUX 3 are op e aboth end at the to identified during these walkdowns. WR 83556, 84434, and 83533 Northwest light fixture above MCC 2L BUS 1. have also been initiated to address this observation.

There is a black barrel collecting leak off from drain line The barrel meets the requirements of the seismic housekeeping AUX 2ZX-1-19 located under the staircase and next to MCC 2L procedure for temporary storage of barrels. The barrel is greater than Northwest BUS 1. The barrel is loosely tied off with rope to the 1.25 times its height from the MCC, and it is tied off to preclude Unistrut supporting panel 2R1A57. movement during a seismic event. No seismic concern exists.

Molded case circuit breakers are generically considered to be non-vulnerable to contact chatter because of the significant seismic forces The light fixture hanging from the ceiling is about 3" to 6" required to spuriously operate these devices. Any force imparted by AUX B E- from an electrical box that is connected to panel 219. the light fixture falling on the panel would be less significant than the MON During a seismic event the fixture may hit the electrical seismic motion of the panel itself. As the panel and breakers are box. designed to withstand the design basis seismic event, the small impact due to the failure of a light fixture would not affect breaker operation. It is not a seismic concern.

Ifthe unit cooler supply and return lines break during a This condition was previously evaluated in a plant calculation which AUX B E- seismic event, it may result in flooding the room. There is performed a determination of seismic adequacy of ZH system 5 no floor drain in the train B event monitoring room. pressure boundary in the Event Monitoring Rooms and other locations Reference hangers 2-RHRH-453, 2-RHRH-448, 2-RHRH- within the plant. No additional review is required based on the 449, and 2-RHRH-454. identified plant documentation. There is no seismic concern.

There are open "S" hooks on the fluorescent lights in CAP 1352001 has been initiated to evaluate the open "S"hooks AUX numerous locations. However, none of the fixtures are identified during these walkdowns. In addition to writing this action NORTH WEST above safety related equipment. There is no seismic request, WR 83556, 84434, and 83533 have been initiated to address concern, this observation.

The wrench hanging from 2MS-27-2 is a potential hazard CAP 1352195 has been initiated to evaluate this observation. In AUX to SV-33266 and SV-33264. The recommendation is to addition to writing the action request, WR 83607 has also been NORTH WEST re-locate the wrench to a height lower than the SV initiate to resst, condition.

elevation, so that it is no longer a potential hazard.

F-1 2

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report

^I I&I^ 1AF ý  % r% r% e%ý ý^l lmý wwlýý - .. . - - W W_ -. 1-Table F-2: Disposition of Area Walk-by Observations Area Walk by Question Observation Disposition Checklist No.

AUX The chain fall located near 2FT-495 should be restrained Site engineering reviewed this observation and concluded itwas not a NORTH WEST 7 so that it doesn't have the potential to impact the seismic concern because the transmitter and tube lines are not safety-transmitter. related.

XThe tube lines near 2FT-495 could potentially impact the These flow transmitters are not safety related and are not required to AUXtulnsmner 2t-495rco uld tiallyhimpactethe be seismically designed per the plant licensing basis. Therefore, there NORTH WEST restrained, is no impact to plant safety as a result of a seismic interaction with the transmitter.

CAP 1352001 has been initiated to evaluate the open "S"hooks D5/D6 There are open "S"hooks for lighting fixtures throughout identified during these walkdowns. In addition to writing this action 221/222 BUS the room. They are not a seismic concern, request, WR 83556, 84434, and 83533 have been initiated to address this observation.

The cabinets are non-safety related. The cabinets are considered D5/D6 D5 There is a trash receptacle between cabinets D5-RTV- seismically mounted, because they are in the area of other safety CONTROL cabinet and remote terminal unit D5. related equipment. The condition described is acceptable, as there is no impact to equipment.

The fire protection piping rod hung sprinkler system has This system is a pre-action system. The piping is filled with D5/D6 D6 5 threaded connections and could pose a flooding hazard if compressed air and it requires a "preceding" fire detection event (heat ENGINE this piping failed during a seismic event, or flame) in order to introduce water into the piping. This piping is not a seismic concern.

CAP 1352001 has been initiated to evaluate the open "S"hooks D5/D6 26 There are open "S" hooks on light fixtures above and identified during these walkdowns. In addition to writing this action BUS adjacent to breaker 26. request, WR 83556, 84434, and 83533 have been initiated to address this observation.

F-1 3

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report

......- WIT', .9lLD .RO. V1M PUDALC. .... ...

Table F-2: Disposition of Area Walk-by Observations Area Walk by Question Observation Disposition Checklist No.

Open "S" hooks were identified on the following fluorescent lighting fixtures: CAP 1352001 has been initiated to evaluate the open "S"hooks TURB 22 a.

b west bv of the or4 turbine driven auxiliary feedwater pump identified during these walkdowns. In addition to writing this action AFWP 4 b.above door 42 request, WR 83556, 84434, and 83533 have been initiated to address

c. above the 12 motor driven auxiliary feedwater pump this observation.

(only 1 chain)

d. above 124 AC The 1-1/2" fire protection sprinkler lines are flexible and The horizontal sprinkler head piping is supported with clips to a TURB 22 threaded so they could be a potential spray hazard if they Unistrut or other large-diameter piping. The vertical supply lines to the AFWP are filled with water. The lines are over the motor driven sprinklers are of the pendant style (hang down from above), and are and turbine driven auxiliary feedwater pumps. considered seismically robust. They are not a seismic concern.

An earthquake significantly beyond the plant's design basis The chain fall near TB2395 could potentially impact tubing earthquake would be required to swing the chain into the stainless TUB 2 7 on concrete wall. It is recommended that this chain be steel tubing. Ifa beyond design basis earthquake did occur, the loss AFWP restrained, of this tubing would not negatively affect plant safety. Therefore, it is not a seismic concern.

The gravitational force from the hammer would not be large enough to A fire protection break glass hammer is adjacent to the damage the tubing to the point where it could no longer feed CV-TURB 22 123 air compressor control panel 70557. The hammer 31191, the 123 Station Air Compressor Unloader. Additionally, both of AFVVP compre ntrol panel 75. the these valves are non-safety related. The loss of these valves in a could potentially impact the nearby air tubing. design basis earthquake would not negatively affect plant safety. It is not a seismic concern.

CAP 1352001 has been initiated to evaluate the open "S"hooks TURB BATT 22 4 Some of the'S"closed.

not completely hooks forNone lighting fixtures of the lightinginfixtures the areawith are identified R856 rqet during these walkdowns. In additioneniiitdt 43.ad853hv to writing this action drs open "S" hooks are over the batteries. request, WR 83556, 84434, and 83533 have been initiated to address this observation.

F-1 5

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report SUNS' WIT' 11'19LD1 FROM PUDbLC D~si~CLOURE Table F-2: Disposition of Area Walk-by Observations Area Walk by Question Observation Disposition Checklist No.

Door 228 counterweight is next to Panel 22. Because of the low peak vertical acceleration at the site, there is no reason to suspect that the "S"hooks could become unloaded to allow the weight to disengage.

TURB 22 The counterweight "Sf hook is also open and the However, CAP 1352343 was initiated to address the open "S"hook.

BATT counterweight could fall to the floor or against PNL 22. In addition to writing this action request, WR 83645 and WR 83646 were initiated to upgrade the remaining doors so that they are connected to a pull cable with a threaded carabineer.

TURB 22 Eyewash station is securely stationed to the wall. Plant engineering reviewed the restraint for the water supply to the BATU 4 However, the water supply canister on the cart is secured eyewash station and concluded that the bungee cord was an by a bungee cord which may not be an adequate restraint, acceptable means of restraining the canister.

Duct tape is preventing a chain for a fluorescent light TURB BUS fixture from making contact with a conduit. This type of CAP 1352192 has been initiated to evaluate this observation.

121 restraint is not necessary and should be removed. It is a Additionally, WR 83605 has been initiated to correct the condition.

housekeeping issue and not a seismic concern.

Supply and return lines for the 121 switchgear room unit Plant engineering has evaluated this observation and concluded that TURB BUS cooler are unsupported laterally across the room, and may the piping is seismically installed. The subject piping is analyzed in a 121 not be adequately restrained to prevent excessive nozzle loads on the unit cooler, plant calculation, and is shown to be acceptable.

Plant engineering has evaluated this observation and noted that as The cables going into relay racks 2AMR1,2ARP1, 2ARP2, the cables exit the rack, they are bundled and secured to the cable TURB 2ARP3, 2ARP4, and 2ASG2 are each two feet long. They tray supports prior to entering the tray. Cables of this type are allowed RELAY 3 are tied to a single Unistrut with tie wraps. The Unistrut to have significantly longer unsupported vertical runs, according to site may not be adequate to support the load from the cables, procedure. The grouping and securing of these cables to the supports on top of the cable tray load it is already supporting. with tie wraps is a cosmetic function only. The installation is in accordance with site procedures and is acceptable.

F-1 6

Prairie Island Nuclear Generating Plant - Unit 2 Seismic Walkdown Submittal Report SUNS' - WITh 1 -L 119:13FR( PUBLIC 1305eteURE Table F-2: Disposition of Area Walk-by Observations Area Walk by Question Observation Disposition Checklist No.

Plant engineering evaluated the installation of these abandoned TURB There are several large rolls of abandoned cable that are cables and determined that the cables are marked and coiled in RELAY Comments tied together with cable ties to Unistrut. These abandoned accordance with site guidance for abandoned cables and conduits. It cables are near MCC 2BMRI and TB-2228. is not a seismic or housekeeping concern.

A calculation was found which previously performed a determination TURn TRN Supply Supply and return ERoom lines are laterally unrestrained and may of seismicand adequacy of ZH system other locations pressure within the plant. boundary in the No additional 122 Bus review is required based on the identified plant documentation. There is no seismic concern.

AUX There are lighting diffusers tied off to the support grid.

CONTROL 4 Unit 1 and Unit 2 "C" panels have a fluorescent light fixture CAP 01352209 has been initiated to evaluate this observation.

ROOM on chains too close (within 1"-2") to the panel.

AUX The trash can next to the racks R23, R24, R13, and R14 The trash cans are located next to non-safety related miscellaneous CONTROL 7 are immediately adjacent to the racks, which violates the racks. This condition is acceptable per site procedure guidance.

ROOM seismic housekeeping procedure. There is no seismic concern.

AUX CAP 01352001 was initiated to evaluate this observation. Off of CAP CONTROL 7 There were several open S-hooks on light fixtures (nearest 01352001, WR 83556, 84434, and 83533 were initiated to address ROOM the panel in most cases). this observation.

The trash cans are located next to non-safety related miscellaneous AUXTRL Se aladdero adaen totheracks. R23e Rheels Rshod Re i racks. There is no impact to the equipment. However, all wheeled NROLM 7he cksd. carts should be chocked. The FIN team has been notified to chock the ROOM chocked. wheels.

F-1 7

PR6PRIETARY' INFEORr4ATIONl WIE113flHe13B FRE)M PUBble B3ESebE)SURB Sheet I of 3 Status: Y0 NO] U[]

Seismic Walkdown Checklist (SWC)

Equipment IDNo. 55320 Equip. Class, (20) Instrumentationand Control Panelsand Cabinets Equipment Description D5 DSL GEN ENG I AUX DESK Location: Bldg. D/QD6 Floor El. - Room, Area Q5 ENGINE 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 SWVEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

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

The SWEs verified the anchorage of the steel skid to the frame, There were ten 1/2' anchors, five on the front and five on the back, as well as, eight anchors,four each on either side.

2. Is the anchorage free of bent, broken, missing or loose hardware? YN NO U0 N/AQ

3. Is the anchorage free of corrosion that is more than mild surface Y0 NO UO N/AO oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YN NOI U- N/A"

5. Is the anchorage configuration consistent with plant documentation? Y0 NE UO N/A[D (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 YONEI U potentially adverse seismic conditions?

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

PROPRIET*RY IUFeMIATICN wiTHU3LD FROZI PUBLIC DiseLCJbRH Sheet 2 of 3 Status: Y[] NEI U11 Seismic Walkdown Checklist (SWC)

Equipment ID No. 55320 Equip. ClassL (20) Instrumentationand Control Panels and cabinets Equipment Description D5 0SL 3EN ENG 1AUX DESK Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y0 NO Ur N/AO

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Yo NI] UQ N/AO and masonry block walls not likely to collapse onto the equipment?

There are no block walls and everything In the viclnily is seismically braced.

9. Do attached lines have adequate flexibility to avoid damage? YP9 NE-I U. N/AIi

10. Based on the above seismic interaction evaluations, is equipment free Yj@ NO UI" of potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that conld Y0 NCi UI adversely affect the safety functions of the equipment?

I There are missing cap nuts on the south side of the cabinet, This Is a maintenance Issue and not a seismic Issue.

CAP 1356613has been Initiatedto evaluate this observation, In addition, WRO48ft was initiatedto address this observation.

499'97-1 Commlents (Additional pages may be added as necessary)

The front doors were openedand no anomalies were found, Evaluated by: Walter Dordievia Date:

Wye Krieseil 5~

PRePRITAIZY~ INFORMATION WITHHOLD PROP! PUBLLIC DISCLO0StURE Sheet of ii Status: YO NE] UEf Seismic Walkdown Checklist (SWC)

Equipment ID No. 2LT-921 Equip. Class, (18) Instruments on Racks Equipment Description 21 RWSTLVL XMTR Location: Bldg, AUX Floor El. - Room, Area 21/22 SI PUMP 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 YO NEI of the 50% of SWEL items requiring such verification)?

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

3. Is the anchorage free of corrosion that is more than mild surface YN NEI U[-1 NIAE-oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YOf NEI UD N/AU

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

The transmitteris bolted to the plate using the factory mounting hardware. The plate is welded to two 2"x2"x 1/4"angles. The angles are bolted to the wall using four 1/2" diametershell anchors that are in a 9Ux 17." boltpatternperthe SQUQ SEWS. There are no seismic or configurationconcerns.

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

PTAPPTRITAPV TWFOATh43.TTO WTTTTHOT.P PPOM PY-MlT.Tr- PTnr-9rrP'qTP Sheet 2 of 11 Status: YO NEI UE-Seismic Walkdown Checklist (SWC)

Equipment ID No. 2LT-921 Equip. Class (18f Instruments on Racks Equipment Description 21 RWST LVL XMTR

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

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO NEI UONI/AD

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YOI NEI U-I N/A'-

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

9. Do attached lines have adequate flexibility to avoid damage? YO NEI UD N/AQ

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

The cabinetlabeled 'clean chemical handlingequipment" (36' x 24"x 75a high) is stored about 40"from the level transmitteron the otherside of the walkway. Its aspect ratio would cause it to fall over Into the transmitterIfit is not anchoredto the wall.

I> C.

GP3512O btuetj in~iglcied tO evaiuaie ibis oLbsEuvaLipon. J '2 -*

Site Engineering discovered later that the cabinet is anchored to the wall with two small anchors, which can only be found by opening the cabinet and moving internal contents to see them. Therefore this observation is resolved and there is no adverse seismic condition.

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?

PReROHIITAR-Y INFORMATION WIThHOL1D FROIM PUBLIC DIGGLEOGiRB Sheet 3 of :a Status: YM NE-] U]'

Seismic Walkdown Checklist (SWC)

Equipment ID No. 2LT-921 Equip. Classl (18) /nstruments on Racks Equipment Description 21 RWwsT LVL XMTR .

C mt..a. .. ... .. . . .

Comments44100W.i~a pugk.sin y be ad d.i M.ncc ssqry Evaluated by: BrucO Lorv Date: /6-ý*' -,Z DileeD Cheropalle .i~ RA

PROPR- -N,-IUGF ET\R-Y r, T'I WITHH41OLD FROM PgBLIC DISC-LOSURE Sheet i of 14 status: YN NEI U[]

Seismic Walkdown Checklist (SWC)

Equipment ID No. B-2 Equip. Class' (20) Instrumentation and Confrol Panels and Cabinets Equipment Description CONTROL PANEL B-2 Location: Bldg. AUX Floor El. - Room, Area CONTROL 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? Y ND " WN/AD

3. Is the anchorage free of corrosion that is more than mild surface YO NEI UEI NIAD]

oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y0 NO UD1 N/AI]

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

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

I Enter ihe equipmenl class name from Appendix B: Classes of Equipment.

PTflPT lT.V NPPAT O TATII AM~PDI ~D CLf~l Sheet 2 of 14 Status: Y1 NEI U-I Seismic Walkdowh Checklist (SWC)

Equipment ID No. 1-2 Equip. Classi (20) Instrumentationand ControlPanelsand Cabinets Equipmelt Description CONTROL PANEL B-2 Inteitaction Effeets

7. Axe soft targets fi'ee firom impact by nearby equipment or structures? YZ NEI U[I N/ADl

8. Are overhead equipment, distribution sys'tedns, ceiling tiles and lighting, and masoniy block walls not likely to collapse onto the pquipogent?

Y0 NEI UD N/AU

9. Do attached lines have adequate flexibility to avoid damage?

Y0 ND UD

10. BOWsd on the pbove seismic interaction evaluations, is equipment free of potentially adverse seismic intenaction effects?

Other Adverse Conditions i1. Have you looked for and found to other seismic conditions that could YM NEI U-adversely affect the safety functions of lie equipment?

Comments (Additional pages niy be added 4s necessary.)

B 1. Duct tape was kdetified bpbllnd Panqlf-E-t about 8' hlgh between the CVCS letdown and RHR labels.

%0\\9 5 *

-4P 1V5

........... ...... i &a I Ad tqy, WR-69F08 has been Initiated tM remove the foreign materal.

2. There Is a bent bock covarplate for the CVCS letdown monitor, It is locatedat about 10' high near the CVCS letdown label, The cover plate is non-structuraland Is not an adverse seismic condition.

Evaluated by:;ruce M, Lor Date:

Dileen Cherlonalle aVI. tA6e &6e g 4 4A Date: to 6*-* ,-.

PROPRIETARY INFOllLATION WI-T!HHOLD FROH PUBD31- DIZCLGSURE Sheet 1 of 21 Status: YNI NEIJ U-1 Seismic Walkdown Checklist (SWC)

Equipment ID No. E-2 Equip. Class' (20)Instrumentationand ControlPanelsand Cabinets Equipment Description CONTROL PANEL E-2 Location: Bldg. AUX Floor El. - Room, Area CONTROL 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 SWBL. 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 (Le., is the item one YU NO of the 50% of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? YE NEI UI N/AQ"

3. Is the anchorage free of corrosion that is more than mild surface Y0 NEI U0J N/AQ oxidation?

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

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

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

Interaction Effects

7. Are soft targets firee from impact by nearby equipment or structures? YN NO U0I NWAD I Enter the equipment class name from Appendix B: Classes of Equipment.

PRGPRIBTAlZY .NFORMATIE. WEITHHOLD FR..M PUL.. DIC.L. .URE Sheet 2 of 21 Status: YM NI U[-]

We~smlo Walkdown Checklist ($WC)

Equiptuent JD No. E-2 Equip. Class. (20M1nstrumentation and Contfo1 Panels and cabinets ...: . .. ..

Equipment Desijption. CONTROL PANEL E09

8. .Are overhead equipmnt, distribution systems, ceiling tiles and lighting, YE ND U[f 'N/AO and masonry block walls not likely to collapse onto the equipment?

The light fixture nearE-2 in the middle section has one open ."8 hook out of four hooks. E-2 is not In the zone of influence, therefore It Is not a seismic concern. This fight fixture was noted duringthe area walkbys.

CAP 1352001 has been initiatedto evaluate the open "S" hooks on light fixtures which have been identified during these walkdowns. In -addition to this action reqUest, WR 83556 has been initiatedto address these observations.

9. Do attached lines have adeqxuate flexibility to avoid darange? YN -N[_! UT] N./AD.

10, Bad on the .bove seismic interaction evluations, is equipment.free YZNO IUD of potentially adverse seismic interao.tion effects?

Other Adverse .Conditions SI 1,Have you looked for and found io. other seisniic.conditiojaS that could YZ NO Ut]

adversely affect the safety functions of the oquipt 46ht?

CommentS (Additional pages may be added as necessary)

The SWEs identified the following foreign materials;

1. Duct tape was found on the side of the first monitor,about 8' high on the generatorcontrols.

2. A broken tie wrap is inside E-2 andpinned to a diagonalsupport.

3. A tie wrap was found on the edge of a .HVAC duct exhaust above E-2.

CAP 1352954 has been initiatedto evaluate this observation. Additonally, WR 83785has been Initiatedto remove the foreign material.

In addition to the foreign material,the pig tail of a cable with a mult/pin connector was found storedon Pc.

Stop of the box. It Is not a selsmio concern, but it is recommended that the site evaluat@gth c ndtion,

<?_2e-*CAP485 4 hasMLn Initiated to evalUate,this obsejVation. Addition#a1sy Men

[Initiated to remove the foreign material. See Appendix F for site engineerinrk resolution to comment.

Evaluated by* Bruce M. Lore Date: 0 1g, Dileep Cherlopale .. . . . Date:' It , -"V.

PROPRIETARY iNFE)RMATEEGN IWrIT-TTHEh'"D FREW PUrLI- DI-ICLOlSURi Sheet 1 of 4 Status: YjZ NEI I[O Seismic Walkdown Checklist (SWC)

Equipment ID No. MV-32384 Equip. Class' (8) Motor-Operatedand Solenoid-OperatedVames Equipment Description 21 MD AFW PMPDISCH TO 22 SG MV Location: Bldg. TURB Floor El. - Room, Area 02AFWP 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.

Anchorase

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

2. Is the anchorage free of bent, broken, missing or loose hardware? YO NO UO NIAN

3. Is the anchorage free of corrosion that is more than mild surface Y[-1 NO UO NIAS oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YO NO ISO MN/I

5. Is the anchorage configuration consistent with plant documentation? YO NO UO NIAO (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 YE NO UO potentially adverse seismic conditions?

Enter the equipment class name from Appeadix B: Classes of Equipment

PROPRIBTARY ..IF...TI. N ..

wiTiH.. . FRe..

.. PtULIC ..i.....uR Sheet 2 of 4 Status: Y[ NEJ U-]

Seismic Walkdown Checklist (SWC)

Equipment IDNo. MVM32384 Equip. Class' (8) Motor-Qoeratedand So/enoid-OperatedValvae Equipment Description 21 MO AFWPMP DISCH TO 22 S2 MV Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO NEI UI' NIA -I The cantilevered conduit routed above Isnot deemed a seismic hazard because it will not hit the valve.

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[ NEI Uf N/A']

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

9. Do attached lines have adequate flexibility to avoid damage? Y@ NEI UD N/AQ"

10. Based on the above seismic interaction evaluations, is equipment free YZ NO UQ]

of potentially adverse seismic interaction effects?

Other Adverse Conditions 11, Have you looked for and found no other seismic conditions that could Y(@ NEI U0 adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

P1AC 1 &OW Theeon d but requires evaluation.

below the valve is missing one bolt. This is not a seismic issue for the valve, CAP 1356520 has been Initiatedto evaluate this observation. In addition, WR 84626 was initiated to J

addressthis observation.

Evaluated by: Walter Diordievic k1k:: -- Data: It We Wesel Date:

PROPRIETARY INFGRM2TION WIT4111OLD FROM PUBLIC- D1-SCLOCUT1E Sheet I of 8 Status: YE]--I UM Area Walk-By Checklist (AWC)

Location: Bldg. AUX Floor El. Room, Area' 2I/22 CNTM SPRAY 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 YMI NEJ UL] N/AE]

potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant YO NO] U0- N/AL]

degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit YO NE] U0 N/AL]

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 YEI NO ULI N/A[]

interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

1. See comment in the MV-32180 seismic walkdown checklist regardingthe light fixture seismic interactionover MV-32180.

2. Next to the pressuregauge P1-18249, there is a portable cord reelsupportedon the wall by a pin. Since the cord is free to rotate, the reel could swing in a seismic event andpotentially impact the valve and tubing of the pressure gauge.

CAP 1352923 has been initiatedto document the observation, and WR 83779 has been initiatedto eithersecure the portable cord reel from movement or re-locatethe portable cord reel to a more suitable location.

'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.

7REWRfBT-ARLY iNFORPDATION WIT........ IR. . PUBLIC DIS*LO*3UUR Sheet 2 oif 8 Status: YE] NO UE!

Area Walk-By Checklist (AWC)

Location: Bldg. ABIX Vloor El. Room, Area, 21/22 CNTM SPRA Y

5. Does it appear that the .areais freed of paotetially advetse seismid YM NO ULO N/A[0 interoti.Uns that could cause.floodingior spray in the area?

6. Does it'appear that the area is free o-fpotentially adverse seismic Y9/ NO) UI W/AD interaetjuns that 4cm!ld cause fafire in ihe aft?

7. Does It appeat that: the area is free of potentially adverse seistic YED NDi U01 NA9-4

ihteadUions p8soeiated. With ho'tsekeeping pta

cticek, ttofage of portable tqUjpMhent. and temppoary .intallations(e.g., scaffolding, lead ishielding)?

1. Radiation monitor DRM-2MIa attachedmagneticaltyto.electridal panel 2RIA54. The magneticbase may notbe strong enough to prevent the monitor from telling andimpacting the pressure9auge Pl-1824* or associ*ated tubig.o '.,* -"

p

-tme-e~4e~adJ#on-nen~fs CA

.. A -

airbe-nAAtdW

ý35Olsh.~

~AL~iidiiu,, &t

8. Have ou looked for and found no other seismic condittons that could yoNI U13

)

adveraely affect the safety functions of tho equipment in rthe area?

Comments (Additiodal pages may be,added .as necessary)

Foreign material,such as Open bndtie wraps, was; Jdentified. POWt pesonnel rofnoved thls matefial.

Evaluated .bY Dilee. Cherioyalie .d. -A..,. Date: . -

Bruce M .. ...... .. ...

PRePRIETARY IENFORMATIEW w3ET-iffiei3E) FRem ibxBE33Ee B3Esei3esuRE ,

Sheet I of 13 Status: YEJ N0* uI-]

(AWC)

Area Walk-By Checklist Location: Bldg. AUX Floor El. Room, Area' NORTH 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 YO NO UO N/AD potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant YO N[ UQ N/AO degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit YO NE ULD N/AD 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 Y0 NO UD N/AO interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

There are open "S"hooks on the fluorescent lights In numerous locations. However, none of the fixtures are above safety related equipment. There is no seismic concern.

CAP 1352001 has been Initiatedto evaluate the open "Sohooks Identified during these walkdowns. Inaddition to writing this action request, WR 83556 has been Initiatedto addressthis observation.

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.

PROPRiHTARY iNUFORIT3EN wITHHOLeD FROm PUBLICf DiseCLsuRH Sheet 2 of 13 Status: YW -NO UE)

Area Walk-By Checklist (AWC)

Location: Bldg. AUX Floor El. I - Room, Area' t&QRTH WEST i

,-Do appear r 6iUt rfmrew f eupo ttlyadverse snie i-NEFlUsj-NA[-

Interactions that could cause flooding or spray in the area?

The steam unit heater Is suspended on 121 long rods which could break the steam Oine attachedto the heater. The equipment in the area is designedto be environmentally qualified iora Steam line break, therefore thereIs no concern.

6. Does it appear that the area is free of potentially adverse seismic YO NE UQ N/AD interactions that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic YO NO UC] N/AD interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

1. The wrench hanging from 2M8-27-2 is a potentialhazardto SeV-33286 andSV-3M264. The recommendation is to re-locatethe wrench to a height lowerthen the..5G'?elevation, so that i /s no longer a potentlal hazard. '5 '0 -;'5541 ,,,

CAP 1352195 has been initiatedto evaluate this observation. In addition to writing the actionrequest, WR 83607has also been Initiated to addressthis condition. Z*,/4

2. The chain fall located near4LFT.-495should be restrainedso that It doesn'thave the potentialto Impact the transmitter.

_GaP _ _. . . nI .Zl # 13 3V._* 2 11.

., A, ",..

S .r7.........

. .4*' , *V.* rA-%.. ,- - yt.. v',J 24)2

8. Have you looked for and found no other seismic conditions that could YRI NO3 U[O adversely affect the safety functions of the equipment In the area?

The tube lines neakrr-495could potentialyimpact the transmitter. ft is recommended that these lines be restrained.

Site engineeringhas reviewed this observationandconcluded there is no seismic concern, because the transmitterand tube lines are non-safety related. Pleaserefer to the table containedin Appendix F for the dispositionof this observation.

W I T H H O LT " F RO MT P UB1-m D I TGGrT-O -I '

Sheet 3 of 13 Status: Y[] NZ U[]

Area Walk-By Checklist (AWC)

Location: Bldg. AUX Floor El. I Room, Area' NORTH WEST Comments (Additional pages may be added as necessary)

Evaluated by: Wa/ter 0iorcdevic Date:

Dennis Zercher i,5 3 Z- Zor,

PROpRiETARY J*A"T*.-..N iU. - wI.THH.L-. .[.

FR-m Lie D" sC*.J.sb.

Sheet I of 4 Status: Y0 N[ U[-]

Area Walk-By Checklist (AWC)

Location: Bldg. TUB , Floor El. - Room, Arcal BUS 121 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 Y9 N[3 U[-3 MAE potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant YZ N[] U[] N/A[]

degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit YO NO U] N/AD 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)?

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.

PReRi. T.RY INORmATIONw wiT. .O FR,-

.. PUDLIC D....OCUR, Shet 2 of 4 Status: YO NE U[]

Area Walk-By Checklist (AWC)

Location: Bldg. 7VMRB Floor El. ___- Room, Areas BUS 121 _

---4-.Doeflappwe-thath'"e aft.its-f oEnly a-, selsmlo-spatWa - YG-NO -UUI-Nl0-interactions with other equipment in the area (e.g., ceiling tiles and lighting)7

1. The fluorescent light chains are In contact with the cable traysas well as the flex conduit. This is adjudgednot to be a seismic concrn.

2. Duct tape Is preventing a chain for a fluorescent lht f&ure from making contactwth a condult. This type of restraintto not necessaqy and should be removed. It is a housekeeping Issue and not a seismic concern.

CAP 135219.rhasbeen initiated to evaluate this obevation.

Additionally, WR 83605 has been Initiatedto correct the condition.

3. The ladderadJacentto the 0G column Is ad4ustedso that the center of gravity Is beneath the ladderstorage hooks. itIs acceptable.

5. Does it appear that the area is free of potentially adverse seismic YO NO UD1 N/AfJ interactions that could cause flooding or spray in the area?

Supply andreturn lines for the 121 swithgear room unit coolerare unsupportedlateralyacrossthe room, and may not be adequately restrainedto prevent excessive nozzle loAds on the unit cooler.

Site engineeringhas revewed this observationand concluded there is no seismic conoem, Pleaserefer to the table containedIn Appendix F for the disposition of this observation..

6. Doos it appear that the area is froc of potentially adverie oismic YO NO3UCIN/A[:

interactions that could cause a fire In the area?

7. Does it appear that the area Is free of potentially adverse seismic YO N[3 UE3 NIAO Interactions associated with housekeeping practices, storage of portable equlpment, and temporary installations (e.g., scaffolding, lead shielding)?

PIZOPIIETAPRY !NFORMATIEGN WIT1111813E) FREW PUBEife DISeE38Sb'RH Sheet 3 of 4 Status: YOJ NE] U[]

Area Walk-By Checklist (AWC)

Location; Bldg. TURB FloorEl, Room, A-eal BUS 121

8. Have you looked for and found no other seismic conditions that could YO NEI UO adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

Evaluated by: Wafter d vip Date.

Denot acer____ ____