ML17297A323

From kanterella
Jump to navigation Jump to search
Enclosure 2 (Redacted): Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic Updated Transmittal for Prairie Island Unit 1
ML17297A323
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 11/14/2014
From:
Stevenson & Associates, Xcel Energy
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17297A332 List:
References
L-PI-14-113
Download: ML17297A323 (219)


Text

CONTAINS SYNSI WIHIHOu) FROM PYBblC DISCbOSYRe YNDeR 2.390 ENCLOSURE 2 PRAIRIE ISLAND NUCLEAR GENERATING PLANT -UNIT 1 NTTF RECOMMENDATION 2.3 -SEISMIC UPDATED SEISMIC WALKDOWN REPORT (REDACTED)

(218Pages Follow)

SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 50.54(f) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR*TERM TASK FORCE RECOMMENDATION 2.3: SEISM I C UPDATED TRANSMITTAL (ENCLOSURE 1, REVISION 1) for the PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT 1 Renewed Facility Operating License No.

NRC Docket No. 05000282 Preparer:

Reviewer:

Approver: 250 Marquette Plaza -MP4 Minneapolis , MN 55401 Prepared by: Stevenson

& Associates 1661 Feehanville Rd., Suite 150 Mt. Prospect. IL 60056 Submittal Date January 5. 2015 Printed Name Michael Wodarcyk (Enclosure

1. Rev. 1) Bruce M. Lory (Enclosure
1. Rev. 1) Bruce M. Lory (Enclosure
1. Rev. 1) Signature Peer Review Marlene Delaney Team Leader: (Enclosure 1, Rev. 1) Site Acceptance
Corporate Acceptance
Date 11/14/2014 11/14/2014 12/30/2014 Document Number: 13L0201-RPT-002 Document Title: UPDATED SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 50.54(f) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC for the PRAIR I E ISLAND NUCLEAR GENARATING PLANT UNIT 1 Document Type: Criteria D Interface D Report Specificat i on D Other D Drawing D Project Name: NTIF R2.3 Seismic Walkdo w ns (Outage 1 R29) for Xcel Energy Job No.: 13L0201 . II XceIEnergy

' Client: This document has been prepared in accordance with the S&A Qual i ty Assurance Program Manual, Revision ..Jl.....

and project requ i rements: Initial Issue (Rev. 0) Prepared by: Michae l Wodarcyk Date: 11/14/2014 Reviewed by: Bruce M. Lory Date: 11/14/2014 Approved by: Bruce M. Lory Date: Revision Record: Revision No. Prepared byl Revie w ed byl Approved byl Description of Revision Date Date Date DOCUMENT APPROVAL SHEET Figure 2.8 JOB NO. 13L0201 Table of Contents Prairie I sland Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated List of Tables.............................. ..........................................

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

............... iii E x ecutive Summary ............

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

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

iv 1 Introduction

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

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

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

1-1 1.1 Background

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

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

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

.......................... 1-1 1 .2 Plant Overview ...........................

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

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

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

............ 1-1 1 .3 Approach .........................................................................

........................................ 1-2 2 Seismic Licensing Basis .......................

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

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

.... 2-1 2.1 Overview ................

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

................... 2-1 2.2 Design Basis Earthquake (DB E) ....................................

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

....... 2-1 2.3 Design of Seismic Category I SSCs ...........

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

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

2-1 2.3.1 Summary of Seismic Design ..................................

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

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

.... 2-2 2.3.2 Methods for Qua lifying Electrical and Mechanical Equipment and Instrumentation

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

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

...........

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

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

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

2-2 2.3.3 Summary of Codes and Standards

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

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

2-3 3 Personnel Qualifications

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

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

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

......................... 3-1 3.1 Overview ..........................................

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

........... 3-1 3.2 Walkdown Personnel

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

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

............................ 3-1 3.3 Personnel Qualifications

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

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

.............. 3-3 4 Selection of SSCs ................................

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

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

..................... 4-1 4.1 Overview ...............................................

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

...... 4-1 4.2 SWEL Development

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

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

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

.............................. 4-1 4.2.1 SWE L 1 _ Sample of Required Items for the Five Safety Functions

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

.4-2 4.2.2 SWEL 2 -Spent Fuel Pool Related Items ................

.................................... .4-4 4.2.3 SWEL 2 -Development Conclusion

............................................................. .4-7 4.3 Changes to the Final SWE L 1 ....................

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

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

.................. 4-7 4.4 Changes to the Final SWEL 2 ............

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

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

4-7 5 Seismic Walkdowns and Area Walk-Bys ..................................

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

......... 5-1 5.1 Overview .........................

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

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

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

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

5-1 5.2 Seismic Wa lkd owns ...........................................................

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

... 5-1 5.2.1 Adverse A nchorage Conditions

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

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

....... 5-2 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated 5.2.2 Configuration Verification

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

.............................................................. 5-2 5.2.3 Adverse Seismic Spatial Interactions

............................................................ 5-3 5.2.4 Other Adverse Seismic Conditions

............................*..........*........................ 5-4 5.2.5 Issues Identified during Seismic Walkdowns

...............*................................. 5-5 5.3 Area Walk-Bys ...........................................

..........................*.................................. 5-6 5.3.1 Seismically-Induced Flooding/Spray Interactions

............*......*...................... 5-7 5.3.2 Seismically-Induced Fire Interactions

............................................................ 5-7 5.3.3 Issues Identified during Area Walk-Bys ......................................................... 5-8 6 Licensing Basis Evaluations

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

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

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

6-1 7 IPEEE Vulnerabilities Resolution Report ..........................

........................................... 7-1 8 Peer Review ...............

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

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

.......................................... 8-1 9 References

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

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

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

.................. 9-1 Appendices A Equipment Lists ...........................

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

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

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

..................... A-1 B Deferred Seismic Walkdown Checklists (SWCs) ..................................

...................... B-1 C Deferred Area Walk-By Checklists (AWCs) ...................

............................................. C-1 D Peer Review Report ...........

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

................................................................ D-1 ii Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated 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 November 26,2012 Seismic Walkdown Effort 3-2 Table 4-1: Substituted Equipment for Revised SWEL 1 4-7 Table 5-1: Anchorage Configuration Verification 5-3 Table 5-2: Prairie Island Unit 1 SWC CAP Status 5-9 Table 5-3: Prairie Island Unit 1 Area Walk-By CAP Status 5-11 Table 7-1: Prairie Island IPEEE Seismic Vulnerabilities 7-2 Table A-1: Prairie Island Unit 1 -Base List 1 A-2 Table A-2: Prairie Island Unit 1 -Base List 2 A-35 Table A-3: Prairie Island Unit 1 -Final SWEL 1 A-37 Table A-4: Prairie Island Unit 1 -Final SWEL 2 A-43 Table B-1: Prairie Island Unit 1 SWCs Completed after November 26 , 2012 B-2 Table C-1: Prairie Island Unit 1 AWCs Completed after November 26 , 2012 C-2 Table 0-1: SWC Samples from Seismic Walkdown Inspection for Unit 1 performed after November 26, 2012 0-7 Table 0-2: AWC Samples from Seismic Walkdown Inspection for Unit 1 performed after November 26 , 2012 0-8 iii Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Executive Summary Following the accident at the Fukushima Dai-ichi nuclear power plant resulting from the March 11 , 2011, Great Tohoku Earthquake and subsequent tsunami, the NRC established the Near-Term Task Force (NTTF) in response to Commission direction. The NTTF Charter , dated March 30, 2011, tasked the NTTF with conducting a systematic and methodical review of NRC processes and regulations and determining if the agency should make additional improvements to its regulatory system. Ultimately , a comprehensive set of recommendations contained in a report to the Commission (dated July 12 , 2011, SECY-11-0093 (Agency wide Documents Access and Management System (ADAMS) Accession No. ML 111861807>>

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-11-0093 (ADAMS Accession No. ML 112310021), in part , to determine which of the recommendations could and should be implemented without unnecessary delay. On September 9, 2011, the NRC staff provided a document to the Commission (ADAMS Accession No. ML 11245A 158) 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. nu c lear 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 Novemb e r 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. Ina ccessib ility 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 1 Seismic Walkdown Submittal Report, Updated the timing of the is s uan ce 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) 1 R30 and submitting an updated Seismic Walkdown report 60 days following the end of the refueling outage in 2016. 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 ne xt refueling outage , if possible.

The NRC staff requested that licensee s 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 1 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 (R FO) 1 R29. Following th e 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 RAls 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 Actio n Program Act ion Requests (CAPs) were entered into the site's 10 CFR 50 Appendix B qualified corrective action program. v Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated The EPRI Seismic Walkdown Guidance was used for the engineering walkdowns and evaluations described in this report. In accordance with the EPR I Seismic Walkdown Guidance, the following topics are addressed in the subsequent sections of this report:

  • Seismic Licensing Basis
  • Personnel Qualifications
  • Select i on 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 NTIF Recommendation 2.3 , Seismic (Reference 6). No additional Seismic Walkdowns are required for PINGP Unit 1. vi 1 Introduction Prairie Island Nuclear Generating Plant -Unit 1 Seis mic Walkdown Submittal Report , Updated

1.1 BACKGROUND

In response to Near-Term Task Force (NITF) 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 specific degraded , nonconforming , or unanalyzed conditions (through the corrective action program), verify the adequacy of monitoring and maintenan c e for protective features , and inform the NRC staff of the results of the walkdowns and corrective actions taken or planned. The Nuclear Energy Institute (NEI), with the Electric Power Research Institute (EPRI), prepared industry guidance to assist licensees in responding to this NRC request. The industry guidance document , EPRI Technical Report 1025286 , Seismic Walkdown 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 2-loop pressurized water reactors owned by NSPM. Westinghouse Electric Corporation designed and supplied the nuclear steam supply systems , initial reacto r 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:

1-1 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated 1.3 ApPROACH The EPRI Seismic Walkdown Guidance (Reference

1) is used for PINGP Unit 1 engineering walkdowns and evaluations described in this report. In accordance with Reference 1, the following topics are addressed in the subsequent sections of this report:
  • Seismic Licensing Basis (Section 2)
  • Personnel Qualifications (Section 3)
  • Selection of SSCs (Section 4)
  • Seismic Walkdowns and Area Walk-Bys (Section 5)
  • Licensing Basis Evaluations (Section 6)
  • IPEEE Vulnerabilities Resolution Report (Section 7)
  • Peer Review (Section 8) 1-2 2 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated 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 (DB E) is based upon a ma x imum 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 , Classification of Structures and Components
  • USAR Section 12.2.1.3.5 , Seismic Loads
  • USAR Section 12.2.1.4, General Design Criteria for Structures
  • USAR Section 12.2.1.4.3, Structural Design Basis
  • USAR Section 12.2.1.5., Seismic Analysis of Mechanical and Ele c trical Equipment These USAR sections should be referred to for a detailed understanding of the seismic licensing basis. 2-1 Prairie Island Nuclear Generati ng Plant -Unit 1 Seismic Walkdown Submittal Report, Updated 2.3.1 Summary of Seismic Design The site Opera ting Basis Earthqua ke (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 dete r mine the ma x imum 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 mean-square (RMS) method. From this , a set of curves were developed showing the ma x imum translational accelerations , displacements , shears, and moments as varying with height. The ma x imum 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, Appe ndi x E -Reference 2). The se OBE and DBE ground response spectra were plotted at 0.5%, 2% a nd 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 Electrical and 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 Stati c Analysis Static analysis is performed for an equipment item determined to be rigid. The seismic forces on each component of the equipment a re 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 forc es are converted to stresses and are added to the other equipment stres ses, 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 1 Seismic Walkdown Submittal Report, Updated 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 afte r 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 e x trapolation from similar equipment or simi la r 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:

  • Cont"inment

-the applicable codes , standards , and specifications for the containment are 1 through 23 in T able 2-1 below.

  • Containment Intern a l Structures

-all of the items listed in Table 2-1 below are applicable for the conta inm ent 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 1 Seismic Walkdown Submittal Report, Updated Table 2-1: List of Codes , Standards , and Specifications Specification Specification or Reference Number Standard Title Designation American Concrete Building Code Requirements for Reinforced 1 Institu t e (ACI) 318-71 , 77 , 83 Concrete (Reference

14) 2 ACI301 Specifications for Structural Concrete for Buildings (Reference
15) 3 ACI347 Recommended Practice for ANSI A 145.1 Concrete Formwork (Refere nce 16) 4 ACI305 Recommended Practice for Hot ANSI A 170.1 Weather Concreting (Reference
17) Recommended Practice for Selecting 5 AC1211.1 Proport i ons for Normal Weight Concrete (Reference
18) Recommended Practice for Measuring , Mixing , 6 ACI304 Transporting , and placing concrete (Reference
19) 7 ACI315 Manual of Standard Practice for Detailing Reinforced Concrete Structures (Reference
20) 8 ACI306 Recommended Practice for Cold Weather Concreting (Reference
21) 9 ACI309 Recommended Practic e for Consolidation of Concrete (Reference
22) 10 ACI308 Recommended Practice for Curing Concrete (Reference
23) Recommended Practice for ANSI A 146.1 11 ACI214 Evaluation of Compression Test Resu l ts of Field (Reference
24) 12 ACI311 Recommended Practice for Concrete Inspect ion (Reference
25) 13 ACI304 Preplaced Aggregate Concrete for Structural and Mass Concrete (Reference
26) 14 Report by ACI Plac ing Concrete by Pumping Method Co mmittee 304 (Reference
27) Specification for the Design , F ab ricat io n , and 15 AISC-69 , 78 Ere ction of Structura l Steel for Building (Reference
28) Structura l Welding Code (Reference
29) 16 AWS 01.1 2-4 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table 2*1: List at Codes , Standards , and S pecifications Specif i ca ti on Specificat i o n o r S t a n dard Title Reference Numbe r Desig n ati o n ASME Boiler & Pressure Vessel Code ,Section III (Reference 3D) ASME-1971, S73 Division 1, Subsection NE ASME-1974 , S75 Division 1, Subsection NF 17 Division 2, Proposed Standard Code for ASME-1973 Concrete Reactor Vessels and Containments Issued for Trial Use and Comments ASME-1980 Division 2, CC 6000 ASME-1992 1992 Addenda, D ivisi on 1,Section XI, Subsection IWL , IWE American Public Test Methods Sulphides in Water , Standard 18 Health Assoc. Methods for the E x amination of Water and (APHA) Waste Water (Reference
31) 19 ASTM Annual Books of ASTM Standards (Reference
32) 20 CRSI MSP-1 Manual of Standard Practice (Reference
33) Proposed Supplementary Q.A. Requirements for Installation, I nspection 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 CRD Department of the Army, Handbook for Concrete and Cement Volume I and II , Corps of Engineers U.S. Army (Reference
35) 23 ACI-349-76 , 85 Code Requirements for Nuclear Safety Related Concrete Structures (Reference
36) 24 AISI Specification for design of cold-formed stee l structural members (Reference
37) 2-5 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submitta l Report , Updated 3 Personnel Qualifications 3.1 O V ERVIEW This section of the report identifies the personnel that part i cipated in the NTIF Recommendation

2.3 Seismic

Walkdown efforts. This sect i on also describes the qualifications of t hese personnel.

A descr i ption of the responsibilities and minimum qualifications of each Seismic Wa l kdo w n participant's role(s) i s provided in Section 2 of the EPRI Report 1 0 25286 (Reference 1). 3.2 WALKDOWN PERSONNEL Table 3-1 belo w summarizes the names and corresponding roles of personnel w ho participated in the initial NTIF Recommendation

2.3 Seismic

Walkdo w n effort. The names and correspond i ng roles of personnel w ho part i cipated in the NTIF Recommendation 2.3 Seis mi c Walkdo w n effort after November 26, 2 012 are provided in Table 3-2. Table 3-1: Personnel Roles -Initial Seismic Walkdown Effort Equ i pment Se i smic Licensing Plant Wa l kdown I PEEE Peer Name Selection Operations Engineer Basis Reviewer Reviewer Engineer (SWE) Reviewer B. Lory (S&A) X X W. Djordjev i c (S&A) X D. lercher (NSPM) X D. Cherlopalle (NSPM) X X' K. Kriesel (NSPM) X X 3 S. Seilh y mer (N S PM) X X' P. V altakis (NSPM) X X T. B a c o n (S&A) X2 M. Etre (S&A) X D. M oor e X Note s. 1. Peer Revi ew Team member for SWE L revie w onl y. 2. Peer Revie w Team Lead e r. 3. N o licensing basis evaluations w ere performed. 3-1 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Table 3-2: Personnel Roles -Post November 26,2012 Seismic Walkdown Effort Equipment Seismic Licensing P l ant Walkdown IPEEE Peer Name Select i on Operations Engineer Basis Reviewer Reviewe r Engineer (SWE) Reviewer B. Lory (S&A) X X D. Cherlopalle (NSPM) X X' K. K ri ese l (NSPM) X X 3 S. Se il hymer (NSPM) X X' M. Delaney (S&A) X' P. Gazda (S&A) X M. Wodarcyk (S&A) X D. Moore X B. Fauver (NSPM) X X Notes. 1. Peer Revie w Team member for SWEL revie w only. 2. Peer Revie w Team Leader. 3. No licensing basis evaluations w ere performed. 3-2 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated 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. Lorv

  • Activities Performed: Equipment Se l ection, SWE
  • Seismic Training Completed:

Instructor for the Fundamentals of Equipment Seismic Qualification Tr aining 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 19+ years in Seismic Qua lif ication of equipment and components , and 16+ years of Environmental Qua lification experience, in consu lting services and in utility positions.

Currently works as a senior consultant for Stevenson and Associates with specialization in Seismic and Environmental Qua lifi cat ion , as well as Single Failure-Proof crane design verification. Walter (Wally) Djordjevic

  • 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 Te chnology

  • Professional Experience:

38+ years o f 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 seism i c, blast , fluid , and wind load s. 3-3 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Dennis Zercher

  • Activities Performed: SWE
  • Seismic Training Completed:

EPRI SQUG Training

  • Education:

BSCE, Michigan Technological University

  • Professional Experience
28+ y ears 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 NTIF 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
12+ 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 Nucle a r Generating Plant -Unit 1 Seismic Wa l kdown Submittal Report , Updated Stephen Se ilhym er

  • Activities Performed
Equipment Selection Peer Reviewer
  • Seismic Training Completed: N/A
  • Education:

Bachelor of Science in Physics -Applied Nuclear Science f rom Winona State University

  • Professiona l Experience:

Rea ched rank of Electronics Technician First Class and performed as Reactor Operator and Engineering Watch Superv i sor on a nuclear powered submarine in the United States Navy. Obtained Senior Reactor Operato r License and has comp l eted ro l es as Equipm ent Operator , Contro l Room Supervisor , Shift Manager , Assistant Operations Manager, Li censed Operato r Requalification Training Superv i sor, and Opera tion s Simulator and Classroom I nstructor positions at PINGP. Has a total of 30 years of nuclear expe r ience, wi th 18 years of experience as a Senior Reactor Operator. Pete Va ltakis

  • Activities Performed: Equipment Selection (In itial phase on l y)
  • Seism i c Training Comp l eted: N/A
  • Education: Bachelor of Sc i ence in Physics , Wi nona State University
  • Professional E x perience: Acted as a Reactor Operator on a nuclear powered submarine in the United States Navy , and was also assigned as a L eading Petty Officer of the Reactor Controls Division , an Engineering Officer of th e Watch, and a Training Coordinator for th e Naval Prototype Training Unit. Obta in ed Senior Reactor Ope r ator License at PINGP and has completed r o l es as Reactor Operator, L ead Ope r ator, Control Room Supervisor, and Shift Manager a t PINGP. Participated in a ll phases of pre-operational testing and init ia l 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 1 Seismic Walkdown Submittal Report, Updated Todd Bacon

  • Activities Performed:

Peer Review Team Leader

  • Seismic Training Compl e ted: Near Term Task Force Recommendation 2.3-Plant Seismic Walkdowns
  • Education: Bachelor of Science in Civil Engineering from the University of Illinois -Champaign
  • Professional E xperie nce: 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 e x perience 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 Gen e rating Plant -Unit 1 S eismic Walkdown Submittal Report , Updat e d David L. Moore

  • Activities Performed: IPEEE Reviewer
  • Seismic Training C ompleted:

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 E x perience: 30+ years of seismic PRA and SMA e x perience 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 s uccess paths and seismic equipment lists , performance of seismic w alkdowns , quantification of seismic CDF and LERF , and performance of uncertainty and sensitivity analyses. Currently works as a Consultant for several seismic PR A 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 E x perience: 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 1+ years of e x perience as a Senior Reactor Operator.

Marlene Delaney

  • Activities Performed: P e er 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 E x perience: 30+ years of experience in commercial nuclear industry.

Currently a Proje c t (Structural)

Engineer at Stevenson

& Associates (S&A). 3-7 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated 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
3+ years of e x perience in commercial nuclear industry. Currently a Project (Structural)

Engineer at Stevenson

& Associates (S&A). 3-8 4 Selection of SSCs Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated 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 entitled Base List 1.
  • Table A-2 contains the list of equipment that are required to support Spent Fuel Pool (SFP) Cooling and are classified as Seismic Category 1. This list of equipment is entitled Base List 2.
  • Table A-3 is the PINGP Unit 1 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 SFP equipment which is in SWEL 2. This list of equipment is termed SWEL 1.
  • Table A-4 is the PINGP Unit 1 list of equipment necessary to support SFP cooling and inventory , has gone through the screening process defined in Reference 1 , and then selected from this list to be seismically inspected in accordance with Reference
1. Th is l ist of equipment is termed SWEL 2. 4.2 SWEL DEVELOPMENT The selection of SSCs process described in EPRI Technical Report 1025286 , Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force R eco mmendation 2.3: Seismic , dated June 2012 (Re ference 1). was utilized to develop the SWEL for PINGP Unit 1. 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. 4-1 Prairie I s land Nuclear Generating Plant -Unit 1 Seismi c Walkdown Submittal Report , Updated 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 shutdo w n and maintaining containment integrity began w ith th e 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 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 1 E devices were identified as Se i smic Category I. Seismic Category I and Class 1 E 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 H V AC 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 10 CFR 50.54(1) 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 thi s change in order, the Base List 1 in Table A-1 of Appendi x 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 is identified for each item on SWEL 1. 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, Sy s tems to Support Saf e ty Fun c ti o n(s), of Reference
1. 4-2 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated B. Major n ew and replacement equipment The equipment included on SWEL 1 includes several items that have been modified or replaced over the past several years. Ea c h item on SWEL 1 that is n ew or replaced is identified. C. A variety of types of equipment The equipment class is identified for each item on SWEL 1. The equipment included on SWEL 1 is a representative sample from each of the classes of equipment listed in Reference 1 Appendix B: Classes of Equipment.

Where appropriate, at least one piece of equipment from each class is included on SWEL 1. Screens #1 , #2, and #3 resulted in no equipment in equipment classes (12) Air Compressors or (13) Motor Generators.

D. A variety of en vironments 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> 5.0E-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 th e final SWEL 1. Add ition a lly , the list of risk-significant equipment from internal plant PRA was compared with the draft SWEL 1 to confirm that a reasonable sample of significant equipment (relevant for a seismic event) was included on SWEL 1. 4-3 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submitta l Report , Updated 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 ma int aining the following five safety functions:

A. Reactor Reactivity Control B. Reactor Coolant Pressure Control C. Reactor Coolant Inventory Control D. Decay Heat Removal E. Containment Function These five safety functions were defined in Section 3 of Reference

1. The first four functions are associated with bringing the reactor to a safe shutdown cond it ion. The fifth function is associated with maintaining containment integrity. It is noted that items on SWEL 1 with a specific safety function(s) a r e 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, cor responding 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 process for selecting a sample of SSCs associated with the spent fuel pool (SFP) began with a review of the plant design and licensing basis documentation for the SFP and the interconnecting SFP coo ling system. The following four screens narrowed the scope of SSCs to be in cluded on the second Seismic Walkdown Equipment List (SWEL 2): 1. Screen #1 -Seismic Category 1 Only those items identified as Seismic Category 1 (SC-I) are t o be included on SWEL 2 with exception of the SFP structure.

As described in Reference 1 , the adequacy of the SFP structure is assessed by ana ly sis as a Seismic Category 1 structure.

Therefore, the SFP structure is assumed to be seismically adequate for the purposes of this program and is not included in the scope of items included on SWEL 2. Within the SFP system , only the SFP pumps and heat exchangers are classified as Non-Safety Related , Seismic Category 1 equipment.

Therefore , these equipment 4-4 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated items are added to SWEL 2. There are no motor-, air-, or fluid-operated valves in the SFP system flow paths. 2. Screen #2 -Equipment or Systems This screen considers only those items associated with the SFP that are appropriate for an equipment walkdown process. The spent fuel pool structure is designed as Class I structure that fully meets the seismic and tornado design criteria given in Section 12 of Reference

2. The fuel pool structure is also designed to withstand the hydraulic pressure of the contained water, as well as other credible static and dynamic load cases (Section 10.2.1.2.1

-Reference 2). The SFP gates are between the pools and the transfer canal. These gates are part of the overall SFP structure and are designed as SC-1 structures; therefore , the SFP transfer gates are included in the SFP structural analysis and are thereby excluded from being added to SWEL 2. 3. Screen #3 -Sample Considerations This screen represents a process that is intended to result in a SWEL 2 that sufficiently represents a broad population of SFP Seismic Category 1 equipment and systems to meet the objectives of the NRC 50.54(f) Letter. The results of this screen are provided in Table A-2 of Appendix A of this report. The following attributes were considered in the development of SWEL 2: A. A variety of types of systems The system is identified for each item on SWEL 2. The equipment included on SWEL 2 is a representative sample of the systems associated with the SFP and its cooling system. B. Major new and replacement equipment The equipment included on SWEL 2 includes items that have been modified or replaced over the past several years. No such equipment has been identified.

C. A variety of types of equipment The equipment class is identified for each item on SWEL 2. The equipment included on SWEL 2 is a representative sample of each class listed in Reference 1 Appendix B: Classes of Equipment.

Where appropriate , at least one piece of equipment from each class is included on SWEL 2. The classes/types of equipment include; (5) Horizontal Pumps and (21) Tanks and Heat Exchangers.

None of the valves i n the SFP system are power-operated (motor, pneumatic, hydraulic);

therefore , no valves are included on SWEL 2. 4-5 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated D. A variety of environments The location for each item is identified on SWEL 2. The equipment included on SWEL 2 is to represent a variety of environments (locations) for equipment associated with the SFP and its cooling system. All items are , located in the Auxiliary Building. 4. Screen #4 -Rapid Drain-Down This screen identifies items that could allow the spent fuel pool to drain rapidly. Consistent with Reference 1, the scope of items included in this screen is limited to the hydraulic lines connected to the SFP and the equipment connected to those lines. For the purposes of this program it is assumed the SFP gates are installed and the SFP cooling system is in its normal alignment for power operations. The SFP gates are passive devices that are integral to the SFP. As such , they are considered capable of withstanding a design basis earthquake without failure and do not allow for a rapid drain-down of the SFP. The SSCs i dentified in this screen are not limited to SC-1 items, but are limited to those items that could allow rapid drain-down of the SFP. Rapid drain-down is defined as lowering of the water lev el to the top of the fuel assemblies within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after an SSE. Excerpts from the PINGP USAR 10.2.2 document the design features which preclude rapid drain down of the Spent Fuel Pit. The spent fuel pool cooling system is designed to remove the heat generated by stored spent fuel elements from the spent fuel pool. System design does not incorporate redundant components except for the spent fuel pool pump and the heat exchanger.

Alternate cooling capability can be made available under antiCipated malfunctions or failures; System piping is so arranged that failure of any pipeline does not drain the spent fuel pool below the top of the stored spent fuel elements.

The spent fuel pool pump suction line is lo cated above the fuel assembl i es; this prevents uncovering fuel assemblies during loss of water as a result of a possible suction line rupture. The most serious failure of this system is complete loss of water in the storage pool. To protect against this possibility , piping connections enter the top of the spent fuel pool as stated above except for the drain connection from the transfer canal to the holdup tank recirculation pump. Even if the water in the transfer canal were completely drained, the active portion of the spent fuel would not be uncovered due to the elevation of the bottom of the gate connection in the wa ll separating the transfer canal from the spent fuel pool. Thus , comp l ete siphon draining of the pool is impossible.

The spent fuel pool pump suction connection only goes approximately 4 feet below the normal water level. The cooling water return line which extends 10 feet below the normal water level i s prevented from siphon draining the pool by a 0.5 inch hole in the pipe located 4 feet below the normal water level. 4-6 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Based on the PING P spent fuel pool design described , the spent fuel pool does not have a rapid drain down scenario.

4.2.3 SWEL 2 -Development Conclusion There are no rapid drain-do w n considerations included in the PINGP SWEL 2 list. The SFP is shared between both units at the PINGP. The results of the seismic walkdowns for SWEL 2 are presented i n this report for the PINGP Unit 1. The seismic walkdown report for PINGP Unit 2 does not contain a discussion of SWEL 2 walkdo w ns. 4.3 CHANGES TO THE FINAL SWEL 1 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 1 R29, NSPM evaluated component availability to determine opportunities where the equ i pment 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 two (2) components that would not be out of service during 1 R29 to allow for internal cabinet inspections. These two (2) components were Seismic Walkdown Equipment List 1 (SWEL 1) items BUS 16 and BUS 122. NSPM identified two (2) similar components that were available in the outage for inspection. For the 480V switchgear internal cabinet inspections , BUS 15 was substituted for BUS 16, and BUS 112 was substituted for BUS 122. In addition, equipment tag no. 174-013 (13 Containment Fan Coil Unit) was removed from the l i st of equ i pment whose anchorage required verification , due to its internal anchorage being inaccessible during RFO 1 R29. The anchorage verification requirements described in Sect. 5.2.2 of this report are met despite the removal of 174-013 from the anchorage verification l i st. A summary of the SUbstitutions is provided in Table 4-1. Table 4-1 -Substituted Eq u ipment for Revised SWEL 1 Original Equipment Tag Replacement Equipment Tag BUS16 BUS15 BUS 122 BUS 112 4.4 CHANGES TO THE FINAL SWEL 2 After the November 26,2012 report (Reference 13), no changes were made to the final SWEL2. 4-7 5 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated 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 the Seismic Walkdowns have been documented on the Seismic Walkdown Checklists (SWCs) and A rea Walk-By Checklists (AWCs). The results of ali 107 Seismic Walkdowns were documented on Seismic Walkdown Checklists.

The Seismic Walkdown Checklists 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 C hecklists , but are not included with the Seismic Wa lkdown 5-1 Prairie I s l and Nuclear Gene r ating Plant -Unit 1 Seismic Wa l kdown Submittal Report , Updated Checklists because they are readily retrievable documents through the station's document management system. The following subsections describe the approach followed by the SWEs to identify potentially adverse anchorage conditions , adverse seism i c interactions , and other adverse seism ic 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 identifi ed item of equ ipm ent to the civil structure on which it is mounted. For example, the welded connect ion s that secure the base of a Motor Control Center (MCG) 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 subsect ion " 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 loo se hardware
  • Corrosion that is more than mild surface oxidation
  • Visib l e 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 clear l y no evidence of degraded, nonconforming , or unanalyzed conditions , then it was indicated on the checklist and a licensing basis eva luati on was not necessary.

However, if it was not possib l e 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 I n addition to the visual inspections of the anchorage as described above, for at least 50% of applicable equipment items, the configurat i on of the in stalled anchorage was verified to be consistent with existing plant documentat i on. 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. 5-2 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Examples of documentation that is considered to verify that the anchorage installation configurations are consistent with the plant documentation include the following:

  • Design drawings
  • Seismic qualification reports of analyses or shake table tests
  • IPEEE or USI A-46 program documentat i on, as applicable Table B-1 in Appendix B documents which deferred SWCs had anchorage configuration verification performed.

Additionally, Table 5-1 below sho w s the final count of the 50% anchorage configuration verifications. Tab l e 5-1: Anchorage Configurat i on Verificati o n NO.ofSWEL Line-Moun t ed Req u ired to SWEL It ems Items Verify? Items Verified (A) (B) (A-B)/2 1 107 30 39 42 2 2 0 1 2 Totals 109 30 40 44 5.2.3 Adverse Seismic Spatial Interactions An adverse seism i c spatia l i nteract i on 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 surround i ng the SWEL i tem to identify any seismic interaction condit i ons 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 wer e considered are as follo w s:

  • Proximity
  • Failure and fall i ng of SSCs
  • Flexibility of attached lines and cables Detailed gu i dance for evaluating each of these types of seismic spatial interactions is described in Appendix D , Seismic Spatial Interaction, of Reference
1. The Seismic Walkdo w n Engineers exercised their judgment to ident i fy seismic interaction hazards. Section 5.2.5 provides a summary of issues identified during the seismic Walkdo w ns. 5-3 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated 5.2.4 Other Adverse Seismic Conditions In addition to adverse anchorage conditions and adver s e seismic interactions, described above , other potentially adverse seismi c conditions that could challenge the seismi c adequacy of a SWEL item could have been present. E x amples 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 e x ternal components to equipment
  • Large , h e avy 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 is e x pected that all electrical cabinets on the SWEL that can be reasonably opened without undue safety or operational hazard will be opened during the walkdown, whether or not it is necessary to look inside to check 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. 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 e x posing energized conductors , these visual inspections included an assessrnent of the MCCs' anchorage. For lower voltage cabinets (e.g., 120 V AC distribution panels), the panel fa c eplate was removed to allow visual inspection of the anchorage and internals while the component was energized. If wires or other internal cornponents blocked the view of any anchors , they were not moved to permit inspections. The ope r ational 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 ele c trical components, if the individuals do not cross the specified approa c h boundary 5-4 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated distance for the particular component.

The approach boundary for low voltage cabinets allowed visual in spection of the cabinet interiors without impacting personnel safety. Instead of re-performing the e x ternal 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 in spections performed during RFO 1 R29. These and all other SWCs for equipment deferred until RFO 1 R29 can be found in Appendix B of this 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 Wa lkdowns. The table includes an update on the status of the corrective actions for the concerns previously identified in the Reference 13 report. Seven (7) additional concerns were identified in completion of the deferred Seismic Walkdowns:

BUS 15: Small screw missing on insulator cap in back of breaker 15-1. No impact from light plastic cover. MCC 1AB2: Two metal clips were found in base of MCC (Cell C6 , cell BS and cell AS). The foreign material in MCC 1AB2 base is a housekeeping issue and does not impact the equipment.

MCC 1 K2: A loose screw in the bottom section belo w cubicle cell C4 was found , as was some duct tape. MCC 1 K2: One side of the MCC is missing plastic inserts. MCC 1 L2: One of the two anchors under the cell A4 is relocated to the edge of the cell from the middle. The rear anchor is a different kind than the typical anchors for the MCC. MCC 1 L 2: Foreign material was identified under the cell ZS. Black insulation about 2" x 1" x 6" long is under the cell ZS. It is a housekeeping concern , and not a seismic issue. Material has since been removed. PNL 1S3: Foreign Material (fuses , wire, and metal debris) at base of panel is not a seismic concern. F M removed by electricians. Nineteen (19) concerns were identified during the Seismic Walk-Bys and entered into the site's CAP. In addition, two (2) observations (associated with B15 LOGIC-2 and B1) identified during the seismic wa lkd owns are not in the site's CAP but are in the work management process for resolution , and are conservatively included in this report for 5-5 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated tracking purposes.

All of the identified concerns were assessed and it was concluded that the anomaly or issue would not prevent th e 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-Bvs 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. Six Area Walk-Bys were completed after November 26,2012. Therefore , a total of 35 Area Walk-Bys were performed for PINGP Unit 1. The Area Walk-By Checklists (AWC) completed before November 26, 2012 were submitted in Appendi x C of Reference

13. The si x area walk-bys completed after November 26 , 2012 are provided in Appendi x C of this document.

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 A ppendix 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. 5-6 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated 5.3.1 Seismically-Induced Flooding/Spray Interactions Seismically-induced flooding/spray interactions are the effect of possible ruptures of vessels or piping systems that could spray, flood or cascade water into the area where SWEL items are located. This type of seismic interaction was considered during the IPEEE program. Those prior evaluations were considered , as applicable , as information for the Area Walk-Bys. 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 irnpact. 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
  • 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 1 R29. 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. E x amples where seismically

-induced fire interactions could occur include the following:

  • Hazardouslflammable 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 5-7 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated 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 e x ercised 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 1 R29. 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. (Note that Area Walk-By designations for CAPs generated during the walkdowns performed prior to November 26 , 2012 are labeled with the designators shown in Table C-1 of the original submittal report.) In total, thirty-six (36) concerns were identified during the Area Walk-Bys and entered into the site's CAP , five (5) of which were identified during the RFO 1 R29 walkdowns.

These new concerns were assessed for operability and it was concluded that the issues would not prevent the associated equipment from performing their function(s).

In addition, eleven (11) observations 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. 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. 5-8 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submitta l Report, Updated No. E q uipment Descript i on of Issue CAP# Status 10 Multiple open "S" hooks for lighting fi x tures w ere identified during the Seismic WR84434, WR 1 Multiple Walkdo w ns. An act i on request w as in i tiated 1352001 83556, and WO to track all of these occurrences and perform 465427 are active. an e x tent of condition. Bottom latch has some apparent deterioration Closed to WR 83855. degradation due to engine vibration. This W0433865 2 55000 condition does not affect seismic capacity; 1353290 completed as part of ho w ever , recommend repair for maintenance EC 21042. purpose. 3 035-012 1352373 Closed to WR 83651. WO 465606 complete.

4 035-012 1352717 Closed to WR WRis The day tank foundation has eight (7/8" Closed to WRs 83768 5 053-321 d i ameter) anchors. One of these anchors 1352845 and 83775. WRs are appears to not be fully seated. complete. There is a coil of cable that looks like it is Closed to WR 83841. 6 111M/X FMR co il ed up using electrical tape. This is not a 1353147 WR is complete. seismic issue for 111 M X FMR. Foreign mater i al (black insulation 1" x 2" x 8") 7 145-1 2 2 found behind the 12 CC pump at column base 135 2 321 Complete. 1-CCH-375 WRs 83878 83879 are associated w ith this observation.

SWEs noted that CV-31652 FIR and CV-In addition , WRs 31653 FIR are mounted to a single vertical 83880 and 83881 are Unistrut with just one machine scre w. The associated w ith sim i l ar machine scre w s are not fully threaded into concems for U2 8 CV-31652 t heir associated nuts. Instead , they are 1353368 componen t s CV-appro x imately half-threaded into their 31654 FIR and CV-associated nuts. SWEs judge current 31655 FIR. WOs configuration as acceptable for seismic 465969 and 465975 loading , but full thread engagement is (Unit 1), and WOs needed. 465982 and 465987 (Unit 2) are associated w ith this The conduit feeding po w er to C V-31652 has one conduit clamp that is missing a nut. 9 C V-3 165 2 SWEs judge e X ist i ng conduit configuration is 1353581 WR 83924 is still seism i cally adequate and acceptable. complete. Ho w e v er, i t is recommended that the nut be put back on. 5-9 No, Equipment 10 10 E-1 11 MCC H2-XFRSW 12 B15 LOGIC-2 13 EM-B1 14 BUS 15 15 MCC 1AB2 16 MCC 1K2 17 MCC 1K2 18 MCC 1L2 19 MCC 1L2 20 PNL 153 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table 5-2: Prairie Island Unit 1 SWC CAP Status Description of Issue CAP# Status The partition wall for K-1 (ne x t to E-1 ) is missing all six floor bolts. The bolts Closed to WR 84916 connecting the partition wall to the vertical 1357500 and WO 467570. w alls are in place. Is the partition wall seismically qualified i n this configuration?

There is foreign material behind the transfer s w itch H2 , near the wall (an 0 ring that is red 1352321 Complete. in color). It is a housekeeping issue and not a seismic concern. Foreign material was found inside the cabinet WR 83773 is at the bottom (one scre w and a piece of w ire N/A complete. insulation). On the inside of EM-B 1 there is a single WR 83653 and WO screw and washer missing from the left N/A 465590 are vertical support. The rema i ning two scre w s associated with this and washers are present. observation. Small scre w missing on insulator cap in back WR 107989 and WO 511052 are of breaker 15-1. No impact from light plastic 1452052 associated w ith this cover. observation. Two metal clips were found in base of MCC (Cell C6, cell B5 and cell A5). The foreign WR 83705 is material in MCC 1 AB2 base is a 1352515 complete. housekeeping issue and does not impact the equipment.

A loose scre w in the bottom section belo w WR 83647 and WR cubicle cell C4 w as found , as w as some duct 1352344 83648 are complete. tape. The cover plate on the end of the MCC 1 K2 1352415 WR 83670 and WO cabinet is missing a dust plug. 465596 are complete. One of the two anchors under the cell A4 is WR 83781 and WO relocated to the edge of the cell from the 135292 7 466347 are middle. The rear anchor is a different kind associated w ith this than the typical anchors for the MCC. observation. Foreign material w as identified under the cell Z5. Black insulation about 2" x 1" x 6" long is 1352321 , WR 83644 is under the cell Z5. It is a housekeeping 1352344 associated with this concem, and not a seismic issue. Material has observation. since been removed. Foreign Material (fuses, w ire, and metal debris) at base of panel is not a seismic 1451358 Complete.

concern. FM removed by electricians. 5-10 No. 1 2 3 4 5 6 7 8 9 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table 5-3: Prairie Island Unit 1 Area Walk-by CAP Status Area Wal k-by Desc r iption of Issue CAP# Status Des i gnat i on Multiple open " S" books for li ghting fi x tures WRs 84434, 83556, w ere ident i fied during the Seismic Mult i ple Wa l k do w ns. An action request was in i tiated 1352001 83533 , and WO 465427 are associated to track all of these occurrences and w ith this observation. perform an e x tent of condition. The drip pan beneath the 12 conta i nment WR 83885 and WO 1 spray pump is missing a bolt on the south 1353388 465983 are associated side. w i th this observation. T w o drums are present under the component cooling heat exchanger to WR 83853 is 3 collect leak off. The drums are poorly tied 1353280 complete. off by rope to a small copper drain line for the 11 component cooling pump un i t cooler. One of the two floor brackets for the unistrut that supports the component cooling motor WR 83865 and WO 3 po w er cables appears to be bent and t he 1353327 465979 are complete. anchor is loose. There is a tygon tube w edged under the c0rt;ler. A top cover plate w ing nut is missing from the 2RE-39 radiation monitor. There is also a loose scre w on the s i de door cover. The WR 83571 and WO 5 monitor is resting on the floor area near the 1352076 471191 are associated wall , and is located between the 22 w ith th i s observat i on. component cooling pump and the stairs to the upper level. T h e light fi x ture above the " VFD" cabinets 6 for 11 and 13 charging pumps is close 1352209 Open. (roughly 1" gap) to the conduits running into the top of the VFDs. Duct tape needs to be removed from the 6 special vent zone line near hanger l-CCH-1352391 Complete. 185. T h ere are two abandoned hanger rods WR 83712 and WO 6 above the component cooling line with 1352549 465652 are associated hanger rod l-RHRH-385 near MCC 2K with this observation. BUS2. There w ere scaffold carts within 2" of touching the MCC 1 L , BUS 2. The cart w heels are chocked but in the w rong 7 orienta t ion. The cart configu r at i on allo w ed 1355467 Complete.

the ca rt to slide into the MCC. The condition w as fi x ed upon d i scovery. Site personnel chocked the w heels in the acceptable orientation. 5-11 No. 10 11 12 13 14 15 16 17 18 19 20 21 Prairie Island Nuclear Generating Plant -Un it 1 Seismic Walkdown Submittal Report, Updated Tab l e 5-3: Prairie Island Unit 1 Area Walk-by CAP Status Area W a l k-by Descriptio n of Issue CAPt Status Des i gnatio n Terminal Box A1749 (terminal box for high flux) is missing an anchor bolt to wall at the WR 83891 and WO 8 lower right corner. There are three other N/A 465984 are associated bolts; therefore , the SWEs judged that the w ith this observation. terminal bolt is seismically anchored to the wall and is acceptable. Missing anchor from baseplate of support 1-WR 83874 and 10 1353371 465974 are associated RMSH-15. with this observation. One light fixture is abandoned in overheard WRs 83892 and 93952 10 near pipe support 1-CCH-311 in 121 SFP 1353409 are associated w ith HX Room and should be removed. this observation. Behind the cabinet RMU2N, one wing nut WR83724 is 13 holding the emergency battery EL-28 is N/A complete .. missing. WR 83579 completed Unit 1 and Unit 2 " E" panels have side all panels except for 15 panels that have slid out of position. This i s 1352102 CS-46880 , CS-46550 , a housekeeping issue and not a seismic and CS-46798 , which concern. will be addressed by W0465436.

There are lighting diffusers tied off to the 15 support grid. Unit 1 and Unit 2 "CO panels 1352209 Open. have a fluorescent light fixture on chains too close (w ithin 1"-2") to the panel. The filing cabinets adjacent to the ma i n 15 control board in both Unit 1 and Unit 2 are 1357683 Complete.

close to the main control board. The cart adjacent to the Protection Systems lit and the cart adjacent to cabinets RPI-1 , -15 2, and -3 in Unit 1 are near to the 1357686 Complete.

equipment.

The chain is not used to restrain the carts. Fire extinguisher bracket 224 has a rotated WR 83584 is 15 bracket (into the insulation) and should be N/A associated wi t h this repaired.

observation. 16 A wood 10"x20" insert on the floor ne xt to 1353367 WR 83876 and WO the grating is a combustible.

465981 are complete. The cable trays adjacent to the south w all WR 83893 and WO 16 house cables w hich are resting on top of, 1353415 465985 are associated and out of, a tray that is unrestrained with this observation. laterally. There are two loose 114" co ncrete anchors WR 83868 and WO 17 N/A 466351 are associated on the bracket supporting PI-17652.

w ith this observation. 5-12 No. 22 23 24 25 26 27 28 29 30 31 32 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Table 5-3: Prairie Island Unit 1 Area W alk-by CAP Status Area Walk-by Descript i on of Issue CAPt Status Designat i on The 121 filtered w ater strainer adjacent to WR83771 , WR 83772, and WO 19 the diesel oil day tank skid as corroded 1352851 471207 are associated anchors (w et environment). with this observation. The chain fall for 2AF-13-1 can potentially WR 83796 and WO 21 1352961 465937 are associated strike MCC 1 A BUS 1. with this observation.

There is a missing fastener on the guard for WR 83793 and WO 21 1352975 466348 are associated 121 instrument air compressor.

w ith this observation.

As a precaution , the SWEs recommend Initiated WR 83645 and WR 83646. WO 22 closing the door pulley O S" hook above 1352343 465563 and WO doors 226 and228. 465564 are complete. Electrical cable 2C-2885 is tie-wr apped to 25 the conduit above BUS 111 480V XFMR 1353147 WR 83641 is Temp. Monitor near door 54, next to an complete. electrical cable tray. A light fixture may come in contact w ith the WR 83854 is 25 fle x ible conduit into the 11A transformer.

It 1353277 associated w ith this is located on top of the 11A transformer w ith observation. only 2" of clearance. 25 The back cover bolts are loose for 111 M N/A WR 83828 init iated. voltage regulator cabinet. WO 466349 complete.

A conduit bo x is attached to Unistrut and 25 both scre w s are loose. They are located N/A WR 83834 is appro x imately 10' from the floor and above complete. the voltage regulator in BUS 111. Vertical rigid conduit to box CS19148 (BUS 111 safeguards SWGR unit cooler) and 25 Panel 132-10 has a conduit clamp not N/A WR 83829 is attached to the condu i t. Located on column complete. E9, it has a misplaced loose attachment at about 10' from floor underneath duct. The conduit bracket attached to the unist r u t 25 for the conduit running to 480V Bus 111 and N/A WR83833 is 112 control panel seems to be loose w ith a complete. gap between the bracket and the unistrut.

25 Condu i t bo x fasteners above 111 M voltage N/A WR 83834 is regulator to t he Unist r ut are loose. complete.

5-13 No. 33 34 35 36 37 38 39 40 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table 5-3: Prai r ie Isla n d Unit 1 Area Walk-by CAP Status Area Walk-by Description of Issue CAP# Status Des i gnation The conduit support on top of the RMU 213 25 cabinet on the west w all has a bolt that is N/A WR 83836 is not fully engaged. The support is located complete.

about 10' from floor level. The emergency light EL 15 located on the safety related block wall number 26 and 26 above the test station for the breaker 1352966 WR 83790 is cabinets has a missing wing nut on the side complete.

for the threaded rod holding EL 15 to the w all bracket. Above breaker 15-6 , the conduit support Closed to WR 83835 is 26 attachment seems to be loose. It is 1353223 complete. connecting the conduit to the unistrut.

28 A single light fi x ture has duct tape and it 1352391 Complete. needs to be removed for housekeeping. The cover plate on the end of the MCC Initiated WR 83671. 28 1352415 W0465605 is 1 GA2 cabinet is missing a dust plug. complete. The unistrut support for panel 1 LPB-4 and 1 RPB3 seems to have no anchor bo l ts on one of the legs. There are anchor bo l ts for the other leg. The leg might have poor-qua lity fillet w elds. 1 LPB-4 is mounted on a unistrut frame that also supports 1 RPB3 Initiated WR 83676. 28 and the three transformers above. The 1352426 WO 465598 complete. unistrut frame is clip-angled to a structural column in three places and is welded to an I-beam at both ends. If there is no fillet w eld on the left leg , the frame is still seismically adequate and will not pry from the w all and impact the MCC 1 GA BUS 1. There is scaffolding tied to the spent fuel 28 pool heat e x changer 122. One of the 1352559 Complete.

scaffold couplers is within 1" of touching CC-43-7. There is lead radiation protection sh i elding WR 83641 is also 29 chained to the w all near the spent fuel pool N/A associated with this skimming pumps. If the shielding falls , it issue. could potentially damage the tubing. 5-14 No. 4 1 42 4 3 44 45 46 47 Prairie Island Nuclear Generating Plant -Unit 1 Se i smic Walkdo w n Submittal Report , Updated Table 5-3: Prairie Island Unit 1 Area Wa l k-by CAP Status Area Wal k-by Description of Issue CAP# Status Designation A 3" copper line is runn i ng along the ceiling above 121 and 122 pumps. It has beam Initiated WR 8 3747. 29 clamps in the same direction and a broken 13527 3 3 WO 465742 complete.

hanger rod. Th i s configuration may be vulnerable in a seismic event. There is s t ored Operat i ons test equipment above the electrical cab i net 1 RPB6 ne x t to WR 83723 and WO 29 t h e 121 spent fuel pool pump. Also , there 1 3 52586 465662 are as s ociated are electrical w ires loosely tied around the w ith this observation.

piping ne x t to the 184 entry door. Rack wi th FIS 18365 missing 1 of 4 w all WR 107939 and WO lR29-1 anchors. Component i s ligh tw eight; 3 of 4 1451548 5 1 1079 are associated bolts are acceptable for seism i c loads. wi th this observa t ion. Bent-plate racks w ith 1 L T -427 and 1 L T -487 are mounted to the Reactor Support Structure w alls via 4 anchors. The 2 WR 108837 and WO lR29-2 anchors on the bottom of the racks are not 1455254 512420 are associated w ithin the bolt holes but instead are located w ith this observation. belo w the plate; the edge of the plate bears against t he anchors. Tube clamp is not engaged to the " Loop A WR 108133 and WO 1R29-3 Hot Leg 11 RCP Vault." Tube is fle x ible and 1 4 52744 511527 are associated has supports near the m i ssing ones. w ith this observat i on. Judged to be acceptable. 4" diameter stainless steel pipe has U-bol t WR 108839 is 1R29-4 w ith loose nuts. Pipe is a drain from 13 FCU 1455258 complete. Work is COND COIL tank. complete. Rack contain i ng 1 FT -475 and 1 LT -471 is WR 107748 and WO lR 2 9-6 mi s sing 1 of 6 w all anchors (bottom left 1451550 511455 are associated anchor). w ith this observation. 5-15 6 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Licensing Basis Evaluations Section 5 , Seismic Lic e nsing 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. A ll 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.

6-1 7 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Wa lkdown Submittal Report , Updated IPEEE Vulnerabilities Resolution Report In the NRC 10 CFR 50.54(1) letter (Reference 6), the NRC requested that li censees provide a list of plant-specific vulnerabilities (including any seismic anomalies , outliers, or other findings) id entif ied by the Individual Plant Examination of External Events (IPEEE) as we ll as a description of the actions taken to eliminate or reduce them (inc luding their comp letion 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 E xam in ation of E x ternal 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 shou l d describe the actions that were taken to e liminate 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 Addit ional Information (RAI) to NSPM as part of their review of PINGP plant licens e renewal application (Reference 5). Th e NRC's RAI "SAMA 3.c" requested the following information

" As stated in the IPEEE seismic analysis , se v era l potential seismic outliers were dispositioned through an analysis process whic h determined that the impacted function was not required or cou ld 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 co rre ct ive actions have been completed , and that their use is supported by procedures and training, as appropr iate." (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 li sted 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 lett er from the NRC to Northern States Power dated August 5 , 1998 , Re s olution of Unre so lved 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 equ ipment outliers, resolution descriptions , and resolution timeline , if not already comp l eted , in Attachment 2 of an RAI response lette r 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 1 outage in December 1998 and PINGP Unit 1 outage in May 1999. Of those four remaining equipment outliers , three (3) were related to components li sted in sectio n A.2.4.1.1 of the PINGP IPEEE. The equipment included control valves C V-39409, C V-39 401 , and Motor Contro l Center MCC-2LA2. The actions taken to resolve the three outliers are describ e d 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 -Un it 1 Seismic Walkdo wn Submittal Report, Updated resolved.

Aside from this completed work, no addit i onal procedure changes or training is requi r ed to close the identified outliers.

Table 7-1: Prairie Island IPEEE Seismic Vulnerabilities Equipment Potential Failure Mode Resolution Date Description Completed Control va l ve CV-39409 was The airline to valve CV-39409 was Identified as an out li er because relocated such that the airline Is 1 R20 refueling CV-39409 contact w ith surrounding conduits greater than two (2) inches from other outage in May could break the solenoid tap electrical conduits In the a r ea. of 1999 connection. The ai r line and associated solenoid valve for CV-39401 w ere rerouted so Control valve CV-39401 w as t ha t the airline and solenoid valve are Identified as an outlier because a minimum of fINo Inches a w ay f r om 1 R20 refueling C V-39401 contact with surrounding conduits existing conduits.

Also , the eleelrlcal outage In May could break the solenoid tap junction box associated With the of 1999 solenoid valve for CV-39401 w as connection. relocated such that the box Is greater than two inches from othe r electrical conduits in the area. Motor Control Center MCC-2LA2 w as Identified as an outlier because Ne w angle support braces we re 2R19 refueling MCC-2LA2 It was obse rved that the MCC installed at the base of MCC-2LA2 to outage in rocked about its weak axis w hen Increase the structural stabil i ty of the November of bumped, mak i ng the w elding at the MCC. 1998 base suspect. 7-2 8 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Peer Review A peer review team consisting of 4 individuals was assembled and peer reviews were performed in accordance with Section 6, Peer Reviews , 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 0 of this report. 8-1 9 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated References Reference drawings related to SWEL items are provided in the Seismi c Walkdown Checklists and if applicable , in the Area-Walkdown Che c kl i sts. 1. EPRI Te c hnical Report 1025 2 86 , Se i s mic Walkdo w n Guidan c e for Re s olution of Fukushima Near-Term Task Force Re c ommendation 2.3: Seismi c, dated June 2012. 2. Prairie Island Nuclear Generating Plant Updated Final 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 (not used). 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. NR C Letter to NSPM , "Request for Additional Information Regarding the Analysis of Severe Ac c ident Mitigation Alternatives for Prairie Island Nuclear Generating Plant , Units 1 and 2 ," dated October 23 , 2008 , A DAMs Accession No. ML082950604. 6. NRC (E Leeds and M Johnson) Letter to All Power Reactor Licensees et aI., " R e quest for Information Pur s uant to Title 1 0 of the Cod e of F e deral Regulations SO.S4(f) Regarding Recommendation 2.1 , 2.3 , and 9.3 , of the Near-Term Ta s k F o rc e Review of In s ights from the Fuku s hima Dai-ichi Accident ," dated March 12,2012 , ADAMS Accession No. ML 12056 A 046. 7. John A. Blame & Associates , Engineers , " Prairie Island Nuclear Generating Plant Earthquake Analysis: Reactor-A uxiliary-Turbine Building Response A c celeration Spe c tra" , JAB-PS-04, February 16 , 1971 (not used). 8. NRC Lette r, " Endorsement of Electric Power Research Institute (EPRI) Draft Report 1025286, 'Seismic Wa l kdown Guidance ,'" dated May 31 , 2012, A DAMS A c c e s sion No. ML 12145A529. 9. NSPM Letter to NRC. " PINGP Unit 1 -Proposed Resolution of the R e maining Seismic Walkdowns A ssociated with NRC Request for Information Pursuant to 10 CFR 50.54 (f) Regarding the Seismic Aspects of Re c ommendation 2.3 of the Near-Term Task For c e Rev i ew of Insights from the Fuku s hima Da i-ichi Accident ," dated Se p tember 12 , 2013. ADAMS Accession No. ML 13259A028. 9-1
10. 11. 12. 13. 14. 15. 16. 17. 18. 19. 20. 21. 22. 23. 24. 25. 26. 27. 28. 29. 30. Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated NSPM Letter to NR C , "Prairie Island Nuclear Generating Plant's 120-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(1) Regarding the Seismic Aspects of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acciden t ," dated July 9,2012. 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. ML 13333B457.

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. ML 13136A003. NSPM Letter to NRC, "PINGP Unit 1 -Final Response to NRC Request for Information Pursuant to 10 CFR 50.54(1) Regarding the Seismic Aspec ts of Recommendations 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ," dated November 26 , 2012 , ADAMS Accession No. ML 12334A495. ACI 318-71 , 77, 83 , Building Code Requirement s for Reinforced Concrete ACI 301 , Specifications for Structural Concrete for Buildings ACI 347 , Recommended Practice for ANSI A 145.1 Concrete Formwork ACI 305 , Recommended Practice for Hot ANSI A 170.1 Weather Concreting ACI 211.1 , Recommended Practice for Selecting Proportions for Normal Weight Concrete ACI 304, Recommended Practi ce for Measuring , Mixing, Transporting, and placing concrete ACI 315 , Manual of Standard Practice for Detailing Reinforced Concrete Structures ACI 306, Recommended Pr actice for Cold Weather Concreting ACI 309, Recommended Practice for Consolidation of Concrete ACI 308 , Recommended Practice for Curing Concrete ACI 214 , Recommended Practice for ANSI A 146.1 Evaluation of Compression Test Results of Field ACI 311, Recommended Pr actice for Concrete Inspection AC I 304 , Preplaced Aggregate Concrete for Structural and Mass Concrete Report by AC I Committee 304, Placing Concrete by Pumping Method AISC-69,78, Specification for the Design , Fabri cation, and Erecti o n of Stru c tural Steel for Building AWS D 1.1 , Structural Welding Code ASM E Boiler & Pressure Vesse l Code ,Section III -ASME-1971 , S73 Division 1, Subsection NE 9-2

31. 32. 33. 34. 35. 36. 37. 38. 39. 40. 41. 42 43 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated ASM E-1974 , S75 Division 1 , Subsection NF ASME-1973 Division 2, Proposed Standard Code for Concrete Reactor Vessels and Containments I ssued for Trial Use and Comments ASME-1980 Division 2 , CC 6000 ASM E-1992 1992 Addenda, Division 1 ,Section XI , Subsection IWL , IWE American Public Health Assoc. (APHA) Test Methods Sulphides in Water , Standard Methods for the Examination of Water and Waste Water ASTM Annua l Books of ASTM Standards CRSI , MSP-1 , Manual of Standard Practice ANSI N45.2.5, Proposed Supplementary Q.A. Requirements for Installation , Inspection and Testing of Structural Concrete and Structural Stee l During Construction Phase of Nuclear Power Plants 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 ACI-349-76 , 85 , Code Requirements for Nuclear Safety Related Concrete Structures AISI , Specification for design of cold-formed steel stn/ctura l members Prairie Island Nuclear Generating Plant Maintenance Procedure D80, Rev. 27, "Scaffo lding, Ladders and Cable Tray Platforms." Prairie Island Nuclear Generating Plant Seismic Housekeeping Procedure H41, Rev. 13 , "Control of Temporary Structures and Equipment." NSPM (M.D. Wadley) Letter to NRC , "Responses to NRC Requests for Additional Information Dated October 23 , 2008 Regarding App lication for Renewed Operating Licenses ," dated November 21 , 2008 , ADAMS Accession No. ML083370505.

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. NRC Memorandum, "Su mmary of the August 1 , 2013 , Public Conference Call on the Delayed Inspection Items Associated with Japan Lessons Learned Near-Term Ta sk Forc e Recommendation

2.3 Seismic

Walkdowns," dated A ugu st 14 , 2013 , ADAMS Accession No. ML 13218B361. NRC Letter, "Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3 , Seismic Walkdowns," dated November 1 , 2013, ADAMS Accession No. ML 133048418.

9-3 A Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Equipment Lists Appendix A contains the equipment lists that were developed as part of the equipment selection for the SWEL. The following contents are found in Appendix A: Table A-1 , Prairie Island Unit 1 -Base List 1 A-2 Table A-2 , Prairie Island Unit 1 -Base List 2 A-35 Table A-3 , Prairie Island Unit 1 -Final SWEL 1 A-37 Table A-4 , Prairie Island Unit 1 -Final SWEL 2 A-43 A-1 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated 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 "Sase List 1." Table A-1: Prairie Is l and Unit 1 -Base List 1 E q uipment Tag Descrip t ion 16143 D1 DSL GEN ENG CRANKCASE PS 16144 D2 DSL GEN ENG CRANKCASE PS 16206 D1 DSL GEN CLNT FROM ENG JCKT HI TRIP TS 16207 D2 DSL GEN CLNT FROM ENG JCKT HI TRIP TS 17700 11 AFP LO DISCH PRESS TRIP PS 17701 22 AFP LO DISCH PRESS TRIP PS 17704 11 AFP LO SUCT PRESS TRIP PS 17776 12 AFWP LO SUCT PRESS TRiP PS 17777 12 AFP LO DISCH PRESS TRIP PS 19603 12 & 14 FCU CLG WTR RTN ORIFICE B-P VLV ES 21005 LOOP A CLG WTR HDR P XMTR 21006 LOOP B CLG WTR HDR P X MTR 21033 12 MD AUX FW PMP DSCH P XMTR 21034 11 TD AU X FW PMP DSCH P X MTR 21230 11 CNTMT FCU CLG WTR OUTL P X MTR 21231 12 CNTMT FCU CLG WTR OUTL P XMTR A-2 Prairie Island Nuclear Generating Plant -Un it 1 Seismic Walkdo w n Submittal Report , Updated Table A-1: Prairie Island Unit 1 -Base List 1 Equ i pment Tag Description 21232 13 CNTMT FCU CLG WTR OUlL P X MTR 21233 14 CNTMT FCU CLG WTR OUTL P X MTR 23122 AUX FW TO 11 STM GEN F X MTR 2 3 127 AUX FW TO 12 STM GEN F X MTR 23128 AUX FW TO 21 STM GEN F X MTR 23129 AU X FW TO 22 STM GEN F X MTR 27 1 45 AU X FW TO 11 STM GEN F ORIF 27147 AU X FW TO 12 STM GEN F ORIF 31211 CHG LN TO 21 REGEN HT E X GR CV 31420 CHG LINE TO 22 RCS LOOP COLD LEG ISOL CV 32138 13 FC CLG WTR RTRN ISOL MV A 32139 13 FC CLG WTR RTRN ISOL MV B 3 2378 13 FC CLG WTR INLT ISOL MV 33186 01 DSL GEN WTR SPLY SV 33187 02 DSL GEN WTR SPLY SV 33199 11 LOOP A MN STM HDR AIR SPLY SV A 3320 1 11 LOOP A MN STM HDR AIR E X HT SV A 33254 12 LOOP B MN STM HDR AIR SPLY SV B 33 2 55 12 LOOP B MN STM HDR AIR E X HT SV A 33285 11 TO AU X FW PMP RCRC/LUB E OIL CLG SV A-3 Prairie Island Nuclea r Generating Plant -Un it 1 Seismic Walkdown Submittal Report, Updated Table A-1: Prairie Is l and Un i t 1 -Base List 1 Equi p ment Tag Descript i on 33286 12 MD AUX FW PMP RCRC/LUBE OIL CLG SV 33371 11 FAN COIL U N IT DSCH TO CONTM DOME DMPR SV 33372 11 FAN COIL U NIT NORM DSCH TO GAP & STRUC DMPR S 33373 12 FAN COIL UNIT DSCH TO CONTM DOME DMPR SV 33374 12 FAN COIL UN I T NORM DSCH TO GAP & STRUC DMPR S 33375 13 FAN COIL UN IT DSCH TO CONTM DOME DMPR SV 33376 13 FAN COIL UNIT NORM DSCH TO GAP & STRUC DMPR S 33377 14 FAN COIL UNIT DSCH TO CONTM DOME DMPR SV 33378 14 FAN COIL UNIT DSCH TO GAP & STRUC DMPR SV 33644 Dl DSL GEN AIR STRT SV A 33646 02 DSL GEN A I R STRT SV A 33693 11 SCVNG & COMBTN AIR DMPR SV A 33694 11 CLASS I ROOF EXHT FAN DMPR SV 33702 121 CONT RM AIR HNDLR OA SPLY DMPR SV 33704 122 CONT RM AIR HNDLR DSCH DMPR SV A 33709 121 CONT RM PAC FLTR SPLY DMPR SV 33711 122 CONT RM PAC FLTR SPLY SV 33821 122 CONT RM AIR HNDLR DSCH DMPR SV B 33828 11 SCVNG & COMBUSTION AIR DMPR SV B 33987 121 DSL GEN RM AIR DMPR SV A-4 Prairie Island Nuclear Generating Plant -Un it 1 Seism i c Walkdown Submittal Report, Updated Table A-1: Prairie Island Unit 1 -Base List 1 Equ i pment Tag Description 37201 11 & 13 FCU ClG WTR RTN OR I F B-P SV 37203 12 & 14 FCU ClG WTR RTN ORIF B-P SV 55000 01 DSl GEN GAUGE PANel (DGP) 55300 01 DSl GEN ENG/GEN PANEL (EGP) 55410 01 REMOTE CONTROLS ISOLAT I ON PANEL 55500 02 DSl GEN GAUGE PANEL (DGP) 55800 02 DSl GEN ENG/GEN PANEL (EGP) 57303 121 CONT RM WTR CHllR lCl CONT PNl 57304 122 CONT RM WTR CHllR lCl CONT PNl 70300 12 DO ClWP lCl PNl 70385 121 SFGDS TRAVELING SCRN DIFF CO NT PNl 70386 122 SFGDS TRAVELING SCRN D I FF CONT PNl 032-011 12101 DIESEL GENERATOR EXHAUST FAN 032-012 122 DIESEL GENERATOR ROOM EXHAUST FAN 032-041 12101 DIESEL GENERATOR SUPPLY FAN 032-042 12202 DIESEL GENERATOR SUPPLY FAN 032-141 121 RELAY & COMPUTER ROOMS RETURN FAN 032-231 12101 DIESEL GENERATOR OUTSIDE EXHAUST FAN 032-232 12202 DIESEL GENERATOR OUTSIDE EXHAUST FAN 034-011 12101 DIESEL GENERATOR A-5 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table A-1: Prairie Island Unit 1 -Base List 1 Equipment Tag Description 034-021 02 D IESEL GENERATOR 045-271 121 DSL GEN OIL STOR TK SUBMERSIBLE PUMP 045-273 123 DSL GEN OIL STOR TK SUBMERSIBLE PUMP 045-30 1 121 DSL CLG WTR PMP OIL STOR TK SUBMERSIBLE PMP 045-302 122 DSL CLG WTR PMP OIL STOR TK SUBMERSIBLE PMP 045-591 121 CONTROL ROOM CHILLED WATER PUMP 045-592 122 CONTROL ROOM CHILLED WATER PUMP 046-031 121 D1 DIESEL GENERATOR STARTUP AIR RECEIVER 046-032 12202 D I ESEL GENERATOR STARTUP AIR RECEIVER 053-201 121 Dl D I ESEL GENERATOR FUEL OIL DAY TANK 053-202 122 D2 DIESEL GENERATOR FUEL OIL DAY TANK 053-221 121 DIESEL GENERATOR OIL STORAGE TANK 053-223 123 DIESEL GENERATOR OIL STORAGE TANK 053-251 121 COOLING WATER PUMP DIESEL O I L STORAGE TANK 053-252 122 COOLING WATER PUMP DIESEL OIL STORAGE TANK 053-321 12 COOLING WATER PUMP DIESEL OIL DAY TANK 053-381 121 CONTROL ROOM CH I LLED WATER EXPANSION TANK 053-382 122 CONTROL ROOM CHILLED WATER EXPANSION TANK 053-481 121 D1 DIESEL GENERATOR EXPANSION TANK 053-482 122 D2 DIESEL GENERATOR EXPANSION TANK A-6 Prairie Island Nuclear Generat i ng Plant -Unit 1 Seismic Walkdo w n Subm i ttal Report , Updated Table A-1: Prairie Island Unit 1 -Base List 1 Equipmen t Tag Description 067-011 121 SAFEGUARD TRAVELING WATER SCREEN 067-012 122 SAFEGUARD TRAVELING WATER SCREEN 069-161 121 Dl DIESEL GENERATOR AIR INTAKE FILTER 069-162 122 D2 DIESEL GENERATOR AIR INTAKE FILTER 074-031 121A RELAY ROOM FAN-COIL UNIT 074-032 121B RELAY ROOM FAN-COIL UNIT 074-033 122A RELAY ROOM FAN-COIL UNIT 074-034 122B RELAY ROOM FAN-COIL UNIT 075-011 121 CONTROL ROOM WATER CHILLER 075-012 122 CONTROL ROOM WATER CH I LLER 076-021 121 CONTROL ROOM A I R HANDLER 076-022 122 CONTROL ROOM A I R HANDLER 078-011 121 Dl DIESEL GENERATOR EXHAUST MUFFLER 078-012 122 D2 DIESEL GENERATOR EXHAUST MUFflER 078-021 121 D1 DIESEL GENERATOR AIR INTAKE SILENCER 078-022 122 D2 DIESEL GENERATOR AIR INTAKE SILENCER 1 CRDM/X FMR CRDM MAIN CONTROL TRANSFORMER 101!X FMR 101 TRANSFORMER 102/X FMR 102 TRANSFORMER l1BATI 11 STATION BATIERY A-7 Pra i rie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table A-1: Pr airie Is l and Un it 1 -Base List 1 Equ i pment Tag Desc rip tion 11BATICHG 11 BATIERY CHARGER 11 BATI CHG/XFM 11 BATIERY CHARGER TRANSFORMER 11IBA/XFMR INTERRUPTABLE BUS AUX TRANSFORMER lllNV 11 INVERTER 110BT/PT 110 BT POTENTIAL TRANSFORMER 111M/XFMR 111M TRANSFORMER 112M/XFMR 112M TRANSFORMER 113-011 12 CL PUMP DIESEL START-UP AIR COMPRESSOR 117-111 11 AUXILIARY FEEDWATER PUMP LUBE OIL COOLER 117-112 12 AUXILIARY FEEDWATER PUMP LUBE OIL COOLER 117-121 12 CL PUMP GEAR OIL COOLER 11M BAT CHG/XFM 11 MOBILE BATIERY CHARGER TRANSFORMER 11MR 11 MISCELLANEOUS RELAY RACK 11RM RADIATION MONITORING RACK 11RM 12BATI 12 BATIERY 12 BATICHG 12 BATIERY CHARGER 12 BATICHG/XFM 12 BATIERY CHARGER TRANSFORMER 121NV 12 INVERTER 120BT/PT 120BT POTENTIAL TRANSFORMER 121M/XFMR 121M TRANSFORMER A-8 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table A-1: Prairie Island Unit 1 -Base List 1 Equ i pment Tag Descriptio n 121MR 121 MISCELLANEOUS RELAY RACK 121SR 121 SEISMIC RECORDER SYSTEM RACK 122M/XFMR 122M TRANSFORMER 122MR 122 MISCELLANEOUS RELAY RACK 123MR 123 MISCElLANEOUS RELAY RACK 124MR 124 MISCELLANEOUS RELAY RACK 125MR 125 MISCElLANEOUS RELAY RACK 126MR 126 MISCELLANEOUS RELAY RACK 12MR 12 MISCELLANEOUS RELAY RACK 131NV 13 INVERTER 132-141 121 RELAY ROOM RETURN FAN 132-281 11 SCREENHOUSE ROOF EXHAUST FAN 132-291 11 SCREENHOUSE DIESEl COOLING SUPPLY FAN 135-021 11 RCP SEAL WATER RETURN HEAT EXCHANGER 135-101 12 CL PUMP DIESEL JACKET ClG HX 135-111 REGEN HT EX -13MR 13 MISCELLANEOUS RELAY RACK 141NV 14 INVERTER 145-041 11 CHG PUMP 145-042 12CHG PUMP A-9 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Table A-1: Prairie Is l and Unit 1 -Base List 1 Equipment Tag Description 145-201 11 TD AFW PUMP 145-331 12 MD AFW PUMP 145-392 12 DO CLP 145-821 12 Cl PUMP CNSTNT LUBE OIL PUMP 146-011 12 CL PUMP DIESEL START-UP AIR RECEIVERS 14MR 14 MISCELLANEOUS RELAY RACK 151NV 15 INVERTER 15-2/CTl 01 EMERG GEN CURRENT TRANSFORMER 1-52/RTA A -TRAIN REAC TRIP BREAKER 1-52/RTB B -TRAIN REAC TR I P BREAKER 153-011 11 PRESSUR I ZER RELIEF TANK 153-021 11 VOLUME CONTROL TANK 153-081 RFLG WTR STG TK 15-5/CT1 11 CC PUMP CURRENT TRANSFORMER 15-5/CT2 11 CC PUMP CURRENT TRANSFORMER 15-6/CTl 101 STA AUX XFMR CURRENT TRANSFORMER 15-6/CT2 101 STA AUX X FMR CURRENT TRANSFORMER 158-011 11 COOLING WATER STRA I NER 16-1/CTl 12 AFW PUMP CURRENT TRANSFORMER 16-1/CT2 12 AFW PUMP CURRENT TRANSFORMER A-10 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Table A-1: Prairie Island Unit 1 -Base List 1 Equ i pment Tag Description 16-2/CT1 102 STA AUX XFMR CURRENT TRANSFORMER 16-2/CT2 102 STA AUX XFMR AURRENT TRANSFORMER 16-3/CTl 12 CC PUMP CURRENT TRANSFORMER 16-3/CT2 12 CC PUMP CURRENT TRANSFORMER 16-7/CT1 D2 EMERG GEN CURRENT TRANSFORMER 169-031 11 SEAL WTR IN! 169-032 12 SEAL WTR IN! 169-061 11 SEAL WTR IN! 169-062 12 SEAL WTR IN! 171NV 17 INVERTER 174-011 11 CNTM FAN COil UN I T 174-012 12 CONTAINMENT FAN COil UNIT 174-013 13 CNTM FAN COil UNIT 174-014 14 CONTAINMENT FAN COil UNIT 174-031 15 SAFEGUARD SWITCHGEAR FAN-COil UNIT (4160V) 174-032 16 SAFEGUARD SWITCHGEAR FAN-COil UNIT (4160V) 174-051 12 AUXILIARY FEEDWATER PUMP MOTOR FAN COil UNIT 174-131 11 CHARGING PUMP MOTOR FAN-COil UNIT 174-132 12 CHARGING PUMP MOTOR FAN-COil UNIT 174-161 101 SAFEGUARD SWITCHGEAR FAN-COil UNIT A-11 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated Table A-1: Pra i rie Island Unit 1 -Base List 1 Equ i pment Tag Descr i ption 174-162 102 SAFEGUARD SWITCHGEAR FAN-COIL UNIT 174-163 102A SAFEGUARD SWITCHGEAR FAN-COIL UNIT 181NV 18 INVERTER lAMRl MISCELLANEOUS RELAY RACK lAMRl lARPl REACTOR PROTECTION RELAY RACK lARPl lARP2 REACTOR PROTECTION RELAY RACK lARP2 lARP3 REACTOR PROTECTION RELAY RACK lARP3 lARP4 REACTOR PROTECTION RELAY RACK lARP4 lARPS REACTOR PROTECTION RELAY RACK lARPS lASGl SAFEGUARD RELAY RACK lASGl lASG2 SAFEGUARD RELAY RACK lASG2 lBl PROCESS PROTECTION RACK lBl lB2 PROCESS PROTECTION RACK 1B2 lBMRl MISCELLANEOUS RELAY RACK lBMRl lBRPl REACTOR PROTECTION RELAY RACK lBRPl lBRP2 REACTOR PROTECTION RELAY RACK lBRP2 lBRP3 REACTOR PROTECTION RELAY RACK lBRP3 lBRP4 REACTOR PROTECTION RELAY RACK lBRP4 lBRPS REACTOR PROTECTION RELAY RACK lBRPS lBSGl SAFEGUARD RELAY RACK lBSGl A-12 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Table A-1: Prairie Island Unit 1 -Base List 1 Equipment Tag Description lBSG2 SAFEGUARD RELA V RACK lBSG2 lCVCSl PROCESS CONTROL RACK lCVCl lCVCS2 PROCESS CONTROL RACK lCVC2 lOG-3 01 JACKET CLNT HTR RELI EF lFE-115 11 REAC CLNT PMP SL WTR INJ F ORIF lFE-116 12 REAC CLNT PMP SL WTR INJ F OR IF lFE-820 11 AUX FEEDWATER VLV MS-20-4 OUTL FE lFI-115A 11 REAC CLN T PMP SL WTR INJ FI lFl-116A 12 REAC CLNT PMP SL WTR INJ FI lFT-115 11 REAC CLNT PMP SL WTR INJ F XMTR lFT-116 12 REAC CLNT PMP SL WTR INJ F XMTR lFT-176 12 RCP SEAL LEAKOFF HI ACC FLOW XMTR lFT-178 12 RCP SEAL LEAKOFF FLOW XMTR lFT-464 MN STM FR 11 STM GEN CHNNL I RED F XMTR 1FT-465 MN STM FR 11 STM GEN CHNNL II WHITE F XMTR 1FT-474 MN STM FR 12 STM GEN CHNNL III BLU F XMTR lFT-475 MN STM FR 12 STM GEN CHNNL IV VEL F XMTR lFT-476 12 STM GEN LOOP B FW INLT F XMTR lFT-494 11 STM GEN LOOP A HI ACC STM F XMTR lFW PROCESS CONTROL RACK lFW A-13 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Table A-1: Prairie Is land Unit 1 -Base List 1 Equipment Tag Description 1HC-431K 1 REAC CLNT LOOP PRZR PRESS CONT STA 1HC-468 1 MN STM SAF RlF TO ATM lOOP A CO NT STA 1HC-478 MN STM SAF R l F TO ATM lOOP B CONT STA llC-141A VOL CONTROL TANK lEVEL CONTROllER llC-141B VOL CONTROL TANK lEVEL SINGLE ALARM llQ-141 11 VOL CONT TNK lVl PWR SPlY llQ-426 PRESSURIZER lEVEL XMTR PWR SPlY llQ-428 PRESSURIZER lEVEL XMTR PWR SPlY llQ-461 STM GEN lEVEL XMTR PWR SPlY llQ-471 STM GEN lEVEL XMTR PWR SPlY llR-428 1 REAC PRZR lVl RCDR llT-112 11 VOL CONTTNK lVl XMTR llT-141 11 VOL CONT TNK lVl XMTR llT-426 1 REAC ClNT lOOP PRZR (CHNNl I-RED) lVl XMTR llT-428 1 REAC ClNT lOOP PRZR (CHNNl III-BLU) lVl XMTR llT-461 11 STM GEN LOOP A CHNNl I-RED lVl X MTR llT-471 12 STM GEN lOOP B CHNNl IV VEL lVl XMTR llT-487 11 STM GEN lOOP A WR lVlXMTR llT-488 12 STM GEN LOOP B WR lVl XMTR llT-7S1 11 RX VSl HEAD UPPER RNG TRN A DiP X MTR A-14 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Tab l e A-1: Prairie Island Unit 1 -Base Lis t 1 Equipment Tag Descrip t ion 1LT-7S2 11 RX VSL HEAD FULL RNG TRN A DiP XMTR llT-7S3 11 RX VSl HEAD DYNAMIC RNG TRN A DiP XMTR 1LT-761 12 RX VSL HEAD UPPER RNG TRN B DiP XMTR 1LT-762 12 RX VSL HEAD FULL RNG TRN B DiP XMTR llT-763 12 RX VSl HEAD DYNAMIC RNG TRN B DIP XMTR llT-920 11 RWST LVl XMTR 1LT-921 11 RWST LVl XMTR 1NE-S1 EXCORE DETECTION TRN A DETECTOR ASSY 1NE-S2 EXCORE DETECTION TRN B DETECTOR ASSY 1NI-S1A EXCORE DETECT I ON TRN A SHUTDOWN MONITOR 1NI-S2A EXCORE DETECTION TRN B SHUTDOWN MONITOR 1NM-Sl EXCORE DETECT I ON TRN A AMPLIFIER 1NM-S1A EXCORE DETECT I ON TRN A OPTICAL ISOLATOR 1NM-S2 EXCORE DETECTION TRN B AMPLIFIER lNRl NUCLEAR INSTRUMENTAT I ON RACK 1NR1 lNR2 NUCLEAR INSTRUMENTATION RACK 1NR2 1NR3 NUCLEAR INSTRUMENTATION RACK 1 N R3 1NR4 NUCLEAR INSTRUMENTATION RACK lNR4 lNU-S1A E X CORE DETECTION TRN A RACK MTD SIGNAL PROCESSOR 1NU-S1B EXCORE DETECTION TRN A WALL MTD SIGNAL PROCESSOR A-15 Prairie I s land Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Table A-1: Prairie Island Unit 1 -Base List 1 Equ i pment Tag Description 1NU-S 2 A E X CORE DETECTION TRN BRAC K MTD S I GNAL PROCESSOR 1PlP PROCESS CONTROL RACK 1PlP 1PQ-4 2 9 1 REAC ClNT lOOP PRZR (CHNNl l-RED) P PWR S PlY 1PQ-431 1 REAC ClNT LOOP PRZR (CHNNlllI-BLU) P PWR SPlY 1PQ-468 STEAM PRESSURE TRANSMITTER PWR SPlY 1PQ-478 STEAM PRESSURE TRANSMITTER PWR SPl Y 1PR-42 9 1 REAC ClNT LOOP PRZR PRESS RCDR 1PR-468 11 STM GEN LOOP A STM PRESS RCDR (3 PEN) 1PT-139 11 REAC ClNT VOL CONT TNK RlF P X MTR 1PT-173 11 REAC ClNT PMP SHFT Sl DIP X MTR 1PT-17 4 1 2 REAC ClNT PMP NO 1 Sl DIP X MTR 1PT-429 1 REAC ClNT lOOP P R ZR (CHNNll-RED)

P X MTR 1PT-431 1 REAC ClNT lOOP PRZR (CHNNlllI-BlU)

P X M T R 1PT-46 8 11 STM GE N lOOP A (CHNNll-RED) P X MTR 1PT-469 11 STM GEN LOOP A (CHNNlll-WHI)

P XMTR 1PT-478 12 STM GEN lOOP B (CHNNllIl-BLU)

P X MTR 1PT-479 12 STM GEN lOOP B (CHNNlIV-VEl)

P X MTR 1PT-482 11 STM GEN LOOP A (CHNNlllI-BlU) P X MTR 1PT-4 8 3 12 STM GEN LOOP B (CHNNll-RED)

P X MTR 1PT-709 lOOP A ReS PRES S X MTR A-16 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Tab l e A-1: Prai r i e Island Unit 1 -Base L ist 1 Equ i pment Tag Description lPT-710 lOOP B RCS PRESS XMTR lPZRHTRA/CT A 1 PRZR HTR GRP A CURRENT XFMR A lPZRHTRA/CT C 1 PRZR HTR GRP A CURRENT XFMR C lPZRHTRA/PT A 1 PRZR HTR GRP A POTENTIAL XFMR A lPZRHTRA/PT C 1 PRZR HTR GRP A POTENTIAL XFMR C lPZRHTRA/XFMR 1 PRZR HTR GRP A TRANSFORMER lPZRHTRB/CT A 1 PRZR HTR GRP B CURRENT XFMR A lPZRHTRB/CT C 1 PRZR HTR GRP B CURRENT XFMR C lPZRHTRB/PT A 1 PRZR HTR GRP B POTENTIAL XFMR A lPZRHTRB/PT C 1 PRZR HTR GRP B POTENTIAL XFMR C lPZR HT RB/XFMR 1 PRZR HTR GRP B TRANSFORMER lRl PROCESS PROTECTION RACK lRl lR2 PROCESS PROTECTION RACK lR2 lRCSl PROCESS CONTROL RACK lRCSl lRCS2 PROCESS CONTROL RACK lRCS2 lTT-450A R/E RCS TEMPERATURE TH lTT-450B R/E RCS TEMPERATURE TC lTT-451A R/E RCS TEMPERATURE TH lTT-451B R/E RCS TEMPERATURE TC lWl PROCESS PROTECTION RACK lWl A-17 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walk down Submitta l Report, Updated Table A-1: Prair i e Island Unit 1 -Base List 1 Equ i pment Tag Description 1W2 PROCESS PROTECTION RACK 1W2 1Y1 PROCESS PROTECTION RACK 1 Y1 1Y2 PROCESS PROTECTION RACK 1Y2 AC11 BOP ANNUNCIATOR CABINET AC11 AC12 BOP ANNUNCIATOR CABINET AC12 AC13 BOP ANNUNCIATOR CAB INET AC13 AC14 BOP ANNUNCIATOR CABINET AC14 AC15 BOP ANNUNCIATOR CABINET AC15 AC16 BOP ANNUNCIATOR CABINET AC16 B-1 CONTROL PANEL B-1 B110/ AUX CAB BUS 110 480V AUX RLY CAB B120/ AUX CAB BUS 120 480V AUX RLY CAB B15 LOGIC-l BUS 15 LOGIC CAB 1 B15 LOGIC-2 BUS 15 LOGIC CAB 2 B1S/LOAD SEQ CAB BUS 15 SAFEGUARDS LOAD SEQUENCER CABINET B1S/SWGR BUS 15 4.16KV SWITCHGEAR B16 AUX RELAY CAB BUS 16 AUX RELAY CABINET B16 LOGIC-l BUS 16 LOGIC CAB 1 B16 LOGIC-2 BUS 16 LOGIC CAB 2 B16/LOAD SEQ CAB BUS 16 SAFEGUARDS LOAD SEQUENCER CABINET A-18 Prair i e Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table A-1: Prairie Isla n d Unit 1 -Base L ist 1 Equ i pment Tag Descript i on B16/SWGR BUS 16 4.16KV SWITCHGEAR BUS 111 BUS 111 480V SWITCHGEAR BUS 112 BUS 112 480V SWITCHGEAR BUS 121 BUS 121480V SWITCHGEAR BUS 122 BUS 122 480V SWITCHGEAR BUS 13 BUS 13 4.16KV SWITCHGEAR BUS 14 BUS 14 4.16KV SWITCHGEAR BUS 15 4.16KV SFGDS BUS 15 BUS 16 4.16KV SFGDS BUS 16 C-1 CONTROL PANEL C-1 CD-34049 121/122 DSL GEN RM OUTS AIR CD CD-34072 11 FCU DISCH TO CNTMT DOME CO CD-34073 11 FCU NORM DISCH TO GAP & STRUCT CO CD-34074 12 FCU DISCH TO CNTMT DOME CO CD-34075 12 FCU NORM DISCH TO GAP & STRUCT CD CD-34076 13 FCU DISCH TO CNTMT DOME CD CD-34077 13 FCU NORM DISCH TO GAP & STRUCT CO CD-34078 14 FCU DISCH TO CNTMT DOME CO CD-34079 14 FCU NORM DISCH TO GAP & STRUCT CO CO-34136 11 SCVNG & COMBTN AIR CO A-19 Prairie Island Nuclear Generating Plant -Unit 1 Seism i c Walkdo w n Submittal Report. Updated Table A-1: Prairie Island Unit 1 -Base List 1 Equipment Tag Desc r iption CO-34137 11 CLASS I ROOF E X HT FAN oSCH CD CO-3414 2 121 CONT RM AIR H N DLR OA SPLY CD CO-34143 121 CONT RM AIR HNoLR oSCH CD CO-34144 122 CONT RM AIR HNoLR oSCH CD CO-3414S 122 CONT RM A I R HNDLR OA SPLY CD CO-34179 1 2 1 CONT RM PAC FLTR SPLY CD CO-34181 122 CONT RM PAC FLTR SPLY CD CO-3 4 203 121 RLY RM/COMP RM FIRE PREV ISOL SPLY CD CO-34 2 04 121 RLY RM/COMP RM FIRE PREV ISOL RTRN CD CL-2S-1 12 ooCLP JACKET H X RELIEF CL-S7-3 11 CONTM FAN COIL-RELIEF CL-S7-4 12 CONTM FAN COIL-RELIEF CL-S7-S 13 CONTM FAN CO I L-RELIEF CL-S7-6 14 CONTM FAN COIL-RELIEF CV-31OS9 1 1 AFWP MN STM THTL CV CV-31084 11 STM GEN MN STM SAF RLF TO ATM CV CV-31089 12 STM GEN MN STM S AF RLF TO ATM CV CV-31098 11 LOOP A MN STM HoR ISOL CV CV-31099 12 LOOP B MN STM HDR ISOL CV CV-3115 3 11 TO AU X FW PMP RCRC/LUBE OIL CLG CV A-20 Prairie Island Nuclear Generat i ng Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table A-1: P r a iri e Island Unit 1 -Base List 1 Equipment Tag Oesc ri ptlon CV-31154 12 MO AU X FW PMP RCRC/LUBE O I L CLG CV CV-31205 11 LTON OVRSN VCT/HLD-UP TNKS CV CV-31226 1 REAC CLNT LOOP PRZR L TON LN ISOL LCV A CV-31231 1 PRZR PORV B CV CV-31232 1 PRZR PORV A CV CV-31255 1 REAC CLNT LOOP PRZR L TON LN ISOL LCV 2 CV-31334 11/12 RCP SEAL BYPASS RETURN CV CV-31335 11 REAC CLNT PMP SL WTR DUTL ISOL CV CV-31336 12 REAC CLNT PMP SL WTR OUTL ISOL CV CV-31423 12 OOCLP JCKT CLR OUlL CV CV-31505 01 OSL GEN CLG WTR SPLY CV CV-31506 02 OSL GEN CLG WTR SPL Y CV CV-31652 11 CLG WTR STRNR BCKWSH CV CV-31759 122 N RLY RM FAN COIL TRN B CV CV-31760 121 N RLY RM FAN COIL TRN A CV CV-31761 1225 RLY RM FAN COIL TRN B CV CV-31768 122 CONT RM A/C CHL WTR RTRN CV CV-31769 121 CONT RM CHLLR UNIT CDSR CLG WTR OUlL TCV CV-31785 122 CONT RM CHLLR UNIT COSR CLG WTR OUTL TCV CV-31786 121 CONT RM A/C CHL WTR RTRN CV A-21 Prair i e Island Nuclear Generating Plant -Unit 1 Seismic Wa l kdo w n Submittal Report, Updated Table A-1: Prairie Island Unit 1 -Base L i st 1 Equ i pment Tag Desc r iptio n CV-3 1953 D1 D S LGEN AIR STRTCV A CV-31954 D1 DSL GEN AIR STRT CV B CV-31955 D2 DSL GEN AIR STRT CV A CV-31956 D2 DSL GEN AIR STRT CV B CV-3 1 99B 11 TO AFW PMP STM BLOC K CV CV-39201 11 & 13 FCU CLG WTR RTN B-P CV CV-39 2 03 12 & 14 FCU CLG WTR RTN ORIF B-P CV CV-39401 11/13 FCU CLG WTR SUPPLY CV CV-39402 11/13 FCU CHILLED WTR SUPPLY CV CV-39403 12/14 FCU CLG WTR SUPPLY CV CV-39404 12/14 FCU CH I LLED WTR SUPPLY CV CV-39405 11 SHROUD CLG CO I LS TR A CHILLED WTR SUPPLY CV CV-39406 12 SHROUD CLG COILS TR B CHILLED WTR SUPPLY CV CV-39407 11 SHROUD CLG CO I LS TR A CHILLED WTR RETURN CV CV-3940B 1 2 SHROUD CLG COILS TR B CH I LLED WTR RETURN CV CV-39409 12/14 FCU CLG WTR RETURN CV CV-39410 12/14 FCU CHILLED WTR RETURN CV CV-3 9 41 1 11/13 FCU CLG WTR RETURN CV CV-3941 2 11/13 FCU CHILLED WTR RETURN CV D-1 CONTROL PANEL D-1 A-22 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table A-1: Prairie Island Unit 1 -Base List 1 Equipment Tag Description 01 CFRP/XFMR 01 CLEAN FUEL RTRN PMP TRANSFORMER 01/GEN RLY PNL 01 EMERG GEN RELAY PNL 01/GNOXFMR NEUTRAL GROUNDING TRANSFORMER 01-3 GENERATOR RELAY BOX 01-3 E-l CONTROL PANEL E-l EM-Al EVENT MONITORING RACK EM-Al EM-A3 EVENT MON I TOR I NG RACK EM-A3 EM-Bl EVENT MONITORING RACK EM-Bl EM-B3 EVENT MON I TORING RAC K EM-B3 F-l CONTROL PANEL F-l G-l CONTROL PANE L G-l MCC lAl MOTOR CONTROL CENTER lA BUS 1 MCC1A2 MOTOR CONTROL CENTER lA BUS 2 MCC1AA2 MOTOR CONTROL CENTER lAA BUS 2 MCC lABl MOTOR CONTROL CENTER lAB BUS 1 MCC lAB2 MOTOR CONTRO L CENTER lAB BUS 2 MCC lACl MOTOR CONTROL CENTER lAC BUS 1 MCC lAC2 MOTOR CONTROL CENTER lAC BUS 2 MCC lJAl MOTOR CONTROL CENTER lJA BUS 1 MCC lJA2 MOTOR CONTROL CENTER lJA BUS 2 A-23 Prairie Island Nuclear Generat i ng Plant -Unit 1 Seismi c Walkdo w n Submittal Report , Updated Table A-1: Pra i r i e Island Unit 1 -Base list 1 Equ i pment Tag Desc ri pt i o n MCC1K1 MOTOR CONTROL CENTER 1 K BUS 1 MCC 1K2 MOTOR CONTROL CENTER 1K BUS 2 MCC 1KA2 MOTOR CONTROL CENTER 1KA BUS 2 MCC III MOTOR CONTROL CENTER 1L BUS 1 MCC 1L2 MOTOR CONTROL CENTER 1L BUS 2 MCC 1LA1 MOTOR CONTROL CENTER 1LA BUS 1 MCC 1LA2 MOTOR CONTROL CENTER 1LA BUS 2 MCC1M1 MOTOR CONTROL CENTER 1M BUS 1 MCC1M2 MOTOR CONTROL CENTER 1M BUS 2 MCC1MA1 MOTOR CONTROL CENTER 1MA BUS 1 MCC1MA2 MOTOR CONTRO L CENTER 1MA BUS 2 MCC 1R1 MOTOR CONTROL CENTER 1R BUS 1 MCC lSI MOTOR CONTROL CENTER I S BUS 1 MCC lT1 MOTOR CONTROL CENTER IT BUS 1 MCC lT2 MOTOR CONTROL CENTER IT BUS 2 MCC lTAl MOTOR CONTROL CENTER lTA BUS 1 MCC lTA2 MOTOR CONTROL CENTER lTA BUS 2 MCC l X l MOTOR CONTROL CENTER I X BUS 1 MCC 1 X2 MOTOR CONTROL CENTER I X BUS 2 MTR 111C-21 11 COOLING WATER STRA I NER A-24 Prairie Island Nuclear Generating Plant -Unit 1 Seism i c Walkdown Submittal Report, Updated Table A-1: Prairie Island Un it 1 -Base L i st 1 Equ i pment Tag Descri p tion MTR 111E-45 11/21 AFW PUMPS UNIT COOLER MTR 1111-51 121-N(U2)

& 121-S(U1)

RELAY ROOM UNIT COOLERS MTR 112G-12 121 CONTROL ROOM CHILLED WATER PUMP MTR 1211-51 122-N(U2)

& 122-S(U1)

RELAY ROOM UNIT COOLERS MTR 122G-12 122 CONTROL ROOM CHILLED WATER PUMP MV-32016 11 S/G STEAM SUPPLY TO 11 TO AFW PUMP MV MV-32017 LOOP B MN STM TO 11 TO AFWP MV MV-32025 11 TO AFW PUMP SUCT CLG WTR SUPPLY MV MV-32027 12 MD AFW PUMP SUCT CLG WTR SUPPLY MV MV-32031 1 TURB BLDG CLG WTR HDR MV MV-32034 121 CLWP DSCH HDR MV A MV-32035 121 CLWP DSCH HDR MV B MV-32036 121 CLWP DSCH HDR MV C MV-32037 121 CLWP DSCH HDR MV D MV-32047 12 MSIV BYPASS MV MV-32061 11 VOL CONT TNK TO CHG PMPS ISO L MV MV-32132 11 FC CLG WTR RTRN ISOL MV A MV-32133 11 FC CLG WTR RTRN ISOL MV B MV-32135 12 FC CLG WTR RTRN ISOL MV A MV-32136 12 FC CLG WTR RTRN ISOL MV B A-25 P r airie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Table A-1: Prairie Island Unit 1 -Base Li st 1 Equipment Tag Descrip tion MV-32138 13 FC CLG WTR RTRN ISOL MV A MV-32139 13 FC CLG WTR RTRN ISOL MV B MV-3214 1 14 FC CLG WTR RTRN ISOL MV A MV-3214 2 14 FC CLG WTR RTRN ISOL MV B MV-3 2 14S 11 CC HX CLG WTR IN L ET MV MV-32146 12 CC HX CLG WTR INLET MV MV-32166 1 REAC EXes LTON LINE ISOL MV A MV-32199 1 REAC EXes LTON LINE ISOL MV B MV-32238 11 TO AUX FW TO 11 STM GEN MV MV-32239 11 TO AUX FW TO 12 STM GEN MV MV-32242 11/12 AUX FW TO 11 STM GEN ISOL MV MV-32243 11/12 AUX FW TO 12 STM GEN ISOL MV MV-3 2 322 11 AU X BLDG CLG WTR RTRN HDR MV MV-32332 11 AU X BLDG CLG WTR RTRN HDR ISOL MV MV-32371 11/12 TURB OIL COOLERS CLG WTR BYPASS MV MV-32377 11 FC CLG WTR INLT ISOL MV MV-32378 13 FC CLG WTR INLT ISOL MV MV-32379 12 FC CLG WTR INLT ISOL MV MV-32380 14 FC CLG WTR INLT I SO L MV MV-3 23 81 12 AFWP DSC H TO 11 S T M GEN MV A-26 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Table A-1: Prair i e Island Unit 1 -Base List 1 Equ i pment Tag Description MV-32382 12 AFWP DSCH TO 12 STM GEN MV PNLll DISTRIBUTION PANEL 11 PNL 111 I NSTR BUS II PANEL (WHI) 111 PNL 1111 AC DISTRIBUTION CAB (WH I) 1111 PNL 1112 AC DISTRIBUTION CAB (RED) 1112 PNL 1113 AC DISTRIBUTION CAB (BLUE) 1113 PNL 1113-16 127 MISCELLANEOUS RELAY RACK PNL 1114 AC DISTRIBUTION CAB (YEL) 1114 PNL 1114-14 128 M I SCELLANEOUS RELAY RACK PN L 112 INSTR BUS I PANEL (RED) 112 PNL 113 INSTR BUS III PANEL (BLUE) 113 PNL 114 INSTR BUS IV PANEL (YEL) 114 PNL 115 ROD POSITION DISC SW PNL 115 PNL 116 NON-INTERRUPTABLE PANEL 116 PNL 117 INTERRUPTABLE PANEL 117 PNL12 DISTRIBUTION PANEL 12 PNL 131 DC DISTRIBUTION PANEL 131 PNL 132 AC DISTR I BUTION PANEL 132 PNL 132-7 11/21 AFW PUMPS UNIT COOLER PNL 133 AC DISTRIBUTION PANEL 133 A-27 Prairie I sland Nuclear Gene r ating Plant -Unit 1 Se i smic Walkdown Submittal Report , Updated Table A-1: Prairie Island Unit 1 -Base L ist 1 Equipment Tag Descriptio n P N L 133/XFMR DIST PNL 1 33 X FMR PNL 134 AC DISTRIBUTION PA N EL 13 4 PNL 135 AC DISTRIBUTION PANEL 135 PNL136 AC DISTRIBUTION PANEL 136 PNL137 AC DISTRIBUTION PANEL 137 PNL 15 NUCLEAR DISTRIBUTION PANEL 15 PNL 151 DISTRIBUTION PANEL 151 PNL 152 DISTRIBUTION PANEL 152 PNL 153 DISTRIBUTION PANEL 153 P N L 16 NUCLEAR DISTRIBUTION PANEL 16 P N L 161 DC DISTRIBUT I ON PAN E L 161 PNL 162 DC DISTR I BUTION PANEL 162 PNL163 DC DISTRIBUTION PANEL 163 PNL17 DC DISTRIBUTION PANEL 17 PNL1 8 DC DISTRIBUTION PANEL 18 PNL 191 DC DISTRIBUTION PANEL 191 PNL 1EM DISTRIBUTION PANEL 1EM PNL lEMA DISTRIBUTION PA N EL lEMA PNL 1EMA-ll ICCM UNIT 1 TRAIN A MICROP R OCE S SOR 1 L M-7S0 P N L 1EMA-5 E X CORE DEl AMPLIFIER 1NM-S1 A-28 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Table A-1: Prairie Island Un i t 1 -Base List 1 Equ i pmentTag Description PNL1EMA-8 TB A168S ICCM UNIT 1 TRAIN A PLASMA DISPLAY PNL1EMB DISTRIBUTION PANEl1EMB PNL1EMB-11 ICCM UNIT 1 TRAIN B MICROPROCESSOR 1LM-760 PNL1EMB-3 EXCORE DEl AMPLIFIER 1NM-S2 PNL1EMB-8 TB 2889 ICCM UNIT 1 TRAIN B PLASMA DISPLAY RC-1O-1 PRESSURIZER RELIEF VALVE RC-1O-2 PRESSURIZER RELIEF VALVE RS-21-1 SAFETY VALVE HEADER STM GENERATOR 11 RS-21-10 SAFETY VALVE HEADER STM GENERATOR 12 RS-21-2 SAFETY VALVE HEADER STM GENERATOR 11 RS-21-3 SAFETY VALVE HEADER STM GENERATOR 11 RS-21-4 SAFETY VALVE HEADER STM GENERATOR 11 RS-21-S SAFETY VALVE HEADER STM GENERATOR 11 RS-21-6 SAFETY VALVE HEADER STM GENERATOR 12 RS-21-7 SAFETY VALVE HEADER STM GENERATOR 12 RS-21-8 SAFETY VALVE HEADER STM GENERATOR 12 RS-21-9 SAFETY VALVE HEADER STM GENERATOR 12 SA-S4-3 01 DSL GEN MAIN AIR RCVR RELIEF SA-S4-6 02 DSL GEN MAIN AIR RCVR RELIEF SA-S6-1 12 CLG WTR PUMP -DIESEL STARTING AIR A-29 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report. Updated Table A-1: Prairie Island Unit 1 -Base List 1 Equ i pment Tag Description SV-33133 CLG WTR TO 121 SFGROS TRVLG SCRNS SV SV-33134 CLG WTR TO 1 2 2 SFGROS TRVLG SCRNS SV SV-33 1 86 01 OS L GEN WTR SPLY SV SV-33187 02 OSL GEN WTR SPLY SV SV-33188 01 OS L GEN CLNT E X PN TNK F I LL SV SV-33189 02 OSL GEN CLNT E X PN TNK FILL SV SV-33199 11 LOOP A MN STM HOR AIR SPLY SV A SV-33200 11L00P A MN STM HOR AIR SPLY SV B SV-33201 11 LOOP A MN STM HOR AIR EXHT SV A SV-33202 11 LOOP A MN STM HOR AIR EXHT SV B SV-33204 12 LOOP B MN STM HOR AIR SPLY SV A SV-33234 11 REAC CLNT VOL CO NT TN K LVL CONT VENT SV SV-33235 11 REAC CLNTVOL CONTTN K LVL CONT MAN/AUTO SV SV-33 2 4 2 01 OSL GEN AIR STRT VENT SV SV-33 2 45 02 O S L GEN AIR STRT VENT SV SV-3 3 254 1 2 LOOP B MN STM HOR AIR SPLY SV B SV-33255 12 LOOP B MN STM HOR AIR E X HT SV A S V-33256 1 2 LOOP B MN S TM HOR AIR E X HT SV B S V-33285 11 TO AUX FW PMP RCRC/LUBE OIL CLG SV SV-33286 12 MO AU X FW PMP RCRC/LUBE OI L CLG SV A-30 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table A-1: Prair i e Island Unit 1 -Base List 1 Equipment Tag Description SV-33299 11 TO AFW PMP STM BLOCK SV SV-33323 1 REAC CLNT LOOP PRZR LTON l N ISOL SV*2 SV-33343 11 CLG WTR STRNR BCKWSH SV SV-33371 11 FAN COIL UNIT DSCH TO CONTM DOME DMPR SV SV-33372 11 FAN CO I L UNIT NORM DSCH TO GAP & STRUC DMPR S SV-33373 12 FAN COil UNIT DSCH TO CONTM DOME DMPR SV SV-33374 12 FAN COIL UNIT NORM DSCH TO GAP & STRUC DMPR S SV-33375 13 FAN COIL UNIT DSCH TO CONTM DOME DMPR SV SV-33376 13 FAN COIL UNIT NORM DSCH TO GAP & STRUC DMPR S SV-33377 14 FAN COIL UNIT DSCH TO CONTM DOME DMPR SV SV-33378 14 FAN CO I L UNIT DSCH TO GAP & STRUC DMPR SV SV-33464 12 DD CLG WTR PMP AIR MTR RS SV A SV-33465 12 DD CLWP AIR MTR LS SV B SV-33512 1 REAC CLNT LOOP PRZR LTON LN ISOL SV 1 SV-33578 12 AUX FW PMP MTR UNIT CLR SV .. SV-33644 D 1 DSl GEN AIR STRT SV A SV-33645 D1 DSL GEN AIR STRT SV B SV-33646 D2 DSL GEN AIR STRT SV A SV-33669 11 REAC CLNT PMP SL WTR OUlL ISOL SV SV-33670 12 REAC CLNT PMP SL WTR OUlL I SOL SV A-31 Prairie Island Nuclear Generating Plant -Un it 1 Seismic Walkdown Submittal Report , Updated Table A-1: Prair i e Island Unit 1 -Base List 1 Equipment Tag Description SV-33693 11 SCVNG & COMB T N AIR DMPR SV A SV-33694 11 CLASS I ROOF EXHT FAN DMPR SV SV-33702 121 CONT RM AIR HNDLR OA SPLY DMPR SV SV-33703 121 CONT RM A I R HNDLR DSCH DMPR SV A SV-33704 122 CONT RM AIR HNDLR DSCH DMPR SV A SV-33705 122 CONT RM AIR HNDLR OA SPLY DMPR SV SV-33709 121 CON T RM PAC FLTR SPLY DMPR SV SV-33711 122 CONT RM PAC F L TR SPLY SV SV-33716 1 22 CONT RM CH L LR CLG WTR SV SV-33717 121 CONT RM CHLLR CLG WTR SV SV-33774 D2 DSL GEN A I R STRT SV B SV-33776 12 DO CLWP DSL JCKT CLR OUTL SV SV-33820 121 CON T RM AIR HNDLR DSCH DMPR SV B SV-33821 122 CONT RM A I R HNDLR DSCH DMPR SV B SV-33828 11 SCVNG & COMBUSTION AIR DMPR SV B SV-33987 Dl & D2 DSL GEN OUTSIDE AIR CD-34049 TRN AS SV-37022 121 CONT RM HNDLR OA SPLY STM EXCL B SV SV-3702S 122 CONT RM HNDLR OA SPLY STM EXCL A SV SV-37035 RCS VENT SYS PRZR VENT SV SV-37036 RCS VENT SYS PRZR VENT SV A-32 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Table A*1: Pra iri e Island Unit 1 -B ase List 1 E qu i pment Tag Desc ri ption SV-37037 RCS VENT SYS REACTOR HEAD VENT SV SV-37038 RCS VENT SYS REACTOR HEAD VENT SV SV-37039 RCS VENT SYS TO PRT SV SV-37040 RCS VENT SYS TO CNTMT ATMOS SV 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-37201 11 & 13 FCU CLG WTR RTN ORIF B-P SV SV-37203 12 & 14 FCU CLG WTR RTN ORIF B-P SV SV-37401 11; 13 FCU CLG WTR SUPPLY SV SV-37402 11; 13 FCU CHILLED WTR SUPPLY SV SV-37403 12; 14 FCU CLG WTR S UPPLY SV SV-37404 12; 14 FCU CH I L L ED WTR SUPPLY SV SV-3740S 11 SHROUD CLG COILS TR A CHILLED WTR SUPPLY SV SV-37406 12 SHROUD CLG COILS TR B CHILLED WTR SUPPL Y SV SV-37409 12; 14 FCU CLG WTR RETURN SV SV-37411 11; 13 FCU CLG WTR RETURN SV SV-37460 UNIT 1 TRAIN A CHILL WTR/CLG WTR ISOL SV SV-37461 UNIT 1 TRAIN B CHILL WTR/CLG WTR ISOL SV SV-37 4 6 2 UNIT 1 TRAIN A CH I LL WTR/CLG WTR ISOL SV A-33 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Subm i ttal Report , Updated Table A-1: Prair i e Island Unit 1 -Base L i st 1 Equipment Tag Desc rip tion SV-37463 UNIT 1 TRAIN B CHILL WTR/CLG WTR ISOL SV TB 1203 RELAY ROOM AUX RELAY CAB I NET TB 1209 RELAY ROOM TERMINAL BOX TB 1243 TB FOR 12 CHARG I NG PUMP TB 1244 TB FOR 11 CHARGING PUMP TBA1640 11 TD AUX FEEDWATER PUMP RELAY CAB I NET VC-1-1 CHARGING PUMP SUCTION FROM RWST VC-24-1 VOLUME CONTROL TANK RELIEF VALVE VC-2S-1 RC PUMPS DISCH LINE TO SEAL WTR FILTER -RELIEF VC-2 6-1 1 REGEN H X LETDOWN LINE OUTLET RELIEF TO PRT VC-28-1 11 CHG PMP DISCH RELIEF VC-28-2 12 CHG PMP DISCH RELIEF ZH-16-1 121 CHILLER OUTLET -R L F ZH-16-2 122 CH I LLER OUTLET -RLF A-34 A.2 Equipment Selection

-Base List 2 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table A-2 is a list of the equipment resulting from Screen #3 and entering Screen #4 for the SFP. The screens utilized for selecting equ i pment for the SWEL is described in Sections 4 of this report. This list of initial equipment is called "Base List 2 ," per the guidance in Reference

1. Table A-2: Pra I rie Is l and U nit 1 -Base List 2 Equipment Tag Description 035-011 121 SFP HX 035-012 122 SFP HX 045-101 121 SFP PMP 045-102 122 SFP PMP A-35 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated A.3 Final SWEL 1 This section provides a list of the final equipment selected for PINGP's SWEL 1 in Table A-3 below. This table identifies which items were selected for anchorage configuration verification, as well as which items were deferred due to in accessib ilit y. The comments column of this table identifies the following selection criteria w hi ch 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-36 Equipment Tag 22024 032-041 032-292 046-03 1A 053-321 053-382 069-242 076-022 125MR M V-32034 SA-54-3 S V-33694 SV-37025 22017 55000 55400 57304 70300 032-011 034-011 045-592 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Table A*3: Prairie Island Unit 1 -Final SWEL 1 Class Safety System Verify Deferred Description 1 Function' 3 Anchorage

? Comments ? 121 MD CLG WTR PMP AREA T XM TR B 18 1 , 2 , 3 , 4 , 5 ZR 121 D1 DSL GEN SPLY FAN 9 1 , 2 , 3 , 4 , 5 D1 Yes 122 CONT RM CLEAN-UP FAN 9 1,2 , 3,4 , 5 ZN D1 DSL GEN START-UP AIR RCVR A 21 1 , 2 , 3 , 4 , 5 D1 Yes 12 DD CLG WTR PMP DSL OIL DAY TNK 21 1 , 2 , 3 , 4,5 CL Yes 122 CONT RM CHLD WTR E XPN TNK 21 1 , 2 , 3 , 4 , 5 ZH Yes 122 CONT RM PAC FLTR 0 1 , 2 , 3,4,5 ZN 122 CONT RM AIR HNDLR 10 1 , 2 , 3 , 4,5 ZN 125 MISC RELAY RACK 20 1 , 2 , 3 , 4 , 5 MP 121 CLWP DSCH HDR MV A 8 1 , 2 , 3 , 4 , 5 CL D1 DSL GEN MAIN AIR RC V R RELIEF 7 1 , 2 , 3 , 4 , 5 SA 11 SFGDS SCRNHSE ROOF E XHT FAN CD-8 1,2,3,4,5 ZR Ne w or replaced 34137 S V 122 CO NT RM AIR HNDLR OA SPLY CD-34145 8 1 , 2 , 3,4,5 ZN SV D1 DSL GEN RM TEMP XMTR 18 1 , 2 , 3,4 , 5 ZG D1 DSL GEN GAUGE PANEL (DGP) 20 1 , 2,3,4 , 5 D1 Yes IPEEE Enhanced D1 DSL GEN AUX CO NT PNL 14 1,2,3 , 4 , 5 D1 Yes 122 CONT RM CHLR LCL CO NT PNL 20 1 , 2 , 3,4 , 5 ZH 12 DD CLWP LCL PNL 20 1, 2,3 , 4 , 5 CL Yes IPEEE Enhanced 121 D1 DSL GEN EXHT FAN 9 1 , 2,3,4 , 5 ZG Y es D1 DSL GEN 17 1,2 , 3,4 , 5 D1 Yes 122 CO NT RM CHLD WTR P MP 5 1 , 2 , 3,4 , 5 ZH Yes A-37 Equipment Tag 053-201 053-481 075-012 11 BATT 11 BATT CHG 111M/XFM R 112M/XFM R 117-111 12 BATT 12 BATT CHG 122M/X FM R 132-2 81 135-101 145-042 14 5-071 145-122 145-201 145-392 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Wa l kdown Submittal Report , Updated Table A-3: Prairie Island Uni t 1 -Final SWEL 1 Class Safety System Verify Deferred Description 1 Function' 1 Anchorage

? Comments ? D1 DSL GEN FUEL OIL DAY TANK 21 1 , 2 , 3 , 4,5 D1 Yes D1 DSL GEN E X PANS ION TANK 21 1 , 2 , 3 , 4,5 D1 Yes 122 CONT RM CHLR 11 1 , 2 , 3 , 4 , 5 ZH Yes IPEEE Enhance d 11 BATTERY (& BATTERY RACK) 15 1 , 2 , 3 , 4 , 5 DC Yes IPEEE Enhanced Ne w or replaced (EC 17202 replaced existing safety-related 11 BATTERY CHARGER 16 1,2 , 3 , 4 , 5 DC Yes Yes battery charger w ith ne w safety-related battery charger), IPEEE Enhanced 111 M TRANSFORMER 4 1 , 2 , 3 , 4 , 5 EB Risk significant 112M TRANSFORMER 4 1 , 2 , 3 , 4 , 5 EB 11 TO AFW PMP L-O CLR 21 4 AF Yes 12 BATTERY (& BATTERY RACK) 15 1,2 , 3 , 4,5 DC Yes IPEEE Enhanced Ne w or replaced (EC 17202 replaced existing safety-related 12 BATTERY CHARGER 16 1,2,3,4,5 DC Yes battery charger with new safety-related battery charger), IPEEE Enhanced 122M TRANSFORMER 4 1 , 2 , 3 , 4 , 5 EB 11 SFGDS SCRNHSE ROOF EXHT FAN 9 1 , 2 , 3 , 4 , 5 ZR Yes Yes IPEEE Enhanced 12 CLG WTR PMP DSL JCKT CLG HX 21 1 , 2 , 3 , 4 , 5 CL Yes IPEEE Enhanced 12CHG PMP 5 1,2 , 3 VC Yes 11 SI PMP 5 3 SI Yes 12 CC PMP 5 2, 3 CC Yes Risk significant 11 TDAFWPMP 5 4 AF Yes 12 DD CLG WTR PMP 6 1,2 , 3 , 4 , 5 CL Yes IPEEE Enhanced A-38 Equ i pment Tag 158-011 174-013 174-031 174-162 1ASG1 1FT-464 1LT-428 1LT-461 1LT-762 1LT-763 1LT-920 1LT-921 1NR3 1PT-469 1PT-479 B-1 B15 LOGIC-2 BUS 112 BUS 1 5 C V-31 059 C V-31153 CV-31423 CV-3 1 505 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Table A-3: Prairie Island Unit 1 -Final SWEL 1 Class Safety System Verify Deferred Descr i ption 1 F unction' 1 Anchorage

? Comments ? 11 CLG WTR STRNR 0 1 , 2 , 3,4 , 5 CL Yes 13 CNTMTFCU 10 5 ZC Yes IPEEE Enhanced 15 SWGR RM UNIT CLR 10 1 , 2 , 3 , 4 , 5 ZH Yes TRN A E V ENT MON RM WEST UNIT CLR 10 1 , 2,3,4 , 5 ZH SAFEGUARD RELAY RACK 1ASG1 20 1,2 , 3 , 4,5 RP MN STM FR 11 STM GEN CHNNL I RED F XMTR 18 4 RP Yes 1 PRZR (CHNL III-BLU) LVL X MTR 18 3 RP Yes 11 STM GEN LOOP A CHNNL I RED LVL XMTR 18 4 RP Yes U1 RVLlS HEAD FULL RANGE TRN B D I P XMTR 18 3 EM 12 RX VSL HEAD DYNAMIC RNG TRN B DIP 18 3 EM XMTR 11 RWST L V L XMTR 18 1 , 2,3 EM 11 RWST LVL XMTR 18 1 , 2 , 3 EM Yes NIS RACK III (BLU) 1 NR3 20 1 NI IPEEE Enhanced 11 STM GEN LOOP A (CHNNL II-WHI) P XMTR 18 4 RP Yes 12 STM GEN LOOP B (CHNL IV-YEL) P XMTR 18 4 RP Yes CONTROL PANEL B-1 20 1 , 3 , 4 , 5 BM IPEEE Enhanced BUS 15 LOGIC RELAY CAB 2 20 1 , 2 , 3,4 , 5 EA Yes BUS 112 480V SWITCHGEAR 2 1,2 , 3 , 4 , 5 EB Yes Substituted for BUS 1 22 BUS 15 4_16KV SWITCHGEAR 3 1 , 2 , 3 , 4,5 EA Yes Substituted for BUS 16 11 TO AFW PMP TRIP THROTILE CV 7 4 AF 11 TO AFW PMP RECIRC/L-O CLG CV 7 4 AF 12 DO CLG WTR JCKT CLR OUTL CV 7 1 , 2 , 3,4,5 CL 01 DSL GEN CLG WTR SPL Y CV 7 1 , 2 , 3 , 4 , 5 CL A-39 Equipment Tag C V-31652 CV-31953 CV-39401 CV-39405 D-l D1/GEN RLYPNL E-l EM-B1 MCC 1A1 MCC 1AB2 MCC 1K2 MCC 1L2 MCC 1T2 MCC 1T2IXFR SW MTR 111F-31 MTR 111F-32 MV-32017 MV-32025 MV-32077 MV-32133 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Subm itt al Report , Updated Table A-3: Prairie Island Unit 1 -Final SWEL 1 Class Safety System Verify Deferred Description , Function 2 1 Anchorage

? Comments ? 11 CLG WTR STRNR BCKWSH CV 7 1 , 2 , 3 , 4 , 5 CL Dl DSL GEN AIR START CV A 7 1,2 ,3, 4 , 5 D1 11/13 FCU CLG WTR SPL Y CV 7 5 LX IPEEE Enhanced 11 CRD M SHRD CLG COIL SPL Y CV 7 5 LX Yes CONTROL PANEL D-l 20 4 BM Yes IPEEE Enhanced D1 DSL GEN RELAY PNL 20 1 , 2,3,4 , 5 D1 Yes CONTROL PANEL E-l 20 1 , 2 , 3 , 4 , 5 BM Ye s IPEEE Enhanced U1 EVENT MON RACK E M-B1 20 4 , 5 EM Yes MOTOR CONTROL CENTER 1A BUS 1 1 1 , 2 , 3 , 4 , 5 EB Yes MOTOR CONTROL CENTER 1AB BUS 2 1 1 , 2 , 3 , 4 , 5 EB Yes Yes IPEEE Enhanced MOTOR CONTROL CENTER 1K BUS 2 1 1,2 , 3 ,4, 5 EB Ye s Yes MOTOR CONTROL CENTER 1 L BUS 2 1 1 , 3,5 EB Yes Yes IPEEE Enhanced MOTOR CONTROL CENTER 1T BUS 2 1 1 , 2 , 3 ,4, 5 EB Yes Ye s Ne w or rep l aced (99E B01 purchased, qualified , and MCC 1T2 X FR SW 4 1 , 2 , 3 , 4 , 5 EB installed ne w transfer s wi tch , modification on Manual Transfer S w itch Cabinet anchor bolts) 11 INVERTER (INSTR BUS II-WHI) 16 1 , 2 , 3 , 4 , 5 IP Yes 13 INVERTER (INSTR BUS Ill-BLU) 16 1 ,2, 3 , 4 , 5 IP Yes 12 SG MS SPLYTO 11 TO AFW PMP MV 8 4 MS 11 TO AFW PMP SUCT CL SPL Y MV 8 4 CL SUMP B TO 11 RHR PMP TRN A (OUTSIDE)

MV 8 3 , 4 S I 11 FCU CLG WTR OUTL ISOL MV B 8 5 CL A-40 Equ i pment Tag MV-32141 M V-32145 M V-32238 M V-32242 M V-32380 MV-32381 PNL11 PNL 111 PNL 113 PNL12 PNL 133 PNL 133/X FMR PNL 136 PNL 136/X FMR PNL 153 PNL 191 PNL1EM RS-21-1 SV-33186 SV-33242 SV-33343 SV-33371 SV-37460 SV-37462 V C-28-2 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Subm i ttal Report , Updated Table A-3: Prairie Island Unit 1 -Final SWEL 1 Class Safety System Verify Deferred Descript io n 1 Function' J Anchorage

? Comments ? 14 FCU CLG WTR OUTL ISOL MV A 8 5 CL Yes EC 691 installed manual bonnet vent valves 11 CC HX CLG WTR INL T MV 8 3 CL 11 AFW TO 11 SG MV 8 4 AF 11/12 AFW TO 11 SG ISOL MV 8 4 AF 14 FCU CLG WTR INLT ISOL MV 8 5 CL EC 691 installed manual bonnet vent valves 12 MD AFW PMP DISCH TO 11 SG MV 8 4 AF DISTRIBUTION PANEL 11 14 1 , 2 , 3 , 4 , 5 DC Yes Yes IP EEE Enhanced INSTR BUS II (WHI) PNL 111 14 1,2 , 3 , 4 , 5 IP Yes INSTR BUS III (BLUE) PNL 113 14 1 , 2 , 3 , 4 , 5 IP Yes DISTRIBUTION PANEL 12 14 1,2 , 3 , 4 , 5 DC Yes IPEEE Enhanced AC DISTRIBUTION PANEL 133 14 1,2,3 , 4 , 5 E X Yes Yes DIST PNL 133 XFMR 4 1 , 2 , 3 , 4 , 5 EX AC DISTRIBUTION PANEL 136 14 1,2,3 , 4 , 5 E X Yes Yes DlST PNL 136 XFMR 4 1 , 2 , 3,4,5 E X DISTRIBUTION PANEL 153 14 3 , 5 DC 'Yes Yes DC DISTRIBUTION PANEL 191 14 3,4 , 5 DC Ye s DIST PNL 1EM 14 1 , 2,3,4 , 5 EM Yes 11 SG MS HDR RELIEF 7 4 MS 01 DSL GEN WTR SPL Y SV 8 1 , 2 , 3 , 4 , 5 CL 01 DSL GEN AIR START VENT SV 8 1 , 2,3 , 4,5 01 11 CLG WTR STRNR BCKWSH SV 8 1 , 2 , 3 , 4,5 CL 11 FCU DISCH TO CNTMT DOME CD-34072 SV 8 5 ZC Yes New or replaced U1 TRN A CHLD WTRlCLG WTR ISOL SV 8 1 , 2,3,4 , 5 ZX Yes U1 TRN A CHLD WTRlCLG WTR ISOL SV 8 1 , 2,3 , 4 , 5 ZX 12 CHG PMP DISCH RELIEF 7 1 , 2 , 3 VC A-41 Notes: AF AT BM CC CL D1 D2 D5 D6 DC EA EB EH EL EM EX FO FW IP Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated 1) Class -Class as defined in Appendix B of Reference

1. 21 Safety function -Defined as follow s: 1 = Reactor Reactivity Con trol 2 = Reactor Coo l ant Pressure Contro l 3 = Reactor Coolant inve nt ory Cont r ol 4 = Decay Heat Removal 5 = Containment Function 3) System -Ide n tifie s the system associated with th e eq uipment. T he abbreviations for these systems are listed below. AUXILIARY FEEDWATER MP MISC PLANT IN STR U MENTS AUX STAR T-U P/STDBY XFMRS MS MAIN S T EAM SITE MISCELLANEOUS NI NUCLEAR INSTRUMENTATION MA I N TEN ANCE COMPONENT COOLING PI ROD POSITION INDI CAT I ON COOLING WATER RC REACTOR COOLANT D1 EMERGENCY DIESEL RP REACTOR PROTECTION D2 EMERGENCY DIESEL SA STAT I O N & IN STRUME NT AIR D5 EMERGENCY DIESEL SE STEAM EXCLUSION D6 EMERGENCY DIESEL SF SPEN T FUEL POOL COOLING DC AUXILIARIES SI SAFETY IN JEC TION 4.16KV ELECTRICAL VC CHEMICAL & VOLUME CONTROL 480V ELECTRICAL ZC CONTAINMENT VENT ELECTRO-HYDRAULIC SYSTEM ZG DIESEL ROOMS VENT SIT E LIGHTING ZH SAFEGUARDS CHILL ED WATER EVENT MONITORING ZR SCREENHOUSE VENT 240/120V MISC AUXILIARIES ZX CNTMT & AUX BLDG COOLING FUEL OIL FEEDWATER INSTRUMENT POWER SOURCES A-42 A.4 Final SWEL 2 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report. Updated This section provides a list of the final equipment selected for PINGP's SWEL 2 for the SFP. Table A-4lists the components selected for the SWEL 2 walkdo w ns. Table A-4: Prairie Island Unit 1 -Final SWEL 2 Equ i pment Tag Description 035-012 122 SFP HX 045-102 122 SFP PMP A-43 B Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated 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 29 deferred seismic walkdowns that needed to be comp l eted at a later date. Two (2) items were inaccessible during RFO 1 R29 and were therefore substituted for similar components. 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 inac c essible. NSPM completed 29 deferred seismic walkdowns. The SWCs are provided after Table B-1 , and are in the same chronological order as listed in the table. The SWCs in this appendix include information on the location of SWEL components , which is considered Sensitive Unclassified Non-Safeguards Information (SUNSI), of which the loss , issue , modification , or unauthorized access can reasonably be foreseen to harm the safe operation of the nuclear plant. Pages which contain 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. A copy of this report with the SUNSI information redacted has been provided as Enclosure 2 of this letter package. B-1 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated 8-2 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 1 of 3 Status: y[g] NO uO Seismic Walkdown Checklist (SWC) EquipmenllD No _____ Eq uip. C la ss' (211 Tanks and Heat E xc hangers E quipm e nt Description Location:

OIdg. _ 1'1001' 131. __ Room , Arca _>--------


Manufaclurer, Model, E l c. (oplional bul r eco mmend e d) Instructions foJ' Complcting Checldist This checklist may be used t o document the re s ult s of the Seismic Walkdown of an item of equipmenl on the SWEL. The space below each of the following qu est i o ns may b e used to record the resnlts of judgment s and findings. Additional spacc i s providcd al the end ofthi. chccklist for doctllll c ntin g olher co mment s. Anchonlge I. I s the anchorage configuration verification required (i.e., is the item one yo N[8J oflhe 50% ofSWEL items requiring s u c h verification)?

2. I s Ihe anchorage Free o f benl, broken, mi ss ing or lo ose hardware?

Y[8J NO UO NI AD 2 of 8 anchors not viewed due to elevation of the tani<, considered acceptable as no signs of degradation.

3. I s Ihe anchorage free of'corrosionlhal i s m o re than mild s urfa ce Y[8J NO UO N/AO ox idalion? I I. I s Ih e anchorage free ol'visible cmeks in the concrete near the anch o rs'? Y[8J NO UO N/AO 5. I s the an c horage configuration consistent with planl documentation?

yo NO UO N/A[8J (Not e: Thi s <<nc s tion a ni), applies iflhe ilem i s Ol1e oflhe 50% for which all anchol'£lgc cOllfigl\l'ution vel"ificn tion i s required.) 6. Based a ll th e above anchorage eva luatio11 s, is the allchorage free or Y[8J NO UO p o tentiall y adverse seis mi c co nditioll S? I Enlr..:l' th e t:quip tw:nt dn s$ lIill1\1.; fr ol1l Appendix B: C la sses of EC]uiplllcn

1. B-3 Prairie Island Nuclear Generating' Plant -Unit 1 Seism i c Walkdo w n Submittal Report , Updated S h ee t 2of3 Stat u s: vIZ] NO uO Seismic Walkdown Checldist (SWC) Eq uipill e nt ID Nn. ___ E quip. C la s s' (21) T anl(s a n (1 Heat Excllan ge rs Eq uipill e nt D esc ription _ Int e ractioll E ffects 7. A r c ,o fi tar ge t , ti'co liulil illipa e t b y II c arb y cqllipiliont 0 1' , trll o illr o,? YI8I NO UO N/AO No equipmen t in area o f sigM glass l evel tu be. H. Ar c ove rh e ad c quil'm c II I , di s l r ibuli o n sys t e lll s , ce ilill g lile s and li g htiu g , yo NO UO N/AI8I and ma so nr y bl od; wa ll s ll o t lik e l y t o co ll a p se on t o th e e quipl1l e nt? 9. Do al laeh ed lill o, 1111 1'0 adequat e flexibilily 1 0 avoid d,ulla ge? YI8I NO UO N/AO 10. Ba sed 0 11 th e ab ove se i s mi c int e ra c ti o n ev aluati o n s, i s e quipm e nt fr ee Y!8J NO UO n rp o tciltiall y se i s mic ilit e nH.!li o J1 c lrc cts? OIl.cl' Advcl'sc COllllition, II. 1-1: l ve yo u loo k e d for tlild r O llnd 11 0 o lh e r se i s mi c co nditi ons tlial co uld ad verse l y arl ee l til e s al'ely fUll c ti o n s o rlh e e quip11l e nt? Diese l gene r a t or ex pan sio n t an/( (05 3-48 1) lI as a mi ssing U-/Jo ft on the f irs t demineralizer wa t e r lin e S Uppolt aeljace nt to tile t anle S it e enginee ri ng ilas review e d tN s obse l valion and conclu(l ee l tilere i s no se i smic concern. C omment s (Addi ti omll pa g es ma y b e ad d e d as ll ccc:)sa r y) Y I8I NO lJ O This e quipment wa s originally inspected during the online in s pection s , !Jut d e f erred based on access restric t ions. Ev a lual e cl by:

_________ Dal e: 09/'1812014 Diteep C ll el'fopa li e c* v.o i 't 'f"

____ _ 09118120'1 4 8-4 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generat i ng Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Sh e cl30f3 Statu s: y[g) NO u O *** L ____ E quip. C la ss' 1211 Tank s a nd Heal Excllanqers Eq uipm e nt ID No. Eq u i pm e nt Desc ripti o n 8-5 Prairie Island Nuclear Generating Plant, Unit 1 Seismic Walkdo w n Submittal Report , Updated Sh ee t 1 of3 Status: y[gJ NO uO Seismic Walkdown Checklist (SWC) E quipm e nt 10 No. E quip. C la ss'" l w lCL..>C,,/Ji//ers-_____________ _ Equ ipm e nt De sc ripti on __ Location: Bld g .* ___ _ Floor C I ' Room , Area Ma nu fac tur e r , Model , Etc. (op ti o n a l but r eco mm ended) Instructions for COlllpletiug C hecldist This c h eck li st m ay be u sed to docum e nt th e r es ult s of' th e Seismic Walkdown of a n item of eq uipm e nt o n th e SWEL. The sp nce below cac h o f the fo ll owi ng qu estio n s mn y be u sc d t o rec o rd the res ult s of'jud g m e nt s and finding s. Additional space i s pr ov id cd at t h e end of this c he c klist for d oc um e nting o ther co mm e nt s. Anchorage

1. I s the anchorage config urati on verifica ti o n requ ired (i.e., i s th e it e m one yo N!8I of th c 50% ofSWEL itcm s rcquiring s u c h ve rifi ca ti o n)? 2. I s the an c h orage Ii'ee ofben t , broken , mi ss ing or l oose hardware?

Y!8I N O U O N/AO 3. I s th e "nc h orage free of co rrosi o n that i s m o re than mild s ur face Y!8I N O UO N/AO oxidation?

'I. Is the a n c h o r age f r ee of visibl e cracks in th e co n c r ete n car th e anchor s'! Y!8I N O UO N/A O 5. I s the a n c h orage co nfi guratio n cons i stent with pl a nt documentation?

y o N O UO N/A!8I (Not e: Thi s qu es ti o n on l y ap pli es if th e item i s one orthe 50% fo r w hi c h un unchorage con fi gu r at i o n verification i s r eq uir e d.) 6. Based o n th e above anc h orage eva lu a ti o n s, i s the a n chorage rr ee or Y!8I NO UO p o t entia ll y adverse sc i s m i e cand it iOll s? I EIl Ler t lu.: l'll, lip1l1 l!JlI class lliUlH; rr u nl Append i x n: C l a sses of E (lU ipIII CIiI.

Prairie Island Nuclear Generating Plant -Unit 1 Seismic Wa l kdown Submittal Report, Updated S h ec l 2 01'3 Slalu s: y[8J N O uO Seismic Waikdowil Checklist (SWC) EC luipm e nliD N o. ___ E quip. C la ss' u (1 C..!I:L).>C"-i1"'i1" l e"-f s"-_____________

_ E quipm e ul D ese ripli o n IlIlernctioll Eftecls 7. Arc s o li lar ge l s Ii*ee li"O m imp ac i b y lI e arby e quipm e lll or s lrll c lur es'! Y(gJ N O UO N/AO x. Ar c ov e rh e ad eqllipm e l1l , di S lriblili o ll sys l e m s , ce ilil1 g lil es al1dli g hlil1 g , Y (gJ N O U O N/AO al1dma so nr y bl o c k wall s u o l lik e l y 10 co llap se o nl o Ih e e qllipm e nl? Rod hun g h oa/or unit i s l ocatod so th oro i s n o imp a ct with c hill or 075 0 1 2. 9. D o H ltn c h e d lin e s ha ve ad e CJuat e n cx ibilit y t o nv o id dama ge? 10 , Ba s e d olllll C ah o v e SC i S llli c int e ra c ti o n CV alll<lli o ll S , i s equipln e nt rr e e o r p O l e llli;lIl y <"I v e r s e se i s m ic inl e rn c li o ll e f'l e c l s? OilIer Adverse C ontiililllls II. I-la ve Y(H I Ju n k e ll r o r lIl H ll iJl llld II I l o th e r se i s mi c c OIJ(lili l lll S Ihal c ntlld adv e r se l y alT e e l l b e s ald y lilll e linn s orlb e eqllip"1 0 1l1'/ C UlIIlIIenls (Add i ti o n a l pa g e s llI a y b e a d d t.: d i l S Il cccss m y) Y (gJ NO UO N/AO Y(gJ NO UO Y (gJ NO IJO E V" III" l e d b y: !-'f(L'I"'o-'.I (!!.r"'i o"'s"'o/'--_+7fL-b----,=-=-z....=

c-_--::;o,L-

______ I)" I e: 0 912412014 Di l eep C/l or i opa ll e 0912 4 12014 8-7 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated S h ee t 3 of 3 ,slatu s: NO uO EqllipllI c lltlD No. __ Eqllip. C la ss'_(u 1-,-1 L) C><I"'l;"'" e'-'.f-s ____________ _ E qilipllI e lit D e sc riptioll 8-8 Prairie Island N uc lear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated of 4 Slalus: ytgJ NO uO Seismic Walkdown Checklist (SWC) Eq uipm e nt ID No. __ Eq uip. C l ass' (16 1 Bat/ery C h argers and In ve rte rs L oca ti o n: Bldg. __ Floor E I. ___ Room , Arca _1-----------Manufh c tur er, M o d e l , E t c. (o pti ona l bnt r eco mm e nded) In s tl'uctioJls 1'01' Co ml,leting Checklist T his c he c kl i s t m ay be u sed to do c um e nt the re s ult s of th e Sei s mi c Walkdown of a n it em of equipment o n th e S W EL. The s p ace below eac h of the foll o win g qu es ti ons m ay be u s ed to r eco rd th e re s ult s of jud g m e nt s a nd finding s. Additional s p ace is provided a t th e e nd of thi s check li s t for d oc um e nting o th e r comments.

Anchorngo I. I s the anchorage co nti g u nlt i o n ve rifi ca ti o n required (i.e., i s th e it e m o n e YI8I NO oft h e 50% ofSWE L it e m s r e quirin g s u ch v e rifi ca ti o n)? 2. I s th e anc h orage free o fb c nt , broken , mi ss ing or l oose h a rdw a r e? YI8I NO UO N/A O 3. I s th e anchorage free o r co rro s i o n that i s m o r e th a n mild s urfa ce YI8I NO U O NI AD o x idnti o ll? Cracks were nol ed bul th ey do n 'I pass within th e sl J ear co n e of the anc h or. SW E's judged Ihe c r acks as acceplable and no/ a seismic co n cern. 4. I s th e anchoragc Ii'ee o f vi s ibl e cracks in th e concretc n ca r the anchor s? YI8I NO LJO N/AO 5. I s th e anchorage co nfi g ur atio n co n s i stcnt wi th pl a nt dOClllllentation?

YI8I NO UD N/AO (Note: This qLle s ti on o nl y ap pli es if th e i tem i s one of t h e 50% for whi c h an a n c h orage co nf ig urati o n ver ili ca li o n is required.) The ca l cu lati o n PI-99S-94-S 01 , revision 2, s h ows fou r 3/4" diameter anchor bolts. 6. Ba se d on th e ahove an e h omge eva lLl a ti o n s, is th e an c h orage fr ee of YI8I N O LJO p o tentially ncl v crse seis mic co nditi ons? I Enter the eq u i pment cl nss IJIIlIl C frolll App c mlb; 11: C la sses or Eq uip ment. 8-9 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Sh cc l 20 f4 S l al u s: y[gJ NO uO Seismic Walkdown Checkl i st (SWC) Eq uipm e nl ID No. ___ Eq uip. C la s s' 1161 Balle ry C/J araers a nd Inv e rt e rs Eq uipm e nl D ese riplion Interactioll Effect s 7. A rc so H lar gc l s fre c ti*o m im pac i b y n c arb y equipmen l o r s lru c lur es'? Y(gJ NO UO N/AO 8. Ar c ove rh ea d e qnipm e nl , di s lribuli on sys l e lll s , ce ilin g lil es and l i g hlin g , Y(gJ NO UO N/AO :llld ma SO lll Y bl ock wa ll s n O I lik e l y t o co llap s e 011 1 0 th e eq uipm e nt? 9. Do allached lin cs hav e ",I c qnal e n e, ibilil y 1 0 a vo id dallia ge? Y(gJ NO UO N/AO 10. na se d ollih e ab ovc sc i s mi c inl e ra e li o n evahHllio" s , i s e qllipllI e nl free Y(gJ NO UO or p O l e nt iall)' m l ve r s e se i s mi c inlcrHcl i O Il e ff ec t s? Otlier Adverse C OIulitiolis II. Il ave yo u lo o k e d Illl" and I b und n o ol h er se i s m ic co ndili o n s Ihal co uld adver se l y arre e llh e s al e l y liln e li uns or lh e cCll ripm e nl? C Ollllllent s (Addi ti o llal p ag e s lila), b e mhh: d as n ece ss a r y) Int e rnal in spec tion p e rformed. No is s ue s flotecl in t e rn a lly. Y(gJ NO UO " v a Ill a l cd b y: Da Ie: 0912412014 Dileep C h erlopalle 09124/2014 6-10 Sei s mi c Walkdown Checklist (SWC) Prairie Island Nu c lear Generating Plant -Unit 1 Seismi c Walkdo w n Submittal Report , Updated S h ee t 3 o f 4 S tn t ll s: y(8) NO u O E quipm e nllD No. __ Eq uip. C l nss' (16) Ba t tery C/l arae r s a n d tn ve rt ers E quipm e nl Desc ripl io n 8-11 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated S h e e t 4 01'4 8-12 Prairie Island Nuclear Gen e rating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Sheet l o f 3 Status: NO uO Seismic Walkdown Checklist (SWC) *** 1-----Equip. C la ss' (09) Fans Equipm e nt ID No. Equipment Description Locntion:

Bldg ___ ._ Floor E I. ___ Room, Ar ca _._ Manuf oc turcr , Model, Et c. (optionnl but recolllmcnded)

I nslmclinns fol' Com plcting Checl<list This c h eck li s t lII ay be u sc d to d ocu llIent Ihe r es uit s oft h c Seis mi c Wal kdo lVn of a n it C Ill ofcquipmeJ1t o n th e S WEL. The s pnce below en ch oflhe following qu es ti o n s llI ay b e u se d to rec o rd the r es ult s o fju1,1 , .. ,.,,,..,1'\:2 eAd::! (IM" ,,!-

Mi c/w e/ Woc/amv/( tI Y I8I NO U O Da l e: 10/, 1 4/2 014 10/14/2014 8-1 4 Seismic Walkdowll Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Sh cc t 3 of 3 Statu s: N O u O E quipm en! 10 No. __ E quip. C l nss'-.J("'O"'9)u F"'a"'n"'s _____________ _ 6-15 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Shc(,t 1 of 3 Status: y[gJ NO uO Seismic Walkdown Checklist (SWC) Equipmcnt lD No. *** 1-----Equip. Class' (10) Air H8ndlars Equipment Description

___ ========================= L oca tion: Bldg. ___ Floor EI. ___ Room, IIrca _f----------Mnnulacturer, Modol, Etc. IlIsl1'IICliolls 1'0)' COlllllleliug Checklisl This checklist Illay be us ed to documcntth e results oflhe Seismic Walkdown ol'an item orequipmenl on the SWEL. The s pace below cH ch of the following questions IllHy l>e used to record the resuits of judglllents and findings.

AdditionHI space i s pr oy jded at th c end ortllis checklist for doculllenting other comments.

Aneho"ll)!e I. I s the nnchorage configuration verilien!ion required (i.e., i s the ilem one yo N[gJ of th e 50% of SWflL items requiring such verilication)?

2. I s the anchomge li'e e orhent, broken , mis si ng or loo s e hardware'?

Y[gJ NO UO N/AO 3. I s the \lIl c horage rree of corrosion that is more thnnmild surrace Y[gJ NO UO N/AO oxidation?

'I. [s the anchorage li..:e of visible c meks in the concrete Hear th e "nehOl's? Y[gJ NO UO N/AO 5. I s the anchorage conl1guratioll co n sistent wilh planl d oc umentati o n? yo NO UO N/A[gJ (Note: This question only applies if the item is one oflhe 50% for whiell nil nncllonlge contigurntioll vel'ification is required.) 6. Based on Ihe abol'e anch o rage evalualions, is the anch o rage lI'ec or Y[gJ NO UO llotcntinlJy ndvcrse s eismic cond itions,? I EUler the equipment clt\$s IHlIUC fr om AppcJ\c1ix U: C ln sscs of EquipnlC'1l1.

8-16 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Sheet 2 of 3 Status: y(gJ N O uO Seismic Waikdowil Checklist (SWC) EquipluclltlD No. ___ Equip. C la ss'--'-'U"'O"'

i.!:, A"'itC,!*r"'/" al"'ld"'i"'e l"'*s'-___________ _ Equipmellt Des e riptioll Illtcraetioll Effects 7. Arc so n lar ge t s Ii'ee li'o m i mpa e l by lI ear by e qu i pment 01' st ruetllr es? Y[8) NO UO N/AO 8. Arc ove rhead c'I uipm c llt, di s tributioll systems, ee ilill g li l es a nd lighlin g. Y[8) NO liD N/AO n l1dmll 5 0 l1ry block wall s 110t lik e l y 10 collap s e 0 111 0 th e eq uipmel1l? Conduils above are su ppo/ted by Uni s lml s, w/)i c/) are ot/aeiled 10 lil e FCU frame wil il 4 beam cla mp s. T/)i s i s accep la/J/e. 9. Do nil ached li li es hn l'e adequate Il ex ibil ily t o "vo id damage'! Y[8) NO UO N/AO 10. Ho s ed 011 th e above se i s mi c il1t erne ti ol1 el'alualiol1 s, i s equ ipm e l1t free Y[8) NO UO of pot e l1tiall y adver s e seis mi c il1teractiol1 e ff ec t s'! Othe), A<Il'e)'.,e C","litioIlS II. Ila ve YO II l ooked f i ll' nnd f O llnd 11 0 other se i s mi c cond iti o n s thnt cOlll d adversely af'lccl the s a ret)' rUIlI..:liullS of th e equipment?

COllllllcIIIs (A ddilioll,,1 p"g es Ill"), be "dded " s I1ccessm,),) "I'n l ual e cl hy: Di/eep Ciler/opalle C. " . t:i \ \!U> " ell e R e Mi c ilael Woc/arev/( f/I"/,,rtfj.

Y[8) NO UO Onlc: 10/13/2014 10/13/2 014 8-17 Seismic Walkdowll Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 3 of 3 Status: y[gJ NO uO .... ____ Equip. C la ss' (101 Air Handl ers Equipmcllt It) No. Equipmcllt Dcscription 8-18 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Shee t 1 of 3 . Status: NO uO Seismic Walkdown Checklist (SWC) *** 1-----Equip. C la ss' (181 Instruments on Racks EquipmcntlD No. Bquipment Description Location:

Bld g. __ rlonr EI. __ R oo m , A rea _1------------

M an ufa c tur e r , Model , Etc. (o p t ion a l hut re colll m e nd e d) Jllstructioll s l iu' COlllllletillg C hecklist This checklist ma), be u sed t o do c ument th e r es nit s of the Se i s mi c Wnlkclown or an item or eq uipment o n (h e SWEL. The s p oce below eac h of the following qnestions ma), be u se d 1 0 re cor d th e results of judgments and Iintiing s. Additional s p ace is provid e d AI (h e end of this c he ck li s t for d oc lIm e nting o th er cOlllment s. Allchorngc I. I s th e IInehornge co nfi g urati on verifi ca tion requir ed (i.e., is th e item one yo NI8J of th e 50% of SWEL i tems requidn!;

s lI c h veri fi ca ti on),! 2. I s th e anchorngc n*cc of hent , hroken, mi ss in g or l oose h ArdwA r e'! Yt8l NO UO N/AO 3. Is th e anchorage f r ee o i" co r ros ionthat i s mor e than mild sud" ce Yt8l NO UO N/AO oxidation?

'I. I s th e anchomgc f r ee of visible cracks ill th e co n c rctc neM th e allchors? Yt8l NO UO N/AO Minor s urfa ce cracks n ear 2 o f 1110 3 b o llom ancliors are acceptable.

S. I s the a n c horng e co nfi g urati on consi s tent wi1h pl a nt do cu menta1i on? yo NO UO NI At8l (Note: This qnestion o nl y applie s iflhe it em i s O lle of the 5 0% for whi c h a n anchorage cOll li g urali oll vCl'ili cH ti oll i s r eq ui red,) 6. nas e d 011 1h e "bol'e anchorage eva lunti" n" i s the an c h o rage f r ee of Y I8J NO UO potenlially adve r s e st!is ml c comlilions'?

-_ ... _--_. __ ._----I En l er e q uipm e nt cl oss n Llme r rnm I\pp c n tiix R: C l llSSCS or E q llipmcnt.

8-19 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated S h ee t 2 01'3 S t a lu s: y0 N O uO S eismic Walkdown Ch e cklist (SWC) E qllipll1 c lIl 10 No. ___ E qll i p. C la ss' (1 8) In slr um e nls o n Rac k s E qll i pll1 c nl Descr ipli o n IlIl c ra c li o ll Eff e cl s 7. Ar e soft 1 m-ge l s fi*ce fm lll ill1pa c ll>y n ea rb y e qlliplll e ni o r s l r ll c lur es? YI2l NO UO N/A O W a ll (way a n e l (r a m e p rotec t e qui p m e nt (rom i nt erac ti ons o v e rh ea d. R. A r c o ve rll em l cqllipll1 e n l. di s iribllii o n sys l e ll1 s , ce ilin g lil es a nd li g il l in g , Y I2l N O U O N/AO and 1111"0 111), b l ock w a ll s 11 0 1 lik e l), 1 0 co llap se 0 111 0 Ill e eq"ip"l e lll'l 9. Do a lla c ll e d lili es lI a v e ,"l e qll" l c n cs ibilil), 1 0 a vo i d d" lII age? YI2l N O lJO N/AO 10. Il" se d o nili c ab ove seis llli c inl e l"ll c l ion el'"lI la li o n s, is e qlliplll en i l i*ce YI2l NO U O o r po t e nt i al ly a dv erse sc i s m i c ilil crac ti ol l c lr ce l s'? Olh e l" Adl'cl*se CO llIlHions II. Il ave ),O ll l oo k e d l or a nd 1 0 1lnd n o ni li er se i s llli c eo no i l io n s tll a l eO lll d ad ve r se l), a rr ee l Ill e sn r C I), lilll e l i o ns o f th e e qll iplll e nt'/ C Ollllll c ni s (A dd i ti o n ill pa ges Ill ay h e lid d e d a s ncccs s ury) YI2l NO UO El'a lll a l e d b y: D il eoI' e l lerlopallo

c. *v* Da l e: 1011312 01 4 l IM IT ,,!

Mic h ae l W oe l arc.Y..!'/{ _______ " tI _________ _ 1 011312014 B-20 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report. Updated Sh e et 3 o r 3 Statu s: yl8l NO uO Equiplll e nt jj) N o. Equ ip. C la ss' (18) In s trument s on Ra c ks i--:c N:-O"-I('-' ----------------------------Notr, --------8-21 Prairie Island Nuclear Generat i ng Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet I of 3 Status: Y\8J NO uO Seismic Walkdown Checklist (SWC) Equipment to No. *** L. _____ Equip. Class' (18) in.§lrlllnellts Oil Racks Equipment Location:

Dldg. ___ . Floor TIl. a-.-Room, Area Manufacturer, Model, Etc. (optional but recommended) instrnctions 101' Completing Checldist Thi s chccklist may be used to document the results of the Seismic Wolkdown of an item of equipment on the S\VEL. The spoec heloll' each of the following quost ion s may be used to record the resulis of judgments and findings.

Addilioual space is provided at the end ofthi, checklist for do c nmenting other comments.

Anchomgc I. Is the anchornge configuration verificntion rcquired (i.e., is the item one yo Nt8l orlhe 50% orSWEL items requiring s uch vcrificntion),/

2. Is the nnchoruge free of bent, broken , missing 01' loose hnrdwnre?

yt8l NO lJO N/AO ]. Is the nnchontge free ofcol'I'osiunthnt is more thon mild slIIfaee Yt8l NO lJO N/AO Qxidatiol}?

4. Is Ihe anchorage Ii'ce ofvisiblc cmcks inlhc concrete ncar Ihe anchors? Yt8l NO lJO N/AO 5. Is Ihc wlchol'ftgc cont1guralioll consi s tent with planl do c umentation'!

yo NO UO N/At8l (Note: This qu es tion onl)' applies iflhc item i s Ol1e ofthc 50% for which nn Anchorage configuration verificntion is required.)

6. Bascd onth" nbol'c nnchol'l1ge ol'>1lul\tions, is tho anchorage fi'ee of Yl8J NO lJO potentially adverse sei s mic conditions?

I Enler Ihe equipment clnss 1\i11l1e from Appendix 13: Cln s!i l!s of Equipment.

6-22 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated She e t 2 o f3 Status: y{gj NO uO Seismic Walkdown Checklist (SWC) Eq llipm c lIl If) No. Eqllipmcn l De sc riplion In/emelion

!cffeets Eqllip. In st rum e nts o n Racl (s 7. Are s oflulI'ge l s rree li'om impa c i by ncarby eqllipmen l o r sl rlleilir es? YI81 NO UO N/AO R. Ar c ol'er h e ad o qllipm e lll , di s iriblilillll sys l c m s, ec ilill g lile s and li g hling, YI81 NO lJO N/A O a nd ma so nr y hl oc k wall s 11 0 1 li kely 1 0 co llap se o nl o Ih e eqllipmenl?

9. [)o at ta c h ed lin cs hal'e adeqllat e Ile"ibility 10 al'oid dnmage? YI81 N O UO N/AO Instrum e nt lin es nnd lI exi l)l e co n c luit s are acceptable. 10. !:la se d o n th e "bol'e sc ismi e inl crae lion el'allialiol1 s, i s eql1 ipm e nt Ii'eo YI81 NO UO o f p O l e n Ii a ll y adver se s eismic inl ernelion e fleci s? OIlier Adv e r,e C o",lilions I I. I-Iav c YOIl l oo ked f o r n nd f O lll1d 110 o lh e r se i s mi c eOlldi li ons Ihal conld IIdversely "rfecllhe s nlel), li lll ct ion s or Ih e equipmenl?

CfIIl1nH'Jlts (Aclcliliona l p ages lIlil)' b e ndded C1 S II cccssnry)

Y I81 NO UO Eva Ili ale d b y: Di/eep C ll e rlo p"'a"'" e"--_-" c."".;.* ",V.c.* p",',-,"'t.UICii'-'X

.>., Dale: 1 0114120 14 Micllael Wac/Elley/(

10//4/20 14 8-23 Seismic Walkclowil Checklist (SWC) E quipmeni ID No. Noto: Prairie Island Nuclear Generating Plant -Un it 1 Seismic Walkdown Submittal Report , Updated S he e t 30 f 3 S tatu s: NO uO E qnip. C la ss' (18) Ills/rum e lli s 011 R ae/(s Note: 6-24 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 1 of3 Status: NO uO Equip m e ntlD No, Equip. Class' (18) Inslrumani s on Racks -------Eq uipm e nt Loention:

Aldg. ____ Ploor EI. Mnnufacturer, Model, Etc. (optional but r ecommended)

Instructions 1'01' Completing ChecJdist T his checkl i st may be used to document Ihe re sults ofthc Se i smic Wnlkdown ofnn item of equipment o nlh e SWEL. The space below each of the Jbllowil1g questions may be u sed 10 record Ihe resuits of judgmenls and findings.

Addilional space is provided at Ih e end of thi s check ii sl for documenting othe r COlllments.

Anchol'age I. Is Ihe "nchornge eonfiglll'niion verifiealion required (i.e., i s the item o n o yo NI8I oflhe 50% ofSWEL item s requiring suc h verification)?


2. Is Ih e anchorage fiec or bent , hrnken, mi"ing or loose hnrdware?

YI8I NO UD N/A D 3. Is Ih e an c horage li'ee of corros i on thai is mOle lI",n mild surfnce YI8I NO NI AD oxidation'!

4. Is Ihe anchorage free or vi s ible cracks in th e concrete near Ih e anchors? YI8I NO UO N/AD Minor s urface cracks near 2 of 1I1e 3 bollom anci10rs are acceptable.
5. Is Ih e anchorage configuralioll consisten t with plant documenlalion?

yo NO UD N/AI8I (Note: This qucslion on l y applics ifth c itelll i s one of the 50% for which nn anc h orage configuration verificntion i s required.) 6. flased o n Ih e above anchomge ev a lu a l ions, is Ihe anehol'Hge Ii*ee of YI8I NO UO potentially ndvcrse se i smic condit i ons? 1 Eiller the CqUiplll C llt closs 1l1\ll1C!

fi'om 13: C lnsses of B-25 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated ShcC l20f 3 Sla lu s: NO uO Seismic Walkclowl1 Checklist (SWC) Equiplllellt II) No. "quip. C ia ,,' (lB) In s lrum en ls o n Ra c ks Equ ipll.e lll De s eri pi i O Il Ilt c l'Ileli"" Effects 7. Arc s o n t o r g e l , r,'ee lI'olll illlpOCI by Il co rb y eq uiplll eill o r sl ru e l u re s? Yl8l N D UD N/AD Wall,way and l rame prot e ct eq u ipme nt from int eractio n s over ll ead. 8. Are ove rl.cod e quiplll e ll l , di s lribuli o ll sys l e lll s, ee ilill g tiles alld li g hl illg , Yl8l N D liD N/AD "lid Illa S OIlI')' blo c k \\,,, 11 5 11 0 1 lik ely 1 0 colla p se 01110 Ih e cq uiplll elll? 9. Do altac h e d lili e s hav e "d e qllal e fl ex ibilil Y 1 0 avoid ,Ialllage?

Yl8l N D liD N/AD 10. ["la s ed 011 lir e above s e i s llli c illieraciioll eva illali olls, i s eq uip llle ill Ii'ee Yl8l N D liD o fp otc ntiall y advers e s e i s mic interaction effe c t s'? Ol hel' """c" s e CO llditions II. Ila ve yo u l o o ked 1'01' ",,,II'o ull d 11 0 o il.e r s e i s mi c cOlldi l ioll S I h al co ul d udver s e l y afli: c l lhe sll l'ely fUll e lioll s of th e equ ipm ell!'? C Ol1l1l1(: llls (Add i tiu llal pll g c s 1lI 1l)' be iHld c d li S n e ces s ary) Eva lu a l ed b y: Di/e e p Cll e r/opalle C . v* ti, \ **

p &e f/6IM/j Mi c h ae/ Woe/arc I< .-={I __ _ Yl8l ND liD ----I)ale: 10/1312014 10/13/2014 8-26 Seismic Walkdowl1 Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated S h ee t 3 or3 S t at u s: vl8] NO uO EquiplIlcllt ID No. __ Eqllip. C la ss' (18) Ill st rum ell t s O il Racks Notl': No t e: '-----------B-27 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Sheet l of3 Status: y(gJ NO uO Seismic Walkdown Checklist (SWC) E quipm en t ID No. __ Equip. C l ass' (02)Lo w Volta ge Sw it c/wear E quipm e nt De sc ripti o n L oca ti o n: Bldg. ___ F l oo r EI. __ R oo m , Area _-------------Mamlt i l c tur c r , M ode l , Etc. (optional but re co mm e nd ed) Instru c tions for Completing Checklist T hi s checkli st m ay b e u sed t o d oc um e nt th e r es ult s o f the Seismic W a lkd olVn of an item of equ ipm e nt on the SWEL, The s pa ce b e l ow each or th e following qu es tion s mn y b e u sed t o record the res ult s of judgment s and findings.

Additional space i s p rov id e d at th e en d of thi s checkli s t lor documcnting ot her c o mm e nt s, Anello.'age I. I s the anchorage configuration ve rifi catio n requir e d (I.e" i s th e it e m one y o NI8l of th e 50% of S W E L it e m s r e quirin g s u c h vcr ifi eat ion)? 2. I s thc a n c h orage free of bent , broke n , mi ss ing or l oose ha rdware? YI8l NO UO N/AO 3. I s the anchorage f'r ee of corro s i o n th at i s m ore than mild s urfa ce YI8l NO UO N/A O oxi dati o n? 'I. I s th e anchorage f'rce o f'v i s iblc cl'I1cks in th e concrete near the a n c h ors? YI8l NO UO N/AO 5. I s the anc h orage co nl'iguration co n s i s tent with plant documentation?

yo NO UO N/AI8l (Note: This qu es ti on o nl y a ppli es if the it em is o n e of th e 50% for which an an c h o r age cO llfi g tll'n li o n ve rifi c ation i s re Cluired.) 6. Base d o n th e above anchorage eva luati o n s, i s the a n cho r age free of YI8l NO UO p o t e ntiall y adverse se i s mi c coneiitions?

I Ellh: r th e CC]UiPlll l.: lll c l ass II tlmc rr olll A P PClldi ,\" 0: of Eq t lip11lcn l. 8-28 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 20f3 Status: NO uO Seismic Walkdown Checklist (SWC) -Equ ipm e nt ID No. I: q uipm e nt De sc ripti o n Eq uip. C ia ,,' (02/Low Vol/age Sw it c hg ear I nfcl'actioll Effects 7. Arc s on tar ge l s I ke fr o m impa c t by n ea rb y e qnipm c nt or s tru ct nr es? Y I8l NO UO N/AO R. Arc ove rh cn d equipm e nl , di s trihntion sys t e m s, ceiling til es and li g htin g, YI8l NO LID N/AO [lmllll:I SO I1I), hlo c k wn ll s nOI lik e l y t o co ll:lJl se onlo th e C qUiptll C III'! 9. D o attached lili es hav e ad e qLlat e fl ex ibili ty t o avoid dnnHl ge? Y I8l NO UO N/A O Flexible co n c lLl i l illi o t o p o ( Bu s 112 i s accep t able. 10. n" s ed on th e "h nve sei s mi c illi ern e tioll e v"lunti o n s, i s eq Lliplll e nl fre e YI8l NO li D o rp olcll liall y ndvcr sc se i s mi c intera c ti o n e ff ec t s? Other Adverse C"",litiulI s II. Iln" e yo u l ook e d "11' and r O llnd 11 0 ot h e r sc i s l1li c ellllciilioll s that eO llld adver se l y an cc t Ih e sn l e l y Iim e li o l1 s or lh e c qLlipm c LlI'! Min or g ro ut cracks in siele ca bin et 112-4 n o t a ssoc ia te el Ivill) anc hora ge of /Ju s. CO IllJllCllf s (A dditi o llal pa ge!) ma y b e add e d n s Il Cl:CSsil r y) Int e rn a l in spec ti on perform eel. N o conce rn s n ote el internally. YI8l NO UO r: 1':1 I U'I t cd b y: fu",le c.<I", (,.!>*i e", s",e!-1

_____ -Da t c: 1012012014 Dil eep C h erlo Ja ll e 1012012014 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated Sh ee t 3 of3 Status: NO uO E quiplll ent ID No. ___ Eq uip. C l ass' (02JL ow Vol/age Sw il c/lQ ear 8-30 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 1 of3 Status: Y!8l NO uO Seismic Walkdown Checklist (SWC) Equipment ID No. ___ Equip. Class' (03) Medium Voltage Swilcllgear Equipment Description Location:

Bldg. ___ 1'1001' EI. ___ Room , Arca ________ _ Manufacturer , Model, Etc. (optional but r eco lllmended)

Instruction.

for Com plcting Chccldist This checklist may be u sed to document the re su lt s of th e Seismic Walkd ow n of an item ofeqllipment on th e SWEL. The s pace below each of the f o llowing questions may b e II se d to rec o rd the reslIlts ofjudgmcnts and IIndings.

Additi ona l space is provided at the end of thi s checklist for documenting other comments.

Anchorage I. I s the auchoragc co nfiguration verification required (i.e., i s the item one yo N[8I of th e 50% ofSWEL item s requiring s u c h verification)?

2. I s th e anchorngc fr ee of b e nt, br oke n, missing or l oose hardwar e? Y[8I NO UO N/AO 3. I s thc anchorage li-ec o f co rr os i o n that i s m o r e than mild Su r/-'lce Y[8I NO UO N/AO ox id a tion? 4. I s th e anchorage li'Cc of visible cracks in the concrete ncar th e anchors? yo NO UO N/A[8I Weld ed 10 em b edde d s le e l. Minor sllri nkage cracks in floor with no impact. S. I s th e anchorage configuration co nsi s tent with plant documentation? (Note: This qu es tion only applies if the it em i s one ofthc 50% for which an nnchornge configlJl'ntioll verification is required.)
6. Ba sed 011 th e above anchorage evaluations, is the Hilchomge rrcc of p ote ntially advcrse se i s mic conditions?

I Enlel' the cqllipll1Cllt clus s /lalil e from App c lldi;-; IJ: C l a sse s yo NO UO N/A[8I Y[8I NO UO 6-31 Prairie Island Nuclear Generating Plant-Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 2 o f 3 Sta tu s: yr:g] N O uO Seismic Walkdown Checklist (SWC) Eq uipm e nl ID No. Eq uipm e nt Description

  • Equip. C l ass' (03) Medium Voltage Switchgear

-InterHction E ffects 7. Are so n [(ll'gc ts fr ee Ii'o m imp act b y n cn ru y equipment 0 1' struc ture s? YI8J NO UO NIAO 8. Are overhead e quipmenl , di s lribuli o n sys l e m s, ce ilin g lil es and li g hlin g, YI8J NO UO NIAO and ma somy block \Vall s n o l likel y 10 co llap se ont o the e quipm en t? 9. Do attached lin es h nvc ndcqufll c ncxibilily to avoid d<1l11a g e? YI8J NO UO NIAO 10. !la se d o nlh e above se i s mic inl e ra clio n eva lualion s , is eq uipm eo l Ii'ec or polent iall y adverse sc i s l1l i c int e rH c ti on e ffe c t s? Olher Allver,c C ()JI(Ii1iolls YI8J NO UO I I. I-lave YO LI lo o k ed for and l el Ulllln() nlher se isilli c cO lldili ons IIHlI co uld YI8J NO LJO adversely afTcel the sa rely runclinns n("th" equipmenl? Small screw missing on insulafor cap in bae/! of breaker 15-1. No impaci from lighl plaslic cover. AR 01452052 ane! WR 00107989 were generaleLi.

COllllllClifs (Additional page s 111<1)' be add ed <I S n ecess ar y) Infernal inspeclions performee!.

Eva lu a I c d by:

"":i;'!:. -=---7' Da I e: "/0/20/201" Dilee{) C/lello{)alle

"/0/2012014 6-32 Seismic Walkdown Checklist (SWC) E quip", c n t II) No. _1!': qll iP"'Clil De s e ri pI i O ll Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Subm i ttal Report, Updated Shec l 30f3 S l at u s: NO uO ECJu ip. C la ss' (03) Medium Voltage Switc h gear 8-33 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo wn Submittal Report , Updated Sh eet lof3 Status: y[gJ NO uO Seismic Walkdown Checklist (SWC) Equipment ID N o. Equip. Class'-1Q1J

_EM d-Operated V'!/"'ve"'s'--________ . Equipmenl D ese l'iption Location:

Bld g. __ Floor E I.

  • __ Ro o m , Area _---.-------Manufa ct urer , Model, Elc. (oplional bu l rec o mm e nd e d) Jllstl'lIetiollS for Completillg Cheeldist This c h eck I istlllay be u see l 1 0 do c ument the r es ult s of Ihe Se i s mic Walkdo\\,l1 of a ll ilem of eq uipment on Ih e SWEL. The space below cneh of the following questions mny be u scd to re co rd ihe re su lts o fjudgm c nts ond fin din gs. Additional space is prov ide d 01 th e end of thi s checklist fOI" d oc umenting o th e r commenls.

Anchorage I. I s th e anchorage co nfiguration verification requi rc d (i.e., i s Ihc it e m olle YO NI8l oflhe 5 0% ofSWEL il e lll s r e quiring s uch verificntion)'1

2. I s the free of ben I, broken, mi ss in g or l oose h a rdwnre? yo NO UO N/AI8l 3. I s the Anchorage fre e of co rro s ion that i s m ore thnnmi l" s urra ce yo NO UO N/AI8l oxidation?
4. Is th e nnchol'age free ofvisiblc cracks i n thc co n c r et e ncnr th e nnehors? yo NO DO NI A 181 5. Is th e onehomgc co nfigul'fltion co n s istcnt with pl ant d oc ument a ti o n? YO NO uo N/AI8l (Note: This que s ti o n only applies irthe item i s o ne orlhe 50% r (,,' which nn anchorage

<.: o nfi g untti o ll ve rifi ca t io n i s r e quir e d.) 6. nosed 0 11 th e obovc allchorngc eva luation s, i s the unehornge fr ee of YI8l NO U O p o tentially adverse seismi c condilions?

I En lel' th e l'qn iJ)l ll cnl c la ss 11:11ll C frOiIl Appendix 13: C l nsscs 8-34 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Seismic Walkdown Checklist (SWC) Sh ee l20f 3 Stnlus: ND uD EquiplIl e nl If) N o. ___ Equip. C la ss' 1071 Fluid-O pera/e e l Valve s Equipllleni Intel'actioll E ffe c ts 7. Arc so n lar gels r,'cc li'O m ililp aci by n c arby eq uipm" nl or s lru c lur es'! Y(gJ NO UO N/AO N. Arc over h cad cqlli plll c nl , di s tribulion s y s lelll s , ceilin g lil es a nd li g hlin g, Y(gJ NO LI D N/AO ane/illa so nry hloek wall s 1101 lik ely 10 co llap s e onlo Ih e equipmenl?

9. Do allaehed lin es hav e a d e qlla t e flexibililY 10 avoid dalila ge? Y(gJ NO LI D N/AO 10. nased on Ihe above se i s illi c inlera c ti o ll eva illalion s , i s cqllipmenl li'ec Y(gJ N O LJO ol'polentially adver se se i s m ic int erac ti o n e ffe c t s? Othel' Advel'se C onditions I I. Iinve ),"" l ooked for alill (("",dn o o lh er sc i s mi c co ndi lio n s 'hal cO lild ud vcr se l y a rlc e l 'h e s a liJI)' I\lIl el iOll s 0 r I h e e(1 u i pmcII!'1 (A t idililill ul p ages ilia), oe ad d e d a s I1 c<.: c.: s s ar y) Evalnaled by: Dile e!) C her/c!)B ll e c.v , b l\""?¥.', ""...cQ
  • I/("/"."!

Mi c ha el Wodar ey/( {/ Y(gJ N O LJO Dale: 10/1 3120 14 10/1312 014 8-35 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheel of3 Slalus: y[gJ NO uO Eqll iplll c lll I D No. __ Eqll ip. C ln ss'_(07 L) L F"'llI"'id"'-"'O,p ,,"'er"'a""le<;d!...,!CVa""""vee,s'---

_______ _ 8-36 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 1 of 3 Status: NO uO Seismic Walkdown Checklist (SWC) Eq uipment ID No. __ E quip. C la ss' (01! Motor Control Centers Eq uipment Description Location:

B l dg. __ r l oo r 13 1. ___ Room, Area _-----------Manufacturcr, Model, Etc. (opt i o n"1 but rc commcmlcd)

IlIslo'lIetiolls lill' Co mpleting C h ec klist This c h ecklist may be u sed t o documcnt the resuits o f the Seis mi c Walkdown of an item of equipme nt on th e SWEL. The s p ace below each of the fOllowing que s tions may be u sed to record th e resuits of judgme nt s and findings. Addi ti o n a l space is provided a t the e nd of thi s check li st for documenting ot h er com m ents. Anchol'ngc I. I s th e anchorage co nfi g uration ve rifi cation r eq uir ed (i.e., is th e item o n e yo NIZI of the 50% ofSWEL items requiring s u ch verification)?

2. I s the anc h omge free of bent, brokcn , mi ss in g 01' l oose h ardwarc? YIZI NO U O N/A O 3. I s the anc h orage free of cor r os i o n that i s m ore than mil d s n rfaee YIZI NO UO N/AO oxidat i o n'? 4. I s the anchllmge free oFvisihle cr!lcks inlhe co n c ret e ncar the anc h ors? YIZI NO lIO N/AO 5. Is the anc h ol'Hge configuratio n consis t ent with plant documentmion

? yo NO U O N/AIZI (Nole: This q u es ti on only applie s if th e it em is one oflhe 50% for w hi c h an flllc h orage co n figu r at i on verification i s r CC)llir ccl.) 6.

on the above anc h orage i s th e anchorage free of YIZI NO UO potcnliall y adve r se se ismi c condi l ions? I Enter th c eq uipm c nt c l a s s n: lI11 C rrom Appendix D: C la ss t.: s of Eqllipment.

B-37 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Shecl20f3 S L atus: NO uO Seismic Walkdown Checklist (SWC) E'I" ipm ell l ID N o. Equipmenl De se ripli,," Interaction Effect s E quip. C l a s s' (01) Motor Con t ro l Centers 7. Ar c so il la rge l s Ii'ce li'Ulu ill1pacl b y I1carb y equipmc l1l o r sl ru c lur es? YI8J NO UO N/AO H. Are ove rh ea d e quipm e nl , di s lribuli on sys len", ce ilin g lil es andli g hlil1 g , YI8J NO UO N/AO :Jllllm:J s o llr y b l ock ",a il s 1101 likel y 10 co llap se 0 111 0 Ihe eq uipm c l1t? 9. Do attached lil1 cs hav e ad e qual e llexihililY 10 avoid dama ge? YI8J NO UO N/A O 10. Ba se d o l1lh e above sc i s mic inl e nt e li o n ev aluali o n s , i s eq uipm e n l i're e YI8J NO UO 0 1' pol e nt iall y ad verse se i s lll i c i nlcrn e l i O Il effe c t s'? Other Adverse Co ndilions I I. IllI ve ),0 11 l oo k e cll or an d f o und no olh c r se i s mi c co ndilion s lhat co uld :ldvcrsely

iI"i ec llh c sa l e l y l i lli c ii o n s orlhe cq l1ipm e l1l'! C omlllent s (Ad d i l io lH" p ag es llIay b e ad d e d a s n e ce s sn r y) No internal M CC in spec ti on was pe/f o rmecl per NRC s ul)mill a l. YI8J NO L I O Eva lual e d b y:

____ Dal e: 09/1712011 f5y1e <<riesel 09/1 7 12014 8-38 Seismic Wa l kdown Check li st (SWC) E quipm e nt I I) No. Equi pm e nt D esc r i pt i o n N ufc: Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated Shecl3 of 3 Stntu s: y[g] NO uO E quip. C l ass' 1011 M o tor Co n/ro f Cent ers ,------8-39 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated Sheell of 3 Status: yt:gJ NO uO Seismic Walkdown Checklist (SWC) Equipmcnt ID No , __ Equip, C la ss' (01) Motor Control Centers Equipment Description L oca tion: I3ldg, __ rloor E I. __ Manufacturer , Mod e l, Etc, (optional but r ec OJi1ll1cmlcd)

Instl'lIctions f(u' Completing Checltlist Thi s checklist ma y he u se d to document the re s ult s of th e Se i s mi c Walkdown oran item of eq uipm e nt o n th e SWEL. The s pa ce below each of th e following qnestion s mal' be nsed 10 record Ih e r es ull s orjndg",enls and finding s, Additional s pa ce is provid ed at th e end of thi s checklist for do c um e ntin g other comments, AnchoJ'agc I , I s the anchorage configuration verific*ationrequired (Le" is the item o ne YI:ii:I ND of the 50% or SWEL it e ms r e qniring s uch verification)?

2, I s th e anchorage rree of bent, broken, mi ssi n g 01' loo se hardware? YI:ii:I ND UD NI AD TiJ ere a re six 112" SIJieid expansion anchors (see ske t c h below), 20" 3, I s the anchorage rree o r corrosion that i s more than mild s urfa ce YI:ii:I ND lJD N/AD oxidation?

", I s the anchorage rree or visible cracks in the co n cre t e neal' the anchors? YI:ii:I ND UD NI AD 5, I s th e anchorage co nfi g llration consistellt with pimlt d oc um e nt at i o n? YI:ii:I N D LID N/AD (N ote: This que st i o n only appli es iFthc item i s one o r the 50% ror which an anchorage co nfigurati o n verification i s required,)

Verified against SQ UG A46 SEWS, 6, Bascd o n the above a n c h orage ev aluHti ons , i s th e flnchomgc Ii'eo of YI:ii:I ND LID potentially se i s mic conditions?

I E nt er th e equ ipm ent cla ss !lame from Ar p cndi.\: 13: C la s s es of Eqllipml!IIL 8-40 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated She e t 2 o r 3 Statu s: NO uO Seismic Walkdown Checklist (SWC) E quipl11 e nl ID No. ___ E quip. C la ss' (01) Motor Con trot Ce nt ers Eq uiplll e ni D esc ripti o n Inte .... etion Erreds 7. Arc s urt lar ge t s (j'C" rrol11 imp ac t b y n e arb y eq uipm e nt or s iru c ture s? YI8I NO UO NfAO E x h aust (an i s near i nc oming co n(/uit s bu t ro (/ hung fan i s l aterally braced. II is not a seism i c co n cern. 8. Ar c ov erh ea d eq uipm en t , di s tribut io n sys tem s , ce ilin g til es and li g htin g , YI8I NO UO N/AO a nd 1l1 aso nr y blo c k ",a il s not lik e l y t o co llap se o nt o th e e quipm e nt'! 9. D o allacheel lin cs h ave adequat c Il cx ibility 1 0 av oid dam age'! Y I8I NO I JO N/A O Th e y a r e draped from cab l e tray. 10. U nse e! 011 th e nbovc seis mi c int e ra c ti o n cvn lua l i o n s , i s c qllipm c nl fr ce Yl8l NO UD o rp o t c illinll y a d verse se i s llli c int e ra ct i o n effec t s? Other Ad"e!'se C ondition s II. 1*la l'e ),o u l ooke d r o r and ro und n o o ther s e i s 1l1i c co ndi t i o n s tha t co uld ad verse l y I1ITccllh e s af ety r Ull c ti o n s o rth c equ ipm e nt'? Two m e t al clips w e re f o u nel in b ase of MCC (Celt C6, ce ll B5 anel ce lt A5). Til e (oreignma t eriat in Me C 1AB2 ba se i s a l lOuse l (eep in g i ss u e all(/ do es not impa c t the equipmen t. CAP 1352515 was initi a t e ci t o (/ocumen t thi s o b se l vation. WR 83705 was a t so initi ateel t o a(/elress th is issue. Co mllient s (Additi o nal p age s 111:1)' b e add e d CIS Il cc(.'s s nr y) No i nt e rn al M CC inspec t ion was perform eel p e r NR C s u lJmi ll a i. " v a lual e d b y: ""1<-"v l""o,L I<", n",*e,,,soe!.* '---1"7 J!/LL"'-;,A&=0iZ""'-_.c.2'---

______ _ -Dileep C il e li opa tf e Y I8I NO UO I)"t e: 0 9/2'//20 11 091241201" B-41

-Seismic Walkdown Checklist (SWC) Prairie I sland Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report. Updated Shecl30r3 S tatu s: Y!2J NO uO E quiplllcullD No. __ E quip. (01) Motor C ontrol Cen t ers "'1uiplllcnl D esc riplion N oll': N ul,*: B-42 Prairie Is l and Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 1 of 3 Status: yrgJ NO uD Seismic Walkdown Checklist (SWC) Equipment ID No. __ Equip. C lass' (Ot) Motor Control Centers Equipment Description Location:

Bld g. ___ rloor E I. Manufacturer, Model , Etc. (optional but r eco mmended) Instructions for Completing Chccklist This checklist ma y be u se d to d oc um e nt th e re s ult s of th e Seismic Walk"own ofn n item orequipmcnt o n the SWEL. The splice below each or the following qu es tions mny bc used t o record the re s ult s ofjudglllents and findin gs. Additional s pa ce i s provided at the end of this checklist for d oc umenting other comments.

Anchorngc I. I s the anchorage coniigul'Htion verifieationrequircd (i.e., is lh e it e m one yt81 NO of t he 50% o rSWEL it c m s requiring s u c h verilication)?

2. I s th e nnchol'Hge free or b ent, broken , mi ss ing 01' l oose hardwllr e? yt81 NO UO Nt AO 3. I s the anchorage rree of co rro s ion thaI is m o re than mild s urfac e yt81 NO UO NtAO oxidation?
4. I s the anchorage li'ec of vi s ibl e cracks in the concrete ncar th e anchors? yt81 NO UO Nt AO There is a sllrinkage crack in tile comer below_ TlJis is not a seismic concern. Plant engineering evaluated tlJi s condition using tile guidelinss in the Structures Monitoring program. It was concluded that since the n o tic ed cracles are within til e allowable widlll (less lllan 0.4 mm in width), no CAP or WR needs to be initiated at this time. Chip on SE comer of equipment paclnot near a n c horag e. 5. I s th e anchorage configuration co n s i s tent with plant do c lIm enta ti o n'? (Nole: This question only applies if'the item i s one o r th e 50% ror which HII anchorage configuration vel'ificHtion is required,)

2*112" diameter J-b ofts as per c ub ic l e shown on drawing NF-38313-1 and NF-38312-2.

6. Based all the above anchorage evaluations, is the anchorage free of p o t ent ially adverse seis mi c conditions?

I Elllt'r Ih e c l a ss nalll C 1'1'(1111 A pl'c mli x 13: C Ii1 sS C S orEquipm c nl. yt81 NO UO NtAO yt81 NO UO B-43 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Shee l 2 of 3 Status: yr:g] NO uO Seismic Walkdown Checklist (SWC) Eq uipm e nt 10 No. _,I O quipment Description IlIlel'I1clioll Ef fecl s Equip. C la ss' (01) Molar Con lrol Cen l ers 7: A r c so ft lar gc t s /i'ee fr o m imp act by n ca rb y equ ipm e nt o r sl ru ct ur es'! YI8I NO UO N/AO 8. Are over h ea d e quipm en t , di s tribnti o n sys t e m s, ce ilin g til es Hlld li g htin g , YI8I NO UO N/AO ""dma so my blo c k walls n o t lik e l y t o co ll a p se o nto the eq uip,ucllt? 9. 0 0 a tta c h e d lilie s have mlequnte n exibility t o nvoid dnma gc'/ YI8I NO UO N/AO 10. Based 0 11 th e above seis mi c illt erac ti o n cVil lu n li u ll s, i s e quipm e nt ('rc e y t8j NO UD u f'putentially m lv erse se ismic inten.lcliull e ff ec t s? Olioel' A.lvel'se C Ollllilioll S II. Ila ve YO Il l ooke d ror nnd r O llnd Ilootioer sc i S llli e co n dit ion s th n t co uld ne l ve r se l y nrrect th e s arety i"lm ct ion s "ft h e eq lliplll e nl? YI8I NO UO C OJlllllent s (Addi li(JI1iI1 pa ges lIla y b r.: added a s I1 ccC'ssm)') '/. A l oose screw in Ille bollom secl i o ll below cubicle cell C4 was fOllllel , as was so m e elllc i lape. CAP 1352344 I, as beell illitialed 1 0 evaluale Ihis obselValioll. WR 83647 allel WR 83648 h ave also beell illilialed 10 add r ess Ihi s obse l val i on. 2. Olle side of the MCC i s mi ss ill g pla s tic illselts. CAP '1 352415 and WR 83670 have beell illilialed 1 0 addre ss Ihis obse l valioll. 3. No illiemal MCC ill s pe c tioll was "erfonned per NRC su b mi ll a l. Ill ateci h)': !.: 1<"VLSle"'I"<u.rie ,,,s.., e"-I ___

__ ;)-_______ Dat e:

OWN/l OU D il eep \).=,' e f4> , ,, ... II 91l 4/2 0 1*1 B-44 Seismic W a lkdown Checklist (S WC) F.q ll i plll C IlI I D No. De sc ripti o ll los N Ol e: Prairie Island Nuclear Generating Plant -Un it 1 S e i smic Wal k do w n Submittal Report , Updated S h e et 3 0 1'3 S t at u s: NO uO E qllip. C l a ss' (0'11 Mo t or Contro l Ce nt ers N ol e: 845 Prairie Island Nuclear Generat i ng Plant -Unit 1 Seismic Walkdo wn Submittal Report. Updated S h ee t 1 o f 3 S t a lu s: NO uO Seismic Walkdown Checklist (SWC) E quipm c nt ID N o. __ E quip. C la ss' (01) Mot o r Control C e nt e rs E quipm e n t Descrip l io n Loca ti o n: B l dg. ___ F l oo r E I.

  • __ Roo m. Ar ea _------------M a nu rnc lur c r. M o d el. E l c. (o p t i o nal but r e c o mm e nd e d) IlIstructiollS fol' C Olllpleting C heckli s t This c h ec kli st m ay be u sed t o d oc um e nt th e r es ult s o f th e Se i s mi c W a l k d ow n o ran it e m o r e qnipm e nt o n th e S W E L. Th e s p ace h e l o\\' eac h o rlh e followin g qu es ti o n s may b e u se d 1 0 re cor d Ih e r es ult s of jud g m e nt s a nd findin gs. A ddi l i o nal s p ace i s pr ovi ded a t thc e u d or thi , c h ec kli st f or d oc um e nting o th e r co mm c nt s. Anchorag e I. I s t he a n c h orage co nfi g urali o n ve rifi ca ti o n req uir e d (i.e., i s th e it e m o n e YI:8I NO o f th e 50% of S W E I , i l e m s r e quiring s u c h veri fi ca ti o n)? 2. I s the a n c h orage fr ee or b e nt , brok e n , mi ssi ng or l oose h a rd wa r e? . YI:8I NO UO N I AD One o f ti le tw o a n clJO r s und e r th e _ i s r e l oca t e d to th e ed g e of th e ce ll f ro m th e m iddle. Th e r ea r a n c"/i0r7Sa diff e rent k i nd tl la n th e typ ica l a n c h o r s for th e M CG. Th e ce ll in q u es ti on (A4) is i n th e mi dd le o f th e M CC, th e r e f o r e th e MCC's ab ilit y t o res i s t se i s mic o v e/1urnin g i s n o t a ff ec ted. C AP 1 352 9 27 w as w rit/en t o id e ntif y tile c l/a nge a n d WR 83781 w as i ssued. SQ U G S EW S eva luat es til e M CC a n cllo r age accep t a bl e w illI o nly 5 a n c ll ors in 3 ca b i n e t s t o acco unt f or th e n o t ed an c ll o r d e fi c i e n cy. 3. I s the a n c h o r age fr ee of co r ros i o n th a i i s m o re Ihan mild s u r f ace Y I:8I N O U O N/AO ox id a ti o n? Til e r e i s mild o xidatio n o n til e a n c ll o r s u nd er_ It i s n o l a se i s mi c conce rn. 4. I s th e an c h o r age fr ee o f v i s ibl e c ra c k s in Ih e co n c r c l e n e al' Ih e a n c h o r s? Y I:8I N O U O NI AD 5. I s th e Iln c h omge co nfi g ul'lIti o n eons i s t e nl lV ith pl a nt d oc um e n ta ti o n? YI:8I NO U O N/A O (No t e: Th is qu estio n o nly a ppli e s i f the i t e m is o n e of th e 50% f or w hi c h n il an c h o r age co nfi g ur a ti o n ve r i fi ca ti on i s r e q u ir e d.) SQ U G S E WS eva lu a t es til e MCC a n c h orage accep t ab l e w itll o nl y 5 anc ll ors in 3 ca bi ne t s to acco unt f or fil e n o t e d a n c/JO r de fi cie n cy. 6. Based o n th e a bove an c h orage eva lu a ti o n s, i s t he a n c h orage fr ec o f Y I:8I N O U O p o t e nt i a ll y adverse s c ism i c co nd it i o n s? I E llt C I' t h e C qUiplllC ll t c l a ss name rrom Ap p e n di x n: C la ss e s of E q uiplll c ll l. 8-46 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Sh e et 2o f3 Stalu s: yrgJ NO uO E'Iuipm e nllD No. ___ r: quip. C la ss' 1011 Motor Gontrot Gen ter s Equipmen l De sc ripli o n Iliferllctioll
7. Arc so rt lar ge l s rree rroln iUlp a" 1 b y n ea rh y O'lUipuloul or sl ru c lur es? YIEI NO UO N/AO 8. A r c ove rh ead equipm e nl , di s lribuli on sys l e m s, ce ilin g lile s allClli g hlin g, YIEI NO UO N/AO and nl<ISO nl), b l ock wa ll s n o l lik e l y 1 0 co ll ap se o nl o Ih e e quipm e nl? 9. Do a lla c hcd line s h ave ade'lu"l e fl ex ihilil y 1 0 "vnid dama ge? Y IEI NO UO N/AO 10. l3a sc d 011 Ih c above seis m ic inl e ra c li o n eva luali ons , i s equ iplll eni rre e YIEI NO UO or p O l e nl in Il l' "dver se sc i sm i c i nlernel i o n e lf ce l s? The piping in s utation i s rol,lclllng t o p of til e M CC. Il ave judgecl Tile in s ulation ensures 1/1 e re i s no I larc l con t act and 1/1 e conduit will no t b e imp ac t ed. Tile piping was add itionally r es t rained LInd er de s ign c han ge 970E02 I Jeca Ll se of tlli s s pe c ific co n ce rn. R e feren ce piping sLl ppOll s 1-0WH-86 amll-0WN-87.

Tlli s i s not a se ismi c concern.

Adverse Cu nditiulls II. I lave yuu l ooke d ror illid f O llnd 110 o th e r sc i s l1I il.: c ond i ti o n s lh ill cou ld ad v cr sc l y alTt.:ct tilt.: s a rel y rUli c tion s o r till': e qu ipl1le llt? C OlUllIClils (A dditi o nal pil ges lII il)' b e ndded a s n ece ss ar y) YIEI NO UO F o r eig n materi a t wa s id en tifi ec l IIn c l e r the _. Btacl< i nsutation abo ut 2" x l" x 6" t o ng i s LInd er 1/1 e_ It is a h O ll se l<eepi ng conce rn, a nd n o t a se i s mi c i ss u e. GAP 1352321 a nd 13 52344 have be e n initi a te cl to e v a lu a t e th is o b serva ti o n. Addi ti onally, WR 836 44 was initiat ed t o ad dr ess 1/1 e I JOusel<eeping conce rn. M a t e ri a llla s si n ce b een r e mov ed. N o in t e rn al M GG in s p ectio n was pedormed per NR C su bmitt a l. Ev alual e d tr y: I(vle Kriese l 2 Oileep Clle rl opa ll e c.".p,l,pp¥q ,.

1)"l c: Dnt c: 0 9/2-//2 111*1 0 9/24/2 11 1-1 8-47 Seismic Walkdown Checklist (SWC) 1-:'1" iplll e lil II) No. Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Sheet 3 of 3 Statu s: NO uO Eqllip. C la ss' 1011 Motor Control Ceil/er s 9-48 Prairie Island Nuclear Generating Plant -Unit 1 Sei smic Walkdo w n Submittal Report , Updated Sheet 1 of3 Status: NO uO Seismic Walkdown Checklist (SWC) Equipment If) No. B quipm en t Description Bq uip. Cia,,' (o1JMoior Conlrol C@"n .. ,"'le....,'s

'---__ Locntion: Bldg. _ 1'1001' EI. __ Room, Arcn ____ --------Mallufactlll'cr, Model, E tc. (optional but recommended)

Ills tructions ful' Completillg C hc c ldist Th i s c h ec kli s t Ill ay be lIscd t o do e llmcnt th e result s o f Ih e Se i s mi c Walkdown o f a n i t e m o r cqu ipment on th e SWEL. The s p nce b elow e a ch o f th e following questions may bc used to r cco rd th e results of jud g m c nt s li nd finding s. Additional s p nce is p rovide d nt th e end of thi , checklist for d oc um e ntin g other comillents.

Anc horage I. I s th e anchorage eonfigurntiOIl vedficntioll r eq uircd (i.e., i s the it em o n e YI8I NO oflhe 5 0% ofS WEL it ems r e quirin g s u c h veriJiention)?

2. Is thc a n c h orage fl'ee of be nt , brok en, mi ss ing or l oose hardware'!

YI8I NO UO N/AO 3. I s the anchorage fre c of cor ro s i o n thnt i s Illor e thau l11i ld s urfa cc YI8I N O UO NI AD oxidation?

4. I s t he n n e h Ol'age free ofvisi"lc crac k s in thc concrete n en r th e nnehor,? YI8I NO UO N/AO 5. I s the nnehomge co nli g u mt ion consis t e nt w ith "Inn t d oc uill e ntati o n? YI8I NO 1JO N/AO (No t e: Thi s Cjuestion on l y applies if t h e it em i s one ort h e 50% f o r which a n >l n c h om!,,,, co n/i g urati o n verification i s r equ ir ed.) Verified (16) 1 12" 0 CEAs per SEWS. 6. na s ed on th e ab ove anc h orage evaluat i o n s, is th e a n c ho rage Ii'ce or YI8I NO UO potenti a li y adverse se i s mi c co ndition s'! 1 Entt.:r tlw 1.'(jlliP!l1C lll clas s 1Ii1ll1l:

from App c nd i ii B:

ofEqui pllI c nt. 6-49 Prairie Island Nuclea r Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Seismic Waikdowil Checkli st (SWC) S h eet 2 of 3 Statu s: NO uO *** IJ-----E quip. C la ss' (01lMolor Con l rol Cen l ers E quipm e nl ID No. E quipm e nl l1e scr ip l i on Inlerne!ioll E ff ee!s 7. Arc son l argels fr ee rl'Om impa e l by u enr b)' equ ip mc n l 01' sl ru c lur es'? YI8l NO 110 N/AO 8. A r e over h e ad e quipm enl , di s lri b ulion sys l e m s, cei lin g lil es and li g hli ng, YI8l NO UO N/AO "nd IIH1 S 0 11l'y b l ock 1I'"lIs n o l lik e ly t o co ll"p se o nt o Ih e eq ui pme nl'! 9. Do ,,"a c li ed l ines Ii ave " d oq ual e n ex i hi lil y 1 0 avo id d"m"go'! 10. Un se e! 0 11 t h e ahove se i s mic int erac ti o n evalua ti o n s, is e quipment rr ee o rp o t c lIliall y a d verse se i s mic int erac t io n ef f ects? Olhel' "elvel'st!

C Ulllliliun s II. I-I ave you l ooke d 1'01' nlll ll'o unel n o olh e r sc i s mi c co nditi o n s Ih al co ul d "elver sc l), " n ccl th e sn rel), I\lnetion s or lli e eq nipm c n t'l C mlllll C llfs (A dditiun a l pages m<ly h e (H Id ed li S necessary)

No inlemal MCC i nspec l ion was peiformec l per NRC s lll!millal. Evalua l e d b y: Diloep Che r/opalle e v.r;, I ** f)(" ,.,,,,d 2 e Mic/Ja e l WodBlcvl< CI YI8l NO UO NlA O Yl8J NO UO YI8l NO tJO 1 0114 12 01"-." __ 1 11 1 1*/1 211 1 4 8-50 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated S h ee t 3 of3 Sta tu s: y[gJ NO uO Eq uip", e llt to No. ___ E quip. e llls s' (01/Motor Con/I'o! Ce nter s Equ ip", e llt Des c ripti o ll 8-51 Prairie Island Nuclear Generating P l ant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Sheel! of 3 Statu s: y0 NO uO Seismic Walkdown Checklist (SWC) Equipment ID No. E quip. C la ss' (161 Battery Chargers and Inverter s i2q uipment Des c rip t i o n Location:

Bldg. ___ Floor 121. __ Room, Area _1-----------Manufacturer, Model, E t c. (optioual but r ecom m e nded) Instl'uctions 101' Completing Checklist Thi s checklist may be u s ed to document Ihe r es ulls o rlhe Seismic WalkdolVn o r a n item of equip men I o n th e SWEL. The s pa ce below each of the foll ow in g questions may b e u se d to record the result s of judgments and findings. Additi o nal space i s provided at the e nd of thi s checkli st r o r do c um e ntin g other comments.

Anchol'age I. I s the anc h orage configuration verification requir e d (i.e., i s the ilem one yo NI8I of the 5 0% o r SWEL items requiring s u c h vcril1cation)?

2. I s the anchorage free of bent , br oken, mi ss in g or lo ose hardwllr e? YI8I N O UO Nt AO 3. I s the anchorage fre e or corros i o n that i s 1II0re thanl11ild s urfa ce YI8I NO UO NlAO ox idati o n? 4. I s the anehOl'age free of visible cracks i n th e concrete neal' th e anchOl's?

YI8I N O UO Nt AO 5. Is the anchorage configuration c o n sis tent with plant documentation?

yo NO UO NtAI8I (Note: This qu est i o n o nly a pplie s ifth e it em i s one of the 50% for \vhich an anchorage configuration verification i s required.)

6. Based o n th e above a n c h orage evaluations, i s th e anchorage free o f YI8I NO LJO potentially adverse se i s mic co nditi o n s? I EllIcr th e eq uipm ent d nss Il ame Ihlll i Appendix H: C la ssc!' or Equipm e llt. 8-52 Se ismic W a lkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated Sheet 2 0 1'3 S t a lu s: N O uO Eq u i pmeut ID N o. __ E qu i p. (161 Battery Cllaraers and In verters E quipm e nt D esc ripti o n Int c l'f ,ction E fI'cci s 7. A r e so n tar ge t s fr ee r,'o m im pac t by n e arh y eq uipm e nt 01' s tru c tur es? YI8I NO Uo N/A o g. A r c ove rh e ad e quipm e nt , di s tri b u t i on sys t e m s, cc ilin g til cs l ig htin g , YI8I NO LI D N/A o nnd ma so nr y bl oc k wa ll s 11 0 1 lik e l y 1 0 c o ll nps e o nt o th e eq uipm e n t? 9. Do l i n es h ave adequa t c fl ex ibilit y t o YI8I NO LID N/A o 10. Ba se d on Ih e a h ove seis mi c inl e rac li o n eva lua t i o n s , i s cq uipm e nl f r ee YI8I NO t i D o f p O l e nl iilll)' nd vc r sc se i s mi c int e rn e t i o n c lr ce l s? O ther C Uliditiull S tl. Ha ve you l oo ked 1 (, 1' found n o o lh e l' sc i s mi c co nd i li on s Ih al co nld ad vc r se l y af fee l I h e fun c li o ns o f Ih e e quipm e n l? C Ollllllcnt s (A ddi t i ona l pages lIl ay be added a s Ilc ce ss ilry) Int e rn at inspection p edo lil/ee l. N o co n ce ms n oted intemally. h y: I<vle K ri esel Dileep C il e ll opalle YI8I N O l I D I)a l e: 10/211201'1 8-53 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 3 of3 Statu s: NO uO E quipment ID No. _---Eq uip. C l nss' (161 Ba tt ery Chargers a nd Inv erters 8-54 Prairie Island Nuclear Generating Plant -Unit 1 S eismic Walkdo wn Submittal Report, Updated Sh cetl of 3 St a tu s: NO uO Seismic Walkdown Checklist (SWC) E qu i pm e nt ID N o. __ E quip. C la ss' (16) B a tt ery C ha rge r s an d In ve rt e rs E quipm e nt D esc ript io n L oca ti o n: B ld g. __ F l oo r EI. __ R oo m , Ar ea _1---------Manu fac ture r, Mo del, E t c. (op ti o n a l b ut r eco mm e nded) Instrnction s roo' C Olllllleting C hecldi s t Thi s c h ec kli st m ay b c u scd t o d oc lim e lit the res uits o f th e Seis mi c W a lkd ow n o f an i te m o f c quip11l e nt o n th e S WEL. The s p ace b e l ow e ac h o f th e f o ll ow ing q u es tion s m ay b e u sed t o re co rd th e r es ults o f jud g m e nt s a nd findin gs. Additi o n a l s p ac e i s p rov id e d a t the e n d o f this c h eck li s t f o r d oc um e n t i ng o th e r co mm e nt s. Anchorage I. I s th e an c h or a g c co nfi g ur a ti o n ve rifi ca ti on r e qui re d (i.e., i s t he i t e m o n e yo NI8I o f t h e 50% o f S W EL i t e m s re quir i ng s u c h verifi c ati o n)? 2. I s th e an c h ornge free of be nt , b ro k c n , mi ss in g or l oose h ar d w ar e? YI8I NO UO N/A O 3. I s th e an c h ornge fr ee of co r ros i o n th at i s m o r e th a n mild s ur laee Y I8I N O UO N/AO Qx id H t i o n? 4. I s t h e a n e h o m ge fr ee of v i sib l e c rn e k s in th e co n cre t e near th e a n c hor s? YI8I N O UO N/A O 5. I s th e an c h o r age co nfi g urati o n co n s i ste nt w ith pl a nt d oc um e n ta ti o n? y o N O U O N/AI8I (No l e: T his q u es ti o n o nly a ppli es ifth e it e m is o n e of th e 50% for w h ic h an fl n c h o r flge co n fig ur a ti o n \'e r i fic a ti on i s r e qui red.) O. Oose d o n th e a bove a n c h o r age eva lu a ti o n s, i s th e a n c h o ra ge lI'ec of YI8I N O U O p o t e nt ia ll y adverse se i s mi c co n d iti ons? I En l a Ih l; eq ui p ill e n t class JUl lll C f rolll A p pe l1 liix 13: Classes of Equ i pmenl. B*55 Prai ri e I s land Nu cl e ar G e nerating Plan t -Unit 1 Se ismi c Wal k do w n Submittal Report , Updated S h ee t 2 o f 3 Stat u s: yl2?J NO uO Se i s mi c W a lkdown Ch e ckli s t (S W C) Eq ui p m e nl I f) N t). __ E quip. C i a , ,' (1 6 1 Ba tt e N Charg e r s ane ll nve l t e r s E qu ip m e nl f)ese r ip li o n fn t crn cti o n E ff ects 7. A I so n I m ge l s Ii'c e Ii'o m i m pa e l b y ncarb y equip m e n l o r s l ru c lur e s? YjgJ N O UO N/AO T e mp o ra l Y el ec lri cal equ ip m e nl l o b e r e m o veel pri or 1 0 re s lalt i s ac ce p l abl e. S. A r e o v e rh e a d e q ui p m e nl , d i s l ri b uli o n sys l e m s, ce ilin g l i l es nn d li g h l i n g , YjgJ NO UO N/A O a n d m a s o nr y b l oc k w nll s n o t li ke l y 1 0 co ll H p se 0 111 0 th e eq ui p m e n t? 9. Do a tt a c h e d l in es h a l'C ad e qu a l e I k ,i bi l i l y 1 0 a v o id d ama ge? Y jgJ NO U O N/AO 1 0. Ba s e d O ll th e a b o v e se i s m i c.: i nl n:l c li o n ev a lu H t i o n s, i s eq uiplll e nt fr e e Y!&1 NO U D o r p o t e nli a ll y a d v ers e se i s m i c int erac ti o n c ll ec l s'! ------O th e r A d ve r se C Olldilioli S I I. I-l a ve yo u lo o k e d 1 i.)1' al1d r<')l II H IIl O o lh e r seis llli c c o nditi o n s tli al c O lild m l ve r s e l y : lI r cc l t h e s a f e t y fUll c ti o n s of Ih e e quipm e n t? CO llllll e nt s (A d di ti onal Jl , t gcs Ill ay b e "'dd e e! a s n ece ss ary) I n le rn al in s p ec ti on p e lf o rm e d. N o co n ce rn s n o l e d inlern a lly. Y jgJ NO LJ O l , v ll h Hl l e d b y:

______ 1)" l e: '1 0 12012 0'14 D i leep C/J e r lopa ll e 1 012012 0'/4 8-56 Se ismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Un it 1 Seismic Wa l kdown Submittal Report , Updated S h ccl 3 01'3 Sta tu s: NO uO " Cftdpm C IlI If) No. ***** ___ E quip. C l ass' 11 6 1 Batt ery Cl larg erS and Inv e rt ers E CfU i pm e lll De se ripl i O Il B-57 Prairie Island Nuclear Generat i ng Plant -Unit 1 S e ismic Walkdo w n Submittal Report, Updated Sh e et 1 NO uO Seismic Walkdown Checklist (SWC) E quipmcnllD No. ____ E quip. C la ss' (08) M o lor-O pera leelanel So l e n oid*O pe rateel Valv es Eq uipmcnl !J cse 11OtlOJ L oc ali o n: Bldg. __ Floor EI. ____ R oo m , Area _-------.-----Manufacturer, Model, Etc. (optional but re c ollllllended)

Illsh'uclioJls for Compleling Chccldisl Thi s checklist m ny be II s cd to d OC U111ent the re s llit s of th e Se i s mi c W n lkd ow n ofnn it e m ofeqn il'm ent o n th e S W E L. Til e s p ac e b e l o\\' e ac h o rtlle roll ow ing qn es tion s ma y b e u s ed t o rc co rd the re s ults o f judgments and linding s. Additional s p ace i s p ro vid e d a t the e nd or Ihi s checkl i s t for do c umenting other conunents. Allchnmgc I. I s Ihe anchorage configurati o n vcrificalionrequired (i.e., i s Ih e it e m one yo NI8I of Ih e 50% or SWEL il e m s r equ iring s uch ve rifi ca tion)'! 2. I s th e anchorage fre e of bent , bro ke n , mi ss in g or loo se hardware?

yo NO UO NfAI8I 3. I s th e anchorage rre e of corrosion th a t i s lIl orc thllnmild s urfa ce yo NO UO NfAI8I oxidati o n? 4. I s Ih e anchorage fi*cc of visible crac k s inlh e eo ncrel e He a r Ihe nnc h ors? yo NO UO N fAI8I 5. Is the anchorage co nfiguration co n s istent wilh plant cl oc umentation?

yo NO UO Nf A 181 (Not e: Thi s question o nl y a ppli es if the i l em i s nne o rlhe 50% ror which an anchorage co nfigura t i on ve r ifi cal ion i s r e'l uired.) 6. B ase d o n the ab ove anchomge evaluations , is th e anchorage fre e of YI8I NO IJO potenlially adver se se i sm i c co nditi o n s'! I Elllcr cq uiJ lIllc nl Chl:>S Hum!.! ('Will Apllcndi.x B: C l a ss!!s of Equ il llll C I II, B-58 Prair ie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown S ubmittal Report , Updated Seismic W a lkdowll Che c kli st (SWC) Sheet' 2 or 3 Sta lu s: v[8J NO uO Eq uipm c nt II) No. E quip l u c ntl)cscri pti o n Eq uip. C l n s s' (081 Motor-Opera t ed and Sotenoie/-Opera t eci Valves (ntenleli un Er r ects 7. Arc so rt I""get s free fronl impaci by ncarhy equipmen t or s tru c t urcs? VIE! N O UO NIAO 8. A r c ol'c rh ead eq u iplllc nt , di sl ri bu ti u n sysle m s , cci lin g tiles and li g htin g, VIE! NO UO NIAO alld n lOS0 111 ,), hlo c k wa ll s ll ot like l y 1 0 co lla pse Ollto Ih e eq llipm eil l'/ 9. Do all ac h ed lill CS h!ll'c ad e qu nte n ex ibili ty t o III'0 id dalllage?

VIE! NO UO NIAO F l ex i lJ/e cone tllits a r e acce (Jl alJ/e. 1 0. Un s ed 0 11 ti le nb ovc scis lni c i n t crnctio ll eva luati o n s , i s equ ipm e nt fr ee o f' p o t e ntially seis m ic ill te r ac ti o ll Othel' A dl'cl'sc Conditions II. I l ave YOll l onked f o r a n d ""nH ln n ot h e r sc i s mi c co n d i l i o n s th a i coul d adl'c r se l y an cc t th e s af e t y fUll e ti o n s orth e cq uipm e ll t? C Olliment s (Add iti on al pn g es 11111)' be (H i ded as Ill!ces!'inry) "I'a lu nled h y: ai/eap C il er/opa" o C .y. p" Micllael Woe/arc Vie 11t;/J,r"!*

VIE! NO UO VIE! NO lJO I)a t e: 10/11/201 1. __ _ '10 11112014 8-59 Seismic Walkdown Checklist (SWC) Equipllle lli ill NoIS *** L ___ _ Note: Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated Sheet 3 of 3 Statu s: NO uO Equip. C l ass' (08) Motor-Opera t e el al1d So t e l1 oi d-Operated V a tve s Note: B-60 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear G e nerating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Sheetl of 3 Statns: y[8J NO uO Eq u ipm e nt II) N o. __ E qu i p. C la ss'--'-'(1"'4u.i-=O<!.is"'t"'riY-b"ut"'io"'n1.L P"'a"ne"""s

__________ _ Eq uipm c nt Description Location:

B l dg. _ p l oor EI. ___ Room, Area Malll.n.cturer, Model, E t c. (optional but recommended)

Instl'uctions fol' Completing C hecklist This check li st m ay be tl se d t o doctlmentthe re s tllt s of th c Se i s mic Walkdown of au it em o r e qllipment on th e SWEL. The s p ace below eac h of the following qu es ti ons m ay b e used t o r ecor d th e re s ult s orjudgments and finding s. Additioual space i s provided a t the e nd of this checklist for d oc um e ntin g ot h er co mm en t s. Anchorage I. I s the anc h orage configuration verification requir e d (i.e., is tbe it e m o n e YI8I NO of lhe 5 0% ofSWEL it e m s requiring s u c h verification)?

2. I s the a n c h orage free of b e nt , broken, mi ss in g 01' l oose h ar dwar e? YI8I NO U O NI AD 3. I s the an c h orage fr ee of co rr os i o n that i s m ore than mi I d s tlrra ce YI8I NO lJ O Nt AD ox idati o n? 4. I s th e anchorage l're e of visible cracks ill th e co ncret e n ca r th e anchors? YI8I NO UO N/AO 5. I s th e all choragc con/i g mat iu n co n s istent wi th pl a nt d ocu m e ntati on? YI8I NO UO N/AO (No t e: Thi s question o nl y applie s if th e it e m is u nc o f'th c 50% 1'01' w hi c h an anchorage co nfi g ur a li o n verification is r eq uir ed.) SQ U G SEWS "nd ca l c lliati o n ENG-CS-098 II s ed f or n n c h orage vcrifi c ation of e i g ht 1 12" th readed anc h o r s. Not g r o ut ed a nd acce ptabl e in thi s co nfi g ur at i on per above calc ul at i on. 6. Bfl sc d 011 th e above a n c horage eva lu a ti o n s , i s th e n n c h orage f r ee of potentially u d ve r se se i sm i c co nditi o n s? 1 E lli e!" tI le cC]lIipllH;nt cl ass n alile from Appt.:lldix 13: C l as s e s of Equ i plll c lll. YI8I N O U O 8-61 Prairie Island Nuclear Generat i ng Plant -Un it 1 Seismic Walkdown Submitta l Report , Updated S h ee t 2 of 3 Statu s: NO uO Seismic Walkdown Checklist (SWC) E quipment 1 0 No. _1-Equipment Desc ript ion Intel'lIclio

.. E ffects Equip. C la ss' 14 Di s tribution Pan e l s -7. A r e so li tar ge t s free f ro m impa ct b y n c arb y eq uipment o r s tru c tur es? YI8I NO Uo N/Ao 8. A r e ove rhead eq uipm e nt , di s tributi o n sys t ems, ce ilin g tile s n nd li g htill g , YI8I NO Uo N/Ao and III1I S0 ll'")' bl oc k wa ll s not likel y t o co ll npse on t o th e e quipmellt?

9. Do allnch e d lili es h ave ad e quat e Il e.x ibilit y t o avoid damage? YI8I N O IJ o N/Ao Ill. lIa se d o uthc ab ove sc i s mi c illt ernc ti oll cva luati oll5 , i s e<[lIipm c ilt I*r cc YI8I NO Uo of p o l c nlinlly adv e r se se i s mi c inl e rn c ti o ll e i'l ecls? Oilier Adverse C OIlllitiOIlS II. Iin ve ),0 11 l oo ked l o r l llld f o und 11 0 o ilI e r se i s mi c co nditi ons that cou ld ad ve r se l y nlk c llh e s alel y fUll c tion s orlile e quipm e nt? CO llllll e lit s (Addit i o nal pa ge s lIl ay br ad de d a s n Cl'c ss ilry) Intern a l inspection pelformeci.

N o co n ce rn s n otec l inl erna lly. D il eef) e/lerlopatle YI8I NO Uo Date: /012012014 1012012014 8-62 Seism ic Walkdown Checklist (SWC) E quipm c ut ID N o. _f-E quipm e nt De sc ripti o n N ol e: Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated S h ee t 3 0 1" 3 Statu s: NO uO E quip. C la ss' (1 4) D i s tributi o ll Pa llel s ---------------N ule: 8-63 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated S h eet 10f3 Status: yl8l NO uO Eq u ipment ID No. __ Eq uip. __________ _ E quipmellt De sc riptioll 7 Mallufae lur cr , Mode l, E l e. (opt i o nal but rccom ll1 e nd ed) Instl'llctions fa .. Co mill e ting C h e delist T hi s chcck li s lll1a), be u sed to doeUlllcnllhe r esu lt s of th e Se i s mi c Walkdowll o ran item ofcq uipm c lll onlhe S WEL. The s pace below eac h of Ih e following que s li olls may be u scd 1 0 r ecord Ih e result s of judgmenls a nd finding s. Ad diti o n a l s pace i s provid e d al the e nd of thi s check li s t for d oc um e nlin g ot h e r comlllent s. Ancho .. age I. I s the a n c h o rage co nti g urali o n ve riti cation re qu ired (i.c., i s Ih e il em o n e yo NI8I of the 50% ofSWEL il e m s r eq uiring s u c h ve rifi cation)? 2. I s Ih e anc h orage free of hent, br o ken , mi ss ing or l oose h ardwa r e? YI8I NO U O N/AO 3. I s Ihe anchorage fr ee o f co r ros i on tlllll i s 1I1 0rc Ihan lI1ild s u rf n ee YI8I NO UO N/A O ox id a ti on? 4. I s the anchora ge free ofv i s ihl e crac l" inlh c conc r ete n ea r Ih e anc h ors? YI8I N O UO N/AO 5. Is I he anc h o ra ge configura ti on co n s i s lenl wi lh p l anl d ocuillen i atio n? yo NO UO N/AI8I (Note: Thi s qll cstion o nl y appli es il'thc il em i s one oflh e 50% for w hi c h an a n c h orage co nfi g ur al i o n ve rifi ca tion i s r eq llir ed.) 6. BHsed 0 11 th e above anch o rage eva luati o n s, i s th e anchorage fi'ce of Y!8J NO UO potentia ll y a dver se se i sm i c co n ditions? I E ul e r th e c: qllipnH':1l 1 dass mtrn e 0: C l a!'scs l1fEquip"lCnl.

8-6 4 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated S h ed 2 of' 3 Statu s: NO uO Seismic Walkdown Checkli st (SWC) E quipm e nt ID No. Eq uipm e nt D esc ription Intemeliun Elfects E quip. C la ss' (14) Di s tribution Pan e l s 7. Are so n target s fr ce li'om impa c t b y n carby eq uipm e nt o r s tru c tur e s? Y[8J NO UO N/AO H. Ar c ove rh ead e quipm e nt , di s t r ibuti o n sys t e m s, ce ilin g til es a","ightin g , Y[8J NO UO N/AO a lld m asonry blo c k wall s 11 0 1 li ke l y t o co ll np::;e on l O Ih e e quipm e nt? 9. D o aUa c h e d lin cs ha ve ad e quat e Ile x ibilit y to avo id dam age'! Y[8J NO UO N/AO to. H ose d on th e ahov e se i s illi c int e nl c tion eva lu a ti o n s , i s eq nipl1l e nt rr ee Y[8J NO LJO of poi c litinll y adver se sc i s mi!.! illt c r:1 c li o ll e ff ects? Othe,' A,lve,.se Conditiuns II. Iln vc YOl l l nn k c tl for lind (lH llld tin o th e r sc i s nli c c onditi o n s that cOIlld adv e r sely arrc c llh c sa f e l y run c ti o n s o rill e eq uipm e nt? C OllllllClit s (Add iti u nal pa ges lIla y b e m ld!.:d as [l Cl:css;w y) Internal in spec ti on pe r form e d. No concerns noted inte ll1 a lly. Dileep e/l er l opa ll e Y[8J NO UO Dat e: 101 2 1 120'11 1012 '1120 14 B-65 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated Shccl301'3 Statu s: YIZ! NO uO leq" i I'm e ll tiD No. __ Eq u i 1'. C In ss '_1L!1-'!4LI

",O",is",trJ],ib",u[!!ti",OIl.L1 LPE8LLlle"""-s

_________ _ N ot e: Nn tl': 8-66 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 1 of 3 Stat u s: NO uO E quipment ID No. E quip. Class'.i-1.124JwD"""is"'tr1.!ib"u"'tl,,*o"'n-'P

...B!1.n"'e"'ls'-

_________ _ Equi pm e nt Description

...

Manufacturer , Mudel , Et c. (optioual but recollImended)

Instl'uction s fol' C omilleting Checklist This c h eck li s t ma y be u sed t o d oc ument th e r es ult s of th e Se i s mi c W al kdown o f an it e m of equipment on th e S W E L. The s pac c b e low eac h or the foll ow in g qu es ti o n s may b e u se d t o r eco rd the r e s ult s of judgment s and f'indin gs. Addition a l s pa ce i s provid e d at the e nd of this c he ck li s t for d oc nm e ntin g other cO lllm e nt s. Allchorage I. I s the a n c h o rage con fi g ur a ti o n v e ri t icati on required (i.e., i s th e item one yo N[8J of th e 50% ofS W EL item s re quirin g such verification)

? 2. I s th e a nch o ra ge f r ec or b e nt , bro ke n, mi ss ing 0 1' l oose h a rdwar c? YI8I NO UO N/A O 3. I s th e IIn c h o rage free of co rr os ion that i s m o re th a n mild s ml'lee YI8I NO UO N/AO ox id a ti o n? 4. I s th e anchorage free o f vi s ible crnc k s ill the concrete Il ea l' th e an c hor s? YI8I N O UO N/AO 5. I s th e anchorage config urati o n co n s i s t e llt with plant d oc ll l ncntati o n? yo NO UO N/AI8I (Notc: Thi s qucstion o nl y ap pli es ifth c item i s on e of th e 5 0% f or whi c h an anc h orage co nfi g urati on verificAtion i s r e quir e d.) 6. Ba se d o n th e a bo ve anchorug c eva hmti o ll s, i s th e a nch o rn g e {j'el! of yt8J NO lJD p o t e nliall y a dver s e se i s mi c conditions?

1 En l e l' the Cqllipll1ClI1 cla ss IImnc frolll Appcndi s 13:

or E q ui pm ent. 8-6 7 Prairi e Island Nucl e ar Generating Plant -Unit 1 Sei s mic Walkdo w n Submittal Report , Updated S h eet 2 01"3 S t at u s: NO uO Se i s mi c W a lk d own Ch e ckli s t (S W C) Eq u i pm e llt 1 0 Nu. ___ E q u i p.

__________ _ Eq u ip m e nt De sc ri pt io n Int e ractioll E ffe c t s 7. A r e so ft t nrge t s f r ee rrom im pac t by n eHrby eq uipm e n t o r s t ru c tu re s? yo NO UO N/A[g] R. Arc ove rh ea d eq u i pm e nt , di s t ri b uti o n sys t e m s , cc ilin g til es li nd li g h t i u g , Y[g] N O UO N/AO tlild m a so nr y b l ock wa ll s n o l lil\c l y 1 0 co ll H p se 0 111 0 the e quipm en t? 9. Do a tt ac h e d lili es h avc ade qu a t e Il esib il i t y t o avoi d d am age? Y[g] N O UO N/AO 1 0. Bn se cl 011 (he a b ove sc i s lll it.: int e r ac ti o n eva l ua ti o ll s, i s e qui p m en t JI'ce Y(8) N O UD or p ote nt i a ll y a d ve r s e se i s mi c i n t e r ne t i o n e rr ec t s'? O th e .. A li ve .. " C unditiull s I I , H nvc YO Ll l ooke d n J I' n n d f O llnd 11 0 o th e r seismic cond iti o ll s (h ilt co uld adve r se l y a l feet th e sa r cty lilll e ti o ll s " rth e eq uipill e nt? C Onll1l C lll s (Acidili(1I 1al p a ges Il la y h e added a s 1 1ClTSSiU')

') I n l e rnal i nspectio n pe/1ormed. N o conce rn s noled inl e rn ally. Eva lu n t ed b y: " 1<,,V"'le"'I"'<"'rie""s"'e"-

I_---,I--F-Y--"/---,I-JO.<

J/}""", ,,,,,,-,.L-_ . _______ _

Di/e e p C h e r/opall e Y[g] NO I J O Dllt e: 091'/7120'/4 09//712011 8-68 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant* Unit 1 Seismic Walkdo w n Submittal Report. Updated S h ee t 3 o f 3 St a tu s: NO u O E qu i 1'111 e ll ti D N o, ___ E q II i p , C I" ss '---,-,(1",4

1.) -'=O"'i s"'t'ib'''tO'-'Il-'-P-8Ile ls _________ _ N ut e: N oll': 8*69 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 1 Of3 Status: y[gJ NO uO Seismic Walkdown Checklist (SWC) Eq uipm e nt ID No. __ -----Equip. C las s'-L1.11 Di s tribution Panels Eq uipm e nt De sc ripti o n __ L oc ation: Bldg. ___ rloor EI. ___ R oo m , Area __ 1---------

---Manuf ac tur e r , Mod e l, E t c. (optional but r eco mmend e d) Instl'uctions fol' COlllpletiug Chccldist This c h eck li s t ma y b e u se d to d oc ument th e r es ult s o f th e Se i s mi c Walkdown o r a n it e m o f equipment on th e SW E L. The s p ace below eac h of th e foll o win g qu esti on s may he u se d t o re co rd th e re s uit s o f jud gme nt s a nd findin gs. Additional s p ace i s pro v id e d at the e nd o f thi s c h ec kli st f or d ocu m e ntin g o th er comment s. Anchomge I. I s th e an c h o ra ge co nfi g urati o n ve rifi c ation r eq uir e d (i.e., i s t h e item one yo Nt8I of th e 50% of S WEL it e m s requiring s u c h ver ili ca ti o n)? 2. I s the an c h o rage (j'ee o f b e n!, brok e n , mi ss in g or l oose hardwar e? Yt8I NO UO N/AO 3. I s th e an c h o rag e f r ee o f corros i o n that i s m ore than mild s ur t"ce Yt8I NO UO N/AO ox idati o n? 4. I s th e a nch o ra ge tj'ce o f vis ible cra c k s in the co n crete n ca r th e an c h ors'! Yt8I NO UO N/AO 5. I s th e a n c h mage co nfi gu r a ti o n co n s i s t e nt w ith pl a nt d oc um e nt a t io n? yo NO UO N/A[gJ (N o te: Thi s qu es ti o n o nly a ppli es if the it e m i s one of th e 50% 1'0 1' whicll an flnchorage c o nfi g u ra ti o n vcrifi cu li o ll is r e qui re d.) 6. Based o n th e above an c h o rag e ev a Ill a ti o n s, i s th e ""c h o rag e Ii'ee o r Yt8I N O UO p o t e nti a ll y adve r se seis mi c co nditi o n s? I E nl e r t he I.:Cll1i p mC IlI c1n ss Il nlll C f rolll APPCll di ,,= 13: C la sses o r E ql l i p m c ll l. B-7 0 Prairie I sla nd Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 2 of 3 S t a tu s: vIZ! NO uO Seismic Walkdown Checklist (SWC) Eq llipm c lIl If) N o. Eqlli p. (14) Dis t ribution Pane t s Eq llipm ell l De s c ripli on __ Inlemetion E H e el s 7. Are s o rt t ar g e t s rree from h y nCHI'b y e qllipmelltlll' s t rll c ture s? YI8J N O U O N/AO 8. A r e ove rh ea d equip m e nl , dis lribuli on sys l e m s. ce ilin ll lil e s 11 n d li ll hlinll. YI8J NO UO N/AO nnd m a so nr y bl o c!; wa ll s not li ke l y t o c o llap se o n to Ih e eq uipm en l? Saf e ty rotat e d bt ec i< watl 1/ 7 i s in vi c inity is a cc eptable. 9. Do a ll" c hed lin c s h avc "dequale n c, ib ilil y 10 avoid dn ma g c? YI8J NO UO N/AO 10. On s.d o nlh o nbo ve se i s m i c inl e ra c li o n e va iliali o n s. i s e qll i pme nl fr e e YI8J NO l I D ofpo l cllt iall y ndv e r s c s e i s mi c int e ra c ti o n e l1 ccl s? Olhel' Advel'se C onditiun s II. I-I<l ve YOII l o o k e d 1'0 1' :Ind found lin ot h e r se i s mic c o n d i t i o n s II HlI c O llld advcrs e l y arl e c llh e s al e l y fun c li o n s of Ih e e q u i pm e nl? YI8J NO l i D C Ollllllents (Add iti onal pa ges m a y be mldcd as n ec e ss ar y) Int e rnal inspection p e l1ormed. No c o n c ern s not e d int e rnally. E v n lunled b y: ___

_____ Dal e: 09/2-//2 IJI-I

.. ), .. -cF"'=-----Dal e: Ii <)/2 .J/2 IJ I.J B-71 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated S h ee t 3 of 3 Statu s: y[8J NO uO Eq uipill e nt I I) No. Equip. C l ass' (141 Distribution Pan e l s E quipill e nt D esc ripti o n __ 8-72 Prairie Island Nuc l ear Generating Plant -Unit 1 Se i smic Walkdo w n Submittal Report , Updated S h ee t 1 o f 3 S t a tu s: N O uO Seismic Walkdown Checklist (SWC) *** l------E quip. C l ass' (14) Di s tr ibu ti on P a n e l s E quipm c nl ID No. E quipm e nl D csc rip t i o n L oc ati o n: Bld g. __ F l oo r E J. ___ Ma nufa c tur e r , M o d e l, E t c. (o prion a l but r ec ommcnd e d) In s truction s 1'01' Completing Checldist Thi s c he ck li s t m" y b e u se d 1 0 d oc um e nt Ih e r es uli s o f th e Se i s mi c W a l k d olV n o f a n it e m o f equ ip m e n I o n th e S W EL. Th c s p ace b e l ow e ac h o f th e f o ll ow in g qu e s ti o n s m ay b e used t o reco rd th e re s ult s of jud g m e nt s a nd lindin gs. Add i ti o nal s p ace i s pro vi ded al th e end of th is c h eck li s t to,' d oc um e nling o lh e r co mment s. Anchorage I. Is Ih e an c h ora g e co nli g ur a li on ve rili ca l io n re quir ed (i.e., i s th e i le m o n e YI8I NO o rlh e 5 0% o f S WEL il e m s r e quirin g s u c h ve rifi c ati o n)? 2. I s I h e " n c h o m ge fi'ee of b e nt , b ro k e n , mi ss ing o r l oose h a rd wa r e'! YI8I N O UO Nt AD 3. I s Ih e a n c h o n'ge fr ee o f co rr osio n th a t i s m o r e Ih a n mild s lirfa ce Y I8I NO UO Nt AO 4. I s Ih e an c h o ra ge fr ee o f vi s ible c ra c k s in Ihe co n c r e l e n e ar I h e ", c h Ol's? YI8I N O UD Nt AO 5. I s the a n c h o ra ge co nli g llrali o n co n s i s l e nl wi lh pl a nt d oc um c nl a li o ll? YI8I NO U O NtA O (No l e: T hi s qu es l io n o nl), a p p li cs i flh e it e m is o n e o f th e 5 0% f o r w hi c h an an c h o ra ge co nfi g urati o n v erifi c ali on i s re'luir e d.) Bo lt ed 1 0 s tru t w itl1 six f aste n ers p e r dr aw in g X H-529-1. 6. B a se d O n th e n b ove n n c h o ra ge ev aln a t io n s , i s th e a n c h o ra ge fr ee o f Y I8I N O UO p ote ll t i a ll y a dv erse se i s mi c c OllC lili o ll s? I En t er 11 11.: cln ss from Appc ll d i.'\ D: C l n ss c s of Eq u i p m cll t. 8-73 Seismic Walkdown Checkl i st (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sh ee t 2 0 1'3 S lalu s: N O uD Equipm e llt ID N o. E quip. C ln ss' (14) Di s tributi o n P an e ls l;quiplIl C IiI D esc ripti o n I"tentetio" Effect s 7. Ar e s oli tar g et s fre e l i'O lll impa c t b y II c arb y equipm e llt 0 1' s tru c tur es'! YI8l NO UO N/AO X. Ar e o l'er h e" d " quipm e ll t , di s tributi o ll sys t e m s , ce ilin g til es nnd li g htin g, Y I8l NO U O N/AO ;]IlClll1 aso nr y blo c k wHl l s n ot lik e l y 1 0 co ll a p se O l1t o the e quipm e nt? 'I. Do a tta c h e d lill es ha vc ad e qu a te /l ex ibilit y t o a vo id d a ma ge? Y I8l NO UO N/A O S hor/. r ig i e ll y a n c l/o r ec t co n e tui/ i s acce pt a bl e. I n. !la se d O il th e ah ol'e sc i s mi c illt e m e ti o ll e l'alua l i o ll s , i s e(luiplll e lll rr ee Y I8l N O UO n rpOl c nti l.l ll y ad ver s e se i s mi c i n te ra c ti o n e lr ee t s? Olher Adver s e C OlillifilJII S II. I lave )'OU look e d Ii,,' alld 1'"111<1"" o lh e r se i s mi c co lIC/ili o ll S Ihat co uld ad ve r se l y alT ee tth e s nl'e l y rim e ti o ll s oI'th e e quipm e llt? C Ollllllents (A ddition a l pa ges may h e add e d tiS n ecess ar y) tn/em a l in s p ec ti on p er f or m e d. N o co n ce m s n o/e d i n/e m a lly. YI8l NO 1/0 " v a luat c d b y: ==------:::;0

... /"---------Dn t e: 0 912 4 12 014 .

Dileep e/l e rl opa ll e 0 912 4/20 1 4 B-74 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated S h cet 3 of3 Status: NO uO E quip"'c u! I D No , __ Eq uip , C la , s'-, (L!1;!4 ,-, 1 D""'st'fIbutioIl'-'-P-8IJe i's ________ _ 8-75 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Sheet 1 of 3 Status: YIX! NO uO Seismic Walkdown Checklist (SWC) Eq uipment ID No. ___ Equ ip. C la ss'---" U"'4u.i-"O!!c i s", l!.!ri"-b!!.ut"'i o"'n.!..L P Ba!.!.II"'el"'s __________ _ Equipment lJescl'iption Location:

Bldg. ___ Floor EI. Room , Area _----------Manufacturer, Model, Etc. (optional but recommended) (nstl'llctions fol' Completing Checklist Thi s check li s t mny be u sed t o document the I'e s uits of the Sei,m i e Walkdown o f an item of eq uipm e nt on the SWEL. The s pa ce below each of thc following questions m ay be u sed to record the r es ult s of jud g m ents nnd i1ndings.

Additional s pac e i s provided at the end of this c he ck li st for documenting o th e r comments.

Anchol'age I. I s the anchomge eonliguratiou ve l'ili ea ti o n required (i.e., i s the item o n e Y[8I NO of the 50% ofSWEL items requiring slIeh verification)?

2. I s the anchorage free of bent, broken , mi ssi n g 0 1' l oose hardware?

Y[8I NO Uo Nf AD 3. Is the anchorage li'ee of cor ro s i o n Ihat is more than mild s llrf ilce Y[8I NO Uo NfAo oxidation?

4. I s Ihe "nchol'age free of v i s iblc cracks in the concrete neal' the a n c h ors? Y[8I NO Uo NfAo 5. Is the anchorage conliguration cons i ste nt with pl ant documentation?

Y[8I NO Uo NfAo (Nole: This que s ti on only applies ifthc it em i s one of th e 50% for w hi ch nn flnchorage configuration verification is required.)

AttaclJed at 6 bolt lo ca ti ons to inslalled slrul sectio ns , p e r drawing XH-529-2. 6. Ba s ed O n th e above anchorage evaln"tions, is th e anchorage free or Y[8I NO LID potentially adverse se i sm i c conditions?

I EIlIi.: r th e ('lJl1iP IIl CIlI dass lIamc fnlll1 I\ppcm l i.x 13: Cla s se s o r Eqllipll1!::nl.

B-76 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated S h eet 2o f3 S tatu s: NO uO Seismic Walkdowl1 Checklist (SWC) I O quipmcnl1lJ No. ___ Equ ip. C la's'-'-11!..:4!J.

l .... 0"'i".s l"'*butio'cc1!...P-a.L!n.!<.el s'-_________ _ E quiplll c ni D escr iption Inlel'aclion E rf ects 7. A r e su n {[n'gel s ('ree Ii'o m impa ci b y uea,.b y equipm e nt o r s tru c lllI'C'? N O UO N/AO 8. Ar c over h ead e quipm e nl , di s tribuli o n sys t e m s, ce ilin g lil es and li g ht ing , NO U O N/AO a nd ma s on r y bl o ck wa ll s n o l lil ,c l y t o co ll ap se o nt o th e eq uipm e n t? 9 , Do allach e d lin cs hav e ",l e<<("aIC n c,ib ilil y t o av o id d a ma ge? yo NO UO Rigid co ndu i l is acceplable.

10. Ba se d o nlh e ah ovc se i s mi c inlera c t ion eva (":Iti o n s, is eq lli pmenl ('r ec NO UO 0 1' p ote nt iall y ad verse se i s lll i c i ntCnt c l ion (' n ee t s'! Olhel' Advel'se C undilions II , J-Inv e YO II l ooke d 1 (11' HUci ro und 11 0 nlil c r cO ll d ili o ll S lilal c ou ld adv e r sely al'ft:c lth e s af ely l i lil c ti o ll s o rth c c quiplll e nl'! C omm e nt s (A dditi o nal p ages IIla y b e a dd e d a s n e cc ssnry) Inl erna l inspection p erfor m ec/. N o co ncern s nol ed inlernally.

E va("al e d b y: Kyle I(ri ese l O il eep Clrer/opalle

(..., \). b NO lJO Dat e: 0911712014 09//712014 8-77 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated S h ee t 3 o f 3 S lalu s: y[8J NO uO E q LI i plll e ll I I J) No. ___ Eq LI i 1'. C I a ss '_ll.!l",4 L) ",D",is",/, ,,,ib,,, u ,,,/i!!.O/ce' -"-P-"a!!IJ"'e'-s _________

_ --------------j No t e: Nu l,-: 8-78 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walk down Submittal Report, Updated Sheet I of 3 Slatus: NO uO Seismic Walkdown Checklist (SWC) Equipmcnt JD No. Equip. Cla s s' (14) Distribution Panels Equipment Dese";ption

__ Location: Bldg. ___ .... Floor EI. ___ Room, Arca _------------

Moclel, Etc. (optional butrccol11mendcd) Instl'llction

., rot* COlllpleting Chccldist This checklislmay be used to documcnllhc rcsults of'the Seismic \Valkd o wn of au itcm of equipment all the SWEL. Thc space below each o[lhe following queslions mil)' bc used to rccord the resuits ofjudgnwnts

!lnd finding s. Addition,,1 spacc is provided nt the end orthis checklist for documenting other comments. Anchorage I. Is the anclwragc configurntion vcrificationrcquircd (i.e., is the item one YI8I NO of the 50% ofS\vEL items requiring such verificntion)?

2. Is the nnchorngc Ii'ee orbent, broken, missing or loose hordwnre?

YI8I NO UO NlAO 3. I s the anchornge free of corrosion Ihut is m o re than mild surface Y[8J NO UO N/AO oxidation?

4. Is the anehoruge free of'visible cracks in the concrete neur the anchors? yo NO UO N/A[8J Panel balled to lillis/rut frame wllic/J Is welded to steel structure.
5. Is the anchorage conJigliration consistent with plant documentati o n? Y[8J NO lJO N/AO (Nole: This (Inestion only applies if the item i s one or the 50% for which on onchornge configuration verificotion is rcquired.) Refc/ence: calculalion ENG-CS-101. 6. Dose<i on the above anchorage evaluations , i s the anchorage

]i'CC of YI8I NO UO Jl o tcntiolly u<iverse scismic conditions?

I En!cl'thc equiplllcnt cla ss IlCllllt!

frOIl] Appr:.ndix lJ:

of.Equipmclll. 6-79 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 2 or3 Status: NO uO Seismic Walkdown Checklist (SWC) Equipmcut I D No. Equip. Class' (14) Distribution Panels Equipment Description

___ Intel'oction Effects 7. Ar c so li tar gets Ii'ee Ii'o m impa c t h y n ca rb y equ ip ment or s tru c tur es? Y[8J NO UO N/AO 8. A r c ovc rh ea d equipment, distributio n syste m s, ce ilin g tile s a n d li g htin g, Y[8J NO U O N/AO and m uso.n ,), b loc k wall s not lik e l y t o co llap se o nt o th e e quiplll e nt? 9. D o all ac h ed li ncs hav e ad e qllat e Il exi bility t o avoid dallla ge'! Y[8J NO U O N/AO 1 0. Ba se d o nth e above seis llli e int erac ti o n eva lu a ti o n s, i s e quiplll c nt fr ee Y[8J NO UO of p ote ntiall y lid verse se i s llli e int erac ti o n e n ce t s? Other AdY e!'se C OIl<iitions II. H ave )'O U l ooke d l o r a nd I l llllld no o th e r se i s llli c co nditi o n s th a t cOlild Y[8J NO U O ad verse l), afl cc t th e ,a l'e t y lilll c ti o n s o fll.e eq lliplllellt

? Foreign Malerial (fuses, w ire , me/al r/e bri s) f o un r l a/ ba se o f pan e l lIa s I Jeen remover/'

/I is n o/ a se i s m ic conce rn. CAP 01451358 was genem/er/.


C ommellts (Add i tio n a l page s Ill a), be added a s lIece ssar),) /n/ernal i n spectio n p e lfOl/ll e rl. No co n ce rn s n o/ee/ in/el'llolly.

I;v aillateci h y: Dileep C ll er/opa/le (.y. 0,\"" Ij>\("'_ Mic/lae/ Woc/arcvlr fIt;;".tIJ-Dat e: 1011412014 10/14/2014 8-80 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Sh ee t 3 of 3 Sta tu s: v0 NO uO E quipm e llt ID No. _,----Eq llip. C l ass' (14 1 Distriblltion Panets Equipmellt Descriptioll

__ 8-81 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated Sh ee t l o f 3 Status: NO uO E quipment ID N o. E quip. C la ss' w (1", 4u.I __ O" i s", t", ri", b", ut", io"" L..J '--P"'a" ne"'/"'s __________ _ E quipm e nt De sc ripti o n L o c ati o n: Bldg. __ Floo r E I. __ Ro o m , Ar ea M a nul" , c tur e r , M o del, E t c. (o pti o nal but r eco mm e nded) Instructions for Completing Checklist This c h ec kli s t m ll y be u sed t o docum e nt the re s uits o f the Se i s mic Walkd ow n o f an it e m o f e quipment o n th e S WEL. Th e s p ace b e l o w ea c h of thc f o ll o wing qu es ti o n s ma y b e u sed t o re c o r d thc rc s uits o f jud g ment s and findin gs. Additi o nal s p ac e i s provided at th e end of thi s checkli st f or d o cum e ntin g other co mm e nt s. Anchorage I. I s the anch o ra ge co nfigul'Oti o n v e rifi c ati o n required (i.e., i s th e it e m on e yo NI8I o f th e 5 0% o fSWEL itcm s requiring s u c h v e rification)

? 2. I s the "n e h o rage free o f bent , brok e n , mi ss in g or l oose h a rdw a r e'! YI8I NO UO N I AD 3. I s th e an c h o ra g e lI'c e o f co rr os i o n that i s m o r e than mild s llrfa ee YI8I NO UO N/AO o xi dation? 4. I s th e an c h o ra ge free o f vi s i b le c rack s in Ih e co n c r e te n ea l' the a n c h o r s? YI8I NO UO N/AO 5. I s th e an c h o ra g e co nfi g urat io n co n s i s tent w ith p!.mt d oc um e nt a ti o n? yo NO UO N/AI8I (N ote: Thi s qu es tion o nl y appli es if th e it em is o ne o f th e 5 0% f o r w hi c h an an c h o ra ge c o nfiguration verifi c ation i s requir e d.) 6. Ba se d O JI the above aJl c h o m ge e valu a ti o Jl s, i s th e aJlchom ge fr ee o f YI8I NO U O p o t e ntiull y ad ve r se seis mi c co ndition s? I En t er ti ll: t.:q uip l1 l c nl c l a ss 11 11 1 1 1 1.: f ro m 13: C l as s cs o f '*: qU i pIIH.: IlL. 8*82 Prairie I sland Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated S h cc l 2 of 3 S t a t us: NO uO Seismic Walkdown Checklist (SWC) **** ____ Equip. C l oss' (14) Dis t ribution Panels Equ ipm e nl ID No. Equip m e nl Desc rip tio n Intcraction E ff ects 7. !Ire so n targe t s rr ec Ii'o m imp act by n ca rb y eq uipm e nt o r s ll'll c ture s'! YI8l N O U O N/AO !Ir e overhead c quipnlenl , d i s lribuli o n sys l c m s , ce ilin g lil es "",llighling , YI8l NO UO N/!lO a n d m asonry bl ock wa ll s n ot lik e l y to co ll a p se on t o Ih e eq uipm e n l? 9. Do a u ached lin es h ave "dequal c n cs ibilit y 1 0 av o id dama ge? yo NO UO N/AI8l I n. Ba se d O il th e n h ovc int erac ti o n cvn l u n tiol1 s , i s eq uiplll e llt fr ee NO UD n rp oic nli n ll y ndve r se se i s mi c inl cr:lc li o n c l rce l s'? Other A li v er s e Cu nliitiull s II. I lnvc yo u l ooked Inr "", I r o und no o lh e r scis nl ic co ndilion s Ih al cou lli adve r se l y n lT cc t th e sa f e t y !"ull c t io n s o rlh e eq uipm e n t? C Ollllllent s (Addi t io n;1I page s 11m)' be.! milled (I S ne ce s s ar y) Int erna l i ns p ec tion pe lf ormec l. No co n cerns fl oted int ernally. Ev a h,al e d b y:

__ !5Y.te Krieset YI25:l NO UO 1)"le: 091171201

'I 0911712014 8-83 S e ismic Walkdown Checkli s t (SWC) Pra i rie Island Nuclea r Generating Plant -Unit 1 Seism i c Walkdo w n Submittal Report, Updated S h eet 3 01"3 S t a tu s: NO uO E'I" i pill e l1\ II) No. __ E'III i p. C I a ss '...JILL1::!4L)

",D",is",t r", i b", u C!.!ti"olcc' LP"a"'ll e"'l"s _________ _ N ot,-: N o te: 8-84 Seismic Walkdown Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 1 0[3 Status: N O uO E quipm e nt ID No. ___ E quip. C la ss' (08) M%r-Opera/ed and Solenoid-Opera/ed Valves Equipment Description Location: Bldg. __ Flo or El_ Room , Area __ --.----------ManutRclmer, Model , Etc. (optional but recommended)

Jnsl .... ctions for Completiog Checklist This c h eck li s t may bc u scd 10 do e lllllent th c .. esu lt s oflhe Sei s mic Walkdown of an it em of equipment on the S W EL. The s pa ce below caeh of the following questions may be use d to record Ihe result s ofjudgmcnts and findings.

Additional space is pr ov id ed at the end oflhis checklist fOl' documenting other COllllnents.

Anchorage I. Is thc anchornge cOllfigurntion vcrificatioll required (i.e., i s th e it em OIiC yo N(8] of th e 50% ofS WEL itelll s requirillg s u c h verilieation)?


2. Is the anchorage free of ben I, brokell , mis s ing or loo se hnrdw"re? Y(8] NO UO N/AO J. Is th e 311choragc free of corrosion that i s lllore than mild surt:, e e Y(8] NO UO N/AO oxidation?

Mild surface o x idation is accep/able. 'I. I s the anchorage Ji-ee of visible cra cks in th e concrete Ileal' the anchors? yo NO UO N/AI8l Unislrul SlIpport i s welded 10 s/eel frame. 5. I s the an c horu gc configuration c o n s i s tent with planl doculllentotion?

yo NO LJO N/A(8] (Note: This question oniy applies if the it em i s one oflhe 50% for which on anchorage co utigurati o n vel'ifieation is required.)

6. Bo se d on the nbove n n c h omge evnlllotion s, is the nnch o ra g c free of Y(8] NO UO p ote lltially mlvel's e se i s mic cOlltiiLioll!-i?

1 Enlel' [h e equipment cla ss nnillC from AppClldix n: ofEq l1ipm c nl. 8-85 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Wa l k d own Submittal Report, Updated Seismic Waikdowil Checkli st (SWC) S h eet 2 of 3 Statu s: YrzJ NO uO Eq llil)m e lll II) No. E qllipm e nt D csc ripti o n Eqllip. C lll ss' (08) Motor-Oparata c l allc l So l alloie l-Operatacl Valves IIIt<motion Effeds 7. Arc so li t argets fr ee from impa ct b y nearby eq llipm e nt or s trll c tur es? Y{gJ NO UO N/AO S. Ar c over h ea d e qllipm e nt , di s tribllti o n sys tem s, ec ilin g til es and li g hlin g, Y{gJ NO lJO N/AO and ma 5 0l\l'y block wall s n o t lik e ly t o eoliap se onto the eq llipm e nt? 9. lJ o attached lin es h ave ad e qll a te lI es ibilit), t o avoid dlllllll ge? Y{gJ NO UO N/AO 10. Ba s ed o nthe above s e i s mi c int eracl i o n eva ill a ti o n s , i s eq llipm e nt fr ee Y{gJ NO UO or p o tent i a ll y ad ve r se se i s mi c interaction e rf ects? . Other Adverse C Ollditions II. Il ave YOII l oo k ed I b r and I b llncl no o ther se i s mic co nditi o ns that eO llld adverse l y an ee t t h e s af e l y Iiln ct i ons of th e eq ll i pme nt'l CU Ill III ell t s (Additiona l pa ge s 111<1)' be added as I1cc c.s sa ry) Eva illat e d h y: Oil oop C il e ri o nal/e C . ')J

  • t;, \0"1'1<" ,_A. n O_ Miclwel Woclarcyl<

f!t1'kt!J-j;;;.;,.,lJl::.-

Y{gJ NO lJO Dllt e: 10113120'/4 1011312014 8-86 Seismic Waikdowil Checklist (SWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated Sh ee t 30 1'3 S t a tu s: vl8] NO uO E quipm e nt II) No. ___ E quip. C l n ss' (0 8 1 M o lof-O p era t e d a nd S o/e n oi(/-O p erate d V e/ves 8-87 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Sheet 1 of 3 Statns: YI8! NO u O Seismic Walkdown Checklist (SWC) EquipmentlD No __ Eq uip. Class' (081 MO/OI'Operaled and Solenoid-Opera/ed Valves Equipmen t De sc ription Location:

Bldg. ___ rloor E I. ___ -. Room, /\rea ___ ------__ _ Manufacturel', Model, E t c. (opt ional but recommended)

Instl'nctions ful' Completing ChccJdis!

This c hcekl i st may bc tls ed to document th e rcsults of thc Seismic Walkdowu of an item of equipment on the SWEL. The space be l ow cach of the following que s tions mny be tlsed t o re co rd the result s of judgments a nd findings.

Additional splice is provided at the end of til i s checklist for documenting otller co nlln ents. Anchorage

t. Is the anchomge configumtion Ycrificlltion required (i.e., i s the item a ile yo NI8I of the 50% ofSWEL items r eq ui r ing stich veriticntion)?
2. Is the an c h omge free of bent, broken , mi ss ing or loo se hardware?

YI8I NO UO N/AO 3. Is the anchorage ti'ce ufcOI'rosion that is 111 000e thanl1lild s nri ace YI8I NO UO N/AO ox id a tion'! 4. I s Ih e anchor age !i'cc of visible cracks ill the cOllc ret e IIcar the ,,"chors'l yo NO UO N/AI8I 5. Is the anchomgc configuratio ll cOllsis/cllt with d oc um clllnt i on? yo NO UO N/AI8I (Not e: This question oilly applies if the it em is one oft hc 50% tor which on n nch orngc co nfigura tion verificatioll i s required.) 6. Bn se d on Ih e nilove anchornge cI'nluatiolls, is the anchornge free of YI8I NO liD potentially ndverse seismic cOllditions?

1 En ter the l'qll i plllcnt clHSS Il:Hll C lhll n J\pp c mli.'\ B: Cla s ses of Eqllipmcnl.

8-88 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Seismic Walkdown Checklist (SWC) Sheet 2 of 3 Status: yrgJ NO uO Eq uipm c llt m No. Equipmcllt De s eripti o ll ____ Equip. C ln ss' (08) Motor-Ope rated and Sote n oid-Opera t ed Valves J IIlemelioll EITed. 7. Ar c so rt tar gc t s n*c c li'o m impact b y IIcarb y cquipmelll or st ru c tur es? YI8l NO UO N/AO 8. Ar e ov e rhead e qllipmellt , di slrib llt ioll sys tem s, ce il ill!!, til es nlldli!!, htill!!" YI8l NO U O N/AO Hlldmnsolll'Y block lI'ali s 11 0 1 lik e ly 1 0 co llnp sc Ollto Ih e eq uipm e llt? 9. D o nUn c h e d lillc s hnl'e ndequ"t e fl e xibility t o II 1'0 id dam,,!!, e? YI8l NO UO N/AO 10. Onse d olliho "bol'e s e i s mi c illtera c lioll ev"lu"li o ll s , i s cq uipm e llt Ii'c e YI8l N O UO or POlclltially adverse s e i s mi c int crac li o JI crrcct s'l Other Adl'el's,'

C,,,,,liliulIs II. H"ve yo u l oo ked luI' ,,111 1 roulld 11 0 othe r s ei s mic cOll diti o ll S tl"'l cou ld nclv e l's cly nrr ee l th e s nl e ty rUll e ti o ll S o rthe eqllipmellt?

CO l1llllents (Additiol1al pn gcs Illa y h e "del e d a s tl'" III" l e d by: Dil eep Cher/apalle c:.y , n-,\op pKu,.,.",d.

Michae l W a dar cy l<

YI8l NO UO Dnl e: 10 1 13/2 014 10 1 13/20 11 8-89 Seismic Walkdown Check l ist (SWC) Pra i rie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Sheet 3 of3 Stalus: NO uD Eq uipm e nt If) No. __ E'l uip, Clnss' (081 M%r-Opera/eel anel So/ellojc/-Opera/ec/

Valves 6-90 c Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated 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 six deferred Area Walk-Bys. Table C-1 below provides the list of the deferred Area Walk-By checklists 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 include information on the location of SWEL components , which is considered Sensitive Unclassified Non-Safeguards Information (SUNSI), of which the loss , issue , modification , or unauthorized access can reasonably be foreseen to harm the safe operation of the nuclear plant. Pages which contain SUNSI information have been mar k ed with a header , and the sensitive information , such as locations and pictures of safety-related components, has been redacted.

A copy of this report with the SUNSI information redacted has been provided as Enclosure 2 of this letter package. C-1 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated C-2 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Sllcct I 01'3 Stntus: yO N0 uO Area Walk-By Checklist (AWC) Localion:

Bldg. ___ Floor EI. __ . Room, Areal _ Instl'uctions fol' COlllpleting Cheer,list This c he c kli s lmay be u se d 10 d oc um en t th e r es ult s of Ih e Area Walk-By ncar o ne or m o re SWEL ilems. The space below each of Ihe following qucslions Illay b c ll sed 10 re co rd Ihe results ol'judgmenls and findings. Additi o nal space is provided at the end oflhis checklist for documenting other comments.


I. Does anchorage of equipment in the area appear to be frec of YC8I NO UO NiAO p O lenlially adverse scismic conditions (if vi sib le without ncees sa rily opcning cahinols),1

2. Docs anehol'flAc ofeqllipment in thc area appeal' to be frcc o l'signiticant yo NC8I UO NiAO degnlded conditions?

Rack witll F/S 18365 missing 1 of 4 wall anchors. Component is IIgl1lweigl1l

3 o( 4 boll s are acceptable (or seismic load s. AR 01451548 was initiated. WO 00511079 initiated for installing missing ancllor. J. Oa scd on a visual i n spectio n from the 11001', d o the cableiconduil YC8I NO LJO N/AO mcewa)'s and HV AC dlleting appear 10 be frce of potcntiall), adver se se i s mic co nditions (e.g., condition of s upports i s ade quat e lind fill conditions of cable tra)'s appear to be insido acceptllble limits)? Overhead conduit aI/ached via beam clamps fo VB/tical feg of auxHiary stee l anglas above TB 1137 and TB 1182. Tile condu it is lightweight; impact on cabinets below would be negligible during a sais mic event. 4. Dues it appeal' thnt the area is Ii'ee of pot en Ii a ll)' adverse sc i s mic spatial YC8I NO \)0 N/AO interaction s with 0 1 her equipmenl in Ihe mell (e.g., ceiling tiles and lighting)'!

I Htlle room in whir.h Ih e SWEL item i s l oenled is very large (e.g., TuriJ ine Hall), I he ;u"e a se l ected sho uld b e described.

This se lect ed nl'cn shOilld he based onjudgmcllt", c.g.) 011 th e oJ'der of abOllt 35 fe c t fl'O l1l the S\'V F.J. itc:m. C-3 Prairie Island Nuclear Generating Plant -Uni t 1 S ei s mic Walkdo w n Submittal Report , Updated S h ee t 2 ot'3 S t o tu s: y O lJO Ar ea W a lk-B y Ch e cklist (AWC) L oca t io u: Bld g ___ 1'1 00 1' r.t. ___ 1(00 111 , 5 , Docs it appca l' th a t al'ca i s rl'ee or p o t c nti a ll y a d verse seis m ic YI8I NO lJO N/AO int e ra c ti o n s tl lll i co uld Cll ll SC fl oo dill g o r S p nty i n (h e n r en? Co n c l ellsa ti o n (ro m coo li ng l i n es is no/ a fl ooding COl/ce rn , 6, D ocs it a pp em' th a t th e a r e a i s fr ee o r p o t e nti a ll y a dv e r se seis mi c YI8l NO lJ O N/A O in terac t io n s th at co uld co u s e a fi re i ll th e orca? 7, Docs i t ap p eo l' t ha t t h e nl'eo i s r r ee o l'p ote ntinll y a dv e r se se i s mi c YI8l N O 1 10 N/i\O int e ra c ti o n s nssm.: i a l e d w ilh h O ll se k ee pin g pr ac tice s, s lol'll ge o f p o rt a bl e eq uiplll e nt , n nd t e lllJl ol'H l'Y ill s l a ll a li olls (e,g" sea ll o ldill g, I ca d , h iel d i Il g)? 1'em p oraty oll/age-r ela/or l eCfllip m onl/o I le re m oved prior 1 0 r es l art is accep t ab l e , 8, 1'llIv e )'0 0 l oo k e d ror n n d fO ll ll d 11 0 o lh e r se i s llI ie e o n dili o ll s Ihal eo nld YI8I NO lJO o d ve r se l y n l Tee llh e sare l y l i m e li o n s o rlh e e qui p lll en i i n I h e ar e a? Co mm e nt s (A d d it ionn l p nges Ill a y he a dd ed n s n cccssnry)

Eva I o a I c d by: D ilcO I ,-l "'C"J I"'e"" r Jo""""Ja"'/"" o'---__ ", G"""" V'-',->.h"",.u 1 '1'1'

): \ "" .. 8 e II iI;:j Da l e: 1 0/1 4/2011 Mic h ael Wo d arcvlc 1 0 11412014 C-4 Area Walk-By Checklist (AWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated S h ee t 3 o f 3 S tntll s: yO N!8J u O L oc ati o ll: Bld g. ___ Fl oor E I ___ I tOO Ill , !\r ca' _ C-5 Prairie I sland Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Siteet I of 4 Stat u s: NO uO Area Walk-By Checklist (AWC)

Bldg, __ Floor Ill. _, Tnsh'ue!iulls fol' Completing ClI.clellst This checklist may be u sed 10 document the results of the Area Walk-By near one or more SWEL ilems, The Sllaee below ""ch of Ih e /ollowing queslions be u scd 10 record Ihe re s ults of judgments and ilndings.

Addilional spnce i s provided at the end of t his c h eck li sl for documenting ot h er conllHcnls.

I. Does nnchornge of equipment in the aren nppcnr 10 be free of YI8l NO UD NlAD potenlially adverse seismic cond iti ons (i f visible lI'ilhout necessarily opening cabinets),1 Bent-plate rack with 1LT*427 is motlnted to the concrete vaull wall via 4 anchors. TllO 2 anellors all tlla bottom of tila rael( ara not within the bolt holes of the bent-plate, btlt instead are located below tile plaia; the edge of the plate bears against tile ancllOrs. Tile typical 4-anchor configuration for these racks is evaillated ill ENG-CS-064 , Each anchor ill the typical configuration is lightly loaded (maximum IR of 0.20 ill Ihe dead+SSE l oading condition), In addition, the lower bolts are not in tension and tlJUS have lesser IRs than 0 , 20, Conservatively neglecting any contribution from the lower bolts in tension or s/18ar and thereby cloubling the IR for tile upper bolts, tile I R i s still less tilan 1 , 0 , Tile existing ancllOrage configuration is acceptable , CAP 01455254 and WR 00108837 are initiated for 1LT-427 wall bracket bottom ancilorage , 2. Docs anchorage uf"quipmellt in the area appeal' 10 be li'ee of'signilicanl YI8l N O UD NlAD dcgrmled cOlJ(liti uns', 3. Based on a visual inspection fi'om the nOOI', do the cable/conduit YI8l NO UD N/AD meeways and HVAC ducting appear to be Ii'ee of potenlially adverse se i smic conditions (e.g" condition of'supports is ade"uate and fill conditions of cable trays appeal' 10 be inside ncceploblc limits)? I Jfthc room in whidl the SWET , itel11 is I Ot'llt('d i s vcr)' lurge (l t g., 'I'll I'hiIIC HIlII), Ihe 81'C!\ sCIe.C I Cd shou ld he dt's cribeti, ThiS sele("ted Ol"C(l should he based on judgment, e,g., 011 the. order of ahoul35 feN rrollllhc SWEl. ileln. C-6 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Sheet 2 of 4 Status: yrgJ NO uO Area Walk-By Checklist (AWC) Location: Bldg. __ FloorEI. RooJ11 , Arca_ 4. Does it nppenr that the nren is free of pol e nti a Ill' adverse se i s mi c spatin l YI8I NO UO NlAO intera c tion s \Vilh other equipment in the area (e.g., ceiling tiles a nd light i ng)? S. Docs it appem' that the nrca i s frec of pot e ntia Ill' adve rs e sei s mic YI8I NO UO N/AO internet ions that could cause flooding 01' s pray i n the nrea? 6. Does it appeal' that th e area is free of p oten tially adverse se i smic YI8I NO UO NI AD intera c tion s that could cause a tire in the arca? 7. Docs it appear that the area i s Ii'ec or potentially adverse seis mi c YI8I NO UO N/AO intera ct ion s assodated with h o u s ek eep in g practice s, sto ra ge of portable equipment, and temporary installati o ns (e.g., sca ffolding, lead s hielding)?

Temporary olliage-relaled eqllipmenl fo be removed prior 10 re s/an is accepla ble. ----_._ .. _--------8. l'lal'e you looked for and I" und no o lher se i sm ic conclitions thai cou ld adversely al'l'cctthc s alcty function s oftlw equipment itl tlw arc a? YI8I NO UO C-7 Area Walk-By Checklist (AWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Subm ittal Report. Updated S h ee t J of' 'I S tlltu S: y (gJ N O uO L oc ati o n: Uld g, ___ 1'1001' E I. ._ R OO I11 , Ar e n' _ C Ollllllellis (Ad d iti o nal p a g e s lila>, b e adtl ed .\$ ll Cccs s ilr y) E I'll h, n t cd b y: __ -,, C.,,--,' V ,--,'Cj D2'.L' ..,\ ... Q'"' ... l'-bk .... "".........c9.0_""-',....A

.. n a t e: 10 1 14 12 014 Mic ll ae l W o clar cy le '10/14 12 01 4 C-8 Area Walk-By Checklist (AWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated S h ee t 4 0 1'4 YrgJ NO uO Locntioll:

Bld g. ___ PloOl' E I. ___ Roolll, Ar cn' __ _ C-9 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Area Walk-By Checklist (AWC) Locati o n: Bldg. ___ F lo o r E I. _ IlIstl'lIcliOlls fol' Complcting Chccldist Room , A r ea'_ Shect I 00 Status: NO uO This c h ec kli s t mil)' be u sed 10 d oc ullIentthe re s uit s of'thc Ar ca Walk-By II ca r aile 0 1' mor e SWEL ilem s. Thc s pa ce below cac h o fth e foll owi ng qucstions llI ay be u sed t o rc cor d the r es uits of judgments alld filld ill gs. Additiollal spacc i s provided nt the clld of this c h ec kli s t for d oc uillen t ing o ther co mm e nt s. I. D oes " n c h orngc of e quipment in th e area nppear to be fre e of Y!8! NO UO N/A O potentially adverse se i s mic co udit ions (if vi s ibl e without n ecessa rily o p c ning cnbillets)?

2. D ocs a n c h oroge of' cq ui p mcnt in tb c arc a nppcn>' to be f ,'cc of s i g nifi can t Y!8! NO UO NlA O d cg rnd c d co nditi o n s? 1) A I Ih e sou thw es t colum n o{ steel {ramo ad ja cer1tlo MCC IV Bu s 1 and Bus 2 (supporting TB 1 FMD4), II/er e is a n anchor wit/lOul (ull thread engagement 10 lh e base. 1 thre ad is nol engaged. Jud g ecl to be acceptable.

Pe r ca l cu lati o n ENG-CS-080 , th e existing ""e ad engagement is adequate. 2) Tube cle m p is no t engagod f o f' " Loop A Hot Leg 11 RCP V a ull" tubing. Tube i s fl exiblo and is suppo rt ed n ear 1/10 un-engaged clamp. /I was ju dged t o be acce pl a/J/e. CA P 01452744 a nd WR 010813 3 were generated. J. [la se d 0 11 It visunl in s pecti o n 1;'01 n til e nODI', d o the cable/conduit Y!8! NO UO N/AO ra ce way' 111](1 HVA C ducting appe a r t o be free o f' pot e ntially a d verse se i s mi c conditions (c.g., condition of s upp orts is Adequate and till condilion s ofe.blc Iray s appcar t o bc in s id e nc c cptnble limit s)? 4. Doc s it appenr th n l th e nrcn i s fi'ec o f potent in Ill' ndv erse se i s mic s pnti nl Y!8! NO lJO N/AO int ernc t io ll s with ot h er eq\lipment in th e nrcn (e.g., c eiling tile s and li g htin g)? I Hlhe 1'00111 i ll which til e SWE L il e m i s J ocn t ed i s y cry l Arge (c.g., Tur bine H n ll), th e nren selec ted s h o uld be descrilled.

This s e l ec ted u r ea shou ld b e bll!;(!cI flnjurlg m c lIl, c.g., Olllhc orci er of n botH3 5 re e l from the SWEL item. C-10 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated Area Walk-By Checklist (AWC) Sheet 2 o rJ Stntll s: NO uO Lo c atioll: Hldg. 5. Do cs it appear Ihat the arca i s frcc ofpotcliliolly advcrs e se i s mi c YIEI NO UO N/IIO inlernctioll s that cou ld ca li se Ooodill g or s pray ill th e ar c a'? G. Do o s it appear Ihat the nrca i s Ii'co orput c lltinll y adl'crse se ismic YIEI NO UO N/AO int e ra c ti o n s thai co uld C:l Il SC a lire in th e urea'! 7. D ocs it app ea r that th e "rcn i s li'ec or p o t o lltially adv e r se se i s mi c YIEI NO UO N/AO illt c ra ct iOll s n s s ocintcd wit h h o u sekee pill g pmel i c e s, s t ornge of p or tnhle equ ipmellt , alld temp orn r y ill s tall"l io ll s (e.g., s enfloldillg , lend s hi e ldillg)? Temp o ralY o lil age-re ial ecl eq llipmellil o lJe remove (1 plior 10 reslart i s accep la/)Ie. R. Ila ve YO II l oo ked 1'0 1' alld l a ulld 110 u th e r se ismic co llditi o ll s th at cOlild YIEI NO UO adver se ly anee! th e sa r e t y fUll c ti o n s ol'th c equipment ill the ar('a? COIllllll'uts (At.lditi{lIlHi pagt=s lIlil)' u e m ld cd , I S lI e c e s sa ry) ["" hint ed h y: Di/eep Cher/opalle c*v* Dat c: 10//31201 4 Mic/wel WoclareVI<

1011312014 C-11 Area Walk-B y Checklist (AWC) Location:

llidg. ___ 1"1001' E I. Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated ROOIll , ArCH' _-I-I S h eet 301'3 S i nl u s: y[gJ NO uO C-12 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Area Walk-By Checklist (AWC) Locntion:

Bldg. __ Floor 1:11. .' Instl'uctiOJIS fol' Com pIe ling Checklist Room, Arcn' _ Shcet 1 of3 Status: NO uO Thi s checklist IIIny be used to doculllent the results orthe Area Walk-By nea,' one or more SWEL items. The spnce below each of the following que st ions mny be lIsed 10 r eco rd the results o fjudgmenl S and findings , Additional space is provided at the end of this check li s t for documenting other comlllents.

I , Doe s auc1lOmge of equipment in the arca appeal' to be free of potentially adverse seis mie conditions (if visi ble without necessnrily opening cabinets)'!

YI8I NO UO N/AO 2, Docs anchorage of equipment inlhe nrcn appenr 10 be fre e of significmlt YI8I NO UO NI AD degrnded conditions'!

3. Ba se d on a visual inspection Ii'o lll the noor, do the cable/conduit YI8I NO UO N/AO raceways and HVA C du e ling appeal' to be 1\'ce ofpotcntillily ndver se seismic conditions (e.g., condition of supports i s udeqnate and fill conditions of cnble tmys nppcnr to be inside ncceptable limits)? 4. Doe s it appeal' that the arca is r,'ee of potentially advers e seismic spatial YI8I NO UO N/AO interactions with other equipment in the lIrea (e.g., ceiling tile s and lighting)'!

Liglltiflg is rigklly-suppDlted. I Trth e 1'0 0 111 in whkh til e SWEl. it e lll i s lorated is vel')' large (e.g., Turbin e Bnll), the lIl'e-a se le c ted s hould be des c rihed. This selec ted fll'ea shoilid be bAs e d 011 judgmen t, e.g., 011 Iht! order or ahemt 35 fet:1 frolll Ih e S\\'EL item. C-13 Prairie Island Nuclear Generating Plant -Un it 1 Seismic Walkdo w n Submittal Report , Updated Area Walk-By Ch ecklist (AWC) Loclliion:

B ld g. ___ I'loo r 12 1. _ I(no m , ArCll' _ S h cc i 2 or J Slnl ll s: NO u O 5. Does il app e ar Ihallh e arCa i s rree o/"polcnli" ll y "dv e r s e sc i sm i c YI8l NO UO N/AO int e racti o n s th a t co uld ca li se fl oo din g O J' s pra y ill th e Cir ca? All pip es a r e welded. 6. /)o es il nppcn,*lhnt th e nrcn i s n*cc ofpatcntinlly "dv e r se se i sm i c YI8l NO UO N/AO int e rn c tio ll s Ihnt co uld c a li s e [I lire in Ih e flrcn? 7. Does it nppear th n l the nren i s free arp ate nti n lly ndv e rse se i smic YI8l NO UO N/AO intera c ti o n s ns s o c int cc l wilh hOl1 5ckec pin g (lm c li cc s, stortlge o fp n rlnbl c eq llipm e nl , nnd t e mpo r", y ill sta llali o n s (c.g., s cn lT a ldin g , l ead s hi c ld ing),! Tempor8fY o ll/age-rela/er l oq ll ip m e n//o IJe re m over l prior/a res/aI! is aeeep/aI J l e. --------------------8. 1*111 ,," YO Il lo"k e e l f o r'lIIe1 rOllnd no o th e r se i s mi c c o n d ili on s Ih n l co uld Y I8l NO U O ndvcr s ely n ff c e t Ih e sn f e l Y funclions o rlh c e quipm en t inlh e nr en'? 4" d ia m e te r s l ai nl ess s/eel p ipe li as U-boll wi/ll l oose rwl s. Pipe i s a e l rain f rom 1 3 FCU CO ND Ca LL l a nle Nul s on /11 0 interior si d e o f /lI e angle 1 0 wllie ll U-/Jo lI i s m O llnl ee l a r e l o rqu ee l s uffi cie n/ly a mi p reve nl l a leral m o v e m e nl o f /lIe pip e. C l a mp s lipporll Je l ow U-boll a/ (f oor p e n e l ra tion p rovie l es ae l e lition a l s llpp o rl. Movemen/ dllrin g seis mi c eve nl wOll/cllJe min ima l. J ll c l gecllo I Je accep l a/)/e. CA P 0 14 55258 ami WR 0 01 088 39 a re inilialec/. -'--------


C OlHllI C lIl s (Additional pages m ay b e add e d as n e ces s ary) Eval ua led b y: D il eep C ll er l opal/e M i c/mol W odnrcv l c 10//3/20"/4 C-14 Area Walk-By Checklist (AWC) Prairie Island Nuclear Generating Plant -Unit 1 Seismic Wal k do w n Submittal Report. Updated S h ce t] o r] S t n tu s: v l2?! NO uO L oca ti o ll: Old g. ___ Fl oo r 1>1. ._1-R o o m , A l'c a' _ C-15 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Area Walk-By Checklist (AWC) Sheet 1 of3 Status: ycg) NO uO _ ..

______ .___ ['100" EI. ___

Mea' IIIIIII!I:::

_ ::: .. ==========_ rnstnlCtion.

fol' Comllieting Checklist This checklist mny be used to document the results of the Aren Walk-By near one or more SWEL items. The space below each of the following questions may be u se d to record the resulls of'judgments "nd finding s. Additional space i s provided at the end or this checklist for do c umenting other commonts.

I. Docs anchorage or equipmcnt in the area appea,*to be frc o or potentially adverse seismic conditions (if visible without nece ss arily opening cnbinets)?

YI81 NO UO NlAO 2. Docs anchorage of' equipmcnt in the arCR appear to b e fr ee of s ign iii cant YI81 NO UD NIAO dcgraded conditions'!

3. Oased on a visual inspection li'Ofl1 the nOllr, do the cable/condnit YI2I NO UD N/AO raceways and HVAC dneting appear 1 0 be free of potentially adverse seis mic conditions (e,g" condition ofsupporlS is adequate and liII conditions of cable tmy s appear to h e inside acceptable limits)? Temporary olltage*relaled cables to be removed prior to restart ar e acceptable.
4. Do es it nppcnrthnt the arcn i s fI'cc ofpotcntinlly n dv c rs c sc ismic spatial Y{8] NO 1)0 N/AO interuction s with other equipment in the IIrea (e.g., ceiling tile s lind lighting)?

TemporalY olltage-relatecllig/lting to be removed plioI' to !estall is acce ptable. I l[(h e room ill which th e S\VEL item is loc ated is vefY l arge (e.g., Ttll'bine.

II a ll), th e area se le cted should be de sc ribed. This selecteel um/l should 1m )HlfWd 011 judgm e nt , c.g., 011 the! order of nlwut 35 f cc l rrom the SWEL it em. C-16 /

Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report, Updated Area Walk-By Checklist (AWC) I.oe" tion: 1l1<lg, ___ 1'1001' ,,1. __ S h ee t 2 0/"3 Stntus: NO uO 5. D ocs i t ap p c al' that th e nl'c n i s li'ee or p o t e ntially a"v c r se s e i s lIli e Yl'8l NO UO NI AD in t c r i l c ti o ll s th nt co uld c au se fl oo din g o r sp r ay in th e ar ea? 6. Do cs it npp e nr th ot th e al'ca i s rl'ce or p o t e ntia II)' o<l vc l's e sc i s mi c Y l'8l NO UO N/AO int e m e ti o n s th n t co uld cn u se n fire in th e ol'eo? Gas /J o lli e i s adeq uat e ly r es t ra in ed, 7, Do cs it app e nl' th nt thc ol'cn i s li'ee of p o t en ti n il y n dve l'se sc i s mi c Yl'8l NO UO N/AO inlern c lioll s H!:isoc ialed with h ousekee pin g pl'll c li c c!-i, s t o ra ge o rpnrlabl c equipm e nt , nn d tem p orary in s tallat ions (e,g., se llm,ld i ng , lead s hieldin g)? T e mp o rmy o llt age-r e lat ed equipment t o lJ e r e m ovec l pr ior 10 r es tm1 i s ac ce ptalJl e, 8. Il ave yo u l ooke d I e I' a n d l'o und no o t he r se i s mi c co ndi t i o n s th nt c o uld ori ve l'sc l), nrf ee t th e s o r e t)' l i lll c l ion s of the e quipm e nt in the nl'c o? Comllle nt s (Addition n ill ngcs ma y b e il<ld c cl o s n c cc ss iII')') Yl'8l NO UO Ii "" I u at c d by: DileSI",) ." C"-,/l"-e l",'l o", p",a,,," ,,-e __ -,C,-,,.v,,-,-,. D.l.-' \","'"-1'\"'<.

... ,.,,, ..... ,,.. nil t e: 1011312011 11t;;".t/

j).

t/

__ __

Mic ha s l Wo c l a r GjI/( C-17 Are a Walk-B y Checklist (AWC) Prairie Island Nuclear Generating Plant -Un it 1 Seismic Walkdo w n Submittal Report , Updated S h eet 3 of3 S t at u s: NO uO I.ncetio,,:

B ld g. ___ Fl oo r 1'.1. __ C-18 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Area Walk-By Checklist (AWC) Sheet I 01'3 Slatu s: yO N0 uO Location: __ Floor fl. ___ Room, Area? Inslnlcn,,"s for Completillg Chccldist This chcckiisl may be II se d 10 do c ulll on llh c r esu lt s oflha Area Walk-By near one or more SWEL item s. The space below each of the foll o wing qu es lion s m ay b e u sed t o re co rd th e resulis ofjudgmenls and findin gs. Additional s pace is provided ot the end ofthi, c heckli st for doculllentin g othel' COllllllents . . _-------I. Does anchorage of equipment inlhe area oflflenr to be free of Y!8l NO LJO N/AO potenlially adverse seismic conditions (if visible wilhout necessarily opening c llbin ets)? 2. Docs onchorngc ofeqllipll1cnl in the area appear to be free ofsigniliealll YO NI8/ LJO N/A O degmded conditions?

Ra ck containing 1FT-475 and ILT-471 is missing 1 of 6 wall anchors (bollom left a n c llor). The remaining 5 of 6 ancllOrs are in good condit/on.

Rack and equipment are light compared to anchor capacity.

Exisllng configuration Wit/I 5 of 6 8ncllors is acceptable by engineeri ng jlldgment CAP 1451550 anci WR 107748 are generated for this condilion.

3. Ba sed on" visual inspeclion

!i'OInlhe noor , do Ihe cable/conduil YI8/ NO UO N/AO race","ys and HVAC dueling appeal' to be n'ee 0 1' polonlilllly adverse seis mic cond ilions (e.g., co ndition of sup pOI' Is i s ndcquale and Jill conditions of cable tmy s "ppem to be in s id e acceptable lilllils)?

4. Docs it appear thai th e nrca is free of pot en ti n Ill' ndvcrse seis mi c s p a lial YI8/ NO LJO N/AO interactions with olhel' equipment in th o area (e.g., ceiling tiles nnd lighting)'

1 'If t he room in which the SWEL item is loca ted i,,'el), larg e (e.g., Turbine Ha ll), the area selecte d should be described.

This se le c t ed nrCH should bt' bH.'i C d o njudwn e llt, e.g., 011 th e DI'del' of about 35 f eet from th e SWELitcm. C-19 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Area Walk-By Checklist (AWC) -----L oca li on: Dldg , __ rl no r E I. _ Roolll, A r ca' _ S h ee l 2 of) S lnlU s: yO N!8l u O 5, Docs il :Ip p enr Ih n l Ih c are n i s fre e of p O l enl iall y a d ver se s e i s illi e YIlSI NO UO Nt AD int crac li o ll s Ih n l cou ld cn u sc no o d ing o r sprny ill th e or c n? G, Docs il "pp e ar Ih"t th e ar ea i s free "fpal e nlially "elvc r s e s e i s illic YI8l N O U O NlAO inlernelinns Ihal co uld en u se" fir e in Ihe n r en? 7 , Ones il appeal' Ihat Ih e arc a is Ii'eo of p O l ell liall y adve r se s ci s illi c YI8l N O lJO NtAO inl en:lc li o ll s associil ted w ith II01I sc k ccp in g pmc li ces, s t orage O f pDrl abl c equipment, nlld temporary (e.g., sca l To ldill g, l ea d s h i e l eli Il g)? Remov a/ of /I re l emporary equipmen l (slag e d f or oll i age) /Je f ore slal1 up i s aeeeplalJ/e, 8, Il n l'e YO Il l ooke d fo r nnd f nllnd 11 0 o l he r scis illi c eo ndiliolls Ih nl cOlil d YIlSI NO UO adl'e r s cty anecllhc sale l y lilll el i o ll s O rlh e O ,!lI iP Ill C IlI in Ih o arca'l C omment s (A d dit i ona l p ages Ilw)' be addc(1 a s Ilccessnry)

r. Vlll ll ntcd by: Dileel!...) "C'-'-/r e""""/o"'p"'a"'"e"-_---"'--', ,,V"".I"P"-,, IlJ!e ... .. .. ::l!-----Dnl e: 1011312014 Michael Woc/arey l' f/!";,,.dj 10/13/2011 C-20 Area Walk-By Checklist (AWC) Prairie I sland Nuclear Generating Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated S h ee l) 01'3 $Ini lls: yO uO --------------------------------------------------------------

Loc nlioll: Bld g. _---rl oo l' EI. ___ R oo m , !\ren' _ C-21 D Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown $ubmittal Report, Updated 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 Peer Review of SSC Selection , of Reference

1. 0-1 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report , Updated Peer Review Report for Near Ter I Task Force (NTTF) Reco nmendation 2.3 ;eismi : Walkdown Inspect .on co Ipleted after November 26,2012 of -P r airie Island Nuclear Gene Station Unit 1 Marlene )elaney December 30, 2014 Prepared by Peer Reviewers Marlene M Delaney, SE, PE (Team Leader) Philip Gazda, S :, PE Dileep Cherlop aile S. Seilhymer Peer Review Team Leader Certification Signature Date: 12/30/14 0-2 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Introduction Overview This report documents the independent peer review for the Near Term Task Force (NTIF) Recommendation

2.3 Seismic

Walkdowns performed after November 26,2012 for Unit 1 of the Prairie I sland 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 Wa lkdo wn Equipment List (SWEL) specifically focusing on changes made to the SWEL after November 26, 2012.
  • Review of a sample of the check li sts prepared after November 26 ,20 12 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 1 are Ms. Marlene M. Delaney and Mr. Phi lip Gazda of S&A, and Mr. Dileep Cherlopalle and Mr. 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 e x perience. She has received the Seismic Capability Engineer (EPRI-S QUG) 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 Wa l kdown Engineer (SWE EPRI 2-day training). Mr. Cher lo palle from site engineering and Mr. S. Sei lhymer from the plant 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 1. Revisions to the SWE L 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 conta in ed in this peer review report. D-3 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated Interviews were conducted with the SWE inspection team after review of a sample of the Unit 1 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 , and Dileep Cherlopalle, of the SWE inspection teams on December 4 , 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 1 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 1 after November 26 , 2012. Peer Review Activity -Selection of SSCs The guidance in EPRI Technical Report 1025286, Sei s mic 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 initial SWEL: Mr. P. Valtakis, Prairie Island Plant Operations 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.

D-5 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report, Updated

  • Verification that the SSCs selected include an appropriate representation of items having the following samp l e selection attributes:

o Various types of systems o Ma j or new and replacement eq u ipment o Various types of equipment o Va rious env ironm ents 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 la ck of accessibility to perform 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 SWE L for SSCs walked down after November 26, 2012 determined that the SSCs selected include a sample of items that represent each attribute/consideration id entified above. Peer Review Findings -Selection of SSCs This peer review found that the process for selecting SSCs that were added/removed from the initial 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 December 22, 2014 is attached to this document.

Resolution of Peer Review Comments -Selection of SSCs A ll comments requiring resolution were incorporated prior to completion of this peer review. Conclusion of Peer Review -Selection of SSCs This peer review conc ludes 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 C l ass I equipment and systems to meet the objectives of the NRC 50.54(1) lette r. 0-6 Prairie Island Nuclear Generat i ng Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Review of Sample Seismic Walkdown & Area Walk-8ys Checklists Overv i ew A peer revie w of t h e SWCs and AWes generated after November 26,2012 w as performed after w hich a n intervie w was conducted w i t h the SWE inspection team in accordance w ith the Seismic Walkdo w n Guidance (SWG) requirements.

Intervie w s were conducted w ith the SWEs on December 4,201 4. The SWE trained w alkdo w n eng i neers w ere Messrs. Kyle Kriesel , Dileep Cherlopalle , and Michael Wodarcyk. Sample Checkl i sts Table D-l li sts the SWC and AWC samples w hich rep r esent appro x imate l y 34% of the SWCs and 50% of the AWCs. Table 0-1: SWC Samples from Seismic Walkdown Inspection for Unll1 performed after November 26 2012 Equipment Equipment Class Walkdown Item Observations Identification 1FT-464 18 MN STM FR 11 STM GEN CHNNL I RED F XMTR No concerns. 11 BATT 16 No concerns. CHG 11 BATTERY CHARGER l l l NV 16 11 INVERTER No concerns. 075-012 9 122 CONT RM CHLR No concerns.

No concerns. MCC lAB2 1 MOTOR CONTROL CAP written for CENTER lAB BUS 2 housekeeping i ssue but no impact on seism i c capacity No concerns. BUS15 3 BUS 154.16KV ARfWR w r i tten for missing SWITCHGEAR scre w but no impact on seism i c capacity. MV-32141 14 14 FCU CLG WTR OUTL No c o ncerns. ISOL MVA PNL12 1 4 DISTRIBUTION PANEL 12 No concerns. No concerns. FEM issues PNL 153 14 DISTRIBUTION PANEL addressed. CAP 15 3 generated. SV-37460 8 Ul TRN A CHLD No concerns. WTR/CLG WTR ISOL SV 0-7 Prairie Island Nuclear Generat i ng Plant -Unit 1 Seismic Walkdo w n Submittal Report , Updated Table 0-2: AWe Samples from Seismic Walkdown I nspection for Unit 1 performed after November 26 , 2012 Area Walkdown Description Observations Note that checkl i st is N based on field w alkdo w n notes and is 1CNTM 715-NORTH not revised to a Y status even though there are no seismic concerns. Th i s is consistent for the project. AR w ritten to resolve issue. 1CNTM 735-EAST No concerns. Issues identified during w alkdo w n resolved via judgment or CAP. Note that checklist is N based on field walkdown notes and is 1 CNTM 755-WEST not revised to a Y status even though there are no seismic concerns. This is consistent for the project. All issues resolved via judgment or CAP. Evaluation of Findings There w ere no find i ngs that challenged the licensing bas i s. Tables 5-2 and 5-3 of the Seismic Walkdo w n Report (final submittal report) prov i de the lists of the issues encountered for th e equ i pment seismic w alkdo w ns and area w alk-bys. All i ssues w ere adequately addressed on the SWCs and entered into Tables 5-2 and 5-3 as appropriate. The scaffolding and seismi c housekeep i ng procedures w ere revie w ed by the SWEs in order to gain a full understanding of the plant pract i ces in regard to those procedures. The r e w ere no seismic concerns noted i n Unit 1 w ith regard to scaffold erection. The scaffolds w ere properly t ied off and braced , and properly tagged with respect to the procedure. The peer rev i ewers consider the judgments made by the SWEs to be appropriate and in accordance w ith the SWG. 0-8 Prairie Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submitta l Report, Updated Review of Licensing Basis Assessments Tables 5-2 and 5-3 of the Seismic Walkdown Report provide a list of the i ssues encountered during the Unit 1 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 we re identified that resulted in a seismic li cens in g basis evaluation.

The peer reviewers concur with this outcome. D-9 Prairie Island Nuclear Generating Plant -Unit 1 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) letter' are met. Further , the efforts completed and documented within the final submittal report are in accordance with the EPRI guidance document. , NRC Letter to All Power Reactor Licensees et aI., " 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 0-10 Appendi x D. Attachment 1 Peel' Review Checklist for SWEL IIIStl'uctiolls fol' Completillg Chcc/dist Prair ie I s land Nucle a r Ge n e r at ing Plant -Unit 1 Seis mi c Walkdown Submittal Report. Upd a t ed Sheet I 01'2 Thi, p ec r r ev iew c he c kli s t !nay be u se d t o d oc um e nt tho r ev iew oflhe Seisillic Wlllkd bw n Equipmellt List (SW E L) in Accordancc with Section 6: P eer Review. Th e s p nce below citch qu es tion in thi s checklist should be t o de s el'ibe any .Iindill!!s identifl ed durin g the pecl: revi ew process and h ow th o SWEL mny have c h n nged to tho se tinding s. Additional s pri ce provided n t the c nd ofth l , c h ec kii st tor do c um e ntin g other cOll1l11ents.

I. Were th c liv e 'Afety rup cl'i on s odequately r ep r cse nt e et in the SWEL I se l ection? 2. poes S W E L I ill c lude ,\II appl'Opdate rcpre sc ntlltion of items hnviug th e following sumpl. selection attl'ibutes:

a. VUriOIi S typ es o f syste ms? v&1NO b. Mujol' new nnd rcpln cc m e ni equipment?
c. Vnl'i o u s lyp es 01' equipment' l d. V u l'i o u s cnvirotllncnts'l VSNO e, Eqliipillcill enhon cc d b ose d o n lh e iindin gs o r the IP EEE (01' equivnlcnt)

Pl'ogl'tl lll? D-11 Appendix D, Attachment 1 Prair i e Island Nuclear Generating Plant -Unit 1 Seismic Walkdown Submittal Report. Updated Peer Review Checklist for SWEL t: Were fisk insights considel'cd in the devolopment of SWEL I? 3, POI' SWEL 2: n. Were spent 111el pool)'elnted it'ems considered, ond if opplicnblc inclpd ed in SWEL 27 b, Was nil ApprOI)"'R!O justiticnliiln docum e nled 1'01' spent fI,el pnnl )'elnled items not included in SWEL 2'1 4, Provide any o lhel' com111ents relnled 10 the pee)' ),eview oflhc S WELs , 5, Hav e ulipccr review cOl11l11enls been odequllicly IIddrcss c d ill the nnlll SWBL? Sheet 201'2 V0 NO vef NO VBND 1/ n 0--.._ Peel' Reviewel' 112: E.,-J s O L-H rM", ,-Date: I L -2..2. -/ '-f D-12