RS-14-001, Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal 1 (Annex a) for the Peach Bottom, Unit 3. Report No. RS-14-001

Enclosure 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex a) for the Peach Bottom, Unit 3. Report No. RS-14-001

ML14091A480
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Issue date:	03/25/2014
From:	Gallagher T, Schlaseman C Exelon Generation Co, MPR Associates
To:	Office of Nuclear Reactor Regulation
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RS-14-001 MPR-3812, Rev. 3
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U.S. Nuclear Regulatory Commission Supplemental Response to 50.54(f) Letter NTTF Recommendation 2.3: Seismic March 25, 2014 ENCLOSURE 1 Seismic Walkdown Report In Response To The 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Updated Transmittal #1 (Annex A) for the Peach Bottom Atomic Power Station, Unit 3, Report No. RS-14-001 (168 Pages)

SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 50.54(f) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC UPDATED TRANSMITTAL # I (ANNEX A) for the PEACH BOTTOM ATOMIC POWER STATION UNIT 3 1848 Lay Road, Delta, PA 17314 Facility Operating License No. DPR-56 NRC Docket No. STN 50-278 Correspondence No.: RS-14-001

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SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 50.54(M) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC for the PEACH BOTTOM ATOMIC POWER STATION UNIT 3 1848 Lay Road, Delta, PA 17314 Facility Operating License No. DPR-56 NRC Docket No. STN 50-278 Correspondence No.: RS-12-173 AE Exeton Exelon Generation Company. LLC (Exelon)

PO Box 809398 Chicago, IL 60680-5398 Prepared by:

MPR Associates, Inc.

320 KIng StrK Alexandria, VA 22314 Report Number. MPR-3812, Reviso 3 Printed Name S1000 DNA Caroline 11116/2012 Prpeprer. Schieseman eoer. Benamin Frazer A26 - 11/1612012 prov.W John Sknon 11/1612012 Peer Review Team Leader Pabirk Butler a

-- * *11/16/2012 Lead Responsible Engneer. Jesse Lucas BranchenJefre Mnaerec Cati Chb.mr K-Wmr PC Senior hanager Design Engineering: Michael Weidmnan  %%IfA Ito Corporate Acceptance: etvClr

• MPR ASSOCIATES INC,.

E N G I N EEF S NTTF 2.3 Seismic Walkdown of Peach Bottom Atomic Power Station Unit 3 MPR-3812 Revision 3 November 2012 QUALITY ASSURANCE DOCUMENT This document has been prepared, reviewed, and approved in accordance with the Quality Assurance requirements of 10CFR50 Appendix B and/or ASME NQA-1, as specified in the MPR Nuclear Quality Assurance Program.

Prepared by: ________

Caroline S. Schlaseman Reviewed by: ____ ___

Benjffin M. Frazier Approved by:9 ,0k Jo W.imons -,

Peer Review <LL**It Team Leader: L Patrick J. Butler PrincipalContributors Mojtaba Oghbaei Craig B. Swanner James N. Wiggin Kevin Gantz Preparedfor Exelon Generation Company, LLC A Exeton 320 KING STREET ALEXANDRIA, VA 22314-3230 703-519-0200 FAX: 703-519-0224 http:%Nwww.mpr.com

RECORD OF REVISIONS Revision Affected Pages I Description 0 All Initial Issue 1 All Minor editorial changes were made throughout the report.

The formatting and text of Tables 5-2, 5-3, 7-2, and E-2 were changed.

Some photos were removed from Appendix C due to security concerns.

2 All Incorporated station's TVT comments.

3 All Deleted citation for Unit 2 work order in Table 7-1.

Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173

Contents Tables.......................................................................................................................................... iii Executive Sum m ary................................................................................................................... Iv 1 Introduction..................................................................................................................... 1-1 1.1 B a ckg ro u n d ............................................................................................................. 1-1 1.2 Plant Overview ........................................................................................................ 1-1 1.3 A p p ro a ch ................................................................................................................. 1-1 2 Seism ic Licensing Basis.......................................................................................... 2-1 2.1 Safe Shutdown Earthquake (SSE) .......................................................................... 2-1 2.2 Design of Seismic Class I SSCs ................................. 2-1 3 PersonnelQualifications............................................................................................... 3-1 4 Selection of SSCs ........................................................................................................... 4-1 4.1 SW EL Developm ent Overview ................................................................................ 4-1 4.2 SWEL 1 - Sample of Required Items for the Five Safety Functions ....................... 4-1 4.3 SW EL 2 - Spent Fuel Pool Related Item s .............................................................. 4-3 4.4 Com posite SW EL .................................................................................................... 4-4 5 Seismic Walkdowns and Area Walk-Bys ................................................................. 5-1 5 .1 O v e rvie w ................................................................................................................. 5 -1 5.2 Seism ic Walkdowns ............................................................................................... 5-1 5.3 Area Walk-Bys ........................................................................................................ 5-3 6 Licensing Basis Evaluations......................................................................................... 6-1 7 IPEEE VulnerabilitiesResolution Report ................................................................. 7-1 8 Peer Review .................................................................................................................... 8-I 8 .1 O v e rvie w ................................................................................................................. 8-1 8.2 Review of SW EL ..................................................................................................... 8-1 8.3 Review of Sample Seismic Walkdown and Area Walk-By Checklists ..................... 8-1 8.4 Review of Licensing Basis Evaluations ................................................................... 8-2 8.5 Review of Subm ittal Report ..................................................................................... 8-2 Peach Bottom Atomic Power Station Unit 3 MPR-3812, Revision 3 Correspondence No.: RS-12-173

Contents (cont'd.)

9 References ...................................................................................................................... 9-1 Appendices A ProjectPersonnelResumes and SWE Certificates.................................... Not Included B Equipment Lists............................................................................................. Not Included C Seismic Walkdown Checklists (SWCs) ....................................................... Not Included D Area Walk-By Checklists (AWCs) ................................................................ Not Included E Plan for Walkdown of InaccessibleEquipment and Assessment of Electrical CabinetInternal Inspections ........................................................................ Not Included F Peer Review Report....................................................................................... Not Included Peach Bottom Atomic Power Station Unit 3 Correspondence No.: RS-14-001

Tables Table 3-1. Personnel R oles ................................................................................................. . . 3-1 Table 5-1. Anchorage Configuration Confirmation ..................................................................... 5-2 Table 5-2. Issues Identified during Seismic Walkdowns ............................................................ 5-2 Table 5-3. Issues Identified during Area Walk-Bys .................................................................... 5-4 Table 7-1. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolutions ................ 7-2 Table 7-2. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolved by Analysis .7-6 Table B-1. S WE L for Unit 3 ......................................................................................... Not Included Table B-2. SWEL for Unit 0 (common) ....................................................................... Not Included Table B-3. Deferred to RFO or Electrical Bus Outage: Inaccessible or Electrical Safety C oncern ........................................................................................ Not Included Table C-1. Unit 3 Seismic Walkdown Checklists (SWCs) ........................................... Not Included Table C-2. Unit 0 Seismic Walkdown Checklists (SWCs) ........................................... Not Included Table D-1. Unit 3 Area Walk-By Checklists (AWCs) ................................................... Not Included Table D-2. Unit 0 Area Walk-By Checklists (AWCs) ................................................... Not Included Table E-1. Summary of Inaccessible Equipment ........................................................ Not Included Table E-2. Assessment of Unit 3 Electrical Cabinet Internal Inspections ................... Not Included Table E-3. Assessment of Unit 0 Electrical Cabinet Internal Inspections ................... Not Included Annexes Annex A. Updated Transmittal#1 ...................................................................................... A-1 Peach Bottom Atomic Power Station Unit 3 iii Correspondence No.: RS-14-001

Executive Summary PURPOSE This report documents the seismic walkdowns performed at Peach Bottom Atomic Power Station (PBAPS) Unit 3 in response to NRC 50.54(f) letter dated March 12, 2012, Enclosure 3, Recommendation 2.3: Seismic. Exelon committed to perform this work in accordance with the NRC-endorsed Seismic Walkdown Guidance document (Electric Power Research Institute (EPRI) Technical Report 1025286, Reference 1).

SCOPE OF WORK In addition to defining the qualifications of personnel performing this work, the EPRI Seismic Walkdown Guidance identifies the following key activities:

• Selection of Systems, Structures, and Components (SSC) to be included in the sample scope of the seismic walkdowns. Screening criteria are applied to obtain an informed sample of electrical and mechanical equipment that are required to perform the four reactor safety functions and containment function, and address NRC concerns about Spent Fuel Pool related equipment. (see Section 4 of this report)

• Seismic Walkdowns and Area Walk-Bys are performed by trained, two-person teams of Seismic Walkdown Engineers (SWEs), who document their inspections on structured checklists included in the EPRI Guidance. (see Section 5 of this report)

• Seismic Licensing Basis Evaluations are performed for issues identified as "potentially adverse seismic conditions," and all issues, whether they rise to this level or not, are included in the Corrective Action Program (CAP) so that standard plant processes can be used to address the issue. (see Section 6 of this report)

" IPEEE Vulnerabilities Resolution Report is required for plants who identified seismic vulnerabilities during their IPEEE program and made commitments to resolve them. IPEEE seismic commitments are identified, resolutions documented, and confirmatory checks made during these walkdowns are documented. (see Section 7 of this report)

• Peer Review is required by a team comprised of at least two individuals for each of the key activities of this project. (see Section 8 of this report)

RESULTS The Seismic Walkdown Equipment List (SWEL) for PBAPS Unit 3, including the items selected that are common to both Units 2 and 3, e.g., emergency cooling tower equipment, is comprised of 122 items. Of this list, 109 equipment items were walked down during the 180-day window of completion of the initial scope of work required by the 50.54(f) letter. Walkdowns for the remaining 13 items were deferred to the Unit 3 Peach Bottom Atomic Power Station Unit 3 iv MPR-3812, Revision 3 Correspondence No.: RS-12-173

Refueling Outage (RFO) or future electrical bus outages due to accessibility issues, e.g.,

location inside primary containment or 4KV bus outage requirements. Additionally, confirmation that equipment anchorage is consistent with plant design documentation is required for 50% of the SWEL items having anchorage (e.g., not line-mounted). A total of 55 anchorage configurations were confirmed to be installed in accordance with the design documentation.

All electrical cabinets on the SWEL require assessment of the need for inspections to address the potential for "other adverse seismic conditions" internal to the cabinet. This assessment is required due to an NRC clarification of their expectations for seismic walkdowns, which was received after the online seismic walkdowns were completed.

Tables E-2 (for Unit 3) and E-3 (for common equipment) list all electrical items that require assessment. Accessibility of equipment, basis for accessibility determination, completion date of internal inspections, tracking number (if internal inspection has not yet been performed) and inspection results are provided in these tables.

None of the issues identified during the walkdowns of PBAPS Unit 3 equipment and nearby areas required formal seismic licensing basis evaluations because none of the issues ultimately were assessed to be adverse seismic conditions. Smaller issues, however, such as missing mounting fasteners for a solenoid valve, were identified and entered into the plant's Corrective Action Program (CAP). A total of 12 Issue Reports (IRs) were issued, and the status of IR resolutions is provided in Tables 5-2 and 5-3 for issues identified during equipment walkdowns and area walk-bys, respectively.

All seismic vulnerabilities identified during the IPEEE (or A-46) program are summarized in Tables 7-1 and 7-2, including resolutions and confirmatory checks made during these walkdowns. All IPEEE seismic vulnerabilities for Peach Bottom Unit 3 have been resolved.

CONCLUSIONS

1. As confirmed in the Peer Review Report (see Appendix F), all activities required by the 50.54(f) letter were conducted in accordance with the NRC-endorsed EPRI Seismic Walkdown Guidance, except for the following items:

Thirteen (13) inaccessible equipment items will need to be walked down during the next Unit 3 RFO or future electrical bus outages.

Six (6) electrical cabinets will need to be opened for an internal inspection for "other adverse seismic conditions" in accordance with NRC expectations that were provided to industry after these walkdowns were completed. These inspections are scheduled for the next available electrical outages.

2. None of the 109 equipment items included in the walkdowns have conditions that would prevent them from performing their safety-related functions following a licensing basis seismic event. Additionally, a sample of more than 50% of equipment with anchorage was confirmed to be consistent with design basis documentation.

3. The twelve (12) anomalies or discrepant conditions identified during the equipment walkdowns or area walk-bys have been assessed in accordance with the plant Peach Bottom Atomic Power Station Unit 3 v MPR-3812, Revision 3 Correspondence No.: RS-12-173

corrective action program (CAP), and their resolutions are being tracked for timely closure.

ANNEX A

SUMMARY

To address the items deferred due to inaccessibility and the supplemental inspections of electrical cabinets, follow-on Seismic Walkdowns and Area Walk-Bys were conducted during the fourth quarter of 2013. No degraded, nonconforming, or unanalyzed conditions that required either immediate or follow-on actions were identified.

Annex A to this report provides:

1) Additional information obtained from these follow-on inspections performed on the open items listed on Tables E-1, E-2 and E-3.

2) Status updates on the conditions identified during the previous Walkdowns and Walk-Bys, listed on Table 5-1, Table 5-2 and Table 5-3.

As of October 25, 2013, follow-on activities required to complete the efforts to address Enclosure 3 of the 50.54(f) letter are now complete.

Peach Bottom Atomic Power Station Unit 3 vi Correspondence No.: RS-14-001

1 Introduction

1.1 BACKGROUND

In response to Near-Term Task Force (NTTF) Recommendation 2.3, the Nuclear Regulatory Commission (NRC) issued a 10CFR50.54(f) letter on March 12, 2012 requesting that all licensees perform seismic walkdowns to identify and address plant degraded, non-conforming, or unanalyzed conditions, with respect to the current seismic licensing basis. The Nuclear Energy Institute (NEI), through 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.

This report documents the technical basis for Exelon's response to the 10CFR50.54(f) request to conduct seismic walkdowns at Peach Bottom Atomic Power Station Unit 3.

1.2 PLANT OVERVIEW The Peach Bottom Atomic Power Station (PBAPS) consists of two boiling water reactor (BWR) generating units, located in southeastern Pennsylvania. Both units have GE Mark I containments, are rated at 3514 MWt power, and were designed and constructed by Bechtel (PBAPS Updated Final Safety Analysis Report (UFSAR) (Reference 2),

Section 1.1). PBAPS Unit 3 received its full-power license in July 1974 (Facility Operating License No. DPR-56 (Reference 9)).

1.3 APPROACH The EPRI Seismic Walkdown Guidance (Reference 1) is used for the PBAPS Unit 3 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

• Personnel Qualifications

• Selection of SSCs

" Seismic Walkdowns and Area Walk-Bys

" Licensing Basis Evaluations

" IPEEE Vulnerabilities Resolution Report

• Peer Review Peach Bottom Atomic Power Station Unit 3 1-1 MPR-3812, Revision 3 Correspondence No.: RS-12-173

2 Seismic Licensing Basis 2.1 SAFE SHUTDOWN EARTHQUAKE (SSE)

The PBAPS design of Seismic Class I structures are based on a dynamic analysis using the spectrum response curves developed for the site. The structures are analyzed for the maximum credible earthquake (MCE) which considers a maximum horizontal ground acceleration of 0.12g (Reference 2, Section C.2.2). The vertical ground acceleration associated with the MCE is 2/3 of the horizontal acceleration which is 0.08g (Reference 2, Section C.2.2). Critical plant structures were designed in accordance with the response spectra based on data developed from the seismology studies performed for the site. It was concluded that the solid rock foundation is subject to only minor earthquake activity and it is expected to respond well with no adverse effects (Reference 2, Section 1.6.1.1.7).

2.2 DESIGN OF SEISMIC CLASS I SSCS Generic Letter 87-02 issued on February 19, 1987 and Supplement No. I issued May 22, 1992, list PBAPS Unit 3 as an USI A-46 Plant (Table A, Category 3). Seismic Class I mechanical and electrical equipment at PBAPS are qualified using rational stress analysis, empirical methods, or the Seismic Qualification User's Group (SQUG) Generic Implementation Plan (GIP) methodology (Reference 2, Section C.5.1). The use of the SQUG method is limited to the listed equipment classes and cannot be used for equipment PBAPS has specifically committed to the NRC to qualify to IEEE 344-75 (Reference 2, Section C.5.1.3).

Peach Bottom Atomic Power Station Unit 3 2-1 MPR-3812, Revision 3 Correspondence No.: RS-12-173

3 Personnel Qualifications Table 3-1 below summarizes the names and corresponding roles of personnel who participated in the NTTF 2.3 Seismic Walkdown effort.

Table 3-1. Personnel Roles Equipment Plant Seismic Licensing IPEEE Peer Name Selection Walkdown Basis Engineer Operations Engineer Reviewer Reviewer Reviewer (SWE) Reviewer B. Frazier X X X X 2

C. Swanner X X X(Note )

M. Oghbaei X X J. Wiggin X X K. Gantz X X C. Schlaseman X(Note 1) X x(Note 3)

P. Butler J. Hanley X (Exelon)

Notes:

1. SWE team member for six seismic walkdowns and one area walk-by; therefore did not act as Peer Reviewer for this portion of the walkdowns.

2. Peer Review Team Member for SWEL review.

3. Peer Review Team Leader.

A description of the responsibilities of each Seismic Walkdown participant's role(s) is provided in Section 2 of the EPRI Seismic Walkdown Guidance (Reference 1).

Resumes provided in Appendix A provide detail on each person's qualifications for his or her role.

The SWEL preparer, Ben Frazier, does not have prior experience with the IPEEE program, which was performed during the 1990s. The Peer Reviewers, however, do have experience with IPEEE. For SWEL preparation, Mr. Frazier was provided with the plant's IPEEE submittal report and NRC requests for additional information (RAI) responses, as well as the NRC Safety Evaluation (SE) on the IPEEE program.

Mr. Frazier's review of these documents, combined with the reviews by the Peer Reviewers, was sufficient to meet the intent of the guidance in Reference 1 that Equipment Selection Personnel "should also have knowledge of the IPEEE program."

Peach Bottom Atomic Power Station Unit 3 3-1 MPR-3812, Revision 3 Correspondence No.: RS-12-173

In addition to the MPR personnel listed above, Exelon Plant Operations, J. Hanley, reviewed the SWEL. Mr. Hanley is a former licensed Senior Reactor Operator (SRO) at another station, currently holds an SRO Certification at PBAPS, and currently supports operator training. Station personnel also provided support to the SWEL preparer in identifying major equipment or system modifications, equipment and systems located in different environments, and equipment and systems that would be accessible for inspection during the plant walkdowns, in accordance with Reference 1.

Peach Bottom Atomic Power Station Unit 3 3-2 MPR-3812, Revision 3 Correspondence No.: RS-12-173

4 Selection of SSCs 4.1 SWEL DEVELOPMENT OVERVIEW The EPRI Seismic Walkdown Guidance (Reference 1) defines the process used to develop the Seismic Walkdown Equipment List (SWEL) for PBAPS Unit 3.

In accordance with Reference 1, a SWEL is comprised of two groups of items:

1. SWEL 1 is a sample of items needed to safely shut down the reactor and maintain containment integrity

2. SWEL 2 is a list of spent fuel pool related items 4.2 SWEL I - SAMPLE OF REQUIRED ITEMS FOR THE FIVE SAFETY FUNCTIONS The PBAPS Safe Shutdown Equipment List (SSEL) (Reference 3) is considered the "Base List 1"and is provided in Appendix B of this report. To ensure the SSEL Base List 1 meets the EPRI Seismic Walkdown Guidance, the SSEL was compared with the screens described in the following sections. It is noted that the PBAPS SSEL does not specifically address the containment function. Therefore the SSEL was reviewed for components having at least one safety-related containment function. The number of SSEL components with a containment function was considered sufficient for selecting a sample of equipment representing the containment function.

4.2.1 Screen #1 - Seismic Class I As described in Reference 1, only items that have a defined seismic licensing basis are to be included in SWEL 1. The seismic classification was identified for each item on the SSEL, and items that were not Seismic Class I were removed from consideration for inclusion in SWEL 1. Seismic classification was determined through a review of current design and licensing basis documentation.

4.2.2 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 removed Seismic Class I Structures, Containment Penetrations, and Seismic Class I Piping Systems from consideration for inclusion in SWEL 1. Cable/conduit raceways and HVAC ductwork are addressed in area walkbys and not as discrete components in SWEL 1.

Peach Bottom Atomic Power Station Unit 3 4-1 MPR-3812, Revision 3 Correspondence No.: RS-12-173

4.2.3 Screen #3 - Support for the 5 Safety Functions This screen narrowed the scope of items included on the SWEL 1 to only those associated with maintaining the following five safety functions:

1. Reactor Reactivity Control

2. Reactor Coolant Pressure Control

3. Reactor Coolant Inventory Control

4. Decay Heat Removal

5. Containment Function The first four functions are associated with bringing the reactor to a safe shutdown condition. The fifth function is associated with maintaining containment integrity.

Reference 3 (Page 5) identifies the primary and backup systems that are applicable to each of the first four safety function. Reference 3 also identifies the support systems for those safety functions (e.g., emergency diesel generators). Components on the SSEL that are essential to the containment function were identified as part of this project because, as noted above, the SSEL did not specifically include equipment for containment function.

4.2.4 Screen #4- Sample Considerations The items selected from the Base List 1 SSEL for inclusion in SWEL 1 are shown in Tables B-1 (Unit 3) and B-2 (Unit 0, common equipment for both Units 2 and 3) of this report. As described in Reference 1, Screen #4 is intended to result in a SWEL 1 that sufficiently represents a broad population of plant Seismic Class I equipment and systems to meet the objectives of the NRC 50.54(f) Letter. The following attributes were considered in selecting items from the SSEL for inclusion in SWEL 1:

1. A variety of types of systems 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 as listed in Reference 1, Appendix E:

Systems to Support Safety Function(s). Examples include Emergency Diesel Generators and related systems, Emergency Core Cooling systems (Residual Heat Removal, Reactor Core Isolation Cooling, Core Spray, High Pressure Coolant Injection), power systems (125 VDC, 120 VAC, 480 VAC), and Ultimate Heat Sink (High Pressure Service Water System and Emergency Service Water System).

Note, however, that the Reference 1 Appendix E table of generic BWR safety function systems includes some systems that are not applicable for PBAPS Unit 3 because the SSEL was not required to include all potential shutdown paths, and some systems do not exist at PBAPS (e.g., Isolation Condenser).

2. Major new and replacement equipment The equipment included on SWEL 1 does not include items that have been recently modified or replaced. Due to the amount of modifications performed in the 1990's Peach Bottom Atomic Power Station Unit 3 4-2 MPR-3812, Revision 3 Correspondence No.: RS-12-173

as part of SQUG and IPEEE programs, PBAPS Unit 3 has not made significant modifications to Seismic Class 1 equipment recently.

3. 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 used in the SSEL, which are the same as the equipment classes used in Reference 1. At least one piece of equipment from each class is included on SWEL 1, except for Class 11, "Chillers;" Class 12, "Air Compressors," and Class 13, "Motor Generators." No Seismic Class I chillers, air compressors, or motor generators were included in the SSEL, and none have been identified that support the five Safety Functions included in this project.

4. A variety of environments The location for each item is identified on SWEL 1. The equipment included on SWEL 1 is a representative sample from a variety of environments (locations) in the station. These environments include the Screen House, Pump Structure, Diesel Generator Structure (common to both units), Emergency Cooling Tower (common to both units), Turbine Building, Reactor Building, and Drywell.

5. Equipment enhanced due to vulnerabilities identified during the IPEEE program As discussed in Section 7 of this report, a significant number of IPEEE seismic-related plant improvements were implemented, or were committed to be implemented for PBAPS Unit 3. Table 7-1 shows that all committed changes were made and identifies the sample of this equipment that was included in the SWEL.

6. Contribution to risk In selecting items for SWEL 1 that met the attributes above, some items with similar attributes were selected based on their higher risk-significance. To determine the relative risk-significance, the Risk Achievement Worth (RAW) and Fussell-Vesely (F-V) importance for a Loss of Off-Site Power (LOOP) scenario from the internal plant PRA were used (Reference 5, Tables 2 and 4). The LOOP scenario from the internal plant PRA includes lists of the 20 pieces of equipment for Unit 3 with the highest F-V risk ranking (0.0168 and above) and highest RAW risk ranking (9.0 and above). The lists of risk-significant components for the LOOP PRA (Reference 5) were compared with the draft SWEL 1 to confirm that a reasonable sample of risk-significant components (relevant for a seismic event) were included on SWEL 1.

In accordance with Reference 1, equipment access was considered when selecting the sample components. Equipment in lower dose areas were selected for the walkdown sample instead of the same component in a different train, but located in a higher dose area.

4.3 SWEL 2- SPENT FUEL POOL RELATED ITEMS In accordance with Reference 1, four screens are used to select the SSCs to be included on the second Seismic Walkdown Equipment List (SWEL 2), as described in the following sections.

Peach Bottom Atomic Power Station Unit 3 4-3 MPR-3812, Revision 3 Correspondence No.: RS-12-173

4.3.1 Screen #1 - Seismic Class I Only Seismic Class I SSCs, or SSCs that could result in rapid drain-down of the SFP (see Screen #4 below), are to be considered for inclusion in SWEL 2. As described in Reference 1, the adequacy of SFP structures is assessed by analysis and is not included in the scope of these walkdowns.

The review of the design and licensing basis documentation for the SFP identified no Seismic Class I equipment for PBAPS Unit 3 (Reference 2, Appendix C and Reference 6). Therefore, no Seismic Class I items are included in SWEL 2.

It is noted that the spent fuel pool cooling and clean-up system is cross-connected to the RHR system (Reference 6, E-2, 3). This is done with a spool piece and does not result in any spent fuel pool cooling and clean-up components being safety-related.

4.3.2 Screen #2- Equipment or Systems This screen considers only those items from Screen #1 that are appropriate for an equipment walkdown process. Since no Seismic Class I items are included in SWEL 2, no items meet the Screen #2 requirement.

4.3.3 Screen #3- Sample Considerations Sample considerations do not apply because no Seismic Class I items meet the Screen #1 requirement.

4.3.4 Screen #4 - Rapid Drain-Down This screen identifies items that could allow the spent fuel pool to drain rapidly. Rapid drain-down is defined as lowering of the water level 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 the earthquake. 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, the SFP gates are considered to be 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 and do not allow for a rapid drain-down of the SFP.

Based on review of the PBAPS Unit 3 SFP design information, there are no connections to the fuel storage pool which could allow the fuel pool to be drained below 10 feet above the top of active fuel (Reference 2, Section 10.3.4.2 and Reference 6). The spent fuel pool cooling and clean-up return lines are the only lines that extend below this level but are equipped with siphon breaker holes to prevent inadvertent pool drainage (Reference 6, Note 3). Therefore, no items are required to be added to SWEL 2 to address rapid drain down.

4.4 COMPOSITE SWEL As described in Section 4.1 above, the final Seismic Walkdown Equipment List (SWEL) for PBAPS Unit 3 is the combined SWEL 1 and SWEL 2. For PBAPS Unit 3, there are Peach Bottom Atomic Power Station Unit 3 4-4 MPR-3812, Revision 3 Correspondence No.: RS-12-173

no items in SWEL 2, so the composite SWEL is the same as SWEL 1. Appendix B includes the composite SWEL.

Peach Bottom Atomic Power Station Unit 3 4-5 MPR-3812, Revision 3 Correspondence No.: RS-12-173

5 Seismic Walkdowns and Area Walk-Bys 5.1 OVERVIEW Seismic Walkdowns and Area Walk-Bys were conducted by 2-person teams of trained Seismic Walkdown Engineers, in accordance with the EPRI Seismic Walkdown Guidance (Reference 1). The Seismic Walkdowns and Area Walk-Bys are discussed in more detail in the following sections.

5.2 SEISMIC WALKDOWNS An overview of the equipment included in the Seismic Walkdowns is shown on the PBAPS Unit 3 SWEL and Unit 0 (common equipment with Unit 2) SWEL in Appendix B.

A Seismic Walkdown Checklist (SWC) from Appendix C of Reference 1 was completed for each item on the SWEL, except for the deferred items identified at the end of the SWEL. Additionally, photos are included with each SWC to provide a visual record of the item and any significant comment noted on the SWC. Drawings and other plant design documents are cited in most of the SWCs, but they are not included with the SWCs because they are readily available in the plant's electronic document management system. Seismic Walkdowns were completed for 80 of the 92 items on the PBAPS Unit 3 SWEL, plus 29 of the 30 items on the Unit 0 (common) SWEL, for a total of 109 items, not including the 13 deferred.

5.2.1 Anchorage ConfigurationConfirmation As required by Reference 1 (page 4-3), the anchorage for at least 50% of the items were confirmed to be consistent with design documentation. The second to last column of Tables C-1 and C-2 show which items are line-mounted and therefore do not count in the anchorage confirmation total (marked "N/A"). Items evaluated for consistency with design documentation was marked "Y"; those that were not compared with design documentation are marked "N". See Table 5-1 below for the accounting of the 50%

anchorage configuration confirmations, and the individual SWC forms in Appendix C for the specific documents used in each confirmation.

Peach Bottom Atomic Power Station Unit 3 5-1 MPR-3812, Revision 3 Correspondence No.: RS-12-173

Table 5-1. Anchorage Configuration Confirmation Unit 3 or Unit 0 No. of SWEL N/A Items Required to Items Unimmornt Items (B) Confirm? Confirmed (Common)? (A) (A-B)I2 3 80 11 34 38 0 (Common) 29 4 13 17 Unit3and 109 15 47 55 Common 5.2.2 Issue Identification None of the anomalies or issues identified by the SWEs during the equipment walkdowns were ultimately judged to be "Potentially Adverse Seismic Conditions" because in all cases it was concluded the anomaly or issue would not prevent the equipment from performing its safety-related function. Additionally, based on the IRs for each issue, all equipment affected by the as-found condition was determined to be functional. Table 5-2 provides a summary of the issues identified during the Seismic Walkdowns.

Table 5-2. Issues Identified during Seismic Walkdowns Action Actions Component ID Description of Issue Request Complete ID YIN(Notes 1, 2) 3DD003 (also Possible open S-hook noted on light IR 01413285 Yes AWC-UO-1) fixture.

SV-3-03-033 SV Mounting does not match print. IR 01413655 No (also AWC-U3-13) 30C003, The MCR ceiling's restraint system is IR 01428651 No 30C004C, consistent with design documentation but 30C005A, L13-2 the design basis Calculation G-106-1 could 113, LI-9027, not be located from records management LR/TR-9123B, or Iron Mountain. This issue is to P13-6-90A, re-constitute design analysis to PR/TR3-2-3-404B, supplement existing calculation 26-5/Z-12, PR/TR-5805 (also specifically at MCR ceiling perimeter, AWC-UO-7) during NTTF 2.1 seismic re-evaluation.

3AE56, 3AE57, Anchorage for ECCS room coolers does IR 01437853 No 3AE58, 3BE55, not match drawings. (Note 3) 3BE57 (also AWC-U3-8) 30B338 A front panel screw is missing and another IR 01424719 Yes screw is loose.

Peach Bottom Atomic Power Station Unit 3 5-2 MPR-3812, Revision 3 Correspondence No.: RS-12-173

Table 5-2. Issues Identified during Seismic Walkdowns Action Actions Component ID Description of Issue Request Complete ID Y/N(Notes 1, 2) 30C722A The internal flow detector instrument has a IR 01424662 No loose mounting screw.

30C722B The two internal power supplies are IR 01424692 No missing mounting screws where they are mounted to the cabinet.

OAG12, OBG12, Inconsistency between the observed IR 01438055 No 0CG12, 0DG12 OAG12, 0BG12, 0CG12, and 0DG12 anchor bolt size and vendor document E-5-155.

Notes:

1. "Yes" indicates that corrective actions resulting from the issue are complete.

2. "No" indicates that corrective actions resulting from the issue are NOT complete. Actions are tracked by the IR number in the station Corrective Action Program.

3. IR 01411581 was originally identified on the SWCs as being applicable to this issue. Upon further investigation IR 01437853 was written to fully capture the issue.

5.3 AREA WALK-BYS In accordance with Reference 1, Area Walk-bys were performed for each room or area within a large room which included one or more items on the SWEL. The last column of Tables C-1 and C-2 show the number of unique Area Walk-By Checklists (AWCs) completed during the walkdowns for PBAPS Unit 3 and Unit 0 (common). All completed AWCs are included in Appendix D. Photos are not included with the AWC forms because they are part of the SWC package of the identified equipment item. A total of 25 AWCs were completed for Unit 3, plus 13 for Unit 0 (common).

None of the anomalies or issues identified by the SWEs during the Area Walk-Bys were judged to be "Potentially Adverse Seismic Conditions" because in all cases the anomaly or issue would not prevent surrounding equipment from performing its safety-related function. Additionally, based on the IRs for each issue, all equipment affected by the as-found condition was determined to be functional.

Table 5-3 at the end of this section provides a summary of the issues identified in the Area Walk-Bys.

Peach Bottom Atomic Power Station Unit 3 5-3 MPR-3812, Revision 3 Correspondence No.: RS-12-173

Table 5-3. Issues Identified during Area Walk-Bys Component Action Actions Comoent Description of Issue Request Complete IDIArea ID y/N(Notes 1,2)

AWC-U3-2 U-bolt identified as unattached on a non-Q IR Yes line. 01413652 AWC-U3-3 Severely corroded nut on 3A HPSW Plate. IR No 01410116 AWC-U3-25 Ladder identified on floor of SW Screen IR Yes House. 01406272 AWC-U3-7 Loose cover plate bolt identified on 30C221 IR No judged acceptable. Bolt should be tightened. 01424737 Notes:

1. "Yes" indicates that corrective actions resulting from the issue are complete.

2. "No" indicates that corrective actions resulting from the issue are NOT complete. Actions are tracked by the IR number in the station Corrective Action Program.

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6 Licensing Basis Evaluations As noted in Sections 5.2.2 and 5.3, the issues identified during the Seismic Walkdowns and Area Walk-Bys were not determined to be "Potentially Adverse Seismic Conditions" because in all cases the anomaly or issue would not prevent the equipment from performing its safety-related function. Therefore, no formal Licensing Basis Evaluations were necessary and none were performed.

Peach Bottom Atomic Power Station Unit 3 6-1 MPR-3812, Revision 3 Correspondence No.: RS-12-173

7 IPEEE Vulnerabilities Resolution Report The Individual Plant Examination of External Events (IPEEE) report for PBAPS (Reference 7) and the NRC Safety Evaluation on the IPEEE report (Reference 8),

identified a number of seismic vulnerabilities. This occurs since the IPEEE reviews were performed in parallel with the original SQUG seismic verification of various equipment.

Each of the seismic vulnerabilities identified in Reference 7 were verified to be implemented and closed out per AR No. A1056479 (Reference 10). Additionally many of the identified IPEEE vulnerabilities were verified to be implemented during the seismic walkdowns. Table 7-1 below lists identified IPEEE (and A-46) vulnerabilities, indicates how each one was resolved, and identifies the specific items that were verified in the field during the walkdowns. Table 7-2 lists the PBAPS Unit 3 and Common IPEEE seismic vulnerabilities that were previously resolved by analysis. There are no outstanding IPEEE vulnerabilities and all previously identified IPEEE vulnerabilities have been resolved.

Peach Bottom Atomic Power Station Unit 3 7-1 MPR-3812, Revision 3 Correspondence No.: RS-12-173

Table 7-1. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from AIR Sample Component Walkdown

1. Al 056479 Resolution 00B97 Interaction concerns. Breaker hoist will be restrained or removed. Work completed under work order C0188074 on None 00B98 August 1, 2000.

00B99 30B10/11/12113 Some cubicles missing plug welds Add missing plug welds. Work completed for plug welds under work orders 30B010 and 30B013 included in to embedded angle. Breaker hoist will be restrained or removed. C0186234 and C0186267 on August 1, 2000, and walkdown sample.

under work orders C0186428 and C0186429 on Breaker hoists are interaction Modification will replace with ventilated dry type October 16, 2000. Confirmed issue resolved.

concern, not prevented from tipping. transformers that are properly anchored. Work completed for breaker hoist under work order Adjacent oil filled transformers are C0183131 on August 1,2000.

unanchored. A walkdown was performed on April24, 1997 to verify that all of the new transformers were installed for MOD 5099.

00B94/95/96 Unanchored switchgear and Switchgear will be anchored. Work completed for anchorage under work orders None transformers. C0189242 and C0189243 on August 1, 2000, and Hoist will be restrained or removed. C0189244 on October 16, 2000.

Interaction concern with breaker Work completed for breaker hoist under work hoist. orders C0188074 on August 1, 2000.

30A15/16/17/18 Door latching mechanisms are only Latches will be fastened and neoprene pads Work completed under work order C0177308 on None engaged at center of door. Latching may be provided. August 1, 2000.

bolts at top and bottom are not engaged. Spare breakers will be removed or secured. Per Item 4, p. 17 of Al 056479, as of August 1, 2000, spare breakers removed and will not be 30A15,16,17 have spare breakers stored in switchgear rooms per procedure SO which are not adequately secured. 54.7.C. No PIMS work recorded for removal of spare breakers.

30X133/150 30KVA transformer coils are missing Perform evaluation of coil anchorage and ECR PS 97-02258 has been completed. CALC 30X133 included in walkdown 2 of 4 holding bolts, modify if required. PS-0947 reviewed the transformers and concluded sample.

that the outlier conditions are seismically acceptable (September 29, 1997). No modification to confirm.

30X31/33 Oil filled transformers are Replace with ABB 1000KVA VPE ventilated dry A walkdown was performed on April 24, 1997 to 30X33 included in walkdown sample.

unanchored. type transformer properly anchored, verify that all of the new transformers were installed for MOD 5099. Confirmed issue resolved.

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Table 7-1. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from AIR Sample Component Walkdown

1. Al 056479 Resolution 00X103 Anchorage of transformer coils to Vendor drawings will be reviewed and ECR PB 97-02258 has been completed. CALC None 30X135 enclosure support surface evaluated and if necessary anchorage will be PS-0947 reviewed the transformers and concluded indeterminate, reworked to comply. that the outlier conditions are seismically acceptable (September 29, 1997).

0AX26/0BX26/0CX26 Anchorage could not be verified. Transformer will be anchored. Work completed under work order C01 89169 on None August 1, 2000.

3AP42/3BP42/3CP42/3DP42 Pump casing and shaft are greater Analytic evaluation proved pump casings and Analysis completed as of IPEEE submittal May 3CP042 and 0BP057 included in 0AP57/0BP57 than 20 ft. shafts acceptable. 1996. walkdown sample.

Non-tied down yard gantry crank Yard crane will be restrained when not in use. Work completed under A/R Al 188705 on August 1, Confirmed issue resolved.

2000.

could fall on pump house.

MO-33-0498 Valve has interaction concern with Support for radiation element outlet will be Work completed under work order C01 82155 on MO-0-33-0498 included in walkdown radiation element outlet. modified. August 1, 2000. sample.

Confirmed issue resolved.

A03-03-33 Distances from pipe centerline to Review documentation and perform analysis if ECR PB 97-02258 has been completed. CALC A03-03-33 included in walkdown top of valve operator is outside of required to demonstrate seismic capacity. PS-0947 reviewed the air operated valve and sample.

experience database. concluded that the outlier conditions are seismically acceptable (September 29, 1997). No modification to confirm.

M03-13-5487 Valve operator weights and/or Review documentation and perform analysis if ECR PB 97-02258 has been completed. CALC None centerline distances are outside of required to demonstrate seismic adequacy. PS-0947 reviewed the MOV and concluded that the experience database, the outlier conditions are seismically acceptable (September 29, 1997).

0AV035/36 Overhead ducts need to be Evaluate overhead systems and modify as ECR 97-00992 was taken to approved (and 0AV036, 0BV035, and 0BV036 0BV035/36 reviewed as part of the IPEEE for required or develop suitable operator actions, complete) status on July 24, 1997. The required included in walkdown sample.

seismic adequacy. physical (MOD) work in the plant was tracked by A1056479-12. No issues identified with overhead ducting.

00F043 Overhead ducts are an interaction Evaluate overhead systems and modify as ECR 97-00992 was taken to approved (and None concern. required or develop suitable operator actions, complete) status on July 24, 1997. The required physical (MOD) work in the plant was tracked by A1056479-12.

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Table 7-1. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from AIR Sample Component Walkdown

1. Al1056479 Resolution 0AV034 Attached heating piping at upper Evaluate steam piping and modify if required. ECR 97-00992 was taken to approved (and None nozzles is poorly supported. Evaluate overhead systems and modify as complete) status on July 24, 1997. The required required or develop suitable operator actions, physical (MOD) work in the plant was tracked by Overhead ducts are an interaction A1056479-12.

concern.

30D22/23/24 Depth of panels are less than that Top supports will be provided and existing floor Work completed under work order C0190338 on None which is included in earthquake anchorage will be evaluated and modified as December 14, 2000.

experience database, required.

Anchor bolts have 2 1/4" eccentricity and in addition, corner plates are too flexible and do not provide an adequate load path.

3ADO1/3BD01/3CDO1l3DD01 Batteries are more than 450 lbs. Review of existing data showed that the Work completed under work order C0193773 on 3BC01, 3CD01, and 3DD01 included (actual weight 700 lbs.) which is batteries are qualified to IEEE-323 (1974) and August 1, 2000. in walkdown sample.

outside experience database. Also, IEEE-344 (1975).

end rails are not snug with batteries. Confirmed issue resolved for 3BC01 Also overhead fluorescent lights are A snug fit will be provided at end rails and the and 3DD01.

suspended with chains having open S-hooks will be closed.

S-hooks.

CAG 1210BG1 2/OCG12/ODG1 2 Interaction concerns with overhead Overhead crane controller will be tied down Work completed under work orders C01 81161, OAGO12 and ODG012 included in crane controller. Local panel on when not in used. C0181153, C0181159, and C0179951, and walkdown sample.

vibration isolators without lateral C0193768 on August 1,2000.

capacity. Vibration isolators will be modified to preclude Confirmed issue resolved.

dislodging in SSE.

TIC-30223 Cover on temperature controller is Cover will be secured. Component was secured under ECR 99-00149 on None loose. August 1, 2000.

OAG1 3/0BG 13/OCG 13/ODG1 3 Interaction concerns exist regarding Overhead crane controller will be tied down Work completed under work order C01 93768 on 0AC097 included in walkdown 0AC097/0BC097/0CC097 overhead crane controller, when not in use. August 1, 2000. sample.

0DC097 Confirmed issue resolved (documented for OAGO12).

0OC29A/B/C/D Interaction concerns with Items will be removed or restrained. Work completed under work order C0183590 on 00C29B included in walkdown 30C124 housekeeping issues in the Control August 1,2000. sample.

Room.

Confirmed issue resolved.

Peach Bottom Atomic Power Station Unit 3 7-4 MPR-3812, Revision 3 correspondence No.: RS-12-173

Table 7-1. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from A/R Sample Component Walkdown

1. A1056479 Resolution 30C32/33 Cabinets are not bolted to the Adjacent cabinets will be tied together front and Work completed to resolve cabinet interactions 30C32, 30C33, and 30C722B 30C722B adjacent cabinet. Interaction back. under work order C01 90338 on December 14, included in walkdown sample.

concerns exist with adjacent non- 2000.

safety cabinets and cable tray. Table will be blocked and located so tipping will Confirmed issue resolved.

not cause impact.

Work completed to resolve cable tray interaction Cushioning will be provided between adjacent with 30C032 under work order C0193837 on non-safety cabinet and impact loading will be August 1, 2000.

evaluated.

Pipe stanchion supports Lateral load criteria not met. Install knee brace at top of stanchion at Work completed under work orders C01 89101, None - issue not applicable to this midspan of raceway and attach to floor or C0189160, and C0190050 on August 1, 2000. walkdown.

Rx. Bldg. 195' install lateral supports.

RW Bldg. 165' U3 HCU's Top horizontal frame for HCU piping Horizontal bracing will be added. Work completed under work orders C0187209 and HCU-06-47 and HCU-14-35 included does not have adequate lateral C0187392 on August 1,2000. in walkdown sample.

bracing.

Confirmed issue resolved.

El. 165' Mech. Equipment Various duct and interaction issues Perform evaluation of overhead systems and Work completed under work orders C0190892, None Room HVAC ducting including aux. steam piping, modify as required or develop suitable operator C0187741, C0191039, and C0182488 on August actions. 2, 2000, and underwork order C0195436 on December 18, 2000.

Peach~

BottomAtomicPowerStationU~nit 3 7-5 MPR-3812,Revision 3

No.: RS-12-173 Correspondence

Table 7-2. PBAPS Unit 3 and Common IPEEE Seismic Vulnerabilities Resolved by Analysis Component ID Issue Planned Resolution Actual Resolution of Condition Resolution Date 30D11 Anchorage evaluation required. Evaluate anchorage. Anchorage evaluation completed and anchorage of 5/1997 00B54 MCCs are adequate.

00B55 00B56 A03-01-O8ONBIC/D Distance from pipe centerline to top Evaluate centerline distance of valve operators. Calculations show valves have acceptable seismic 2/1996 A03-0l-O86AIBICID of valve operator is outside of capacities.

experience database.

M03-23-019 Valve operatorweights and/or Evaluate weight and centerline distance of Existing documentation review indicates valves are 5/1996 M03-23-025 centerline distances are outside of valve operators, qualified to an acceptable seismic acceleration.

M03-12-015 the experience database.

M03-10-025A/B M03-13-027 M03-13-131 M03-13-132 M03-30-3233A/B Cast iron yoke. Evaluate suitability of cast iron yoke. Existing documentation was reviewed and 511996 components were determined to be seismically adequate.

3AC65 Anchorage does not screen. Evaluate anchorage. Evaluation of anchorage was performed and was 5/1997 shown to be seismically adequate.

3AE24/3BE24/3CE24/3DE24 Heat exchanger anchorage Evaluate anchorage. Review of RHR Heat Exchanger modification 1/2004 evaluation is unknown. calculations evaluated anchorage capacity for the RHR Heat Exchangers and found them to be seismically adequate.

Peach Bottom Atomic Power Station Unit 3 7-6 MPR-3812, Revision 3 Correspondence No.: RS-12-173

8 Peer Review 8.1 OVERVIEW In accordance with the EPRI Seismic Walkdown Guidance (Reference 1), a peer review of this project was performed during the preparation of the Seismic Walkdown Equipment List (SWEL), during implementation of the seismic walkdowns and area walk-bys, and following completion of the issue resolutions. Specifically, the peer review addresses the following activities:

• Review of the selection of the structures, systems, and components, (SSCs) that are included in the Seismic Walkdown Equipment List (SWEL),

• Review of a sample of the checklists prepared for the Seismic Walkdowns &

Walk-Bys,

• Review of any licensing basis evaluations,

• Review of the decisions for entering the potentially adverse conditions in to the plant's Corrective Action Program (CAP), and

" Review of the final submittal report.

The complete Peer Review Report is included in Appendix F.

8.2 REVIEW OF SWEL The peer review checklist for SWEL is included as an attachment to the Peer Review Report. This checklist was used to ensure that the SWEL 1, SWEL 2, and composite final SWEL meet the criteria of Reference 1. All peer review comments on the SWEL were resolved.

8.3 REVIEW OF SAMPLE SEISMIC WALKDOWN AND AREA WALK-BY CHECKLISTS Approximately 26% of the Seismic Walkdown packages, i.e., SWC forms, photographs, and drawings (where applicable) were reviewed by the peer review team. Additionally, interviews were conducted with both teams of Seismic Walkdown Engineers to ensure that the seismic walkdowns and area walk-bys were performed in accordance with Reference 1.

The peer review team did not require any clarifications be added to the SWC and AWC forms reviewed.

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8.4 REVIEW OF LICENSING BASIS EVALUATIONS As discussed in Sections 5 and 6 of this report, the issues identified during the seismic walkdowns and area walk-bys did not threaten the ability of Seismic Class I equipment to perform their safety functions. The specific items that have been entered in the PBAPS Corrective Action Program (CAP) were reviewed, and no concerns with the assessments or proposed resolutions were identified.

8.5 REVIEW OF SUBMITTAL REPORT The signature of the Peer Review Team Leader on the cover of this report indicates a satisfactory review and resolution of any comments and confirms that all necessary elements of the peer review were completed.

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9 References Reference drawings related to the walkdown of SWEL items are documented on the Seismic Walkdown Checklists (SWCs) in Appendix C, and if applicable, on the Area Walk-By Checklists (AWCs) in Appendix D.

1. EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012.

2. Peach Bottom Atomic Power Station Updated Final Safety Analysis Report (UFSAR), Revision 23.

3. PECO Document No. NE-117-51, Safe Shutdown Equipment List (SSEL) for Peach Bottom Atomic Power Station, Revision 0.

4. Not used.

5. Exelon Document No. PB-MISC-009, Risk Ranking to Support NTTF 2.3 Seismic Walkdowns, Revision 0.

6. PBAPS Drawing No. M-363, P & I Diagram - Fuel Pool Cooling and Clean-up, Sheet 2, Revision 40.

7. PECO Energy Company, Peach Bottom Atomic Power Station Units 2 and 3, Individual Plant Examination for External Events, May 1996.

8. NRC Letter (B. C. Buckley) to PECO (J. A. Hutton), Review of Peach Bottom Atomic Power Station, Units 2 and 3, Individual Plant Examination of External Events Submittal (TAC NOS. M83657 AND M83658), dated November 22, 1999.

9. Facility Operating License No. DPR-56, NRC Docket No. 50-278, Amendment No. 284, Dated May 29, 2007.

10. PBAPS Action Request Al 056479, Last updated 12/20/2000.

Peach Bottom Atomic Power Station Unit 3 9-1 MPR-3812, Revision 3 Correspondence No.: RS-12-173

Annex A Updated Transmittal # I Peach Bottom Atomic Power Station Unit 3 Correspondence No.: RS-14-001 A~i

Contents of Annex A Tables....................................................................................................................................... Aiv Al Introduction.......................................................................................................... Al-A 1.1 P u rp o s e ................................................................................................................ Al -I A1.2 Background ...................................................................................................... A1-2 A1.3 Plant Overview .............................................................................................. A1-2 A1.4 Approach .............................................................................................................. Al -2 A1.5 Conclusion ........................................................................................................... A1-2 A2 Seism ic Licensing Basis............................................................................................. A2-1 A3 PersonnelQualifications............................................................................................ A3-1 A3.1 Overview .............................................................................................................. A3-1 A3.2 Project Personnel ................................................................................................. A3-1 A.3.2.1 MPR Associates Personnel ..................................................................... A3-2 A.3.2.2 Additional Personnel ................................................................................ A3-2 A4 Selection of SSCs ........................................................................................................ A4-1 A5 Seism ic Walkdowns and Area Walk-Bys ................................................................... A5-1 A5.1 Overview .............................................................................................................. A5-1 A5.2 Seism ic Walkdowns ............................................................................................. A5-1 A.5.2.1 Anchorage Configuration Confirmation .................................................... A5-1 A.5.2.2 Issue Identification ................................................................................... A5-2 A5.3 Area Walk-Bys ..................................................................................................... A5-3 A6 Licensing Basis Evaluations...................................................................................... A6-1 A7 IPEEE VulnerabilitiesResolution Report .............................................................. A7-1 A8 Peer Review ................................................................................................................. A8-1 A9 References ................................................................................................................... A9-1 Peach Bottom Atomic Power Station Unit 3 Correspondence No.: RS-14-001 Aii

Appendices AA Project PersonnelResumes and SWE Certificates.................................................. AA-1 AB Equipment Lists ......................................................................................... AB-1 AC Seismic Walkdown Checklists (SWCs) ..................................................................... AC-1 AD Area Walk-By Checklists (AWCs) .............................................................................. AD-1 AE Plan for Walkdown of InaccessibleEquipment and Assessment of Electrical CabinetInternal Inspections....................................................................... AE-1 AF PeerReview Report..................................................................................................... AF-1 Peach Bottom Atomic Power Station Unit 3 Correspondence No.: RS-14-001 Aiii

Tables Table A3-1. Personnel R oles .................................................................................... A3-1 Table A5-1. Anchorage Configuration Confirmation ...................................................... A5-1 Table A5-2. Issues Identified during Seismic Walkdowns ............................................... A5-2 Table A5-3. Issues Identified during Area Walk-Bys ...................................................... A5-3 Table AC-i. Summary of Seismic Walkdown Checklists (SWCs) .................................... AC-2 Table AC-2. Summary of Supplemental Internal Cabinet Inspections ................................ AC-47 Table AD-i. Unit 3 Area Walk-By Checklists (AWCs) .................................................... AD-1 Table AD-2. Unit 0 Area Walk-By Checklists (AWCs) .................................................. AD-1 Peach Bottom Atomic Power Station Unit 3 Correspondence No.: RS-14-001 Aiv

A1 Introduction A1.1 PURPOSE This updated transmittal report is being provided in compliance with the requirements contained in Enclosure 3 of the NRC 50.54(f) letter dated 3/12/12 (Ref. 11). This new report section, Annex A, contains the results of the follow-on activities that have taken place since the initial NRC Transmittal sent by Exelon for Peach Bottom Atomic Power Station Unit 3, under letter number RS-12-173 on November, 19, 2012 (Ref. 12). Annex A, includes follow-on seismic walkdown results associated with NRC Commitments 3 &

4 listed in Enclosure 3 of the letter. Additionally, the update includes the current status of the resolution of conditions found during the initial seismic walkdowns and area walk-bys as documented in Tables 5-2 and Table 5-3, respectively.

Commitment 3, for the completion of the 13 deferred inspection (SWEL) items listed in Table E-1, is now complete. All 13 items were completed by the commitment dates.

This update documents the completion of the 13 inspection items in accordance with the individual item completion schedule.

Commitment 4, for the completion of the 6 remaining internal electrical cabinet inspections listed in Table E-2 and E-3, is now complete. Exelon provided a revised commitment 15 (Ref. 13) to complete these six (6) items by July 31, 2014. These inspections have been completed ahead of the commitment date and the results are documented in this update. Therefore commitment 16 (Ref. 13) is now complete.

The initial anchorage configuration confirmation shown in Table 5-1 is updated with new totals in Table A5-1 to include the deferred items.

The initial NRC Transmittal report documented that 6 conditions identified during the seismic walkdowns, and listed in Table 5-2, remained open. This update documents that 3 conditions are now resolved with all follow-on actions complete.

The initial NRC Transmittal report documented that 2 conditions identified during the area walk-bys, and listed in Table 5-3, remained open. This update documents that the 2 remaining conditions are now resolved.

Annex A, includes updates to each report section where the status has changed or new information is available in accordance with Section 8 of EPRI 1025286, "Seismic Walkdown Guidance - For Resolution of Fukushima Near Term Task Force Recommendation 2.3 Seismic" (Ref. 1).

Peach Bottom Atomic Power Station Unit 3 Al1-1 Correspondence No.: RS-14-001

A

1.2 BACKGROUND

See Section 1.1.

A1.3 PLANT OVERVIEW See Section 1.2.

A1.4 APPROACH See Section 1.3.

A

1.5 CONCLUSION

As of October 25, 2013, all Seismic Walkdowns have been completed at Peach Bottom Atomic Power Station Unit 3 on 13 of the 13 items deferred due to inaccessibility along with 6 of the 6 supplemental electrical cabinet inspections, in accordance with the NRC endorsed walkdown methodology. Area Walk-Bys were also completed, as required, during these follow-on activities. No degraded, nonconforming, or unanalyzed conditions that require either immediate or follow-on actions were identified.

There are no additional follow-on activities to complete the efforts to address Enclosure 3 of the 50.54(f) letter.

No deficiencies were generated during the follow-on walkdowns. The updated completion status for the previous IRs is shown in Table A5-2 and Table A5-3 in Section A5 of this Annex A.

Peach Bottom Atomic Power Station Unit 3 Al1-2 Correspondence No.: RS-14-001

A2 Seismic Licensing Basis See Section 2, no new licensing basis evaluations resulted from the follow-on walkdown activities.

Peach Bottom Atomic Power Station Unit 3 A2-1 Correspondence No.: RS-14-001

A3 Personnel Qualifications A3.1 OVERVIEW This section of the report identifies the personnel that participated in the NTTF 2.3 Seismic Walkdown efforts. A description of the responsibilities of each Seismic Walkdown participant's role(s) is provided in Section 2 of the EPRI Guidance (Reference 1). Resumes provided in Appendix A, and Appendix AA in this Annex A, provide detail on each person's qualifications for his or her role.

A3.2 PROJECT PERSONNEL Table A3-1 below summarizes the names and corresponding roles of personnel who participated in the NTTF 2.3 Seismic Walkdown effort.

Table A3-1. Personnel Roles Equipment Seismic Name NSelection e e int Plant Walkdown Licensing Basis IPEEE Peer Engineer Operations Engineer R Reviewer Reviewer (SWE) Reviewer B. Frazier X (MPR)

K. Gantz X (MPR)

B. Birmingham X (Exelon) x (Note 1)

T. Gallagher X(Note 4) X(Note 4)

(Exelon)

J. Lucas X (Exelon)

P. Kester X (Note 2, 3) X (Exelon)

D. Knepper X (Note 3)

(Exelon)

Notes:

1. Site Lead Structural Engineer for 2.1 & 2.3 Seismic, therefore acted as Peer Review Team Leader for this Annex A.

2. SWE team member for only two seismic walkdowns therefore acted as Peer Reviewer.

3. SQUG Qualified.

4. Performed roles for initial walkdowns only.

Peach Bottom Atomic Power Station Unit 3 A3-1 Correspondence No.: RS-14-001

A3.2.1 MPR Associates Personnel See Section 3, no new MPR Associates participated in the follow-on activities.

A3.2.2 Additional Personnel The following additional Exelon personnel participated in the follow-on activities:

Ms. Gallagher is the Site Structural LRE for the 2.1 Seismic Hazard Evaluations and 2.3 Seismic Walkdowns. She has a BS degree in Civil Engineering from the Pennsylvania State University and has over 6 years of nuclear power experience. She has been trained as an EPRI Seismic Walkdown Engineer. She has been involved with all aspects of plant modification/configuration change activities at Peach Bottom and at other various nuclear power plants. Other activities include rigging evaluations, lead shielding, scaffolding and other support activities.

" Mr. Kester is a Site Senior Design Engineer with over 20 years of experience at Peach Bottom. He has a BS degree in Mechanical Engineering from Princeton University and a MS degree in Civil Engineering from Drexel University. Mr. Kester is a Seismic Capability Engineer (SQUG Qualified) and is the Program Manager for Structural Maintenance Rule Structures Monitoring here at Peach Bottom. He is involved with all aspects of plant modification/configuration change activities. Other activities include penetration seals, hazard barrier control, heavy load rigging evaluations, lead shielding, scaffolding and other support activities.

" Mr. Lucas is a Site Senior Design Engineer with over 25 years of industry experience. He has a BS degree in Nuclear Engineering from Pennsylvania State University and an MBA from Texas Christian University. Mr. Lucas is a licensed Professional Engineer in the State of Delaware. He is the Site LRE for the Peach Bottom Response to NFFT Orders and Recommendations resulting from Fukushima.

• Mr. Knepper is a Site Senior Design Engineer with over 33 years of industry experience. He has a BS degree in Civil Engineering from Geneva College.

Mr. Knepper is a Seismic Capability Engineer (SQUG Qualified).

" Mr. Birmingham is an Operations Representative with over 32 years of industry experience in the field of Nuclear Power Plant Operations, Management, Training and Procedure Writing. He has been assigned to perform as the Operations Representative for the MSO, ASD and Fukushima Projects at Peach Bottom. He was a Nuclear Senior Reactor Operator (SRO),

On Shift Control Room Supervisor for 17 years.

Peach Bottom Atomic Power Station Unit 3 A3 -2 Correspondence No.: RS-14-001

A4 Selection of SSCs See Section 4, no changes were made to the SWEL for the follow-on walkdowns.

Peach Bottom Atomic Power Station Unit 3 A4-1 Correspondence No.: RS-14-001

A5 Seismic Walkdowns and Area Walk-Bys A5.1 OVERVIEW The follow-on Seismic Walkdowns and Area Walk-Bys were conducted by 2-person teams of trained Seismic Walkdown Engineers, in accordance with the EPRI Seismic Walkdown Guidance (Reference 1). The Seismic Walkdowns and Area Walk-Bys are discussed in more detail in the following sections.

A5.2 SEISMIC WALKDOWNS The results of the follow-on Seismic Walkdowns were documented in Appendix AC of this Annex A, using the Seismic Walkdown Checklist (SWC) template provided in the EPRI guidance document. Seismic Walkdowns were performed and the SWC's were completed for 13 of the 13 items identified in Table E-1 and 6 of the 6 items identified in Tables E-2 and E-3. Additionally, photographs have been included with most SWC's to provide a visual record of the item along with any significant comments noted on the SWC.

The Seismic Walkdown Checklists (SWC's) for these nineteen (19) components are documented in Appendix AC of this Annex A to indicate the results of these deferred and supplemental electrical cabinet internal inspections.

A5.2.1 Anchorage ConfigurationConfirmation No additional configuration verification was required as shown in Table A5-1 below. The number of SWEL items increased to include the 13 deferred items. The 6 supplemental internal cabinet inspection items were already included in the original Table 5-1.

Table A5-1. Anchorage Configuration Confirmation Unit 3 or Unit 0 No. of SWEL N/A Items Required to Items Unimmornt Items (B) Confirm? Confirmed (Common)? (A) (A-B)/2 3 92 18 37 38 0 (Common) 30 4 13 17 Unit3and 122 22 50 55 Common Peach Bottom Atomic Power Station Unit 3 A5-1 Correspondence No.: RS-14-001

A5.2.2 Issue Identification No adverse seismic conditions were identified during the follow-on walkdown activities.

Per Section 5.2.2 and Table A5-2, during the previous Seismic Walkdowns eight (8) conditions were identified and entered into the Corrective Action Program. Corrective actions were completed for 5 of the 8 items. Table A5-2 of this Annex A provides an updated summary of the conditions and the status of the corrective actions to address these conditions.

Table A5-2. Issues Identified during Seismic Walkdowns Action Actions Component ID Description of Issue Request Complete2 ID Y/N(Notes 1, )

3DD003 (also Possible open S-hook noted on light IR 01413285 Yes AWC-U0-1) fixture.

SV-3-03-033 SV Mounting does not match print. IR 01413655 Yes (also AWC-U3-13) 30C003, The MCR ceiling's restraint system is IR 01428651 No 30C004C, consistent with design documentation but 30C005A, L13-2 the design basis Calculation G-106-1 could 113, LI-9027, not be located from records management LR/TR-9123B, or Iron Mountain. This issue is to P13-6-90A, re-constitute design analysis to PR/TR3-2-3-404B, supplement existing calculation 26-5/Z-12, PR/TR-5805 (also specifically at MCR ceiling perimeter, AWC-UO-7) during NTTF 2.1 seismic re-evaluation.

3AE56, 3AE57, Anchorage for ECCS room coolers does IR 01437853 Yes 3AE58, 3BE55, not match drawings.

3BE57 (also AWC-U3-8) 30B338 A front panel screw is missing and another IR 01424719 Yes screw is loose.

30C722A The internal flow detector instrument has a IR 01424662 No - next loose mounting screw. RFO 30C722B The two internal power supplies are IR 01424692 No - next missing mounting screws where they are RFO mounted to the cabinet.

OAG12, OBG12, Inconsistency between the observed IR 01438055 Yes 0CG12, ODG12 OAG12, OBG12, OCG12, and ODG12 anchor bolt size and vendor document E-5-155.

Notes:

1. "Yes" indicates that corrective actions resulting from the issue are complete.

Peach Bottom Atomic Power Station Unit 3 A5 -2 Correspondence No.: RS-14-001

2. "No" indicates that corrective actions resulting from the issue are NOT complete. Actions are tracked by the IR number in the station Corrective Action Program.

A5.3 AREA WALK-BYS The purpose of the Area Walk-Bys is to identify potentially adverse seismic conditions associated with other SSCs located in the vicinity of the items being inspected. The results of the Area Walk-Bys were documented on the AWCs included in Appendix AD. A separate AWC was filled out for each area inspected. A single AWC was completed for areas where more than one item was located.

No adverse conditions were identified during the Area Walk-Bys associated with the follow-on walkdowns.

Per Section 5.3.1 and Table 5-3, during the previous seismic walkdowns four (4) conditions were identified and entered into the Corrective Action Program. Table A5-3 of this Annex A provides an updated summary of the conditions and the status of the corrective actions to address these conditions. Corrective actions were completed for all 4 of the 4 conditions identified.

Table A5-3. Issues Identified during Area Walk-Bys Action Actions Component Description of Issue Request Complete ID/Area ID Y/N(Notes 1, 2)

AWC-U3-2 U-bolt identified as unattached on a non-Q IR Yes line. 01413652 AWC-U3-3 Severely corroded nut on 3A HPSW Plate. IR Yes 01410116 AWC-U3-25 Ladder identified on floor of SW Screen IR Yes House. 01406272 AWC-U3-7 Loose cover plate bolt identified on 30C221 IR Yes judged acceptable. Bolt should be tightened. 01424737 Notes:

1. "Yes" indicates that corrective actions resulting from the issue are complete.

2. "No" indicates that corrective actions resulting from the issue are NOT complete. Actions are tracked by the IRnumber in the station Corrective Action Program.

Peach Bottom Atomic Power Station Unit 3 A5 -3 Correspondence No.: RS-14-001

A6 Licensing Basis Evaluations See Section 6, no new licensing basis evaluations were performed as a result of conditions identified during the follow-on Walkdowns or Area Walk-Bys.

Peach Bottom Atomic Power Station Unit 3 A6-1 Correspondence No.: RS-14-001

A7 IPEEE Vulnerabilities Resolution Report See Section 7, no changes of the IPEEE vulnerabilities resolutions were made for this Annex A.

Peach Bottom Atomic Power Station Unit 3 A7-1 Correspondence No.: RS-14-001

A8 Peer Review A peer review team consisted of at least two individuals, was assembled and peer reviews were performed in accordance with Section 6: Peer Reviews of the EPRI guidance document. The Peer Review process included the following activities:

" Review of the selection of SSCs in included in the follow-on walkdowns

" Review the checklists of items completed during the follow-on Seismic Walkdowns and Area Walk-Bys

" Review of Licensing basis evaluations, as applicable

" Review of the decisions for entering the potentially adverse conditions identified during the follow-on walkdowns into the CAP process

" Review of the final 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 AF of this Annex A.

Peach Bottom Atomic Power Station Unit 3 A8-11 Correspondence No.: RS-14-001

A9 References See Section 9 for references 1 - 10. The following new references were added for this Annex A:

11. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012

12. Exelon Generation Company, LLC 180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task force Review of Insights from the Fukushima Dai-ichi Accident, dated November 19, 2012 (RS-1 2-173)

13. Exelon Generation Company, LLC Proposed Resolution for Completion of the Seismic Walkdowns Associated with NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated September 16, 2013 Peach Bottom Atomic Power Station Unit 3 A9-1 Correspondence No.: RS-14-001

Appendix AA Project Personnel Resumes and SWE Certificates Resumes and certificates (where applicable) for the following people are found in Appendix AA of this Annex A:

T . G a lla g h e r . ........................................................................................... AA-2 P . Ke s te r. .............................................................................................. AA -5 J . Luca s ................................................................................ . . ....... AA -7 D . Kn e p p e r. ........................................................................................... A A-9 R . B irm ing h a m ....................................................................................... AA -1 1 Peach Bottom Atomic Power Station Unit 3 AA-1 Correspondence No.: RS-14-001

A- Exelon.

Tracey L. Gallagher EDUCATION Pennsylvania State University, B.S. Civil Engineering, 2007 EXPERTISE

" Steel, Concrete, Foundation Design and Analysis

" Seismic Analysis of New and Existing Structures

" Design Programs: STAAD Pro., GTStrudl, PCA Column, APlan, MathCAD, Visio, Excel, AutoCAD EXPERIENCE Exelon Generation (7/2012 - Present)

Lead Structural Engineer for the Fukushima 2.1 and 2.3 NTTF at Peach Bottom Atomic Power Station. Completed the EPRI Seismic Walkdown Engineer (SWE) Training.

Lead Structural Engineer on the Adjustable Speed Drive (ASD) project.

Sargent & Lundy, LLC - Wilmington, DE (7/2007 - 6/2012)

Structural Associate 3 - Design Engineering in the nuclear power industry.

" Duke Power Company

• Provided design engineering and onsite installation support for the Protected Service Water (PSW) Building Project associated with Oconee Nuclear Station's Tornado and High Energy Line Break (HELB) Mitigation License Amendment.

" PSE&G (Salem & Hope Creek Power Stations)

" Worked on a team which performed a Site Extent of Condition Assessment for the Unattended Openings Program (Security).

" Design of concrete and steel Blast Proof Enclosures for Security Upgrades.

" Design and Analysis of lifting lugs/steel structures to meet the regulatory requirements of NUREG 0612 and ANSI 14.6 "Special Lifting Devices"

" Lead Structural Engineer on the Feedwater Heater Tube Bundle Replacement Project.

Responsible for the analysis of the Turbine Building structure and sub grade concrete vaults for heavy load paths associated with the Rigging Plan. Provided field installation/outage support.

" Lead Engineer on the replacement of the Reactor Pressure Vessel (RPV) Head Strongback and Carousel.

" Seismic analysis of proposed and existing pipe supports, conduit supports and cabinets/panels for new loads.

" Dominion Power Company

• Provided installation support for refueling outages at North Anna and Surry Power Stations. These consisted of major capacity up-rate projects which included the replacement of the Feedwater Heater Tube Bundles and the Generator Stator/Rotor.

Peach Bottom Atomic Power Station Unit 3 AA-2 Correspondence No: RS-14-001

Exeton.

Responsible for the heavy haul path analysis and the re-evaluation of the Turbine Building structure for the increased weight of the new generator.

Exelon 0 Peach Bottom Fall 2007 outage support Borough of State College - State College, PA (5/2006 - 8/2006)

Engineering Intern, Public Works Dept.

PENNDOT - District 5 Allentown, PA (5/2005 - 812005)

Engineering Intern QUALIFICATIONS AND TRAINING EPRI Seismic Walkdown Engineer (SWE) training, 2012 Exelon Qualified Structural Engineer MEMBERSHIPS Member, Women in Nuclear (WIN)

Member, Phi Sigma Rho - National Engineering Sorority Peach Bottom Atomic Power Station Unit 3 AA-3 correspondence No: RS-14-001

010 a-FIrIiI RESEARCH fCIRI( POWER INST!TUTE 0

CL)

Certificate of Completion Tracey Gallagher Training on Near Term Task Force Recommendation 2.3

- Plant Seismic Walkdowns July 27, 2012 Daft ROWmi K. Kauaw.

EPRI UMugaf.

Stwtu*#I Ruisbay & hbtgrf y

Paul R. Kester EDUCATION Princeton University 1987 - B. S. In Mechanical Engineering Drexel University 1995 - M. S. In Civil Engineering PROFESSIONAL EXPERIENCE 1993 - present EXELON Nuclear / PECO Energy - Peach Bottom Atomic Power Station Senior Design Engineer

" Program manager for structural Maintenance Rule implementation

" Program manager for penetration seals and hazard barrier control

" Responsible for station seismic designs and equipment qualification

• Responsible for heavy load rigging evaluations

" Responsible for design of plant structural modifications 1990- 1993 Philadelphia Electric Company - Nuclear Group Headquarters Design Engineer a Program manager for penetration seals and hazard barrier control

• Responsible for design of plant structural modifications

• Responsible for writing design and purchase specifications 1987-1990 Philadelphia Electric Company - Peach Bottom Atomic Power Station Construction Engineer

• Responsible for resolution of field design and installation problems

• Responsible for conceptual design idea development

• Responsible for developing installation and testing procedures for new equipment

• Responsible for final acceptance inspections for new equipment QUALIFICATIONS

• SQUG Seismic Walkdown and Evaluation Qualified Engineer (5 day course)

• EXELON Maintenance Rule Structures Monitoring / Program Coordinator

• Peach Bottom Structural System Manager Peach Bottom Atomic Power Station Unit 3 AA-5 Correspondence No: RS-14-001

CLU Z0 0

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Jesse Lucas, P.E., MBA Relevant Qualifications:

" BS Nuclear Engineering, 7 years Exelon , 25 years industry experience

• MBA and understanding of Exelon Nuclear Project Authorization Process Employment History:

Exelon Generation 2004 - Present

• Design Engineer - responsible for various modifications and evaluations

• Engineering Services Engineer - responsible for department engineering budget, department self-assessments, and representing Engineering at the Station Ownership Committee.

Lead Responsible Engineer (LRE) - Peach Bottom Response to NTTF Orders and Recommendations resulting from Fukushima

= Site LRE for Flood Feature Walkdowns in accordance with NEI 12-07

= Site LRE for Flood Reevaluations in accordance with CR-7046 z Site Engineer for Seismic Walkdowns - completed EPRI Training on NTTF Recommendation 2.3 - Plant Seismic Walkdowns

= Site Engineer for Spent Fuel Pool Instrumentation

=> Site LRE for Hardened Containment Vent System

=> Site LRE for FLEX Modifications - Mechanical and Electrical RCM Technologies, Inc. 1993 -2004

. Client Manger for of design services contracts with power industry clients Impell - ABB Corporation 1991 -1993 Stone & Webster Inc. 1986-1989 Education:

Texas Christian University MBA - Finance Pennsylvania State University BS - Nuclear Engineering Licenses and Associations:

• Professional Engineer - State of Delaware Registration Number 9586 Peach Bottom Atomic Power Station Unit 3 AA-7 Correspondence No: RS-14-001

00 0,1 a-M~al$IIIfAICH INS~tUIf!

0 (D

04 Certificate of Completion "0

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Jesse Lucas Training on Near Term Task Force Recommendation 2.3

- Plant Seismic Walkdowns June 21, 2012 D0ta Rnbee K. Kammawwa EPAS I~gr Sbviaw A --~bI~ &kIph

David P Knepper EDUCATION

. Geneva College - Bachelor of Science Civil Engineering, 1980 PROFESSIONAL EXPERIENCE 1999 - present EXELON Nuclear / PECO Energy - Peach Bottom Atomic Power Station Senior Design Engineer Lead Responsible Engineer for numerous Extended Power Uprate projects Responsible for station seismic designs and equipment qualification Responsible for heavy load rigging evaluations Responsible for design of plant structural modifications 1980- 1999 Gilbert Associates / Parsons Power Design Engineer

• Lead Engineer for structural modifications at Three Mile Island and Salem/Hope Creek Lead Engineer for structural modifications at the Philadelphia Naval Shipyard

• Responsible for structural design of modifications at numerous nuclear power facilities

• Provided site support for modification installation QUALIFICATIONS SQUG Seismic Walkdown and Evaluation Qualified Engineer (5 day course)

EXELON Maintenance Rule Structures Monitoring Peach Bottom System Manager Peach Bottom Atomic Power Station Unit 3 AA-9 Correspondence No: RS-14-001

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(Trrtifiratr of ArI~irturxnet 9J4is is to (6Irrify tipat David P. Knepper 4as (JSomplettb t4i' I'QOI UNtkbowni

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Robert Steele Birmingham 1218 Furnace Road Airville, Pa 17302 Email n2fix@aol.com (717) 858-4144 Career Summary A disciplined, goal oriented professional with over 32 years experience in the field of Nuclear Power Plant Operations, Management, Training, Procedure Writing, Major strengths are organization, attention to detail, problem solving, and change management.

Over 33 years experience as a volunteer fire fighter. Certified scuba diver with over 25 yrs experience.

Work Experience 10/2010 -

12-2013 Westwind Group LLC, Wrightsville Beach, North Carolina.

Assigned to perform as the Operations Representative for the MSO, ASD and Fukushima projects at the Peach Bottom Atomic Power Station for Exelon Nuclear, Delta, Pennsylvania.

9/1992 - Exelon Nuclear, Delta, Pennsylvania 9/2009 Nuclear Senior Reactor Operator, On shift Control Room Supervisor Performed nuclear fuel element handling activities including transfer, core loading and unloading and fuel pool operations. Directed reactor operators and equipment operators during transient and emergency situations, in accordance with abnormal operating, off normal, operational transient and emergency operating procedures. Conducted operations and inspections outside of the control room. Provided oversight during system electrical switching and electric sub station activities. Authorized maintenance activities on units and changes in system and equipment status. Authorized the performance of surveillance testing and reviewed testing upon completion. Approved and authorized system and equipment blocking under the clearance e and tagging process. Provided training to EO, RO and SRO trainees while on shift. Administered EO plant walk around exams for qualification. Coordinated the performance of the plant schedule for plant and equipment testing, equipment blocking and other work activities.

Reviewed all documented plant deficiencies for regulatory and tech spec compliance, and for overall plant impact.

04/1996 - Exelon Nuclear, Delta, Pennsylvania 5/1998 Initial Licensed Operator Instructor Qualified as a classroom and control room simulator instructor and as a simulator operator. conducted classroom, simulator and in-plant training sessions for a class of initial reactor and senior reactor operator trainees. Conducted classroom and in-plant training for a class of initial equipment operator trainees. Maintained an active SRO license while an instructor, performing control room shift supervisor duties during weekends and load drops.

Peach Bottom Atomic Power Station Unit 3 AA-11 Correspondence No: RS-14-001

8/1991 - Exelon Nuclear, Delta, Pennsylvania 9/1992 Trainee, Senior Reactor Operator 7/1988- Exelon Nuclear, Delta, Pennsylvania 9/1991 Reactor Operator, On shift Control Room RO Responded to unit, system or equipment abnormalities, diagnosing the cause and recommending or taking action as required. Recorded data from control room indicators during rounds. Identified malfunctions of equipment, instruments or controls and reported the conditions to the supervisor. Monitored and operated turbines, generators, pumps and auxiliary power plant equipment.

Implemented operational procedures during normal operations and during startups and shutdowns. Dispatched instructions to personnel through radio or telephone systems to coordinate auxiliary equipment operation. Adjusted reactor controls to position control rods and adjust recirc pump speed to regulate flux level, reactor period, coolant temperature and rate of power change in accordance with operating procedures. Performed plant surveillance testing in the control room and coordinated performance of testing outside of the control room. Develop and write system and equipment safety blocking permits under the clearance and tagging process.

8/1987- Exelon Nudear, Delta, Pennsylvania 7/1988 Trainee, Reactor Operator 11/1981 Exelon Nuclear, Delta, Pennsylvania 8/1987 Floor Operator Responded as directed to unit, system or equipment abnormalities and reporting observations to the control room, and taking corrective actions as directed.

Recorded data from plant indicators during performance of rounds. Monitored in plant equipment and identify malfunctions of equipment, instruments or controls and report the condition to the control room. Implemented operational procedures as directed during normal and during startups and shutdowns.

Coordinated activities with the control room or other equipment operators using the radio or telephone systems to operate plant auxiliary equipment. Performed surveillance testing as directed by the control room. Removed equipment from service and applied system and equipment safety blocking permits under the clearance and tagging process. Returned equipment to service after completion of maintenance. Acted and a member of the plant fire brigade and medical safety team.

4/1977 - United States Coast Guard 5/1981 Machinery Technician Served on the cutter POINT ROBERTS, Mayport, Florida and at Training Center Cape May, New Jersey. Attained the rank of Machinery Technician Fist Class MK1 (E-6). Duties on the cutter POINT ROBERTS were maintaining the diesel engines and generators, performing Engineer of the Watch duties in the engine room and standing bridge watches performing helm and navigation duties.

Assigned responsibilities included #1 rescue swimmer and starboard machine gunner. Qualified as a Boarding Officer and participated in the arrest and seizure Peach Bottom Atomic Power Station Unit 3 AA-12 Correspondence No: RS-14-001

of over 200 tons of illegal drugs. Served as armed escort to the President of the United States.

Duties at Training Center Cape May were operating the base steam heating plant, qualifying to the same standard as a New Jersey State Certified Boiler Operator. Maintenance of boiler plant included boiler cleaning and refractory repair, rebuild of plant valves, replacement of system piping and operation of the demineralized water system.

Later responsibilities were managing the base motor pool of over 40 vehicles including cranes, construction equipment, bucket trucks and fire equipment.

Maintained the base deep well fresh water pumps, backup emergency generators, and coordination of all base fuel, oil and water deliveries. Qualified as operator for a 25 ton crane, backhoe and loader, fork lift, and other various equipment. Additional duties were operation of fire equipment to provide backup to the base fire department for structural and aircraft crash fire and rescue and provided mutual aid to the towns of Cape May, Wildwood and Wildwood Crest during major fires.

Extensive experience with diesel engine maintenance, auxiliary boiler operation and aircraft and structural fire fighting.

6/1972 - Central Sports Cars, Holmes, Pa.

7/1976 Technician Responsibilities included managing a two-three person automobile rebuilding shop. Duties were rebuilding body, electrical and mechanical component of wrecked English automobiles, including welding and painting. Coordinated deliveries of automobile parts to other repair facilities in the area. Maintained racing car for SCCA E-Production sports car racing.

Education 1972 Penncrest High School, Media, Pa. Graduated Peach Bottom Atomic Power Station Unit 3 AA-13 Correspondence No: RS-14-001

Appendix AB Equipment List See Appendix B. No changes were made to the Unit 3 and Unit 0 Equipment Lists (SWEL's) for this Annex A.

Peach Bottom Atomic Power Station Unit 3 AB-1 Correspondence No.: RS-14-001

Appendix AC Seismic Walkdown Checklist (SWC's)

Table AC-1 provides a description of each item (13 items), anchorage verification confirmation, a list of Area Walk-By Checklists associated with each item and comments of each Seismic Walkdown Checklist. All items in Table AC-1 were deferred items listed in Table E-1 of this report, and were accessible during the follow-on walkdowns.

Table AC-2 provides a description of each item (6 items) subject to supplemental internal inspections. All items in Table AC-2 of this report were listed in Table E-2 and E-3, and were accessible without safety and operational hazard.

The "Anchorage Configuration Confirmation" column is described in Section 5.2.1 of this report. The last column in Tables AC-1 and AC-2 provides the corresponding Area Walk-By Checklist (AWC). There are a total of 6 AWC's included in Appendix AD of this Annex A. AWC identifiers with asterisks (*) indicate the second or subsequent SWEL item included with a specific Area Walk-By.

Peach Bottom Atomic Power Station Unit 3 AC-1 Correspondence No.: RS-14-001

Table AC-1. Summary of Seismic Walkdown Checklists Anchor Component ID Description Configuration AWC-Ux-YY Confirmed?

E234-R-B 480V Reactor (30B037) Area MCC E234- N U3-29 R-B E13A4 480V Bus E13A4 (00B094) N U0-14 E234 480V Load N U3-24 (30B011) Center E234 E23 Emergency 4kV (30A016) Aux Switchgear N U3-30 E23 Inboard Main AO-3-O1A-080A Steam Isolation N/A U3-26 Valve A Inboard Main AO-3-01A-080C Steam Isolation N/A U3-26 Valve C Safety Relief RV-3-02-071 D Valve D N/A U3-28 Safety Relief RV-3-02-071F Valve F N/A U328 MO03-06-029A Feedwater Stop N/A U3-28 Valve HPCI Turbine MO-3-23-015 SteamN/A Inboard Isolation U3-26 Valve HPCI Discharge MO-3-23-019 to Feedwater Line N/A U3-27 Valve Instrument N2 3BT545 Accumulator U3-28 Instrument N2 3KT545 Accumulator Y U3-28 Peach Bottom Atomic Power Station Unit 3 AC-2 Correspondence No.: RS-14-001

ShtaIf:4 Status: ;MNEI u[-'

Seismic Walkdown Checlist (SWC)

Equipment ID No. 308037 Equip. Class' (01) Motor Control Centers Equipment Description 480V ReactorArea MCC E234-R-B Location: Bldg. RxfBl. Floor El. 135'-0Q Room, Area R3-23 M&-uicfturer, M6- E-( -pti-dmrt-u omnended)-EATONEL-ECTRIGAL - - . . ...

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Ydý3 UO N/AD3

3. Is the anchorage free of corrosion that is more than mild surface YL" UtO N/AO oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y 'NI-I UO N/AQI

5. Is the anchorage configuration consistent with plant documentation? Y-I NO UIO N/Am/*"

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

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

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

Peach Bottom Atomic Power Station Unit 3 AC-3 Correspondence No.: RS-14-001

Saeet of 4 Status: Y4 N12 Ul-Seismic Walkdown Checklist (SWC)

Equipment ID No. 30B037 Equip. Class' (01) Motor Control Centers Equipment Description 480V ReactorArea MCC E234-R-B InteractionEffects

.l1U *9JLI 1UIL IL ilUIil ttAIJUP.L U) II~45U3 G9 UiJziIIL WI tUtULUa £I t~ILJ *f--.1 L~If%4

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y[/NI-I UU N/A]

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

9. Do attached lines have adequate flexibility to avoid damage? *Uf-IUO N/A[

10. Based on the above seismic interaction evaluations, is equipment free MNu3 of potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could VIE 'NO 1 u-adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: T. Gallaaher l ;6F&-tof D/

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Date: 9-20-13 J. Lucas 9-20-13 Peach Bottom Atomic Power Station Unit 3 AC-4 Correspondence No.: RS-14-001

Sheet 3 of 4 Status: YZ NEI UL-Seismic Walkdown Checklist (SWC)

Equipment ID No. 30B037 Equip. Class' (01) Motor Control Centers Equipment Description 480V ReactorArea MCC E234-R-B Photographs Note: Note:

Note: Pre-dnilledholes by manufacturer. Note:

Peach Bottom Atomic Power Statinn Unit 3 AC-5 Correspondence No.: RS-14-001

Sheet 4 of 4 Status: YN N[-I- U[I Seismic Walkdown Checklist (SWC)

Equipment ID No. 30B037 Equip. Class2 (01) Motor Control Centers Equipment Description 480V ReactorArea MCC E234-R-B Photographs Peach Bottom Atomic Power Station Unit 3 AC-6 Correspondence No.: RS-14-001

. g. e,-iF Sheet 1 ofa' Status: Y91 NO UO Seismic Walkdown Checklist (SWC) -

Equipment ID No. 00B094 Equip. Class'=02) Low Voltage Switchoears Equipment Description 480V Bus E13A4 Location: Bldg. ECT-3 Floor El. 163'-0" Room, Area Switch GearRooms Manufacturer, Model, Etc. (optional but recommended) 1005 ITE Circuit BreakerLTD, 33.44640 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be. used to record.the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Yo NOI UQ N/AQ

3. Is the anchorage free of corrosion that is more than mild surface Ypd NOI Uf- N/AO oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y09 NO UD N/AD

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

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

En te r the equ ip m e nt c lass na m e fro m Erre-l Mfw _n ..-- ou " "o n -. _

J_'_' urc z.. ;,r

_r1_-,EIf . z-:n -- . .

Peach Bottom Atomic Power Station Unit 3 AC-7 Correspondence No.: RS-14-001

Sheet 2 of Z fr,1,!M3 Status: Y. NEI UO Seismic Waikdown Checklist (SWC)

Equipment ID No. 00B094 Equip. Class, (02) Low Voltage Switchgears Equipment Description 480V Bus E13A4 Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? YO NO Ur N/AJ

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YR" No Ur N/AI and masonry block walls not likely to collapse onto the equipment?

dqule s

9 th ve to 9p,"

dama 1 YFL A-701 #A,- (I )6

9. Do attached lines have adequal flexibility to avoid damage? YO NO UEJ NIA)A

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Date: z l-U13 Peach Bottom Atomic Power Station Unit 3 AC-8 Correspondence No.: RS-14-001

Sheet 3 of 5 Status: Y] N[-E Ur-]

Seismic Walkdown Checklist (SWC)

Equipment ID No. 008094 Equip. Class1 (02) Low Voltaqe Switchqears Equipment Description 480V Bus E13A4 Photographs Note: Note:

Note: Note: East Bay Peach Bottom Atomic Power Station Unit 3 AC-9 Correspondence No.: RS-14-001

Sheet 4 of 5 Status: YN Nr-" UMI Seismic Walkdown Checklist (SWC)

Equipment ID No. 00B094 Equip. Class (02) Low Voltage Switchcqears Equipment Description 480V Bus E13A4 Photographs I I IIUM týVIIIUI Ody Peach Bottom Atomic Power Station Unit 3 AC-10 Correspondence No.: RS-14-001

Sheet 5 of 5 Status: Y[ NE- UI-Seismic Walkdown Checklist (SWC)

Equipment ID No. 00B094 Equip. Class (02) Low Voltage Switch-gears Equipment Description 480V Bus E13A4 Photographs Peach Bottom Atomic Power Station Unit 3 AC-11 Correspondence No.: RS-14-001

Status: &NO U Seismic Walkdown Checklist (SWC)

Equipment ID No. 30B011 Equip. Class1 (02) Low Voltaa Swltcageam Equipment Description 480V Load Genter E234 Location: Bldg. HhNO Floor El. 1651-00 Room, Area 3.-41 ManufacuerMdLr(poabreomneYiECRLIBEK~T Iutrcdo88 for Compleug Checklft This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and f'mdings. Additional space is provided at the end of this checklist for documenting other comments.

Anomae

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

E4&Aal ~4.69lk/ eyoAe

2. Is the anchorage free of bent, broken, missing or loose hardware? YO1N1 UO N/AU

3. Is the anchorage free of corrosion that is more than mild surface Yv<ý U- N/AU oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Yv-lu UO N/AU

5. Is the anchorage configuration consistent with plant documentation? YO NO UO N/AIVrý (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

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

Peach Bottom Atomic Power Station Unit 3 AC-12 Correspondence No.: RS-14-001

SheetX04 status. NCI U[I Swiamlo Wileown Chekli (SWC)

Equipment ID No. 0B01 1 Equip. Cass (02) Low Volue SmV~maa EquipmentDescription 4cV Laud CantE234

7. Am soft targets free frn impact by nearby equipment or structures? YU0 UD N/AE3

8. Ar overhead equipment, distribution sysms, ceiling Wes and ligbting, U N/MAO and masomny block walls nMt likely to collapse Oano the equipment?

A"swo.5 \ o t, is .etn cc foI

9. Do attached lines have adea flexibility to avoid damage? XR~f~O UO N/AD3

10. Based on the above seim intraction evaluations, is equipnent free YBO-NOUO of potentially adverse seismic interactim e ts?

Other AdvmsCedne

11. Have you looked for and found no other seismic conditions that could YwgýiU[

adversely affect the saft functions of the equipment?

QMMinkJAdditiotml p agsny be added as necessay)

- Jdl -

Evaluated by: T 7ZA 0 Date: 9-20-13 OZ&,4 j.i1 9-20-13 Peach Bottom Atomic Power Station Unit 3 AC-13 Correspondence No.: RS-14-001

Sheet 3 of 4 Status: YZ NEI U-Seismic Walkdown Checklist (SWC)

Equipment ID No. 30B01 1 Equip. Class, (02) Low Voltage Switchqears Equipment Description 480V Load CenterE234 Photographs Note: Note:

Note: Extemally mounted to the foundation Note:

(welded to embedded steel)

Peach Bottom Atomic Power Station Unit 3 AC-14 Correspondence No.: RS-14-001

Sheet 4 of 4 Status: YN NE-- U[LI Seismic Walkdown Checklist (SWC)

Equipment ID No. 30B011 Equip. Class 2 (02) Low Voltage Switch-gears Equipment Description 480V Load CenterE234 Photographs Note:

ote: -ign voltage -nu or Loaa .enter r~ote: I-vign voltage cna OT Loaa uenter Peach Bottom Atomic Power Station Unit 3 AC-1 5 Correspondence No.: RS-14-001

Status: Sheet/

&NOOfuD 4

Sesmlc Walkdown Chckldt (SWC)

Equipment ID No. X0A016 Equip. Class (03) Medka Vo/mta Swtch aws Equipment Description Emeh enc4kVAux Swfthw (E23)

Location: Bldg. TuDtk Floor El. 1A-O" Room, Area T3-71

-Maiw--. urer MndlE jtiii b(li-b mnii YGENE

-- ICTRIC COPANVY-...............

Imsrcdow for Complsu Ceckix st This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documeting other comments.

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

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

Y*iN'C3 UO N/AD

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?

5. Is the anchorage configuration consistent with plant documentation? YO NO UO N/Ap---

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

6. Based on the above anchorage evaluations, is the anchorage free of YffghU13 potentially adverse seismic conditions?

AEnter the equipment class nane from Appendix B: Classes of Equipment.

Peach Bottom Atomic Power Station Unit 3 AC-16 Correspondence No.: RS-14-001

S Sh of 4 Status: VNEI uCi]

Selomio Walkdown Chwlit (SWC)

Equipment ID No. 3QA016 Equip. Class, (03) Medium Vol/ow Swlhadm Equipment Description Emeenv4kVAu Swftchaer (E23) h.d*Aredo Effets YLNwrI DDwAn

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y NI"O UD N/AFD and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YbN1O UO N/AU

10. Based on the above seismic inteaction evaluations, is equipment free Yeý3 UF of potentially adverse seismic interaction effects?

OdrAdvere anite

11. Have you looked for and found no other seismic conditions that could Y9<3J U[

adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: T..Ga/aohe m AAIIIu di Date: 9.20-13

.1 Lucas 9-20-13 Peach Bottom Atomic Power Station Unit 3 AC-1 7 Correspondence No.: RS-14-001

Sheet 3 of 4 Status: YJZ NEI ULI Seismic Walkdown Checklist (SWC)

Equipment ID No. 30A016 Equip. Class' (03) Medium Voltage Switch-gears Equipment Description Emerg.ency 4kV Aux Switch-gear (E23)

Photographs 114ULV.

Note:

Peach Bottom Atomic Power Station Unit 3 AC-1 8 Correspondence No.: RS-14-001

Sheet 4 of 4 Status: YE; NE-1 UDE]

Seismic Walkdown Checklist (SWC)

Equipment ID No. 30A016 Equip. Class2 (03) Medium Voltage Switch-gears Equipment Description Emergency 4kV Aux Switchgear (E23)

Pho Note: Note:

Note: Note:

Peach Bottom Atomic Power Station Unit 3 AC-1 9 Correspondence No.: RS-14-001

Status: YITN*IU[]

Seismic Walkdown Checktlit (SWC)

Equipment ID No. AO-3.01A.OSOA Equip. Class, (07) Fluid(Akrv) Va/ves Equipment Description Inboard Ak, Steam Isdation Valvm A Location: Bldg. H &. Floor El. 134-0" Room, Area Drvwell (D/W 3-18)

Man F! r, el, t. ( o-Wond EIRVALS -OONA OL S .......

Instructluu for Comipleting Checklt This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

I. Is the anchorage configuration verification required (i.e., is the item one YO N12 of the 50% of SWEL items requiring such verification)?

2. h the anchorage free of bent, broken, missing or loose hardware? YýUO WIAO

3. Is the anchorage free of corrosion that is more than mild surface YM0-~ UE3 NIAfJ oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YD3 NO UE3 NIA[PO"

,ko 6(k'Ck&r5 i#k oýLp1k

5. Is the anchorage configuration consistent with plant documentation? YO NO UO NIAW,-'

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

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

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

Peach Bottom Atomic Power Station Unit 3 AC-20 Correspondence No.: RS-14-001

Sheetuf3 Sau:Y S'r-,U1 Selsmi Walkdown ChecMlist (SWC)

Equipment ID No. AO3-OIA-00.4 Equip. Classt (07) Flu*d (AMOWvd) Valves Equipment Description a-: t.,Mslto 7-oad 275Valve

7. Areed sffetsi iii~b eiyeupeto~ltrs eQ --ý

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YW4i M N/AO and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YW'NE3 UD N/AD3

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

11. Have you looked for and found no other seismic conditions that could 0"U adversely affect the safety functions of the equipment?

Othe (Adves oditionlpgsmybededanee,)

Cominals(Additional paMe may be added as necessary)

EvaIunt~d

~~~~~~~1~

... .t bv~ T.T t~nli~w

.. hv . .

JAIA III 0-0/

4L Date: 9-14-13 J.LucaL 9-14-13 Peach Bottom Atomic Power Station Unit 3 AC-21 Correspondence No.: RS-14-001

Sheet 3 of 3 Status: YN NI'- UF-Seismic Walkdown Checklist (SWC)

Equipment ID No. AO-3-OIA-080A Equip. Class1 (07) Fluid (Air/Hyd) Valves Equipment Description Inboard Main Steam Isolation Valve A Photographs Note: Label of valve Note: Chains are for temporaryrigging during the outage.

Note: Rigging chains tied off are lAW Note: Cable tray/Conduit/Pipingabove, no adverse housekeeping procedures. conditions.

Peach Bottom Atomic Power Station Unit 3 AC-22 Correspondence No.: RS-14-001

Status: Sheets 7N[ND '-O 3U[]

Seismic Walkdown Checklist (SWC)

Equipment ID No. AO-3-01A-080C Equip. Class1 (07) Fluid M ~r/-ld Valvew Equipment Description Inbwad MAin Steam Isolation Valve C Location: Bldg. R-. Floor El. 134QL0 Room, Area D~nI-welDW 3-19) mm . i*I*B* IAAl I* a *A*J

• J J*A JAJ*

- manufactureri-MdeiEltcz-opt-1onat-out-reeommenaeo--WEmin-RLVa-ati'vIfl.JiPI Instructions for Completing Checkli This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

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

Lieu - rnwnled vodv.

2. Is the anchorage free of bent, broken, missing or loose hardware? N['] UO N/AO

3. Is the anchorage free of corrosion that is more than mild surface YQONO UD N/All oxidation?

YO: NO: U[O N/Aeýý

4. Is the anchorage free of visible cracks in the concrete near the anchors?

I Ain onekors iA CEzac-dP

5. Is the anchorage configuration consistent with plant documentation? YO NO UO N/A&--*

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

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

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

Peach Bottom Atomic Power Station Unit 3 AC-23 Correspondence No.: RS-14-001

Sheett2au: f Stts: Y93N[I 3U[]

Seinsic Walkdown Checidlt (SWC)

Equipment ID No. AO-3-OIA-080C Equip. Class1 (07)Fluid(Ar/hvd Va/ves Equipment Description InboardMakn Steam Iso n Valve C 7 Are* soft *tS imp-by earby-eqi nt tc s? Y-T6*YUOAf3

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, W/NO UD N/AO and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YOi4tj UO N1AE3

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

Othr Adverse Conditiom

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

Comments (Additional pages may be added as necessary) r.vAUIUtW, U7.v 7 /2'.IIaraLav 7JýMaoi /). WLJiC.

1.0 V drool Peach Bottom Atomic Power Station Unit 3 AC-24 Correspondence No.: RS-14-001

Sheet 3 of 3 Status: YN NE] UM Seismic Walkdown Checklist (SWC)

Equipment ID No. AO-3-O1A-080C Equip. Class, (07) Fluid (Air/Hyd) Valves Equipment Description Inboard Main Steam Isolation Valve C Photoeraphs Note: iNote: main tream "U"Line Peach Bottom Atomic Power Station Unit 3 AC-25 Correspondence No.: RS-14-001

Sheet I of 3 Status: YO NEI UO Sehmic Wdkdown Cecldl (SWC)

Equipment ID No. RV-3-42.071D Equip. Class- (07 FkI (/riHvd)Va Equipment Description Sa@Wy ReW Valve D Location: Bldg. R9 Floor El. 1I5rO" Room, Area DswOW (MDM 3-26)

Manufacturer, Model, Etc. (optional but comnded) TARGET ROCK Imrucl fot Comledu Chneckh This chwckiss may be an~d to dOuacetth rcalm of tle Seisnie Wallkimw e an item of equipmenti ani the-SWEL. The space below each of the following questions may be used to record the results of judgaents and findings. Addiional space is provided at the end of this checklist for documenting other conmmeM

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

2. h the anchorage free of bent. broken, missing or loose hardware? YQU]N Ui N/Ai

3. h the anchorage free of corrosion that is morm than mild smface YIV/N UE! N/AD oxidation?

4. h the anchorage free of visible cracks in the concrete newr the anchors? YO NO liD WAM V ULiet Mvoj4of- riO LWri4oc5

5. Is the anchorage configuration consistent with plant dc eti? YO NO UD NIAMU (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of YLM'/ND Ur potentially adverse seismic conditions?

IEnter th equipmm class fwne from Appendix B: Cmaes of Equoipnen.

Peach Bottom Atomic Power Station Unit 3 AC-26 Correspondence No.: RS-14-001

Sheet 2 of 3 Status: YO NO U[3 Seismic Weudown Cheolde (SWC)

Equipment ID No. RV-.02.71D Equip. ams f07) Fud Af VaW..

Equipment Description &0& RaFW VaW. D

7. Are soft targets free from impact by nearby equipment or structures? Y!1NO UD N/AD

8. Are overhead equipment, distributwio systems, ceiling tiles and ligting YBO'NO UO N/AD and masom'y block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YlE,40 Lui N/Ad3 UD WAD

10. Based on the above seismic inteaction evaluations, is equipment free of potentially adverse seismic intemaction effects?

01zm' Adnmm Codkg

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

fmiMnnk (Additional p s may be added as necmy)

Evaluated by: 77. Lu.e~as~~ Date:

Peach Bottom Atomic Power Station Unit 3 AC-27 Correspondence No.: RS-14-001

Sheet 3 of 3 Status: Y0 N[l UF-Seismic Walkdown Checklist (SWC)

Equipment ID No. RV-3-02-071D Equip. Class' (07) Fluid (Air/Hyd) Valves Equipment Description Safety Relief Valve D Photographs Note: Note:

NNote:

Peach Bottom Atomic Power Station Unit 3 AC-28 Correspondence No.: RS-14-001

Sheet 1of 3 Status: YtTNQ uO]

Seismic Walkdown Checlist (SWC)

Equipment ID No. RV-3.-2.071F Equip. Class' (07 Fluid WHvd) Vales Equipment Descripti SMaet, ReOlW Valve F Location: Bldg. R8 Floor El. 155'-0" Room, Area Drvws#OWM3-29)

Manufacturer. Model, Etc. (optional but recommended) TARGET ROCK Imtuu om for Cuuiht Clwdiht This cckist may be used to ouetterslso h esi *1ionoa 'qqxnev SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

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

Ll u (m4 ,4ed - n(C+ reUAfcJ

2. Is the anchorage free of bent, broken, missing or loose hardware? Yt**it] 1)] N/AD

3. Is the anchorage free of corrosion that is more than mild surface YllO UE] N/AO oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YO NO UD N/AMI

,4}o w Chors.

5. Is the anchorage configuration consistent with plant documentation? YO NO U] N/AQe' (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

YJJ/NE3 UlO

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

IEner die equipmen class name from Appendix B: Claes of EquipmeM.

Peach Bottom Atomic Power Station Unit 3 AC-29 Correspondence No.: RS-14-001

Sheet 2 of 3 Status-: )Z N U[

Seismic Wdkdown Checkidst (SWC)

Equipment ID No. RV-3.M2.071F Equip. Cass (0~ol7) 7:d A'Mwl) VAX7e.

Equipment Description Sfv ROei VA F

7. Are soft targets five from impact by nearby equipment or structures? Y&NDO UO N/AD S. Are ovehead equipmert distribution systems, ceiling tiles and lighting, Y9<3 UD N/WA and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YM/ND UO N/A

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

Odwer Ades Qnld

11. Have you looked for and found no other seismic conditions that could Y IND3 Ui[

adversely affect the safety functions of the equipment?

C~,uis (Additional pages may be added as necessary)

Evaluated uj.

e,

,..J.

1' I~ tv 4,'t

• ,,.v* L ,,,* .-.

Date:10/F Nad m ._____ /0/0,3h Peach Bottom Atomic Power Station Unit 3 AC-30 Correspondence No.: RS-14-001

Sheet 3 of 3 Status: YZ NEI uo-Seismic Walkdown Checklist (SWC)

Equipment ID No. RV-3-02-071F Equip. Class, (07) Fluid (Air/Hyd) Valves Equipment Description Safety Relief Valve F Photographs Note: Tag for valve was not easily accessible/ Note: "Foxtrot"writing on insulation covering.

could not reach Note: Note: Tag for Temperature Element TE 3-02-113F, this is for Safety Relief Valve 71F Discharge Valve (picture to verify correctcomponent)

Peach Bottom Atomic Power Station Unit 3 AC-31 Correspondence No.: RS-14-001

Sheet 1of 3 Status: YONO NEIU Seisnmi Walkdown Chacidit (SWC)

Equipment MINo. ACM464M Equip. Class' (MBa) Aftm Ooemtd Vatmi Equipment Description Foodsater St' Vatm Location: Bldg. RB Floor El. 155'-O" Room, Area DiMW D2 9)

Manufacturer, Model, Etc. (optional but recommended) WALWORTH CO Iiubmrtftsomr CompkUft Checklis 4- ýAsb- -f *Lý 0-60&6 TIF-Ikdftýja a& ý  !"MM Oa 6ona-at 0ý bk^

SWEL The space below each of the following quesons may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

1. Is the anchorage configuration verification required (ie., is the itemn one YO NVO of the 50% of SWEL items requiring such verification)?

U~n - rnAn4fO( - nJ Yfty'(ed.

2. Is the anchorage ftee of butn broken, missing or loose hardware?

3. Is the anchorage free of corrosion that is more than mild surface Y9N6 UO N/AO oxidation?

4. Is the anchorage ftee of visible cracks in the concrete near the anchors? YO NO UO NIAW

5. Is the anchorage configuration consistent with plant docunentation? YO NO UO NIAV*

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

6. Based on the above anchorage evaluations, is the anchorage free of YINE3 UO potentially adverse seismic conditions?

SEnter She equipment da nam from Appendix B: Clasm of EquiponL Peach Bottom Atomic Power Station Unit 3 AC-32 Correspondence No.: RS-14-001

Sheet 2 of 3 Status: YO NE uO Sdmnlo Wadkdown Chseldlt(SWO)

Equipment ID No. )C44&WM Equip. Crss ( o fM r d V&

Equipment Description FmedwatrStag Wahy

7. Are soft targets free from impact by nearby equipment or structures? YI1NO UO N/AO S. Afr overhead equipment, distribution systems, ceil tiles and ligtg, YV(NI U1] N/AO and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YV~N0 110 WAQ

10. Band on the above seismic interaction evaluations, is equipment faree Ygr' U0 of potentially adverse seismic interaction effects?

Other AMnM CoadaM=

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

SK( L(Addit ional paps may be added as necsary)

Evaluated by: -S. A . Date: .1L3/L2.

m WW,,O-r,1 IUd.

%0==-0 z;MPM - V - /0 /a A Peach Bottom Atomic Power Station Unit 3 AC-33 Correspondence No.: RS-14-001

Sheet 3 of 3 Status: YZ NEI U" Seismic Walkdown Checklist (SWC)

Equipment ID No. MO-3-06-029A Equip. Class' (08a) Motor Operated Valves Equipment Description Feedwater StoW Valve Photographs Note: Note:

Note: Note:

Peach Bottom Atomic Power Station Unit 3 AC-34 Correspondence No.: RS-14-001

Status: NI uD Seismic Walkdown Checklist (SWC)

Equipment ID Nol.MO63-23-015 Equip. Class Ma Motor QweleW3 Va-Equipment Description HPCI Turbine Steam Line Inboard Isolation Valve Location: Bldg. Rig Floor El. 134'-0 Room Area DrinvwellW3-15)

IIAmAI abAD*di* * *

- manutaeturer,-ModleI;-ttciOpttonai-tbut-feconunen~aedl fV-kWIJNvf01211 Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchoame

1. Is the anchorage configuration verification required (i.e., is the item one YO NM,"

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

Ut- imunkdc \ýC&16

2. Is the anchorage free of bent, broken, missing or loose hardware? Y23*N'O UO N/AO

3. Is the anchorage free of corrosion that is more than mild surface YQ-13j UD N/AO oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YO NO UO NIAM--'-

)jW atch or 'r) Coyvrheý.

5. Is the anchorage configuration consistent with plant documentation? YO NO UO N/A[---

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

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

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

Peach Bottom Atomic Power Station Unit 3 AC-35 Correspondence No.: RS-14-001

Status: ul Seismic Waikdown Ch-cklit (SWC)

Equipment ID No. M043923-015 Equip. Class2 (08a) Motor Ooerated Va/ves Equipment Description HP:CI Turbine Steam Line Inboard Iso/ation Valve Ae lft iiieiikeT~i

7. Fmatb eiy~iiiei r~bfr Y&4a UD 1w/

A/o- tpJ

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y040 UO N/AU!

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

9. Do attached lines have adequate flexibility to avoid damage? YIr LJuO N/AD]

10. Based on the above seismic interaction evaluations, is equipment free YW90-UO of potentially adverse seismic interaction effects?

Other Adverse Conditlon.

11. Have you looked for and found no other seismic conditions that could Y04i0 Uo3 adversely affect the safety functions of the equipment?

Coments(Additional pages may be added as necessary)

Evaluated by: T. Ga/ahe W Date: 9-14-13 C/

J. Lucas 9-14-13 Peach Bottom Atomic Power Station Unit 3 AC-36 Correspondence No.: RS-14-001

Sheet 3 of 3 Status: Y0 NEI UE-Seismic Walkdown Checklist (SWC)

Equipment ID No. MO-3-23-015 Equip. Class' (08a) Motor Operated Valves Equipment Description HPCI Turbine Steam Line Inboard Isolation Valve Photographs Note: Label of valve Note: MO-3-23-015 valve Note: conduits/pipingarea observed above valve Note: Main Steam to HPCI Peach Bottom Atomic Power Station Unit 3 AC-37 Correspondence No.: RS-14-001

Status:e>3 Seismic Walkdown Cheolist (SWC)

Equipment ID No. M0.3.23019 Equip. Class' (08W)Motor Owrated Vaem IRmoirunpikt TUamir*inn HPCI D~d~IaM. ta F&aAdWA*r LhIM V~h,.

Location: Bldg. HRB Floor El. 135'0" Room, Area ReactorI#SI V RoomI (R3-30)

-ManufacturerModej Etc-.(optionaIuded) WALW OR-hitrkhictleu for Completi Ceckls This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anconee

1. Is the anchorage configuration verification required (i.e., is the item one Yo Nor' of the 50% of SWEL items requiring such verification)?

\ja\jf .

2. Is the anchorage free of bent, broken, missing or loose hardware? urnO N/AQ3

3. Is the anchorage free of corrosion that is more than mild surface UDON1 N/A13 oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YO NO UO N//AV

5. Is the anchorage configuration consistent with plant documentation? YD NO UO N/A1V' (Note: This question only applies if the item is one of the 50%for which an anchorage configuration verification is required.)

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

'Enter the equipment class name from Appendix B: Classes of Equipment Peach Bottom Atomic Power Station Unit 3 AC-38 Correspondence No.: RS-14-001

SheettuS of 3 Stats:jrN uO Seismic Walkdown Checklist (SWC)

Equipment ID No. MO-3-23-019 Equip. Class' (08a) Motor Ooerated Valves Equipment Description HPCI DischarQe to FeedwaterIine VMAve Interaction EffeNtA

7. Are soft targets free from impact by nearby equipment or structiuE ? -- YVU3-UEO-N/AE3

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Yf" J3 Un N/AO and masonry block walls not likely to collapse onto the equipment?

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

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

Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y /N*I" UO adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

Evaluated by: T. Gallaoher Date: 9-18-13 D'I J. Lucas 9-18-13 Peach Bottom Atomic Power Station Unit 3 AC-39 Correspondence No.: RS-14-001

Sheet 3 of 3 Status: YN N[-] UE--

Seismic Walkdown Checklist (SWC)

Equipment ID No. MO-3-23-019 Equip. Class1 (08a) Motor Operated Valves Equipment Description HPCI Dischargeto FeedwaterLine Valve Phoi Note: Valve MO-3-23-019 for outage support only. Note:

Peach Bottom Atomic Power Station Unit 3 AC-40 Correspondence No.: RS-14-001

Sheet I of 3 Status: O NE u[]

Seismic W-kdown Clsoidlet (SWC)

Equipment ID No. 3ST345 Equip. Cls'12U=1 ý =- -- =1 -1ý11=1II =I =7I- 1=1=7 -)I Equipment Description Location: Bldg. fR8 Floor E. 15r* Room, Area * *a MW*3.,Ml Manuatr, Model. Etc. (optional but recommended) SAITHAEON STEEL CO hutrsclla for Compleft Cbeckdi Y'L:~~~ ... h .*- L.LL.--- ' -a---

WER U- ,.- VU. -D~ - - .~.. MJW,

!ý vi uaw M, uuM4 VJIWII ",

ft

~vbw u

%au-.

SWEL The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

1. Is the anchorage configuration verification requked (i.e., is the item one YO N1V of the 50% of SWEL items requmig such verification)?

Jok frert"V-d J;C 4kA S3DO/oCfe4A"ývpwni4 hvd andi of e vias& veri~eo~t¶PyOn ~r

2. Is the anchorage free of bent, brokme missing or loose hardware? YtDNr uo mNAD

3. Is the anchorage free of corosion that is more than mild surface Yai4kiJ UO N/AE3 oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YD NO U[3 N/AM No WohrSi~ i cAcrde-t.

J

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

00n Ancý 9raoe 4km=Ades -,*u*oboGa Mc.hora,A4- 3230 is ccLtq sh. Z anoI - ug- & S6. I,

6. Based on the above anchorage evaluations, is the anchorage free of Ye"NO U1J potentially adverse seismic conditions?

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

Peach Bottom Atomic Power Station Unit 3 AC-41 Correspondence No.: RS-14-001

Sheet 2 of 3 Status: YO NO UO Sglnd Walkdown Chewldt (SWC)

Equipment ID No. 3WTS4 Equip. Class' (21) Tanks or HAeat Aort)

Equipmnt Descripion kmunnt W Acczumar

7. Are soft targets free from impact by nearby equipment or structues? YdNO UO N/AU3

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YV/lO UO N/AU3 and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? YMNOUD N/AU

10. Based on the above seismic interaction evaluations, is equipment free %413 UO of potentially adverse semuc iteraction effects?

Othw Adves Cumdift

11. Have you looked for and found no other seismic conditions that could Y"NU U3 adversely affect the safety functions of the equipment?

£inmNMin(Additiond pages may be added as necessary)

Evaluated by: ", Lucas ý,, C--eý Date:1013 3 Nft..>

10 LO-5115 Peach Bottom Atomic Power Station Unit 3 AC-42 Correspondence No.: RS-14-001

Sheet 3 of 3 Status: YN NEI UI Seismic Walkdown Checklist (SWC)

Equipment ID No. 3BT545 Equip. Class1 (21) Tanks or Heat Exchangers (Horizontal)

Equipment Description Instrument N2 Accumulator Photographs Note: Temporary yellow shielding for outage only. Note:

Note: Note:

Peach Bottom Atomic Power Station Unit 3 AC-43 Correspondence No.: RS-14-001

Sheet I of 3 Status: YO NO UO Ssmic Wufkdown CheiMdt (SWC)

Equipent ID No. WCTI45 Equip. ClMs (21) TMn HeW

• f Ex Wi8 MOIM )

Equipment Description kift&UnW9 A9 ArMrndat Location: Bldg. R8 Floor El. 155CE-o Room, Area Q1kW 3-J Manumfcture, Model Etc. (opioal bw recommended) S."TH-AOON STE CO Immwtiom for ,,-eth Checklst _

This checklist may be used to document the resul of the Seismic Walkdown of an item of eqipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

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

2. Is the anchorage free of bent, brolkn, missing or loose hardware? YNUD WUAD

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

4. Is the anchorage free of visible cracks in the concrete near the anchors? YOlN[3 UE] N/AKY N~o wx~hwS .IA c~bvcre.4e.

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

w~cY'rje "xO6&ES -Owp M--3230 £Sl.

Ol aol oAA -& (P t."k 0 4 'S -  :), b. Yt'N.' U

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

' Enter the equipmen clm -anefrom Appendix 8: Clases of Equ~ipenL Peach Bottom Atomic Power Station Unit 3 AC-44 Correspondence No.: RS-14-001

Sheet 2 of 3 Status: YO N[: U[Q Seismic Wdkdown Choctid (SWC)

Equipment ID No. MKM Equip. Cls121) Tasks or HAW fN.. (mHabw)

E.- ip.en Description buftzan AM Ace dwNLao

7. Are soft targets free from impact by nearby equipment or s*ructures? YMIVNO Urn NIAO

8. Are overhead equipment, distribution systems, ceiling files and lighting, YM104 UD N/AO and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damae? YgOUD NMAD t0. Based on the above seismic interaction evaluations, is equipment free Ygr*k'DUO of potentially adverse seismic interaction e&e?

OdMr !Iv4= CosdIM s

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

£in(in A  ;#anal pages may be added as nCcessaM)

Evaluated hue -*"C- I-ILr&A Date: /Q .3 Z&L Peach Bottom Atomic Power Station Unit 3 AC-45 Correspondence No.: RS-14-001

Sheet 3 of 3 Status: YO NEI U-Seismic Walkdown Checklist (SWC)

Equipment ID No. 3KT545 Equip. Class1 (21) Tanks or Heat Exchangers (Horizontal)

Equipment Description InstrumentN2 Accumulator Photographs Note: Note:

Note: Note:

Peach Bottom Atomic Power Station Unit 3 AC-46 Correspondence No.: RS-14-001

Table AC-2. Summary of Supplemental Internal Inspections Anchor Component ID Description Configuration AWC-Ux-YY Confirmed?

MO-3-23-015 30B324 Motor Control Power Transfer Switch MO-3-13-015 30B325 Motor Control N U3-15 Starter Panel Battery Charger 3CD003 3C N U13-09 Battery Charger 3DD003 3D N U3-01 Diesel Generator 0AC097 OAG12 Control N UO-02 Panel 120V Instru.

30S703 Panel 30Y035 N U3-14 Transfer Switch Peach Bottom Atomic Power Station Unit 3 AC-47 Correspondence No.: RS-14-001

Sheet I of 3 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 30B324 (SEE APPENDIX C PAGE C-13)

Equipment Class: (01) Motor Control Centers Equipment

Description:

MO-3-23-015 Motor Control Power Transfer Switch Project: Peach Bottom Unit 3 SWEL Location (Bldg, Elev, Room/Area): Turbine Bldg, 135'-0", Recirc. MG Set Rm Manufacturer/Model: Nutherm International Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchoraae

1. Is anchorage configuration verification required (i.e., is the item one of the 50%

of SWEL items requiring such verification)?

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

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?

5. Is the anchorage configuration consistent with plant documentation? (Note:

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

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

SEE SWC IN APPENDIX C FOR RESPONSES Interaction Effects

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

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

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

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

SEE SWC IN APPENDIX C FOR RESPONSES Peach Bottom Atomic Power Station Unit 3 AC-48 Correspondence No.: RS-14-001

Sheet 2 of 3 Status: [Y] N U Seiomic Walkdown Checkdlet (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment IDNo.: 308324 (SEE APPENDIX C PAGE C-13)

Equipment Class: (01) Motor Control Centers Equipment

Description:

MO-3-23-01 5 Motor Control Power Transfer Switch Ot~her Advene Codlln ISUPPLEMENrA, CABINET INSPECTION)

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

a. Inenal components securWd? (I.e. no owe or msink fasteners) 0NU af//0/0

b. Are aod n cabkwft secured Wog r? Y f tu All,

c. No other adverse iesmic condtions? [aN U Seismic Walcdown Team T. Gallagher and J. Lucas 09/16/13.

Operations opened the front panel to allow for the visual inspection of the internal anchorage. No missing mounting bolts and no adjacent cabinets. Photos were taken to document the secure configuration of the internal components.

Equipment has external anchorage.

Evaluated by: T. Gallagher Date: 09/16/13 J. Lucas 09/16/13 See Sheet 3.

Peach Bottom Atomic Power Station Unit 3 AC-49 Correspondence No.: RS-14-001

Sheet 3 of 3 Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 30B324 (SEE APPENDIX C PAGE C-13)

Equipment Class: (01) Motor Control Centers Equipment

Description:

MO-3-23-015 Motor Control Power Transfer Switch Photographs Note:

Peach Bottom Atomic Power Station Unit 3 AC-50 Correspondence No.: RS-14-001

Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 30B325 (SEE APPENDIX C PAGE C-16)

Equipment Class: (01) Motor Control Centers Equipment

Description:

MO-3-13-015 Motor Control Starter Panel Project: Peach Bottom Unit 3 SWEL Location (Bldg, Elev, Room/Area): Turbine Bldg, 135-0", Recirc. MG Set Rm Manufacturer/Model: Nutherm International Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50%

of SWEL items requiring such verification)?

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

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?

5. Is the anchorage configuration consistent with plant documentation? (Note:

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

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

SEE SWC IN APPENDIX C FOR RESPONSES Interaction Effects

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

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

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

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

SEE SWC IN APPENDIX C FOR RESPONSES Peach Bottom Atomic Power Station Unit 3 AC-51 Correspondence No.: RS-14-001

Sheet 2 of 3 Status: [Y- N U Selsmic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 30B325 (SEE APPENDIX C PAGE C-16)

Equipment Class: (01) Motor Control Centers Equipment

Description:

MOB 48 46 Motor Control Starter Panel MO-3-136- 01T -a6, 0//0v//*

Othe Adverse CMliUDM (SUPPLEMENTAL. CABINET IISPECTIONM

11. Have you looked for and found no adverse seismic conditions that could adversely affect the safety functions of the equpment? -IL6

& Intralcomonw secured?(I.e. no loose or missing fateners) SN U 0,116#4'

b. Are adacent cafWets secured togeer? Y' &u VIA

c. No other adverseseismic condi  ? jaN U comments Seismic Walkdown Team T. Gallagher and J. Lucas 09/16/13.

Operations opened the front panel to allow for the visual inspection of the intemal aichorage. No missing mounting bolts and no adjacent cabinets. Photos were taken to document the secure configuration of the internal components.

Equipment has exteral anchorage.

Evaluated by: T. Gallagher & Date: 09/16/13 J. Lucas 09/16/13 See Sheet 3.

Peach Bottom Atomic Power Station Unit 3 AC-52 Correspondence No.: RS-14-001

Sheet 3 of 3 Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 30B325 (SEE APPENDIX C PAGE C-16)

Equipment Class: (01) Motor Control Centers Equipment

Description:

MO-3-13-015 Motor Control Starter Panel Photographs Note: i ne note in me prare snown is an open stor Note: Cal for a component. No missing mounting bolts.

Peach Bottom Atomic Power Station Unit 3 AC-53 Correspondence No.: RS-14-001

,t C.

Sheet 1 of 6

. Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Status: [71 N U Equipment ID No.: 3CD003 (SEE APPENDIX C PAGE C-180)

Equipment Clue: (16) Battery Chargers and Inverters Equipment *.scrlon- STATlO-BA¶ERY1CHARGER-PANEL 3C Project Peach Bottom Unit 3 SWEL Location (Bldg, EBev, Room/Area): T3-170 - E-33 Emergency Auxilary Swftchgear Room, 136 ft Manufacturer/Model: Thomas & Bets Power Solutions / 130/200R3-S Immetnoc s for Completing Cheddli This cheddist may be used to document the results of the Seismic Walhdown of an item of equipent on the SWEL The spae below each of the fobwng questions may be used to record te results of jupents and rd'pngs. Additional space is provided at the end of ths chedcist for documenting other comments.

1. Is anchorage configuration verification required (i.e., Is the Item one of the 50%

of SWEL Items requiring such wIfication)?

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

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?

5. Is the anchorage configuration consistent with plant documentation? (Note:

This question only applies Ifthe Item is one of the 50% for which an anchorage configuration verification Isrequired.)

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

SEE SWC IN APPENDIX C FOR RESPONSES Inerato Effects

7. Are soft targets free from Imipact by nearby equipment or structures?

8. Are overhead equipment, distribution systems, cing ties and Uigting, and masonry block walf not likely to collap onto the equipment?

9. Do attached ine have adequate fexibft to avoid damage?

10. Based on the above seismic interaction evaluations, Is equipment free of potentially adverse seismic Interacti6n effects?

SEE SWC IN APPENDIX C FoR RESPONSEs Peach Bottom Atbmic Power Station Unit 3 ". AC-54 CorrespondenceNo.: RS " ...

Sheet 2 of 6 Status: [E N U Seilmnic Walkdown Checkist (SWC) SUPPLEMENTAL CABINET INSPECTION S Equipment ID No.: 3C0D03 (SEE APPENDIX C PAGE C-180)

Equipment Class: (16) BattOy Chargers and Irvertr ES;*d I,;,

AT IN -*1,TEr HAGR PAE*9D.---- -,

Mf Am Condilom MSPPLEMENTAL CABINET SISPECTIOM

11. Have you looked for and found no adveme seismic condcilons that could adversely affect th safety functions of the equiment?

a. Intenal co ponewis secured?(/e.no loose or mssing 06senem) Y N U

b. Are a4fla cab*neft secured kogemr? Y A U ca No otheradverse etsmlontdftm? N U Comments Reference AR AlS86270 for Inspction and Documentation of Result PERFORMED WALKDOWN 3/12/13, ON BACKSHIFT, DURING MAINTENANCE PERFORMANCE OF R1 189616 ACT 01. THE INTERNAL COMPONENTS WERE SECURED AND THERE ARE NO LOOSE OR MISSING FASTENERS. THERE ARE NO ADJACENT CABINETS, 300003 IS A STAND-ALONE CABINET.

THERE ARE NO OTHER ADVERSE SEISMIC CONDITIONS. MAINTENANCE OPENED FRONT DOOR, AND REMOVED REAR PANEL TO ALLOW FOR INSPECTION OF THE CABINET. PHOTOS WERE TAKEN TO DOCUMENT THE SECURE CONFIGURATION OF THE INPUT TRANSFORMER, METERS AND CONTROLS, ELECTRONICS BOARDS, DC FILTER INDUCTOR, AND DC FILTER CAPS.

Equipment has external anchorage Evaluated by: J. Lucas Date: 03/13/13 P. Kester 03/13/13 Peach Bottom Atomic Power Station Unit 3 AC-55 Correspondence No.: RS-14-001

.~l It Sheet 3 of 6 Status: M N U Seismic Walkdown Choct (SWC) SUPPLEMENTAL CABINET INSPECTION O

Equipment ID No.: 3C0003 (SEE APPENDIX C PAGE C-180)

RA Equipment Class: (18) Batley Chargers and Inveres

.......... ATFERY--SUAARGER

• - FA I4oSC Peach Bottom Atomic Power Station Unit 3 AC-56 Correspondence No.: RS-14-001

. 0 .

Sheet 4 of 6 Status: [M N U 0 Seismic Wdkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 3CD003 (SEE APPENDIX C PAGE C-180)

Equipmnt Class: (16) Battery Chargers and Inverters STlATKX8ATTER %dvMWiinOE PANEL. 30 Peach Bottom Atomic Power Station Unit 3 AC-57 Correspondence No.: RS-14-001

Sheet S of 6

[Y]

. Seismic Walkdown Checkdt (SWC) SUPPLEMENTAL CABINET ISPECTION Status: N U Equipment ID No.: 3C0003 (SEE APPENDIX C PAGE C-180)

Equomnant Class: (16) BattwyChargsm and lrwrtors

-AWMIo oK I wi EN IE~HAE PAE -W Peach Bottom Atomic Power Station Unit 3 AC-58 Correspondence No.: RS-14-001

Sheet 6 of 6 Status:[ N U Seismic Wdkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 3CD003 (SEE APPENDIX C PAGE C-180)

Equipment Class: (16) Battery Chargers and InverteW

-- EqumgD . on. TTIN A~eweHRERPA PANEL-Peach Bottom Atomic Power Station Unit 3 AC-59 Correspondence No.: RS-14-001

Sheet 1 of S Status: M N U Seismic Wulkdown Checklds (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 300003 (SEE APPENDIX C PAGE C-202)

Equipment Class: (16) Battery Chargersmand Inverters Equ -: - ATION-ATTERY-GHARGER-PANEL-36 Prject: Peach Bottom Unit 3 SWEL Location (Bldg, Elev, Room/Area): T3-172 = E-43 Emergency Auxiliary Swltchgear Room, 135 ft Manufturer/Model: Thomas & Betla Power Solutions / 130/200R3-S hfotkm fr Competing Checkist This checidist may be used to document the results of the Seismic Wakdown of an iten of equipment on the SWEL The space below each of fhe following questions may be used to record the results o Judgments and findings. Additional space Isprovided at te end of this checkld for documenting other comments.

1. Is anchorage configuration verification required (i.e., is the Item one of the 50%

of SWEL bims requiring such verification)?

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

3. Is the anchorage free of corrosion that is more than mid surface oxiddation?

4. Is the anchorage free of visible cracks In the concrete near the anchors?

5. Is the anchorage configuration consistent with plant documentation? (Note:

This question only applies I the bin Isone of ft 50% for which an anchorage configuration verification Is required.)

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

SEE SWC IN APPENDIX C FOR RESPONSES InteireUmi Effec~ts

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

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

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

10. Based on the above seismic interaction evaluations, is equipment free of potentialy adverse seismic Interaction effects?

SEE SWC IN APPENDIX C FOR RESPONSES Peach Bottom Atomic Power Station Unit 3 AC-60 Correspondence No.: RS-14-001

M Sheet 2 of 5 Status: M N U Seismic Walkdown Checklis (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 3DD003 (SEE APPENDIX C PAGE C-202)

Equipment Class: (16) Battery Chargers and Inverters

.E~i~hantD* :--ipt~nISTATlONBtATrERY*C*ARfr,.NEL-&-,* -.

OtherAdveseConditions(SUP-PLEMENTALCABIET INPECION

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

a. Intmal component secured? (I.e. no loose or mlsshng htee) Y N U

b. Are adjacecabhetssecured toger? A U ca Noo heradverseseismlcaonsdton? X N U Collnorft Reference AR A1892055 and W/O R1 196314 Act 06 for Inspection end Documentation of Results:

PERFORMED WALKDOWN 5101/13, DURING MAINTENANCE PERFORMANCE OF Ri 196314 ACT 01. THE INTERNAL COMPONENTS WERE SECURED AND THERE ARE NO LOOSE OR MISSING FASTENERS.

THERE ARE NO ADJACENT CABINETS, 3D0003 IS A STAND-ALONE CABINET. THERE ARE NO OTHER ADVERSE SEISMIC CONDITIONS. MAINTENANCE OPENED FRONT DOOR TO ALLOW FOR INSPECTION OF THE CABINET. PHOTOS WERE TAKEN TO DOCUMENT THE SECURE CONFIGURATION OF THE INTERNAL COMPONENTS.

Equipment has external anchorage Evaluated by: J. Lucas N,* ZZŽ Date: 05/01/13 P. Kester 4.06* /01113 Peach Bottom Atomic Power Station Unit 3 AC-61 Correspondence No.: RS-14-001

Sheet 3 of 5 Status: M N U Seismic Walkdown Checkldit (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 3DD003 (SEE APPENDIX C PAGE C-202)

Equipment Class: (16) Battery Chargers and Inverters

-Eaimet~sctasw-SATON~-HAGR PANEft A20- - --

Peach Bottom Atomic Power Station Unit 3 AC-62 Correspondence No.: RS-14-001

Sheet 4 of 5 Status: I N U Seismic Walkdown Checkflst (SWC) SUPPLEMENTAL CABINET INSPECTION Equiment ID No.: 300003 (SEE APPENDIX C PAGE C-202)

Equipment Class: (16) Battery Chargem and Inverters Equ--l SW_ -DetisOW: -STATlION BA1I WIE CHiARGER PANL 30 --

(is;.

Peach Bottom Atomic Power Station Unit 3 AC-63 Correspondence No.: RS-14-001

Sheet S of S Status: M N U Seismic Walkdown Cheldist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 3DD003 (SEE APPENDIX C PAGE C-202)

Equipment Class: (18) BatWry Chargers and Inverters Peach Bottom Atomic Power Station Unit 3 AC-64 Correspondence No.: RS-14-001

Sheet 1 of 3 Status: M N U Seismic Wulkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 0AC097 (SEE APPENDIX C PAGES C-347 (Unit 2) and C-310 (Unit 3)

Equipment Class: (20) Control Panels & Cabinets r,

Eaulment

Description:

STBY. DIESEL GEN. OAG12 CONTROL PANEL I Project: Peach Bottom Unit 2 & 3 SWEL Location (Bldg, Elev, Room/Area): Diesel Generator Bldg, 127'-0, D/G-3 (Bay E-1)

Manufacturer/Model: Fairbanks Morse Engine/Coit Ineatronm for Completin Checdlet This checdlist may be used to document the results of the Seismic Walkdown of an Item of equipment on the SWEL The space below each of the following questions may be used to record the results of Judgments and findings. Additional space is provided at the end of Oths chckst for documenting other comments.

1. Is anchorage configuration verification required (i.e., Is the item one of the 50%

of SWEL items requiring such verification)?

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

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?

S. Isthe anchorage configuration consistent with plant documentation? (Note:

This question only applies if the item is one of the 60% for which an anchorage confguration verification is required.)

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

SEE SWC IN APPENDIX C FOR RESPONSES Intwor* Efet

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

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

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

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

SEE SWC IN APPENDIX C FOR RESPNSE Peach Bottom Atomic Power Station Unit 3 AC-65 Correspondence No.: RS-14-001

Sheet 2 of 3 Status: M N U Seismic Walkdown Checldst (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 0AC097 (SEE APPENDIX C PAGES C-347 (Unit 2) and C-310 (Unit 3)

Equipment Class: (20) Control Panels & Cabinets Equipment

Description:

STBY. DIESEL GEN. OAG12 CONTROL PANEL Other Advers CQndWkM (SUPPLEMENTAL CABINET INSPECTION)

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

a. IntenW components se*wed? (Ie. no loose or missing fasteners) r N U

b. Are adfamn cabibets secured oge*w? N U

c. No other adwrseseismic conditions? N U Co'mnlent Seismic Walkown Tewm T. Gallagher and J. Lucas 09/16/13.

Operations opened the back panel to allow for the visual Inspection of fthieternl anchwo*;e. No degraded or mising anchorages were found. Photos were taken to document the secure configuration of the Interal components. Equipment has extermal anchorage.

Evaluated by. T. Gallagher

• 1/1 C0 Doae: 09/16/13 J. Lucas \%"" ' 09/16/13 See Sheet 3.

Peach Bottom Atomic Power Station Unit 3 AC-66 Correspondence No.: RS-14-001

Sheet 3 of 3 Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 0AC097 (SEE APPENDIX C PAGES C-347 (Unit 2) and C-310 (Unit 3)

Equipment Class: (20) Control Panels & Cabinets Equipment

Description:

STBY. DIESEL GEN. OAG12 CONTROL PANEL Note: Diesel GeneratorControl Panel 0AC097 Note: Mounting to adjacent cabinet Note: Internal mounting Note: Internal mounting Peach Bottom Atomic Power Station Unit 3 AC-67 Correspondence No.: RS-14-001

Sheet I of 3 Status: M N U Seismic Walkdown Checids (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 30S703 (SEE APPENDIX C PAGE C-89)

Equipment Class: (14) Distribution Panel Equipment

Description:

120V Instrument Panel 30Y035 Transfer SW 30S703 Project: Peach Bottom Unit 3 SWEL Location (Bldg, Elev, Room/Area): Reactor Bldg, 135'-0, R3-29 Manufacturer/Model: NUTHERM INTERNATIONAL hutruotlone -o- Comle*n Checklist This checklist may be used to document the results of the Seismic Walkdown of an Kemn of equipment on the SWEL The apace below each of the following questions may be used to record the results of judgments and findings. Additionl space is provkid at the end of this checdlist for documenitng other comments.

1. Is anchorage configuration verification required (Le., is the item one of the 50%

of SWEL Items requiring such verification)?

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

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

4. Is the anchorage free of visible cracks in the concrete neaw the anchors?

5. Isthe anchorege configuration consistent with plant  ? (NO:

This question only applies ifthe item is one of the 50% for which an anchorage configuration verification Isrquird.)

6. Baud on the above anchorage evaluations, is the anchorage free of potentally adverse seismic conditions?

SEE SWC IN APPENDIX C FOR RESPONSES

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

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

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

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

SEE SWC INAPPENDIX C FOR RESPONSES Peach Bottom Atomic Power Station Unit 3 AC-68 Correspondence No.: RS-14-001

Sheet 2 of 3 MOMtu:MN U Sokais Wdaiown Cheolldet (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 30S703 (SEE APPENDIX C PAGE C-ON)

Equoit Cms: (14) Dstbuto Panel Equipment Descripton: 120V Instrment Panel 30Y035 Transfer SW 308703

__rM, Adlmee Candilkn MPFL ML'u SU*Mqr

11. Have you boaked for and fouid no advere sim m onditions d that could TIC76 dverly eaect tohe as"y fntion e equpmnt?

a. brmml oomponst sewed? (#.A no ioo or mbuu fauner) foI/Iof'.

b. Are acqaWa ra' Iud1,suue erl Nl/f

c. No ohw advanf seitmn o ditms? Y*U Seimic Wdadmn Tewn T. Galgher and J. Lucas la &/13.

Operatis opined thefrntpaeloowforthe visul opeOn ft Intrnal anchoaoge. No mising mountm"g bob ad no adjacst cdmiw. Phtos w teke to document the scure cmnguation ol he hntal Compmoenrt Equipment has m e amhora.

Evaluaed by. T. G3.e ,r de: IWM3 see shedt &.

Peach Bottom Atomic Power Station Unit 3 AC-69 Correspondence No.: RS-14-001

Sheet 3 of 3 Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: 30S703 (SEE APPENDIX C PAGE C-89)

Equipment Class: (14) Distribution Panel Equipment

Description:

120V Instrument Panel 30Y035 Transfer SW 30S703 Photographs Note: Note: Inside of panel, nothing mounted on the inside of the door.

Note: I'vorc: k~ljlvw, c)W(uiu U' zip u1vz.

Peach Bottom Atomic Power Station Unit 3 AC-70 Correspondence No.: RS-14-001