ML13252A111

WCAP-17680-NP, Supplement 1, Rev. 0, Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2 - Supplemental Information.

ML13252A111
Person / Time
Site:	Palo Verde
Issue date:	08/31/2013
From:	Djordjevic W, Perez R Arizona Public Service Co, Westinghouse
To:	Office of Nuclear Reactor Regulation
References
WCAP-17680-NP, Supplement 1, Rev 0
Download: ML13252A111 (110)

Text

ENCLOSURE 1, APPENDICES A and B CONTAIN Security-Related Information - Withhold under 10 CFR 2.390 UPON SEPARATION THIS PAGE IS DECONTROLLED ENCLOSURE Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2 - Supplemental Information ENCLOSURE 1, APPENDICES A and B CONTAIN Security-Related Information -Withhold under 10 CFR 2.390 UPON SEPARATION THIS PAGE IS DECONTROLLED

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 UDon seDaration this pale is decontrolled Westinghouse Non-Proprietary Class 3 WCAP-17680-NP, Supplement 1 August 2013 Revision 0 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2 - Supplemental Information Westinghouse'

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled WESTINGHOUSE NON-PROPRIETARY CLASS 3 WCAP-17680-NP, Supplement 1 Revision 0 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2 - Supplemental Information Rolando Perez

• Risk Applications & Methods II Walter Djordjevic Seismic Walkdown Peer Review Team Leader August 2013 Reviewer: Derek Seaman*

Risk Applications & Methods II Reviewer: Chris Wandell Senior Consulting Engineer, Arizona Public Service Approved: Dan Sadlon*

Manager, Risk Applications & Methods II

• Electronically approved records are authenticated in the electronic document management system.

Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066, USA

© 2013 Westinghouse Electric Company LLC All Rights Reserved

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled REVISION LOG Rev Date Revision Description Rev. 0 08/2013 Supplement 1 includes the main body of WCAP-17680-NP, Rev. 0 (Reference 48, "Executive Summary" through "References") and new or revised content in the appendices that address the conduct and results of the follow-on walkdown activities performed during and following refueling outage 2R17. Revision bars are used in the main body to easily identify the updates. With the exception of Appendices A and B, revision bars are utilized in the appendices to identify the updates relative to the corresponding appendices of WCAP-17680-NP, Rev. 0. Note that Appendices A and B consist of the completed checklists resulting from the follow-on walkdowns only. Editorial and formatting corrections relative to WCAP- 17680-NP, Rev.

0 are not identified with individual revision bars in this document.

WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Executive Summary Following the March 2011 accident at the Fukushima Dai-ichi nuclear plant, the Nuclear Regulatory Commission (NRC or Commission) established the Near Term Task Force (NTTF) in response to Commission direction. The NTTF made several recommendations, some of which are related to improving the protection of nuclear power plants against natural phenomena. With recommendation 2.3 (Rec 2.3), the NTTF recommended the NRC require licensees to perform Seismic and Flooding Walkdowns to identify and address vulnerabilities and verify the adequacy of hazard protection features.

On March 12, 2012, the NRC issued a letter, pursuant to 10 CFR 50.54(f), that requests information from all power reactor licensees related to NTTF recommendations 2.1, 2.3 and 9.3. For the seismic aspect of Rec 2.3, licensees are required to perform Seismic Walkdowns to verify the current plant configuration with the current seismic licensing basis, verify the adequacy of current strategies and maintenance plans, and identify and address degraded, non-conforming, or unanalyzed conditions. This report contains the Arizona Public Service Company (APS) response for Palo Verde Nuclear Generating Station (PVNGS)

Unit 2 to the request for information related to the seismic aspects of NTTF Rec 2.3, as addressed in enclosure 3 of the NRC letter.

The original version of this WCAP report summarizes the results from the at-power Seismic Walkdowns and Area Walk-Bys performed from July 23 through July 30, 2012. Supplement I incorporates the results from the additional walkdowns performed during and after refueling outage 2R17, from October 13 through October 15, 2012, and on December 5, 2012.

To establish a consistent methodology for performance of the Seismic Walkdowns, the Electric Power Research Institute (EPRI), in conjunction with the industry, developed guidance in EPRI Technical Report TR-1025286. This guidance was endorsed by the NRC on May 31, 2012. The Seismic Walkdowns conducted at PVNGS Unit 2 conform to the requirements of the EPRI Technical Report.

Consistent with the guidance, the following topics are addressed in this PVNGS Unit 2 Seismic Walkdown report:

1. Seismic Licensing Basis for Seismic Category I Systems, Structures and Components (SSCs)

2. Personnel Qualifications

3. Process used for selection of SSCs

4. Seismic Walkdowns and Area Walk-Bys

5. Licensing Basis Evaluations

6. Peer Review

7. IPEEE Vulnerabilities Resolution Report The required Seismic Walkdowns and Area Walk-Bys were performed for accessible equipment in PVNGS Unit 2 during the period from July 23 through July 30, 2012, while the plant was operating in Mode 1. Containment Building equipment and energized high-voltage equipment inspections were conducted October 13 through October 15, 2012, during the 2R17 refueling outage. Palo Verde also performed supplemental inspections of some electrical cabinets in accordance with the NRC response to industry frequently asked question 4.20. Inspection of remaining electrical cabinets, as identified in the PVNGS Unit 2 Seismic Walkdown Report, were conducted on December 5, 2012. Documentation of I these additional inspections and the related evaluations is provided in this supplemental report.

The following information identifies the requests in the 50.54(f) letter (in italics) followed by a summary of the APS response:

a. InJbrination on the plant-specific hazard licensing bases and a description of the protection andmitigationfeatures consideredin the licensing basis evaluation.

WCAP- 17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled 11 The PVNGS current Seismic Licensing Basis (seismic codes, standards, and methods) is documented in report Section 1 and was used to inform the Seismic Walkdown licensing basis evaluations.

b. Information relatedto the implementation of the walkdown process.

The approach used to implement the Seismic Walkdown process at PVNGS conforms to the guidance of EPRI Technical Report TR-1025286. Report Sections 3 through 5 provide detailed descriptions of how the walkdown process was implemented at PVNGS.

c. A list of plant-specific vulnerabilities (including any seismic anomalies, outliers, or other findings) identified by the IPEEE and a description of the actions taken to eliminate or reduce them (including their completion dates).

No plant-specific seismic vulnerabilities were identified at PVNGS Unit 2 by the Individual Plant Examination of External Events (IPEEE) program. The results of the IPEEE program are described in report Section 7.

d. Results of the walkdown including key findings and identified degraded, nonconforming, or unanalyzed conditions. Include a detailed description of the actions taken or planned to address these conditions using the guidance in Regulator, Issues Summar' 2005-20, Revision, 1, Revision to NRC Inspection ManualPart 9900 Technical Guidance, "Operabiliti, Conditions Adverse to Quality or Safeo,," including entering the condition in the corrective actionprogram.

The summary of the key findings of the Seismic Walkdowns and Area Walk-Bys is provided in report Section 4. The licensing basis evaluations of potentially adverse seismic conditions and their resolutions are described in detail in Section 5 and Appendix D of this report. A total of 22 licensing basis evaluations have been satisfactorily closed and ten open evaluations have been entered into the PVNGS Corrective Action Program (CAP) for resolution. Items entered into the CAP are annotated in Appendix D. None of these identified conditions prevent the equipment from performing the intended safety functions during or after a design basis seismic event. Results of the Seismic Walkdowns and Area Walk-Bys are documented on EPRI TR-1025286 checklists in report Appendices A and B, respectively.

e. Any planned or newly installedprotection and mitigationfeatures.

There are no planned or newly installed protection or mitigation features that resulted from the implementation of the Seismic Walkdown guidance at PVNGS. However, one potentially adverse seismic condition that was identified during the Seismic Walkdowns resulted in action being taken to restore seismic design margin. Bookcases installed near the control boards in the Unit 2 Control Room were removed. The condition related to this change would not have prevented safety-related equipment from performing its intended safety function during or after a design basis seismic event, the change was implemented to restore seismic design margin.

f Results andany subsequent actions taken in response to the peer review.

The peer review process performed at PVNGS confirmed and informed the selection of SSCs process, provided real-time feedback to the Seismic Walkdown engineers (SWEs) during performance of the walkdowns, and confirmed that the licensing basis evaluations carefully WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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In summary, PVNGS Unit 2 equipment that was inspected and evaluated for the Seismic Walkdown process, including initial and supplemental inspections and related licensing basis evaluations, was determined to be capable of performing intended safety functions during and after a design basis seismic event. The site monitoring and maintenance procedures were determined to be adequate. Follow-on activities to complete the remaining aspects of this process were completed as described in this supplemental report. Therefore, the required NTTF 2.3 walkdown activities have been successfully completed for PVNGS Unit 2 in accordance with the EPRI Guidance document and the intent of to the NRC 50.54(f) letter has been satisfied.

WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled iv ACKNOWLEDGEMENTS We wish to acknowledge the following contributors to the effort.

Mike Powell - Arizona Public Service (Director Fukushima Response)

Chris Wandell - Arizona Public Service Justin Wood - Arizona Public Service Winston Borrero - Arizona Public Service Randall "Gene" Eimar - Arizona Public Service Jonathon Lucero - Arizona Public Service Nick Reidenbach - Arizona Public Service Derek Morris - Arizona Public Service Mark Meyer - Arizona Public Service Nathan Hardwick - Arizona Public Service Jose "Angel" Delgadillo - Arizona Public Service Michael Cribbins - Westinghouse Electric Company Rolando Perez - Westinghouse Electric Company Derek Seaman - Westinghouse Electric Company Gary Douglas - Westinghouse Electric Company Joe Somsel - Westinghouse Electric Company Paul Karavoussianis - Stevenson & Associates Walter Djordjevic - Stevenson & Associates Cory Figliolini - Stevenson & Associates Hunter Young - Stevenson & Associates Andrew Masiunas - Stevenson & Associates WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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LIST OF ACRONYMS AND ABBREVIATIONS Acronym Definition AFAS Auxiliary Feedwater Actuation Signal AF Auxiliary Feedwater AFW Auxiliary Feedwater System AHU Air Handling Unit APS Arizona Public Service ASME American Society of Mechanical Engineers AUX Auxiliary Building AWC Area Walk-By Checklist CAP Corrective Action Program CE Combustion Engineering CF Containment Function CH Chemical and Volume Control CLB Current Licensing Basis CP Containment Purge CST Condensate Storage Tank CT Condensate Transfer and Storage CTMT Containment CTRL Control Building CVCS Chemical and Volume Control System DBM Design Basis Manual DCM Design Criteria Manual DF Diesel Fuel Oil and Transfer DG Diesel Generator DHR Decay Heat Removal EAHU Essential Air Handling Unit EC HVAC Essential Chilled Water EPRI Electric Power Research Institute EQCF Equipment Qualification Control Form EQID Equipment Identification EW Essential Cooling Water FAQ Frequently Asked Question(s)

FCR Field Change Request GA Service Gas GR Gaseous Radwaste HA HVAC Auxiliary Building HC HVAC Containment Building HD HVAC Diesel Generator Building HJ HVAC Control Building HPSI High Pressure Safety Injection HVAC Heating, Ventilation and Air Conditioning WCAP- 17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled vi Acronym Definition IA Instrument and Service Air IC Reactor Coolant Inventory Control IPEEE Individual Plant Examination of External Events IEEE Institute of Electrical and Electronics Engineers ISRS In-Structure Response Spectra MCC Motor Control Center MOV Motor-Operated Valve MSSS Main Steam Support Structure NCR Non-Conformance Reports NQR Non-Quality Related NRC Nuclear Regulatory Commission NSSS Nuclear Steam Supply System NTTF Near-Term Task Force OBE Operating Basis Earthquake P&ID Piping and Instrumentation Diagram PB Class IE 4.16 kv Power PC Reactor Coolant Pressure Control PE Class IE Standby Generation PG Class IE 480v Power Switchgear PGD Project General Design Criteria PH Class 1E 480v Power Motor Control Center PK Class 1E 125 VDC PN Class 1E Instrument Power PRA Probabilistic Risk Assessment PSA Probabilistic Safety Assessment PVAR Palo Verde Action Request (Corrective Action Program)

PVNGS Palo Verde Nuclear Generating Station RAS Re-circulation Actuation Signal RAW Risk Achievement Worth RC Reactivity Control or Reactor Coolant RCPB Reactor Coolant Pressure Boundary RCS Reactor Coolant System RD Radioactive Waste Drain RLE Review Level Earthquake RM Main Control Board ROB Rule of the Box RWT Refueling Water Tank S&A Stevenson & Associates SA Engineered Safety Features Actuation System SB Reactor Protection SC-1 Seismic Category I SDC Shutdown Cooling WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled vii Acronym Definition SDOC Vendor/Supplier Document SFP Spent Fuel Pool SG Main Steam SI Safety Injection SoV Solenoid-Operated Valve SP Essential Spray Ponds SPRA Seismic Probabilistic Risk Assessment SQUG Seismic Qualification Utility Group SSCs Structures, Systems, and Components SSE Safe Shutdown Earthquake SSEL Safe Shutdown Equipment List SWC Seismic Walkdown Checklist SWE Seismic Walkdown Engineer SWEL Seismic Walkdown Equipment List SWG Seismic Walkdown Guidance (EPRI TR-1025286)

SWMS Site Work Management System SWT Seismic Walkdown Team UFSAR Updated Final Safety Analysis Report UHS Ultimate Heat Sink ZA Auxiliary Building ZG Diesel Generator Building zJ Control Building WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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1. SEISM IC LICENSING BASIS ........................................................................................................... 1-1 1.1 IN-STRUCTURE RESPONSE SPECTRA ............................................................................... 1-1 1.2 SEISMIC QUALIFICATION OF SC-I EQUIPM ENT ............................................................. 1-1

2. PERSONNEL QUALIFICATIONS ................................................................................................ 2-I 2.1 EQUIPM ENT SELECTION PERSONNEL ............................................................................. 2-1 2.2 SEISMIC W ALKDOW N ENGINEERS ................................................................................... 2-1 2.3 LICENSING BASIS REVIEW ERS .......................................................................................... 2-3 2.4 IPEEE REVIEW ERS ................................................................................................................ 2-3 2.5 PEER REVIEW TEAM ............................................................................................................. 2-3

3. SELECTION OF STRUCTURES, SYSTEMS, AND COMPONENTS ............................................ 3-1 3.1 SELECTION PROCESS SUMM ARY ...................................................................................... 3-1 3.2 SAMPLE OF REQUIRED ITEMS FOR THE FIVE SAFETY FUNCTIONS ......................... 3-4 3.2.1 Base List I .......................................................................................................... 3-10 3.2.2 SWEL 1 ...................................................................................................................... 3-10 3.3 SPENT FUEL POOL (SFP) RELATED ITEM S ..................................................................... 3-11 3 .3 .1 B ase L ist 2 .................................................................................................................. 3 -12 3.3.2 Rapid Drain-Down ..................................................................................................... 3-13 3.3.3 SW EL 2 ... ..... ................................................. ............................................. 3-13 3.4 INACCESSIBLE ITEM S ........................................................................................................ 3-14

4. SEISM IC W ALKDOW NS AND AREA WALK-BYS ........................................................................ 4-1

4.1 BACKGROUND

....................................................................................................................... 4-1 4.2 PREPARATION FOR SEISM IC WALKDOW NS .................................................................... 4-2 4.3 WALKDOW N RESULTS ......................................................................................................... 4-3

5. LICENSING BASIS EVALUATIONS ............................................................................................... 5-1

6. PEER RE VIEW ................................................................................................................................... 6-1

6.1 INTRODUCTION

..................................................................................................................... 6-1 6.2 PEER REVIEW - SELECTION OF SSCs ................................................................................ 6-2 6 .2 .1 Purp ose ......................................................................................................................... 6 -2 6.2.2 Peer Review Activity - Selection of SSCs ................................................................... 6-2 6.2.3 Peer Review Findings - Selection of SSCs .................................................................. 6-3 6.2.4 Resolution of Peer Review Comm ents - Selection of SSCs ........................................ 6-5 6.2.5 Conclusion of Peer Review - Selection of SSCs .......................................................... 6-5 6.3 PEER REVIEW OF SAMPLE SEISMIC WALKDOWN AND AREA WALK-BY CHECKLISTS ........................................................................................................................... 6-5 6.4 REVIEW OF LICENSING BASIS EVALUATIONS .......................................................... 6-8 6.5 REVIEW SUBMITTAL REPORT ............................................................................................ 6-9

7. IPEEE VULNERABILITIES .............................................................................................................. 7-1

8. RE FERE NCES .................................................................................................................................... 8-1 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled ix APPENDIX A - SEISMIC WALKDOWN CHECKLISTS (SWCs) ................................................ A-1 APPENDIX B - AREA WALK-BY CHECKLISTS (AWCs) ............................................................ B-1 APPENDIX C - PEER REVIEW CHECKLISTS .............................................................................. C-1 APPENDIX D - LICENSING BASIS EVALUATIONS

SUMMARY

.............................................. D-1 APPENDIX E - Q U A LIFIC ATIO N S ................................................................................................ E-1 APPENDIX F - PVNGS UNIT 2 SWEL REPORT ............................................................................ F-1 APPENDIX G - SWEL DEVELOPMENT TABLES ....................................................................... G- 1 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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LIST OF TABLES Table 3-1: Sort of the Base List 1 Data and Selected SWEL Items Based on "System Type' .....................3-7 Table 3-2: Equipment Selected for SWEL Based on the "Major New or Replacement Equipment" Attribute ....... 3-8 Table 3-3: Sort of the Base List 1 Data and Selected SWEL Items Based on "Equipment Type Number" ............ 3-9 Table 3-4: Sort of the Base List I Data and Selected SWEL Items Based on "Environment (Temperature)". ...... 3-10 Table 3-5: PVNGS-2 Equipment Inaccessible During the Scheduled At-Power Walkdowns ............................... 3-14 Table 3-6: PVNGS-2 FAQ 4.20 Supplemental Cabinet Inspections ...................................................................... 3-15 Table 3-7: PVNGS-2 Equipment Inspected During Refueling Outage 2R17 ......................................................... 3-16 Table 3-8: PVNGS-2 Items Completed During the December 5, 2012 Inspection ................................................ 3-17 Table 6-I: SWC and AWC Peer Review Samples from Seismic Walkdown Inspection for Unit 2 .......................... 6-6 Table 6-2 Table of CAP Status from Seismic Walkdown Inspection ....................................................................... 6-9 T able G -l: PVN G S-2 Base L ist 1............................................................................................................................ G -I Table G -2: PVN G S-2 SW EL 1................................................................................................................................ G -2 Table G-3: PVNGS-2 Base List 2 (SWEL 2 is the same as Base List 2) .............................................................. G-15 Revision 0 WCAP-17680-NP, Supplement 1 WCAP- 17680-NP, Supplement A Revision 0 PVNGS-2 August 2013

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1. SEISMIC LICENSING BASIS This report is applicable to Palo Verde Nuclear Generating Station (PVNGS) Unit 2.

The licensing basis for Seismic Category I (SC-1) equipment at PVNGS Units 1, 2, and 3 is defined in the Updated Final Safety Analysis Report (UFSAR, Reference 32) Section 3.7 and is supported by summary seismic design criteria defined in Design Criteria Manual - Project General Design Criteria (DCM-PGD, Reference 42) Section 1.3.2. Site design ground motion response spectra for the Safe Shutdown Earthquake (SSE) are provided in UFSAR Figures 3.7-1 and 3.7-2, as well as UFSAR Sections 3.9.2.2, 3.9.3 and 3.10, and adhere to Regulatory Guide 1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants (Reference 43). Damping values for SC-1 equipment are listed in UFSAR Table 3.7-1 and conform to Regulatory Guide 1.61, Damping Values for Seismic Design of Nuclear Power Plants (Reference 44).

As defined in UFSAR Section 2.5, the SSE is based on the postulated occurrence of a magnitude 8.0 earthquake located 72 miles from the site. Through use of attenuation curves, extrapolation of response spectra, and analysis of intensity data, 0.2g is considered a conservative representation of the severity of horizontal and vertical vibratory ground motion for the SSE. For additional conservatism, the seismic analysis of all Category I structures was performed utilizing a 0.25g SSE. Figures 3.7-1 through 3.7-4 of the UFSAR show the horizontal and vertical design response spectra corresponding to the SSE and Operating Basis Earthquake (OBE), respectively.

1.1 In-Structure Response Spectra A time-history analysis was used to develop in-structure response spectra (ISRS) for buildings housing SC-1 equipment. Modeling techniques such as the selection of the minimum number of mass points, number of dynamic degrees of freedom per mass point, and torsional effects, are described in Bechtel Topical Report BC-TOP-4-A (Reference 51). The seismic input was defined in terms of the free-field acceleration time history and the soil-structure interaction parameters. The structural damping values used were per Regulatory Guide 1.61 (Reference 44). Soil damping characteristics were modified to account for strain levels. Design basis ISRS are plotted in DBM-C5 (Reference 53) Appendix A.

1.2 Seismic Qualification of SC-I Equipment SC-1 equipment is classified according to Regulatory Guide 1.29, Seismic Design Classification (Reference 45), and is discussed in UFSAR, Section 3.2 (Reference 32) and in DCM-PGD Section 1.4.3 (Reference 42), which states:

Category, I structures, systems. and components are those that are important to safet, and designed to remainfunctional in the event of a sqfe shutdown earthquake(SSE). These structures, systems, and components are those necessary to assure:

• The integrii, of the reactor coolantpressuarebondalry (RCPB).

• The capability to shutdown the reactorand maintain it in a sqfe condition.

• The capabilit, to prevent or mitigate the consequences of accidents that could result in potential offsite exposures.

Per UFSAR Section 3.10.2, SC-1 electrical equipment within the Bechtel scope of supply was qualified per Institute of Electrical and Electronics Engineers (IEEE) Std 344-75 (Reference 46). This standard is comprehensive and similar to current requirements for nuclear safety-related components. Per UFSAR WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 1-2 Section 3.10.5, SC-I electrical equipment within the Combustion Engineering scope of supply was qualified per IEEE Std 344-71 (Reference 41) plus the additional requirements listed. With the additional requirements, the qualification criteria and methods are similar to those of IEEE Std 344-75 (Reference 46). For qualification by testing, per application of the preceding criteria, much of the electrical equipment was subject to shake table testing. The required test levels were typically based on the in-structure response spectra discussed above.

Per Section 3.9.2.2 of the UFSAR, analytical methods without testing were employed to qualify Seismic Category I mechanical equipment such as piping, ductwork, tanks and vessels, heat exchangers, filters, and pumps. Qualification for mechanical components with mechanisms that must change position in order to perform the safety-related function was performed by test or a combination of test and analysis as per the IEEE Std 344-1975 requirements and UFSAR Sections 3.9.2, 3.9.3 and 3.10. These components include American Society of Mechanical Engineers (ASME) and non ASME items such as valves with actuators and their appurtenances as well as check valves, relief valves, fans, chillers, air handling units, and various skid-supplied devices.

WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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2. PERSONNEL QUALIFICATIONS 2.1 Equipment Selection Personnel The Seismic Walkdown Equipment List (SWEL) development was performed by Westinghouse personnel, Messrs. Rolando Perez and Derek Seaman. Resumes are provided in Appendix E. PVNGS Operations (Gene Eimar, Shift Manager and Angel Delgadillo, Senior Auxiliary Operator) provided verification of safety function selections. PVNGS Engineering (Chris Wandell, Winston Borrero) provided technical input to screening and selection of equipment. PVNGS System Engineering input was provided by performing a review of System Health Reports.

Rolando Perez - Mr. Perez is the Technical Leader for the Palo Verde Unit 2 SWEL development activity in the Risk Applications and Methods Group of Westinghouse's Engineering, Equipment and Major Projects Division. Rolando has over 15 years of experience in Westinghouse and over 35 years of experience in the nuclear safety area. Rolando has worked for Westinghouse and Combustion Engineering (CE) as a Training Engineer, Transient Analyst, and Setpoint Analyst. Rolando has conducted lectures on reactor core physics, health physics, fluid systems, protection systems, and plant operational concepts. In 2009 Rolando expanded his expertise to include CE-designed plants that employ digital-based reactor trip and monitoring systems ("CE digital plants").

Derek Seaman - Mr. Seaman is a member of the Palo Verde Unit 2 SWEL development team in the Risk Applications and Methods Group of Westinghouse's Engineering, Equipment and Major Projects Division. Derek has over 6 years of experience in Westinghouse in the nuclear engineering area. Derek has rotated through various plant outage positions including reload engineering analyses and project management of fuel reload campaigns. Derek has evaluated power increase proposals from a safety analysis perspective and has designed and implemented quality assurance systems in the nuclear engineering area.

Chris J. Wandell, P.E. - Mr. Wandell is a Senior Consulting Civil Engineer in the Palo Verde Nuclear Design Engineering Department. Chris is a Professional Civil Engineer with over 30 years of experience in the design, analysis, and modification of Seismic Category I pipe supports, electrical raceway supports, heating, ventilation and air conditioning (HVAC) supports, instrument supports, and steel and concrete structures. His experience also includes Class 1E Seismic Equipment Qualification. Mr. Wandell is Palo Verde's structural and seismic subject matter expert. He has attended EPRI's NTTF 2.3 Seismic Walkdown Training Course and is a certified Seismic Walkdown Engineer.

Winston G. Borrero - Mr. Borrero is a Senior Consulting Mechanical Engineer in the Palo Verde Nuclear Design Engineering Department. Winston has over 30 years of experience in the design and construction of Nuclear Plants having worked for Bechtel, Stone & Webster and Sargent & Lundy Engineers at various nuclear sites. Areas of expertise include stress analysis, fracture mechanics and fatigue analysis, seismic and environmental qualification of equipment, and bolted joint analysis. Mr. Borrero is Palo Verde's bolted joint and fatigue stress analysis subject matter expert. He has attended EPRI's NTTF 2.3 Seismic Walkdown Training Course and is a certified Seismic Walkdown Engineer.

2.2 Seismic Walkdown Engineers The Seismic Walkdown team (SWT) consisted of Seismic Walkdown engineers (SWEs) from Stevenson and Associates (S&A). S&A is recognized as a leading seismic consultant to the nuclear industry and as a WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 2-2 regular contributor to the advancement of earthquake engineering knowledge through funded research projects. The professional staff has expertise and capabilities in earthquake engineering, structural dynamics, and structural design. S&A has performed seismic evaluations of US nuclear power plants, using either Seismic Probabilistic Risk Assessments (PRA) or Seismic Margin Assessments, to address US Nuclear Regulatory Commission (NRC) Individual Plant Evaluation for External Events (IPEEE) for over 35 US and European plants. S&A conducted seismic PRA analyses for all of the US Army depots that are demilitarizing their stores of nerve gas ordnance.

The SWT for PVNGS Unit 2, consisting of Hunter Young and Cory Figliolini of S&A, conducted initial walkdowns from July 23, 2012, through July 27, 2012, and supplemental walkdowns on December 5, 2012. For supplemental watkdowns occurring October 13, 2012, and October 14, 2012, during refueling outage 2R17, the SWT consisted of Hunter Young and Timothy Nealon of S&A (Resumes are provided in Appendix E). Chris Wandell and Winston Borrero led the support from PVNGS for walkdowns as well as the interface with plant operators. Other PVNGS professional staff provided support and guidance and these persons are acknowledged within this report. The Stevenson & Associates Seismic Walkdown Engineers were accompanied by at least one of the following PVNGS qualified Seismic Walkdown Engineers: Chris Wandell, Nicholas Reidenbach, Winston Borrero, Justin Wood, Derek Morris, and Mark Meyer. The PVNGS engineers (along with the Auxiliary Operator team member) provided walkdown oversight relative to expected conduct in the plant (Nuclear, Radiological and Industrial Safety),

compliance with NRC-Approved EPRI Seismic Walkdown Guidance (TR-1025286), PVNGS procedural compliance (inclusive of CAP), and insight into Licensing Basis issues.

Hunter Young, P.E. - Mr. Young is a Senior Engineer in the S&A Phoenix office with specialization in the dynamic analysis and design of structures and equipment for seismic, blast, fluid, and wind loads. He has managed and led Seismic Walkdowns and fragility analyses of structures and components for use in probabilistic risk assessments. Mr. Young has performed the seismic analyses of braced steel frames, concrete foundations, masonry walls, large storage tanks, and electrical and mechanical equipment anchorages. In addition, Mr. Young has executed the walkdown and analysis of tank structures and their associated leak path piping to assess loss of inventory in the event of beyond-design-basis seismic events using manual and finite element methods. Mr. Young has a Master of Engineering in Structural Engineering from the Massachusetts Institute of Technology and Bachelors of Science in Civil Engineering from the University of Notre Dame. He is a licensed P.E. (civil) in California and has completed the 5-day Seismic Qualification Utility Group (SQUG) Walkdown training course.

Cory Figliolini - Mr. Figliolini is a Staff Engineer in the S&A Phoenix office. He has planned and performed Seismic Walkdowns and fragility analyses of structures and components for use in probabilistic risk assessments. Mr. Figliolini has conducted seismic analyses of electrical and mechanical equipment anchorage, storage tanks, and civil structures including containment. Mr. Figliolini has a Joint Master of Science, Structural Engineering & Mechanics from the Universities of Glasgow and Edinburgh and a Bachelors of Science in Civil Engineering from Worcester Polytechnic Institute. He is registered as an E.I.T. in Massachusetts. Mr. Figliolini has completed the 5-day SQUG Walkdown training course.

Timothy Nealon - Mr. Nealon is a Senior Engineer in the S&A Phoenix office with specialization in the dynamic analysis and design of structures and equipment for seismic, blast, fluid, and wind loads. He has participated in Seismic Walkdowns and fragility analyses of structures and components for use in probabilistic risk assessments. In addition, Mr. Nealon has conducted walkdowns and analysis of tank structures and their associated leakpath piping to assess loss of inventory in the event of beyond-design-basis seismic events using various methods. Furthermore, he has been trained and has conducted NTTF 2.3 Fukushima response Seismic Walkdowns at multiple nuclear stations. Mr. Nealon has a Master of WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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2.3 Licensing Basis Reviewers The Licensing Basis Reviewers for PVNGS Unit 2 consisted of Mr. Hunter Young, Mr. Cory Figliolini, and Mr. Timothy Nealon from the SWT. Their qualifications are provided under Section 2.2. Chris Wandell and Winston Borrero participated in the development of the licensing basis evaluations and provided technical bases for Operability Determinations/Functional Assessments for potentially adverse seismic conditions which were entered into the Corrective Action Program.

2.4 IPEEE Reviewers The IPEEE Reviewers consisted of a combination of the Equipment Selection Personnel and the SWT.

Mr. Rolando Perez and Mr. Derek Seaman of Westinghouse Electric Company LLC (qualifications listed in Appendix E) identified equipment subject to IPEEE enhancements for incorporation in SWEL 1. Mr.

Hunter Young and Mr. Cory Figliolini of S&A (qualifications listed in Section 2.2) performed the identification of actions taken to eliminate or reduce the IPEEE vulnerabilities previously identified.

Jonathan Lucero, Engineer Sr. PRA from PVNGS, contributed to the IPEEE review.

Jonathan L. Lucero - Mr. Lucero is a Senior Engineer in the Palo Verde Probabilistic Risk Assessment Department. Jonathan has over 10 years of engineering experience in foundation design, structural dynamics, and uncertainty analysis. His experience also includes multidisciplinary applications, generalized information theory, and fuzzy logic. Mr. Lucero is Palo Verde's seismic PRA subject matter expert. He has attended EPRI's Education of Risk Professionals Program and Seismic PRA training course.

2.5 Peer Review Team The peer reviewers for PVNGS Unit 2 are Messrs. Walter Djordjevic of S&A and Gary L Douglas of Westinghouse. Mr. Djordjevic is also designated the peer review Team Leader. Neither was involved in the Seismic Walkdown inspection process as to maintain their independence from the project. Mr.

Djordjevic is an advanced-degree structural engineer with over 30 years of nuclear seismic experience and has been trained as a Seismic Capability Engineer (EPRI SQUG training), EPRI IPEEE Add-on, and Seismic Fragility and Seismic Walkdown Engineer (SWE). Mr. Douglas is a nuclear engineer with 15 years of nuclear engineering experience and 10 years of aerospace engineering experience. Resumes are provided in Appendix E. Mr. Djordjevic led the seismic peer review activities and Mr. Douglas led the SWEL selection peer review. All peer review activities were performed by both engineers.

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3. SELECTION OF STRUCTURES, SYSTEMS, AND COMPONENTS 3.1 Selection Process Summary This section describes the process used by Westinghouse to select the structures, systems, and components (SSCs) that were included in the Palo Verde Nuclear Generating Station Unit 2 (PVNGS-2)

Seismic Walkdown Equipment List (SWEL). The process described in Section 3 (Selection of SSCs) of EPRI Technical Report 1025286, Seismic Walkdown Guidancefor Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012 (Reference 1), was used as guidance to develop the PVNGS-2 SWEL. The following steps from the integrated project schedule outline this process of SWEL selection:

Project Kickoff Meeting Obtain customer inputs Retrieve original Individual Plant Examination of External Events (IPEEE - full-scope Seismic Margin Assessment) documentation - basis for Safe Shutdown Equipment List (SSEL) Base List 1 Review current Seismic Probabilistic Risk Assessment (SPRA) database Retrieve containment function equipment Retrieve modifications since the IPEEE Retrieve recently modified!upgraded equipment information Retrieve seismic vulnerabilities from Corrective Action Program (CAP)

Retrieve System Health Reports Retrieve spent fuel pool (SFP) SC-I equipment (piping and instrumentation drawings, Design Basis Manuals, and Training Manual) - basis for SSEL Baselist 2 Assemble preliminary Safe Shutdown Equipment List (i.e., Base List 1)

Perform Screen #1, Seismic Category I (non-Seismic Category I SSCs screen out)

Perform Screen #2, Regular Inspections (Structures, Piping, Penetrations screen out)

Perform Screen #3, Safety Function Support Assemble preliminary SSEL (Base List 2)

Perform Screen #1, Seismic Category I (non-Seismic Category I SSCs screen out)

Perform Screen #2, Regular Inspections (Structures, Piping, Penetrations screen out)

Site visit to confirm preliminary SSEL Finalize SSEL Select SWEL 1 Perform Screen #4 System variety Equipment type variety Enviromnent variety Risk importance considerations Equipment access considerations Major new or replacement equipment Recently modified/upgraded (zone of influence effects)

IPEEE Seismic Vulnerability findings Sample considerations including unit-to-unit variation Select SWEL 2 (spent fuel pool Related Items)

Perform Screen #3 System variety Equipment type variety WCAP-17680-NP, Supplement I Revision 0 PVNGS-2 August 2013

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Sample considerations including unit-to-unit variation Perform Screen #4 rapid drain-down assessment Confirm SWEL with Seismic Walkdown Engineers (SWEs)

Obtain PVNGS-2 Operations approval of SWEL SWEL Peer Review Per the guidance provided in Section 2 of Reference 1, PVNGS Operations and Design Engineering staff members participated in the selection of the SSCs comprising the SWEL and provided input and assistance to the Equipment Selection Personnel collecting the data associated with the equipment considered. The exchange of information between the Equipment Selection Personnel and the PVNGS staff members included:

• Review of the IPEEE and PRA list of components was performed by the Westinghouse and PVNGS team to correct discrepancies in classification, errors in equipment identification (EQID),

omissions, risk categorization, etc.

" Weekly status meetings for review of the SWEL progress.

" A presentation held on July 17, 2012, to discuss Westinghouse's methodology for SWEL selection.

• Verification of equipment information through PVNGS's Site Work Management System (SWMS) (Reference 2).

• Provide risk importance data derived from the PVNGS Internal Events Probabilistic Risk Assessment (PRA) model (Reference 33).

• Assist in identifying and categorizing the different operating environment types existing at the plant.

• Discussions with Operations relative to recent upgrades and changes to the plant that have the potential to be relevant to the SWEL.

" Discussions with Design Engineering and Operations to select equipment with operational experience relevant to SWEL selection.

• Equipment Qualification Control Form (EQCF) Database for review of CAP and modifications against seismic equipment.

" Provide System Health Reports and Design Basis Manuals (DBMs) for review by the Equipment Selection Personnel.

• SWEL Peer Review and approval of the SSCs selected for the Walkdowns and Area Walk-Bys (see Appendix F).

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The agenda followed during the meetings included:

• Pre-Job Brief of the SWEL selection project

" Discuss high-level approach to SWEL Development

• Review of preliminary Base List 1 for accuracy and completeness o Populate the Screen #4 Sample Selection attributes o Select the SWEL 1 items o Identify items for follow-up

" Review of preliminary Base List 2 for accuracy and completeness o Populate the Screen #3 Sample selection attributes o Select the SWEL 2 items o Identify items for follow-up

• Identify any unit-to-unit considerations

" Summarize results

• Summary post-job briefing A second meeting was held on July 17, 2012, to provide a presentation summarizing the Westinghouse/PVNGS team's selection methodology and conduct a second working session with PVNGS staff members to further refine the SWEL.

The following personnel participated in these working sessions:

Attendee Company Position Chris Wandell APS Senior Consulting Engineer (Civil)

Winston Borrero APS Senior Consulting Engineer (Mechanical)

Justin Wood APS Engineer (Modifications)

Jose (Angel) Delgadillo APS Auxiliary Operator Randall (Gene) Eimar APS Operations Shift Manager Rolando Perez Westinghouse SWEL Development Lead (participated remotely via WebEx')

Derek Seaman Westinghouse SWEL Developer Per the guidance provided in Section 3 of Reference 1, SSCs were selected in the following two groups:

" SWEL 1 - A sample of items that safely shut down the reactor and maintain containment integrity.

• SWEL 2 - A sample of spent fuel pool (SFP) related items, including items that could result in a rapid drain-down of the SFP.

The SWELs from these two groups were combined into a single SWEL for use during the Seismic Walkdowns and Area Walk-Bys.

WebEx is a trademark or registered trademark of Cisco Systems, Inc.

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3.2 Sample of Required Items for the Five Safety Functions The five safety functions include the four safe shutdown functions (reactor reactivity control, reactor coolant pressure control, reactor coolant inventory control, and decay heat removal, which includes the ultimate heat sink), plus the containment functions.

The IPEEE (Reference 3) Safe Shutdown Equipment List (SSEL) was used as the starting point for compiling a list (Base List 1) of the SSCs to be considered in the SWEL 1 selection process. A list consisting of 979 SSCs was assembled based on the following tables documented in Appendix 3.A of Reference 3:

• Table 3A-I - Reactor Protection System SSEL (36 items)

• Table 3A Support Systems SSEL (403 items)

" Table 3A Required Instrumentation SSEL (72 items)

• Table 3A Primary Auxiliary Feedwater SSEL (70 items)

• Table 3A Secondary Auxiliary Feedwater SSEL (59 items)

• Table 3A Atmospheric Dump Valves SSEL (72 items)

• Table 3A Auxiliary Pressurizer Spray SSEL (42 items)

• Table 3A Shutdown Cooling System SSEL (84 items)

" Table 3A High Pressure Safety Injection SSEL (89 items)

• Table 3A High Pressure Recirculation SSEL (52 items)

A review of the Seismic Probabilistic Risk Assessment (SPRA) database (Reference 34) was then performed to expand the equipment list. Seismic Category I (SC-I) equipment that was considered in the SPRA, but not included in the IPEEE tables, was identified and added to the equipment list, resulting in a total Base List 1 count of 1237 items.

Since the IPEEE applies to the three PVNGS Units, general equipment identification numbers (IDs) were used in the SSEL tables (i.e., the IDs presented therein do not show the Unit number, which is normally indicated by the first character of the equipment ID). In contrast, in the SPRA database, much of the equipment was identified by using the Unit 1 designation. Therefore, all equipment IDs in the list were converted to the Unit 2 designation.

Per the guidance provided in Section 3 of Reference 1, the process for selecting a sample of the SSCs associated with the safe shutdown of the reactor and maintaining containment integrity must include the following four screens:

• Screen #1 - Seismic Category I:

The purpose of Screen #1 is to restrict the scope of SSCs in the SWEL to those that are classified as SC-I. This is intended to comply with the request in the NRC 50.54(f) Letter (Reference 50),

under the "Requested Actions" section, to "verify current plant configuration with the current license basis."

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• Screen #2 - Equipment or Systems:

The purpose of Screen #2 is to filter out the SSCs that regularly undergo inspections to confirm that their configuration continues to be consistent with the established plant licensing basis. The types of SSCs that are excluded consist of SC-1 Structures, Containment Penetrations, and SC-1 Piping Systems.

Manual valves, check valves, flow orifices, fire dampers, and relief valves were also excluded in accordance with the guidance, since they are either considered in-line components or equipment that is regularly inspected.

Out of 1122 items coming in from Screen #1, 778 were retained by Screen #2 and subsequently passed to Screen #3.

" Screen #3 - Support for the 5 Safety Functions:

The purpose of Screen #3 is to filter out the SSCs that do not support at least one of the following safety functions:

o Reactor reactivity control o Reactor coolant pressure control o Reactor coolant inventory control o Decay heat removal, including the ultimate heat sink o Containment function The safety functions supported by each SSC exiting Screen #2 were determined in consultation with PVNGS staff members (Shift Manager/Auxiliary Operator) during the first set of meetings.

Out of 778 items coming in from Screen #2, 415 were retained by Screen #3 and subsequently passed to Screen #4. The list of equipment from Screen #3, entering Screen #4, is defined as Base List 1.

" Screen #4 - Sample Considerations:

The purpose of Screen #4 is to narrow the Base List 1 candidate items to those of most significance. The PVNGS-2 SWEL I contains 1242 representative items from each of the following sample selection attributes:

2 The original SWEL 1 consisted of 126 items. Two items were removed (2JCHAUVO516 and 2MCHEE01) because they were inaccessible in a locked high-radiation area. See discussion in Section 3.4.

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The PVNGS-2 Base List 1 equipment was categorized based on the third and fourth characters of their tag identification numbers (IDs), which identifies the plant system.

There were 31 system categories contained in Base List 1. Table 3-1 shows how these system categories were represented in SWEL 1.

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CP Containment Purge 4 1 CT Condensate Transfer and Storage 3 3 DF Diesel Fuel Oil and Transfer 1 1 DG Diesel Generator 14 3 EC HVAC Essential Chilled Water 8 4 EW Essential Cooling Water 8 5 GA Service Gas 1 1 GR Gaseous Radwaste 2 0 HA HVAC Auxiliary Building 4 4 HC HVAC Containment Building 12 6 HD HVAC Diesel Generator Building 4 2 HJ HVAC Control Building 21 9 JA Instrument and Service Air 1 I PB Class 1E 4.16 kv Power 3 2 PE Class lE Standby Generation 2 1 PG Class IE 480v Power Switchgear 6 3 PH Class 1E 480v Power Motor Control Center 8 4 PK Class 1E 125 VDC 20 11 PN Class lE Instrument Power 12 7 RC Reactor Coolant 16 5 RD Radioactive Waste Drain 2 1 RM Main Control Board 31 7 SA Engineered Safety Features Actuation System 11 0 SB Reactor Protection 14 1 SG Main Steam 42 9 SI Safety Injection 101 16 SP Essential Spray Ponds 4 2 ZA Auxiliary Building 6 0 ZJ Control Building 11 0

• Refer to Section 3.4 for explanation of change to SWEL 1 System Type.

Note that the Gaseous Radwaste (GR) system is not a safety-related system but does have containment isolation valves, which are safety-related. These GR valves are not included in the SWEL since motor-operated valves and solenoid-operated valves (equipment type 8 in Table 3-3; discussed later) are already being well represented (34 valves selected out of 117 total valves). With only 2 valves from the GR system on Base List 1, the exclusion of these valves from the SWEL does not skew the system sampling - the MOV/SOV equipment type (i.e., containment isolation valves) is well represented in SWEL 1.

Note that the SA (Engineered Safety Features Actuation System), ZA (Auxiliary Building), and ZJ (Control Building) systems are not represented because the equipment types covered by each system are already well represented.

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Major new and replacement equipment were identified through a review of either:

1) Section 8 (System Design History), or 2) Section 11 (Change History), of a selection of the major system DBMs (References 4 through 30). Recent modifications were assessed through consultation with PVNGS Operations and Design Engineering staff members. Additionally, System Health Reports were reviewed to ensure that recent modifications were captured and examined for potential impact. The participating PVNGS Operations staff members were asked to provide any information they felt the System Health Reports may not have touched upon. This was to address any recent modifications where 1) weight and/or the location of the center of gravity of the replacement are significantly different, or 2) design of the mounting and anchorage of the replacement is significantly different than the original, or 3) items within the zone of influence had to be reinstalled.

Based on this sampling consideration, 38 Base List I items were identified as having major new or replacement modifications. Of these, the 10 items shown in Table 3-2 were represented in SWEL 1.

Table 3-2: Equipment Selected for SWEL Based on the "Major New or Replacement Equipment" Attribute Item Walkdown Description Major New or Replacement Equipment Equipment Modifications Replacement of POSI-seal hard seats on valves. See 279 2JSIAUVO673 Sump isolation valve Reference 30, p. 249.

280 23SIAUV0674 Sump isolation valve Replacement of POSI-seal hard seats on valves. See Reference 30, p. 249.

Inserted 90/10 Cu/Ni 8-inch sleeves into the inlet and outlet ends of Unit 2 essential cooling water heat 61 2MEWAE01 EW "A" heat exchanger exchangers 2MEWAEOI and 2MEWBEOI to prevent further degradation of the tubes due to primary water stress corrosion cracking. See Reference 8, p. 74 (Unit 2 only).

5 2JAFAUVO037 SG-EOIB isolation valve Replaced actuator and yoke assembly on valves. See Reference 4, p. 104.

1HPSI pump "A" recire iso (closes on Modified the HPSI throttle valves and miniflow isolating 278 2JSIAUV0666 PS) valves from rising/rotating stem valves and changed the RAS) motor operated actuators. See Reference 30, p. 250.

Relocated the motor-operated valve from outside the 274 2JSIAUV0651 RC loop I long-term recirc/SDC bioshield wall to the inside near the hot-leg nozzle to valve eliminate flow-induced vibration in the line. See Reference 30, p. 248.

47 2MDGAF03 DG "A" air intake filter Modified hangers. See Reference 6, p. 104.

208 2JSGAUV0 134A AF turbine steam supply heatup Changed from SOV to MOV. See Reference 4, p. 105 and Reference 21, p. 49 .

2AUV38A AF turbine steam supply heatup Changed from SOV to MOV. See Reference 4, p. 105 (Train A) and Reference 21, p. 49 .

115 2EPBBS04

• 4.16 kV bus S04 Addition of relays. See Reference 6, p. 101

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The Base List 1 items were each assigned to one of the 22 classes of equipment listed in Appendix B of Reference 1. Table 3-3 shows how these classes were represented in SWEL 1. Two classes, compressors and motor generators, were not represented because there is no SC-1 equipment in these categories. Additionally, the transformers that are SC-1 were considered part of the larger equipment typically represented as switchgear or motor control centers (MCCs). Thus, this classification is not individually represented in SWEL 1.

Table 3-3: Sort of the Base List 1 Data and Selected SWEL Items Based on "Equipment Type Number" Equipment Type Number of Items Number of Items Number Description in Base List for SWEL I 0 Miscellaneous 13 5 1 Motor Control Centers 13 7 2 Low-Voltage Switchgear 12 4 3 Medium-Voltage Switchgear 2 1 4 Transformers 0 0 5 Horizontal Pumps 11 .6 6 Vertical Pumps 8 3 7 Fluid-Operated Valves 23 8*

8 Motor-Operated Valves, Solenoid-Operated Valves 117 34 9 Fans 8 3 10 Air Handlers 10 7 11 Chillers 2 1 12 Air Compressors 0 0 13 Motor Generators 0 0 14 Distribution Panels 41 4 15 Batteries on Racks 4 3 16 Battery Chargers and Inverters 12 6 17 Engine Generators 2 1 18 Instruments on Racks 74 14 19 Temperature Sensors 3 2 20 Instrumentation and Control Panels and Racks 40 7 21 Tanks and Heat Exchangers 20 8*

• Refer to Section 3.4 for explanation of change to SWEL I Equipment Type Number.

o A variety of environments:

Since the site is located in a dry environment, typical of a desert climate, it was decided to identify the equipment operating environments based on its location either "inside" (i.e., inside an equipment room) or "outside" (i.e., outdoors) and based on the normal maximum design temperature of the corresponding equipment environment. These design temperatures were determined from a review of Appendix A of the Equipment Qualification Program Manual (Reference 31) and Section 9.4 of the Updated Final Safety Analysis Report (UFSAR) (Reference 32). Based on this review, seven categories of equipment operating environments were identified. Table 3-4 shows how these equipment operating environments were represented in SWEL 1.

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Temperature Number of Items Number of Items (OF) in Base List 1 Selected for SWEL 1 80 143 (All inside) 45 (All inside) 104 150 (All inside) 43 (All inside) 113 8 (2 inside and 6 outside) 4 (2 inside and 2 outside) 120 62 (All inside) 13 * (All inside) 122 6 (2 inside and 4 outside) 2 (All outside) 124 18 (All inside) 7 (All inside) 140 28 (All inside) 10 (All inside)

• Refer to Section 3.4 for explanation of change to SWEL 1 Environment list.

o Equipment enhanced due to vulnerabilities identified during the IPEEE program:

Based on a review of the IPEEE report (Reference 3), there were no Unit 2 seismic vulnerabilities identified. However, the IPEEE report states that a limited number of actions were taken to improve plant seismic capacity; no specific actions other than a Unit 3 example were provided, e.g., the anchorage on the bookcases located behind the control cabinets in Unit 3 was improved to reduce the possibility that the cabinets would be impacted during a seismic event.

The following additional considerations were factored into the SWEL I selection process:

o Numerical measures of risk importance:

The Risk Achievement Worth (RAW) derived from the Internal Events PRA model (Reference 33) was compiled for the Base List 1 items to determine potentially risk-significant SSCs. Items with a RAW value greater than 2 were considered of "high" risk importance. There were 70 items of high risk importance in Base List 1; 35 were selected for SWEL 1.

o Protected train restrictions during the walkdown week:

The protected train schedules [PVNGS "Work Week Schedule"] during the PVNGS-2 walkdown dates (from July 23, 2012, through July 27, 2012) were reviewed so that inaccessible items could be identified and deferred from SWEL 1. Of the 124 items selected for SWEL 1, 1 item (SWEL Item #92) was initially expected to be inaccessible due to protected train restrictions. However, it was later determined that its walkdown could be performed. Therefore, there was no need to defer its walkdown to PVNGS refueling outage 2R17 in fall 2012.

3.2.1 Base List 1 The list of equipment retained by Screen #3 (and subsequently entering Screen #4) is defined as Base List 1 and is summarized in Appendix G, Table G-1.

3.2.2 SWEL 1 The list of equipment retained by Screen #4 is defined as SWEL 1 and is summarized in Appendix G, Table G-2.

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Per the guidance established in Section 3 of Reference 1, the process for selecting a sample of the SSCs associated with the SFP includes the following four screens:

• Screen #1 - Seismic Category I:

The process for selecting SFP-related SSCs using Screen #1 is similar to the process described earlier for Screen #1 of SWEL 1. The purpose of Screen #1 is to limit the items to those that have a seismic licensing basis.

All SSCs initially considered for SWEL 2 (26 items) were passed from Screen #1 to Screen #2.

" Screen #2 - Equipment or Systems:

The process for selecting SFP-related SSCs using Screen #2 is similar to the process described earlier for Screen #2 of SWEL 1. Screen #2 considers only those items associated with the SFP that are appropriate for an equipment walkdown process. The purpose of Screen #2 is to filter out the SSCs that regularly undergo inspections to confirm that their configuration continues to be consistent with the established plant licensing basis.

Of the 26 items retained by Screen #1, 6 were retained by Screen #2 and subsequently passed on to Screen #3.

• Screen #3 - Sample Considerations:

The equipment retained by Screen #2 and subsequently entering Screen #3 is defined as Base List 2.

The process for selecting SFP-related SSCs using Screen #3 is similar to the process described earlier for Screen #4 of SWEL 1. The purpose of Screen #3 is to narrow the Base List 2 candidate items to those of most significance, considering the following sample selection attributes:

o A variety of types of systems o Major new and replacement equipment (including recent modifications) o A variety of types of equipment o A variety of environments Since there were only six items associated with the SFP, all items contained in Base List 2 were selected for input to SWEL 2.

" Screen #4 - Rapid Drain-Down:

The purpose of Screen #4 is to identify items that could allow the SFP to drain rapidly. Per the guidance established in Section 3 of Reference 1, the SSCs considered are not limited to SC-1 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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The Seismic Walkdown Guidance (Reference 1) specifies the following on page 3-8:

"Determine whether there are SFPpenetrationsbelow about 1 0feet above the top of the fuel assemblies. If there are no such penetrations, then no rapid drain-down items would be added to SWEL 2."

UFSAR (Reference 32) Section 9.1.3.3.1.1.1, pages 9.1-35 and 9.1-36, states the following:

"If a pipe break were to occur in the Seismic Categorv I/quality portion of the system, pool cooling could be lost. However, the event would be self-limiting as all pipe penetrations through the pool wall are at or above the minimum required water levels .for spent fuel shielding of lOft as required by Regulatory Guide 1.13. All pipes extending down into the pool have siphon breaker holes at or above the minimum required water level. Under these conditions, sufficient time (longer than 30 minutes) is available to isolate the break and recover the minimum level requiredfor start of the pool cooling system. If the spent fuel pool clean up system is aligned with the refueling pool (drain valves), administrativeprocedures are in place to identify, locate and isolate a pipe break within the containment in a timely manner.

The first two sentences of this UFSAR excerpt deal with the possibility of losing SFP water inventory following a pipe break. The next two sentences deal with how quickly the Fuel Pool Cooling and Cleanup System can be restored following a pipe break and are not pertinent to rapid drain-down.

Based on this documentation, there are no rapid drain-down items for input to SWEL 2.

A review of the SFP and its relationship to the adjacent fuel transfer canal and cask load pit was conducted to ensure that a rapid drain-down could not occur via a loss of gate seal integrity. A system review showed that the bottom of the fuel transfer canal gate and cask load pit gate invert are 3-1/2 inches below the top of the spent fuel racks. Although a loss of these gate seals would result in flooding of the cask load pit and the fuel transfer canal, it would not result in a water level less than 10 feet above the top of the fuel assemblies. This is due to the relatively small volume of the fuel transfer canal and cask load pit. The fuel transfer tube within the fuel transfer canal was also considered since it provides an isolation path to the reactor cavity. The fuel transfer tube seal, canal isolation valve PPCNV 118, and quick-operating closure device MPCEM01A are SC-1 items considered part of the SFP structure assessed by analysis and periodic inspections and were therefore excluded from SWEL 2. Drainage from the cask load pit to the decontamination pit would be limited because the bottom of the decontamination gate invert is 10 feet above the top of the fuel assemblies. Although a rapid drain-down threat associated with the gate seal system was not found, the instrument air supply system to the SFP gate was included in the Area Walk-By.

3.3.1 Base List 2 The equipment retained by Screen #2 and subsequently entering Screen #3 is defined as Base List 2 and is summarized in Appendix G, Table G-3.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 3-13 3.3.2 Rapid Drain-Down SWEL 2 is augmented by the equipment that could potentially cause the SFP to drain rapidly (the equipment retained by Screen #4). As discussed earlier, there are no rapid drain-down items for input to the PVNGS-2 SWEL 2.

3.3.3 SWEL 2 SWEL 2 is defined as the list of equipment retained by Screen #3 plus the equipment retained by Screen

1. 4. As discussed earlier, Screen #3 was not utilized because all 6 items contained in Base List 2 were selected for input into SWEL 2. In addition, there was no equipment associated with rapid drain-down.

Therefore, SWEL 2 is the same as Base List 2 (summarized in Appendix G, Table G-3).

WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 3-14 3.4 Inaccessible Items The equipment items that were inaccessible during the scheduled PVNGS-2 at-power walkdown dates (from July 23, 2012, through July 27, 2012) are identified in Table 3-5. The guidance allows for items to be deferred to a later date if inspection poses a safety concern. Items with electrical safety challenges or items within containment were deferred to ensure safety when inspecting. The items in Table 3-5 were subsequently walked down during and following PVNGS refueling outage 2R1 7.

Table 3-5: PVNGS-2 Equipment Inaccessible During the Scheduled At-Power Walkdowns SWEL I Walkdown Description Equipment Item Equipment Location Number 7 2JCHAHV0205 Auxiliary pressurizer spray valve CTMT 11 2JCHAUV0516 Reactor coolant letdown line to regenerative heat exchanger CTMT isolation globe valve 12 2MCHEE01 Regenerative heat exchanger CTMT 13 2JCHEPDV0240

• Charging header to RCS backpressure control valve CTMT 18 2JCPAUVO004B Containment power access purge exhaust isolation butterfly CTMT damper 58 2EPBAS03 4.16 kV bus S03 CTRL 61 2EPGAL31 480 V LC31 bus CTRL 62 2EPGAL33 480 V LC33 bus CTRL 86 2JRCAPT0102A Przr pressure (required for RPS/SIAS) CTMT 87 2JRCAPT 103 SDC RCS pressure interlock CTMT 90 2JRCNTE 101 Pressurizer temperature CTMT 101 2JSGALTI 113A SG-EO1A WR level (required for AFAS) CTMT 114 2JSIAUVO634 Safety injection tank 1A discharge isolation globe valve CTMT 115 2JSIAUV0644 Safety injection tank IB discharge isolation globe valve CTMT 116 2JSIAUVO651 RC loop 1 long-term recirc/SDC valve CTMT 120 2JSIAUVO673 Sump isolation valve CTMT 123 2JSINPT39l HPSI long-term recirc loop I pressure xmtr CTMT

• This equipment was incorrectly identified in Reference 48 as 2JCHEHV0240. The correct equipment ID is 2JCHEPDVO240; the Operations equipment description is provided. This has been corrected in the tables of Appendix G.

Items 2JCHAUVO516 and 2MCHEE01 were inaccessible in a locked high-radiation area. For radiological safety considerations, it was decided to remove these components from SWEL 1. New items were not selected to replace these items for the following reasons:

" These two items belong to system type CH. The removal of these items reduced the number of CH items in SWEL 1 from 11 to 9 (see Table 3-1), which is still a good representation of this system type.

" These two items were not identified as having major new or replacement modifications (see Table 3-2). Therefore, the removal of these items from SWEL 1 had no effect on the representation of equipment having major new or replacement modifications.

• JCHAUV0516 belongs to equipment type 7 and 2MCHEEO 1 to equipment type 21. The removal of these items from SWEL 1 reduced the number of type 7 items from 9 to 8 and the number of WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 3-15 type 21 items from 9 to 8 (see Table 3-3), which are still good representations of the equipment type.

• These two items are assigned a maximum environment temperature of 1201F. The removal of these items reduced the number of "120'F items" in SWEL 1 from 15 to 13 (see Table 3-4),

which is still a good representation of the environment temperature type.

• These two items were not risk-significant SSCs. Therefore, the removal of these items from SWEL I had no effect on the representation of high-risk-importance items in SWEL 1.

Following the completion of the Unit 2 at-power Seismic Walkdowns, the industry was made aware that the NRC staff had clarified a position on opening electrical cabinets to inspect for other adverse seismic conditions. Supplemental inspections of 18 electrical cabinets per FAQ 4.20 were conducted during the follow-on walkdowns. The list of electrical cabinets that required supplemental inspection is included in Table 3-6.

Table 3-6: PVNGS-2 FAQ 4.20 Supplemental Cabinet Inspections Item WalkdownDescription Equipment Num Equipment Location 63 2EPGAL35 480 V LC35 bus CTRL 64 2EPHAM31 480 V MCC M31 CTRL 65 2EPHAM33 480 V MCC M33 AUX 66 2EPHAM35 480 V MCC M35 AUX 67 2EPHAM37 480 V MCC M37 AUX 68 2EPKAD21 LC 33 control power CTRL 70 2EPKAH 11 Battery charger "A" CTRL 71 2EPKAH15 125 VDC Class 1E battery charger AC CTRL 72 2EPKAM41 DC power to TCB1 control circuit CTRL 74 2EPKCN43 Inverter for shutdown cooling isolation valve 2JSICUV653 CTRL 75 2EPKDD24 DC distribution panel D24 CTRL 77 2EPKDM44 DC power to TCB 1 control circuit CTRL 78 2EPKDN44 Inverter for 2JSIDUV654 shutdown cooling B return inside containment CTRL isolation valve 80 2EPNAN 11 DC/AC inverter "A" CTRL 84 2EPNDN 14 DC/AC inverter "D" CTRL 94 2JRMAB05 Containment pressure CTRL 96 2JRMDB05 Containment pressure CTRL 98 2JSBAC03 Reactor trip breaker "A" AUX The inaccessible equipment walkdowns performed during refueling outage 2R 17 are summarized in Table 3-7. Since Train A was protected during refueling outage 2R17, Train A electrical components were substituted with their counterpart from Train B. Table 3-7 indicates the equipment that were used as substitutes.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 3-16 Table 3-7: PVNGS-2 Equipment Inspected During Refueling Outage 2R17 SWEL I Walkdown Equipment Item Equipment Description Number Location 7 2JCHAHV0205 Auxiliary pressurizer spray valve CTMT 13 JCEPVO40Charging header to RCS backpressure CTMT 13 2JCHEPDV0240 control valve 18 2JCPAUVO004B Containment power access purge CTMT 18____ 2 Vexhaust isolation butterfly damper 58 2EPBBS04 (substitute for 2EPBAS03) 4.16 kV bus S03 CTRL 61 2EPGBL32 (substitute for 2EPGAL3 1) 480 V LC31 bus CTRL 62 2EPGBL34 (substitute for 2EPGAL33) 480 V LC33 bus CTRL 63 2EPGBL36 (substitute for 2EPGAL35; inspected 480 V LC35 bus CTRL to satisfy FAQ 4.20) 64 2EPHBM32 (substitute for 2EPHAM3 1; inspected 480 V MCC M31 CTRL to satisfy FAQ 4.20) 65 2EPHBM34 (substitute for 2EPHAM33; inspected 480 V MCC M33 AUX to satisfy FAQ 4.20) 66 2EPHBM36 (substitute for 2EPHAM35; inspected 480 V MCC M35 AUX to satisfy FAQ 4.20) 67 2EPHBM38 (substitute for 2EPHAM37; inspected 480 V MCC M37 AUX to satisfy FAQ 4.20) 2EPKBD22 (substitute for 2EPKAD2 1; inspected LC 33 control power CTRL to satisfy FAQ 4.20) 72 2EPKBM42 (substitute for 2EPKAM41; inspected DC power to TCB I control circuit CTRL to satisfy FAQ 4.20) 75 2EPKDD24 DC distribution panel D24 CTRL 77 2EPKDM44 DC power to TCB1 control circuit CTRL Inverter for 2JSIDUV654 shutdown 78 2EPKDN44 cooling B return inside containment CTRL isolation valve 86 2JRCAPT0102A Przr pressure (required for RPS/SIAS) CTMT 87 2JRCAPT 103 SDC RCS pressure interlock CTMT 90 2JRCNTE101 Pressurizer temperature CTMT 94 2JRMAB05 Containment pressure CTRL 96 2JRMIDBO5 Containment pressure CTRL 98 2JSBAC03 Reactor trip breaker "A" AUX 101 2JSGALTI 113A SG-EO1A WR level (required for CTMT AFAS) 114 2JSIAUVO634 Safety injection tank 1A discharge CTMT isolation globe valve 115 2JSIAUV0644 Safety injection tank 1B discharge CTMT isolation globe valve 116 2JSIAUVO651 RC loop I long-term recirc/SDC valve CTMT 120 2JSIAUV0673 Sump isolation valve CTMT 123 2JSINPT391 HPSI long-term recirc loop I pressure CTMT xrntr Revision 0 Supplement 1 WCAP-17680-NP, Supplement 2 0 Revision PVNGS-2 Auguist 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 3-17 The equipment that could not be inspected during refueling outage 2R17 is identified in Table 3-8. The walkdown of this equipment was completed on December 5, 2012.

Table 3-8: PVNGS-2 Items Completed During the December 5, 2012 Inspection SWEL 1 Walkdown Equipment Item Equipment Description Number Location 70 2EPKAHI1 Battery charger "A" CTRL 71 2EPKAH15 125 VDC Class IE battery charger AC CTRL 74 2EPKCN43 Inverter for shutdown cooling isolation CTRL valve 2JSICUV653 80 2EPNAN 11 DC/AC inverter "A" CTRL 84 2EPNDN 14 DC/AC inverter "D" CTRL All required and supplemental inspections are complete. Inspection results are documented on the corresponding Seismic Walkdown checklist in Appendix A WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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4. SEISMIC WALKDOWNS AND AREA WALK-BYS

4.1 BACKGROUND

Seismic Walkdowns and Area Walk-Bys were performed in accordance with the requirements of Section 4 of EPRI TR-1025286 (Reference 1). The walkdowns were conducted by the SWT, consisting of the two SWEs mentioned in Section 2.2. Members of PVNGS Operations and Engineering provided support during all walkdowns. The SWEs utilized engineering judgment based upon experience and training indicated in Section 2.2, supplemented by existing current licensing basis (CLB) plant documentation and analyses, where applicable, to identify potentially adverse seismic conditions. For items on the SWEL, these potential seismic conditions included any adverse anchorage conditions, adverse seismic spatial interactions, or other adverse seismic conditions. The results of the walkdown and any pertinent observations were documented for each item on the SWEL using the Seismic Walkdown Checklists (SWCs) included in Appendix A. In addition to potentially adverse seismic conditions, observations described in the SWCs include those that, after discussion between the SWEs, were determined to be adequate.

Area Walk-Bys were conducted by the SWT in each area of the plant that contained an item on the SWEL. The Area Walk-Bys identified potentially adverse seismic conditions associated with other SSCs located in the vicinity of the SWEL item (up to a maximum radius of 35 ft from the component). The area examinations identified: 1) adverse anchorage conditions, 2) degraded equipment in the area,

3) potential seismic spatial interactions, 4) adverse cable/conduit raceways and HVAC ducting,

5) potential flooding/spray or fire hazards, and 6) other adverse housekeeping conditions. The results of the walk-bys and any pertinent observations were documented for each inspected area using Area Walk-By Checklists (AWCs), which are included in Appendix B. Observations described on the AWCs include potentially adverse seismic conditions as well as conditions that were discussed and determined to be adequate at that time.

The SWT was assisted by other individuals present on the walkdown, including PVNGS Operations and Engineering personnel. The SWT for PVNGS Unit 2 consisted of Hunter Young and Cory Figliolini of S&A. Chris Wandell and Winston Borrero led the support from PVNGS for walkdowns as well as the interface with plant operators. Additional PVNGS staff facilitated access to equipment and provided additional information regarding plant procedures and functions of SWEL items. In addition, these individuals assisted in identifying nearby equipment and systems that could cause adverse seismic interaction. Any issue that could not be resolved by consensus of the SWEs during the walkdowns was identified as a potentially adverse seismic condition on the SWC or AWC (as applicable). The conditions identified were evaluated with respect to the CLB. These Licensing Basis Evaluations are listed and described in Appendix D.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 4-2 4.2 PREPARATION FOR SEISMIC WALKDOWNS In preparation for the Seismic Walkdowns and Area Walk-Bys, the SWT obtained the SWEL and selected 50% of the items (excluding line-mounted equipment) for anchorage configuration verification. A total of 89 components were identified as potential anchorage verification candidates and 49 were randomly chosen to fulfill the 50% anchorage configuration verification requirement. The selection was adjusted to consider equipment of interest identified by PVNGS, including items that had recent modifications or anchorage changes. PVNGS design drawings, seismic qualification calculations, and vendor/supplier documents (SDOCs) were reviewed and later taken to the field to verify as-installed configurations were consistent with the CLB established by these documents. The SWT also obtained PVNGS equipment layout drawings to establish a detailed walkdown schedule.

To prepare for observations involving potential interaction with masonry block walls, the SWT reviewed the equipment layout drawings associated with the SWEL and located masonry walls in proximity. The Control Building 74 ft, 100 ft, and 140 ft elevations, in addition to the Auxiliary Building sub-100 ft elevations, were found to have block walls adjacent to SWEL items and Area Walk-By items. The SWT obtained and reviewed calculation 13-CC-ZJ-0120 (Reference 60) for Control Building masonry walls and 13-CC-ZA-0 140 (Reference 6 1) for Auxiliary Building masonry walls. The calculations indicate that all in-scope walls were designed and analyzed to not collapse under SSE accelerations, which enabled the SWT to conclude that the SWEL items were free of seismic spatial interaction due to a postulated masonry block wall collapse. The SWT assessed SWEL and Area Walk-By equipment for seismic spatial interaction due to differential movement between the equipment and the masonry block walls.

In anticipation of potential flooding/spray interaction hazards due to threaded fire piping, the SWT obtained fire suppression diagrams provided within the IPEEE Report (Reference 3). These diagrams were later used in the field for Area Walk-Bys to determine whether threaded fire piping, where present, was normally wet or pre-actuated and dry. Preliminary review of the fire suppression diagrams indicated that areas with threaded fire piping are generally pre-activated sprinkler systems and therefore are normally dry, thus precluding potential flooding/spray interaction hazards. However, the SWT was cognizant of exceptions where threaded piping could be normally wet. For these cases, the SWT would look for long spans with flexible supports, which may lead to excessive threaded joint rotation and potential spray.

Additional current licensing basis documentation obtained and reviewed to support the walkdowns included: the in-structure floor response spectra for the SSE (DBM-C5, Reference 53), structural damping criteria per UFSAR Table 3.7-1 (Reference 32), the PVNGS scaffolding procedure and installation specifications (30DP-9WPll and 13-CN-0380, References 54 and 55), the PVNGS housekeeping procedure (30DP-OWM12, Reference 56), the PVNGS transient material details and analyses (13-A-ZYD-0034 and 13-CC-ZZ-0309, References 57 and 58), the PVNGS lighting details (13-E-ZAL-0011, Reference 59), and the control room ceiling qualification (Log No. 13-10407-A216-12, Reference 65).

The PVNGS IPEEE Report (Reference 3) was also obtained and reviewed. This document is discussed in further detail in Section 7.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 4-3 4.3 WALKDOWN RESULTS The SWT conducted the initial Seismic Walkdowns for Unit 2 at PVNGS July 23, 2012, through July 27, 2012. For components not originally inspected due to having either inaccessible internal anchorages, being located inside containment, or requiring additional interior inspection related to FAQ 4.20, additional walkdowns were conducted during refueling outage 2R17 on October 13, 2012, through October 14, 2012, and during follow-on inspections performed on December 5, 2012. Detailed walkdown results are provided on the SWCs and AWCs in Appendices A and B, respectively. When walkdown activities identified potentially adverse seismic conditions, licensing basis evaluations were performed and are discussed in Section 5 and Appendix D. Appendix D provides additional information on the resolution and Operability Determinations/Functional Assessments of each of these conditions. A summary of initial walkdown statistics follows:

• A total of 137 components were walked down and 63 Area Walk-Bys were performed. Five items listed on the SWEL (2EPKAD21, 2EPKBD22, 2EPKDD24, 2JRMNB04, and 2JRMAB05) were child components contained within parent SWEL components. These child components are referred to as "Rule of the Box" (ROB) items, for which the walkdown observations are identical to those of the parent item.

• Eighteen (18) SWEL components were electrical cabinets whose interiors were not completely examined during the initial walkdowns. Following the completion of the at-power Seismic Walkdowns, the industry was made aware that the NRC staff had clarified under FAQ 4.20 a position on opening electrical cabinets to inspect for other adverse seismic conditions.

Supplemental inspections of 18 electrical cabinets occurred on October 13, October 14, and December 5, 2012. The list of electrical cabinets requiring supplemental inspection per FAQ 4.20 is included in Section 3.4. Seven (7) SWEL electrical cabinets originally inspected during the at-power walkdowns were inaccessible during the supplemental inspections due to the plant protected train. To fulfill the recommendations of FAQ 4.20, sister components for these cabinets on the opposite train were fully inspected-including the cabinet interiors-and documented on SWCs. One hundred twelve (112) components and fifty-six (56) Area Walk-Bys were resolved in the field as having no potentially adverse seismic concerns.

" Thirty-two (32) observations for Twenty-five (25) SWEL components and seven (7) Area Walk-By observations could not be readily resolved by the consensus of the SWEs and were considered potentially adverse seismic conditions requiring further evaluation. It is important to note that some SWEL components or Area Waik-Bys may have multiple potentially adverse conditions that involve anchorage, spatial interaction, or other adverse concerns. Twenty-two (22) of the 32 observations requiring further review involved potential anchorage concerns; six involved potential seismic spatial interaction concerns; two involved other potential adverse concerns; and two involved spray/flooding hazards. Twenty-two (.22) of the 32 potentially adverse conditions were determined to meet the current seismic licensing basis. Ten (10) items could not be readily resolved per the Licensing Basis Evaluation process and were entered into the CAP. All 32 Licensing Basis Evaluation items are discussed in Section 5 and Appendix D, which includes additional information on the current status of potentially non-conforming conditions.

Summaries of Seismic Walkdown observations follow:

Potentially Adverse Anchorage Conditions While inspecting anchorages for SWEL equipment and in-scope Area Walk-By equipment, the SWT noted 22 cases where as-installed configurations could not be verified by the PVNGS documentation WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 4-4 brought in the field (drawings, SDOCs, and calculations). Discrepancies included: exceeded bolt projection lengths, varying equipment pad thicknesses for mechanical components, varying weld patterns for electrical equipment, and varying anchorage spacing. Detailed descriptions of these discrepancies are also indicated in Appendix D. To a limited extent, Field Change Requests (FCRs) and Non-Conformance Reports (NCRs) associated with the anchorage documentation that could verify the as-installed configurations were reviewed as part of Licensing Basis Evaluations.

One potentially degraded anchorage condition was noted for the Auxiliary Feedwater Pump "A" (2MAFP01) for which the SWT observed a sheared-off anchor bolt. PVNGS Engineering informed the SWT that this condition was previously analyzed. The SWT noted the observation as potentially adverse and was provided with documentation indicating the sheared-off bolt was acceptable as shown in the Licensing Basis Evaluation.

The SWT observed no indications of reinforcement yielding and no signs of excessive corrosion for in-scope safety-related equipment. All cracks observed were noted to be hairline or small cracks (less than 0.03 inch) as defined in EPRI NP-6041-SL (Reference 47).

Potentially Adverse Seismic Spatial Interactions In general, the SWT noted adequate clearances around safety-related equipment and sufficient anchorages of potential safety-related equipment impact hazards including transient materials. Potential exceptions included the auxiliary relay cabinets in Room A-202 of the Auxiliary Building and the bookcase south of the main control boards outside the Control Room horseshoe on the 140 ft elevation of the Control Building. The auxiliary relay cabinets were noted to be close to concrete walls and the bookcase was noted to have potentially weak anchorage that could allow overturning and impact with a main control board cabinet. Both concerns were documented for further review under Licensing Basis Evaluations.

The SWT inspected overhead piping and distribution systems including cable trays and found them well-anchored and ruggedly supported throughout the unit. Large fire extinguishers on small hooks that could possibly uplift and fall were found throughout the unit, but no safety-related equipment items were within fire extinguisher zone of influence. Overhead lighting was also noted to be rugged in all areas with sensitive equipment, particularly the Control Building. Where equipment is less sensitive to impact, several instances of lighting fixtures supported by S-hooks with disengaged or missing setscrews were observed. The SWT judged all cases not to be hazardous to safety-related equipment, but the conditions were noted and documented in the CAP.

Attached lines and piping to SWEL equipment were inspected and concluded to have adequate flexibility.

As noted in Section 4.2, all SWEL components and Area Walk-By equipment within the zone of influence of masonry block walls were evaluated prior to walkdowns not to be impact hazards due to collapse per existing calculations. No seismic spatial interaction hazards due to differential movement between the equipment and the masonry block walls were observed during the walkdowns.

All scaffolding encountered by the SWT was found to be adequately braced and anchored in addition to having sufficient clearances to safety-related equipment in accordance with station procedures.

No adverse seismic conditions pertaining to housekeeping were identified. Non-seismic housekeeping issues found in violation of housekeeping procedure (Reference 56) were entered into the CAP.

Detailed descriptions of all potentially adverse seismic spatial interaction concerns are provided in Appendix D.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 4-5 Other Potentially Adverse Seismic Conditions The SWT observed a loose cabinet door on Reactor Trip Breaker "A" (2JSBAC03). Operations opened the door and confirmed that the door was on a separate enclosure from the breaker and, therefore, there was no interaction hazard. The condition was noted and entered into the CAP.

For load center 2EPGBL32, inspected during refueling outage 2R17, the SWT noted 50G Ground Fault Relay L32D4 with 1 out of 4 door-mounting bolts not installed. Ongoing maintenance was being performed on the equipment as part of the electrical bus outage. Given that the Unit was in outage and the equipment was serving no Tech-Spec related function at the time, no adverse seismic condition was recorded. PVNGS generated Palo Verde Action Request (PVAR) 4267409, which documents that fasteners had been restored and there is no current non-conforming condition.

During the Area Walk-By for Room J- 114 in the Control Building, the SWT observed an apparent modification to the DC Equipment Room "B" emergency air handling unit (AHU, 2MHJBZ04) where a P1000 Unistrut member was welded to the AHU to support a non-quality related (NQR) component.

Verification is required to determine whether the modification reconciled the configuration in a manner that preserves the individual AHU seismic qualification. This observation was reviewed during the related Licensing Basis Evaluations, see Section 5 and Appendix D. The SWT did not note any other degraded conditions, missing equipment fasteners, or irregular mountings on equipment.

Potential Flooding/Spray Hazards The SWT was cognizant of potential spray and flooding hazards, particularly from threaded fire piping.

Overhead fire piping was generally found to be welded and ruggedly supported (no rod hung piping) at short and regular intervals. Areas that had threaded piping were generally confirmed to be pre-activated and therefore normally dry. During the Area Walk-By for Room J-A02 on the 74 ft elevation of the Control Building, the SWT noted threaded piping passing through an area without fire suppression. In addition, Room C-A09 was observed to also have threaded fire piping that could not be verified as pre-activated. Since the SWT could not verify the threaded piping sections as dry, the team marked the conditions to be further reviewed under Licensing Basis Evaluations, see Section 5 and Appendix D.

Potential Seismically Induced Fire interactions No potential seismically induced fire interactions were noted for Unit 2 by the SWT. This included no observations of hazardous/flammable material stored in inadequately anchored drums, inadequately anchored shelves, or unlocked cabinets; and no adverse natural gas or hydrogen lines. Hydrogen and oxygen tanks were noted during the Area Walk-By for the 120 ft elevation of the Auxiliary Building in Room A-204. The bottles were adequately secured with no potential impact hazards from adjacent or overhead equipment. Accordingly, no seismically induced fire hazards were noted.

Non-NTTF 2.3 Related Observations The SWT (including PVNGS Operator and Engineering SWEs) were also cognizant of issues not necessarily pertaining to the seismic qualification of safety-related equipment. The SWT noted conditions such as:

• Broken/missing fasteners

• Missing or partially-engaged set-screws on pendant lighting S-hooks

• Broken plastic alarm window

• Battery sample caps not installed WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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• Door hinge pins not fully-engaged

• General housekeeping issues such as:

o Loose ladder restraint o Unsecured cart o Loose insulation band-it o Hose-reel station missing exclusion area marking Non-NTTF 2.3 observations were recorded on the SWCs/AWCs and entered into the PVNGS CAP.

Many of these conditions were also corrected on-the-spot by the operations member of the SWT. None of these observations (by definition) represented potentially adverse seismic conditions - fasteners were located on non-seismic components; lighting and loose or unsecured items were not within the zone of influence of any soft targets.

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5. LICENSING BASIS EVALUATIONS The 32 potentially adverse seismic conditions identified in either the equipment Seismic Walkdowns or the Area Walk-Bys as discussed in Section 4 were evaluated with respect to their seismic licensing basis.

As indicated in Section 4.3, 22 of the 32 items requiring further review involved potential anchorage concerns; six involved potential seismic spatial interaction concerns; two involved other potential adverse concerns; and two involved spray/flooding hazards. These potentially adverse conditions are included in Appendix D, along with their dispositions. Twenty-two (22) of the 32 potentially adverse conditions were determined to meet their seismic licensing basis. The ten potentially adverse seismic conditions that could not readily be shown to meet the current seismic licensing basis were entered into the site's CAP.

For each of the items that fell into this category, the PVAR number is included in the disposition text, which is shown in Appendix D. Additional information pertaining to the current resolution and Operability Determinations/Functional Assessments of these items is included in Appendix D.

General methodologies adopted by the Licensing Basis Reviewers listed in Section 2.3 for addressing the observations noted in Section 4 are summarized in the following subsections.

Evaluations of Potentially Adverse Anchorage Conditions For the anchorage observations noted in Section 4 that involved discrepancies between the as-installed configurations and the anchorage documentation (drawings, SDOCs, and calculations) taken into the field, the Licensing Basis Reviewers collected and reviewed FCRs and NCRs for updates to the field documents that represent the Current Licensing Basis (CLB). Thirteen (13) as-installed anchorage configurations were determined to meet their seismic licensing basis. Nine (9) as-installed anchorage configurations for SWEL components 2EPHAM31, 2EPKDM44, 2EPNAV25, 2JHCAPT0351A, 2JHCAPT0352A, 2JHCCPT0351C, 2JHCCPT0352C, 2MECAT01, and 2MEWAP01 could not be readily shown to reflect CLB documentation, and therefore were entered into the CAP and indicated as potentially non-conforming conditions by the listing of "No" under Question 5 of the SWCs.

Information was provided by PVNGS Engineering that showed the Auxiliary Feedwater Pump "A" anchorage noted to have an anchor bolt sheared-off was analyzed and determined to be acceptable as-installed per Calculation 13-CC-ZQ-MOI (Reference 52) and entered into the Non-Conformance process NCR CC-4087 during construction of Unit 2.

Evaluations of Potentially Adverse Seismic Spatial Interactions Observations involving the possibility of insufficient clearances between safety-related components were generally resolved by estimating relative displacement from the in-structure response spectra of Reference

53. Given equipment anchorage and spatial configuration, the Licensing Basis Reviewers determined lower-bound estimates of component frequencies. These frequency estimates along with the appropriate damping values from UFSAR Table 3.7-1 (Reference 32) were used to obtain spectral accelerations.

Component displacement was then estimated by the following formula (Reference 63):

i S0

• 386.4 S

d=SF* (co *21r)2 Where SF = modal shape factor (1.6 for cantilever)

S,, = spectral acceleration (g) from response spectra

0) = fundamental frequency (Hz)

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 5-2 If the combinations of component displacements under SSE loadings did not exceed the gap noted in the walkdown, the gap was noted as sufficient to preclude impact.

In some instances, licensing basis evaluations of potential spatial interactions were resolved by inspection of installation details and existing analyses. This disposition method was applied for the Auxiliary Relay Cabinets located 3/8-inch from concrete walls. The Licensing Basis Reviewers located EQCF D95-0038 (Reference 65), which indicates that the auxiliary relay cabinets were analyzed by finite element methodology and determined to be rigid. Therefore, the 3/8-inch as-built gap was noted as sufficient.

In other instances, licensing basis evaluations of potential spatial interactions were resolved by generating new analyses that confirmed anchorage strength was adequate to prevent overturning. For example, the Unit 2 bookcase south of the Control Room was evaluated by estimating the tensile demand on existing screws fastened to the metal stud wall. These forces were evaluated by the Licensing Basis Reviewers and determined to be adequately low to preclude failure and overturning.

All of the potential spatial interaction concerns were determined to meet their seismic licensing basis.

Evaluations of Other Potentially Adverse Seismic Conditions The SWT observed a loose cabinet door on Reactor Trip Breaker "A" (2JSBAC03). Operations opened the door and confirmed that the door was on a separate enclosure from the breaker and, therefore, there was no interaction hazard. The condition was noted and entered into the CAP.

The apparent modification to the DC Equipment Room "B" Emergency AHU (2MHJBZ04; refer to the Area Walk-By for Room J-1 14 in the Control Building) could not be readily shown through documentation to reconcile the individual equipment seismic qualification, and therefore was entered into the CAP and indicated as a potentially non-conforming condition by the listing as a "No" under Question 8 of the AWC.

Evaluations of Potential Flooding/Spray Hazards Potential flooding/spray hazards noted during the walkdown were evaluated by further documentation review. For potentially wet threaded fire piping, the Licensing Basis Reviewers reviewed documentation from piping and instrumentation diagrams (P&IDs) to verify the presence of pre-activation valves upstream of the piping that could potentially rupture and pose a hazard to equipment. The subject fire piping was verified to be pre-activated, and therefore dry. Hence, there are no potential flooding and or spray hazards.

Evaluations of Potential Seismically Induced Fire Interactions No potential seismically induced fire interactions were noted for Unit 2 by the SWT; therefore, there are no Licensing Basis Evaluations.

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6. PEER REVIEW 6.1 Introduction This section documents the independent peer review for the Near-Term Task Force (NTTF)

Recommendation 2.3 Seismic Walkdowns that were performed for Unit 2 of Palo Verde Nuclear Generating Station (PVNGS). 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)

• Observation of actual SWE Seismic Walkdowns on July 25, 2012, by the peer reviewers

• Review of a sample of the checklists prepared for the Seismic Walkdowns and Area Walk-Bys

• Review of the licensing basis evaluations

• Review of the decisions for entering the potentially adverse conditions into the plant's Corrective Action Program (CAP)

• Review of the final and supplement submittal reports The peer reviewers for Unit 2 are Messrs. Walter Djordjevic of S&A and Gary L Douglas of Westinghouse. In addition, Messrs. Chris Wandell and Winston Borrero also participated and contributed to the peer review. Mr. Djordjevic is designated the peer review Team Leader and participated in all peer review activities as the seismic subject matter expert. Mr. Douglas participated in all peer review activities and led the SWEL selection peer review as the SWEL selection subject matter expert. Neither peer reviewer was involved in the Seismic Walkdown inspection process. Mr. Djordjevic is an advanced degree structural engineer with over 30 years of nuclear seismic experience. He has received Seismic Capability Engineer (EPRI SQUG training), EPRI IPEEE Add-on, Seismic Fragility, and Seismic Walkdown Engineer (SWE) training. Mr. Douglas is a nuclear engineer with 15 years of nuclear engineering experience and 10 years of aerospace engineering experience. Resumes are provided in Appendix E.

The peer review of the SWEL development began on July 14, 2012, and was completed on August 8, 2012. All findings noted on the SWEL Peer Review Checklist were resolved. The completed SWEL Peer Review Checklist is found in Appendix C. The results of the SWEL development peer review are discussed in Section 6.2.

The peer review of the Seismic Walkdown activities started on July 25, 2012, with a peer check of the actual walkdowns. Messrs. Djordjevic and Douglas joined the walkdown team for a portion of the day's planned walkdowns to observe the conduct of walkdowns and adherence to the Seismic Walkdown Guidance (SWG) (Reference 1). Messrs. C. Wandell and W. Borrero also participated in the actual walkdowns to monitor compliance with the SWG (Reference 1). In addition, an interview was conducted by Messrs. Djordjevic and Douglas with the SWE inspection team on August 17, 2012, after review of a sample of the Seismic Walkdown Checklists (SWCs) and Area Walk-By Checklists (AWCs) to ascertain the quality and compliance with the SWG. An additional interview was conducted by Messrs. Djordjevic and Douglas with Mr. Hunter A. Young on May 29, 2013, to review the SWCs and AWCs completed during the follow-on walkdowns. The discussion of the results of these sample SWC and AWC reviews are provided in Section 6.3.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 6-2 The results of the peer review of licensing basis evaluations are provided in Section 6.4. These results were also discussed with the SWE inspection team on August 17, 2012, and May 29, 2013. The peer reviewers reviewed the 32 licensing basis evaluations and found the final determinations made by the SWEs to be correctly performed, and also concurred with the conclusions for the 10 items that were not readily determined to meet current licensing basis, which were placed in the corrective action program.

6.2 PEER REVIEW - SELECTION OF SSCs 6.2.1 Purpose The purpose of this section is to describe the process used to perform the peer review of the selected SSCs that were included in the SWEL.

6.2.2 Peer Review Activity - Selection of SSCs The guidance in EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resohltion of Fukushima Near-Term Task Force Recommendation 2.3: Seismic (Reference 1 ), Section 3: Selection of SSCs was used as the basis for this review.

This peer review was also based on reviews of the spreadsheets utilized by the SWEL developers to generate the Base Lists and Seismic Walkdown Equipment Lists.

Peer review was also based on interviews with the following individuals who were directly responsible for development of the SWEL:

o Rolando Perez (Westinghouse) o Derek Seaman (Westinghouse) o Chris Wandell (Palo Verde Engineering) o Winston Borrero (Palo Verde Engineering)

This peer review utilized the Seismic Walkdown Guidance checklist shown in Reference I Appendix F:

Checklist for Peer Review of SSC Selection.

For SWEL I development, the following actions were completed in the peer review process:

Verification that the SSCs selected represented a diverse sample of the equipment required to perform the following five safety functions:

o Reactivity Control (RC) o Reactor Coolant Pressure Control (PC) o Reactor Coolant Inventory Control (IC) o Decay Heat Removal (DHR); Ultimate Heat Sink (UHS) o Containment Function (CF)

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 6-3 Verification that the SSCs selected include an appropriate representation of items having the following sample selection attributes:

o Various types of systems o Major new and replacement equipment o Various types of equipment o Various environments o Equipment enhanced based on the findings of the IPEEE program o Risk insight consideration For SWEL 2 development, the following actions were completed in the peer review process:

Verification that spent fuel pool related items were considered and appropriately added to SWEL 2.

Verification that appropriate justification was documented for spent fuel pool related items that were not included in SWEL 2.

6.2.3 Peer Review Findings - Selection of SSCs This peer review found that the process for selecting SSCs that were added to the SWEL complied with the process outlined in Reference 1, Section 3: Selection of SSCs. SWEL 1 selections totaled 124 items and SWEL 2 selections totaled six items.

The peer reviewers verified that the SSCs selected represented a diverse sample of the equipment required to perform the five safety functions. The bases for items selected to SWEL I were the IPEEE Report, Appendix 3.2 (Reference 3), which listed safe shutdown equipment from each redundant train of the systems supporting the five safety functions, and Seismic Category I items from the Seismic Probabilistic Risk Assessment (SPRA) database. A breakdown of the safety functions represented by the SWEL 1 selections follows:

Reactivity control - 39 SWEL selections support this function Pressure control - 84 SWEL selections support this function Inventory control - 56 SWEL selections support this function Decay heat removal/ultimate heat sink - 92 SWEL selections support this function Containment function - 22 SWEL selections support this function The peer reviewers verified that the SSCs selected to SWEL 1 include an appropriate representation of items having the required sample selection attributes. A breakdown of the sample selection attributes represented by the SWEL I selections follows:

Twenty-seven (27) of 31 Base List systems were represented in the SWEL 1 list. Components from the unrepresented systems were component types that were adequately represented by other system selections. Since all five safety functions are also adequately represented by the SWEL, the peer review team concluded that the "various types of systems" sample selection attribute was satisfactorily represented.

Nine (9) of 38 major new or replacement items were represented in the SWEL 1 list. The sources for these items were Design Basis Manuals for the systems supporting the five safety functions.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 6-4 Several of the new or replacement items involved a change to a group of similar items, and at least one item was selected from each group to represent the change. The peer review team

.concluded that the "'major new and replacement equipment" sample selection attribute was satisfactorily represented. During review of the submittal report, a revision to the SWEL was needed to correct an error to this sample consideration attribute in the spreadsheet that was used to track and implement the SWEL selection process. This error did not result in a change to the Base List or SWEL selections; it decreased the number of major new or replacement items represented in the SWEL 1 list. The peer reviewers verified that the Seismic Walkdown Guidance requirements for this sample consideration attribute were maintained.

Twenty (20) of 22 types of equipment were represented in the SWEL I list. The equipment types not represented were "compressors" and "motor-generator sets." The site does not have safety-related equipment in these equipment types. Equipment type "transformer" is a subcomponent to equipment type "switchgear." The peer review team concluded that the "various types of equipment" sample selection attribute was satisfactorily represented.

All environments were represented in the SWEL 1 list. The PVNGS Units are located in a dry environment; therefore, environment classification was based on the maximum design temperature of the equipment rooms. Since at least one item was selected from each environment classification, the peer review team concluded that the "various environments" sample selection attribute was satisfactorily represented.

No items were added to the SWEL 1 list based on findings of the IPEEE program because no equipment enhancements were required in Unit 2.

Thirty-five (35) of seventy (70) risk-significant items were represented in the SWEL list. Risk insights were applied from the Seismic PRA and Internal Events models to the selection of items to the SWEL. The peer review team concluded that the "risk insights" sample selection attribute was satisfactorily represented.

The peer reviewers verified that spent fuel pool related items were considered and appropriately added to SWEL 2.

Spent fuel pool related items considered were based on a review of design basis manual descriptions, piping and instrumentation drawings, isometric drawings, and a system review using the Site Work Management System (SWMS). All items that screened into Base List 2 were selected to SWEL 2.

The peer reviewers verified that appropriate justification was documented for spent fuel pool related items that were not included in SWEL 2.

The justification for screening out spent fuel pool related items was reviewed and found to be supported by the Seismic Walkdown Guidance (Reference 1). Components in-line with Seismic Category I piping were screened out. No rapid drain-down items were included in SWEL 2. This conclusion was supported by a review of the UFSAR (Reference 32), which determined that all pipe penetrations through the pool wall are at or above the minimum required water level of 10 ft above top of fuel assemblies. All pipes extending down into the pool have siphon breaker holes that are at or above the minimum required water level of 10 ft above top of fuel assemblies. All items that screened in to Base List 2 were selected to SWEL 2; therefore, the peer review team concluded that appropriate justification was documented.

The completed peer review checklist in Appendix C documents the peer review results.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 6-5 The SWEL was revised during the follow-on walkdowns to remove components JCHAUV0516 and 2MCHEE0I, and to replace ten (10) protected Train A components with corresponding Train B components which were readily accessible. This change reduced the number of SWEL 1 items from 126 to 124. The components were removed because they were located in a locked high-radiation area. It was not necessary to replace JCHAUV0516 and 2MCHEE01with similar equipment types since the sampling selection attributes remained adequately represented by multiple items on the SWEL. The replacement of Train A components with corresponding Train B components is acceptable per the guidance requirements. The Peer Review Team reviewed these SWEL changes and verified that all sampling selection attributes remained adequately represented on the SWEL.

6.2.4 Resolution of Peer Review Comments - Selection of SSCs The peer review comments documented in the peer review checklist in Appendix C were resolved in a timely manner and improved the Seismic Walkdown process as summarized in the following:

• Editorial corrections were made to the SWEL report to correct minor errors; this provided for a complete and accurate report.

• Notations were added to the SWEL report to explain the sources of information that supported the SWEL selections based on modifications, IPEEE enhancements, and recent upgrades/changes; this provided for a complete and accurate report.

" Notation was added to the SWEL report to explain why equipment type "transformer" was not directly represented on the SWEL; this provided for sample selection clarity in the report.

• A column was added to the SWEL report to indicate inside/outside environments; this provided for sample selection clarity in the report.

• Notation was added to the SWEL report to explain the sources of information that supported the SWEL 2 selections; this provided for clarity in the report.

" Notation was added to the SWEL report to explain how component identifications for Unit 1, 2, and 3 were reconciled and action was taken to perform a review to identify unit-to-unit differences; this provided for a complete and accurate report carried forward to the other units.

6.2.5 Conclusion of Peer Review - Selection of SSCs This peer review concluded that the process for selecting SSCs to be included in the Seismic Walkdown equipment list complied with the process outlined in Reference 1, Section 3: Selection of SSCs. It is further concluded that the SWEL sufficiently represents a variety of the required sampling of plant Seismic Category I safe shutdown equipment to meet the objectives of the NRC 50.54(0 Letter (Reference 50).

6.3 Peer Review of Sample Seismic Walkdown and Area Walk-by Checklists A site visit was made on July 25, 2012, by Messrs. Walter Djordjevic and Mr. Gary L. Douglas to perform the peer review of the Seismic Walkdowns. The SWC and AWC reviews (July 25 and 26, 2012) were performed on a sampling of the checklists that were available at that time. In accordance with the SWG requirements, the peer reviewers performed a final review of the SWC and AWC samples on August 17, 2012, after which the SWEs (Messrs. Hunter A. Young and Cory T. Figliolini) were interviewed regarding their entries on the checklists to ensure they met the SWG requirements. An WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 6-6 additional interview was conducted by Messrs. Djordjevic and Douglas with Mr. Hunter A. Young in accordance with the SWG requirements on May 29, 2013.

The peer reviewers noted four observations of industry good practice during the Seismic Walkdown peer review:

1. Visible exclusion areas employed around selected equipment

2. Engineered scaffolding

3. Comprehensive pre-job briefs by the SWT prior to entering each room

4. Comprehensive daily pre-job and post-job briefs by the walkdown management team Table 6-1 lists the SWC and AWC samples, which represent 20% of the SWC and 20% of the AWC populations, respectively. The sample includes the equipment inspected by the peer reviewers on July 25, 2012, while observing the Seismic Walkdowns and equipment items from other classes to introduce diversity into the sampling.

Table 6-1: SWC and AWC Peer Review Samples from Seismic Walkdown Inspection for Unit 2 Equipment Equipment Walkdown Item Observations Identification (GIP) Class 2MHFAJ01 10 Air Handlers Bolt schedule was used to verify anchorage type.

2MHFBJ01 10 Air Handlers Bolt schedule was used to verify anchorage type.

2MPCAE01 21 Tanks and HX No comment 2MPCBE01 21 Tanks and HX No comment 2MPCAPO1 5 HOR. Pump No comment 2MPCBP01 5 HOR. Pump No comment 2MCHET01 21 Tanks and HX/RWT No comment 2JSAAUVO664 8 MOV No comment 2JSIAHV0684 8 MOV No comment 2MSIAP03 6 Vert. Pump No comment 2MSIAP02 5 HOR. Pump No comment 2JSIAHV0604 8 MOV No comment 2JSIAUV0666 8 MOV No comment 2MHAAZO1 10 Air Handlers No comment 2MHAAZO2 10 Air Handlers No comment 2MECAE01 11 Chiller No comment 2EPHAM31 1 MCC No comment 2EPGAL35 2 LV SWGR Question with clearance between the WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 6-7 switchgear housing and an adjacent cable tray is correctly dispositioned.

2MJAJ01A 9 Fans No comment 2EPKAF11 15 Battery Racks No comment 2EPKAH11 16 Battery Charger A Used SDOC E051-00047 to verify anchorage 2EPNAN11 16 DCA Inverter A Used SDOC E054-00070 to verify anchorage 2EPGBL32 2 LV SWGR Question with clearance between the switchgear housing and an adjacent cable tray is correctly dispositioned.

Assessment of 50G Ground Fault Relay based on discussion with APS staff is correctly dispositioned.

2JSINPT391 18 Instruments on Racks Anchorage configuration verified.

2EPHBM32 1 Motor Control Centers Assessment of loose bolts based on discussion with APS staff is correctly dispositioned.

2EPBBS04 3 MVSWGR No comment 2EPKDD24 14 Distribution Panel No comment 2JCHAHV0205 7 Fluid-Operated Valves No comment Area Walkdown Description Observations Area: Yard No comment Area: Aux, 40, A-D05 No comment Area: AUX, 52, A-C05 No comment Area: Aux, 40, A-D07 No comment AWC: Fuel Bldg, F-103 No comment AWC: Fuel Bldg, F-101 No comment Area: AUX, 52, A-C04 No comment Area: AUX, 100, A-127 Questions with clearance between the relay cabinets and concrete walls, flexibly supported lighting, and S-hook fixtures are correctly dispositioned.

Area: CTRL, 100, J-114 Question on seismic qualification of 2MHJBZ04 is correctly dispositioned.

Area: CTMT, 100, Area N of No comment Transfer Canal Area: CTMT, 100, SIT 1A Proximity No comment WCAP- 17680-NP, Supplement I Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 6-8 Area: CTMT, 100, W Regen HX No comment CTRL Valve Access Area: CTMT, 150, Pressurizer Cube No comment The peer reviewers provided an observation to the SWEs based on the Seismic Walkdowns and review of the checklists. Some immediate remedies such as relocating temporary equipment in close proximity to SWEL equipment (or other equipment in the area) to a benign location were performed during the walkdowns when they were discovered. The peer reviewers made it clear that the "as-found" state determines the final status (Yes or No) of the SWC or AWC assessment in the submittal report. Even when the corrective action has already been accomplished, it should be documented via the PVAR process at PVNGS for both reporting and trending purposes.

6.4 Review of Licensing Basis Evaluations Appendix D provides a list of the potentially adverse seismic conditions identified during the Unit 2 Seismic Walkdowns and Area Walk-Bys and how they were addressed. If a PVAR was generated, it is referenced in Appendix D. Messrs. Djordjevic and Douglas conducted an interview with the SWE inspection team on August 17, 2012, to discuss the issues identified to determine if, in the opinion of the peer reviewers, any of them potentially challenged the current licensing basis of the plant.

As noted in Section 5, there were 32 potentially adverse seismic conditions identified in either the equipment Seismic Walkdowns or the Area Walk-Bys requiring evaluation with respect to their seismic licensing basis. Not all potentially adverse conditions were resolved. The peer reviewers performed a review of all licensing basis evaluations and the walkdown team's decisions for entering these potentially adverse seismic conditions into the plant's CAP. Twenty-two (22) of the licensing basis evaluations I determined that the potentially adverse conditions were ultimately found to be in compliance with the current licensing basis. Of the remaining 10 potentially adverse seismic conditions that were entered into I the plant's CAP, 9 involved follow-up verification of the as-built anchorage configuration with plant documentation and 1 involved a follow-up verification of individual equipment seismic qualification. The peer reviews of Sections 4.3 and 5, and Appendix D led the peer reviewers to conclude that the licensing basis evaluations carefully compared the actual as-found plant configurations to the current licensing basis documentation in order to assess configuration compliance with the Palo Verde design basis, and the decisions for entering conditions into the plant's CAP complied with the expectations of the SWG.

The peer reviewers performed a review of the status of items that were entered into the plant's CAP as a result of the Seismic Walkdowns (see Table 6-2). The submittal report was found to appropriately reflect these updates.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page 6-9 Table 6-2 Table of CAP Status from Seismic Walkdown Inspection CAP Item CAP Status PVAR 4214832 Bookcases in the zone of influence of the main Action completed. Bookcases control boards removed in all three units.

PVAR 4220252 2EPHAM31 anchorage configuration could not be As-found configuration will be readily verified against CLB documentation documented on EDC 2013-00455.

PVAR 4220252 2EPKDM44 anchorage configuration could not be As-found condition meets CLB as readily verified against CLB documentation evaluated in NCR EJ-02396.

PVAR 4267409 2EPGBL32 Ground Fault Relay missing fastener Action completed. Fastener replaced.

PVAR 4275113 2EPNAV25 anchorage configuration could not be As-found configuration will be readily verified against CLB documentation documented on EDC 2013-00455.

PVAR 4275113 2JHCAPT0351A / 2JHCAPT0352A / 2JHCCPT0351C As-found configuration will be

/2JHCCPT0352C anchorage configuration could not documented on EDC 2013-00455.

be readily verified against CLB documentation PVAR 4215794 2JSBAC03 Noted loose cabinet door Action completed. Door adjusted.

PVAR 4275113 2MECATO1 anchorage configuration could not be As-found condition meets CLB as readily verified against CLB documentation evaluated in NCR M J-00520.

PVAR 4275113 2MEWAPO1 anchorage configuration could not be As-found condition meets CLB as readily verified against CLB documentation evaluated per drawing 13-C-ZAS-0241.

PVAR 4275113 Verify whether unistrut welded to 2MHJBZ04 As-found configuration will be reconciles with original seismic qualification documented on EDC 2013-00455.

6.5 Review Submittal Report The entire final submittal report has been reviewed by Messrs. W. Djordjevic and G. Douglas and found to meet the requirements of TR-1025286 - Seismic Walkdown Guidance (Reference 1). The supplement submittal report has been reviewed by Messrs. W. Djordjevic and G. L. Douglas and found to meet the requirements of TR-1025286 - Seismic Walkdown Guidance (Reference 1).

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7. IPEEE VULNERABILITIES A summary of IPEEE vulnerabilities is available in Palo Verde Nuclear Generating Station Individual Plant Examination of External Events report (Reference 3). Per Reference 3, no seismic vulnerabilities were determined to exist at PVNGS-2 and no significant changes to plant design were required in order to demonstrate the ability to mitigate the Review Level Earthquake (RLE). All observations identified from the IPEEE walkdowns were resolved prior to issuing of the IPEEE report on June 1, 1995.

Table 4-1 of PVNGS CORR 94-001-506 (Reference 62) had documented items to review for the Seismic IPEEE prescreening and walkdown of all three units; and Table 3-4 of Reference 3 summarized the resolution of these original walkdown concerns. The IPEEE report (Reference 3) concluded that all components have capacities exceeding the 0.3g peak ground acceleration of the RLE. However, action was taken to improve the seismic capacity of the bookcases located behind the control cabinets in the Unit 3 Control Room. The existing anchorage was determined to be marginal, and additional anchorage was provided prior to issuing of the IPEEE report to resolve the concern. While the condition was also noted for the same bookcases in Unit 2 per Reference 62, the IPEEE report did not specify action to provide additional anchorage for these bookcases.

As noted in Section 4.2, the SWT reviewed the IPEEE report prior to conducting walkdowns. Similar observations noted in the IPEEE report regarding the Control Room bookcases were also noted for review during these walkdowns. The SWT reviewed Detail 35 of 13-A-ZYD-0034 (Reference 57), which specifies 23 metal screws fastening the bookcases in all three units to the metal stud wall. The SWT and licensing basis reviewers determined that, although the as-installed anchorage for the Unit 2 bookcase did not comply with this detail, the demand forces were adequately low to preclude failure; therefore, no adverse spatial interaction was identified. As a result of this observation, PVAR 4214832 was generated and PVNGS removed these bookcases from the zone of influence of the main control boards in all three units.

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8. REFERENCES

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

2. Drawing 13-I-ZZI-0001.R01 1, "Site Work Management System (SWMS) Equipment Database."

3. CORR 102-03407, "Palo Verde Nuclear Generating Station - IPEEE."

4. Design Basis Manual DBM AF, "Auxiliary Feedwater System," Revision 22.

5. Design Basis Manual DBM CH, "Chemical and Volume Control System," Revision 21.

6. Design Basis Manual DBM DF/DG/PE, "Diesel Generator, Class IE Standby Generation, Fuel Oil Storage and Transfer System," Revision 23.

7. Design Basis Manual DBM EC, "Essential Chilled Water System," Revision 13.

8. Design Basis Manual DBM EW, "Essential Cooling Water System," Revision 23.

9. Design Basis Manual DBM FW, "Feedwater System," Revision 13.

10. Design Basis Manual DBM HA, "Auxiliary Building HVAC System," Revision 17.

11. Design Basis Manual DBM HC, "Containment Building HVAC System," Revision 9.

12. Design Basis Manual DBM HD, "HVAC - Diesel Generator Building," Revision 12.

13. Design Basis Manual DBM HP, "Containment Hydrogen Control System," Revision 13.

14. Design Basis Manual DBM MA, "Main Generation System," Revision 8.

15. Design Basis Manual DBM NA, "13.8 kV AC Non-Class IE Power System," Revision 10.

16. Design Basis Manual DBM NC, "Nuclear Cooling Water System," Revision 19.

17. Design Basis Manual DBM NE, "Station Blackout Topical," Revision 18.

18. Design Basis Manual DBM PB, "Class IE 4.16 kV Power System," Revision 13.

19. Design Basis Manual DBM PG, "Class IE 480 VAC Power Switchgear System," Revision 11.

20. Design Basis Manual DBM PH, "Class 1E 480V Power - MCC," Revision 11.

21. Design Basis Manual DBM PK, "Class 1E 125 VDC Power System," Revision 17.

22. Design Basis Manual DBM PN, "Class 1E Instrument AC Power System," Revision 10.

23. Design Basis Manual DBM QD, "Emergency Lighting System," Revision 10.

24. Design Basis Manual DBM RC, "Reactor Coolant System," Revision 29.

25. Design Basis Manual DBM SA, "Engineered Safety Features Actuation System," Revision 16.

26. Design Basis Manual DBM SB, "Reactor Protection System," Revision 18.

27. Design Basis Manual DBM SF-FWCS, "Feedwater Control System," Revision 6.

28. Design Basis Manual DBM SF-SBCS, "Steam Bypass Control System," Revision 6.

29. Design Basis Manual DBM SG, "Main Steam," Revision 31.

30. Design Basis Manual DBM SI, "Safety Injection System," Revision 33.

31. Equipment Qualification (EQ) Files EQDF EQ-PM, Equipment Qualification Program Manual, Revision 21.

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32. Palo Verde Nuclear Generating Station Units 1, 2, and 3 Updated Final Safety Analysis Report, Revision 16B, August 2012.

33. Westinghouse Calculation CN-RAM-1 1-019, "Validation of Probabilistic Risk Assessment Model Conversion for Palo Verde Nuclear Generating Station," September 2012 (Westinghouse Proprietary Class 2).

34. Interim Version of the Westinghouse Seismic PRA Database (Microsoft Access database file "APS-SPRA.mdb," dated August 22, 2012).

35. Design Basis Manual DBM PC, "Fuel Pool Cooling and Cleanup System," Revision 18.

36. Drawing Number 01-M-PCP-0001, "P & I Diagram., Fuel Pool Cooling and Cleanup System,"

Revision 27.

37. Drawing Number 0 1-P-PCF-0501, "Fuel Building Spent Fuel Pool Cooling and Cleanup System Isometric," Revision 4.

38. Drawing Number 01-P-PCF-0502, "Fuel Building Isometric Spent Fuel Pool Cooling and Cleanup System," Revision 2.

39. Drawing Number 01-P-PCF-0503, "Fuel Building Spent Fuel Pool Cooling and Cleanup System Isometric," Revision 0.

40. Drawing Number 01-P-PCF-0504, "Fuel Building Spent Fuel Pool Cooling and Cleanup System Isometric," Revision 0.

41. Institute of Electric and Electronic Engineers Standard IEEE 344-71, "Recommended Practice for Seismic Qualification of Class lE Equipment for Nuclear Power Generating Stations."

42. Design Criteria Manual DCM-PGD, "Project General Design Criteria," Revision 24.

43. Regulatory Guide 1.60, "Design Response Spectra for Seismic Design of Nuclear Power Plants,"

Revision 1, December 1973.

44. Regulatory Guide 1.61, "Damping Values for Seismic Design of Nuclear Power Plants,"

Revision 0, October 1973.

45. Regulatory Guide 1.29, "Seismic Design Classification," Revision 1, August 1973.

46. Institute of Electric and Electronic Engineers Standard IEEE 344-75, "Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations."

47. EPRI Report NP-6041-SL, "A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1)," Revision 1.

48. WCAP- 17680-NP, "Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2," Revision 0, November 2012.

49. Not used.

50. NRC Letter to All Power Reactor Licensees et al., "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident," Enclosure 3, "Recommendation 2.3: Seismic."

51. Bechtel Topical Report BC-TOP-4-A, Rev. 3, "Seismic Analysis of Structures and Equipment for Nuclear Power Plants," November 1974.

52. Calculation 13-CC-ZQ-MO 1, "Seismic Qualification Evaluation - Mechanical Equipment,"

Revision 8.

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53. Design Basis Manual DBM-C5, "Seismic Topical," Revision 4.

54. Procedure 30DP-9WP 11, "Scaffolding Instructions," Revision 24.

55. Specification 13-CN-0380, "Installation Specification for Seismic Cat IX and Non-Seismic Scaffolding," Revision 20.

56. Procedure 30DP-OWM 12, "Housekeeping," Revision 20.

57. Drawing 13-A-ZYD-0034, "Transient Material Restraint Details," Revision 20.

58. Calculation 13-CC-ZZ-0309, "Transient Material Analysis," Revision 5.

59. Drawing 13-E-ZAL-00 11, "Lighting Fixture Mounting," Revision 31.

60. Calculation 13-CC-ZJ-0120, "Concrete Block Walls," Revision 5.

61. Calculation 13-CC-ZA-0 140, "Hatches and Penetrations," Revision 7.

62. Correspondence 94-001-506, "Transmittal of Report Prescreening and Walkdown of PVNGS for Seismic IPEEE."

63. "Dynamics of Structures, Theory and Application to Earthquake Engineering," Anil K. Chopra, University of California at Berkeley.

64. Not used.

65. PVNGS Documents used for Anchorage Configuration Verification and Licensing Basis Evaluations

a. Calculation Number 13-CC-ZG-0070, "Diesel Generator Building Equipment Supports," Revision 6.

b. Calculation Number 13-CC-ZQ-EOO, "Seismic Qualification Evaluation - Electrical Equipment," Revision 5.

c. Calculation Number 13-CC-ZQ-JOO, "Seismic Qualification Evaluation - Control Equipment," Revision 6.

d. Calculation Number 13-CC-ZQ-M00 1, "Seismic Qualification Evaluation -

Mechanical Equipment," Revision 8.

e. Drawing Number 02-E-ZGL-000 1, "Diesel Generator Building Lighting and Communication Plans at El. 100'-0" and 115'-0"," Revision 6.

f. Drawing Number 02-M-FPP-0003, "P&I Diagram Fire Protection System," Revision 17.

g. Drawing Number 13-C-OOA-0001, "Civil-Structural Generator Notes," Revision 24.

h. Drawing Number 13-C-OOA-00 11, "Anchor Bolt Schedule and Details," Revision 9.

i. Drawing Number 13-C-SPS-0376, "Nuclear Service Spray Ponds Sections and Details Sht 1," Revision 11.

j. Drawing Number 13-C-ZAS-0240, "Auxiliary Building Equipment Foundation Details Sht 1," Revision 10.

k. Not used.

1. Drawing Number 13-C-ZAS-0241, "Auxiliary Building Equipment Foundation Details Sht 2," Revision 9.

m. Drawing Number 13-C-ZAS-0242, "Auxiliary Building Equipment Foundation Details Sht 3," Revision 11.

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n. Drawing Number 13-C-ZAS-0243, "Auxiliary Building Equipment Foundation Details Sht 4," Revision 13.

o. Drawing Number 13-C-ZAS-0245, "Auxiliary Building Equipment Foundation Details Sht 5," Revision 8.

p. Drawing Number 13-C-ZCS-0703, "MSSS Concrete Sections and Details," Revision 8.

q. Drawing Number 13-C-ZCS-0705, "MSSS Floor Inserts and Penetrations," Revision 20.

r. Drawing Number 13-C-ZFS-0187, "Fuel Building Concrete Sections & Details,"

Revision 11.

s. Drawing Number 13-C-ZGS-01 10, "Diesel Generator Building Diesel Generator Foundation Plan Sections and Details," Revision 5.

t. Drawing Number 13-C-ZGS-01 16, "Diesel Generator Building Concrete Section and Details Sht 2," Revision 7.

u. Drawing Number 13-C-ZJS-0102, "Control Building Area J1D Concrete and Steel Plans for El. 74' and 100'," Revision 10.

v. Drawing Number 13-C-ZJS-0580, "Control Building Misc Steel Platforms and Details Sht 1," Revision 6.

w. Drawing Number 13-E-ZAL-00 11, "Lighting Fixture Mounting Detail Sheet 1,"

Revision 32.

x. Drawing Number 13-J-O0D-0103, "Auxiliary Building Isometric HCA-PT-351A and HCA-PT-352A Sensing Lines," Revision 4.

y. Drawing Number 13-J-01D-0 104, "Sensing Lines for HCC-PT-351C and 352-C Auxiliary Building," Revision 3.

z. Drawing Number 13-J-01D-0 173, "MSSS Building Iso Sensing Line SGA-PT308, 315; SBG-PT301, 321," Revision 6.

aa. Drawing Number 13-J-04D-01 18, "MSSS ISO AFA-FT-40A and AFB-FT-41A Sensing Lines," Revision 2.

bb. Drawing Number 13-J-ZZS-0157, "Seismic Category I Instrument Mtg. Support for 12"W x 24"H Plate with Unistrut," Revision 6.

cc. EQCF Number D95-0038, "Restraints for Aux. Relay Cabinets."

dd. Field Change Request Number 7030C, "Essential Chiller Outline Drawings."

ee. Field Change Request Number 854 1C, "Control Building Area JIA & B."

ff. Log Number 13-10407-A216-12, "Wyle Job No. 44815 - Seismic Test of Compact Ceiling Light Module and an Incandescent Light Module," Revision A.

gg. SDOC Number E051-00047, "Qualification Report for Class 1E Battery Charger,"

Revision 10.

hh. SDOC Number E054-0070, "Class IE Inverter IEEE 323 and 324 Qualification Report," Revision 7.

ii. SDOC Number E 105-00011, "Outline Line Voltage Regulator 25KVA," Revision 17.

jj. SDOC Number EN050B-A00015, "General Arrangement 28-Cell Battery Rack Sht. 3,"

Revision 5.

kk. SDOC Number J601A-00274, "Nuclear Qualification Test Report for Modulating Atmospheric Dump Valve," Revision 0.

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11. SDOC Number M598-01433, "Mounting and Wiring Detail for Q Class HVAC Instruments," Revision 21.

mm. SDOC Number N001-0502-00322, "Bridge Assembly SFHM V-CE-14439, 3-22-81,"

Revision 4.

nn. Westinghouse Calculation CN-RAM-12-015, "Palo Verde Seismic Probabilistic Risk Assessment - Model Development," November 2012 (Westinghouse Proprietary Class 2).

oo. Westinghouse Calculation CN-RAM- 12-022, "Palo Verde Seismic Probabilistic Risk Assessment - Quantification," December 2012 (Westinghouse Proprietary Class 2).

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page C- I APPENDIX C - PEER REVIEW CHECKLISTS There was no change to this appendix. The SWEL Peer Review Checklist can be found in Appendix C of Reference 48 ("Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2").

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SUMMARY

Item Tag/ID Item Description Problem Description PVAR No. (if NTTF 4 Resolution 3 Status issued) 2EPEAG01 EmewgenGy diesel 1.) Noted sole plate n/a Y Licensing Basis Evaluation: 1.) A closer review of 13-C-ZGS-generator "A" dimension deviations from 0110 (Ref. 65) shows that the sole plate dimensions read in documentation in field. the field by the SWT were for the pockets to be chipped Verify as-built meets CLB. out of the foundation and not the plates themselves.

2.) Noted light fixture and Furthermore, sole plates were provided by vendor and are heater suspended over therefore not to be evaluated per EPRI TR-1025286 Domestic Service water guidance. SSC meets CLB.

line; possible spray hazard if 2.) Diesel Gen lighting plan 02-E-ZGL-0001 (Ref. 65) shows overhead equipment not that light fixture is mounted per Detail 1 of 13-E-ZAL-0011 adequately mounted. (Ref. 65): 1/4" Kwik bolt mounted j-box supporting 3/4" conduit stem. This is a rugged and ductile connection and Judged to be acceptable. The overhead heater Is verified as Seismic Category IX CALC 13-CC-ZG-0070 (Ref. 65). SSC meets CLB.

3 PVAR denotes Palo Verde Action Request which is the entry document for the PVNGS corrective action program.

4 NTTF Status denotes conclusions of LBE for the condition. Y- Condition was found to conform to the current licensing basis. N- Condition is either a Non-Conforming Condition or a Potential Non-Conforming Condition (if PVAR resolution is on-going)

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page D-2 Item Tag/ID Item Description Problem Description PVAR No. (if NTTF 4 Resolution 3 Status issued) 2EPHAM31 480 V MCC M31 Documentation gap on as- 4220252 N Licensing Basis Evaluation: As-installed exceeds vendor installed pattern measured requirements and is therefore acceptable for seismic in field and that shown as adequacy; however, as-installed configuration could not be as-installed in 13-CC-ZQ-EO1 readily shown to match the CLB documentation. PVAR (Ref. 65). 4220252 generated to update the calculation to reflect the as-installed configuration found in the field.

SWC indicates - As-installed weld exceeds vendor requirements; no adverse seismic condition exists.

APS reports this is a potential non-conforming condition.

An Operability Determination concluded that the SSC remained Operable.

Supplemental Report Update: APS reports that configuration documentation determined to be non-conforming. As-found configuration will be documented on EDC 2013-00455.

2EPHBM32 480 V MCC M32 Verify as-Installed n/a V Licensing Basis Evaluation: As-installed configuration configuration recorded on exceeds the requirements per SDOC E018-00564. No checklist per CLB hazard. SSC meets CLB.

documentation.

2EPKAH11 Battery charger Could not verify Y4"weld n/a Y Licensing Basis Evaluation: 1/4" required weld thickness "A" meets CLB configuration verified from SDOC E051-00047 (Ref. 65); SSC meets CLB.

with anchorage documentation taken in field.

2EPKAH15 125 VDC Class 1E Could not verify 14" weld n/a V Licensing Basis Evaluation: 1/4" required weld thickness battery Charger meets CLB configuration verified from SDOC E051-00047; SSC meets CLB.

AC with anchorage documentation taken in field.

2EPKCF13 DC battery "C" Verify that CLB anchorage n/a V Licensing Basis Evaluation: Per SDOC EN05OB-AO0015 (Ref.

configuration consists of 65), the length of welds is a minimum of 4" at the ends of 1/4" welds to embeds at base beams at a thickness of 1/4". Configuration is minimum 5" length. therefore acceptable; SSC meets CLB.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page D-3 Item Tag/ID Item Description Problem Description PVAR No. (if NTTF 4 Resolution 3 Status issued) 2EPKCN43 Inverter.fpr Anchorage documentation n/a Y Licensing Basis Evaluation: Review of FCR 8541C (Ref. 65) shutdown cooling in field did not meet as-built confirms that 1/4" fillet welds connecting the channels to isolAlion laive configuration. 13-CC-ZQ- the embeds are required, which are provided in the field; 2JSIKUV65'3 E01 confirms the as- SSC meets CLB.

installed welds between the inverter tube steel and the base channels, but verification of the channel-to-embed weld is required.

Verify as-built meets CLB.

2EPKDM44 DC power to TCB1 Anchorage documentation 4220252 N Licensing Basis Evaluation: As-installed configuration could control circuit in field did not meet as-built not readily be verified against CLB documentation. PVAR (and DC configuration. Verify as- 4220252 generated to reconcile the configuration Distribution Panel built meets CLB. 4"x3"xl" discrepancy.

D24) thick plates were provided at two locations that differ Supplemental Report Update: APS reports that as-found from that shown on Sheets condition is evaluated in NCR EJ-02396 and meets Current 97 and 98 of Calc 13-CC-ZQ- Licensing Basis. EDC 2013-00455 is in-progress to update E01 (Ref. 65). Calculation 13-CC-ZQ-EO01 (Ref. 65) to reflect NCR-approved configuration.

2EPNAN11 DC/AC inverter Could not verify anchorage n/a Y Licensing Basis Evaluation: Anchorage verified from E054-

"A" meets CLB in field. 00070 (Ref. 65); SSC meets CLB.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page D-4 Item Tag/ID Item Description Problem Description PVAR No. (if NTTF 4 Resolution 3 Status issued) 2EPNAV25 120 V vital ac Could not verify as-installed 4275113 N Licensing Basis Evaluation: As-installed configuration could voltage regulator welding/bolting of channel not readily be verified against CLB documentation. PVAR "A" to embeds meets CLB in 4275113 generated to reconcile the configuration field. discrepancy.

APS reports that PVAR (related work) indicates the as-found anchorage capacity is equivalent to vendor required capacity; therefore no adverse seismic condition exists.

APS reports this is a potential non-conforming condition.

An Operability Determination concluded that the SSC remained Operable.

Supplemental Report Update: APS reports configuration documentation determined to be non-conforming. As-found configuration will be documented on EDC 2013-00455.

2EPNDD28 Power to .PPS "D" Noted 3/4" gap between n/a V Licensing Basis Evaluation: Gap is in the longitudinal lnstriumefatation component and rigid direction of the large panel enclosure, so a frequency of 8 conduit support. Action Hz Is applied. Using 2% damping (conservative), SSE needed to verify gap as acceleration at 100' CTRL building is 0.95g (Ref. 53).

sufficient. Estimated displacement is then (0.95g

• 386.4 in/sA2/g)/(2*3.14*8 Hz)A2 = 0.15 inches. Therefore, 3/4" gap is judged to be sufficient; SSC meets CLB.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page D-5 Item Tag/ID Item Description Problem Description PVAR No. (if NTTF Resolution issued)3 Status4 2JHCAPT0351A / Containment 13-J-01D-0103 (Ref. 65) 4275113 N Licensing Basis Evaluation: No documentation found to 2JHCAPT0352A/ pressure shows 1' gap between show that less than 1" gap is permissible; therefore the 2JHCCPT0351C mounting plates. No gap anchorage configuration is not consistent with plant

/2JHCCPTO352C provided in field. documentation. However, no adverse seismic concern is present since the gap criteria have no influence on the component's safety-related function during and after SSE events. PVAR 4275113 generated to reconcile anchorage configuration.

SWC indicates - absence of gap has no impact on ability to function during/after SSE; no adverse seismic condition exists.

APS reports this is a potential non-conforming condition.

An Operability Determination concluded that the SSC remained Operable.

Supplemental Report Update: APS reports configuration documentation determined to be non-conforming. As-found configuration will be documented on EDC 2013-00455.

2JSBAC03 Noted loose cabinet door. 4213794 V Licensing Basis Evaluation: Ops opened the door and noted b3ýea'ker'V separate enclosure for breaker. Therefore no chatter issue and no adverse seismic concern. SSC meets CLLB. Note that PVAR 4215794 was generated by PVNGS to document the condition and adjust the door.

APS reports this is not a non-conforming condition. An Operability Determination concluded that the SSC remained Operable.

Supplemental Report Update: APS reports that PVAR 4215794 is closed.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page D-6 Item Tag/ ID Item Description Problem Description PVAR No. (if NTTF Resolution issued)3 Status4 2JSGAHV0179 Atmospheric SWT noted Y2"clearance n/a Y Licensing Basis Evaluation: Per SDOC J601A-00274 (SSC 65),

Dump Valve between mounting plate for all valve frequencies are above 33 Hz; therefore"1/2" gap solenoid valves and is sufficient. SSC meets CLB.

independently mounted conduit. Given pipe supports immediately adjacent, independent valve motion is judged as primary contributor to whether the gap can be closed. Verify whether valve is stiff enough to preclude excessive displacement.

2JSINPT391 HPSIlong.term Verify whether CLB n/a Y Licensing Basis Evaluation: Per Dwg 13-J-01D-0119, as-recirc loop 1 documentation matches as- installed configuration meets CLB configuration pressure xmtr built configuration of documentation. No concern. SSC meets CLB.

transmitter mounting plate fastenred by four 1/2" bolts to2 horizontal P1000 Un istrut members, which are 1/4" vertical fillet welded to outsides of column flanges._

2MAFAP01 AF Pump A Noted sheared-off bolt. n/a Y Licensing Basis Evaluation: During original construction, Could not verify this meets the as-built configuration was analyzed with the missing CLB. bolt and determined to be acceptable. Documentation was provided in 13-CC-ZQ-MO1 (Ref. 65). SSC meets CLB.

2MDGAX01 AREA WALK-BY Could not verify as-installed n/a Y Licensing BasisEvaluatlon: The anchorage for the kicker kicker angle anchorage in angle was verified per 13-CC&ZG-0070 (Ref. 65). SSC meets field. Verification against CLB.

CLB documentation is required.

2M ECAE01 Essential chiller Could not verify as-installed n/a V Licensing Basis Evaluation: The only issue was the 5" pad "A" 5" pad configuration meets configuration and this has been verified as acceptable per CLB. FCR 7030C (Ref. 65) which approved the field request to chip the "A" chiller down 1". SSC meets CLB.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page D-7 Item Tag/ID Item Description Problem Description PVAR No. (if NTTF 4 Resolution 3 Status issued) 2MECAT01 EC expansion tank Noted tank leg flange 4275113 N Licensing Basis Evaluation: As-installed configuration could "A" overhangs supporting W8 not readily be verified against CLB documentation. PVAR beam so all-around fillet 4275113 generated to reconcile the configuration weld was not possible. discrepancy.

Could not verify as-installed weld pattern meets CLB. Supplemental Report Update: APS reports that as-found condition is evaluated in NCR MJ-00520 and meets Current Licensing Basis. This condition identified on PVAR 4275113 is closed.

2MEWAP01 EW pump "A" Noted welded plates 4275113 N Licensing Basis Evaluation: As-installed configuration could around anchor bolts that not readily be verified against CLB documentation. PVAR were not noted on field 4275113 generated to reconcile the configuration anchor documentation. discrepancy.

Supplemental Report Update: APS reports that solid plate design matches design detail on drawing 13-C-ZAS-0241 (Ref. 65) and meets Current Licensing Basis. This condition identified on PVAR 4275113 is closed.

2MHFAJ01 FuelBuilding AHY Could not verify 5/8" bolt n/a Y Licensing Basis Evaluation: 5/8" bolts verified per 13-C-meets CLB from field OOA-001 (Ref, 65). SSC meets CLB.

documentation.

2MHFBJO1 Fuel Building AHU Could not verify 5/8" bolt n/a Y Licensing Basis Evaluation: 5/B" bolts verified per 13-C-meets CLB from field OOA-0011 (Ref. 65). SSC meets CLB.

documentation.

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page D-8 Item Tag/ID Item Description Problem Description PVAR No. (if NTTF 4 Resolution 3 Status issued)

Control Room, AREA WALK-BY Noted book case as 4214832 Y Licensing Basis Evaluation: Given that the books will fall Outside potential Interaction hazard out of the case at elevated SSE acceleration levels, the Horseshoe with cabinet RMA-B01. inertial demand generated by the mass of the book case will not exceed the capacity of screws. Therefore, there Is no adverse seismic condition. This configuration meets CLB.

APS reports that PVAR 4214832 was issued and this non-conforming condition was corrected in all 3 units by removal of the book cases. An Operability Determination concluded that the SSC remained Operable.

Supplemental Report Update: APS reports that PVAR 4214832 is closed.

Fuel Bldg 140' AREA WALK-BY Action needed to verify n/a Y Licensing Basis Evaluation: SDOC NOO1-0502-00322 (Ref.

refueling rig cannot uplift 65) confirms that members which fit into grooves on the from track. inside of the rails resist uplift for the spent fuel handling machine (2MZFNM03). SSC meets CLB.

ROOM A-202 AREA WALK-BY Noted small gaps between n/a V Licensing Basis Evaluation: Per EQCF D95-0038 (Ref. 65),

ZAA-C04/C05/C06 and all ZAA and ZAB cabinets were analyzed and determined to concrete walls. 3/8" gap Is be rigid. Therefore, the as-built gap Is sufficient. SSCs meet minimum. Action needed to CLB.

assess displacement and whether essential relays are In the cabinets.

ROOM C-A09 AREA WALK-BY Noted threaded piping as n/a V Licensing Basis Evaluation: Fire piping was verified to be potential spray hazard. pre-activated per fire suppression maps and therefore normally dry. Therefore no spray hazard. This configuration meets CLB.

ROOM G-102 AREA WALK-BY Noted light fixture and n/a Y Licensing Basis Evaluation: Diesel Gen lighting plan 02-E-heater suspended over ZGL-0001 shows that light fixture Is mounted per Detail 1 Domestic Service water of 13-E-ZAL-0011: 1/4" Kwlk bolt mounted ]-box line; possible spray hazard if supporting 3/4" conduit stem. This is a rugged and ductile overhead equipment not connection and judged to be acceptable. The overhead adequately mounted. heater Is verified as Seismic Category IXCALC 13-CC-ZG-0070. This configuration meets CLB.

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Enclosure Appendices A and B contain Security-Retated Wnaormatikon - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page D-9 Item Tag/ID Item Description Problem Description PVAR No. (if NTTF 4 Resolution 3 Status issued)

ROOM J-A02 AREA WALK-BY Could not verify in field n/a Y Licensing Basis Evaluation: 02-M-FPP-003 (Ref. 65) whether threaded piping confirmed FP-686 is pre-activation valve and therefore over 2MECAE01 is normally piping is dry. This configuration meets CLB.

dry.

ROOM J-114 AREA WALK-BY SWT noted apparent 4275113 N Licensing Basis Evaluation: CLB documentation reconciling modification with P1000 original seismic qualification could not be readily obtained; Unistrut support from HJN- therefore PVAR 4275113 will be amended to research CLB.

PDSL-138 welded to 2MHJBZ04. Verify APS reports that configuration documentation determined modification reconciled to be non-conforming. An Operability Determination 2MHJBZ04 original seismic concluded that the SSC remained Operable. As-found qualification. configuration will be documented on EDC 2013-00455 (in-progress).

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page E- 1 APPENDIX E - QUALIFICATIONS This appendix contains only the qualifications of new personnel involved with the 2R17 refueling outage Seismic Walkdowns performed from October 13 through October 15, 2012, and the subsequent walkdowns performed on December 5, 2012. The qualifications of personnel involved with the at-power Seismic Walkdowns performed from July 23 through July 30, 2012, can be found in Appendix E of Reference 48 ("Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2").

WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page E-2 TIMOTHY S. NEALON EDUCATION 2010 - 2012 University at Buffalo, Buffalo, New York Master of Science, Civil Engineering(MSc) 2006-2010 University at Buffalo, Buffalo, New York Bachelor of Science, Civil and EnvironmentalEngineering(BSCE)

PROFESSIONAL CAPABILITIES Structural analysis and design of steel, concrete, and masonry structures using IBC and UBC Dynamic analysis of structures for seismic, vibration, blast, fluid, and wind loads Competed the NTTF Recommendation 2.3 Plant Seismic Walkdown training course Finite element modeling and analysis including use of ABAQUS, and SAP2000 PROFESSIONAL HISTORY 2012 - Present Stevenson and Associates, Goodyear, Arizona Engineer PROJECT EXPERIENCE

SUMMARY

Seismic Fragilit, Projects Mr. Nealon has performed Seismic Walkdowns and fragility analyses of structures and components for use in probabilistic risk assessments. Mr. Nealon has executed the seismic analyses of concrete foundations, masonry walls, large storage tanks, piping, and electrical and mechanical equipment anchorages. In addition, Mr. Nealon has performed Seismic Walkdowns of tanks and their associated leakpath piping to assess loss of inventory in the event of beyond-design-basis seismic events. He has assessed piping systems for excessive stresses due to differential support movement and performed subsequent analyses using manual and finite element methods.

WCAP- 17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page F- I APPENDIX F - PVNGS UNIT 2 SWEL REPORT This appendix contains only the revised SWEL transmittal for the 2R17 refueling outage Seismic Walkdowns performed from October 13 through October 15, 2012, and afterward on December 5, 2012. The SWEL transmittal for the at-power Seismic Walkdowns performed from July 23 through July 30, 2012, can be found in Appendix F of Reference 48 ("Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2").

WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page F-2

• Westinghouse Seismic Walkdown Equipment List, Revision 3 In Response to NTTF Recommendation 2.3: Seismic Palo Verde Nuclear Station Unit 2 (As-Walked Down)

Rolando Perez

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t Equipment Selection Pei sqnnel Lead 'bate Derek Seaman /d- - ,,*. 6/Y A3 Equipment Selection Personnel E i mar, Randall Digitally signed by Eimar, Randall Date G(Z34606)

DN: cn=Eimar, Randall G(Z34606)

Randall Eimar G(Z34606) Date: 2013.08.28 15:15:12 -07'00' Station Operations Date PVNGS Unit 2 Seismic Walkdown Equipment List May21,2013I WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page F-3 Seismic Walkdown Equipment List, Rev. 3 NTTF Recommendation 2.3: Seismic Walkdown Palo Verde Nuclear Station - Unit 2 Revision History Revision 0 of this document provides the Seismic Walkdown Equipment List (SWEL) developed prior to the Palo Verde Nuclear Generating Station (PVNGS) At-Power Seismic Walkdowns performed between Monday, July 23rd, 2012 and Friday, July 27th, 2012. The SWEL contained a total of 132 components (126 SWEL 1 & 6 SWEL 2).

Revision 1 of this document updates the PVNGS SWEL based on modifications required during the At-Power Seismic Walkdowns performed between Monday, July 23rd, 2012 and Friday, July 27th, 2012. As a result of these modifications, the SWEL still contains a total of 132 components (126 SWEL 1 & 6 SWEL 2).

A review of the modifications verified that the requirements of Screen #4 - Sample Considerationsof the EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012 {Reference 1}, are maintained. These modifications include the following:

Component Resolution Justification ID Affected 2JCHALT0203A Replaced with Component ID 2JSBAC02A Item was inaccessible due to security missile barrier.

2JCHDLT0203D Replaced with Component ID 2JSBDC02A Item was inaccessible due to security missile barrier.

2JSIAHV0691 Replaced with Component ID 2JRDBUVO024 Was removed from SWEL to accommodate 2JRDBUVO024 addition.

2JCHAUVO580 Replaced with Component ID 2JCTAL035 Was removed from SWEL to accommodate 2JCTAL035 I addition.

Revision 2 of this document updates the "Major New or Replacement Equipment" column of the SWEL 1 table included in Attachment 1 and Table 3-2 of Attachment 3.

The information related to "Major New or Replacement Equipment" was revised as a result of an error found in the Microsoft Excel spreadsheet that was used track and implement the SWEL selection process. This error did not result in a change to the Base List or SWEL selections. Although the number of "Major New or Replacement Equipment" decreased from 13 to 9, this equipment selection attribute remained adequately represented on the SWEL.

Revision 3 of this document revises the SWEL 1 table provided in Attachment 1 to document the following changes required for the additional walkdowns performed during and after refueling outage 2R17, from October 13 through October 15, 2012 and on December 5, 2012:

1. Items 2JCHAUVO516 and 2MCHEE01 were inaccessible in a locked high-radiation area. Therefore, for radiological safety considerations, it was decided PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 2 I WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 Auaust 2013

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2. Since Train A was protected during refueling outage 2R1 7, the following Train A electrical components were substituted with their counterpart from Train B, which were selected from Base List 1:

a. 2EPBAS03 was substituted with sister component 2EPBBS04.

b. 2EPGAL31 was substituted with sister component 2EPGBL32.

c. 2EPGAL33 was substituted with sister component 2EPGBL34.

d. 2EPGAL35 was substituted with sister component 2EPGBL36.

e. 2EPHAM31 was substituted with sister component 2EPHBM32.

f. 2EPHAM33 was substituted with sister component 2EPHBM34.

g. 2EPHAM35 was substituted with sister component 2EPHBM36.

h. 2EPHAM37 was substituted with sister component 2EPHBM38.

i. 2EPKAD21 was substituted with sister component 2EPKBD22.

j. 2EPKAM41 was substituted with sister component 2EPKBM42.

The components in Items d through j were inspected to fulfill Frequently Asked Question (FAQ) 4.20 regarding the supplemental inspection of electrical cabinets.

These substitutions did not affect the number of SWEL items and since the replacements were performed with equipment of the same type, the revised SWEL 1 still satisfied the Reference 1 guidance. That is, component type, along with other attributes, remain adequately represented on the SWEL.

Revision 3 of this document also revises a typographical error found in the tag ID of SWEL 1 item number 13, which corresponds to Base List 1 item number 36. This equipment was incorrectly identified as 2JCHEHV0240 instead of 2JCHEPDVO240.

Seismic Walkdown Equipment List (SWEL)

A listing of structures, systems, and components (SSCs) that will be inspected during the walkdown, the Seismic Walkdown Equipment List (SWEL), has been prepared in advance of the walkdown effort.

The selection of SSCs process described in EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012 {Reference 1}, was utilized to develop the SWEL for Palo Verde Nuclear Generating Station Unit 2.

The SWEL is comprised of two groups of items:

PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 3 I WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 AuIst' I2t0131 ty

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o. SWEL 1 (Attachment 1) is a sample of items to safely shut down the reactor and maintain containment integrity

• . SWEL 2 (Attachment 2) is a list of spent fuel pool related items APS Operations and Design Engineering Staff Members participated in the selection of the SSCs comprising the SWEL and provided inputs and assistance to the Equipment Selection Personnel to find the data associated with the equipment considered. The interchange of information between the Equipment Selection Personnel and the APS Staff Members included:

" Weekly status meetings for review of the SWEL progress.

" Verification of equipment information through APS's SWMS Database system.

" Discussions with Operations relative to recent upgrades and changes to the plant that might be relevant to the SWELs.

• Discussions with Design Engineering and Operations to select equipment with operational experience relevant to SWEL selection.

• Provided System Health Reports and Design Basis Manuals for review by the Equipment Selection Personnel.

Details describing the process for Selection of SSCs to produce the SWEL have been provided to APS in the form of a formal presentation, given on July 18, 2012.

Additionally, details describing the process for Selection of SSCs to produce the SWEL are provided in the "Selection of SSCs" section of the Submittal Report.

References

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

PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 4 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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1) Seismic Walkdown Equipment List 1

2) Seismic Walkdown Equipment List 2

3) SWEL Sort Tables I

PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 5 I WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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"Outside")

Operations noted engineered 2JAFAFTOO4A uxiliary feedwater MSSS Yes Yes PC DHR Inst. Rack scaffolding was recently added to the (flow

18) AF No 140(I) No No MSSS. This should be examined by area walkby.

Operations noted engineered Auxiliary feedwater Inst. Rack scaffolding was recently added to the 2 2JAFAFTOO4OB flow flw(18)IMSSS Yes Yes PCDHR 1) AF No 140(lI) No No MS.Ti MSSS. This should hudb be examined xmndbby area walkby.

Operations noted engineered scaffolding was recently added to the 3

2JAFAHVO32 SG-E01A reg valve MSSS Yes Yes PC DHR MOV (B) AF No 104 (I) No No MSSS. This should be examined by area walkby.

Operations noted engineered 4 AFA-K02 turbine oil MSSS Yes Yes PC DHR Horz. Pump AF No 10l No scaffolding was recently added to the cooler (5) MSSS. This should be examined by area walkby.

Operations noted engineered S 2JAFAUVO037 SG-E01B isolation valve MSSS Yes Yes scaffolding was PC DHR MOV (g) AF Yes 104 (I) No No MS.Ti hudbrecentlyxmndb added to the valveMSSS. This should be examined by area walkby.

Operations noted engineered 2JAFCHV0033 6 SG-E01B reg valve MSSS Yes Yes PC DHR MOV (8) AF No 104 (I) No No scaffolding was recently added to the MSSS. This should be examined by area walkby.

7 2JCHAHV0205 Auxiliary pressurizer CTMT Yes Yes PC SOV (7) CH No 120 (I) No Yes spray valve 8 2JCHAHVO524 Charging pumps to AUX Yes Yes PC MOV (8) CH No 104 (I) No No regen HX isolation 9 2JCHAHV0531 RWT outlet to SI train AUX Yes Yes IC DHR MOV (8) CH No 104 (I) No No "A"

10 2MCHAP01 Charging pump 1 AUX Yes Yes RC PC IC Horz. Pump CH No 104 (I) No No (5)

Actn=.::.-. I dn TR This item was removed from 44 2,-G AUV0,,6

, Regeni

. . Ye ea. L444 .e& *es RC4G PQVI4 -4;k 4 120() 4 *es E*Ganger isolatio.n. SWEL 1.

......... Ve heale, *This item was removed from eeel;_egev 4a44 __10_* SWEL 1.

Charging Line To 13 2JCHEPDVO240 Reactor Coolant Loop CTMT Yes Yes BCIC POV (7) CH No 120(I) No Yes 2A Isolation Globe Valve 14 2JCHEHV0532 RUT suction iso (fails X Yes Yes RC PC POV (7) CH No 104 (I) No No open on loss of air) 15 2JCHEHV0536 RWT suction isolation AUX Yes Yes RC PC MOV (8)1 CH No 104 (I) No No I

PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 6 1 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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Basis?) "Outside")

Horz. Pump 16 2MCHEP01 Charging pump 3 AUX Yes Yes RC PC IC (5) CH No 104 (I) No No 17 2MCHETO1 RWT (refueling water Yard Yes Yes RC PC IC Tank (21) CH No 113(0) No No tank) DHR Containment Power 18 2JCPAUVOOD4B Access Purge Exhaust CTMT Yes Yes CF MOV (B) CP No 120(l) No Yes Isolation Butterfly Damper 19 2JCTAHV0001 CST isolation valve CST Yes Yes PC DHR MOV (8) CT No 113 (I) No No 20 2JCTAHVO004 CST isolation valve CST Yes Yes PC DHR MOV (8) CT No 113 (I) No No 21 2MCTET01 CST(condensate Yard Yes Yes PC DHR Tank (21) CT No 113(0) No No

___________storage tank) ____ _____

22 2MDFAT02 DG "A" fuel oil day DG Yes Yes RC PC IC Tank (21) DF No 140(l) No No tank 2 D DHR DG "" ar inakeRC PC IC 23 2MDGAF03 DG "A" air intake DG Yes Yes DHR Other (0) DG Yes 140 (I) No No Starting air RC PC IC 24 2MDGAX01A accumulator DG Yes Yes DHR Tank (21) DG No 140(l) No No 25 2MDGAXO1B 25 2MGX0B Starting air accumulator DG DG YesRC Ys Ys DHR PC IC Tank (21) DG No 140 (I) No No 26 2MECAE01 Essential chiller "A" CTRL Yes Yes R Chiller (11) EC No 80(I) No No 27 2MECAP01 Circulating water CTRL Yes Yes Hr Pump EC No 80(l) No No pump "A" DHR (5) 28 2MECAT01 EC expansion tank "A" CTRL Yes Yes R Tank (21) EC No 80(l) No No 29 2ECATOO29 Control room "A" 29EAHU flow reg valve CTRL Yes Yes PC ICDHR POV (7) EC No 80 (I) No No EW "A"heat Heat 30 2MEWAE01 exchanger AUX Yes Yes PC ICDHR Exchanger EW Yes 104 (I) No No (21) 31 2MEWAP01 EW pump "A" AUX Yes Yes PC ICDHR Horz Pump EW No 104(I) No No This pump was replaced in U2R16 (5) EW N0Io T p rl iU 32 2MEWAT01 EW "A" surge tank AUX Yes Yes PC ICDHR Tank (21) EW No 104 (I) No No 33 2JEWAUVO065 EC/NCWS cross tie AUX Yes Yes PC ICDHR MOV (8) EW No 104 (I) No No valve______

34 2EWAU0145EC/NCWS cross tie 34 2JEWAUVO145 e valve AUX Yes Yes PC ICDHR MOV (8) EW No 104 (I) No No High Pressure 35 2JGAAUVO002 Nitrogen Supply AUX Yes Yes CF SOV (8) GA No 104(I) No No Isolation Gate Valve 36 2MHAAZO1 HPSIpump room "A" AUX Yes Yes PC IC DHR AHU (10) HA No 104 (I) No No EAHU 3 MAZ2 LSpuprom"" AUX Yes Yes PCIC DHR AHU (10) HA No 104 (l) No No IEAHUII I

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Basis?) S"Outside")

38 2MHAAZ04 AFW EAHUpump room "A" MSSS Yes Yes PC ICDHR AHU (10) HA No 104 (I) No No 39 2MHAAZ05 ECW pump room "A" EAHUI AUX Yes Yes PC ICDHR AHU (10) HA No 104 (l) No No Inst. Rack 40 2JHCAPT0351A Containment pressure AUX Yes Yes CF (18) HC No 104(I) No No Inst. Rack 41 2JHCAPTO352A Containment pressure AUX Yes Yes CF HC No 104(I) No No (18)

Discharge Sampling 422HCAUOD4S From RU-i 42 2JHCAUVO04 containment Isolation AUX Yes Yes CF SOV (8) HC No 104 (I) No No Valve Inlet Sampling To RU-43 2JHCAUVO046 1 Containment AUX Yes Yes CF SOV (8) HC No 104 (I) No No Isolation Valve 44 2JHCCPT0351C Containment pressure AUX Yes Yes CF (18) HC No 104(I) No No 45 2JHCCPT0352C Containment pressure AUX Yes Yes CF (18) HC No 104 (I) No No 46DG "A"room EAHU DG Yes Yes PC ICDHR Fan (9) HD No 140 (I) No No DG "A" room essential 47 2MHDAJ01 exhaust DG"A"roomfa DG Yes Yes PC IC DHR Fan (9) HD No 140 (I) No No 48 2MHJAF04 Control room EAnHU CTRL Yes Yes PC ICDHR AHU (10) HJ No 80(l) No No 49 49 2MBJAJ1A Battery roo "A" 2 HI J I toom essential "Atfan exhaust CTRL Yes Yes PC ICDHR Fan (9) HJ No 80(l) No No 50 2MHJAMO2 motor-operated CTRL Yes Yes PC ICDHR MOV (8) HI No 80(I) No No 50_ 2M__AM2 damper 1 51 2MNJAM03 motor-operated CTRL Yes Yes PC ICDHR MOV (8) HJ No go (I) No No damper 52 2JHJAM34 Pneumatic Damper CTRL Yes Yes DHR POV (7) HJ No 80(l) No No HJAM34 Solenoid I_______I______I__

53 2MHJAM62 Air-operated damper CTRL Yes Yes PC ICDHR POV (7) HJ No 80(I) No No 54 Control room temp CTRL Y ee Temp NJ 54 2J'A"12 indicating controller Yes ICDHR Sensor (19) No B0(I) No No 55ESF switchgear room CTRL Yes Yes PC ICDHR AHU (10) HJ No 80(l) No No 52MJAZ4 Dr"A"EAEU 56 2MJAZO4 DCnroomu"A" EAHn U CTRL Yes Yes PCSICDR AU(10) J No 80(l) No No Instrument Air Supply 57 2JIAAUVOO02 Containment Isolation AUX Yes Yes CIF SO(8) IA No 104(l) No No I S Gate valve Vot

__P__CMed 2EPBBS04 bus RCPC IC Volt 58 (substitute for 4.16 kV bus S04 2EPAS3(DNR CTRL Yes Yes Med. VoltR

3) P Yes 80(l) No No

ý2EPBAS03) CF SWGR (3)

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"Outside")

Selector Switch For 125 VDC To 2EPBASO3S From Wall Mount 59 2EPBAUO1 Either3Panel m CTRL Yes Yes PC DHR PB No 80 (I) No No Either Panel Cont. (1)

Distribution Or Battery Charger A 60 2EPEAG01 Emergency diesel DG Yes Yes RC PC IC Eng. Gen. PE No 140( I) No No generator "A" DHR (17) 2EPGBL32 61 (substitute for 480 VLC32 bus CTRL Yes Yes RC PC DHR PG No 80 (I) No No 2EPGAL31) SWGR (2) 2EPGBL34 62 2EGBL34Low Volt.

62 (substitute for 480 VLC34 bus CTRL Yes Yes RC PC DHR PG No 80(1) No No 2EPGAL33) SWGR (2) 2EPGBL36 63 (substitute for 480 VLC36 bus CTRL Yes Yes RC PC DHR Low Volt PG No 80(I) No No 2EPGAL35) SWGR (2) 2EPHBM32 64 (substitute for 480 VMCC M32 CTRL Yes Yes RC PC DHR MCC (1) PH No 80(l) No No 2EPHAM31) 2EPHBM34 65 (substitute for 480 VMCC M34 AUX Yes Yes RC PC DHR MCC (1) PH No 104 (I) No No 2EPHAM33) 2EPHBM36 66 (substitute for 480 VMCC M36 AUX Yes Yes RCPC DHR MCC (1) PH No 104 (I) No No 2EPHAM35) 2EPHBM38 67 (substitute for 480 V MCC M38 AUX Yes Yes RC PC DHR MCC (1) PH No 104(l) No No 2EPHAM37) 2EPKBD22 2EPKBD22Dist Panel 68 (substitute for LC34 control power CTRL Yes Yes RC PC DHR PK No 80() No No 2EPKAD21) (14) 69 2EPKAF11 DC battery "A" CTRL Yes Yes RC PC DHR Battery Rack PK No 80(I) No No 1_ _ _(15) 1 70 2EPKAH11 Battery charger "A" CTRL Yes Yes RC PC DHR Battery Chg PK No 80(I) No No (16) 71 2EPKAH15 125 VDC Class 1E CTRL Yes Yes RC PC IC Battery Chg PK No 80(I) No No Battery Charger AC DHR (16) 2EPKBM42 DC power to TCB1 72 (substitute for control circuit CTRL Yes Yes RCPC MCC (1) PK No go (1) No No

_2EPKAM41) 73 2EPKCF13 DC battery "C" CTRL Yes Yes RC PC DHR Battery Rack PK No Boll) No No (15)

Inverter For Shutdown 74 2EPKCN43 Cooling Isolation Valve CTRL Yes Yes DHR Inverter (16) PK No 80(l) No No 2JSICUV653 I

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Number Licensing Inspections?) Support) Class Type equipment? 0 for enhancement? toOutage?

Basis?) "Outside")

72PKD4 DC distribution panel Ds ae 75 2EPKDD24 CTRL Yes Yes RC PC DHR Dist PanelNo () No No 024 (14)_PKNo8(14INoNo 76 2EPKDF14 DC battery "D" CTRL Yes Yes RC PC DHR Battery Rack No ( No No (15) PKNo_80_(I__No__o 77 2EPKDM44 DC power to TCB1 CTRL Yes Yes RC PC MCC (1) PK No 80(l) No No 2EPKDM44 control circuit Inverter For 2JSIDUV654 78 2EPKDN44 Return ShutdownInside Cooling B CTRL Yes Yes CF Jivre Inverter (16)1) PPK Noo8 so(l)t oN No No Containment Isolation Valve Power to PPS "A" RC PC IC Dist Panel 79 2EPNAD25 instrumentation" instrumentation CTRL Yes Yes R DHR (4 (14) PN No 80(I) No No PC IC DHR 80 2EPNAN11 DC/AC inverter "A" CTRL Yes Yes CF Inverter (16) PN No 80ll) No No 81 2EPNAV25 120 V vital ac voltage CTRL Yes Yes PC IC DHR Other (0) PN No 80 (I) No No regulator "A" CF 120 V vital ac voltage PC IC DHR 82 2EPNCV27 regulator "C" CTRL Yes Yes CF Other (0) PN No 80(l) No No 83 Power to PPS "D" CTRL Y RC PC IC Dist Panel PN No 80(l) No No instrumentation DHR (14)

PC IC DHR 84 2EPNDN14 DC/AC inverter "D" CTRL Yes Yes CF Inverter (16) PN No 80(l) No No 120 V vital ac voltage PCICDHR 85 ___2EPNDV28

_____regulator regulat '.lDge "D" CTRL Yes Yes CCF Other (0) PN No 80 (l) No No Przr pressure Inst. Rack 86 2JRCAPTO012A (required for CTMT Yes Yes PC 1 RC No 120 (l) No Yes RPS/SIAS) (18) 87 2JRCAPT13 SDC RCS pressure interlock CTMT Yes Yes DHR Inst(18)TRC Rack No 120 (I) No Yes Inst. Rack 88 2JSBAC02A I/V converter CTRL Yes Yes DHR In8) RC No 80(I) No No

_______ ~~~~~~~(18)

Inst. Rack 89 2JSBDC02A I/V converter CTRL Yes Yes DHR (18) RC No 120 (I) No No 90 2JRCNTE101 Pressurizer CTMT Yes Yes PC Temp RC No 120 (l) No Yes I temperature I Sensor (19)

Isolation Containment When choosing containment isolation 91 2JRDBUVO024 Radwaste Sump AUX Yes Yes CF MOV (8) RD No 104(l) No No valves that exist for both inside and Outlet Isolation Gate outside containment, outside was Valve chosen, Control 92 2JRMAB02 RWT level CTRL Yes

________ Yes

____________ RC IC DHR ~~Panel RM No (201)______________________ 80 (l) No No Control 93 2JRMAB04 RCS temperature CTRI Yes Yes RC RM No 80(l) No No Panel (20)

Control 94 2JRMAB05 Containment pressure CTRL Yes Yes CF Panel Panel (20) RM No 80(I) No No I

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NTTF Recommendation 2.3: Seismic Walkdown Attachment 1 - SWEL 1 (As-Walked Down) Palo Verde Nuclear Station - Unit 2 Screen Screen #4 Sample Considerations Scee Screen #3 Environment Walkdown Ite Walkdown Description Building (SC- I (Regular2 Safety Equipment System Major Temp, F)

Number m EupetLicensing Licensing Inspections?) Support)

Function Class Type eqimn?new or replacement (I for 0fr IPEEE nhcmnt Deferred tooOua?

Comments Eqipens ni ecsos? lasequipment? 0"Inside"or for vulnerability enhancement? Outage?

Basis?) r"Outside")

Ausiliary feedwater Control 95 2JRMAB06 flow CTRL Yes Yes PC DHR Conel RM No 80(1) No No

________ flow___________ Panel 1201 Control 96 2JRMDBO5 Containment pressure CTRL Yes Yes CF Panel 1201 RM No 80(l) No No Pressurizer Control 97 2JRMNBO4 temperature CTRL Yes Yes PC Panel (20) RM No 80 (I) No No Reactor trip breaker Breaker 98 2JSBAC03 AUX Yes Yes RC PC SB No 104 (I) No No "A" Panel (2)

Operations noted engineered 99 Atmospheric dump MSSS Yes Yes PC DHR POV (7) SG No 124 (I) No No scaffolding was recently added to the 99 2SAHV0179 valve HV-179 MSSS. This should be examined by area walkby.

Operations noted engineered 100 2JSGAHV0184 Atmospheric dump MSSS Yes Yes PC DHR POV (7) SG No 124(1) No No scaffolding was recently added to the valve HV-184 MSSS. This should be examined by area walkby.

SG-E01A WR level Inst. Rack 101 2JSGALT1113A (required for AFASI CTMT Yes Yes DHR SG No 120 (I) No Yes Operations noted engineered Instrument air line Inst. Rack scaffolding was recently added to the pressure transmitter MSSS Yes Yes PC DHR (18) S No 104 (I) No No MSSS. This should be examined by area walkby.

Operations noted engineered AF turbine steam scaffolding was recently added to the 103 2SGAUV0134 supplyMSSS Yes Yes PC DHR MV () S No 124 I) No No MSSS. This should be examined by area walkby.

Operations noted engineered AF turbine steam scaffolding was recently added to the 104 2JSGAUV34A supplyMSSS Yes Yes PC DHR MV () S Yes 24 (I) No No MSSS. This should be examined by area walkby.

Operations noted engineered 1AF turbine steam scaffolding was recently added to the 105 SGAUV13 supply a MSSS Yes Yes PC DHR MV () No 124 (I) No No MSSS. This should be examined by area walkby.

AF turbine steam Operations noted engineered 106 2JSGAUV138A supply heat up (Train MSSS Yes Yes PC DHR MOV (8) SG Yes 124 (1) No No scaffolding was recently added to the A) MSSS. This should be examined by area walkby.

SG-2 Line 1 Inst. Rack 107 2JSGDHY0185S Atmospheric Dump MSSS Yes Yes PC DHR (18) SG No 124(I) No No Solenoid 108 2JSIAHV0604 RC loop 1 long term AUX Yes Yes IC DHR MOV (8) SI No 104 (I) No No recircvvalve I I I

PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 11 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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Nm e qupmn Licensing Inspections?) Class Type etioes Ofouehanemnt Basis?)equipment? for enhancement?

Basis?)_ "Outside")

Containment Spray Pump A Discharge To 109 251AHV0684 Shutdown Cooling AUX Yes Yes CF MOV (8) SI No 104 (l) No No Heat Exchanger A Valve 110 2JSIAHV0685 SDHX "A" isolation AUX Yes Yes DHR MOV (8) SI No 104 (I) No No valve 111 2MSIAP02 HPSI pump "A" AUX Yes Yes IC DHR Horz. Pump SI No 104 (I) No No

____________I -___ (5) ______

The CS pump was selected for 112 2MSIAP03 Pump A AUX Yes Yes CF (6) SI No 104 (I) No No walkdown per ops/engineering euet HPSI train "A"request.

113 2JSIAPSVO417 injectin injection to to EDT relief AUX Yes Yes IC DHR Other (0) SI No 104 (I) No No Safety Injection Tank 114 2JSIAUV0634 IA Discharge Isolation CTMT Yes Yes RC IC MOV (8) SI No 120 (I) No Yes Globe Valve Safety Injection Tank 115 2JSIAUV0644 1B Discharge Isolation CTMT Yes Yes RC IC MOV (8) SI No 120 (I) No Yes Globe Valve This item is being specifically walked 116 2JSIAUVO651 RC loop 1 long term CTMT Yes Yes IC DHR MOV (8) SI Yes 120 (I) No Yes down due to its significance in plant recirc/SDC valve history (pipe vibration),

117 2JSIAUV0660 SIltrain"AS

___________(closes on RAS)_____ AUX Yes Yes IC DHR SOV (8) Si No 104 (I) No No _________________

Containment Spray 118 2JSIAUV0664 Pump Recirculation To AUX Yes Yes CF MOV (8) Sl No 104 (I) No No Refueling Water Tank Train A Globe Valve 119 2JSIAUV0666 HPSI pump "A" recirc AUX Yes Yes IC DHR MOV (B) Sl Yes 104 (I) No No iso (closes on RAS) 120 2JSIAUV0673 SUMP isolation valve CTMT Yes Yes IC DHR MOV (8) Sl Yes 120 (I) No Yes 121 2JSIAUVO674 SUMP isolation valve AUX Yes Yes IC DHR MOV (8) S Yes 104 (I) No No 122 2JSIDHV331 RC loop 2 long term AUX Yes Yes IC DHR MOV (8) SI No 104 (I) No No recirc Non Class Power however kept in list 123 2JSINPT391 HpSI pressurecir CTMT Yes Yes IC DHR (18) SI No 120 (I) No Yes because of pressure boundary loop 1 pressure xmtr (18) considerations.

124 2MSPAP01 Spray pond pump "A" SP Yes Yes PC DHR Vert. Pump SP No 122(0) No No UHS (6) 125 2MHSAJ01 Spray pond pump hueehstfnA' SP Yes Yes PC DHR AHU (6) SP Selected per ops/engineering request No 1.22(0O) No No dutohenvrmnalcdios house exhaust fan "A" UHS_ due to the environmental conditions Inst. Rack 126

• 2JCTALT03S CST Level indicator CST Yes Yes RC IC DHR RM No 80({I)No No (20) _ __ I I

• The total number of SWEL 1 items is 124 instead of 126 because items 11 (2JCHAUVO516) and 12 (2MCHEE01) were removed. The item numbers in the first column of this table were not adjusted to make it easier to compare the items listed herein to those in previous revisions of this document.

I PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 12 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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1 2MPCAPO1 Fuel pool cooling pump I PP PC Fuel Building Yes Yes No 2 .2MPCAE01 Fuel pool cooling heat exchanger I HX PC Fuel Building Yes Yes No 3 2MPCBPO1 Fuel pool cooling pump 2 PP PC Fuel Building Yes Yes No 4 2MPCBE01 Fuel pool cooling heat exchanger 2 HX PC Fuel Building Yes Yes No 5 2MHFAJO1 Fuel Building AHU AHU HF Fuel Building Yes Yes No 6 2MHFBJ01 Fuel Building AHU AHU HF Fuel Building Yes Yes No PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 13 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page F-15 Seismic Walkdown Equipment List, Rev. 3 NTTF Recommendation 2.3: Seismic Walkdown Attachment 3 - SWEL Sort Tables Palo Verde Nuclear Station - Unit 2 Table 3-1: Sort of the Base List 1 data based on "System Type" (Note: The GR system is not represented due to the containment isolation valves being well represented.)

Number of Items Number of Items Number of Items System Type in Base List 1 Selected for SWEL 1 System Type Number of Items in Base List 1 Selected for SWEL 1 AF 14 6 PB 3 2 CH 29 9 PE 2 1 CP 4 1 PG 6 3 CT 3 3 PH 8 4 DF 1 1 PK 20 11 DG 14 3 PN 12 7 EC 8 4 RC 16 5 EW 8 5 RD 2 1 GA 1 1 RM 31 7 GR 2 0 SB 14 1 HA 4 4 SG 42 9 HC 12 6 SI 101 16 HD 4 2 SP 4 2 HJ 21 9 IA 1 1 PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 14 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page F-16 Seismic Walkdown Equipment List, Rev. 3 NTTF Recommendation 2.3: Seismic Walkdown Attachment 3 - SWEL Sort Tables Palo Verde Nuclear Station - Unit 2 Table 3-2: Sort of the Base List 1 data based on "Major new or replacement equipment" (Of the 414 items comprising Base List 1, 38 items were identified as "Major new or replacement equipment."

The following 10 items were selected for SWEL 1.)

Item Walkdown Equipment Description 279 2JSIAUV0673 SUMP isolation valve 278 2JSIAUV0666 HPSI pump "A" recirc iso (closes on RAS) 61 2MEWAE01 EW "A" heat exchanger 5 2JAFAUVO037 SG-E01B isolation valve 274 2JSIAUV0651 RC loop 1 long term recirc/SDC valve 47 2MDGAF03 DG "A" air intake structure 208 2JSGAUVO134A AF turbine steam supply heat up 225 2JSGAUV138A AF turbine steam supply heat up (Train A) 280 2JSIAUV0674 SUMP isolation valve 115 2EPBBS04 4.16 kV bus S04 PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 15 [

WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page F-17 Seismic Walkdown Equipment List, Rev. 3 NTTF Recommendation 2.3: Seismic Walkdown Attachment 3 - SWEL Sort Tables Palo Verde Nuclear Station - Unit 2 Table 3-3: Sort of the Base List 1 data based on "Equipment Type" (Note: Equipment type 4 (transformers) are not mentioned as they are part of larger parent equipment (i.e.,

switchgear, load centers). Additionally, EQ type 12 (Air Compressors) and 13 (Motor Generators) are not included as Palo Verde does not have any safety related equipment in this category.)

Equipment Type Description Number of Items Number of Items Number in Base List 1 Selected for SWEL 1 0 Miscellaneous 13 5 1 Motor Control Centers 13 7 2 Low Voltage Switchgear 12 4 3 Medium Voltage Switchgear 2 1 4 Transformers 0 0 5 Horizontal Pumps 11 6 6 Vertical Pumps 8 3 7 Fluid Operated Valves 23 8 8 Motor Operated Valves, Solenoid Operated Valves 117 34 9 Fans 8 3 10 Air Handlers 10 7 11 Chillers 2 1 12 Air Compressors 0 0 13 Motor Generators 0 0 14 Distribution Panels 41 4 15 Batteries on Racks 4 3 16 Battery Chargers and Inverters 12 6 17 Engine Generators 2 1 18 Instruments on Racks 74 14 19 Temperature Sensors 3 2 20 Instrumentation and Control Panels and Racks 40 7 21 Tanks and Heat Exchangers (GIP Section 7) 20 8 I

PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 16 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page F-18 Seismic Walkdown Equipment List, Rev. 3 NTTF Recommendation 2.3: Seismic Walkdown Attachment 3 - SWEL Sort Tables Palo Verde Nuclear Station - Unit 2 Table 3-4: Sort of the Base List 1 data based on "Environment (Temperature)"

(Since the PVNGS Units are located in a dry environment, it was decided to classify the environments based on the maximum design temperature of the equipment rooms. Temperature values were determined from a review of the EQ DBM and the UFSAR.)

Temperature Number of Items Number of Items (7F) in Base List 1 Selected for SWEL 1 80 143 (All inside) 45 (All inside) 104 150 (All inside) 43 (All inside) 113 8 (2 inside and 6 outside) 4 (2 inside and 2 outside) 120 62 (All inside) 13 (All inside) 122 6 (2 inside and 4 outside) 2 (All outside) 124 18 (All inside) 7 (All inside) 140 28 (All inside) 10 (All inside)

I I PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 17 1 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page F-19 Seismic Walkdown Equipment List, Rev. 3 NTTF Recommendation 2.3: Seismic Walkdown Attachment 3 - SWEL Sort Tables Palo Verde Nuclear Station - Unit 2 Table 3-5: Sort of the Base List 1 data based on Risk Achievement Worth (RAW) and the Availability of the Associated Train Base Walkdown Is the Train List 1 Equipment Description RAW IsathelTrain Item Unavailable?

45 2MCTET01 CST (condensate storage tank) 30500 No 40 2MCHET01 RWT (refueling water tank) 56.89 No 113 2EPBAS03 4.16 kV bus SO3 15.27 No 133 2EPKAF11 DC battery "A" 12.62 No 120 2EPGAL35 480 V LC35 bus 3.06 No 126 2EPHAM35 480 V MCC M35 3.06 No 119 2EPGAL33 480 V LC33 bus 3.03 No 125 2EPHAM33 480 V MCC M33 2.87 No 43 2JCTAHV0001 CST isolation valve 2.62 No 44 2JCTAHV0004 CST isolation valve 2.62 No 337 2MSPAP01 Spray pond pump "A" Low Risk No 279 2JSIAUV0673 SUMP isolation valve Low Risk No 280 2JSIAUVO674 SUMP isolation valve Low Risk No 87 2MHDAA01 DG "A" room EAHU fan Low Risk No 88 2MHDAJO1 DG "A" room essential exhaust fan Low Risk No 118 2EPGAL31 480 V LC31 bus Low Risk No 124 2EPHAM31 480 V MCC M31 Low Risk No 37 2JCHEHV0532 RWT suction iso (fails open on loss of air) Low Risk No 262 2MSIAP02 HPSI pump "A" Low Risk No 265 2JSlAPSV0417 HPSI train "A" injection to EDT relief Low Risk No 62 2MEWAP01 EW pump "A" Low Risk No 63 2MEWAT01 EW "A" surge tank Low Risk No 17 2JCHAHV0531 RWT outlet to Sl train "A" Low Risk No 253 2JSIAHV0684 Containment Spray Pump A Discharge To Shutdown Cooling Heat Exchanger A Valve Low Risk No I

PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 18 I WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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Item 278 2JSIAUV0666 HPSI pump "A"recirc iso (closes on RAS) Low Risk No 61 2MEWAE01 EW "A" heat exchanger Low Risk No 116 2EPEAG01 Emergency diesel generator "A" Low Risk No 249 2JSIAHV0604 RC loop 1 long term recirc valve Low Risk No 329 2JSIDHV331 RC loop 2 long term recirc Low Risk No 56 2JECATV0029 Control room "A" EAHU flow reg valve Low Risk No 91 2MHJAF04 Control room EAHU (fan, filters and HX) Low Risk No 53 2MECAE01 Essential chiller "A" Low Risk No 54 2MECAP01 Circulating water pump "A" Low Risk No 127 2EPHAM37 480 V MCC M37 Low Risk No 270 2JSIAUV0634 Safety Injection Tank 1A Discharge Isolation Globe Valve Low Risk No 272 2JSIAUV0644 Safety Injection Tank 1B Discharge Isolation Globe Valve Low Risk No 3 2JAFAHV0032 SG-E01A reg valve Low Risk No 5 2JAFAUVO037 SG-E01B isolation valve Low Risk No 13 2JAFCHV0033 SG-E01B reg valve Low Risk No 38 2JCHEHV0536 RWT suction isolation Low Risk No 277 2JSIAUV0664 Containment Spray Pump Recirculation To Refueling Water Tank Train A Globe Valve Low Risk No 143 2EPKCF13 DC battery "C" Low Risk No 148 2EPKDF14 DC battery "D" Low Risk No 19 2MCHAP01 Charging pump 1 Low Risk No 114 2EPBAU01 Selector Switch For 125 VDC To 2EPBAS03S From Either Panel Distribution Or Battery Charger A Low Risk No 146 2EPKCN43 Inverter For Shutdown Cooling Isolation Valve 2JSICUV653 Low Risk No 151 2EPKDN44 Inverter For 2JSIDUV654 Shutdown Cooling B Return Inside Containment Isolation Valve Low Risk No 198 2JSGAHV0179 Atmospheric dump valve HV-179 Low Risk No 199 2JSGAHV0184 Atmospheric dump valve HV-184 Low Risk No 233 2JSGDHY0185S SG-2 Line 1 Atmospheric Dump Solenoid Low Risk No 254 2JSIAHV0685 SDHX "A" isolation valve Low Risk No I

PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 19 I WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page F-21 Seismic Walkdown Equipment List, Rev. 3 NTTF Recommendation 2.3: Seismic Walkdown Attachment 3 - SWEL Sort Tables Palo Verde Nuclear Station - Unit 2 Base Walkdown RAW Is the Train List 1 Equipment Description Unavailable?

Item 263 2MSIAP03 Containment Spray Pump A Low Risk No 274 2JSIAUVO651 RC loop 1 long term recirc/SDC valve Low Risk No 1 2JAFAFT0040A Auxiliary feedwater flow Not Modeled in the PRA No 2 2JAFAFT0040B Auxiliary feedwater flow Not Modeled in the PRA No 4 2MAFAP01 AFA-KO1 turbine oil cooler Not Modeled in the PRA No 15 2JCHAHV0205 Auxiliary pressurizer spray valve Not Modeled in the PRA No 16 2JCHAHV0524 Charging pumps to regen HX isolation Not Modeled in the PRA No 21 2JCHAUVO516 Reactor Coolant Letdown Line To Regenerative Heat Exchanger Isolation Globe Valve Not Modeled in the PRA No 34 2MCHEEO1 Regenerative heat exchanger Not Modeled in the PRA No 36 2JCHEPDVO240 Charging Line To Reactor Coolant Loop 2A Isolation Globe Valve Not Modeled in the PRA No 39 2MCHEP01 Charging pump 3 Not Modeled in the PRA No 41 2JCPAUVO004B Containment Power Access Purge Exhaust Isolation Butterfly Damper Not Modeled in the PRA No 46 2MDFAT02 DG "A" fuel oil day tank Not Modeled in the PRA No 47 2MDGAF03 DG "A" air intake structure Not Modeled in the PRA No 48 2MDGAX01A Starting air accumulator Not Modeled in the PRA No 49 2MDGAXO1B Starting air accumulator Not Modeled in the PRA No 55 2MECAT01 EC expansion tank "A" Not Modeled in the PRA No 64 2JEWAUVO065 EC/NCWS cross tie valve Not Modeled in the PRA No 65 2JEWAUVO145 EC/NCWS cross tie valve Not Modeled in the PRA No 69 2JGAAUVO002 High Pressure Nitrogen Supply Header Containment Isolation Gate Valve Not Modeled in the PRA No 71 2MHAAZO1 HPSI pump room "A" EAHU Not Modeled in the PRA No 72 2MHAAZO2 LPSI pump room "A"EAHU Not Modeled in the PRA No 73 2MHAAZO4 AFW pump room "A" EAHU Not Modeled in the PRA No 74 2MHAAZO5 ECW pump room "A" EAHU Not Modeled in the PRA No 75 2JHCAPT0351A Containment pressure Not Modeled in the PRA No 76 2JHCAPT0352A Containment pressure Not Modeled in the PRA No 77 2JHCAUVO045 Discharge Sampling From RU-i Containment Isolation Valve Not Modeled in the PRA No PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 20 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page F-22 Seismic Walkdown Equipment List, Rev. 3 NTTF Recommendation 2.3: Seismic Walkdown Attachment 3 - SWEL Sort Tables Palo Verde Nuclear Station - Unit 2 Base Walkdown List I Equipment Description RAW Isthe Train Item Unavailable?

78 2JHCAUVO046 Inlet Sampling To RU-1 Containment Isolation Valve Not Modeled in the PRA No 83 2JHCCPT0351C Containment pressure Not Modeled in the PRA No 84 2JHCCPT0352C Containment pressure Not Modeled in the PRA No 92 2MHJAJO1A Battery room "A" essential exhaust fan Not Modeled in the PRA No 94 2MHJAM02 motor-operated damper Not Modeled in the PRA No 95 2MHJAM03 motor-operated damper Not Modeled in the PRA No 96 2JHJAM34 Pneumatic Damper HJAM34 Solenoid Not Modeled in the PRA No 97 2MHJAM62 Air-operated damper Not Modeled in the PRA No 98 2JHJATIC0123 Control room temp indicating controller Not Modeled in the PRA No 99 2MHJAZO3 ESF switchgear room "A"EAHU Not Modeled in the PRA No 100 2MHJAZO4 DC room "A"EAHU Not Modeled in the PRA No 112 2JIAAUVO002 Instrument Air Supply Containment Isolation Gate Valve Not Modeled in the PRA No 132 2EPKAD21 LC 33 control power Not Modeled in the PRA No 134 2EPKAH11 Battery charger "A" Not Modeled in the PRA No 135 2EPKAH15 125 VDC Class 1E Battery Charger AC Not Modeled in the PRA No 136 2EPKAM41 DC power to TCB1 control circuit Not Modeled in the PRA No 147 2EPKDD24 DC distribution panel D24 Not Modeled in the PRA No 150 2EPKDM44 DC power to TCB1 control circuit Not Modeled in the PRA No 152 2EPNAD25 Power to PPS "A" instrumentation Not Modeled in the PRA No 153 2EPNAN11 DC/AC inverter "A" Not Modeled in the PRA No 154 2EPNAV25 120 V vital ac voltage regulator "A" Not Modeled in the PRA No 160 2EPNCV27 120 V vital ac voltage regulator "C" Not Modeled in the PRA No 161 2EPNDD28 Power to PPS "D" instrumentation Not Modeled in the PRA No 162 2EPNDN14 DC/AC inverter "D" Not Modeled in the PRA No 163 2EPNDV28 120 V vital ac voltage regulator "D" Not Modeled in the PRA No 164 RCAPT0102A Przr pressure (required for RPS/SIAS) Not Modeled in the PRA No 165 RCAPT103 SDC RCS pressure interlock Not Modeled in the PRA No I

PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 21 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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166 2JSBAC02A I/V converter Not Modeled in the PRA No 178 2JSBDC02A I/V converter Not Modeled in the PRA No 179 2JRCNTE101 Pressurizer temperature Not Modeled in the PRA No 181 2JRDBUVO024 Isolation Containment Radwaste Sump Outlet Isolation Gate Valve Not Modeled in the PRA No 182 2JRMAB02 RWT level Not Modeled in the PRA No 183 2J2JRMAB04 RCS temperature Not Modeled in the PRA No 184 2JRMAB05 Containment pressure Not Modeled in the PRA No 185 2JRMAB06 Auxiliary feedwater flow Not Modeled in the PRA No 191 2JRMDBO5 Containment pressure Not Modeled in the PRA No 193 2JRMNBO4 Pressurizer temperature Not Modeled in the PRA No 194 2JSBAC03 Reactor trip breaker "A" Not Modeled in the PRA No 200 2JSGALT1113A SG-EO1A WR level (required for AFAS) Not Modeled in the PRA No 204 2JSGAPT0313 Instrument air line pressure transmitter Not Modeled in the PRA No 207 2JSGAUVO134 AF turbine steam supply Not Modeled in the PRA No 208 2JSGAUVO134A AF turbine steam supply heat up Not Modeled in the PRA No 224 2JSGAUV138 AF turbine steam supply (Train A) Not Modeled in the PRA No 225 2JSGAUV138A AF turbine steam supply heat up (Train A) Not Modeled in the PRA No 276 2JSIAUVO660 SI train "A" recirc (closes on RAS) Not Modeled in the PRA No 336 2JSINPT391 HPSI long term recirc loop 1 pressure xmtr Not Modeled in the PRA No 339 2MHSAJO1 Spray pond pump house exhaust fan "A" Not Modeled in the PRA No 415 2JCTALT035 CST Level indicator Not Modeled in the PRA No I

PVNGS Unit 2 Seismic Walkdown Equipment List May 21, 2013 Page 22 1 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page G-1 APPENDIX G - SWEL DEVELOPMENT TABLES There were no changes to the equipment selected for Base List 1, but two items were removed from SWEL 1 because they were inaccessible in a locked high-radiation area (discussed in Section 3.4).

There were no changes to Base List 2 and SWEL 2.

Table G-i: PVNGS-2 Base List 1 (Refer to Table G-1 of Reference 48, "Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2")

WCAP-17680-NP, Supplement I Revision 0 PVNGS-2 August 2013

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Basis?) Support) equipment? 0 for enhancement?

"Outside")

I 2JAFAFT0040A Auxiliary MSSS Yes Yes PC DHR Inst. Rack AF No 140(l) No No feedwater flow (18)

AuxiiaryInst. Rack 2 2JAAF000Bfeedwater 2JAFAFT0040B Auxiliary floww MSSS Yes Yes PC DHR (18)

Is) AF No 104 (1) No No SG-EOIA 3 2JAFAHV0032 regulating MSSS Yes Yes PC DHR MOV (8) AF No 140 (l) No No valve AFA-KOl Horz.

4 2MAFAP01 turbine oil MSSS Yes Yes PC DHR Pump (5) AF No 104 (l) No No cooler SG-E01B 5 2JAFAUVO037 isolation valve MSSS Yes Yes PC DHR MOV (8) AF Yes 1040() No No SG-E0IB 6 2JAFCHV0033 regulating MSSS Yes Yes PC DHR MOV (8) AF No 120 (I) No No valve Auxiliary 7 2JCHAHV0205 pressurizer CTMT Yes Yes PC SOV (7) CH No 104 (1) No Yes spray valve Charging 8 2JCHAHV0524 pumps to regen AUX Yes Yes PC MOV (8) CH No 104 (l) No No HX isolation RWT outlet to AUX Yes Yes ICDHR MOV (8) CH No 104(l) No No 2JCHAHV0531 SI train "A" AUX YeIeC___O _CH No I8) 104 _,_)_NoNo 10 2MCHAPOI Charging pump SYIC AUX Yes Yes RC PC Horz.(5)

Pump CH No 120(1) No No WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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Basis?) Support) equipment? 0 for "Outside")

Reaetef 6 t -vlint 2JIG AUV *5l (This item was removed from SWEL 1 in eTA4 4es R CIC. 110,() C44 Ne 120(i) NO Supplement I of this report.

See Section 3.4.) heat e4...ie gi..

2N4C'rHEEP1 (This item was l4eat 4 removed from SWEL I in ..... .,0 YA4 R) NO Supplement 1 of this report. heat

.eha.ge. (2-.-)

See Section 3.4.) (-_-4-)

Charging 13 2JCHEPDVO240 header to RCS CTMT Yes Yes RC IC POV (7) CH No 104 (1) No Yes backpressure control valve RWT suction 14 2JCHEHV0532 iso (fails open AUX Yes Yes RC PC POV (7) CH No 104 (1) No No on loss of air) 15 2JCHEHV0536 RWTsuction AUX Yes Yes RC PC MOV (8) CH No 104(l) No No isolation _____

16 2MCHEP0i Charging pump AUX Yes Yes RC PC Horz. CH No 113(0) No No 3 IC Pump (5)

RWT RC PC 17 2MCHET01 (refueling Yard Yes Yes IC DHR Tank (21) CH No 120(1) No No water tank)

Containment power access 18 2JCPAUVO004B purge exhaust CTMT Yes Yes CF MOV (8) CP No 113 (1) No Yes isolation butterfly damper 19 2JCTAHV0001 CST isolation CST Yes Yes PC DHR MOV (8) CT No 113(l) No No valve 20 2JCTAHV0004 CST isolation CST Yes Yes PC DHR MOV (8) CT No 113 (0) No No I____ valve _______________________ I____ I____ _____

Revision 0 Supplement 1 WCAP-17680-NP, Supplement A Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolaNd Page G-4 Table G-2: PVNGS-2 SWEL 1 Screen #4 Sample Considerations Screen Screen Environment Walkdown SWEL #1 Screen #2 #3 Major new Temp., 'F Deferred Item Walkdown Equipment Description Building (SC - 1 (Regular (Safety Equipment System or (I for uPEEE to Number Licensing Inspections?) Function Class Type replacement "Inside" or vulnerability Outage?

Basis?) Support) equipment? 0 for "Outside")

CST 21 2MCTET0I (condensate Yard Yes Yes PC DHR Tank (21 ) CT No 1400() No No storage tank)________

22 2MDFAT02 DO "A"ftael DG Yes Yes RC PC Tank (21) DF No 140(f) No No oil day tank ____IC DHR DO "A" sir RC PC 23 2MDGAF03 intake tilter DG Yes Yes IC DHR Other (0) DO Yes 140 () No No Starting air DG YsYs RC PC 24 2MDGAX0IA accumulator D Yes Yes IC DHR Tank (21) DG No 140 (l) No No Starting air RC PC 25 2MDGAXOIB accumulator DG Yes Yes IC DHR Tank (21) DG No 800() No No Essential RC PC 26 2MECAE01 chillerA" CTRL Yes Yes ICDHR Chiller (11) EC No 80 (1) No No Circulating RC PC Horz Pump 27 2MECAPOI water pump CTRL Yes Yes RC H o Pum EC No 80(1) No No "A" IC D-R (5) 28 2MECAT01 EC expansion CTRL Yes Yes RC PC Tank (21) EC No 80(1) No No tank "A" IC DHR Control room 29 2JECATV0029 "A" EAHU CTR Yes Yes PC IC POV (7) EC No 104(1) No No flow regulating DHR valve EW "A" heat EW""Het APC CIIC Heat Exchanger EW Yes 104 (1) No No 30 2MEWAE01 exchanger AUX Yes Yes DHR Eca2 31 2MEWAP01 EW pump "A" AUX Yes Yes PC IC Horz(5)Pump EW No 104 (1) No No DHR WCAP- 17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

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Basis?) Support) equipment? 0 for "Outside")

32 2MEWATOI EW "A" surge AUX Yes Yes P Tank (21) EW No 104 (1) No No tank DHR 33 2JEWAUVO065 EC/NCWS AUX Yes Yes PC IC MOV (8) EW No 104 (l) No No cross tie valve AX Yses DHR 34 2JEWAUVOI45 ECINCWS AUX Yes Yes PC IC MOV (8) EW No 104 (0) No No cross tie valve AX Yses DHR High Pressure Nitrogen 35 2JGAAUV0002 Supply Header AUX Yes Yes CF SOV (8) GA No 104 (l) No No Containment Isolation Gate Valve HPSI pump PC IC 36 2MHAAZ01 room "A" AUX Yes Yes DHR AHU (10) HA No 104 (1) No No EAHU LPSI pump PC IC 37 2MHAAZO2 room "A" AUX Yes Yes DHR AHU (10) HA No 104 (I) No No EAHU AFW pump PC IC 38 2MHAAZO4 room "A" MSSS Yes Yes DHR AHU (10) HA No 104 (l) No No EAHU ECW pump PC IC 39 2MHAAZO5 room "A" AUX Yes Yes PC AHU (10) HA No 104 (1) No No EAHU DHR 40 2JHCAPT035IA Containment AUX Yes Yes CF Inst. Rack HC No 104 (I) No No pressure (18) 41 2JHCAPT0352A Containment AUX Yes Yes CF Inst. Rack HC No 1041) No No pressure (18)

WCAP-17680-NP, Supplement I Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page G-6 Table G-2: PVNGS-2 SWEL 1 Screen #4 Sample Considerations Screen Screen Environment Walkdown SWEL #1 Screen #2 #3 Major new Temp., 'F Deferred Item Walkdown Equipment Description Building (SC - I (Regular (Safety Equipment System or (n for IPEEE to Number Licensing Inspections?) Function Class Type replacement "Inside" or vulnerability ta Clas Tpe eplcemnt Insde"or enhancement? Outage?

Basis?) Support) equipment? 0 for "Outside")

Discharge Sampling From 42 2JHCAUV0045 RU-I AUX Yes Yes CF SOV (8) HC No 104(1) No No Containment Isolation Valve Inlet Sampling To RU-I 43 2JHCAUVO046 Containment AUX Yes Yes CF SOV (8) HC No 104 (l) No No Isolation Valve 44 2JHCCPT0351C Containment AUX Yes Yes CF Inst. Rack HC No 104 (l) No No 45 2JHCCPT0352C Containment AUX Yes Yes CF Inst. Rack HC No 140 (l) No No pressure (18) 46 2MHDAA0I DG "A"room DG Yes Yes PC IC Fan (9) HD No 140 (I) No No EAHU fan DHR DG "A" room PC IC 47 2MHDAJ01 essential DG Yes Yes PC Fan (9) HD No 80 (1) No No exhaust fan DHR Control room PC IC 48 2MHJAF04 EAHU (fan, CTRL Yes Yes DHR Al-U (10) Hi No 80(1) No No filters and IX) D Battery room PC IC 49 2MHJAJ0IA "A" essential CTRL Yes Yes PC Fan (9) HJ No 80 (l) No No exhaust fan DHR 50 2MHJAM02 motor-operated PC IC MOV (8) HJ No 80 (1) No No damper CTRL Yes Yes DHR 51 2MHJAM03 motor-operated CTRL Yes Yes MOV (8) HJ No 80(1) No No damper DHR Pneumatic 52 2JJAM34Damper 52 2JHJAM34 DJAM34 CTRL Yes Yes DHR POV (7) HJ No 80(I) No No Solenoid WCAP-17680-NP, Supplement I Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page G-7 Table G-2: PVNGS-2 SWEL I Screen #4 Sample Considerations Screen Screen Environment Walkdown SWEL #1 Screen #2 #3 Major new Temp., *F Deferred Item Walkdown Equipment Description Building (SC - I (Regular (Safety Eqimn Equipment System oor (n1frto for IPEEE D r Number Licensing Inspections?) Function Class Type replacement "Inside" or vulnerability Basis?) Support) equipment? 0 for enhancement Outage?

"Outside")

53 2MHJAM62 Pneumatie CTRL Yes Yes PC POV (7) HJ No 80 (1) No No damper DHR Control room PC IC Temp 54 2JHJATICO123 temp indicating CTRL Yes Yes DHR Sensor (19) Hi No 80(1) No No controller ESF 55 2MHJAZO3 switchgear CTRL Yes Yes PC IC AHU (10) HJ No 80(H) No No room "A" DHRI EAHU 56 2MHJAZO4 DC room "A" CTRL Yes Yes PC IC AHU (10) HJ No 104 (I) No No EAHFU DHR Instrument Air Supply 57 2JIAAUVO002 Containment AUX Yes Yes CF SOV (8) IA No 80(I) No No Isolation Gate Valve 2EPBBS04 2EBS44.16 kV bus RC PC RPC Med. Volt 58 (substitute for 4 CTRL Yes Yes IC DHR Med. Vol PB Yes 80(l) No Yes 2EPBAS03) S04CF SWGR (3)

Selector Switch For 125 VDC To 2EPBAS03S Wall 59 2EPBAU01 From Either CTRL Yes Yes PC DHR Mount PB No 140 (1) No No Panel Cont. (I)

Distribution Or Battery Charger A Emergency RC PC Eng. Gen.

60 2EPEAGOI diesel DG Yes Yes IC PC Eng. PE No 80(I) No No generator "A" IC DHR (17) 480 V LC32 RC PC Low Volt.

61 (substitute for bus CTRL Yes Yes DHR SWGR (2)80() No No 2EPGAL3 1) 1 1_1_1_1_1_1_1_1_1 _ 1 WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page G-8 Table G-2: PVNGS-2 SWEL I Screen #4 Sample Considerations Screen Screen Environment Walkdown SWEL #1 Screen #2 #3 Major new Temp., IF Item Walkdown Equipment Description Building (SC - I (Regular (Safety Equipment System or (n for IPEEE Deferredto Number Licensing Inspections?) Function Class Type Clas Tpereplacement eplcemnt "Inside" Insde"or or vulnerability enhancement? ta Outage?

Basis?) Support) equipment? 0 for "Outside")

480 V LC34 RC PC Low Volt.

62 (substitute for bus CTRL Yes Yes DHR SWGR 12) PG No 80 (t) No No 2EPGAL33) 2EPGAL36) 2EPHAM35I) 2EPHBM32 bus__D__RSWGR__(2) 480 V TCYe RC PC MCw PN4tN 64 (substitute for M32CTRL Yes Yes DHRP No 0() No No 2E4480 H M V MCC 2EPHBM34 s RC PC MC (1 65 (substitute for M3 CC AUX Yes Yes R MCC (1) PH No 104 (1) No No 2EPHAM33) 2EPHBM36 48O V MCC RC PC 6 (substitute for M36 AUX Yes Yes DHR MCC (1) PH No 1040() No No 2EPHAM35) 2EPHBM38 480 V MCC RC PC 67 (substitute for M38 AUX Yes Yes DHR MCC (I) PH No 80(1) No No 2EPHAM37) 2EPKBD22 68 (substitute for Lw34r CTRL Yes Yes DHR PC (Pn) PK No 80 (l) No No 2EPKAD21) LC 4 ontolRC PC BattPaery 69 2EPKAFII DC battery "A" CTRL Yes Yes Ys RC DHR PC Battery Rack 015) PK No 80(1) No No 70 2EPKAHI Battery charger RC PC Battery PK No 80(1) No No "A" CTRL Yes Yes DHR Chg (16) 125 VDC Class RC PC Battery 71 2EPKAH15 I E battery CTRL Yes Yes IC DHR Chg (16) PK No 80(1) No No charger AC 2EPKBM42 DC power to 72 (substitute for TCB I control CTRL Yes Yes RC PC MCC (1) PK No 80 (1) No No 2EPKAM41) circuit 73 2EPKCF 13 DC battery "C" CTRL I . Yes IIDHRYes RC P Rack (15) attery) PK Noo8 80(1) 1) Noo No WCAP-17680-NP, Supplement I Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page G-9 Table G-2: PVNGS-2 SWEL 1 Screen #4 Sample Considerations Screen Screen Environment Walkdown SWEL #1 Screen #2 #3 Major new Temp., 'F Item Walkdown Equipment Description Building (SC - I (Regular (Safety Equipment System or (n for IPEEE Deferredto Number Licensing Inspections?) Function Class Type replacement "Inside" or vulnerability to Basis?) Support) equipment? 0 for enhancement?

"Outside")

Inverter for shutdown Inverter PKo8(1Noo 74 2EPKCN43 cooling CTRL Yes Yes DHR (16) PK No 80(1) No No isolation valve

_2JSICUV653 75 2EPKDD24 DC distribution CTRL Yes Yes RC PC Dist Panel PK No 80(1) No No panel D24 DHR (14) 76 2EPKDF14 DCbattery"D" CTRL Yes Yes RC PC Battery PK No 800() No No DHR Rack (15)

DC power to 77 2EPKDM44 TCB I control CTRL Yes Yes RC PC MCC (1) PK No 80(l) No No circuit Inverter for 2JSIDUV654 shutdown Inverter 78 2EPKDN44 cooling B CTRL Yes Yes CF (16) PK No 80(1) No No return inside containment isolation valve Power to PPS RC PC Dist Panel 79 2EPNAD25 "A" CTRL Yes Yes IC DHR (1D4) PN No 80 (I) No No instrumentation DC/AC P C Ivre 80 2EPNAN II i1ere CTRL Yes Yes PC IC Inverter PN No 80(1) No No inverter "A" DHR CF (16) 120 V vital ac PC IC 81 2EPNAV25 voltage CTRL Yes Yes DHR CF Other (0) PN No 80(1) No No regulator "A" 120 V vital ac PC IC 82 2EPNCV27 voltage CTRL Yes Yes DHR CF Other (0) PN No 80 (1) No No regulator "C" Power to PPS RC PC Dist Panel 83 2EPNDD28 "D" CTRL Yes Yes RC PC D14) PN No 80(1) No No instrumentation WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page G-10 Table G-2: PVNGS-2 SWEL 1 Screen #4 Sample Considerations Screen Screen SWEL Environment Walkdown

1. 1 Screen #2 #3 Major new Temp., IF Deferred Item Walkdown Equipment Description Building (SC - I (Regular (Safety' Equipment System or (I for vPEEErabirrtyto Number Licensing Inspections?) Function Class Type replacement "Inside" or vulnerability Outage?

Basis?) Support) equipment? 0 for "Outside")

DC/AC PC IC Inverter 84 2EPNDN 14 D "13" inverter CTRL Yes Yes DC CF DHR (6 (16) PN No 80(l) No No 120 V vital ac PC IC 85 2EPNDV28 voltage CTRL Yes Yes DHR CF Other (0) PN No 120(1) No No regulator "D" Przr pressure Inst. Rack 86 2JRCAPT0102A (required tbr CTMT Yes Yes PC (18) RC No 120 (1) No Yes RPS/SIAS)

SDC RCS Inst. Rack 87 2JRCAPT103 pressure CTMT Yes Yes DHR (18) RC No 80 (l) No Yes interlock 88 2JSBAC02A ILV converter CTRL Yes Yes DHR Inst. Rack RC No 120(1) No No (18) 89 2JSBDC02A IVV converter CTRL Yes Yes DHR Inst. Rack RC No 120 (1) No No (18) 90 2JRCNTE101 Pressurizer CTMT Yes Yes PC Temp RC No 1046() No Yes temperature Sensor (19)

Isolation Containment 91 2JRDBUVO024 Radwaste Sump Outlet AUX Yes Yes CF MOV (8) RD No 80(1) No No Isolation Gate Valve 1 RC IC Control 92 2JRMAB02 RWT level CTRL Yes Yes DHR Panel (20) RM No 80(1) No No 93 2JRMAB04 RCS CTRL Yes Yes RC Control RM No 80(1) No No temperature Panel (20) 94tanmntControl RMN801Noo 94 2JRMAB05 Containment CTRL Yes Yes CF nl RM No 80() No No pressure Panel (20)

WCAP-17680-NP, Supplement I Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page G-11 Table G-2: PVNGS-2 SWEL 1 Screen #4 Sample Considerations Screen Screen Environment Walkdown SWEL #1 Screen #2 #3 Major new Temp., IF Item Walkdown Equipment Description Building (SC - 1 (Regular (Safety Equipment System or (I for IPEEE Deferredto Number Licensing Inspections?) Function Class Type replacement "Inside" or vulnerability to Basis?) Support) equipment? 0 for enhancement?

"Outside")

95 2JRMAB06 Auxiliary CTRL Yes Yes PC DHR Control RM No 80 (1) No No feedwater flow Panel (20) 96 2JRMDB05 Containment CTRL Yes Yes CF Control RM No 80 (0) No No pressure Panel (20) 97 2 Pressurizer CTRL Yes Yes PC Control RM No 1040) No No 9JRM.ALNB04 temperature Panel (20)

Reactor trip AUX Yes Yes RC PC Breaker 98 2JSBAC03 breaker "A" Panel (2) SB No 124 (1) No No Atmospheric 99 2JSGAHV0179 dump valve MSSS Yes Yes PC DHR POV (7) SG No 124 () No No HV-179 Atmospheric 100 2JSGAHV0184 dump valve MSSS Yes Yes PC DHR POV (7) SG No 120 (1) No No HV-184 SG-EOIA WR 101 2JSGALTI I 13A level (required CTMT Yes Yes DHR ns SG No 104 (1) No Yes for AFAS) (18)

Instrument air Inst. Rack 102 2JSGAPT0313 line pressure MSSS Yes Yes PC DHR SG No 124 (I) No No transmitter (18)

AF turbine 103 2JSGAUVOI34 steam supply MSSS Yes Yes PC DHR MOV (8) SG No 124 (I) No No AF turbine 104 2JSGAUVOI34A steam supply MSSS Yes Yes PC DHR MOV (8) SG Yes 124 (1) No No heat up AF turbine 105 2JSGAUVI38 steam supply MSSS Yes Yes PC DHR MOV (8) SG No 124 (1) No No (Train A) I WCAP-17680-NP, Supplement I Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page G-12 Table G-2: PVNGS-2 SWEL 1 Screen #4 Sample Considerations Screen Screen Environment Walkdown SWEL #1 Screen #2 #3 Major new Temp., IF Deferred Item Walkdown Equipment Description Building (SC - I (Regular (Safety Equipment System or (n for IPEEE D r Number Licensing Inspections?) Function Class Type Clas Tpereplacement eplcemnt "Inside" Insde"or or vulnerability enhancement? to Outage?

Basis?) Support) equipment? 0 for "Outside")

AF turbine 106 2SGAUI38Asteam supply 106 2JSGAUVI38A heat up (Train MSSS Yes Yes PC DHR MOV (8) SG Yes 124 (l) No No A)

SG-2 Line I 107 2JSGDHY0185S Atmospheric MSSS Yes Yes PC DHR Inst. Rack SG No 104 (1) No No Dump (18)

Solenoid RC loop 1 108 2JSIAHV0604 long-term AUX Yes Yes IC DHR MOV (8) SI No 104 (1) No No recire valve Containment Spray Pump A Discharge To 109 2JSIAHV0684 Shutdown AUX Yes Yes CF MOV (8) SI No 104 (l) No No Cooling Heat Exchanger A Valve 110 2JSAHV65S D I-X"A" 110 2JSIAHV0685 isolation valve AUX Yes Yes DHR MOV (8) SI No 104 (l) No No IlI 2MSIAP02 HPSI pump AUX Yes Yes IC DHR Horz. SI No 104 (I) No No "A" Pump (5) 112 2MSIAP03 Containment AUX Yes Yes CF Vert. Pump SI No 104 (1) No No Spray Pump A (6)

HPSI train "A" 113 2JSIAPSVO417 injection to AUX Yes Yes IC DHR Other (0) SI No 120(1) No No EDT relief Safety injection tank 114 2JSIAUV0634 IA discharge CTMT Yes Yes RC IC MOV (8) SI No 120 (1) No Yes isolation globe valve WCAP-WCAP-17680-NP, Supplement 1I 17680-NP, Supplement 20130 Revision August Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page G-13 Table G-2: PVNGS-2 SWEL I Screen #4 Sample Considerations Screen Screen Environment Walkdown SWEL #1 Screen #2 #3 Major new Temp., IF Item Walkdown Equipment Description Building (SC - I (Regular (Safety Equipment System or (I for rafirrtyto IPEEE Number Licensing Inspections?) Function Class Type replacement "Inside" or vulnerability Outage?

Basis?) Support) equipment? 0 for "Outside")

Safety injection tank 115 2JSIAUV0644 IB discharge CTMT Yes Yes RC IC MOV (8) SI No 120 (l) No Yes isolation globe valve RC loop 1 116 2JSIAUV0651 long-term CTMT Yes Yes IC DHR MOV (8) Si Yes 104 (I) No Yes recirc/SDC valve SI train "A" 117 2JSIAUV0660 recirc (closes AUX Yes Yes IC DHR SOV (8) SI No 104 (l) No No on RAS)

Containment Spray Pump Recirculation 118 2JSIAUV0664 To Refueling AUX Yes Yes CF MOV (8) SI No 104 (1) No No Water Tank Train A Globe Valve HPSI pump 119 2JSIAUV0666 "A" recirc iso AUX Yes Yes IC DHR MOV (8) SI Yes 120(l) No No (closes on RAS) 120 2JSIAUV0673 Sump isolation CTMT Yes Yes IC DHR MOV (8) SI Yes 104 (l) No Yes valve 121 2JSIAUV0674 Sump isolation AUX Yes Yes IC DHR MOV (8) St Yes 104(f) No No valve RC loop 2 122 2JSIDHV331 long-term AUX Yes Yes IC DHR MOV (8) SI No 120 (1) No No recirc HPSI long-12teSIP39 tem 1ressire lo recirc CTMT Yes Yes IC DHR Inst.(18)Rack SI Noo12()N 122(0) No Yes S e l2 251PT9Iloop I pressure (8 xmtr 1 124 2MSPAPOI Spray pond SP Yes Yes PC DHR Vert. Pump SP No 122(0) No No pump "A" UHS (6)

WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page G-14 Table G-2: PVNGS-2 SWEL 1 Screen #4 Sample Considerations Screen Screen Environment Walkdown SWEL #1 Screen #2 #3 Major new Temp., F Deferred Item Walkdown Equipment Description Building (SC - 1 (Regular (Safety Equipment System or (I for IPEEE to Number Licensing Inspections?) Function Class Type replacement "Inside" or vulnerability Basis?) Support) equipment? 0 for enhancement?

"Outside")

Spray pond 125 2MHSAJOI pump house Y Yes PC DHR AHU (6) SP No 80(1) No No exhaust fan UHS "A"

126 2JCTALT035 2 CST Level CST Yes Yes RC IC Inst. Rack CT No 800() No No Indicator DHR (18) 1 1 1 The total number of SWEL 1 items is 124 instead of 126 because items 11 (2JCHAUVO516) and 12 (2MCHEEO1) were removed (see discussion in Section 3.4). The item numbers in the first column of this table were not adjusted to make it easier to compare the items to those in Table G-2 of Reference 48.

2 2JCTALT035 was added during the walkdown as a replacement for another piece of equipment that was inaccessible.

WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013

Enclosure Appendices A and B contain Security-Related Information - Withhold under 10 CFR 2.390 Upon separation this page is decontrolled Page G-15 Table G-3: PVNGS-2 Base List 2 (SWEL 2 is the same as Base List 2)

(Refer to Table G-3 of Reference 48, "Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2")

WCAP-17680-NP, Supplement 1 Revision 0 PVNGS-2 August 2013