ML12342A138

Engineering Report, JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3

ML12342A138
Person / Time
Site:	FitzPatrick
Issue date:	11/21/2012
From:	Losev Y, Pourghobadi P Entergy Nuclear
To:	Office of Nuclear Reactor Regulation
References
JAFP-12-0134 JAF-RPT-12-00015, Rev. 0
Download: ML12342A138 (208)

Text

JAF-RPT-1 2-00015 Rev. 0 JAF SEISMIC WALKDOWN REPORT FOR RESOLUTION OF FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION

2.3 SEISMIC

NOVEMBER 2012 BOOK 1 OF 3 0 Engineering Report No. JAF-RPT-12-00015 Rev 0 Page 1 of 44*Entergy ENTERGY NUCLEAR Engineering Report Cover Sheet Engineering Report Title: James A. FitzPatrick (JAF) Nuclear Power Plant Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic Engineering Report Type: New [ Revision Dl Cancelled El Superseded Superseded by: 11 IPA El ANO1 [iP2 E ANO2 []IP3 E ECH El Applicable Site(s)JAF 0 PNPS El GGNS [E RBs C3 vy 11 WF3 El wPo El PLP 0 EC No. EC40677 Report Origin: 0 Entergy El Vendor Vendor Document No.: Quality-Related:

El Yes[ No Prepared by: Prepared by: Reviewed by: Reviewed by: Reviewed by: Approved by: Approved by: Yaroslav Losev /15i<%..-..

Date: 11/z i/ia (Print Name/Sign)

Laura Maclay / 7 ".P" Other (Print Name/Sign)

JLI#Richard Casella / ; 44 0 4 Date: Other (Print Name/Sign)

/ 4I t Tom T. Panayotidi

/ýg Peer Review Team Leader (Print N Vincent Bacanskas/

ate: 112 ate: ate: Manager (Print Name/Sign)

D" Other (Pfint Name/Sign) 0 Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 2 of 44 James A. FitzPatrick (JAF) Nuclear Power Plant Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic TABLE OF CONTENTS Section Title Paqe 1.0 SCO PE AND O BJECTIVE .........................................................................................................................................

3 2.0 SEISMIC LICENSING BASIS

SUMMARY

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

4 2.1 SAFE SHUTDOWN EARTHQUAKE (SSE) .............................................................................................................

4 2.2 DESIGN CODES, STANDARDS, AND METHODS ...........................................................................................

5 3.0 SEISMIC WALKDOWN PROGRAM IMPLEMENTATION APPROACH ...............................................................

9 4.0 PERSONNEL QUALIFICATIONS

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

10 4.1 EQ UIPM ENT SELECTIO N PERSO NNEL ............................................................................................................

18 4.2 SEISM IC W ALKDOW N ENG IN EERS ...................................................................................................................

18 4.3 LIC EN S IN G BA S IS R EV IEW ER S .........................................................................................................................

18 4 .4 IP E E E R E V IE W E R S .............................................................................................................................................

18 4 .5 P E E R R EV IE W T E A M ..........................................................................................................................................

18 5.0 IPEEE VULNERABILITIES REPORTING

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

22 6.0 SEISMIC WALKDOWN EQUIPMENT LIST (SWEL) DEVELOPMENT

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

23 6.1 SAMPLE OF REQUIRED ITEMS FOR THE FIVE SAFETY FUNCTIONS

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

23 6.2 SPENT FUEL POOL ITEMS...-',............................

...........

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

26 6.3 DEFERRED, INACCESSIBLE ITEMS on SWEL ..............................................................................................

28 7.0 SEISMIC WALKDOWNS AND AREA WALK-BYS ..........................................................................................

32 7.1 S E IS M IC W A LK D O W N S .......................................................................................................................................

32 7 .2 A R E A W A LK -B Y S ....................................................................................................................................

...........

34 8.0 LICENSING BASIS EVALUATIONS

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

35 8.1 LIC ENS ING BASIS EVA LUATIO NS .....................................................................................................................

36 8.2 CORRECTIVE ACTION PROGRAM ENTRIES ...............................................................................................

36 8 .3 P LA N T C H A N G E S ................................................................................................................................................

36 9.0 PEER R EV IEW .........................................................................................................................................................

38 9.1 P E E R R EV IEW P R O C ES S .................................................................................................................................

38 9.2 PEER REVIEW RESULTS

SUMMARY

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

38 10.0 R EFER ENC ES ..........................................................................................................................................................

42 11.0 ATTAC H M ENTS ......................................................................................................................................................

44 ATTACHMENT A -IPEEE VULNERABILTIES TABLE ATTACHMENT B -SEISMIC WALKDOWN EQUIPMENT LISTS ATTACHMENT C -SEISMIC WALKDOWN CHECKLISTS (SWCs)ATTACHMENT D -AREA WALK-BY CHECKLISTS'(AWCs)

ATTACHMENT E -POTENTIALLY ADVERSE SEISMIC CONDITIONS ATTACHMENT F -LICENSING BASIS EVALUATION FORMS ATTACHMENT G -PEER REVIEW CHECKLIST FOR SWEL ATTACHMENT H -SEISMIC WALKDOWN ENGINEER TRAINING CERTIFICATES ATTACHMENT I -PEER REVIEW COMMENTS Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 3 of 44 O 1.0 SCOPE AND OBJECTIVE The Great Tohoku Earthquake of March 11, 2011 and the resulting tsunami caused an accident at the Fukushima Dai-ichi nuclear power plant in-Japan.

In response, to this accident, the Nuclear Regulatory Commission (NRC) established the Near-Term Task Force (NTTF). The NTTF was tasked with conducting a systematic and methodical review of NRC processes and regulations and determining if the agency should make additional improvements to its regulatory system. On March 12, 2012 the NRC issued a 10CFR50.54(f)

Letter, Pursuant to Title 10 of the Code of Federal Regulations Part 50, Subsection 54(f)Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident [Ref. 10.1], requesting information from all licensees to support the NRC staff's evaluation of several of the NTTF recommendations.

To support NTTF Recommendation 2.3, Enclosure 3 to the NRC requested that all licensees perform seismic walkdowns to gather and report information from the plant related to degraded, non-conforming, or unanalyzed conditions with respect to its current seismic licensing basis.The Electric Power Research Institute (EPRI), with support and direction from the Nuclear Energy Institute (NEI), published industry guidance for conducting and documenting the seismic walkdowns.

The guidance represented the results of extensive interaction between NRC, NEI, and other stakeholders.

This industry guidance document, EPRI Report 1025286* [Ref. 10.2], hereafter referred to as "the Guidance," was formally endorsed by the NRC on May 31, 2012. Entergy James A. FitzPatrick (JAF) Nuclear Power Plant has committed

[Ref.10.12] to using this' NRC-endorsed guidance-as the basis for conducting and documenting seismic walkdowns for resolution of NTTF Recommendation 2.3: Seismic.Entergy fleet procedure EN-DC-168, "Fukushima Near Term Task Force Recommendation

2.3 Seismic

Walk-Down Procedure" [Ref. 10:11], outlines the steps required to gather information as needed to respond to the March 12,2012, 10CFR50.54(f)

Letter as it pertains to the USNRC Near-Term Task Force (NTTF) Recommendation 2.3, Seismic.The objective of this report is to document the results of the seismic walkdown effort undertaken for resolution of, NTTF Recommendation 2.3: Seismic in accordance with the Guidance, and provide the information necessary for responding to Enclosure 3 to the 50.54(f) Letter. .

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 4 of 44.2.0 SEISMIC LICENSING BASIS

SUMMARY

JAF is a single unit BWR-4 (Boiling Water Reactor) with a Mark I containment, located in Oswego County, New York. General Electric (GE) designed the nuclear steam supply system and the turbine-generator.

Stone & Webster was the Architect/Engineer for the plant. JAF began commercial operation in July of 1975, and is currently rated at 2,536 MWt power [Ref.10.3, Section 1.2] and has a rated gross electrical output of approximately 881 MWe when operating at full power. This section summarizes the seismic licensing basis of structures, systems and components (SSCs) at JAF, which bound the context of the NTTF 2.3 Seismic Walkdown program.2.1 SAFE SHUTDOWN EARTHQUAKE (SSE)The seismic design for Class I structures (including the reactor building and all engineered safeguards) is based on dynamic analysis using acceleration response spectrum curves which are normalized to a ground motion of 0.08 g, for the Operating Basis Earthquake, and 0.15 g, for the Design Basis Earthquake.

The basis of this design criterion is presented in Reference 10.3, Section 2.6. Class I seismically designed structures may be referred to as"Seismic Class I" structures

[Ref. 10.3, Section 12.4.6.1].

• The horizontal seismic forces were determined using a lumped mass frequency response analysis considering flexural, translational and rocking (in some cases) response.

These analyses take into account' rock-structure interaction.

The vertical response spectrum is assumed to be two-thirds the horizontal response spectrum of each earthquake and is considered to act simultaneously.

Where applicable, the stresses are added directly.The damping value of 2 percent of critical for concrete structures under Operating Basis Earthquake is less than the range of 3 to 5 percent for design within code allowable stresses ,recommended by Newmark and Hall in their paper "Design Criteria for Nuclear Reactors Subject to Earthquake Hazards." Under the Operating Basis Earthquake, the stresses are within the allowable code stresses; therefore, little cracking will occur in the concrete.Newmark suggests a value of 7 to 10 percent of critical damping for stress levels at or just below yield point. To be conservative and minimize cracking in the concrete under the Design Basis Earthquake, 5 percent of critical damping is used.'Horizontal and vertical displacements due to Operating Basis and Design Basis Earthquakes are determined for all Class I structures.

Based on calculated displacements, adequate space is provided between adjacent structures to ensure that basic structural elements do not strike each other when subjected to the worst combination of rocking, bending and shear deflections and translation movements that might be induced by an earthquake.

All Class I Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 5 of 44 systems passing between adjacent structures are designed to withstand the maximum combination of movement between the adjacent structures without loss of function.

The effect of the relative movement between buildings is considered in the piping stress analysis and in the design and location of supports.'2.2 DESIGN CODES, STANDARDS, AND METHODS Class I structures and equipment are those that are necessary to ensure: a) the integrity of the reactor coolant pressure boundary, b) The capability to shut down the reactor and maintain it in a safe, shutdown condition, or c) the capability to prevent or mitigate the consequences of accidents that could result in potential off-site exposures comparable to the guidelines of 10 CFR 100. Class II structures and equipment are those which may be essential to operation of the plant, but are not included in Class I. Class III structures and equipment are those that are not included in Class I or Class I1. A "Component Quality Assurance Category List" further defines "Class I", "Class I1", or "Class II" structures, systems, and components as "Quality Assurance" (QA) SR, QP, or NSR. QA Categories SR, QP and NSR are synonymous with the previously used I, M and Il/111 (or II or III separately) categories, respectively.

[Ref. 10.3, Section 12.2.1].The Reference 10.8 document provides the basic criteria for the safety related Balance of* Plant (BOP) pipe stress analysis and pipe support qualification and/or design for the JAFNPP. BOP piping systems are those systems which are not part of the General Electric (GE) Nuclear Steam Supply System (NSSS). A listing of the seismically qualified BOP pipe lines is provided in Reference 10.8, Section 7.0.Class IE -The safety classification of the electric equipment and systems, including their supporting systems that are essential to emergency reactor shutdown, containment isolation, reactor core cooling, and containment and reactor heat removal, or otherwise are essential in mitigating the consequences of an accident [Ref. 10.10].Mechanical Equipment and Pipina Code Applicability" USAS (ANSI) B31.1, 1967 Edition through 1969 Addenda, Power Piping Code." ASME Boiler and Pressure Vessel Code for Nuclear Vessels,Section III, Subsection B, 1968 Edition including the 1968 Summer Addendum.Pipe SuDmort Code Applicability

• USAS (ANSI) B31.1, 1967 Edition through 1969 Addenda, Power Piping Code.* AISC Specification for Design, Fabrication, and Erection of Structural Steel for Buildings.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 6 of 44 Applicable USNRC Requlatory Guides Because JAFNPP was designed before the establishment of Regulatory Guides, no Regulatory Guide is directly applicable.

However, the Regulatory Guide 1.61, Revision 0, Damping Values for Seismic Design of Nuclear Power Plants, October 1973, was used for fluid transient analyses [10.8].The USNRC Regulatory Guide 1.92, Section 1.2.1 "The Grouping Method." [Ref. 10.3, Section 12.5.4], was used for combining modal responses in the seismic reanalysis for the Wide Range and Narrow Range reactor water level piping systems.Applicable IE Bulletins* IE Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts.* IE Bulletin 79-07, Seismic Stress Analysis of Safety-Related Piping.* IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Systems including all supplements." IE Bulletin 80-11, Masonry Wall Design.Mechanical Equipment and Equipment Support Analysis" Overall equipment structural response includes loads from nozzles, equipment deadweight, design pressure, operating temperature, equipment earthquake loads and other dynamic loads. Reference 10.8, Section 5.0, Tables 5.0-1 and 5.0-2A through 2E show the accepted equipment nozzle loads that were established during the plant design stage and later during the as-built stress analysis effort.* The criteria, method of analysis, and summary of critical stresses, for various equipment are included in UFSAR Table 16.2-7. [Ref. 10.3]Structures and Seismic Input to Structures and Equipment.

• The seismic motion induced at the pipe supports in the structure is likely to be different from the ground motions. Since the various parts of the structures oscillate in different magnitudes and directions, the piping systems are essentially subjected to different excitations at each pipe anchor and restraint location.

Therefore, amplified response spectra (ARS) for the maximum acceleration at various elevations throughout the structures are determined and the spectrum which is closest to and higher in elevation than the center of mass of piping is used. The JAF ARS curves are provided in Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 7 of 44 Attachment 3-3 (Vol. II), the design criteria for BOP piping stress and supports.

[Ref.10.8]The amplified response spectra were developed using the "Frequency Response Method", a modified Biggs method. A response spectrum is. an envelope of the maximum accelerations of a damped single-degree-freedom system with variable frequencies due to the building motion at a specific elevation.

The building motion at a specific elevation is approximated by a series of sinusoidal motions with the calculated building frequencies and their corresponding acceleration amplitudes at that elevation.

Specifically, the amplified response spectra were developed for several selected elevations of each building for Operating Basis and Design Basis Earthquakes for an equipment (piping) damping value of 0.5% and 1.0%, respectively.

[Ref. 10.8]Electrical Raceways* Reference 10.9 provides a standard for the routing of conduit and the selection of conduit supports.

This standard applies to Nuclear Generation personnel, and to any organization which performs design of seismic electrical conduit and conduit supports.This applies to Safety Related, Augmented Quality, and Non-Safety Related structures, systems and components

[Ref. 10.9].Seismic Interaction (spatial, fire, and flood)* The separation distance criteria between redundant electrical raceways at the time of JAF construction required separation of 3ft horizontally and 7ft vertically.

Using this criteria will result in conservative separation distances for redundant circuits.

JAF-RPT-ELEC-02075, Table 1 provides minimum allowable separation distances for redundant cables in General Plant Areas that may be used as alternate reduced separation distance criteria only for installations where the 3 feet horizontal

/ 7 foot vertical criteria stated in the UFSAR, Section 7.1.9 cannot be met [Ref. 10.10].e A safety design basis for the Primary Containment and Reactor Vessel Isolation Control System is to ensure closure of Group A (communicate with the Reactor Vessel) and Group B (communicate with Primary Containment Free Space) automatic isolation valves is initiated, when required, with sufficient reliability.

UFSAR, Section 7.3.2, states there is sufficient electrical and physical separation between trip channels monitoring the same essential.

variable to prevent environmental factors, electrical faults, and physical events, such as a fire, from impairing the ability of the system to respond correctly.

• The use of Generic Implementation Procedure (GIP) For Seismic Adequacy of Equipment and Parts, as modified and supplemented by the U.S. Nuclear Regulatory Commission Supplemental Safety Evaluation Report (SSER) No. 2 and SSER No. 3, Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 8 of 44 may be used as .an alternative method to existing methods for the seismic design and verification of existing, modified, new and replacement equipment and parts classified as Class 1.- Only those portions of the GIP listed in "Use of Generic Implementation Procedure (GIP) for New and Replacement Equipment and Parts (NARE)" shall be used. The other portions of the GIP are not applicable since they contain administrative, licensing, and documentation information which is applicable only to the Unresolved Safety Issue (USI) A-46 program [Ref. 10.3, Section 12.5.6].Automatic water sprays, are provided in the Reactor Building, at various area boundaries to isolate fire areas from each other. The water spray piping is seismically supported.

[Ref. 10.3, Section 9.8.3.1.4]

All fire protection water piping and mechanical equipment up to and including flow control valves in the Fire Protection Systems protecting Class I systems and components listed below are designed to QA Category QP criteria.1. High Pressure Coolant Injection Pump.2. Reactor Core Isolation Cooling Pump.3. Emergency Diesel-Generator Rooms.4. Diesel Driven Fire Pump.5. Standby Gas Treatment System Charcoal Filters.The fire protection piping for the Battery Room Corridor is seismically supported from the alarm check valve on manifold No. 7 through the sprinkler discharge piping. The system is QA class QP, seismically supported to prevent it from interfering with any safety related system or components in the Battery Room Corridor or Cable Tunnels.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 9 of 44 3.0 SEISMIC WALKDOWN PROGRAM IMPLEMENTATION APPROACH JAF has committed, per JAFP-12-0075

[Ref. 10.12], to conduct and document seismic walkdowns for resolution of NTTF Recommendation 2.3: Seismic in accordance with the EPRI Seismic Walkdown Guidance [Ref. 10.2]. The approach provided in the Guidance for addressing the actions and information requested in Enclosure 3 to the 50.54(f) Letter includes the following activities, the results of which are presented in the sections shown in parenthesis:

Assignment of appropriately qualified personnel (Section 4.0)* Reporting of actions taken to reduce or eliminate the seismic vulnerabilities identified by the Individual Plant Examination of External Events (IPEEE)program (Section 5.0)* Selection of structures, systems and components (SSCs) to be evaluated (Section 6.0)*

• Performance of the seismic walkdowns and area walk-bys (Section 7.0)Evaluation and treatment of potentially adverse seismic conditions with respect to the seismic licensing basis of the plant (Section 8.0)Performance of peer reviews (Section 9.0)The coordination and conduct of these activities was initiated and tracked by Entergy corporate leadership, which provided guidance to each Entergy site throughout the seismic walkdown program, including JAF. Entergy contracted with an outside nuclear services company to provide engineering and project management resources to supplement and assist each individual site. JAF had dedicated engineering contractors, supported by their own project management and technical oversight, who worked closely with plant personnel.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 10 of 44 4.0 PERSONNEL QUALIFICATIONS The NTTF 2.3 Seismic Walkdown program involved the participation of numerous personnel with various different responsibilities.

This section identifies the project team members and their project responsibilities and provides brief experience summaries for each. Training certificates of those qualified as Seismic Walkdown Engineers (SWEs) are included in Attachment H.Table 4-1 summarizes the names and responsibilities of personnel used to conduct the seismic walkdowns.

Experience summaries of each person follow.Table 4-1 Equipment Seismic Licensing IPEEE Name Selection Walkdown Basis Personnel Engineer Reviewer Richard Casella (Entergy)

X X X Alan Porch (Entergy)

X X Jeffrey Cooney (Entergy)

X Yaroslav Losev (ENERCON) x2 X X Pouria Pourghobadi (ENERCON)

X Donald Koberg (ARES) X Harpreet Ghuman (ARES) X Chris Sawatzke (Entergy)

X Bob Kester (Entergy)

X Roger Locy (Entergy)

X1 Notes: 1. Plant operations representative

2. Designated lead SWE Richard Casella Mr. Casella graduated from the Pennsylvania State University with a Bachelor of Science degree in Civil Engineering in May 1976. Mr. Casella is a Registered Professional Engineer in the Commonwealth of Pennsylvania.

Mr. Casella successfully completed the SQUG Walkdown Training course in June 2007. Mr. Casella's related experience is summarized below.Mr. ,Casella has 36 years of experience in the Engineering Design of nuclear power plants.He spent 19 years at Stone and Webster Engineering Corporation (SWEC) associated with Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 11 of 44 the design, startup, and operation of the Nine Mile Point 2 (NMP2) station. The first 7 years of his career were spent in the SWEC design office as a Pipe Stress analyst for ASME III Class 2, 3 and USAS B31.1 Class 4 piping systems. The remaining 12 years of his SWEC service were spent at NMP2 in Lycoming, NY. During this time, Mr. Casella was a Pipe Stress supervisor, then Lead Engineer for Pipe Stress and Supports, and then supported the transition of design responsibilities from SWEC to the Niagara Mohawk Power Corporation (NMPC). After plant startup, Rick worked as a Civil/Structural Design Engineer under NMPC authority until 1995.Mr. Casella joined the New York Power Authority in October 1995 as a Civil/Structural Design Engineer at the James A. FitzPatrick (JAF) plant. His primary role in his 17'year tenure at JAF has been pipe stress. He has worked with ISI Class 1, 2, 3 and non-ISI piping. He has been involved with and has an understanding of the Mark I Containment work performed for JAF by the Teledyne Corporation.

He has dealt with numerous seismic piping issues at JAF including many times assisting the Shift Manager with Operability determinations related to seismic piping and support issues. Mr. Casella has worked 9 Refuel Outages and several LCOs at JAF which have given him valuable "hands and eyes on" experience and knowledge of the plant and how it operates.

Rick has also been associated with many plant modifications with seismic evaluations and calculations including Responsible Engineer for* the replacement of 2-Stage Main Steam Safety Relief Valves with 3-Stage models. He is also experienced in Seismic Qualification of plant equipment and the Boiling Water Reactor Vessel Internals Program (BWR-VIP).

Alan Porch Mr. Porch graduated from the Drexel University with a Bachelor of Science degree in Civil Engineering in June 1974. He is a Registered Professional Engineer in the State of New York. Al successfully completed the EPRI Training on Near Term Task Force Recommendation 2.3- Plant Seismic Walkdowns in July 2012.Mr. Porch has 34 years of experience in the Engineering Design of nuclear power plants. He spent 13 years at Stone and Webster Engineering Corp. (SWEC) associated with the design, startup support, and operation of the Nine Mile Point 2 (NMP2) Station. The first year of his career was spent in the SWEC design office as a structural design engineer performing steel and concrete design activities associated with the design of the Nine Mile Point NPP. The next 5 years he worked at the Fermi II NPP as a pipe support design engineer and the remaining 7 years of his SWEC service were spent at NMP2 in Lycoming, NY. During this time, Mr. Porch was a-Pipe Support engineer and Modification engineer, 'and then supported the transition of design responsibilities from SWEC to the Niagara Mohawk Power Corporation (NMPC). After plant startup, Al worked as a Civil/Structural Design Engineer* under NMPC authority until 1995.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 12 of 44 Mr. Porch joined the New York Power Authority in September 1995 as a Civil/Structural Design Engineer at the James A. FitzPatrick (JAF) plant. His primary role in his 17 year tenure at JAF has been structural design support with a special attention given to pipe support design and acceptance.

He has worked with ISI Class 1, 2, 3 and non-ISI piping systems. He has dealt with numerous seismic piping issues at JAF including assisting the Shift Manager with Operability determinations related to seismic piping and support issues.Mr. Porch has worked 9 Refuel Outages as well as forced outages and down powers and at JAF which have given him valuable "hands and eyes on" experience and knowledge of the plant and how it operates.

Al has also been associated with many plant modifications with have included seismic evaluations and calculations including performing as Responsible Engineer for JAF's Pipe Support Program.Jeffrey Cooney Mr. Cooney is employed as a PSA Engineer for Entergy Nuclear Operations.

He has been employed with the company over 4 years. His expertise is in Probabilistic Safety Assessment (PSA) which includes maintaining/updating the active site PSA model and ensuring that current industry standards, experience, and technology are incorporated appropriately into the model.Yaroslav Losev Mr. Losev graduated from the New Jersey Institute of Technology with a Bachelor of Science degree in Mechanical Engineering in June 2008. He has worked as an ENERCON Mechanical Engineering for three years. For the past 2 years, he has been working in the Engineering department.

Mr. Losev has successfully completed Training on Near Term Task Force Recommendation

2.3 Plant

Walkdowns in 09/13/2012.

Some of Mr. Losev's related experience has been summarized below.As part of Exelon's ongoing commitments to comply with the Nuclear Regulatory Commission (NRC) requirements for post-fire safe shutdown promulgated in 10CFR50 certain scenarios have been-identified by the Exelon Expert Panel that are related to the safe shutdown of Limerick Generating Station (LGS). Plant design changes are required to address issues related to Multiple Spurious Operations (MSOs) as outlined in Nuclear Energy Institute (NEI)00-01, Rev. 2 (Guidance for Post-Fire Safe Shutdown Circuit Analysis) and ensure compliance with NRC Regulatory Guide 1.189, Rev 2 (Fire Protection for Nuclear Power Plants). Mr. Losev prepared technical evaluations and revised existing plant calculations on the capacity of existing raceway supports to support the additional dead weight load of the fire barrier systems including seismic requirements and considerations.

He' also developed technical evaluations for seismic temporary supports in number of other locations at LGS.Engineering change package implementation in Indian Point (IPEC), Units 2 and 3, coating of the walls of the transformer moats for Main Transformers.

During the stone removal to install Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 13 of 44 coating, various existing non-safety related conduits and pipes had to be, temporarily supported as part of' this work activity.

The supports were temporarily attached to existing structural steel and the steel columns, beams and foundations which were evaluated for the additional load. Mr. Losev designed and evaluated 27 uniquely different temporary supports to be installed while the stone was removed., Mr. Losev demonstrated extreme flexibility and imagination in designing these supports.

He also showed technical rigor, fast adaptation to new designs into evaluation, clear client communications, and timely deliverable of the calculation despite fast track schedule of this project.Mr. Losev provided support in walkdowns and design inputs for Honeywell at Metropolis Works (MTW) UF6 Processing Facility in determination and suggestions of seismic supports for their piping systems and equipment.

He reviewed seismic calculations on equipment and provided conceptual designs for supports on the equipment and piping runs to meet NRC's requirements.

Mr. Losev provided mechanical/structural engineering support for American Electrical Power (AEP) D.C. Cook Generating Station on "Pipe Stress Analysis" re-evaluation.

As part of D.C.Cook Generating Station's Large Bore Pipe Reconciliation Project (LBPRP), numerous safety related pipe stress calculations had to be re-evaluated.

The objective of these calculations was to structurally qualify the piping, pipe supports, including integral welded attachments, penetrations/nozzles, and valve accelerations in accordance with the design limits for dead weight, thermal, flow transients, and seismic conditions, and to provide the technical basis for any recommended modifications to the system that would be required to meet the D.C. Cook Generating Station's acceptance criteria.Pouria Pourahobadi Mr. Pourghobadi has worked as an ENERCON Civil/Structural Engineer for the past year. Mr.Pourghobadi has successfully completed Training on Near Term Task Force Recommendation

2.3 Plant

Walkdowns in 09/13/2012.

Some of Mr. Pourghobadi's related experience has been summarized below.As part of commitment to NRC, the Zion ,Solutions contracted.

ENERCON to provide Architectural and Engineering (A/E) Services for the design of an Independent Spent Fuel Storage Installation (ISFSI), various Fuel Handling Building modifications and operations.

Mr.Pourghobadi reviewed calculations and drawings for a new set-down pad with a loaded MAGNASTOR Transfer CASK (MTC) in the lower level of the Reactor Building cavity floor and evaluation of the capacity of existing floor slab to support the additional dead weight load with seismic requirements and considerations of the loaded MTC.Mr. Pourghobadi provided civil/structural engineering support to Exelon Peach Bottom Atomic W Power Station (PBAPS) to design a 75 ft high lighting arrestor as part of an Engineering Change Package. Site unique topography dictated adoption of a more creative approach Engineering Report No. JAF-RPT-.12-00015 Rev. 0 Page 14 of 44 rather than the conventional methods of mast foundation design. Mr. Pourghobadi provided design inputs for development of the foundation and evaluated the dead load of the lighting arrestor onto the foundation design.Donald Kobera Mr. Koberg earned a Bachelor's degree from Washington State University in Mechanical Engineering in 2010. He has been working as a Mechanical Engineer at ARES Corporation for over 2 years. Throughout his two plus years at ARES Corporation he has performed many technical calculations relating to anchorage and support design of piping systems for seismic activities.

Mr. Koberg has successfully completed Training on Near Term Task Force Recommendation

2.3 Plant

Walkdowns on 07/26/2012.

Some of Mr. Koberg's related experience is summarized below.Mr. Koberg's experience with anchorage design consists of designing and analyzing anchorage of piping support system to ASME B31.3 requirements.

Tasks included selection of material, support configuration, and general layout design of the pipe supports for stainless steel piping for use in waste retrieval activities at the Hanford Nuclear Reservation, Hanford, WA. Mr. Koberg has also analyzed various systems, structures and components for adherence to ASME B31.3, "Process Piping".* Mr. Koberg's activities include-design and analysis of waste transfer piping systems including assisting on equipment design and system analysis.

As part of the ASME B31.3 analyses, Mr. Koberg as analyzed multiple sections of piping systems and their supports for structural adequacy during seismic events. Analyzed equipment includes pump assemblies, waste distribution assemblies, and stainless steel piping assemblies.

Harpreet Ghuman Mr. Ghuman earned a Bachelor's degree from Washington State University in Civil Engineering in 2008. He has been working as a Structural Engineer at ARES Corporation for the past 4-years. Throughout his four years at ARES Corporation he has performed, many technical calculations relating to anchorage design, footing/slab design, and pipe support design for seismic activities.

Mr. Ghuman has successfully completed Training on Near Term Task Force Recommendation

2.3 Plant

Walkdowns on 07/26/2012.

Some of Mr. Ghuman's related experience is summarized below.Mr. Ghuman's experience in anchorage design consists of designing expansion or cast in place threaded rod/headed anchors for placement within concrete of various thicknesses and edge distance constraints in accordance with ACI-318, Appendix D. Also included within anchorage design is the design of at grade or embedded base plates. Mr. Ghuman also has experience in designing welds for mechanical supports.

Mr. Ghuman's footing/slab design experience consists of designing the appropriate size concrete foundation including rebar for various mechanical supports.

C Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 15 of 44 Mr. Ghuman has experience in Near Term Task Force Recommendation

2.3 Plant

Walkdowns.

He was part of a team that performed these walkdowns for Duke Energy at the McGuire Nuclear Station Units A and B near Huntersville, NC from August 27, 2012 thru September 13, 2012. Mr. Ghuman's responsibilities during these walkdowns consisted of aiding in filling out the Area Walk-by (AWC) and Seismic Walkdown Checklists (SWC) for various areas and equipment within the plant. He also assisted in the preparation of packages, such as finding drawings/calculations that pertained to equipment on the Seismic Walkdown Equipment List (SWEL), and determined which components should be considered as part of the required 50% design verification components in accordance with EPRI Report 1025286.Mr. Ghuman has worked in Hanford, WA on the contaminated groundwater in the 100 areas that reactor sites were required to be treated then pumped back into the river basin. Mr.Ghuman's task was for these projects was to design pipe supports for the piping line to allow for safe distribution of contaminated water during. seismic or wind events. The design included, fabricating members from structural steel which includes weld and bolt design or constructing pipes supports out of UNISTRUT members. Mr. Ghuman also designed concrete foundations and sized the appropriate expansion or cast in place anchors for the pipe supports or various othei mechanical equipment.

• Chris Sawatzke Mr. Sawatzke graduated from Michigan State University with a Bachelor of Science degree in Civil Engineering in September 1981. He has an Engineer-In-Training (EIT) in the State of Michigan.

Chris successfully completed the EPRI Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns in July 2012. He has also successfully completed EPRI Training on Visual Examination Level II -Containment Inspection Program in September 2005 and the EPRI Comprehensive Coating Training in April 2002.Mr. Sawatzke has 31 years of experience in the Engineering Design of nuclear power plants.He spent 13 years with Niagara Mohawk associated with the design and operation of the Nine Mile Point -Unit 2 Nuclear Plant. The first seven years of his career were spent working for Gilbert/Commonwealth at Washington Power Unit 2, Perry Nuclear Plant Unit 1, Browns Ferry Nuclear Power Plant and Sequoyah Nuclear Power Plant; and Nuclear Power Services (NPS) at South Texas Project Nuclear Plant. During this time, Mr. Sawatzke was a Design Engineer supporting the Civil/Structural Engineering Department performing steel and concrete design activities associated with the design of each of the specific nuclear power plants.Mr. Sawatzke joined Entergy Nuclear Operations in October 2001 as a Senior Civil/Structural Design Engineer at the James A. FitzPatrick (JAF) Nuclear Power Plant. His role in his 11 year tenure at JAF has been structural steel and concrete design for Systems, Structures and Component's (SSC's). He has worked with ISI Class 1, 2, 3 and Non-ISI piping systems. He has dealt with numerous seismic piping and structural issues at JAF including assisting the Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 16 of 44 plant Shift Manager with Operability Determinations related to seismic piping and pipe support issues. Mr. Sawatzke has worked 6 Refuel Outages as well as forced outages and down powers at JAF, 5 refuel outages at other Entergy Fleet plants, and 7 refuel outages as well as forced outages at Nine Mile Nuclear Plant Unit 2; which has provided him valuable"hands on" experience and knowledge of the various plants and systems and how they operate. Mr. Sawatzke has also been associated with many plant modifications as a Responsible Engineer which included seismic evaluations and formal calculations for the JAF Pipe Support Program.Bob Kester Mr. Kester graduated from Lafayette College with a Bachelor of Science degree in Civil Engineering in May 1980. Mr. Kester successfully completed the SQUG Walkdown Training course in August 1993, and performed SQUG USI A-46 walkdowns for James A. Fitzpatrick Nuclear Plant in 1995.Mr. Kester has 32 years of experience in the Engineering Design of nuclear power plants. He spent 10 years at Stone and Webster Engineering Corporation (SWEC) associated with the design of the River Bend and Nine Mile Point 2 (NMP2) stations.

During this period, Bob's experience was primarily associated with pipe stress and support design, and included over 8 W years as a field engineering, which provided valuable experience that integrated aspects of design criteria, design changes, construction and inspection requirements.

Mr. Kester's career shifted to an operating nuclear power station, working for the utility company at the James A. FitzPatrick (JAF) plant since December 1989. In addition to being involved in Plant Modification designs and the JAF SQUG program, Bob has had diverse experiences in civil, structural, and mechanical engineering disciplines as a Plant Engineer.This role has often required a practical approach to seismic evaluations in support of Operability determinations related to plant condition reports. Mr. Kester has worked numerous plant Refuel Outages and system LCOs at JAF which have given him valuable"hands and eyes on" experience and knowledge of the physical plant, and how it operated and maintained.

Bob's involvement with numerous plant modifications has included seismic evaluations for structures, piping, tubing, raceways, and miscellaneous equipment, which has entailed formal design calculations, simplified qualitative evaluations, and also the use of EPRI's GIP & STERI methodology.

For over 15 years in a Plant Support Engineering group, Bob has been the primary responsible engineer at JAF for structural evaluations of temporary conditions in the plant including scaffolding, shielding, leak repairs, freeze seals, as well as staging & storage of transient equipment.

Roqer Locv* Mr. Locy's education and training is summarized as follows: Machinist Mate'"A" School, U.S.Navy, completed May 1966. Basic Nuclear Power School, U.S. Navy, completed April 1967.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 17 of 44 Naval Reactor Prototype, U.S. Navy, completed October 1967. BWR Technology, General Electric, completed December 1972. Site training programs, Duane Arnold Energy Center.Numerous courses for RO cold license and requalification.

License number OP-3424. Site training programs, Duane Arnold Energy Center. Numerous courses for SRO license and requalification.

License Number SOP-2849.

Site'training programs, James A. FitzPatrick Nuclear Power Plant. Numerous courses for SRO license and requalification.

License number SOP-3218.

Regents College, The University of the State of New York. Presently have earned 110 credits toward a Baccalaureate Degree in Nuclear Technology.

From November 1967 to April 1972, U.S.S. Enterprise-Nuclear Powered Aircraft Carrier.From May 1972 to July 1977, Operations Department, Duane Arnold Energy Center. From August 1977 to February 1982, Shift Supervisor, James A. FitzPatrick Nuclear Power Plant.From March 1982 to March 1985, Waste Management General Supervisor, James A.FitzPatrick Nuclear Power Plant. Established Decontamination and Shipping section of Radiological Waste Group in the Operations Department.

Responsible for operation of the Radwaste Facility, all Radwaste shipments for disposal and area/equipment decontamination.

From April 1985 to March 1989, Assistant Operations Manager, James A.FitzPatrick Nuclear Power Plant. Assisted the Operations Manager with the day to day operations of the plant. From April 1989 to March 1997, Operations Manager, James A.FitzPatrick Nuclear Power Plant. Responsible for the safe and efficient operation of the plant.W Provide management over view of operating shifts, operation support and Radwaste Facility operation.

Held a SRO license. From March 1997 to November 2000, Training Manager, James A. FitzPatrick Nuclear Power Plant. Responsible for the design, development, implementation and evaluation of training programs ensuring regulatory compliance, cost effectiveness and plant staff qualification.

From November 2000 to June 2006, Project Manager Operations Support, FitzPatrick Nuclear Power Plant, responsible for operations input to outage planning, maintenance rule operations representative, BWROG Scram Frequency Reduction Committee representative, perform root cause analysis for department events and operations department training coordinator.

From September 2006 to April 2007, Project Manager Operations Training Improvement Program, Ginna Nuclear Power Station.Responsible for the completion of the Operations Training Excellence Plan completion.

Monitored both quality and timeliness of action close out. Oversight of a Operation Lesson Plan Upgrade Program. Supervised 5 contract lesson plan developers.

From October 2007 to August 2009, Operations Procedure Group Lead, Nine Mile Point Nuclear Station.Responsible for the development and maintenance of all Operations Procedures for both units. Oversight of the WordPerfect to Word conversion of all site procedures.

Revised procedures to support outage activities and modifications.

From November 2009 to Present, License Renewal Project Senior Project Manager, James A. FitzPatrick Nuclear Power Plant.Responsible for identification, performance and documentation of One-Time Inspections.

• Assisted with monitoring progress of completion of NRC License Renewal Commitments.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 18 of 44.4.1 EQUIPMENT SELECTION PERSONNEL A total of 3 individuals served as Equipment Selection Personnel

-see Table 4-1.4.2 SEISMIC WALKDOWN ENGINEERS A total of 8 individuals served as Seismic Walkdown Engineers

-see Table 4-1.4.3 LICENSING BASIS REVIEWERS A total of 2 individuals served as Licensing Basis Reviewers

-see Table 4-1.4.4 IPEEE REVIEWERS A total of 2 individuals served as IPEEE Reviewers

-see Table 4-1.4.5 PEER REVIEW TEAM Table 4-2 summarizes the names and responsibilities of personnel used to conduct peer reviews of the seismic walkdown program. Experience summaries of each person follow.Table 4-2 SWEL Peer Walkdown Licensing Submittal NameReviewer Peer Basis Peer Report Peer Reviewer Reviewer Reviewer Tom Panayotidi (ENERCON) x2 X1'2 Alan Porch (Entergy)

X X Richard Sullivan (Entergy) x2 Laura Maclay (ENERCON)

X X Jeffrey Horton (ENERCON)

X2 Richard Casella (Entergy)

X Notes: 1.2.Peer Review Team Leader Lead peer reviewer of particular activity Tom Panayotidi Dr. Panayotidi has graduated with a Doctorate of Engineering Science in Civil Engineering/Engineering Mechanics, with emphasis in finite element analysis, particularly for* seismic and other dynamic loads. He has worked as an ENERCON Civil/Structural Consulting Engineer for the past year, and has successfully completed Training on Near Term Task Force Recommendation

2.3 Plant

Walkdowns on 09/13/2012.

Dr. Panayotidi has Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 19 of 44 over 30 years' experience as a Structural/Seismic Engineer in the nuclear field. Some of his related experience is summarized below.Dr. Panayotidi prepared submittal report for OPPD Fort Calhoun Station per NTTF Recommendation 2.3: Seismic..

He reviewed calculations and drawings for the OPPD Fort Calhoun Station Flood Recovery and Geotechnical/Seismic Evaluation.

Dr. Panayotidi also has experience in Standard Plant Design of Nuclear Island for Mitsubishi Heavy Industries

-US Advanced Pressurized Water Reactor: Seismic Soil-Structure Interaction Analysis of Reactor Building Complex, Foundation Stability for sliding, overturning, bearing pressure (uplift condition), shear key design, nonlinear transient displacement calculation to predict foundation sliding, and Slope stability under seismic loading.Dr. Panayotidi also has experience in Standard Plant Design of new generation compact 125 MW nuclear station for B&W mPower Project: Seismic Soil-Structure-Interaction analysis of underground (buried) nuclear island, he development of ground motion synthetic time history from high frequency CEUS design spectrum, as well as NRC 1.60 spectrum, and generation of in-structure-response-spectra (ISRS).Dr. Panayotidi performed evaluation for NPPD Cooper Nuclear Station. He provided analytical review of the Reactor Building Crane Upgrade: Re-rate analysis of Cooper Nuclear Station Reactor Building, due to an increase in refueling crane capacity.

He also evaluated Reactor building integrity for all applicable loads, including earthquake, tornado, seismic, and crane lifted loads.Dr. Panayotidi developed worked on Accelerator Production of Tritium, DOE, for Savannah River Site: Seismic analysis of reinforced concrete building, including 3-D soil-structure interaction effects due to 60ft embedment, using SASSI. 'He also performed calculation of strained (iterated) soil properties, convolution and de-convolution of input motion using SHAKE91. Dr. Panayotidi also performed seismic anchor motion and soil-structure-interaction analysis of 1-mile long underground accelerator tunnel.Dr. Panayotidi worked on design of 250 MW single-shaft, in-line gas turbine/steam turbine/generator concrete pedestal for River Road Generating Project (WA), including design of batter and vertical foundation piles, steel framing to support hot/cold piping in generation building.Richard Sullivan Mr. Sullivan graduated from University of Tennessee with a Bachelor of Science degree in Electrical Engineering.

Some of Mr. 'Sullivan's related experience and awards are summarized below.Navy Achievement Medal for superior management of the ship's Quality Assurance Program during two heavy maintenance periods.* Extensive experience in the operation and maintenance of a variety mechanical and electrical systems including:

steam systems, cooling water systems, hydraulic systems, atmospheric Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 20 of 44 controls, ventilation systems, electrical distribution, digital and logic systems, and electrical generation.

From January, 2001 to September, 2007 and from October, 2007 to present, in James A.FitzPatrick Nuclear Power Plant, Mr. Sullivan coordinated and developed Operations schedule activities and tagout preparation.

Contributed to INPO 1 rating in 2004 by outstanding simulator scenarios and professional shift operations.

Aided in the development, implementation, and enforcement of high operational standards.

Contributed to the record breaking capacity factor year at JAF in 2001. Developed plant start up procedures in a flow chart format on own initiative.

From May, 1997 to December, 2000, Mr. Sullivan developed and implemented three site-wide Emergency Plan Drills which included scenario design and simulator interface.

Coordinated with other departments in the development of plant Emergency Operating Procedures and Severe Accident Procedure.

Developed JAF licensed operator annual requalification examination.

From November, 1994 to April, 1997, Mr.Sullivan assisted in two error-free refueling outages as Refuel Floor SRO. In October, 1994 Mr. Sullivan earned Senior Reactor Operator License from the Nuclear Regulatory Commission.

From 1988 to February, 1992, in the United States Navy, Mr. Sullivan served on board USS Nevada (SSBN-733).as Tactical Systems Department Head, Strategic Missiles Officer, and O Damage Controls Assistant.

Quality Assurance Officer: Coordinated ship's force and shipyard maintenance on various systems on a Trident submarine ensuring all specifications were met. Also responsible for training 30 personnel ship-wide.

Laura Maclay Ms. Maclay has over five years of experience as a structural engineer, three years with ENERCON Services.

Ms. Maclay holds a Bachelor's degree in Structural Engineering from Drexel University and is a qualified Seismic Walkdown Engineer as stated on her EPRI training certificate dated July 26, 2012. Her tasks have ranged from assisting with the development and preparation of design change packages to performing design calculations and markups, comment resolutions, and drawing revisions.

Ms. Maclay spent a year on site at Turkey Point Nuclear Plant preparing structural evaluations of SSC's for an Extended Power Uprate (EPU). Her work included designing safety related supports for computer and electrical equipment for the Turbine Digital Controls Upgrade package and other similar packages.

Ms. Maclay's responsibilities also included the review of calculations, drawings and vendor documentation for the seismic evaluation of the Unit 3 Palfinger Crane inside containment and new platforms in the High Pressure Turbine enclosure.

Recent work includes Fukushima flooding walkdowns at Limerick Generating Station and seismic walkdowns at Plant Farley. As a member of a two person team, Ms. Maclay was O responsible for evaluating equipment anchorage, spatial interactions and potentially adverse conditions.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 21 of 44 Jeffrey Horton Mr. Horton is a Licensed Professional Engineer with 39 years of experience in the structural design of nuclear power components, pipe systems and building structures.

Mr. Horton is currently employed as a Lead Civil/Structural Engineer.

He holds a B.S. in Aerospace Engineer from Park's College of St Louis University in Missouri and a M.S. in Material Science specializing in Solid Mechanics from Rutgers University in New Jersey. He is a qualified SWE with extensive experience in the seismic design of components and pipe systems in Nuclear power plants.

Engineering Report No. JAF-RPI- 12-00015 Rev. 0 Page 22 of 44 5.0 IPEEE VULNERABILITIES REPORTING During the IPEEE program in response to NRC Generic Letter 88-20 [Ref. 10.4], plant-specific seismic vulnerabilities were identified at many plants. In this context, "vulnerabilities" refers to conditions found during the IPEEE program related to seismic anomalies, outliers, or other findings.IPEEE Reviewers (see Section 4.,4) reviewed the IPEEE final report [Ref. 10.5] and supporting documentation to identify items determined to present a seismic vulnerability by the IPEEE program. IPEEE Reviewers then reviewed additional plant documentation to identify the eventual resolutions to those seismic vulnerabilities not resolved by the completion of the IPEEE program.The seismic vulnerabilities identified for JAF during the IPEEE program are reported in Attachment A. A total of 1 seismic vulnerability was identified by the JAF IPEEE program.For the identified seismic vulnerability, the table in Attachment A includes three pieces of information requested by Enclosure 3 of the 50.54(f) Letter:* a description of the action taken to eliminate or reduce the seismic vulnerability" whether the configuration management program has maintained the IPEEE action (including procedural changes) such that the vulnerability continues to be addressed" date when the resolution actions were completed.

The list of IPEEE vulnerabilities provided in Attachment A was used to ensure that some equipment enhanced as a result of the IPEEE program were included in SWELl (see Section 6.1.2). Documents describing these equipment enhancements and other modifications initiated by identification of IPEEE vulnerabilities were available and provided to the SWEs during the NTTF 2.3 Seismic Walkdowns.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 23 of 44 6.0 SEISMIC WALKDOWN EQUIPMENT LIST (SWEL) DEVELOPMENT This section summarizes the process used to select the SSCs that were included in the SWEL in accordance with Section 3 of the Guidance.

A team of equipment selection personnel with extensive knowledge of plant systems and components was selected to develop the SWEL. The SWEL is comprised of two groups of items: SWEL 1 consists of a sample of equipment related to safe shutdown of the reactor and maintain containment integrity (five safety functions)

• SWEL 2 consists of items related to the spent fuel pool The final SWEL is the combination of SWELl and SWEL2. The development of these two groups is described in the following sections.6.1 SAMPLE OF REQUIRED ITEMS FOR THE FIVE SAFETY FUNCTIONS Safe shutdown of the reactor involves four safety functions:

• Reactor reactivity control (RRC)* Reactor coolant pressure control (RCPC)* Reactor coolant inventory control (RCIC)* Decay heat removal (DHR)Maintaining containment integrity is a fifth safety function* Containment function (CF)The overall process for developing a sample of equipment to support these five safety functions is summarized in Figure 1-1 of the Guidance.

The equipment coming out of Screen#3 and entering Screen #4 is defined as Base. List 1. The equipment coming out of Screen#4 is the first Seismic Walkdown Equipment List, or SWEL 1. Development of these lists is described separately in the following sections.6.1.1 Base List1 Based on Figure 1-1 and Section 3 of the Guidance, Base List 1 represents a set of Seismic Category (SC) I equipment or systems that support the five safety functions.

The IPEEE program was intended to address the seismic margin of SSCs associated with each of the five safety functions.

At JAF the EPRI Seismic Margin Assessment (EPRI SMA) method was used to complete the seismic IPEEE program, based on EPRI Report NP-6041 titled "A Methodology for assessment of Nuclear Power Plant Seismic Margin." Base List 1 was developed using both IPEEE report [Ref. 10.5] and A-46 Safe Shutdown Equipment List (SSEL) [Ref. 10.13]. This equipment list of SSCs Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 24 of 44 is, consistent with the requirements of Screens #1 through #3 of the Guidance.Therefore, the components listed on both the USI-46 composite SSEL and the IPEEE Shutdown Equipment List are initially used as the NTTF 2.3 Seismic Walkdown Base List 1. Base List 1 is presented as Table 9.4.1 in Attachment B, -and has 699 total items. The following components were added to both Base List 1 and SWEL 1.o Core Spray Pump 14P-1A and RHR Service Water Strainer 10S-5A (both on the IPEEE, but not on A-46 Safe Shutdown Equipment List (SSEL))o Standby Gas Treatment Filter Train A Inlet Isolation valve 01-125MOV-14A (listed on the IPEEE, but not on A-46 SSEL)o Administrative Building Ventilation Control Panel, 72HV-7A (although this is Safety Related component, it is not listed on either the IPEEE or A-46 SSEL)o Emergency Diesel Generator A.Air Start Compressor Al, 93AC-A1 (this is an Augmented Quality component and is the only component in compressor equipment class. It is not listed on either the IPEEE or A-46 SSEL)o Reactor Core Isolation Cooling Pump, 13P-1 (this is an Augmented Quality component, which is included on the IPEEE report)o Components 71ACUPS and 71PT-71ACUPS are currently classified as Non-Safety Related (per Equipment Database), these two components were on the original A-46 SSEL and support at least one of the 5 Safety functions.

The following components where replaced in SWEL 1 and are not currently shown on the Base List 1.o SGT Filter Train A Inlet Isolation Valve 01-125MOV-14A replaced with SGT Filter Train B Inlet Isolation Valve 01-125MOV-14B due to component restrictions.

6.1.2 SWELl

Based on Figure 1-1 and Section 3 of the Guidance, SWEL 1 is a broad population of items on Base List 1 including representative items from some of the variations within each of five sample selection attributes.

The selection of SWEL 1 items includes consideration of the importance of the contribution to risk for the SSCs. Equipment Selection Personnel (see Section 4.1) developed SWEL 1 using an iterative process.The following paragraphs describe how the equipment selected for inclusion on the final SWEL 1 are representative with respect to each of the five sample selection attributes while considering risk significance.

In general, preference for inclusion on

• Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 25 of 44 SWEL 1 was given to items that are accessible and have visible anchorage.

SWEL 1 is presented as Table 9.4.2 as in Attachment B, and has 117 total items.Variety of Types of Systems Items were selected from Base List 1 ensuring that each of the five safety functions was well represented.

Additionally, components from a variety of frontline and support systems, as listed in Appendix E of the Guidance, were selected.

The system type of each item on SWEL 1 is listed on Table 9.4.2 of Attachment B.Maior New and Replacement Equipment With assistance from plant operations, equipment selection personnel identified items on Base List 1 which are either major new or replacement equipment installed within the past 15 years, or have been modified or upgraded recently.

These items are designated as such on Base List 1 on Table 9.4.1 of Attachment B. A robust sampling of these items is represented on SWEL 1. The following components were chosen as items that have been replaced since completion of the original SSEL.o 02RV-71 E -Main-Steam Safety Relief Valve o 71 INV-3A -"A" LPCI Inverter o 70RWC-2A (CND) -"A" Control Room Chiller Condenser o 23MOV-14 -HPCI Turbine Steam Supply Isolation Valve o 23AOV-53 -HPCI Turbine Steam Supply Drain Trap T-3 Bypass Valve o 1OS-5A -RHRSW Strainer o 71 SB-2 -"B" Station Battery Variety of Equipment Types.Items were selected from Base List 1 ensuring that each of the equipment classes represented there was also represented on SWEL 1, in the same approximate ratios.The different equipment classes considered are listed in Appendix B of the Guidance.The equipment class of each item on SWEL 1 is listed on Table 9.4.2 of Attachment B.Note that SWEL 1 does not include Class 13 components, because these are not represented on Base List 1. A single Class 12 component (93AC-A1) is included on the SWEL. Although it is only classified as Augmented Quality, there are no compressors designated as Safety Related at JAF.Variety of Environments Items were selected from Base List 1 located in a variety of buildings, rooms, and elevations.

These item locations included environments that were both inside and Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 26 of 44 outside, as well as having high temperature and/or elevated humidity.

The location and environment of each item on SWEL 1 is listed on Table 9.4.2 of Attachment B.IPEEE Enhancements The IPEEE does not include any specific vulnerabilities for components which could be considered for the SWEL 1 (see Section 5.0). However, the following components were chosen based on their "lower" seismic capabilities..

Note that the bottom 3 listed components are associated with seismic induced anchorage failure at ground accelerations between 0.31g and 0.41g: 10E-2A "A" RHR Heat Exchanger 1 0S-5A "A" RHRSW Strainer 09-32 Channel "A" RHR/RCIC Relay Panel 71 MCC-1 61 600V Motor Control Center (Bus 116100)71 DSC-1 1561 Li 5 Unit Substation Transformer T-1 3 High Side Disch SW Risk Significance Information from the plant Probabilistic Risk Assessment (PRA) model and the Maintenance Rule implementation documentation were used to determine whether items were risk significant.

Risk significance was determined by using Risk Importance Measures, Risk Achievement Worth (RAW), and Fussell-Vesely (FV). This risk was considered using a threshold value of RAW > 2 and FV > 0.0001. Higher risk components were given added consideration for selection as a SWEL 1 item.6.2 SPENT FUEL POOL ITEMS The overall process for developing a sample of SSCs associated with the spent fuel pool (SFP) is summarized in Figure 1-2 of the Guidance.

The equipment coming out of Screen #2 and entering Screen #3 is defined as Base List 2. The equipment coming out of Screen #4 is the equipment that could potentially cause the SFP to drain rapidly. The equipment coming out of Screen #3 and Screen #4 is the second Seismic Walkdown Equipment List, or SWEL 2. Development of these lists is described separately in the following sections.6.2.1 Base List,2 Based on Figure 1-2 and Section 3 of the Guidance, Base List 2 represents the Seismic Category (SC) I equipment or systems associated with the SFP. To develop Base List 2, Equipment Selection Personnel (see Section 4.1) reviewed plant design and licensing basis documentation and plant drawings for the SFP and its associated cooling system. Base List 2 is presented as Table 9.4.3 in Attachment B, and has 13 Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 27 of 44 total items. The following components were replaced in SWEL 2 and are not currently shown on the Base List.o Decay Heat Removal Strainer Bypass Valve 32DHR-5 replaced with Decay Heat removal Cooling Water Return Isolation Valve 32DHR-18 because of radiological considerations.

o Decay Heat Removal SFP Water Primary Pump A 32P-1A was removed from the list due to radiological reasons.6.2.2 Rapid Drain-Down Rapid drain-down is defined in EN-DC-168, Attachment 9.4 [Ref. 10.11], as lowering the water level to the top of the fuel assemblies within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after an earthquake.

Consistent with the Guidance, the Equipment Selection Personnel (see Section 4.1)identified SSCs that could cause the SFP to drain rapidly by first reviewing the SFP documentation to identify penetrations below about 10 ft above the top of the fuel assemblies.

Because this review found no such SFP penetrations, there is no potential for rapid drain-down and no items were included on the rapid drain-down list to include on SWEL 2.6.2.3 SWEL 2 Based on Figure 1-2 and Section 3 of the Guidance, SWEL 2 is a broad population of items on Base List 2 including representative items from some of the variations within each of four sample selection attributes (using sample process similar to SWEL 1), plus each item that could potentially cause rapid-drain down of the SFP. Due'to the population of items on Base List 2 being much smaller than Base List 1, the sampling attributes are satisfied differently for SWEL 2 than for SWEL 1. The following paragraphs describe how the equipment selected from Base List 2 for inclusion on SWEL 2 are representative with respect to each of the four sample selection attributes.

SWEL 2 is presented as Table 9.4.5 in Attachment B, and has 11 total items. The SFP at JAF has no qualified rapid drain-down (RDD) components, as described in EN-DC-168, Attachment 9.4 [Ref. 10.11]; therefore no RDDs were included in SWEL 2 list.Variety of Types of Systems There are 2 systems, Spent Fuel Cooling and Decay Heat Removal, associated with SFP. Each of these systems is represented on SWEL 2.

Engineering Report No. JAF-RPT- 12-00015? Rev. 0 Page 28 of 4 0 Ma ior New and Re placement Equi pment New and Replaced components are identified in Table 9.4.5, Column "N/R". Out of 11 SWEL 2 components, 9 were not replaced within 15 years; therefore considered to be new, and 2 components are newly installed.

Variety of Equipment Types There are 5 different equipment classes represented on Base List 2: 01, 05, 07, 20 and 21. Each of these equipment classes is represented on SWEL 2.Variety of Environments 10 out of 11 SFP components noted on SWEL 2 are inside the Reactor Building and are thus located in similar environments.

The remaining component is located outside.6.3 DEFERRED, INACCESSIBLE ITEMS on SWEL The intent of adding each item on the SWEL is for it to be walked down as part of the NTTF 2.3 Seismic Walkdown program. To be able to perform the seismic walkdowns of these items, it is necessary to have access to them and to be able to view their anchorage.

In some cases, it was not feasible to gain access to the equipment or view its anchorage during the entire 180-day response period of Enclosure 3 to the 50.54(f) Letter. For these cases, walkdowns of these items have been deferred until the next refueling outage (RFO) in September of 2014, or the items were deleted from the list. An updated submittal report incorporating these deferred walkdowns will be provided 90 days after the end of RFO21.Deferred and deleted items are summarized in the table below. The reason is identified as either ACC (indicating that the item was deleted because of ALARA reasons) or CAB (indicating that the item requires opening cabinet/panel doors which was not permitted by plant Operations personnel during the walkdown period, due to being energized or otherwise).

A total of 26 items from which 23 items are deferred, 3 are in high dose areas and will not be deferred.

The 23 deferred items are cabinets/panels required to be opened.SWEL# Equipment ID Description Location Reason RWCU supply outbound isolation valve, is located in a Locked High Radiation Area SWEL 1-163 12MOV-18 (LHRA). Dose levels are high, both in RB. EL 300', ACC outage and normal plant operation.

This Column 3, Line R item is deleted from the SWEL list because of dose concern and will not be deferred.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 29 of 44 SWEL# Equipment ID Description Location Reason The skimmer surge tank A condensate make-up check valve, is located in a LHRA RB. EL 369.6', SWEL 2-2 19FPC-32 behind the "A" Skimmer Surge Tank. This ACC item is deleted from the SWEL list because Column 3.5, Line Y of dose concern and will not be deferred.The decay heat removal SFP water primary pump "A", is located in a high RB. 326', SWEL 2-11 3213-1 A radiological area. This item is deleted from ACC the SWEL list because of dose concern Column 3, Line T and will not be deferred.The nuclear station main control board, is deferred.

WO # 52389703 was initiated to AD. 300', track the walkdown of this component on Column 10, Line F 12/2012.The 4160V switchgear distribution (BUS SWELl-430 71-10502 10500) is deferred.

WR # 309411 was EG. 272', CAB'initiated to track the walkdown of this Column 24, Line Al component on 09/2013.The 4160V switchgear distribution (BUS SWELl-433 71-10560 10500) is deferred.

WO # 52448178 was EG. 272', CAB initiated to track the walkdown of this Column 26, Line Al component on 06/2014.The 600V switchgear distribution (bus SWELl-438 71-11502 11500) breaker 02 is deferred.

WO # RB. 300', CAB 52450763 was initiated to track the Column 26, Line Al walkdown of this component on 06/2014.The 4160V switchgear distribution (BUS SWELl-439 71-11602 10600) is deferred.

WR # 290278 was EG. 272', CAB initiated to track the walkdown of this Column 2, Line R component.

The LPCI inverter battery is deferred.

WO RB. 344.6', SWELl-446 71 BAT-3A # 52437751 was initiated to track the CAB walkdown of this component on 08/2013. Column 5.5 The 125 VDC station battery charger is SWELl -448 71BC-1A deferred.

WO # 52440826 was initiated to BR. 272, CAB track the walkdown of this component on Column 12.5, Line E 08/2014.The battery A control board is deferred.

BR. 272, SWELl -450 71BCB-2A WO # 52421057 was initiated to track the CAB walkdown of this component on 05/2013. Column 13, Line C Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 30 of 44 SWEL# Equipment ID Description Location Reason The Li 5 unit substation transformer T-1 3 SWELl-462 71DSC-11561 high side discharge SW is deferred.

WR # RB. 300', CAB 290280 was initiated to track the walkdown Column 2, Line R of this component.

The LPCI MOV independent power supply SWELl-470 711A inverter is deferred.

WO # 52391223 was RB. 344.6', CAB 071INV-3A initiated to track the walkdown of this Column 5.5 component on 01/2013.The 600V switchgear distribution (BUS SWELl-474 71L25 12500) is deferred.

WR # 290281 was EB. 272', CAB initiated to track the walkdown of this Column 18.5, Line Al component on 10/2014.The 600V motor control center (BUS SWELl-481 71MCC-161 116100) is deferred.

WR # 290282 was EB. 272', CAB initiated to track the walkdown of this Column 1.5, Line W component on 09/2016.The 600V motor control center (BUS SWELl-487 71MCC-252 125200) is deferred.

WO # 52404915 was EB. 272', CAB initiated to track the walkdown of this Column 18, Line A component on 03/2013.The 600V motor control center (BUS SWELl -489 71 MCC-254 125400) is deferred.

WO # 52380939 was EB. 272', CAB initiated to track the walkdown of this Column 23, Line Al component on 11/2012.The EDG A engine control panel is SWELl -624 93ECP-A deferred.

WO # 52419775 was initiated to EG. 272', CAB track the walkdown of this component on Column 24 05/2013.The EDG A engine control sub panel is EG. 272', SWELl -628 93ECSP-A deferred.

WR # 290283 was initiated to CAB track the walkdown of this component.

Column 24 The EDG B engine control sub panel is EG. 272','SWELl-629 93ECSP-B deferred.

WR # 290284 was initiated to CAB track the walkdown of this component.

Column 26, Line A3 The EDG C generator control panel is deferred.

WO # 52419771 was initiated to EG. 272', SWELl-636 93EGP-A CAB track the walkdown of this component on Column 24, Line Al 05/2013.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 31 of 44 SWEL# Equipment ID Description Location Reason The EDG B generator control panel is deferred.

WO # 52427217 was initiated to EG. 272', SWELl -637 93EGP-B CAB track the walkdown of this component on Column 26, Line Al 07/2013.The EDG A & C forced paralleling panel is SWELl -640 93FPAC deferred.

WO # 52286384 was initiated to EG. 272', CAB track the walkdown of this component on Column 24.5, Line A 09/2014.The 32P-1A(M) decay heat removal SFP SWEL2-013 71MCC-120-OE1 water primary pump A motor is deferred.

YD. 293' CAB WR # 290285 was initiated to track the walkdown of this component on 03/2013.The 600V Motor Control Center (BUS SWELl-493 71MCC-264 126400) is deferred.

WO # 52449942 was EB. 272 CAB initiated to track the walkdown of this Column 25.5, Line Al component on 10/2013.The Reactor Building DC Motor Control SWELl -456 71BMCC-6 Center is deferred.

WR # 290578 was EB. 272 CAB initiated to track the walkdown of this Column 8, Line Y component.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 32 of 44 O 7.0 SEISMIC WALKDOWNS AND AREA WALK-BYS The NTTF 2.3 Seismic Walkdown program conducted in accordance with the Guidance involves two primary walkdown activities, Seismic Walkdowns and Area Walk-Bys.

These activities were conducted at JAF, by teams of two trained and qualified SWEs (see Section 4.2). JAF in house Civil Engineers performed a portion of the walkdowns.

Both SWEs on these teams have several years of seismic experience.

For the balance of the walkdowns (Performed by contractors), each team (2 teams total).included one engineer with at least several years of experience in seismic design and qualification of nuclear power plant SSCs, whereas the second engineer had somewhat less (though sufficient) experience.

In certain instances, the teams (both JAF and contractors) periodically "shuffled" personnel to cross-check consistency between the two teams.The seismic walkdowns and area walk-bys were conducted over a span of approximately 6 weeks, starting in mid-September of 2012. Pre-job briefs were performed prior to walkdowns.

This pre-job brief was used to outline the components and areas that would be walked down, to ensure consistency between the teams, to reinforce expectations and process for identifying potentially adverse seismic conditions (and other non-seismic plant conditions), and to allow team members to ask questions and share feedback.7.1 SEISMIC WALKDOWNS Seismic walkdowns were performed in accordance with Section 4 of the Guidance for all items on the SWEL (SWEL 1 plus SWEL 2), except for those determined to be inaccessible and deferred (see Section 6.3). To document the results of the walkdown, a Seismic Walkdown Checklist (SWC) with the same content as that included in Appendix C of the Guidance was created for each item. Additionally, photographs were taken of each item and included on the corresponding SWC.In some cases, the SWE teams conducted preliminary "scouting" walkdowns to get a general understanding of plant layout and to identify items on the draft SWEL that were inaccessible.

Items that were identified to be inaccessible on these "scouting" walkdowns were discussed with the Equipment Selection Personnel and were either deleted or deferred while ensuring that the overall integrity of the final SWEL was not compromised.

Prior to performance of the walkdowns, documentation packages were developed that contained the SWC with preliminary data entered and other pertinent information including the location drawings, response spectra information, previous IPEEE seismic walkdown documentation, and anchorage drawings where applicable.

These documentation packages ,, accompanied the SWE teams into the plant during the seismic walkdowns.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 33 of 44 Walkdown inspections focused on anchorages and seismic spatial interactions, but also included inspections for other potentially adverse seismic conditions.

Anchorage, in all cases, was considered to specifically mean anchorage of the component to the structure where applicable.

This included anchor bolts to concrete walls or floors, structural bolts to structural' steel and welds to structural steel or embedded plates. For welds, the walkdown team looked for cracks and corrosion in the weld and base metal. Other bolts or connections, such as flange bolts on in-line components were not considered as equipment anchorage.

These bolts and connections were evaluated by the SWEs and any potential adverse seismic concerns were documented under "other adverse seismic conditions" rather than under"anchorage".

Thus, components with no attachments to the structure are considered as not having anchorage.

Nevertheless, the attachment of these components to other equipment was evaluated and inspected for potentially adverse seismic conditions.

Cabinets/panels on the SWEL that could be reasonably opened without undue safety or operational hazard were opened during the walkdown.

This allowed visual observation of internal anchorage to the structure (where present), as well as inspection for "other adverse seismic conditions" related to internal components that could be observed without breaking the plane of the door. Where opening the cabinet/panel was considered to exhibit undue safety or operational hazards, it was considered inaccessible and the completion of the* walkdown of that item was deferred to a later time (see Section 6.3). Where opening the cabinet/panel required extensive disassembly (e.g., doors or panels were secured by more than latches, thumbscrews, or similar), justification for how the inspection met the program goal without opening the cabinet/panel was included on the SWC and the walkdown of that item is considered complete.In addition to the general inspection requirements, at least 50% of the SWEL items having anchorage required confirmation that the anchorage configuration was consistent with plant documentation.

Of the 128 SWEL items, 81 were considered to have anchorage (i.e., removing in-line/line-mounted components).

Of these 81 anchored components, the walkdowns of 54, not counting deferred components (See Section 6.3), included anchorage configuration verification, which is greater than 50%. When anchorage configuration verification was conducted, the specific plant documentation used for comparison to the as-found conditions was referenced on the SWC.The SWC for each SWEL item, where a seismic walkdown has been initiated is included in Attachment C. A total of 128 SWCs are attached, 105 with completion status marked "Y" ("Y"- Yes, Walkdown is completed), 0 with completion status marked "N" ("N"- No, Walkdown has not been performed), and 23 with completion status marked "U" ("U"- Uncertain, More information on the component is required).

SWCs considered and marked "Uncertain", are 0 those where a walkdown was initiated, but whose completion was ultimately deferred because the cabinet/panel could not be opened during the walkdown period. Therefore, the Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 34 of 44.105 completed SWCs represent the completed walkdowns of the 128 SWEL items accessible during the walkdown period.7.2 AREA WALK-BYS Seismic area walk-bys were performed in accordance with Section 4 of the Guidance for all plant areas containing items on the SWEL (SWEL 1 plus SWEL 2). Area walk-bys were not deferred where components were deferred simply to open cabinets/panels.

A separate Area Walk-By Checklist (AWC) with the same content as that included in Appendix C of the Guidance was used to document the results of each area walk-by performed.

Photographs were taken of each area, and included on the corresponding SWC.Area walk-bys were conducted once for plant areas containing multiple SWEL items in close proximity to each other. In cases where the room or area containing a component was very large, the extent of the area encompassed by the area walk-by was limited to a radius of approximately 35ft around the subject equipment.

In some cases, the extent of the areas included in the area walk-bys is described on the AWC for that area. Because certain areas contained more than one SWEL item, there are fewer total area walk-bys conducted than seismic walkdowns.

A total of 61 area walk-bys was necessary to cover all plant areas containing at least one SWEL item.The AWC for each area walk-by completed is included in Attachment D. A total of 61 AWCs are attached, which represent all of the areas containing a SWEL item that were accessible during the walkdown period. No additional area walk-bys of areas need;-to be performed, since walk-bys for the deferred items have been completed (see Section 6.3).

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 35 of 44 8.0 LICENSING BASIS EVALUATIONS During the course of the seismic walkdowns and area walk-bys, SWE teams sought to identify existing degraded, non-conforming, or unanalyzed plant conditions with respect to its current seismic licensing basis identify.

This section summarizes the process used to handle conditions identified, what conditions were found, and how they were treated for eventual resolution.

CONDITON IDENTIFICATION When a potentially adverse condition was observed by a SWE team in the field, the condition was noted on the SWC or AWC form and briefly discussed between the two SWEs to determine whether it was a potentially adverse seismic condition.

These initial conclusions were based on conservative engineering judgment and the training required for SWE qualification.

For conditions that were reasonably judged as insignificant to seismic response, the disposition was included on the SWC or AWC checklist and the appropriate question was marked "Y", indicating that no associated potentially adverse seismic condition was observed.Unusual or uncertain conditions were reported to site personnel for further resolution (see Section 8.2). A total of 17 seismically insignificant conditions wqere identified.

These conditions were generally related to either housekeeping or mild degradation.

For conditions that were judged as potentially significant to seismic response, then the condition was photographed and the appropriate question on the SWC or AWC was marked"N" indicating that a potentially adverse seismic condition was observed.

The condition was then immediately reported to site personnel for further resolution and was documented for reporting in Attachment E. *A total of 17 potentially adverse seismic conditions were identified.

These conditions were generally related to non-conforming anchorage, spatial interaction, non-conforming support spacing, or inadequate line flexibility.

CONDITION RESOLUTION Conditions observed during the seismic walkdowns and area walk-bys determined to be potentially adverse seismic conditions are summarized in Attachment E, including how each condition has been addressed and its current status. Each potentially adverse seismic condition is addressed either with a Licensing Basis Evaluation (LBE) to determine whether it requires entry into the Corrective Action Program (CAP), or by entering it into the CAP directly.

The decision to conduct a LBE or enter the condition directly into the CAP was made on a case-by-case basis, based on the perceived efficiency of each process for eventual resolution of each specific condition.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 36 of 44 Unusual conditions that were not seismically significant were immediately brought to attention to plant personnel.

Further resolution of these conditions is not tracked or reported as part of the NTTF 2.3 Seismic Walkdown program, except by noting that the condition was observed by SWE and it was immediately brought to attention to plant personnel on the applicable SWCs and AWCs.8.1 LICENSING BASIS EVALUATIONS Potentially adverse seismic conditions identified as part of the NTTF 2.3 Seismic Walkdown program may be evaluated by comparison to the current licensing basis (CLB) of the plant as it relates to the seismic adequacy of the equipment in question, as is described in Section 5 of the Guidance.

If the identified condition is consistent with existing seismic documentation associated with that item, then no further action is required.

If the identified condition cannot easily be shown to be consistent with existing seismic documentation, or no seismic documentation exists, then the condition is entered into the CAP.Of the 17 identified potentially adverse seismic conditions, 14 did not require a LBE. All items summarized in Attachment E, are entered into the CAP or justification of their acceptability is provided in Attachment F.O 8.2 CORRECTIVE ACTION PROGRAM ENTRIES Conditions identified during the seismic walkdowns and area walk-bys that required further resolution were entered into the plant's Corrective Action Program (CAP) for further review and disposition in accordance with the plant's existing processes and procedures.

Conditions entered into the CAP included three types of unusual conditions identified:

• Seismically insignificant unusual conditions" Potentially adverse seismic condition that does not pass a LBE* Potentially adverse seismic condition that bypasses a LBE A total of 15 Condition.

Reports (CRs) were generated from the CAP as a result of the NTTF 2.3 Seismic Walkdown program. A total of 15 CRs were written relative to potentially adverse seismic conditions identified.

The CR numbers, current status, and resolution (where applicable and available) are summarized for these potentially adverse seismic conditions in Attachment E.8.3 PLANT CHANGES The CAP entries (CRs) generated by the NTTF 2.3 Seismic Walkdown program are being a) resolved in accordance with the plant CAP process, including operability evaluations, extent-of condition evaluations, and root cause analysis (where applicable).

Initial evaluations indicate that no immediate plant changes are necessary.

Final and complete resolutions of Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 37 of 44 the CRs for seismically insignificant unusual conditions and potentially adverse seismic conditions will determine if future modifications to the plant are required.

While no immediate plant modifications have been identified as a result of the seismic walkdowns and walk-bys, various cases were found where repairs are required or housekeeping issues are being addressed.

Current status and resolutions (where applicable and available) for CRs related to potentially adverse seismic conditions are provided in Attachment E.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 38 of 44 O 9.0 PEER REVIEW 9.1 PEER REVIEW PROCESS The peer review for the Near Term Task Force (NTTF) Recommendation

2.3 Seismic

Walkdowns was performed in accordance with and in conformance to Section 6 of the Guidance.

The peer review included an evaluation of the following activities:

review of the selection of the structures, systems, and components, (SSCs) that are included in the Seismic Walkdown Equipment List (SWEL);review of a sample of the checklists prepared for the Seismic Walkdowns and area walk-bys* review of licensing basis evaluations and decisions for entering the potentially adverse conditions in to the plant's Corrective Action Plan (CAP); and review of the final submittal report.At least two members of the peer review team (see Section 4.5) were involved in the peer review of each activity, the team member with the most relevant knowledge and experience taking the lead for that particular activity.

A designated overall Peer Review Team Leader provided oversight related to the process and technical aspects of the peer review, paying special attention to the interface between peer review activities involving different members of the peer review team.The peer review team was provided with an early draft of this submittal report for peer review.The peer review team verified that the submittal report met the objectives and requirements of Enclosure 3 to the 50.54(f) Letter, and documented the NTTF 2.3 Seismic Walkdown program performed in accordance with the EPRI Guidance.

The peer review team provided the results of review activities to the SWE team for consideration.

The SWE team satisfactorily addressed all peer review comments in the final version of the submittal report.The signature of the Peer Review Team Leader provides documentation that all elements of the peer review as described in Section 6 of the EPRI Guidance were completed.

9.2 PEER REVIEW RESULTS

SUMMARY

The following sections summarize the process and results of each peer review activity.9.2.1 Seismic Walkdown Equipment List Development The selection of items for the SWEL was peer reviewed in accordance with Section 3 of the EPRI Guidance.

Peer review comments were resolved and incorporated into the final SWEL, ensuring that all recommendations of the EPRI Guidance have been met.

Engineering Report No. JAF-RPT- 12-00015 f Rev. 0 Page 39 of 44 The final SWEL contains a diverse sample of equipment required to perform the five safety functions specified in the EPRI Guidance, which are:* Reactor reactivity control* Reactor coolant pressure control* Reactor coolant inventory control* Decay heat removal* Containment integrity In addition, the peer review process verified that SWEL items included major new and replacement items, a variety of environments, equipment enhanced based on findings of the IPEEE (if any), and risk insight considerations.

The peer review checklist of the SWEL is provided in Attachment G.9.2.2 Seismic Walkdowns and Area Walk-Bys Peer review of the seismic walkdowns and area walk-bys was conducted by two peer reviewers, each of whom is a qualified SWE and has broad knowledge of seismic engineering applied to nuclear power plants. One of the peer reviewers participated in the seismic walkdown program for a different utility, and the other is engaged with the industry team which developed the Guidance (see Section 4.5). The peer reviews were conducted at JAF concurrent with the conduct of walkdowns, at approximately 50% completion.

The peer review was performed as follows: The peer review team reviewed the walkdown packages (including checklists, photos, drawings, etc.) for SWEL items already completed to ensure that the checklists were completed in accordance with the Guidance.

A total of 23 SWC and 16 AWC forms were reviewed, each representing approximately 18% and 26%, respectively, of their totals. In the context of the Guidance, the peer review team considered the number of walkdown packages reviewed to be appropriate.

The packages reviewed represent a variety of equipment types in various plant areas. Specific SWC forms reviewed are SWELl -001, 032, 052, 069, 137, 157, 213, 433, 448, 452, 457, 474, 494, 501, 519, 624, 646, 670, 683, 686, 690, SWEL2-007 and SWEL2-009.

Specific AWC forms reviewed are AWC-003, 006, 009, 013, 015, 017, 018, 021, 022, 029, 033, 034, 045, 047, 049, and 057. During the selection of SWC's and AWC's to be peer reviewed, particular attention was given to obtaining a broad sample of items that encompass a variety of equipment and systems, equipment classes and environmental conditions.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 40 of 44* While reviewing the walkdown packages, the peer reviewers conducted informal interviews of the SWEs and asked clarifying questions to verify that they were conducting walkdowns and area walk-bys in accordance with the Guidance." The peer review team held a meeting with the SWE teams to provide feedback on the walkdown and walk-by packages reviewed and the informal interviews, and discuss potential modifications to the documentation packages in the context of the Guidance., The peer review team held a meeting with the SWE teams to provide feedback on the walkdown and walk-by observations, and discuss how lessons learned from review of the walkdown packages had been incorporated into the walkdown process.As a result of the peer review activities, the SWE teams modified their documentation process to include additional clarifying details, particularly related to checklist questions marked "N/A" and where conditions were observed but judged as insignificant.

The peer review team felt these modifications would be of benefit for future reviews of checklists incorporated into the final report. These modifications were recommended following review of the walkdown and area walk-by packages, and the observation walkdowns and area walk-bys demonstrated that the SWEs understood the recommendations and were incorporating them into the walkdown and area walk-by process. Previously completed checklists were revised to reflect lessons learned from the peer review process.Based on completion of the walkdown and walk-by peer review activities described, the peer review team concludes that the SWE teams are familiar with and followed the process for conducting seismic walkdowns and area walk-bys in accordance with the Guidance.

The SWE teams adequately demonstrated their ability to identify potentially adverse seismic conditions such as adverse anchorage, adverse spatial interaction, and other adverse conditions related to anchorage, and perform anchorage configuration verifications, where applicable.

The SWEs also demonstrated the ability to identify seismically-induced flooding interactions and seismically-induced fire interactions such as the examples described in Section 4 of the Guidance.

The SWEs demonstrated appropriate use of self checks and peer checks. They discussed their observations with a questioning attitude, and documented the results of the seismic walkdowns and area walk-bys on appropriate checklists.

9.2.3 Licensing

Basis Evaluations All potentially adverse seismic conditions were entered into the plant's CAP program for further review and disposition.

See Attachment E for summary of CRs and LB Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 41 of 44 evaluations.

The review team verified the decisions for identifying such conditions as being sound, and the dispositions were conducted in accordance with the plant's CLB.A peer review of the licensing basis evaluations was completed.

Within these licensing basis evaluations, CRs were generated for maintenance issues to replace missing bolts, nuts or remove items for housekeeping issues, or to provide further, detailed resolution of the potentially adverse seismic condition when applicable.

The remaining licensing basis evaluations were created to document potentially adverse seismic conditions that were immediately entered into the CAP for detailed evaluation and investigation.

See Attachment F for detailed LB evaluations.

The peer review of these LB evaluations ensured that all the information provided from the walkdown team to the licensing basis evaluation team member, provided enough detail for accurate and timely resolution.

See Attachment I for comments received on LB evaluations.

9.2.4 Submittal

Report The peer review team was provided with an early draft of this submittal report for peer review. The peer review team verified that the submittal report met the objectives and requirements of Enclosure 3 to the 50.54(f) Letter, and documented the NTTF 2.3 Seismic Walkdown program performed in accordance with the Guidance.

The peer review team provided the results of review activities to the SWE team for consideration.

The SWE team satisfactorily addressed all peer review comments in the final version of the submittal report. The signature of the Peer Review Team Leader provides documentation that all elements of the peer review as described in Section 6 of the Guidance were completed.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 42 of 44 O

10.0 REFERENCES

10.1. 10CFR50.54(f)

Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident, dated March 12, 2012 10.2. EPRI 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, June 2012 10.3. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report (UFSAR)10.4. Generic Letter No. 88-20, Supplement 4 and 5, Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities 10.5. James A. Fitzpatrick Nuclear Power Plant Individual Plant Examination of External Events (IPEEE), JAF-RPT-MISC-0221 1, Revision 0, Submitted June 1996.10.6. Generic Letter No. 87-03, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue (USI) A-46 10.7. Seismic Qualification Utility Group (SQUG) Procedure:

Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Power Plant Equipment, Revision 3A, December 2001 10.8. JAF Document 18570.00, Rev. 1, "Design Criteria for Balance of Plant (BOP)Piping Stress and Supports -James A. FitzPatrick Nuclear Power Plant." 10.9. Engineering Standard Manual: CES-2B, Rev. 0, "Seismic Design of Electrical Conduit Supports for JAF." 10.10. JAF-RPT-ELEC-02075, Rev. 2, "Design Criteria for Independence of Redundant Electrical Circuits." 10.11. EN-DC-168, Rev. 0, "Fukushima Near-Term Task Force Recommendation

2.3 Seismic

Walk-down Procedure." 10.12. JAFP-12-0075, "Entergy's 120-Day Response to the NRC Request for Information (RFI) Pursuant to 1 OCFR50.54(f)

Regarding the Seismic Aspects of Recommendation 2.3 of the Near Term Task Force Review of Insights from the Fukushima Dai-ichi Accident."

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 43 of 44 10.13. USI A-46, "Seismic Evaluation Report Volume INI, Stevenson

& Associates," September 1995.10.14. James A. FitzPatrick Nuclear Power Plant, Safe Shutdown Equipment and Relay Evaluation For unresolved Safety Issue USI A-46," September 1995, Volume I of XII.

Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 44 of 44 11.0 ATTACHMENTS ATTACHMENT A -IPEEE VULNERABILTIES TABLE ATTACHMENT B -SEISMIC WALKDOWN EQUIPMENT LISTS ATTACHMENT C -SEISMIC WALKDOWN CHECKLISTS (SWCs)ATTACHMENT D -AREA WALK-BY CHECKLISTS (AWCs)ATTACHMENT E -POTENTIALLY ADVERSE SEISMIC CONDITIONS ATTACHMENT F -LICENSING BASIS EVALUATION FORMS ATTACHMENT G -PEER REVIEW CHECKLIST FOR SWEL ATTACHMENT H -SEISMIC WALKDOWN ENGINEER TRAINING CERTIFICATES ATTACHMENT I -PEER REVIEW COMMENTS Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Attachment A"IPEEE Vulnerabilities Table" 0 Attachment A Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 1 of 1 ATrACHMENT

9.3 IPEEE

VULNERABILrmES TABLE FoRM V-0 Seismic-induced station blackout sequences are controlled by Strengthen high nisk emergency diesel generator building (EGB) Design change DC#O1-96-011, Rev.0 and calculation JAF-CALC-_

Y 1211911997 seismic-induced failures of emergency diesel generator block walls EGB-272-6, 7, 9 and 10. The seismic-induced station EDG-02153, Rev0. implemented and evaluated the proposed building (EGB) and electric bay (EB) block walls: blackout sequences responsible for the 0.17g pga overall plant modification which reinforced the block wall to a higher frequency HCLPF -High Confidence Low Probability Failure HCLPF capacity for JAF are controlled by seismic-induced failures range, and the corresponding structural capacity of block walls EGB-272-6,7,9 and 10 (HCLPF = 0.17g) of these block walls, increased to 0.26 g. The existing steel structures are capable to EB-272-15 (HCLPF = 0.22g) A modification (MOD# D1 011) is being planned to accomplish resist the additional load due to modification.

This is based on the EB-286-2 (HCLPF = 0.23g) this strengthening existing concrete structure is capable to resist all of the seismic loads.Calculation 93C2803-C01 2, "HCLPF for Block Walls EB-272-1,2, Rev. 0, evaluated Electrical Bay block walls and the block walls were found acceptable.

Yaroslav Losev/ Dae 1-221 Prepared by: Date: 11/12/2012 Engineering Report No. JAF-RPT-12-00015 Rev. 0 Attachment B"Seismic Walkdown Equipment Lists" S Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 1 of 86 ATTACHMENT

9.4 SEISMIC

WALKDOWN EQUIPMENT LISTS FORM Table 9.4.1 -Base List I (BL 1)I JNTSOUG EQUIP~ CUNRENR SL111IETEUPMEN DES~CRIPTION SCREEN I RW2ýCRE E#4II.- SCREEN 4 F-SfyFb hapAJe EQUIPMENT ID 0_8A -MOtor- SGT FILTER TRAIN A O perated O1.125MOV-14A O1-125MOV-14A INLE ISOLATION YES NO

• YES NO N/A I NO NO X Valves VALVE 20 -Instrument RSEACTOR VESSEL 02-3L1-85A 02-3L1-85A LE INDIATION YES NO NO NO N/A NO and ControlLVEI Panels 20-I Instrument 02-3LI-85B (02- 02-3L1-85B (02- DIV I RX WATER YES NO NO NO N/A I NO and Control 3LR-85B) 3LR-85B) LEVEL RECORDER Panels 18 --REACTOR VESSEL Instrument 02-3LT-85A 02-3LT-85A WIDE RANGER YES NO NO NO N/A I NO RaCks LEVEL xMrrOrER EQ 18- REACTOR VESSEL Instrument 02-3LT-85B 02-3LT-85B WIDE RANGER YES NO NO NO N/A I NO Racks LEVEL XMITTER EQ 07- ADS REACTOR HEAD Pneumatic-02AOV-17 02AOV-17 VENT INBD ARE YES NO YES NO N/A I NO X Operate, OPER VALVE Valves 07 -Pemc ADS REACTOR HEAD 1 Peratec 02AOV-18 02AOV-18 VENT OUTBD AIR YES NO YES NO N/A I NO X Operated OPER VALVE Valves 07- ADS MAIN STEAM Pneumatic-LN 02RV-71A 02RV-71A LINEYES NO YES NO N/A NO Operated SAFETY/RELIEF Valves VALVE EN-DC-168 REV 0 e Attachment B Engineering Report No. JAF-RPT-12-O0015 Rev. 0 Page 2 of 86 UI -MAIN Z I hAM 1 Pneumati -0o2RV-71B 02RV-71B LINE A ISAFETY/RELIEF x YES NO YES NO I N/A NO x x IVALVE 07- ADS MAIN STEAM 02RV-71C 02RV-71C LINEYES NO YES X Operatedj SAFETY/RELIEF Valves VALVE 07- ADS MAIN STEAM Opneated 02RV-71D 02RV-71D LINEYES NO YES X x x SAFETY/RELIEF Valves VALVE 07- ADS MAIN STEAM 02RV-71E 02RV-71E LINE C YES NO YES Xx Operated SAFETY/RELIEF.

YE NOES ES /AITO Valves VALVE 07- ADS MAIN STEAM 02RV-71F 02RV-71F LINETC YES NO YES Xx Operated SAFETY/RELIEF YS NOES ES /AIO Valves IVALVE 07-- ADS MAIN STEAM Pneumati-LINE C O2RV-71G 02RV-71G LINES NO YES Operated SAFETY/RELIEF YES NO YES NO N/A I No Valves VALVE 07- ADS MAIN STEAM Pneumatic-LN 02RV-71H 0O2RV-71H LINE D YES NOxESx Operated 02RV-71 H OýRV-71 H SAFETY/RELIEF YES NO YES NO N/A I NO Valves VALVE 07- ADS MAIN STEAM 02RV-71J 02RV-71J LINE D YES NO YES Xx Operated SAFETY/RELIEF Valves VALVE 07- ADS MAIN STEAM O)2RV-71K 02RV-71K LINE A YES NO YES Xx Operatedl SAFETY/RELIEF Valves VALVE EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 3 of 86 EN-DC-168 REV 0.

A h .Attachment B*Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 4 of 86 I Ubb -Solenoid-Operated Valves 02SOV-71G2 02SOV-71 G2 DL)S/MST C 02NV-71G REMOTE MANUAL PILOT SOLENOID VALVE YES NO YES NO N/A NO x x x 08B -ADS/MST D 02RV-71H Solenoid-02SOV-71H2 02SOV-71H2 REMOTE MANUAL YES NO YES NO N/A I NO x x x Operated PILOT SOLENOID Valves VALVE 08B -ADS/MST D 02RV-71J Solenoid-02SOV-71J2 02SOV-71J2 REMOTE MANUAL YES NO YES NO N/A I NO X X X Operated PILOT SOLENOID Valves VALVE 08B -ADS/MST A 02RV-71K Solenoid-REOEMNA 02SOV-71K2 02SOV-71K2 REMOTE MANUAL YES NO YES NO N/A I NO X X X Operated PILOT SOLENOID Valves VALVE 08B -ADS/MST D 02RV-71L Solenoid-02SOV-71L2 02SOV-71L2 REMOTE MANUAL YES NO YES NO N/A I NO X X X Operated PILOT SOLENOID Valves VALVE 07-Pneumatic-03AOV-126(HCU-03AOV- HCU INLET SCRAM YES NO YES NO NIA I T NO X Operated 02-19) 126(HCU-02-19)

AIR OPER VALVE Valves 07-Pneumnatic-03AOV-127(HCU-03AOV- HCU OUTLET SCRAM YES NO YES NO N/A I T NO X Operated 02-19) 127(HCU-02-19)

AIR OPER VALVE Valves 08B -08B -HCU-02-19 SCRAM Solenoid-D3SOV-117(H-CU-O3SOV- HC-21SRA Operatd 02-19) 117(HCU PILOT AIR SOLENOID YES NO YES NO N/A I NO X Operated 02-19) 117(HCU-02-19)

OPER VALVE Valves 08B -08B -HCU-02-19 SCRAM Solenoid-03SOV-118(HCU-03SOV- HC--1SRA olenoid 02-19 8(H 18-HCU PILOT AIR SOLENOID YES NO YES NO N/A I -NO X Operated 02-19) 1 18(HCU-02-19)

OPER VALVE Valves EN-DC-168 REV 0 e Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 5 of 86 08B -Solenoid-03SOV-120(HCU-I03SOV-I Operated 102-19) 1120(HCU-02-19)

Valves.HCU-02-19 WITHDRAW SETTLE SOLENOID OPER VALVE YES NO YES NO N/A NO X 08B -HCU-02-19 INSERT 1 Solenoid-03SOV-121(HCU-03SOV- EXHAUST WATER YES NO YES NO N/A I NO X Operated 02-19) 121(HCU-02-19)

SOLENOID OPER Valves VALVE 08B -HCU-02-19 1 Solenoid-03SOV-122(HCU-03SOV- WITHDRAW DRIVE YES NO YES NO N/A I NO Operated 02-19) 122(HCU-02-19)

WATER SOLENOID Valves OPER VALVE BB -HCU-02-19 INSERT 1 Solenoid-03SOV-123(HCU-03SOV- DRIVE WATER YES NO YES NO N/A I NO X Operated 02-19) 123(HCU-02-19)

SOLENOID OPER Valves VALVE 08B -Solenoid-SDIV ISOL TEST 1 03SOV-29 03SOV-29 SOID VALVE YES NO YES NO N/A I NO X Operated SOLENOID VALVE Valves 08B- SDIV A AOV Solenoid-INSTRUMENT AIR 1 od- 03SOV-31A 03SOV-31A SUP ENOID YES NO YES NO N/A I NO X Operated SUPPLY SOLENOID Valves VALVE EQ 08B -SDIV B AOV Solenoid-INSTRUMENT AIR 1 03SOV-31B 03SOV-31 B SUP ENOID YES NO YES NO N/A I NO X Operated SUPPLY SOLENOID Valves VALVE B EQ 1 0-Other 03TK-125(HCU.

03TK-125(HCU-WATER YES NO YES NO NIA I T NO 02-19) 02-19) ACCUMULATOR 1 0-Other 03TK-128(HCU-03TK-128(HCU-NITROGEN YES NO YES NO N/A I T NO 02-19) 02-19) ACCUMULATOR 21- Tanks CRD A SDIV SCRAM 1 and Heat 03TK-1A 03TK-1A DISCH INSTRUMENT YES NO YES NO N/A I NO X Exchangers AIR VOLUME TANK EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-O0015 Rev. 0 Page 6 of 86 EN-DC-168 REV 0 e Attachment B Engineering Report No. JAF-RPT-12-O0015 Rev. 0 Page 7 of 86 I iibuumn 109-39 and Control Panels 09-39 HPCI RELAY PANEL YES NO YES NO N/A NO x x x 20-Instrument B9-45LOWDOWN YES NO YES NO NIA I NO NO x X x and Control RELAY CABINET Panels 20 -Instrument CORE SPRAY 09-46 09-46 CHANNEL"A" RELAY YES NO YES NO N/A I NO X x x and Control CABINET Panels IBN 20 -In0 n CORE SPRAY Instrument 09-47 09-47 CHANNEL "B RELAY YES NO YES NO N/A I NO X x x and Control CABINET Panels 20 -Instrument REACTOR CONTROL 09-5 09-5 MAIN CONTROL YES NO YES NO N/A I NO X x x x and Control BOARD Panels 20-Instrument BALANCE OF PLANT andtCont 09-6 09-6 (MECH) MAIN YES NO NO NO N/A I NO Panels CONTROL BOARD 20- EMERGENCY CORE Instrument COOLING SYSTEM 09-95 09-95 DYES NO NO YES N/A I NO and Control DIV 1 A/C TRIP Panels CABINET 20- EMERGENCY CORE Instrument 09-96 09-96 COOLING SYSTEM YES NO NO NO N/A I NO and Control DIV 2 B/D TRIP Panels CABINET 20-Instrument 09AR-5A 09AR-5A (RED)A AUXILIARY YES NO YES NO N/A I NO x and Control RELAY CABINET Panels EN-DC-168 REV 0 e Attachment B 0 Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 8 of 86 I 4u -Instrument and Control Panels 09AR-5B 09AR-5B (BLUE) B AUXILIARY RELAY CABINET YES NO YES NO N/A NO X 077-a RHR A LPCI Pneumatic-IOAOV-68A IOAOV-68A TESTABLE CHECK YES NO YES NO ">NIA I T NO X Operated VALVE Valves 07 -Pn7 c RHR B LPCI 1OAOV-68B 10AOV-68B TESTABLE CHECK YES NO YES NO N/A I NO X Operated VALVE Valves 07- RHR HEAT Pneumafic-10AOV-71A 10AOV-71A UXCHANGER A YES NO YES NO N/A I NO X Operated OUTLET TO TORUS Valves OR RCIC ISOL VALVE 07- RHR HEAT Pneumatic-EXCHANGER Bx 1OAOV-71B I0AOV-71B EUTLE R YES NO YES NO N/A I NO Operated OUTLET TO TORUS Valves OR RCIC ISOL VALVE 21 -Tanks RESIDUAL HEAT and Heat 10E-2A' 10E-2A REMOVAL SYSTEM YES NO YES NO N/A I NO NO. X Exchangers HEAT EXCHANGER A 21 -Tanks RESIDUAL HEAT and Heat 1OE-2B 1OE-2B REMOVAL SYSTEM YES NO YES NO N/A I NO X Exchangers HEAT EXCHANGER B 20-Irnstrument IOFI-132A 10FI-132A RHRSW PUMPS A&C YES NO YES NO N/A I NO X X and Control DISCH FLOW INDIC Panels 20-Instrument 1OFI-132B 10FI-132B RHRSW PUMPS B&D YES NO YES NO N/A I NO X X and Control DISCH FLOW INDIC Panels EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 9 of 86 I Instrument and Control Panels 10FI-133A 10FI-133A CONTAINMENT SPRAY LOOP FLOW INDIC YES NO YES NO N/A NO x 20- B REACTOR AND Instrument 10FI-133B 1OFI-133B SONTAINMENT YES NO YES NO N/A I NO X and Control SPRAY LOOP FLOW Panels INDIC 18- -RHR LOOP A FLOW Instrument 1-FT-109A 1OFT-109A YES NO YES NO N/A NO x X Racks XMITTER EQ 18-18-RHR BDISCH HDR Instrument 1OFT-109B 1OFT-109B FLO B ISER YES NO YES NO N/A I NO X X Racks FLOW XMII-ER 18- RHRSW A DISCH Instrument 1OFT-97A 1OFT-97A HDR FLOW XMITTER YES NO YES NO N/A I NO X x Racks 18- RHRSW LOOP B Instrument 1OFT-97B 10FT-97B FLOW XMITTER EQ YES NO YES NO N/A I NO X x Racks 08A -Motor-Operated IOMOV-12A IOMOV-12A RRYES NO YES NO A I NO NO X x Valves OUTLET ISOL VALVE 08A -Motor- RHR HEAT EXCH B Operated 10MOV-12B 10MOV-12B YES NO YES NO N/A I NO X X Valves OUTLET ISOL VALVE 08A -Motor-RHR PUMP A SUCT Operated 10MOV-13A 1OMOV-13A TORUS SQL VALVE YES NO YES NO N/A 'I NO X X Valves 08A -Motor-RHR PUMP B SUCT Operated IOMOV-13B 10MOV-13B TORUS ISOL VALVE YES NO YES NO N/A I NO x X Valves 08A -Motor- RHR PUMP C SUCT N Operated 10MOV-13C IOMOV-13C TORUS S VALV YES NO YES NO N/A INO X X Valves TORUS ISOL VALVE EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 10 of 86 1 ObA -Motor-Operated Valves RHR PUMP D SUCT IOMOV-13D 10MOV-13D YES NO YES NO N/A NO x x TORUS ISOL VALVE 08A -Motor- RHRSW A TO RHR 1 Operated 10MOV-148A 1OMOV-148A CROSS TIE UPSTR YES NO YES NO N/A I NO X Valves ISOL VALVE 08A -Motor- RHRSW B TO RHR 1 Operated 10MOV-148B 10MOV-148B CROSS TIE UPSTR YES NO YES NO N/A I NO X Valves ISOL VALVE 08A -Motor- RHR PUMPS A&C 1 Operated 10MOV-151A 10MOV-151A SUCT SUPPR POOL YES NO YES. NO N/A I NO x Valves ISOL VALVE 08A -Motor- RHR PUMPS B&D 1 Operated 1OMOV-151B 10MOV-151B SUCT SUPPR POOL YES NO YES NO N/A I NO X Valves ISOL VALVE aBA -Motor- IRHR PUMP A SUCT SHUTDOWN 1 Operated 10MOV-15A IOMOV-15A YES NO YESx Valves COOLING ISOL VALVE 08A -Motor- RHR PUMP B SUCT 1 Operated 10MOV-15B 10MOV-15B YES NO YES NO N/A I NO X Valves COOLING ISOL VALVE 08A -Motor- RHR PUMP C SUCT 1 Operated 10MOV-15C 10MOV-15C SHUTDOWN YS N E O NA IN VavsCOOLING ISOL YE NOYE NO /A IOX ValvesVALVE OBA Moor-RHIR PUMP D SUCT 08A -Motor- SHTDW SHUTDOWN 1 Operated IOMOV-15D 1OMOV-15D YES NO

• YESx Valves COOLING ISOL VALVE 08A -Motor- RHR HEAT EXCH A 1 Operated 1MOV-166A 10MOV-156A UPSTR VENT TO YES NO YES NO N/A I NO x Valves TORUS ISOL VALVE EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-O0015 Rev. 0 Page 11 of 86 EN-DC-168 REV 0 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 12 of 86 I 08A -Motor-Operated Valves 1OMOV-34A 1OMOV-34A COOLING SUPPLY VALVE YES NO YES NO N/A NO x 08A -Motor- RHR B TORUS Operated 10MOV-34B 10MOV-34B COOLING SUPPLY YES NO YES NO N/A I NO X Valves VALVE 08A -Motor- RHR A TO TORUS Operated 10MOV-38A 1OMOV-38A YES NO YES NO N/A I NO X Valves SPRAY ISOL VALVE 08A -Motor- RHR B TO TORUS Operated IOMOV-38B 10MOV-38B RAY ISO VALVE YES NO YES NO N/A I NO x ValvesSPRAY ISOL VALVE Valves 08A -Motor- RHR A TORUS Operated 10MOV-39A 1OMOV-39A COOLING ISOL YES NO YES NO N/A I NO X Valves VALVE 08A -Motor- RHR B TORUS Operated 1OMOV-39B 10MOV-39B COOLING ISOL YES NO YES NO N/A I NO X Valves VALVE 08A -Motor- RHR HEAT EXCH A Operated 10MOV-65A 10MOV-65A SHELL INLET ISOL YES NO YES NO N/A I NO x Valves VALVE 08A -Motor- RHR HEAT EXCH B Operated 1OMOV-65B 10MOV-65B SHELL INLET ISOL YES NO YES NO N/A I NO X Valves VALVE 08A -Motor- RHR HEAT EXCH A Operated 10MOV-66A 10MOV-66A YES NO YES NO N/A NO x Valves BYPASS VALVE 08A -Motor-OBA -Motor- ~~~RHR HEAT EXCH B YE NOES O N/ I Operated 10MOV-66B 10MOV-66B BYPAT VALVE YES NO YES NO N/A NO X Valves BYPASS VALVE 08A -Motor- RHR HEAT EXCH A Operated 10MOV-70A 1OMOV-70A STEAM INLET ISOL YES NO NO NO N/A I NO X Valves VALVE EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 13 of 86 EN-DC-168 REV 0 0 A Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 14 of 86 1 00 -Other IORHR-274 10RHR-274 KI-RH LUOP A CONTAINMENT SPRAY KEEP-FULL COND XFER CONNECTION VALVE YES NO NO NO I N/A NO 07- RHRPUMPA Pneumatic-10RV-41A 10RV-41A SHUTDOWN YES NO NO NO NO Operated COOLING SUCT Valves RELIEF VALVE 07- RHRPUMPB Pne umatic- SUDW P m 10RV-41B 10RV-41B YES NO NO NO NO Operated COOLING SUCT Valves RELIEF VALVE 07- RHR PUMP C Pneumatic-I0RV-41C 10RV-41C SHUTDOWN YES NO NO NO N/A I NO Operated COOLING SUCT Valves RELIEF VALVE 07- RHRPUMPD Pne umatic- SUDW P 10RV-41D 1ORV-41D SHUTDOWNYES NO NO NO NO Operated COOLING SUCT Valves RELIEF VALVE 07P RHR HEAT Pneumatic-1ORV-43A 1ORV-43A EXCHANGER A TUBE YES NO NO NO N/A I NO Operated SIDE RELIEF VALVE Valves 07- RHR HEAT P 10RV-43B 1ORV-43B EXCHANGER B TUBE YES NO NO NO N/A I NO Operated SIDE RELIEF VALVE Valves 07- RHR HEAT Pne umatic-P 1ORV-46A 1ORV-46A EXCHANGE A SHELL YES NO NO NO N/A I NO Operated SIDE RELIEF VALVE Valves EN-DC-1 68 REV 0 Attachment B Engineering Report No. JAF-RPT-12-O0015 Rev. 0 Page 15 of 86 1 07-Pneumatic-Operated Valves 1ORV-46B 1ORV-46B RHR HEAT EXCHANGER B SHELL SIDE RELIEF VALVE YES NO NO NO N/A NO RESIDUAL HEAT 00 Other 10S-5A1 10S-SA REMOVAL SERVICE YES NO YES YES WA I T NO X WATER STRAINER 08B -RHRSW PUMP A Solenoid-0SOV-10A 10SOV-10A MOTOR COOLING YEs NO NO NO I NO Operated WATER RETURN Valves SOLENOID VALVE 08B -RHRSW PUMP B Solenoid-10SOV-101B 1OSOV-101B MOTOR COOLING YES NO NO NO N/A I NO Operated WATER RETURN Valves SOLENOID VALVE 08B -RHRSW PUMP C Solenoid-10SOV-10iC 10SOV-101C MOTOR COOLING YES NO NO NO N/A I NO Operated WATER RETURN Valves SOLENOID VALVE 08B -RHRSW PUMP D Solenoid-MOTOR COOLING So 1OSOV-101D 10SOV-11D WATER RETURN YES NO NO NO N/A I NO Operated WATER RETURN Valves SOLENOID VALVE 08B -RHR HEAT Solenoid-EXCHANGER A SIOSOV-263A 10SOV-263A OUTLET INNER YES NO NO NO N/A I NO Operated SAMPLE SOLENOID Valves VALVE 08B -RHR HEAT Solenoid-EXCHANGER B S1OSOV-263B 1OSOV-263B OUTLET INNER YES NO NO NO N/A I NO Operated SAMPLE SOLENOID Valves VALVE EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 16 of 86 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 17 of 86 EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-O0015 Rev. 0 Page 18 of 86 EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 19 of 86 I 19-Temperatur e Sensors 16-IRTD-131A 16-1RTD-131A TORUS BULK TEMP MONITOR 0 AZIMUTH BAY L X-232 RESIST TEMP DETECTOR EQ YES NO YES NO N/A T NO x 19- TORUS BULK TEMP MONITORO0AZIMUTH N Temperature 16-1RTD-131B 16-1RTD-131B BAYLX-232MREAIMT YES NO NO N/A Sensors BYLX22RSS SensorsTEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 22.5 Temperature 16-1RTD-132A 16-1RTD-132A AZIMUTH BAYKX- YES NO NO NO N/A I NO Sensors 233 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 22.5 Temperature 16-1RTD-132B 16-IRTD-132B AZIMUTH BAY K X- YES NO NO NO N/A I NO Sensors 233 RESIST TEMP I DETECTOR EQ TORUS BULK TEMP 19- MONITOR45 Temperature 16-1RTD-133A 16-1RTD-133A AZIMUTH BAY J X-234 YES NO NO NO N/A I NO Sensors RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 45 Temperature 16-1RTD-133B 16-IRTD-133B AZIMUTH BAY J X-234 YES NO NO NO N/A I NO Sensors RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 67.5 Temperature 16-1RTD-134A 16-1RTD-134A AZIMUTH BAY I X-235 YES NO NO NO N/A I NO Sensors RESIST THERMAL DETECTOR EQ EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 20 of 86 I 19-Temperature Sensors 16-1RTD-134B 16-1RTD-134B I -Qu Du-r I -VIVI MONITOR 67.5 AZIMUTH BAY I X-235 RESIST TEMP DETECTOR EQ N/A YES NO NO NO NO TORUS BULK TEMP 19 -MONITOR 90 Temperature 16-1RTD-135A 16-1RTD-135A AZIMUTH BAY H X- YES NO NO NO N/A I NO Sensors 236 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 90 Temperature 16-1RTD-135B 16-1RTD-135B AZIMUTH BAY H X- YES NO NO NO N/A I NO Sensors 236 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 112.5 Temperature 16-1RTD-136A 16-1RTD-136A AZIMUTH BAY G X- YES NO NO NO N/A I NO Sensors 237 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 112.5 Temperature 16-1RTD-136B 16-1RTD-136B AZIMUTH BAY G X- YES NO NO NO N/A I NO Sensors 237 RESIST TEMP I> DETECTOR EQ TORUS BULK TEMP 19 -MONITOR 135 Temperature 16-1RTD-137A 16-1RTD-137A AZIMUTH BAY F X- YES NO NO NO N/A I NO Sensors 238 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 135 Temperature 16-1RTD-137B 16-1RTD-137B AZIMUTH BAY F X- YES NO NO NO N/A I NO Sensors 238 RESIST TEMP DETECTOR EQ EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 21 of 86 1 19-Temperature Sensors 16-1RTD-138A.

16-1RTD-138A I UKUO bULN I r-Mr MONITOR 157.5 AZIMUTH BAY E X-239 RESIST TEMP DETECTOR EQ YES NO NO NO N/A NO TORUS BULK TEMP 19,- MONITOR 157.5 Temperature 16-1RTD-138B 16-1RTD-138B AZIMUTH BAY E X- YES NO NO NO N/A I NO Sensors 239 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 180 Temperature 16-1RTD-139A 16-1RTD-139A AZIMUTH BAY D X- YES NO NO NO N/A I NO Sensors 240 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 180 Temperature 16-1RTD-139B 16-1RTD-139B AZIMUTH BAY D X- YES NO NO NO N/A I NO Sensors 240 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 202.5 Temperature 16-1RTD-140A 16-1RTD-140A AZIMUTH BAY CX- YES Nb NO NO N/A I NO Sensors 241 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 202.5 Temperature 16-1RTD-140B 16-1RTD-140B AZIMUTH BAY C X- YES NO NO NO N/AW I NO Sensors 241,RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 22.5 Temperature 16-1RTD-141A 16-1RTD-141A AZIMUTH BAY B X- YES NO NO NO N/A I NO Sensors 242 RESIST TEMP DETECTOR EQ EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 22 of 86 1 19-Temperature Sensors 16-1RTD-141B 16-1RTD-141B TORUS BULK TEMP MONITOR 22.5 AZIMUTH BAY B X-242 RESIST TEMP DETECTOR EQ YES NO NO NO N/A NO TORUS BULK TEMP 19- MONITOR 247.5.Temperature 16-1RTD-142A 16-1RTD-142A AZIMUTH BAY A X- YES NO NO NO N/A I NO Sensors 243 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 247.5 Temperature 16-1RTD-142B 16-1RTD-142B AZIMUTH BAYA X- YES NO NO NO N/A I NO Sensors 243 RESIST TEMP IDETECTOR EQI TORUS BULK TEMP 19- MONITOR 270 Temperature 16-1RTD-143A 16-1RTD-143A AZIMUTH BAY P X- YES NO NO NO N/A I NO Sensors 244 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 270 Temperature 16-1RTD-143B 16-1RTD-143B AZIMUTH BAY P X- YES NO NO NO N/A I NO Sensors 244 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 292.5 Temperature 16-1RTD-144A 16-1RTD-144A AZIMUTH BAY OX- YES NO NO NO N/A I NO Sensors 245 RESIST TEMP DETECTOR EQ TORUS BULK TEMP 19- MONITOR 292.5 Temperature 16-1RTD-144B 16-1RTD-144B AZIMUTH BAYOX- YES NO NO NO N/A I NO Sensors 245 RESIST TEMP DETECTOR EQ EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 23 of 86 EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-O0015 Rev. 0 Page 24 of 86 EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 25 of 86 I 10-Instrument 23LT-202A Racks 23LT-202A aU rrm0Iuv rUvUL HPCI LOGIC LEVEL XMITrER EQ YES NO YES NO I N/A NO NO x 18- SUPPRESSION POOL 1 Instrument 23LT-202B 23LT-202B HPCI LOGIC LEVEL YES NO NO NO N/A I NO Racks XMIT-ER EQ O0A -Motor- HPCI TURBINE I Operated 23MOV-14 23MOV-14 STEAM SUPPLY ISOL YES NO YES YES N/A I T NO x X x X Valves VALVE 08A -Motor-Operated 23MOV-15 23MOV-15 HPCI STEAM SUPPLY YES NO YES YES N/A I NO X X x X 1 atved MINBD ISOL VALVE Valves 08A -Motor- HPCI TURBINE 1 Operated 23MOV-16 23MOV-16 STEAM SUPPLY YES NO YES YES N/A I NO X x X X Valves OUTBD ISOL VALVE HPCI BOOSTER 08A -Motor- PIOSE OB oo-PUMP P-i1B SUCT 1 Operated 23MOV-17 23MOV-17 FROM 33TK-1A & B YES NO YES NO N/A I NO x X x Valves FO 3K1 ISOL VALVE 08A -Motor- HPCi PUMP DISCH 1 Operated 23MOV-19 23MOV-19 TO REACTOR INBD YES NO YES NO N/A I NO X X X Valves ISOL VALVE 08A -Motor- HPCI PUMP DISCH 1 Operated 23MOV-20 23MOV-20 TO REACTOR OUTBD YES NO YES NO N/A I NO X x X Valves ISOL VALVE HPCI FULL FLOW Operated 23MOV-21 M3MOV-21 TEST RETURN TO YES NO YES NO N/A I NO CST 33TK-1A & B Valves UPSTR ISOL VALVE 08A -Motor- HPCI FULL FLOW 1 Operated 23MOV-24 23MOV-24 TEST RETURNTO YES NO NO NO N/A I NO CST 33TK-1A & B VDNSTR ISOL VALVE EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 26 of 86 1.JUR -motor-Dperated Valves 23MOV-25 23MOV-25 IH)'.UI MVAIN tUMP t-IM MIN FLOW ISOL VALVE YES NO NO NO N/A.NO HPCI BOOSTER 08A -Motor- PUMP P-1B SUCT 1 Operated 23MOV-57 23MOV-57 FROM SUPPRESSION YES NO NO NO N/A I NO Valves POOL DNSTR ISOL VALVE HPCI BOOSTER 08A -Motor- PUMP P-1B SUCT 1 Operated 23MOV-58 23MOV-58 FROM SUPPRESSION YES NO YES NO NIA I NO X X X Valves POOL UPSTR ISOL VALVE 08A -Motor- HPCI TURB EXH LINE 1 Operated 23MOV-59 23MOV-59 VAC BREAKER YES NO YES NO N/A I NO X X X Valves VALVE HPCI TURBINE 08A -Motor- STEAM SUPPLY 1 Operated 23MOV-60 23MOV-60 OUTBD ISOL VALVE YES NO NO YES N/A I NO Valves 23MOV-16 BYPASS I IVALVE OS -H Horizontal 23P-150 23P-150 HPCITURBINEAUX YES NO .YES NO N/A I T NO X Pumps LUBE OIL PUMP 05- -PIOSE 1 Horizontal 23P-1B 23P-1B PCUMOOTE YES No YES NO N/A I NO X X X Pumps 05-H Horizontal 23P-1M 23P-1M HPCI MAIN PUMP YES NO YES NO N/A I T NO X X X Pumps 05-Horz- HPUMAP LBOI E NO YES NO N/A I NOX X X 1 Horizontal 23P-1MO 23P-MO HPCl MAIN P uMP YES I NO Pumps EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 27 of 86 EN-DC-1 68 REV 0 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 28 of 86 EN-DC-168 REV 0 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 29 of 86 EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 30 of 86 I 18-Instrument Racks 27NS-CB 27NS-CB.AU b NI IXUUtrN SUPPLY INSTR CABINET YES NO NO NO N/A NO 21 -Tanks CAD TRAIN A and Heat 27NV-9A 27NV-9A YES NO NO NO N/A I NO Exchaners ABIENT VAPORIZER Exchangers 21 -Tanks CAD TRAIN B and Heat 27NV-9B 27NV-9B AMBIENT VAPORIZER YES NO NO NO N/A I NO Exchangers 07- 27PC-101A Pneumatic-27COA 1 27PCV-101A 27PCV-101A NITROGEN SUPPLY YES NO NO NO N/A I NO Operated PRESS REGULATOR Valves 07- 27PC-IOIB Pneumatic-27PCV-101B 27PCV-101B NITROGEN SUPPLY YES NO NO NO N/A I NO Operated PRESS REGULATOR Valves 07- 27FCV-111 P'neumatic-PSTOE Pneumatc 27PCV-102A 27PCV-102A POSITIONERYES NO NO NO N/A I NO Operated NITROGEN SUPPLY Valves. PRESS REGULATOR 07- 27FCV-1 11 SIGNAL Pneumatic-CONVERTER 1 27PCV-102B 27PCV-102B NITROEN YES NO NO NO N/A I NO Operated NITROGEN SUPPLY Valves PRESS REGULATOR 07P. 27PCV-120 Pneumatic-27PCV-114 27PCV-114 NITROGEN SUPPLY YES NO NO NO N/A I NO Operated PRESS REGULATOR Valves 19 -27FCV-103A SIGNAL 19- CONVERTER Temperature 27PCV-116A 27PCV-116A NITROGEN SUPPLY YES NO NO NO N/A I NO Sensors PRESS REGULATOR EN-DC-1 68 REV 0 0 A 4,ttachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 31 of 86 I 18-Instrument Racks 27PCV-1 16B 27PCV-116B

!It'LNV-lUS bIUNAL CONVERTER NITROGEN SUPPLY PRESS REGULATOR YES NO NO NO N/A NO DRYWELL PCV AND Pneumatic-INSTR NITROGEN Operated 27PCV-120 27PCV-120 BACKUP SUPPLY YES NO NO NO N/A I NO Operated PRESS CONTROL Valves VALVE 07- 27PCV-122A Pneumatic-27PCV-121A 27PCV-121A POSITIONER YES ,NO NO NO N/A I NO Operated NITROGEN SUPPLY Valves PRESS REGULATOR 07- 27PCV-122B Pneumatic-POSITIONER Operated 27PCV-121B 27PCV-121B NITROGEN SUPPLY YES NO NO NO N/A I NO I OperatedIIRGNSPL Valves PRESS REGULATOR Pu7i- PRESS BUILDING P 27PCV-122A 27PCV-122A COIL A INLET PRESS YES NO NO NO N/A I NO Operated CONTROL VALVE Valves 07 -Put PRESS BUILDING P 27PCV-122B 27PCV-122B COIL B INLET PRESS YES NO NO NO N/A I NO Operated CONTROL VALVE Valves 07 -Pemc 27AOV-131A I 27PCV-124A1 27PCV-124A1 NITROGEN SUPPLY YES NO NO NO N/A I NO Operated PRESS REGULATOR Valves 07 -Pemc 27AOV-132A P 27PCV-124A2 27PCV-124A2 NITROGEN SUPPLY YES NO NO NO N/A I NO Operated PRESS REGULATOR Valves EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 32 of 86 EN-DC-1 68 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 33 of 86 EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 34 of 86 EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 35 of 86 EN-DC-168 REV 0 9 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 36 of 86 EN-DC-1 68 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 37 of 86 EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 38.of 86 U, -1 Pneumatic-Operated Valves 27SV-202 27SV-202 UKYVVWLL IUV ANU INSTR BACKUP SUPPLY SAFETY VALVE YES NO NO NO N/A NO 21 -Tanks CAD A LIQUID 1 and Heat 27TK-7A 27TK-7A NITROGEN AID YES NO YES NO NIA I NO NO X X X Exchangers 21 -Tanks CAD B LIQUID 1 and Heat 27TK-7B 27TK-7B NITROGEN TANK YES NO NO, NO N/A I NO Exchangers 21 -Tanks MST D OUTBD MSIV I and Heat 29AC-1A 29AC-IA MST ACCUTO YES NO YES NO N/A I T NO X ExchagersAIR ACCUMULATOR Exchangers I 21 -Tanks MST A INBD MSIV 1 and Heat 29AC-1B 29AC-1B N2IAIR YES NO YES NO NIA I T NO X Exchangers

-ACCUMULATOR 21 -Tanks MST D INBD MSIV and Heat 29AC-1C 29AC-1C N2/AIR YES NO YES NO N/A I NO X Exchangers ACCUMULATOR 21 -Tanks MST B OUTBD MSIV 1 and Heat 29AC-1D 29AC-1D YES NO YES NO N/A NO X ExchangersAIR ACCUMULATOR 21 -Tanks MST C OUTBD MSIV and Heat 29AC-IE 29AC-1E AIR ACCUMULATOR YES NO YES NO* N/A I NO X Exchangers 21 -Tanks MST B INBD MSIV 1 and Heat 29AC-1F 29AC-1F N2/AIR YES NO YES NO N/A I NO X Exchangers ACCUMULATOR 21 -Tanks MST A OUTBD MSIV 1 and Heat 29AC-1G 29AC-1G AIR ACCUMULATOR YES NO YES NO N/A I NO X Exchangers 21 -Tanks "MST C INBD MSIV 1 and Heat 29AC-1H 29AC-1H N2/AIR YES NO YES NO N/A I NO X Exchangers ACCUMULATOR EN-DC-168 REV 0 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 39 of 86 I Pneumatic-Operated Valves 29AOV-80A 29A0V-80A MST A INBD MAIN STEAM ISOL VALVE NO YES NO YES NIA T NO x 07-Pneumatic-MST B INBD MAIN Operated 29AOV-80B 29AOV-80B STEAM ISOL VALVE YES NO YES NO N/A I NO X Valves 07-Pneumatic-MST C INBD MAIN Operated 29AOV-BOC 29AOV-80C STEAM ISOL VALVE YES NO YES NO N/A I NO x Valves 07-Pneumatic-MST D INBD MAIN Operated 29AOV-80D 29AOV-80D STEAM ISOL VALVE YES NO YES NO N/A I NO X Valves 07 -Pneumatic-MST A OUTBD MAIN YES NO YES NO N/A I T NO X Operated 29AOV-86A 29AOV-6A STEAM ISOL VALVE Valves 07 Pneumatic-MST B OUTBD MAIN 29AOV-86B 29AOV-86B ST B OT MAIN YES NO YES NO N/A I' NO x Operated STEAM ISOL VALVE Valves 07-Pneumatic-MTCOTDMI Peumatec 29AOV-86C 29AOV-86C MST C OUTLD MAIN YES NO YES NO N/A I NO x Operated STEAM ISOL VALVE Valves 07-Pneumatic-29AV-86D MST D INBD MAIN Operated STEAM ISOL VALVE YES NO YES NO N/A I NO Valves 08A -Motor- MST INBD LINE Operated 29MOV-74 29MOV-74 DRAIN INBD ISOL YES NO YES YES N/A I NO X Valves VALVE EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 40 of 86 1 duo-Instrument and Control Panels 33LI-101A 33LI-101A CND STORAGE TK-12A.& B LEVEL INDIC YES NO NO NO N/A NO 21 -Tanks and Heat 33LT-101 33LT-101 SYES NO NO NO N/A NO Exchangers 21 -Tanks CONDENSATE and Heat 33TK-12A 33TK-12A STORAGE TANK A YES NO YES NO N/A I NO X X Exchangers 21 -Tanks CONDENSATE and Heat 33TK-12B 33TK-12B YES NO YES NO N/A I NO X X Exchangers STORAGE TANK B 10 -Air CR/RR VENT 70AHU-1 l 46(70)ESW-101 46(70)ESW-101 3A & 12A ESW YES NO NO NO N/A I NO Handlers SUPPLY ISOL VALVE 10 -Air CR/RR VENT 70AHU-Handlers 46(70)ESW-102 46(70)ESW-102 3B & 12B ESW YES NO NO NO N/A I NO SUPPLY ISOL VALVE 10 -Air CR/RR VENT 70AHU-Handlers 46(70)ESW-103 46(70)ESW-103 3A & 12A ESW YES NO NO NO N/A I NO RETURN ISOL VALVE 10 -Air CRIRR VENT 70AHU-Handlers 46(70)ESW-104 46(70)ESW-104 3B & 12B ESW YES NO NO NO N/A I NO RETURN ISOL VALVE EMERGENCY 08A -Motor-EMRNC Operated 46MOV-1ASERVICE WATER YES NO YES NO NIA I NO ,NO X Valves LOOP A SUPPLY HEADER ISOL VALVE EMERGENCY 08A -Motor-EMRNC Operated 46MMoto 01- 46M0V-101B SERVICE WATER YES NO YES NO N/A I 1 Operated 46MsV-101B LOOP B SUPPLY NO Valves HEADER ISOL VALVE EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 41 of 86 EN-DC-1 68 REV 0 0 0 Attachment B Engineering Report No.-JAF-RPT-12-00015 Rev. 0 Page 42 of 86 U, -I rllu.l~l7 66TCV-107E 66TCV-107E ESCE II %.aoKýOc I AREA UC-22E SWS INLET TEMP CONTROL VALVE YES NO YES NO NIA NO NO x x x Valves 10 -Air WEST CRESCENT Handlers 6UC-22A 6UC-22A AREA UNIT COOLER YES NO YES NO N/A I NO NO X X x 22A 10 -Air EAST CRESCENT Handlers 66UC-22B 66UC-22B AREA UNIT COOLER YES NO YES NO NIA I NO NO X X X 22B 10 -Air WEST CRESCENT Handlers 66UC-22C 66UC-22C AREA UNIT COOLER YES NO YES NO IN/A I NO X X X 22C 10 -Air EAST CRESCENT 1 Handler 66UC-22D 66UC-22D AREA UNIT COOLER YES NO YES NO N/A I NO X X X 22D 10 -Air WEST CRESCENT 1 66UC-22E 66UC-22E AREA UNIT COOLER YES NO YES NO N/A I NO X X x Handlers 22E 10 -Air EAST CRESCENT 1 66UC-22F 66UC-22F AREA UNIT COOLER YES NO YES NO N/A I NO X X X Handlers 22F 10-Air WEST CRESCENT Handlers 66UC-22G 66UC-22G AREA UNIT COOLER YES NO YES NO N/A I NO X x x 22G 10- Air EAST CRESCENT 1 Handlers 66UC-22H 66UC-22H AREA UNIT COOLER -YES NO YES NO N/A I NO X x x 22H 10-Air WEST CRESCENT 1Handlers 66UC-22J 66UC-22J AREA UNIT COOLER YES NO YES NO N/A I NO X x X 22J 10 -Air 66UC-22K 66UC-22K HPCI ROOM UNIT YES NO YES NO N/A I NO X X X Handlers COOLER 22K EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 43 of 86 WEST CABLE 1 10- Air 67E-11 Handlers I 57E-11 TUNNEL VENT SUPPLY COOLING COIL YES NO, NO NO I N/AI NO 10-Air EAST CABLE TUNNEL 1 airs 67E-14 67E-14 VENT SUPPLY YES NO NO NO N/A I NO COOLING COIL 10 -Air WEST ELECTRIC BAY 1 67MOD-16A1 67MOD-16A1 UC-16A DISCH ISOL YES NO NO NO N/A I NO Handlers DAMPER 10 -Air WEST ELECTRIC BAY 1 67MOD-16A2 67MOD-16A2 UC-16A DISCH ISOL YES NO NO NO N/A I NO Handlers DAMPER 10 -Air EAST ELECTRIC BAY 1 67MOD-16B1 67MOD-16BI UC-16B DISCH ISOL YES NO NO NO N/A I NO Handlers DAMPER 10- Air EAST ELECTRIC BAY 1 Hander 67MOD-16B2 67MOD-16B2 UC-16B DISCH ISOL YES NO NO NO N/A I NO Handlers DME DAMPER ELECTRIC BAY UC-10-Air 16A & B SERVICE 1 Handlers 67PCV-101 67PCV-101 WATER RETURN YES NO NO NO N/A I NO PRESS CONTROL VALVE 10- Air 67UC16A 67UC16A WEST ELECTRIC BAY YES NO NO NO N/A I NO Handlers UNIT COOLER 1 1-Air 67UC-16B 67UC-16B EAST ELECTRIC BAY YES NO NO NO N/A I NO Handlers UNIT COOLER 10 -Air RELAY ROOM VENT 1 70AHU-12A 70AHU-1 AIR HANDLING UNIT YES NO NO NO N/A I NO Handlers ANTCOE A RELAY ROOM VENT 10 -Air 70AHU-12B 70AHU-12B AIR HANDLING UNIT YES NO NO NO N/A I NO Handlers B EN-DC-168 REV 0 S Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 44 of 86 LM-ILLt-K IUUM 10-Air 1 1 70AHU-19A Handlers 70AHU-19A VENT AIR HANDLING I YES NO NO NO IN/A I I NO UNIT A 10-Air CHILLER ROOM 1Handler 70AHU-19B 70AHU-19B VENT AIR HANDLING YES NO NO NO N/A I NO Handlers UI UNIT B 10 -Air CONTROL ROOM 1 70AHU-3A 70AHU-3A VENT AIR HANDLING YES NO NO NO N/A I NO Handlers UNIT A 10- Air CONTROL ROOM 0Handlers 7AHU-3B 70AHU-3B VENT AIR HANDLING YES NO NO NO N/A I NO UNIT B 10 -Air 7OFD-I1 70FD-1 RELAY ROOM INLET YES NO NO NO N/A NO Handlers VENT FIRE DAMPER 10 -Air SOUTH/NORTH 1 70FD-10 70FD-10 CABLE.ROOMS FIRE YES NO NO NO N/A I NO Handlers DME DAMPER 10 -Air RELAY ROOM VENT 0Handlers 7FD-2 70FD-2 EXHAUST FANS YES NO NO NO N/A I NO INLET FIRE DAMPER 10- Air RELAY ROOM VENT 1 70FD-4 70FD-4 EXHAUSTFIRE YES NO NO NO N/A NO Handlers DAMPER 10 -Air RELAY ROOM VENT 1 Handlers 70FD-5 70FD-5 EXHAUST FIRE YES NO NO NO N/A I NO DAMPER 10 -Air RELAY ROOM VENT 1 70FD-6 70FD-6 SUPPLY FIRE YES NO NO NO N/A I NO Handlers DAMPER 10 -Air -RELAY ROOM VENT 1Handler 70FD-7 70FD-7 EXHAUST FIRE YES NO NO NO N/A I NO Handlers DAMPER 1 09 -Fans 70FN-13A 70FN-13A RELAY ROOM VENT YES NO NO NO N/A I NO EXHAUST FAN A EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-O0015 Rev. 0.Page 45 of 86 1 09- Fans 70FN-13B 70FN-13B Kr-LPY UtUM VLN I YES EXHAUST FAN B NO NO NO N/A NO CONTROL ROOM 1 09 -Fans 70FN-4A 70FN-4A VENT EXHAUST FAN YES NO YES NO WA I NO NO X A CONTROL ROOM 1 09 -Fans 70FN-4B 70FN-4B VENT EXHAUST FAN YES NO NO NO N/A I NO -B 10-Air RELAY ROOM VENT 1 ler 70MOD-101A 70MOD-101A AHU-12A OUTLET YES NO NO NO N/A I NO 1 Handlers ISOL DAMPER 10-Air RELAY ROOM VENT 1 air 70MOD-1O1B 70MOD-101B AHU-12B OUTLET YES NO NO NO N/A I NO Handlers ISOL DAMPER RELAY ROOM VENT 10 -Air 70MOD-102A 70MOD-102A EXHAUST FAN 13A YES NO NO NO N/A I NO Handlers OUTLET ISOL DAMPER RELAY ROOM VENT 10 -Air EXHAUST FAN 13B 1 a10-er 70MOD-102B 70MOD-102B EXHAUT FAN YES NO NO NO N/A I NO Handlers OUTLET ISOL DAMPER 10 -Air RELAY ROOM VENT O 70MOD-104A 70MOD-104A RECIRC ISOL YES NO NO NO N/A I NO Handlers DAMPER A 10 -Air RELAY ROOM VENT 1 70MOD-104B 7OMOD-104B RECIRC ISOL YES NO, NO NO N/A I NO Handlers DAMPER B CONTROL ROOM 10 -Air ETAU3" 1 70MOD-106A 7OMOD-106A VENTYES NO NO NO NO Handlers OUTLET ISOL DAMPER EN-DC-168 REV 0 A Attachment B 0 Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 46 of 86 I 10 -Air Handlers 70MOD-106B 70MOD-106B UUN I KUL ROUM VENT AHU-3B OUTLETISOL DAMPER YES NO NO NO N/A NO CONTROL ROOM 10-Air 70MOD-108A 70MOD-108A VENT EXHAUST FAN YES NO NO NO N/A I NO Handlers 4A OUTLET ISOL DAMPER CONTROL ROOM 10-Air 70MOD-108B 70MOD-108B VENT EXHAUST FAN YES NO NO NO N/A I NO Handlers 4B OUTLET ISOL DAMPER 10 -Air CONTROL ROOM 1 70MOD-110A 70MOD-110A VENT RECIRC ISOL YES NO NO NO N/A I NO Handlers DAMPER A 10 -Air CONTROL ROOM 1 70MOD-110B 70MOD-1IOB VENT RECIRC ISOL YES NO NO NO N/A I NO Handlers DAMPER B 07- CR/RR CHILLER Pneumatic-70PCV-100A1 70PCV-100A1 CONDENSER A SWS YES NO NO NO N/A I NO Operated PRESS CONTROL Valves VALVE 1 07- CR/RR CHILLER 0Pneumatic-7PCV-10OA2 70PCV-10OA2 CONDENSER B SWS YES NO NO NO N/A I NO Operated PRESS CONTROL Valves VALVE 2 07- CR/RR CHILLER Pneumatic-70PCV-100B1 70PCV-100B1 CONDENSER A SWS YES NO NO NO N/A I NO Operated PRESS CONTROL Valves VALVE 1 07- CR/RR CHILLER Pneumatic-70PCV-100B2 70PCV-10OB2 CONDENSER B SWS YES NO NO NO N/A I NO Operated PRESS CONTROL Valves VALVE 2 EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 47 of 86 1 D7 -Pneumatic-Operated Valves 70RV-101A 70RV-101A CR/RR CHILLER A CONDENSER SERVICE WATER RELIEF VALVE YES NO NO NO N/A NO 07- CRIRR CHILLER B Pumatic- 70RV-101B 70RV-101B CONDENSER YES NO NO NO N/A NO Operated SERVICE WATER Valves RELIEF VALVE 1D7RWC- CONTROL ROOM 1 Chillers 70RWC-2A(CND)

D) CHILLER A YES NO YES YES N/A I NO NO X"A(D CONDENSER 7CR WC- CONTROL ROOM 11 -hilles 7ORC-2B0ND WCN 1Chillers 70RWC-2B(CND) 2B(CND) CHILLER B YES NO NO NO N/ANO CONDENSER 07- CR/RR CHILLER Pneumatic-ROOM AHU-19A Opeated 70TCV-123A 70TCV-123A CHILLED WATER YES NO NO NO N/A I NO Operated OUTLET TEMP Vves CONTROL VALVE CR/RR CHILLER Pneumatic-ROOM AHU-19B 70TCV-123B 70TCV-123B CHILLED WATER YES NO NO NO N/A I NO Oeatved OUTLET TEMP Ve CONTROL VALVE 03- Medium 4160V SWITCHGEAR Vo 71-10502 71-10502 DISTRIBUTION (BUS YES NO YES NO N/A T NO X X x Metal-Clad 10500)Switchgear 03- Medium EMERG DIESEL Voltage, 71-10512 71-10512 GENERATOR C FEED YES NO YES NO N/A I NO X X X Metal-Clad TO EMERG 4KV BUS Switchgear 10500 03-Medium 4160V SWITCHGEAR Voltage, 71-10514 71-10514 DISTRIBUTION (BUS YES NO YES NO N/A I NO X X x Metal-Clad10500)

Switchgear1 EN-DC-168 REV 0 Attachment B.Engineering Report No. JAF-RPT-12-O0015 Rev. 0 Page 48 of 86 EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 49 of 86 1 UZ -LOW Voltage Switchgear and Breaker Panels 71-12602 71-12602 600V EMERG BUS 12600 FEED BREAKER YES NO YES NO I N/A NO X X IX/14-Distribution RELAY ROOM Panels and EEGNYAE Patna 71ACAaA2 ACA2 EMERGENCY PANEL YES NO YES NO N/A I NO X X X Automatic DISTRIBUTION Transfer PANEL Switches 14- DISTRIBUTION Distribution PANEL 71ACA4 Panelsand 71ACA4 71ACA4 EMERGENCY YES NO YES NO N/A I NO X X X Automatic CONTROL & INST Transfer Switches POWER A 114- DISTRIBUTION Distribution PANEL7IACB4 Panels and. 71ACB4 71ACB4 EMERGENCY YES NO YES NO NIA I NO NO X X X Automatic CONTROL & INST Transfer POWERB Switches 14-Distribution RELAY ROOM Panels and 71ACUPS 71ACUPS UNINTERRUPTABLE NO NO YES NO NIA I NO NO X X X Automatic BUS DISTRIBUTION Transfer PANEL Switches 15 -Battery 71BAT-3A 71BAT-A LPCI INVERTER YES NO YES NO NWA I NO NO X X X Racks BATTERY 15 -Battery 71BAT-3B 71 BAT-3B LPCI INVERTER YES NO YES NO N/A I NO X X X Racks BATTERY EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 50 of 86 EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 51 of 86 EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 52 of 86 EN-DC-168 REV 0 e Attachment B 0 Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 53 of 86 I 03 -Medium Voltage, Metal-Clad Switchgear 71H05 71H05 4160VSWITCHGEAR DISTRIBUTION (BUS 10500)YES NO NO NO N/A NO 03 -Medium 4160V SWITCHGEAR Voltage, 71H06 71H06 DISTRIBUTION (BUS YES NO NO NO N/A NO Metal-Clad 160 Switchgear 10600)16 -Battery LPCI MOV INDEP Chargers 71INV-3A 7IlNV-3A POWER SUPPLY A YES NO YES YES N/A I T NO X x and Inverters INVERTER 16 -Battery LPCI MOV INDEP Chargers 71INV-3B 71INV-3B POWER SUPPLY B YES NO NO NO N/A I NO and Inverters INVERTER 02 -Low Voltage 600V SWITCHGEAR Switchgear 711-15 71L15 DISTRIBUTION (BUS YES NO NO NO N/A I NO and Breaker 11500)Panels 02 -Low Voltage 600V SWITCHGEAR Switchgear 71L16 71L16 DISTRIBUTION (BUS YES NO NO NO N/A I NO and Breaker 11600)Panels 02 -Low Voltage 600V SWITCHGEAR Switchgear 71L25 71L25 DISTRIBUTION (BUS YES NO YES NO N/A I NO NO X X and Breaker -12500)Panels 102 -Low Voltage 600V SWITCHGEAR Switchgear 71L26 71L26 DISTRIBUTION (BUS YES NO YES NO NIA I NO NO x X and Breaker 12600)Panels EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 54 of 86 EN-DC-168 REV 0 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 55 of 86 1 ul -Motor Control Centers and Wall-Mounted Contactors 71MCC-162 7`1MCC-162 600V MOTOR CONTROL CENTER (BUS 116200)YES NO NO NO I N/A NO 01 -Motor Control 600V MOTOR Centers and 60 OO W anl 71MCC-163 71MCC-163 CONTROL CENTER YES NO NO NO N/A I NO Mounted (BUS 116300)Contactors 01 -Motor Control 600V MOTOR Centers and 60 OO 71MCC-165 71MCC-165 CONTROL CENTER YES NO NO NO N/A I NO Wall-Mounted (BUS 116500)Contactors 01 -Motor Control Centers and 600V MOTOR 71MCC-166 71MCC-166 CONTROL CENTER YES NO NO NO N/A I NO Watt-Mounted (BUS 116600)Contactors 01 -Motor Control 600V MOTOR Centers and 71MCC-251 71MCC-251 CONTROL CENTER YES NO NO NO N/A I NO Wall-Mounted (BUS 125100)Contactors 01 -Motor Control 600V MOTOR Centersand 71MCC-252 71MCC-252 CONTROL CENTER YES NO YES NO N/A I NO NO X X Wall-Mounted (BUS 125200)Contactors EN-DC-1 68 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 56 of 86 1 UI -oiAor Control Centers and Watt-Mounted Contactors 71MCC-253 71 MCC-253 600V MOTOR CONTROL CENTER (BUS 125300)YES NO NO NO I N/A NO 01 -Motor Control 600V MOTOR Centers and71MCC-254 71MCC-254 CONTROL CENTER YES NO YES NO NIA I NO NO x x Wall-Mounted (BUS 125400)Contactors 01 -Motor Control 600V MOTOR Centers and 71MCC-261 71MCC-261 CONTROL CENTER YES NO NO NO N/A I NO Wall-Mounted (BUS 126100)Contactors 01 -Motor Control 600V MOTOR Centers and 60 OO 71MCC-262 71MCC-262 CONTROL CENTER YES NO YES NO N/A I NO NO x X Wall-Mounted (BUS 126200)Contactors 01 -Motor Control 600V MOTOR Centers and 71MCC-263 71MCC-263 CONTROL CENTER YES NO NO NO NMA I NO Mounted (BUS 126300)Contactors.

01 -Motor Control 600V MOTOR Centers and71 C-6 7MC24 60MOR 71MCC-264C 71MCC-264 CONTROL CENTER YES NO YES NO N/A I NO NO X X Wall-Mounted (BUS 126400)Contactors EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 57 of 86 I 04 -Transformer s 71PT-71ACA2 71PT-71ACA2 DISTRIBUTION TRANSFORMER 71MCC-253-OD3 YES NO YES NO NIA NO NO x 04- EMERGENCY Transformer 71PT-71ACA4 71PT-71ACA4 DISTRIBUTION YES NO YES YES NWA I NO NO X X TRANSFORMER s 71MCC-254-A3A EMERGENCY 04- 71PT-71ACB2 71PT-71ACB2 DISTRIBUTION YES NO NO NO N/A I- NO Transformers TRANSFORMER 71 MCC-263-OE3 EMERGENCY 04- 71PT-71ACB4 71PT-71ACB4 DISTRIBUTION YES NO NO YES N/A I NO Transformers TRANSFORMER 71MCC-264-A3A 04 -UNINTERRUPTIBLE BUS 37.5 KVA NO NO YES NO NIA NO I Transformer 7IPT-71ACUPS 71PT-71ACUPSTRNFME TRANSFORMER N O YS N A IN s 71MCC-252-OD2 SAFEGUARD BUS A 04- DSRBTO s 71PT-71ESSAI 71PT-71ESSAl YES NO NO NO N/A I DT INO Transformers TRANSFORMER 71 MCC-252-OC2 SAFEGUARD BUS B-71PT-71ESSB1 71PT-71ESSB1 DISTRIBUTION 15KVA YES NO NO NO N/A I NO Transformers TRANSFORMER 71 MCC-252-OB3 15- Battery 71 7-1 125 VOLT STATION YES NO YES YES N/A I NO NO X X X X X Racks BATTERY A 15 -Battery 7lSB2 7ISB2 125 VOLT STATION YES NO YES YES N/A I NO NO X X X X X Racks BATTERY B 04- 600V UNIT 71T-13 71T-13 SUBSTATION L15 YES NO NO No N/A I NO TransformersTRANSFORMER EN-DC-168 REV 0 S Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 58 of 86 I 04-Tas e 71T-14 Transformersi 71T-14 600V UNIT SUBSTATION L16 TRANSFORMER YES NO NO NO N/A NO SWITCHGEAR L25 04 -10 041 71T-15 71T-15 100KVAYES NO NO NO N/A NO Transformers TRANSFORMER 71-10560 04- 600V UNIT 71T-16 71T-16 SUBSTATION L26 YES NO NO NO N/A I NO Transformers TRANSFORMER 13 -Motor Generator 71UPS-1(MTR) 71UPS-1(MTR)

YES NO NO NO N/A I NO Generators 72AHU-30A 72AHU-30A BATTERY ROOM A Handlers AIR HANDLING UNIT 10 -Air BATTERY ROOM B 172AHU-30B 72AHU-30B ARHNLGUIT YES NO NO NO IN/A INO Handlers RHADIGUT BATTERY ROOM A 72FD13 72FD13 VENTEXHAUST YES NO NO NO N/A I NO Handlers FANS A & C SUCT FIRE DAMPER BATTERY ROOM B 10 -Air VENT EXHAUST 1 72FD-14 72FD-14 FANS BX&ADST YES NO NO NO N/A I NO Handlers FANS B & D SUCT FIRE DAMPER BATTERY ROOM A 10 -Air VENT EXHAUST I -Air 72FD-3 72FD-3 FANS A & C DISCH YES NO NO NO N/A I NO Handlers FN IC FIRE DAMPER BATTERY ROOM A 10-Air ECIRC FANA 10 -Air 72FD-4 72FD-4 EXHUS FIR YES NO NO NO N/A I NO Handlers EXHAUST FIRE DAMPER EN-DC-168 REV 0 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 59 of 86 EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 60 of 86 1 10-Air ILXI-hyIUUM I Handlers 72MOD-101B 72MOD-101B

ýAHU-30B RECIRC Handlers IISOL DAMPER YES NO NO NO N/A NO 10-Air BATTERY ROOM A 1 72MOD-102A 72MOD-102A RECIRC FAN A DISCH YES NO NO NO N/A I NO ISOL DAMPER 10 -Air BATTERY ROOM B 1 72MOD-102B 72MOD-102B RECIRC FAN B DISCH YES NO NO NO N/A I NO ISOL DAMPER 10 -Air BATTERY ROOM A 1 72MOD-103A 72MOD-103A EXHAUST FAN A YES NO NO NO N/A I NO DISCH ISOL DAMPER 10 -Air BATTERY ROOM B 1 72MOD-103B 72MOD-103B EXHAUST FAN B YES NO NO NO N/A I NO DISCH ISOL DAMPER 10 -Air BATTERY ROOM A Handlers 72MOD-103C 72MOD-103C EXHAUST FAN C YES NO NO NO N/A I NO DISCH ISOL DAMPER 10 -Air BATTERY ROOM B 1 72MOD-103D 72MOD-103D EXHAUST FAN D YES NO NO NO N/A I NO Handlers DISCH ISOL DAMPER 10 -Air 7 BATTERY ROOM A 72MOD-104A 72MOD-104A VENT RECIRC FAN A YES NO NO NO N/A I NO EXHAUST DAMPER 10 -Air MB BATTERY ROOM B Handlers 72MOD-104B 72MOD-104B VENT RECIRC FAN B YES NO NO NO N/A I NO EXHAUST DAMPER 10 -Air ESW/RHRSW PUMP H 73FD-1A 73FD-1A ROOM A FIRE YES NO NO NO N/A I NO Handlers DME DAMPER 10- Air ESW/RHRSW PUMP 73FD-1B 73FD-1B ROOM B FIRE YES NO NO NO N/A I NO Handlers DAMPER EN-DC-168 REV 0 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 61 of 86 I 10- Air Handlers 73FD-1C 73FD-1C C0;VV/l'M'r~n vv I-UMr ROOM B FIRE DAMPER YES NO NO NO N/A NO 10 -Air WEST DIESEL FIRE 1 0ndler 73FD-1D 73FD-1D PUMP ROOM FIRE YES NO NO NO N/A I NO Handlers DAMPER ESWIRHRSW PUMP 09 -Fans 73FN-3A 73FN-3A ROOM EXHAUST FAN YES NO NO NO N/A I NO A ESW/RHRSW PUMP 09 -Fans 73FN-3B 73FN-3B ROOM EXHAUST FAN YES NO NO NO N/A I NO B 10-Air EDG A SWITCHGEAR Handlers 92CD-1 92CD-1 AREA VENT C02 YES NO NO NO N/A I NO ISOL DAMPER 10 -Air EDG B SWITCHGEAR 1 92CD-2 92CD-2 AREA VENT C02 YES NO NO NO N/A I NO Handlers ISOL DAMPER 10 -Air EDG C SWITCHGEAR 1 92CD-3 92CD-3 AREA VENT C02 YES NO NO NO N/A I NO Handlers ISOL DAMPER 10- Air EDG D SWITCHGEAR Handlers 92CD-4 92CD-4 AREA VENT C02 YES NO NO NO N/A I NO ISOL DAMPER EMERG DIESEL GEN 1 10-Air 92FD-01 92FD-01 VENT SUPPLY FANS YES NO NO NO N/A I NO Handlers A &-C FRESH AIR SUCT FIRE DAMPER EMERG DIESEL GEN 10 -Air 92FD-02 92FD-02 VENT SUPPLY FAN A YES NO' NO NO N/A I NO Handlers RECIRC SUCT FIRE DAMPER EMERG DIESEL GEN 1 0ndler 92FD-03 92FD-03 VENT SUPPLY FAN A YES NO NO NO N/A I NO Handlers DISCH FIRE DAMPER EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 62 of 86 I 10 -Air Handlers I 92FD-04 EMERG DIESEL GEN VENT SUPPLY FAN C RECIRC SUCT FIRE YES NO NO NO N/A NO DAMPER 10 -Air EMERG DIESEL GEN Handlers 92F0-05 92FD-05 VENT SUPPLY FAN C YES NO NO NO N/A I NO DISCH FIRE DAMPER 10- Air EMERG DIESEL GEN 12FD-06 92FD-06 VENT SUPPLY FAN B YES NO NO NO N/A I NO Handlers DISCH FIRE DAMPER EMERG DIESEL GEN 10 -AirVETSPLFAB 1 HAr 92FD-07 92FD-07 VENT SUPPLY FAN B YES NO NO NO N/A I NO Handlers RECIRC SUCT FIRE DAMPER 10 -Air EMERG DIESEL GEN 1 0ndler 92FD-08 92FD-08 VENT SUPPLY FAN D YES NO NO NO N/A I NO Handlers DISCH FIRE DAMPER EMERG DIESEL GEN 10-Air 92FD-09 92FD-09 VENT SUPPLY FAND YES NO NO NO N/A I NO Handlers RECIRC SUCT FIRE DAMPER EMERG DIESEL GEN 10 -Air 9VFD10 92FD10 VENT SUPPLY FANS YES NO NO NO N/A NO Handlers B & D FRESH AIR " SUCT FIRE DAMPER 1 09 -Fans 92FN-IA 92FN-IA EMERG DIESEL GEN YES NO YES NO N/A I NO NO X x x X A VENT SUPPLY FAN EMERG DIESEL GEN 1 09 -Fans 92FN-1A. 92FN-1A B VENT SUPPLY FAN YES NO NO NO N/A INNO EMERG DIESEL GEN 1 09- Fans 92FN-1C 92FN-1C C VEN SUL FAN YES NO NO NO N/A I NO C VENT SUPPLY FAN 1 09- Fans 92FN-ID 92FN-1D EMERG DIESEL GEN YES NO NO NO N/A I NO D VENT SUPPLY FAN EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-O0015 Rev. 0 Page 63 of 86 1 LU°-Instrument and Control Panels 92HV-9A 92HV-9A-UU V:N I A-& U HEATINGNENT LOCAL CONTROL PANEL YES NO NO NO N/A NO N 20- EDG VENT B & D Instrument HEATINGNENT I 92HV-9B 92HV-9B LOAL CONT YES NO NO NO N/A I NO and Control LOCAL CONTROL Panels PANEL 10- Air MDEMERG DIESEL GEN 92MOD-143A 92MOD-143A A VENT EXHAUST YES NO NO NO N/A I NO Handlers ISOL DAMPER 10 -Air EMERG DIESEL GEN H 92MOD-143B 92MOD-143B B VENT EXHAUST YES NO NO NO N/A I NO ISOL DAMPER 10 -Air EMERG DIESEL GEN 1 92MOD-143C 92MOD-143C C VENT EXHAUST YES NO NO NO N/A I NO ISOL DAMPER 10 -Air EMERG DIESEL GEN H 92MOD-143D 92MOD-143D D VENT EXHAUST YES NO NO NO N/A I NO Hlandlers ISOL DAMPER EMERG DIESEL GEN 10 -AirVETSPLFAA 1 92MOD-148A 92MOD-148A VENT SUPPLY FAN A YES NO NO NO N/A I NO Handlers RECIRC SUCT ISOL DAMPER EMERG DIESEL GEN I10 -Air VENT SUPPLY FAN B 1 92MOD-148B 92MOD-148B YES NO NO NO N/A I NO Handlers RECIRC SUCT ISOL DAMPER EMERG DIESEL GEN 10 -Air VENT SUPPLY FAN C 92MOD-148C 92MOD-148C VENT SUCT FAN YES NO NO NO N/A I NO RECIRC SUCT ISOL DAMPER EN-DC-168 REV 0 0 A Attachment B 0 Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 64 of 86 I 10 -Air Handlers 92MOD-148D 92MOD-148D EMERG DIESEL GEN VENT SUPPLY FAN D RECIRC SUCT ISOL DAMPER -YES NO NO NO N/A NO EMERG DIESEL GEN 10-Air 92MOD-149A 92MOD-149A VENT SUPPLY FANA YES NO NO NO N/A I NO Handlers FRESH AIR SUCT]SOL DAMPER EMERG DIESEL GEN 10 -Air 2O.4B VENT SUPPLY FAN B Handlers 92MOD-149B 92MOD-149B VENT SUP F YES NO NO NO N/A I NO ISOL DAMPER EMERG DIESEL GEN 10-Air 92MOD-149C VENT SUPPLY FAN C YES NO NO NO N/A I NO Handlers FRESH AIR SUCT ISOL DAMPER EMERG DIESEL GEN 10-Air 92MOD-149D 92MOD-149D VENT SUPPLY FAND YES NO NO NO N/A I NO Handlers FRESH AIR SUCT ISOL DAMPER EMERG DIESEL GEN 10 -Air VENT SUPPLY FANS 92MOD-150A 92MOD-150A A & C FRESH AIR YES NO NO NO N/A I NO WEST SUPPLY ISOL DAMPER EMERG DIESEL GEN 10 -Air VENT SUPPLY FANS Handler 92MOD-150B 92MOD-150B B & D FRESH AIR YES NO NO NO I NO Handlers WEST SUPPLY ISOL DAMPER EMERG DIESEL GEN 10-Air VENT SUPPLY FANS Handlers 92MOD-150C 92MOD-150C A & C FRESH AIR YES NO NO NO N/A I NO Handlers EAST SUPPLY [SOL.DAMPER EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 65 of 86 1 10 -Air Handlers 92MOD-150D 92MOD-150D IhMt-RU LIJ1:Z:L Ut1"N VENT SUPPLY FANS B & D FRESH AIR EAST SUPPLY ISOL DAMPER YES NO NO NO N/A NO EMERG DIESEL GEN Temperatur 92RTD-101A 92RTD-IOIA A ROOM SOUTH SIDE YES NO YES NO NIA I NO NO X X X X eRESIST TEMP DETECTOR 19- EMERG DIESEL GEN Temperatur 92RTD-IOIB 92RTD-101B 8YES NO YES NO NIA I NO NO X X X X 1 I Sensors RESIST TEMP DETECTOR EMERG DIESEL GEN 19-C ROOM NORTH Temperature 92RTD-101C 92RTD-101C SIDE RESIST TEMP YES NO NO NO N/A I NO Sensors SD EITTM DETECTOR 19- EMERG DIESEL GEN D ROOM NORTH Temperature 92RTD-101D 92RTD-101D D RESS TE YES NO NO NO N/A I NO SensorsSIDE RESIST TEMP SenorsDETECTOR EMERGENCY DIESEL 12 -AirGEEAOAAI 1 93AC-A1 93AC-Al GENERATOR A AIR NO NO NO NO NIA I NO NO Compressor START COMPRESSOR Al 21 -Tanks EMERGENCY DIESEL and Heat 93AR-Al 93AR-A1 GENERATOR A AIR YES NO YES NO N/A I NO NO X X X X Exchangers START RECEIVER Al 21 -Tanks EMERGENCY DIESEL GENERATOR A AIR and Heat 93AR-A1O 93AR-A0 G YES NO NO NO N/A I NO START RECEIVER Exchangers A10 21 -Tanks EMERGENCY DIESEL and Heat 93AR-A2 93AR-A2 GENERATOR A AIR YES NO NO NO N/A I NO Exchangers START RECEIVER A2 EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 66 of 86 z, -Iank.1 and Heat 93AR-A3 Exchangers 93AR-A3 tMrNlI'NUY UIlL GENERATOR A AIR YES START RECEIVER A3 NO NO NO I N/A NO 21 -Tanks EMERGENCY DIESEL and Heat 93AR-A4 93AR-A4 GENERATOR A AIR YES NO NO NO N/A I NO Exchangers START RECEIVER A4 21 -Tanks EMERGENCY DIESEL and Heat 93AR-A5 93AR-A5 GENERATOR A AIR YES NO NO NO N/A I NO Exchangers START RECEIVER A5 21 -Tanks EMERGENCY DIESEL and Heat 93AR-A6 93AR-A6 GENERATOR A AIR YES NO NO NO N/A I NO Exchangers START RECEIVER A6 21 -Tanks EMERGENCY DIESEL and Heat 93AR-A7 93AR-A7 GENERATOR A AIR YES NO NO NO N/A I NO Exchangers START RECEIVER A7 21 -Tanks EMERGENCY DIESEL and Heat 93AR-A8 93AR-A8 GENERATOR A AIR YES NO NO NO N/A I NO Exchangers START RECEIVER A8 21 -Tanks EMERGENCY DIESEL and Heat 93AR-A9 93AR-A9 GENERATOR A AIR YES NO NO NO N/A I NO Exchangers START RECEIVER A9 21 -Tanks EMERGENCY DIESEL and Heat 93AR-B1 93AR-B1 GENERATOR B AIR YES NO NO NO N/A I NO Exchangers START RECEIVER B1 21 -Tanks EMERGENCY DIESEL GENERATOR B AIR and Heat 93AR-B10 93AR-B1O YES NO NO NO N/A I NO START RECEIVER Exchangers B10 21 -Tanks EMERGENCY DIESEL and Heat 93AR-B2 93AR-B2 GENERATOR B AIR YES NO YES NO N/A I NO NO X X X Exchangers START RECEIVER B2 21 -Tanks EMERGENCY DIESEL and Heat 93AR-B3 93AR-B3 GENERATOR B AIR YES NO NO NO N/A I NO Exchangers START RECEIVER B3 I EN-DC-168 REV 0 S Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0_ Page 67 of 86 I ii -anKs and Heat Exchangers 93AR-B4 93AR-B4-M-KU:NUY GENERATOR B AIR YES START RECEIVER B4 NO NO NO N/A, NO 21 -Tanks EMERGENCY DIESEL 1 and Heat 93AR-B5 93AR-B5 GENERATOR B AIR YES NO NO NO N/A I NO Exchangers START RECEIVER B5 21 -Tanks EMERGENCY DIESEL 1 and Heat 93AR-B6 93AR-B6 GENERATOR B AIR YES NO NO NO N/A I NO Exchangers START RECEIVER 86 21 -Tanks EMERGENCY DIESEL 1 and Heat 93AR-B7 93AR-B7 GENERATOR B AIR YES NO NO NO N/A I NO Exchangers START RECEIVER B7 21 -Tanks EMERGENCY DIESEL 1 and Heat 93AR-B8 93AR-B8 GENERATOR B AIR YES NO NO NO N/A I NO Exchangers START RECEIVER B8 21 -Tanks EMERGENCY DIESEL 1 and Heat 93AR-B9 93AR-B9 GENERATOR B AIR YES NO NO NO N/A I NO Exchangers START RECEIVER B9 21 -Tanks EMERGENCY DIESEL 1 and Heat 93AR-C1 93AR-C1 GENERATOR C AIR YES NO NO NO N/A I NO Exchangers START RECEIVER Cl 21 -Tanks EMERGENCY DIESEL 21 -Tanks ~~~GENERATOR C AIR YS N O N /1 and Heat 93AR-C1O 93AR-C1O YES NO NO NO N/A NO Exchangers START RECEIVER I cdo 21 -Tanks EMERGENCY DIESEL and Heat 93AR-C2 93AR-C2 GENERATOR C AIR YES NO NO NO N/A I NO Exchangers START RECEIVER C2 21 -Tanks EMERGENCY DIESEL and Heat 93AR-C3 93AR-C3 GENERATOR C AIR YES NO NO NO N/A I NO Exchangers START RECEIVER C3 21 -Tanks EMERGENCY DIESEL and Heat 93AR-C4 93AR-C4 GENERATOR C AIR YES NO NO NO N/A INO Exchangers START RECEIVER C4 EN-DC-168 REV 0 S Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 68 of 86 I 21 -Tanks and Heat.Exchangers 93AR-C5 93AR-C5 EMERGENCY DIESEL GENERATOR C AIR START RECEIVER C5 YES NO NO NO I N/A NO 21 -Tanks EMERGENCY DIESEL and Heat 93AR-C6 93AR-C6 GENERATOR C AIR YES NO NO NO N/A I NO Exchangers START RECEIVER C6 21 -Tanks EMERGENCY DIESEL and Heat 93AR-C7 93AR-C7 GENERATOR C AIR YES NO NO NO N/A I NO Exchangers START RECEIVER C7 21 -Tanks EMERGENCY DIESEL and Heat 93AR-C8 93AR-C8 GENERATOR C AIR YES NO NO NO N/A I NO Exchangers START RECEIVER C8 21 -Tanks EMERGENCY DIESEL and Heat 93AR-C9 93AR-C9 GENERATOR C AIR YES NO NO NO N/A I NO Exchangers START RECEIVER C9 21 -Tanks EMERGENCY DIESEL and Heat 93AR-D1 93AR-D1 GENERATOR D AIR YES NO NO NO- N/A I NO Exchangers START RECEIVER Dl 21 -Tanks EMERGENCY DIESEL and Heat 93AR-D1O 93AR-D1O GENERATOR D AIR YES NO NO NO N/A I NO START RECEIVER Exchangers DIO 21 -Tanks EMERGENCY DIESEL 1 and Heat 93AR-D2 93AR-D2 GENERATOR D AIR YES NO NO NO N/A I NO Exchangers START RECEIVER D2 21 -Tanks EMERGENCY DIESEL and Heat 93AR-D3 93AR-D3 GENERATOR D AIR YES NO NO NO N/A I NO Exchangers START RECEIVER D3 21 -Tanks EMERGENCY DIESEL and Heat 93AR-D4 93AR-D4 GENERATOR D AIR YES NO NO NO N/A I NO Exchangers START RECEIVER D4 21 -Tanks EMERGENCY DIESEL and Heat 93AR-D5 93AR-D5 GENERATOR D AIR YES NO NO NO N/A I NO Exchangers START RECEIVER D5 EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 69 of 86 EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 70 of 86 EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 71 of 86 20-Inl~tnalmflntR rmFdIJ:IATrlR I 1 .93EQP-B 193EGP-8 I2 Z 2. I YES NO YES NO NIA NO NO I X X X X X and uontrol Panels CON I R(LPIANEL 20-Instrument 93EGP-C 93EGP-C EDG C GENERATOR YES NO YES NO N/A I NO X X X X X and Control CONTROL PANEL Panels 20-1 Instrument 93EGP-D 93EGP-D EDG D GENERATOR YES NO YES NO N/A I NO X X X X. X and Control CONTROL PANEL Panels 20-It n PEDG A & C FORCED I Indtuontr 93FPAC 93FPAC PARALLELING YES NO YES NO N/A I NO NO X X X X X and Control PANEL Panels 20-Instrument EDG B & D FORCED 1 93FPBD 93FPBD PARALLELINGOPAEL YES NO YES NO N/A I NO X X X X X and Control PARALLELING PANEL Panels 18- EDG A FUEL OIL DAY I Instrument 93LI-102A 93LI-102A TANK 7A LEVEL YES NO YES NO N/A I NO NO X X X X X Racks INDIC I8- EDG B FUEL OIL DAY I Instrument 93LI-102B 93LI-102B TANK 7B LEVEL YES NO YES NO N/A I NO NO X X X X X Racks INDIC 18- EDG C FUEL OIL DAY 1 Instrument 93L1-102C 93L1-102C TANK 7C LEVEL YES NO YES NO N/A I NO X X X X X Racks INDIC 18- EDG D FUEL OIL DAY 1 Instrument 93LI-102D 93LI-102D TANK 7D LEVEL YES NO YES NO N/A I NO X X X X X Racks INDIC 21 -Tanks EMERGENCY DIESEL aInd Heat 93LOE-1A 93LOE-1A GENERATOR A LUBE YES NO YES NO N/A I NO NO X X X X X Exchangers OIL COOLER EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-OOOi5 Rev. 0 Page 72 of 86 I 21 -Tanks and Heat Exchangers 93LOE-IB 93LOE-1IB EMERGENCY DIESEL GENERATOR B LUBE OIL COOLER YES NO YES NO N/A NO NO X X X X X 21 -Tanks EMERGENCY DIESEL 1 and Heat 93LOE-1C 93LOE-1C GENERATOR C LUBE YES NO YES NO N/A I NO X X X X X Exchangers OIL COOLER 21 -Tanks EMERGENCY DIESEL and Heat 93LOE-1D 93LOE-ID GENERATOR D LUBE YES NO YES NO N/A I NO X X X X X Exchangers OIL COOLER 18- EDG A FUEL OIL DAY Instrument 93LT-102A 93LT-102A TANK 7A LEVEL YES NO NO NO N/A I NO Racks XMIT-rER 18 -EDG B FUEL OIL DAY 1 Instrument 93LT:102B 93LT-102B TANK 7B LEVEL YES NO NO NO N/A I NO Racks XMI]-rER 18- EDG C FUEL OIL DAY 1 Instrument 93LT-102C 93LT-102C TANK 7C LEVEL YES NO NO NO N/A I NO Racks XMITrER 18 -EDG D FUEL OIL DAY I Instrument 193LT-102D 93LT-102D TANK 7D LEVEL YES NO NO NO N/A IN Racks XMI17ER '05- EMERGENCY DIESEL GENERATOR A FUEL I Horizontal 93P1-Al 93P1-A1 YES NO YES NONA IO X X Oumps OIL TRANSFER PUMP N Y 05 -EMERGENCY DIESEL 1 Horizontal 93P1-A2 93P1-A2 LENERATOR A FUEL YES NO YES NO N/A I NO X X X Pumps)IL TRANSFER PUMP Pumps 05 -EMERGENCY DIESEL 05-GENERATOR B FUEL YE J NOESN 1 Horizontal 93P1-B1 93P1-B1 OIL TRANSFER PUMP YES NO YES NO N/A I NO X X X Pumps BI EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0-Page 73 of 86 EN-OC-168 REV 0 e Attachment B 0 Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 74 of 86 I 06 -Vertical Pumps 93P-3A 93P-3A EMERGENCY DIESEL A YE TURBOCHARGER LUBE OIL PUMP NO YES NO NIA NO NO X X X EMERGENCY DIESEL 06 -Vertical GENERATOR B Pumps 93P-3BTURBOCHARGER YES NO YES YES N/A I NO NO X X X LUBE OIL PUMP EMERGENCY DIESEL 06 -Vertical 93P-3C 93P-3C GENERATOR C YES NO YES YES N/A I NO X X X Pumps TURBOCHARGER LUBE OIL PUMP EMERGENCY DIESEL 06 -Vertical 93P-3D 93P-3D GENERATOR D YES No YES YES N/A NO X -X X Pumps TURBOCHARGER LUBE OIL PUMP 05- EMERGENCY DIESEL Horizontal 93P-4A 93P-4A GENERATOR A FUEL YES NO YES NO N/A I NO X X X Pumps OIL PUMP 05- EMERGENCY DIESEL Horizontal 93P-4B 93P-4B GENERATOR B FUEL YES NO YES NO N/A I NO X X X Pumps OIL PUMP 05- EMERGENCY DIESEL Horizontal 93P-4C 93P-4C GENERATOR C FUEL YES NO YES NO N/A I NO X X X Pumps OIL PUMP 05 -EMERGENCY DIESEL Horizontal 93P-4D 93P-4D GENERATOR D FUEL YES NO YES NO N/A I NO X X X Pumps OIL PUMP EMERGENCY DIESEL 21 -anksGENERATOR A and Heat 93TK-IA 93TK-IA JETEWATER YES NO YES NO N/A I NO NO X X X Exchangers JACKET WATER ExchagersEXPANSION TANK EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 75 of 86 I 21 -Tanks and Heat Exchangers 93TK-1 B 93TK-1 B rffMKIrL.T ulEOcL GENERATOR B JACKET WATER EXPANSION TANK I YES NO YES NO I NIA NO NO X X X 21 -aEMERGENCY DIESEL 21 -TanksC 1 hand Ieat 93TK-C 93TK-C JACKET WATER YES NO YES NO N/A I NO X X X Exchangers EXPANSION TANK EMERGENCY DIESEL 21 -TanksGERAO0 1 and Heat 93TK-1D 93TK-1D AETEWATER YES NO YES NO N/A I NO X X X ExchagersJACKET WATER Exchangers EXPANSION TANK 21 -Tanks EMERGENCY DIESEL 1 and Heat 93TK-6A 93TK-6A GENERATOR A FUEL YES NO YES NO N/A I NO X X X Exchangers OIL STORAGE TANK 21 -Tanks EMERGENCY DIESEL 1 and Heat 93TK-6B 93TK-6B GENERATOR B FUEL YES NO YES NO N/A I NO X X X Exchangers OIL STORAGE TANK 21 -Tanks EMERGENCY DIESEL 1 and Heat 93TK-6C 93TK-6C GENERATOR C FUEL YES NO YES NO N/A I NO X X X Exchangers OIL STORAGE TANK 21 -Tanks EMERGENCY DIESEL 1 and Heat 93TK-6D 93TK-6D GENERATOR D FUEL YES NO YES NO N/A I NO X X X Exchangers OIL STORAGE TANK 21 -Tanks EMERGENCY DIESEL and Heat 93TK-7A 93TK-7A GENERATOR A FUEL YES NO YES NO N/A I NO NO X X X Exchangers OIL DAY TANK 21 -Tanks EMERGENCY DIESEL and Heat 93TK-7B 93TK-7B GENERATOR B FUEL YES NO YES NO N/A I NO NO X X X Exchangers

-OIL DAY TANK 21 -Tanks EMERGENCY DIESEL and Heat 93TK-7C 93TK-7C GENERATOR C FUEL YES NO YES NO N/A I NO X X X Exchangers OIL DAY TANK EN-DC-1 68 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 76 of 86 1 4 1 -i anKs and Heat Exchangers GENERATOR D FUEL YES 93TK-7D 93TK-7D NO YES NO IN/A NO X X X OIL DAY TANK 2)1 -Tanks EMERGENCY DIESEL 21 -anksGENERATOR A and Heat 93WE-1A 93WE-1A JETEWATER YES NO YES YES N/A I NO X X X ExchagersJACKET WATER Exchangers HEAT EXCHANGER 21 -Tanks EMERGENCY DIESEL 21 -anksGENERATOR B and Heat 93WE-1B 93WE-1B JETEWATER YES NO YES YES N/A I NO X X X ExchagersJACKET WATER Exchangers HEAT EXCHANGER 21 -Tanks EMERGENCY DIESEL and Heat 93WE-IC 93WE-IC GENERATOR C YES NO YES YES N/A I NO NO X X X JACKET WATER Exchangers H~EAT EXCHANGER EMERGENCY DIESEL 21 -Tanks GENERATOR D and Heat 93WE-1D 93WE-1D JACKET WATER YES NO YES YES N/A I NO NO X X X Exchangers HEAT EXCHANGER 18- CORE SPRAY Instrument IR-25-01 IR-25-01 CHANNEL "A" INST YES NO YES NO NIA* I NO NO X Racks RACK 18- REACTOR Instrument IR-25-05 IR-25-05 PROTECTION AND YES NO NO NO N/A I NO Racks NSSS SYSTEM RACK 18- REACTOR Instrument IR-25-06 IR-25-06 PROTECTION AND YES NO NO NO N/A I NO Racks NSSS SYSTEM RACK 18-Instrument IR-25-50 IR-25-50 HPCI INST RACK YES NO NO NO N/A I NO Racks 18- RHR CHANNEL"A' YN Instrument IR-25-59 IR-25-59 INSTYES NO NO NO NA NO Racks EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 77 of 86 I Instrument Racks IR-25-60 R-25-60 LUXt CHANNEL B" INST RACK YES NO NO NO I N/A NO is- RIHIRCHANNEL "B" I Instrument IR-25-62 IR-25-62 INST RACK YES NO YES NO NIA I NO NO X X Racks 08A -Motor- SGT FILTER TRAIN A S Operated 01-125MOV-14A 01-125MOV-14A WNLE ISOLATION YES NO NO NO N/A t NO Valves VALVE 20-1 nstrument 02-3LI-85A 02-3LI-85A REACTOR VESSEL YES NO NO NO N/A I NO and Control LEVEL INDICATION Panels 20-S Instrument 02-3LI-85B (02- 02-3L1-85B (02- DIV I RX WATER YES NO NO NO N/A I NO and Control 3LR-85B) 3LR-85B) LEVEL RECORDER Panels EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 78 of 86 ATTACHMENT

9.4 SEISMIC

WALKDOWN EQUIPMENT LISTS FORM Table 9.4.2 -Seismic Walkdown Equipment List I (SWEL 1)SWEL1#ýQIMN ID DECITC BLDG ýELV ROCM ~TRAIN 'JYSTEM TYP C LA$SS Ei AOM ANC DWG~1-001 01-125MOV-14B SGT FILTER TRAIN B INLE ISOLATION VALVE SG 272 1D B Containment 8A I N N/A 1-011 02RV-71D ADS MAIN STEAM LINE B SAFETY/RELIEF VALVE PC 295 4.5R B Automatic Depressurization 7 IT N N/A 1-012 02RV-71E ADS MAIN STEAM LINE C SAFETY/RELIEF VALVE PC 295 5W C Automatic Depressurization 7 IT N N/A 1-032 03AOV-126(HCU-02-19)

HCU INLET SCRAM AIR OPER VALVE RB 272 5Y Control Rod Drive Injection 7 I,T N N/A 1-033 03AOV-127(HCU-02-19)

HCU OUTLET SCRAM AIR OPER VALVE RB 272 5Y Control Rod Drive Injection 7 I,T N N/A SEWS,11825-FC-1-043 03TK-125(HCU-02-19)

WATER ACCUMULATOR RB 272 5Y Control Rod Drive Injection 0 I,T Y 22 22P 1-044 03TK-.128(HCU-02-19)

NITROGEN ACCUMULATOR RB 272 5Y Control Rod Drive Injection 0 IT Y SEWS, 11825-FC-22P 1.51-272, DSK-9A, 1-5 93DSK-9B, FE-38AB, 1-052 09-3 NUCLEAR STATION MAIN CONTROL BOARD CR 300 1OF Low Pressure Coolant Injection 20 I Y DClulBo F-Calculation JAF-CALC-MISC-00285 1-053 09-32 CHANNEL "A" RHRJRCIC RELAY PANEL RR 285 .9.5F A Low Pressure Coolant Injection 20 I N N/A 1.83-10 (OUTLINE), FE-1-056 09-45 AUTO BLOWDOWN RELAY CABINET RR 285 9.5FG Automatic Depressurization 20 I Y 38AC, Calculation JAF-CALC-MISC-00285 1-065 10AOV-68A RHR A LPCI TESTABLE CHECK VALVE PC 284 5R A Low Pressure Coolant Injection 7 I,T N N/A 1-069 10E-2A RESIDUAL HEAT REMOVAL SYSTEM HEAT EXCHANGER A RB 272 2.5A A Suppression Pool Cooling 21 I Y 4.12-2 (OUTLINE)1-079 1OMOV-12A RHR HEAT EXCH A OUTLET ISOL VALVE RB 272 2A A Suppression Pool Cooling 8A I N N/A 2.28-2 (OUTLINE), 1-119 10P-1A. RHR SERVICE WATER PUMP A SP 255 26B *A Suppression Pool Cooling 6 I,T Y FP-37A (PIPING), FP-37B (PIPING)1-123 1OP-3A RESIDUAL HEAT REMOVAL PUMP A RB 227 3A A Low Pressure Coolant Injection 6 I,T Y 2.11-5 (OUTLINE), FC-20B, FC-20D 1-124 1OP-38 RESIDUAL HEAT REMOVAL PUMP B RB 227 3D B Low Pressure Coolant Injection 6 I,T Y 2.11-5 (OUTLINE)1-137 10S-5A1 RESIDUAL HEAT REMOVAL SERVICE WATER STRAINER SP 255 26 Suppression Pool Cooling I,T N N/A 1-155 11EV-14A SLC A DOUBLE SQUIB ACTIVATED SHEAR EXPLOSIVE VALVE RB 326 6R A Standby liquid Control System 0 I N N/A EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 79 of 86 P7L#E~lýVETI ESCRIPTO LG LV '0 R_ ___IN____________

CLASS___________ANCDW 1-157 11 P-2A STANDBY LIQUID CONTROL A PUMP RB 326 6P A Standby liquid Control System 5 I Y 2.16-i (OUTLINE), IFC-25D, 2.16-lB 1-161 11TK-1 STANDBY LIQUID CONTROL TANK RB 326 6P Standby liquid Control System 21 I Y FC-25D, 3.37-3 1-164 13MOV-15 RCIC STEAM SUPPLY INBD ISOL VALVE PC 291 4R B Steam Condensing Mode of RHR 8A I,T N N/A 1-165 13MOV-16 RCIC TURBINE STEAM SUPPLY OUTBD ISOL VALVE RB 24 3R A Steam Condensing Mode of RHR 8A I,T N N/A_ 1 1825-FC-20D, 1-166 13P-1 RCIC PUMP RB 227.5 3P Steam Condensing Mode of RHR 5 I,T Y 2.12-3 2.12-3 1-169 14MOV-12A CORE SPRAY LOOP A INBD ISOL VALVE RB 300 4.5R A High Pressure Core Spray System 8A I N N/A 1-17 14-1ACOR SPAY UMPPFSK-2343 S~Il 1-171 14P-1A CORE SPRAY PUMP RB 226 4 A High Pressure Core Spray System 5 I Y PFSK-2343 SH2 PFSK-2343 SH2 1-172 16-IRTD-131A TORUS BULK TEMP MONITOR 0 AZIMUTH BAY L X-232 RESIST TEMP DETECTOR EQ SU 227 4P A Suppression Pool Cooling 19 I, Y 7.48-13 1-209 23AOV-53 HPCI TURBINE STEAM SUPPLY DRAIN TRAP T-3 BYPASS VALVE RB 227 iT High Pressure Coolant Injection 7 I,T N N/A 1-210 23E-2 HPCI LUBE OIL COOLER RB 227 IT High Pressure Coolant Injection 21 I,T N 2.03-02 1-213 23HOV-1 HPCI TURBINE STOP VALVE RB 227 iT High Pressure Coolant Injection 7 I,T N N/A 1-217 23LT-202A SUPPRESSION POOL HPCI LOGIC LEVEL XMITTER EQ RB 227 4.5A A High Pressure Coolant Injection 18 I Y 7.31-198 1-219 23MOV-14 HPCI TURBINE STEAM SUPPLY ISOL VALVE -RB 227 iT High Pressure Coolant Injection 8A IT N N/A 1-232 23P-150 HPCI TURBINE AUX LUBE OIL PUMP RB 227 iT High Pressure Coolant Injection 5 I,T Y FC-20A, FC-20D, 2.03-2 1-234 23P-1M HPCI MAIN PUMP RB 227 IT High Pressure Coolant Injection 5 IT Y FC-20B, FC-20D, 1-243 23TK-1 HPCI LUBE OIL SUMP RB 227 IT High Pressure Coolant Injection 21 I,T Y 2.03-02 1-314 27SOV-131A CAD TRAIN A NITROGEN MAKE-UP ISOL VALVE SOLENOID VALVE EQ SU 260 2T A Automatic Depressurzation 8B I,T N N/A 1-319 27SOV-145 CAD DRYWELL INSTR NITROGEN BACKUP SUPPLY ISOL VALVE RB 295 3RT A Automatic Depressurization 8B I N N/A 1-333 27TK-7A CAD A LIQUID NITROGEN TANK CB 271 0.5RP A Automatic Depressurization 21 I- Y FC-22Q, 6.29-25, 6.29-26 1-335 29AC-1A MST D OUTBD MSIV AIR ACCUMULATOR ST 272 6.5T A Containment 21 I,T Y 6.35-39 1-336 29AC-1B MST A INBD MSIV N2/AIR ACCUMULATOR PC 276 5.5T B Containment 21 I,T Y SEWS 1-343 29AOV-80A MST A INBD MAIN STEAM ISOL VALVE PC 276 5.5T A Main Steam Line Isolation Valves 7 I,T N N/A 1-347 29AOV-86A MST A OUTBD MAIN STEAM ISOL VALVE ST 272 6.5T A Main Steam Line Isolation Valves 7 I,T N N/A 1-360 46MOV-101A EMERGENCY SERVICE WATER LOOP A SUPPLY HEADER ISOL VALVE SP 255 268 A Equipment Cooling 8A I N N/A 1-364 46P-2A EMERGENCY SERVICE WATER PUMP A SP 255 26B A Equipment Cooling 6 I Y Vendor 71452-D EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-O0015 Rev. 0 Page 80 of 86 14 EQUIPMENTID DEMGSCRIIONC BLDG. P IH H K SP ,ROOM TRA EquEMi TPEn CooS ENVIRONMENT A DWG 1-366 46STR-5A1 EMERG SERVICE WATER PUMP A DISCH SOUTH BASKET STRAINER SP 255 26B A Equipment Cooling 0 I Y 6.60-2 1-367 465TR-5A2 EMERG SERVICE WATER PUMP A DISCH NORTH BASKET STRAINER SP 255 26B A Equipment Cooling 0 IY 6.60-2 1-371 66TCV-107E EAST CRESCENT AREA UC-22E SWS INLET TEMP CONTROL VALVE RB 242 3A A Equipment Cooling 7 I N N/A 1-372 66UC-22A WEST CRESCENT AREA UNIT COOLER 22A RB 242 3D A Equipment Cooling -10 I Y 10.00-113 1-373 66UC-22B EAST CRESCENT AREA UNIT COOLER 22B RB 242 4D B Equipment Cooling 10 I Y 10.00-113 1-406 70FN-4A CONTROL ROOM VENT EXHAUST FAN A AD 300 9.5V A Control Room Cooling 9 I Y SEWS, SFSK-41 1-426. 70RWC-2A(CND)

CONTROL ROOM CHILLER A CONDENSER AD 300 10.5S A Control Room Cooling 11 I Y FC-32C Vender drawing" 1-430 71-10502 4160V SWITCHGEAR DISTRIBUTION (BUS 10500) EG 272 24A1 A Vital Bus Power 3 I Y Vend05a5 0673D0515 1-433 71-10560 4160V SWITCHGEAR DISTRIBUTION (BUS 10500) EG 272 26A1 A Vital Bus Power 3 Vender drawing 0673D0515 vender drawing 1-434 71-10602 4160V SWITCHGEAR DISTRIBUTION (BUS 10600) EG 272 26A1 B Vital Bus Power 3Y v0673D0516

.1-436 71-10614 4160V SWITCHGEAR DISTRIBUTION (BUS 10600) EG 272 26A1 B Vital Bus Power 3y vender drawing 0673D0517 1-437 71-10660 4160V SWITCHGEAR DISTRIBUTION (BUS 10600) EG 272 26A1 B Vital Bus Power 3 I vender drawing I I 0673D0518 1-438 71-11502 600V SWITCHGEAR DISTRIBUTION (BUS 11500) BKR 02 RB 300 2R Vital Bus Power 2 1,T Y DSK-71S 1-439 71-11602 600V SWITCHGEAR DISTRIBUTION (BUS 11600) BKR 02 RB 300 6R B Vital Bus Power 2 I Y DSK-71S 1-444 71ACB4 DISTRIBUTION PANEL 71ACB4 EMERGENCY CONTROL & INST POWER B EG 272 26A B Vital Bus Power 14 I Y SEWS 1-445 71ACUPS RELAY ROOM UNINTERRUPTABLE BUS DISTRIBUTION PANEL RR 284.8 11F Vital Bus Power 14 I Y SEWS 1-446 71BAT-3A LPCI INVERTER BATTERY RB 344.6 5.5 A Vital Bus Power 15 I Y SEWS 1-448 71BC-1A 125 VDC STATION BATTERY CHARGER BR 272 12.5E A Vital Bus Power 16 I Y SEWS 1-450 71BCB-2A BATTERY A CONTROL BOARD BR 272 13C A Vital Bus Power 14 I Y 1.52-11, DSK-71U 1-452 71BMCC-1 RB WEST CRESCENT DC MOTOR CONTROL CENTER RB 242 1R Vital Bus Power 1 I Y FE-38N, 1.43-16 1-456 71BMCC-6 RB DC MOTOR CONTROL CENTER RB 272 8Y Vital Bus Power 1 I Y SEWS 1-457 71DC-A2 DISTRIBUTION PANEL 71DC-A2 DC CONTROL POWER A RR 284.4 10F A Vital Bus Power 14 I Y SEWS 1-462 71DSC-11561 L15 UNIT SUBSTATION TRANSF T-13 HIGH SIDE DISC SW RB 300 2R A Vital Bus Power 3 I,T Y FE-38P, DSK-71S, 1.42-3 1-470 71INV-3A LPCI MOV INDEP POWER SUPPLY A INVERTER RB 344.6 5.5 A Vital Bus Power 16 I Y 1.26-2, 1.26-102 1-474 71L25 600V SWITCHGEAR DISTRIBUTION (BUS 12500) EB 272 18.5AI Vital Bus Power 2 I N N/A 1-475 71L26 600V SWITCHGEAR DISTRIBUTION (BUS 12600) EB 272 18.5B Vital Bus Power 2 I Y SEWS EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 81 of 86 SWELI# EQUIPMENTm ID DECRIPTION BIDGQ.IELEV.

ROOM I TRAN ISYSTEM TYP CLSSJNVIRQMMENT I AC DWG 1-481 71MCC-161 600V MOTOR CONTROL CENTER (BUS 116100) RB 272 1.5W Vital Bus Power 1 I N N/A 1-487 71MCC-252 600V MOTOR CONTROL CENTER (BUS 125200) EB 272 18A Vital Bus Power I I N FE-38F, FE-38G, FA-2A, 1.43-87-1-489 71MCC-254 600V MOTOR CONTROL CENTER (BUS 125400) EG 272 23A1 Vital Bus Power 1 1 N FE-38AH, FC-38A, 1.43-96 1-491 71MCC-262 600V MOTOR CONTROL CENTER (BUS 126200) EB 272 18B Vital Bus Power I Y FE-38F, FE-38G, FA-2A, 1.43-88 1-493 71MCC-264 600V MOTOR CONTROL CENTER (BUS 126400) EG 272 25.5A1 Vital Bus Power 1 I y FE-38AH, FC-38A,-1.43-98 1-494 71PT-71ACA2 EMERGENCY DISTRIBUTION TRANSFORMER 71MCC-253-OD3 CS 272 11C A Vital Bus Power 4 I Y SEWS 1-495 71PT-71ACA4 EMERGENCY DISTRIBUTION TRANSFORMER 71MCC-254-A3A EG 272 24A A Vital Bus Power 4 I Y SEWS Stone & Webster 1-498 71PT-71ACUPS UNINTERRUPTIBLE BUS 37.5 KVA TRANSFORMER 71MCC-252-OD2 EB 272 14A Vital Bus Power 4 I Y calculation 12966-S-82-6 1-501 71SB-1 125 VOLT STATION BATTERY A BR 272 14E A Vital Bus Power 15 I Y 1.20-3, 1.20-8 1-502 71SB-2 125 VOLT STATION BATTERY B BR 272 12F B Vital Bus Power 15 I Y 1.20-3,1.20-8 1-508 72AHU-30A

/ BATTERY ROOM A AIR HANDLING UNIT BR 272 12E A Vital Bus Power 10 I N N/A 1-516 72FN-31A BATTERY ROOM A RECIRC FAN BR 282 12E A Vital Bus Power 9 1 Y SEWS 1-518 72FN-46A BATTERY ROOM A EXHAUST FAN BR 282 12E A Vital Bus Power 9 I Y 1.79-474 SEWS 1-519 72FN-46B BATTERY ROOM B EXHAUST FAN BR 282 12F B Vital Bus Power 9 I Y 1.79-474, SEWS 1-522 72HV-7A ADMIN BUILDING VENTILATION CONTROL PANEL BR 272 11.5C A Control Room Cooling 20 I Y 1.79-131 1-555 92FN-1A EMERG DIESEL GEN A VENT SUPPLY FAN EG 272 24A1 A Vital Bus Power 9 I Y 10.00-194 1-577 92RTD-101A EMERG DIESEL GEN A ROOM SOUTH SIDE RESIST TEMP DETECTOR EG 300. 23A2 A Vital Bus Power 19 I N N/A 1-578 92RTD-101B EMERG DIESEL GEN B ROOM SOUTH SIDE RESIST TEMP DETECTOR EG 300 27A2 B Vital Bus Power 19 I N N/A 1-581 93AC-A1 EMERGENCY DIESEL GENERATOR A AIR START COMPRESSOR A1 EG 272 24A2 A Vital Bus Power 12 I Y 1.12-2 1-582 93AR-A1 EMERGENCY DIESEL GENERATOR A AIR START RECEIVER Al EG 272 24A2 A Vital Bus Power 21 I Y 1.12-43 1-594 93AR-B2 EMERGENCY DIESEL GENERATOR B AIR START RECEIVER B2 EG 272 26.5 B Vital Bus Power 21 I Y 11825-1.12-43B 1-624 93ECP-A EDG A ENGINE CONTROL PANEL EG 272 24 A Vital Bus Power 20 I Y 1.12-58.1-625 93ECP-B EDG B ENGINE CONTROL PANEL EG 272 26A3 B Vital Bus Power 20 I Y 1.12-58 1-628 93ECSP-A EDG A ENGINE CONTROL SUB PANEL EG 272 24 A Vital Bus Power 20 I Y 1.12-125 1-629 93ECSP-B EDG B ENGINE CONTROL SUB PANEL EG 272 26A3 B Vital Bus Power 20 I Y 1.12-125 1-634 93EDG-C EMERGENCY DIESEL GENERATOR C EG 272 24A2 A Vital Bus Power 17 i Y 1.12-95 EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 82 of 86 SWEL1# EUPET ID IDESCRPTON 4lG ELEV M TRAI SYSTEM TYPE CLA ~SS ENVIRON4MENT AN DWG~1-635 93EDG-D " EMERGENCY DIESEL GENERATOR D EG 272 26.5 B Vital Bus Power 17 1 Y 1.12-95 1-636 93EGP-A EDG A GENERATOR CONTROL PANEL EG 272 24A1 A Vital Bus Power 20 1 N 1.12-97,1.12-98, SEWS 1-637 93EGP-B EDG B GENERATOR CONTROL PANEL EG 272 26A1 B Vital Bus Power 20 1 y 1.12-97,1.12-98.

SEWS 1-640 93FPAC -EDG A & C FORCED PARALLELING PANEL EG 272 24.5A A Vital Bus Power 20 1 Y 1.12-58 1-642 93LI-102A EDG A FUEL OIL DAY TANK 7A LEVEL INDIC EG 272 23.5A4 A Vital Bus Power 18 I N 1.12.59 1-643 93LI-102B EDG B FUEL OIL DAY TANK 7B LEVEL INDIC EG 272 26A4 B Vital Bus Power 18 I N 1.12.59 1-646 93LOE-1A EMERGENCY DIESEL GENERATOR A LUBE OIL COOLER EG 272 24 A Vital Bus Power 21 I N N/A 1-647 93LOE-1B EMERGENCY DIESEL GENERATOR B LUBE OIL COOLER EG 272 26A3 B Vital Bus Power 21 I N N/A 1-658 93P1-C1 EMERGENCY DIESEL GENERATOR C FUEL OIL TRANSFER PUMP C1 EG 272 24A4 A Vital Bus Power 5 I Y 1.12-99 1-660 93P1-D1 EMERGENCY DIESEL GENERATOR D FUEL OIL TRANSFER PUMP D1 EG 272 26.5A4 B Vital Bus Power 5 I Y FC-38A, 1.12-99 1-662 93P-2A EMERGENCY DIESEL GENERATOR A CIRCULATING LUBE OIL PUMP EG 272 24 A Vital Bus Power 6 I N N/A 1-663 93P-2B EMERGENCY DIESEL GENERATOR B CIRCULATING LUBE OIL PUMP EG 272 26A3 B Vital Bus Power 6 I N N/A 1-670 93P-4A EMERGENCY DIESEL GENERATOR A FUEL OIL PUMP EG 272 24A4 A Vital Bus Power 5 I .N 1.2013 .2 1.12-123,1.12-1-671 93P-4B EMERGENCY DIESEL GENERATOR B FUEL OIL PUMP EG 272 26.5A4 B Vital Bus Power 5 I N 120 1-674 93TK-1A EMERGENCY DIESEL GENERATOR A JACKET WATER EXPANSION TANK EG 272 24A4 A Vital Bus Power 21 I N N/A 1-675 93TK-1B EMERGENCY DIESEL GENERATOR B JACKET WATER EXPANSION TANK EG 272 26A4 B Vital Bus Power 21 I N N/A 1-682 93TK-7A EMERGENCY DIESEL GENERATOR-A FUEL OIL DAY TANK EG 272 24A4 A Vital Bus Power 21 I Y 1.12-128, SEWS 1-683 93TK-7B EMERGENCY DIESEL GENERATOR B FUEL OIL DAY TANK EG 272 26.5A4 B Vital Bus Power 21 I Y 1.12-128, FC-38A, FC-38B 1-686 93WE-1C EMERGENCY DIESEL GENERATOR C JACKET WATER HEAT EXCHANGER EG 272 24A4 C Vital Bus Power 21 I Y 1.12-35,1.12-101 1-687 93WE-1D EMERGENCY DIESEL GENERATOR D JACKET WATER HEAT EXCHANGER EG 272 26.5A4 D Vital Bus Power 21 I N 1.12-35, 1.12-101 1-690 IR-25-01 CORE SPRAY CHANNEL "A" INST RACK RB 242 4A A Low Pressure Coolant Injection 18 I Y 7.70-81D 1-696 IR-25-62 RHR CHANNEL "B" INST RACK RB 242 3D B Low Pressure Coolant Injection 18 I Y 7.70-75, 7.70-76, 1 1 7.70-81 D EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 83 of 86 ATTACHMENT

9.4 SEISMIC

WALKDOWN EQUIPMENT LISTS FORM Table 9.4.3 -Base List 2 (BL 2)B129 QIMENT ID DSRPINBG.

JEEV ROM TRAI YSETP CLS ENVIONEN NIR~2001 19TK-SA FUEL POOL COOLING SKIMMER SURGE TANK A RB 344 4D A Fuel Pool Cooling 21 -Tanks and Heat Exchangers I N 2002 19FPC-32 SKIMMER SURGE TANK A COND MAKE-UP CHECK VALVE RB 369.6 3.5Y A Fuel Pool Cooling 00 -Other I N 2003 19LS-65 SKIMMER SURGE TANK A HIGH LEVEL SWITCH RB 344 4D A Fuel Pool Cooling 20 -Instrument and Control I N Panels 2004 19LS-67 SKIMMER SURGE TANK A LOW-LOW LEVEL SWITCH RB 347 4D A Fuel Pool Cooling 20 -Instrument and Control I N Panels 2005 19FPC-33 SKIMMER SURGE TANKS A & B TO CNDSR HOTWELL ISOL VALVE RB 326.9 3R A&B Fuel Pool Cooling 07 -Pneumatic-Operated Valve I N INLET ISOL 2006 19AOV-09 SKIMMER SURGE TANKS A & B TO CNDSR HOT WELL ISOL VALVE RB 326.9 3R A&B Fuel Pool Cooling 07 -Pneumatic-Operated Valve I N 2007 19FPC-01 SKIMMER SURGE TANKS A & B DRAIN VALVE RB 326 3T A&B Fuel Pool Cooling 07 -Pneumatic-Operated Valve I N 2008 19P-1A FUEL POOL COOLING RECIRC PUMP A RB 326 3T A Fuel Pool Cooling 05 -Horizontal Pumps I N 2009 19E-1A ( FUEL POOL COOLING HEAT EXCHANGER A RB 326 4.5R A Fuel Pool Cooling 21 -Tanks and Heat Exchangers I N 2010 71MCC-131-ODI 19P-IA(M)

FUEL POOL COOLING RECIRC PUMP A MOTOR RB 326.9 3P A Fuel Pool Cooling I -Motor Control Center I N 2011 32P-1A DECAY HEAT REMOVAL SFP WATER PRIMARY PUMP A RB 326 2.5Y A Fuel Pool Cooling 05 -Horizontal Pumps I N 2012 32DHR-5 DECAY HEAT REMOVAL CLG WATER RETURN ISOL VALVE RB 300 1Y A Fuel Pool Cooling 07 -Pneumatic-Operated valve I N 2013 71MCC-120-OEI 32P-1A(M)

DECAY HEAT REMOVAL SFP WATER PRIMARY PUMP A 2g MOTOR YD 293 N/A A Fuel Pool Cooling 05 -Horizontal Pumps N EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 84 of 86 ATTACHMENT

9.4 SEISMIC

WALKDOWN EQUIPMENT LISTS FORM Table 9.4.4 -Rapid Drain-Down List (RDD)JAF does not have qualified RDD components in SFP. The table below is intentionally left blank.RDD4 ~DESRIPTION, BASIS FOR INCLWSION/XCLUSION<

RDD~EN-DC-168 REV 0 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 85 of 86 ATTACHMENT

9.4 SEISMIC

WALKDOWN EQUIPMENT LISTS FORM Table 9.4.5 -Seismic Walkdown Equipment List 2 (SWEL 2).WEL2#. EQUIPMENT ID OEO RDD 2-001 19TK-8A FUEL POOL COOLING SKIMMER SURGE TANK A RB 344 4D A Fuel Pool Cooling 21 -Tanks and Heat Exchangers I N N/A 2-003 19LS-65 SKIMMER SURGE TANK A HIGH LEVEL SWITCH RB 344 4D A Fuel Pool Cooling 20-Instrument and Control Panels I N N/A 2-004 19LS-67 SKIMMER SURGE TANK A LOW-LOW LEVEL SWITCH RB 347 4D A Fuel Pool Cooling 20-Instrument and Control Panels I N N/A 2-005 19FPC-33 SKIMMER SURGE TANKS A & B TO CNDSR HOTWELL ISOL RB 326.9 3R A&B Fuel Pool Cooling 07 -Pneumatic-Operated Valve I N N/A VALVE INLET ISOL 2-006 -19AOV-09 SKIMMER SURGE TANKS A & B TO CNDSR HOT WELL ISOL RB 326.9 3R A&B Fuel Pool Cooling 07- Pneumatic-Operated Valve I N N/A VALVE7 2-007 19FPC-01 SKIMMER SURGE TANKS A & B DRAIN VALVE RB 326 3T A&B Fuel Pool Cooling 07 -Pneumatic-Operated Valve -I N N/A 2-008 19P-1A FUEL POOL COOLING RECIRC PUMP A RB 326 3T A Fuel Pool Cooling 05-Horizontal Pumps I N N/A 2-009 19E-1A FUEL POOL COOLING HEAT EXCHANGER A RB 326 4.5R A Fuel Pool Cooling 21 -Tanks and Heat Exchangers I N N/A 2-010 71MCC-131-OD1 19P-1A(M)

FUEL POOL COOLING RECIRC PUMP A MOTOR RB 326.9 3P A Fuel Pool Cooling 05- Horizontal Pumps I N N/A 2-012 32DHR-18 DECAY HEAT REMOVAL CLG WATER RETURN ISOL VALVE RB 300 lY A Fuel Pool Cooling 07 -Pneumatic-Operated Valve I N N/A 2-01332P1A(M)

DECAY HEAT REMOVAL SFP WATER PRIMARY PUMP YD 293 N/A A Fuel Pool Cooling 01-Motor Control Centers -0 N N/A A MOTOR EN-DC-168 REV 0 Attachment B Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 86 of 86 ATTrACHMENT

9.4 SEISMIC

WALKDOWN EQUIPMENT LISTS FORM Seismic Walkdown Equipment List Approval Prepared by: Rick Casella / , Equipment Selection Personnel Prepared by: Jeff rev Coonev J / ,v v-Equipment Selection Personnel Prepared by: Roger Locv Equipment Selection Perso nnel Reviewed by: Al Porch / L o -Peer Reviewer PIS '#- "/6le2 Concurrence by: Richard Sullivan 4 Operations Personrnel-/

Date: h,/, Date: r 2.Date: I bZOI1-Date: "/ /12 Date: ILI, EN-DC-168 REV 0 Engineering Report No. JAF-RPT-12-00015 Rev. 0 0 Attachment C"Seismic Walkdown Checklists (SWCs)"

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 1 of 573 SWEL #

• I Page_ #1-001 01-125MOV-14B 6 1-011 02RV-71D 10 1-012 02RV-71E 15 1-032 03AOV-126(HCU-02-19) 19 1-033 03AOV-127(HCU-02-19) 23 1-043 03TK-125(HCU-02-19) 27 1-044 03TK-128(HCU-02-19) 31 1-052 09-3 35 1-053 09-32 40 1-056 09-45 45 1-065 10AOV-68A 50 1-069 1OE-2A 54 1-079' 10MOV-12A 58 1-119 1OP-lA 62 1-123 1OP-3A 66 1-124 1OP-3B 70 1-137 1OS-5Al 74 1-155 11EV-14A 78 1-157 11P-2A 82 1-161 11TK-1 87 1-164 13MOV-15 91 1-165 13MOV-16 96 1-166 13P-1 100 1-169 14MOV-12A 105 1-171 14P-lA 109 1-172 16-1RTD-131A 114 1-209 23AOV-53 119 1-210 23E-2 123 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 2 of 573 0 1-213 23HOV-1 127 1-217 23LT-202A 131 1-219 23MOV-14 135 1-232 23P-150 139 1-234 23P-1M 144 1-243 23TK-1 148 1-314 27SOV-131A 153 1-319 27SOV-145 158 1-333 27TK-7A 162 1-335 29AC-1A 166 1-336 29AC-1 B 170 1-343 29AOV-80A 175 1-347 29AOV-86A 180 1-360 46MOV-101A 184 1-364 46P-2A 188 1-366 46STR-5A1 192 1-367 46STR-5A2 196 1-371 66TCV-107E 200 1-372 66UC-22A 204 1-373 66UC-22B 208 1-406 70FN-4A 213 1-426 70RWC-2A(CND) 217 1-430 71-10502 222 1-433 71-10560 227 1-434 71-10602 232 1-436 71-10614 237 1-437 71-10660 241 1-438 71-11502 245 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 3 of 573 1-439 71-11602 250 1-444 71ACB4 255 1-445 71ACUPS 260 1-446 71 BAT-3A 264 1-448 71BC-1A 268 1-450 71BCB-2A 273 1-452 71BMCC-1 278 1-456 71BMCC-6 283 1-457 71DC-A2 288 1-462 7i DSC-1 1561 292 1-470 71 INV-3A 297 1-474 71L25 301 1-475 71L26 305 1-481 71MCC-161 310 1-487 71MCC-252 315 1-489 71MCC-254 319 1-491 71MCC-262 324 1-493 71 MCC-264 328 1-494 71 PT-71ACA2 332 1-495 71 PT-71ACA4 336 1-498 -71PT-71ACUPS 341 1-501 71SB-1 345 1-502 71 SB-2 350 1-508 72AHU-30A 354 1-516 72FN-31A 358 1-518 72FN-46A 363 1-519 72FN-46B 368 1-522 72HV-7A 373 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 4 of 573 1-555 92FN-1A 377 1-577 92RTD-101A 382 1-578 92RTD-101B 386 1-581 93AC-A1 390 1-582 93AR-AI 395 1-594 93AR-B2 400 1-624 93ECP-A 404 1-625 93ECP-B 409 1-628 93ECSP-A 413 1-629 93ECSP-B 418 1-634 93EDG-C 422 1-635 93EDG-D 427 1-636 93EGP-A 432 1-637 93EGP-B 437 1-640 93FPAC 442 1-642 93LI-102A 447 1-643 93LI-102B 451 1-646 93LOE-1A 455 1-647 93LOE-1B 460 1-658 93Pl-Cl 465 1-660 93P1-D1 470 1-662 93P-2A 474 1-663 93P-2B 479 1-670 93P-4A 483 1-671 93P-4B 488 1-674 93TK-1 A 492 1-675 93TK-1 B 497 1-682 93TK-7A 501 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 5 of 573 1-683 93TK-7B 506 1-686 93WE-lC 510 1-687 93WE-1 D 515 1-690 IR-25-01 519 1-696 IR-25-62 523 2-001 19TK-8A 527 2-003 19LS-65 531 2-0 0 4 19LS-67 535 2-005 19FPC-33 539 2-006 1 9AOV-09 543 2-007 19FPC-01 547 2-008 19P-1A 551 2-009 19E-IA 556 2-010 71MCC-131-OD1

• 561 2-012 32DHR-18 566 2-013 71MCC-120-OE1 570 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 6 of 573 0 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet I of 4 Status: Y] NE-] UrI Seismic Walkdown Checklist (SWC) SWEL 1-001 Equipment ID No. 01-125MOV-14B Equip. Class' 8- Motor-Operated Valves Equipment Description SGT Filter Train B Inlet Isolation Valve Location:

Bldg. SG Floor El. 272 Room, Area Col. 1. Line Y Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one Y[] NZ of the 50% of SWEL items requiring such verification)?

The item is an inline valve 0 2. Is the anchorage free of bent, broken, missing or loose hardware?The item is an inline valve 3. Is the anchorage free of corrosion that is more than mild surface oxidation?

The item is an inline valve 4. Is the anchorage free of visible cracks in the concrete near the anchors?The item is an inline valve YEr NEI u- N/AZ YEI NEI uE- N/AZ YEr NEI uE- N/AZ 1 Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 7 of 573 ATrACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: Y[ NO UI-Seismic Walkdown Checklist (SWC) SWEL 1-001 Equipment ID No. 01-125MOV-14B Equip. Class 8- Motor-Operated Valves Equipment Description SGT Filter Train B Inlet Isolation Valve 5. Is the anchorage configuration consistent with plant documentation?

YE- NEI U[E N/A[(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of N[E U[]potentially adverse seismic conditions?

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

The soft targets are free from Impact.8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

Three overhead pipes with unsupported spans of 12'6, which is greater than the suggested span in ANSI B311 Sec 121.1.4.The inline valves and systems are noted below: 39BAS-108:

SBGT Filter Train B Breathing Air Manifold 39SAS-20:

SBGT Filter Train B Service Air Manifold 46SWS-53G2:

RX BLDG 272'EI SGT Room East Service Water In a seismic event, the pipes are likely to fail, based on engineering judgment and the fact that the connections are soldered.

The collapse of copper pipes on the valve (made of steel) will not result in damage to the valve. Hence, this is an industrial safety issue and not an adverse seismic interaction.

Site personnel were notified immediately..

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

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y] NE UEl N/AEl YN NE-' UEi N/AE-YZ NEI UE N/AE YZ N'- UEi Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 8 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 4 Status: YZ Nr-1 U--Seismic Walkdown Checklist (SWC) SWEL 1-001 Equipment ID No. 01-125MOV-14B Equip. Class 8- Motor-Operated Valves Equipment Description SGT Filter Train B Inlet Isolation Valve Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Donald Kobero/ Pouria Pourphobadi Date: 9/25/12 9/25/12 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 9 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: YE ND1 UDýSeismic Walkdown Checklist (SWC) SWEL 1-001 Equipment ID No. 01-125MOV-14B Equip. Class 8- Motor-Operated Valves Equipment Description SGT Filter Train B Inlet Isolation Valve PhotoaraDhs Note: 01-125MOV-14B Valve Note: Unsupported Pipe Spans Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 10 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: Y[ NLI U[:]Seismic Walkdown Checklist (SWC) SWEL 1-011 Equipment ID No. 02RV-71D Equip. Class Pneumatic-operated valves Equipment Description ADS main steam line b safetv/relief valve Location:

Bldg. PC Floor El. 295 Room, Area Drywell, Azimuth 0°, Col. 4.5 Line R Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1: Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

YE- NM 2. Is the anchorage free of bent, broken, missing or loose hardware?The item is an inline valve.YLI NEI ijEl N/AZ 3. Is the anchorage free of corrosion that is more than mild surface oxidation?

The item is an inline valve.4. Is the anchorage free of visible cracks in the concrete near the anchors?The item is an inline valve.YEI NEl UE- N/A[YEI NEl UEr N/A[

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 11 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YZ NEI U-III Seismic Walkdown Checklist (SWC) SWEL 1-011 Equipment ID No. 02RV-71D Equip. Class Pneumatic-operated valves Equipment Description ADS main steam line b safetv/relief valve 5. Is the anchorage configuration consistent with plant documentation?

YE- NEI ULi N/AZ (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y[ NEI UE: N/AE Y[ NEI uE-1 N/AEl YZ NE] uE N/AE: YZ N[ u-Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 12 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ NID U-'Seismic Walkdown Checklist (SWC) SWEL 1-011 Equipment ID No. 02RV-71D Equip. Class Pneumatic-operated valves Equipment Description ADS main steam line b safetv/relief valve Other Adverse Conditions

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

Comments (Additional pages may be added as necessary) 02TE-113D valve temp element off SRV discharge elbow is loose at threaded nipple. CRTJAF-2012-06495 initiated.

This deficiency does not result in any adverse seismic interaction.

ýF- tell Evaluated by: Rick Casella Date: 9-28-12 Alan Porch 9-28-12 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 13 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YE NR UI--Seismic Walkdown Checklist (SWC) SWEL 1-011 Equipment ID No. 02RV-71D Equip. Class Pneumatic-operated valves Equipment Description ADS main steam line b safety/relief valve Photographs IMULu. U,//*Shield Wall:logical 0 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 14 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YZ NR ULI Seismic Walkdown Checklist (SWC) SWEL 1-011 Equipment ID No. 02RV-71D Equip. Class Pneumatic-operated valves Eauipment DescriDtion ADS main steam line b safetv/relief valve 0 Note: Loose temperature element at threaded nipple to branch connection on SRV tailpipe elbow.Note:

Attachment C, Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 15 of 573 ATTACHMENT 9.6, SEISMIC WALKDOWN CHECKLIST FORM Sheet I of 4 Status: YZ NE] UiI Seismic Walkdown Checklist (SWC) SWELl-012 Equipment ID No. 02RV-71E Equip. Class Pneumatic-operated valves Equipment Description ADS main steam line c safety relief valve Location:

Bldg. PC Floor El. 295 Room, Area Drywell, Azimuth 1380. Col 5 Line W Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e.., is the item one of the 50% of SWEL items requiring such verification)?

Y['] NO 2. Is the anchorage free of bent, broken, missing or loose hardware?The item is an inline valve.3. Is the anchorage free of corrosion that is more than,mild surface oxidation?

The item is an infine valve.'4. Is the anchorage free of visible cracks in the concrete near the anchors?The item is an infine valve. -Y-I NEil Ui[] N/A[YE-- NEI- UEI N/AO YEI N[l] ULI N/AN Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 16 of 573 0 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: YZ NE] U-I Seismic Walkdown Checklist (SWC) SWELl-012 Equipment ID No. 02RV-71E Equip. Class Pneumatic-operated valves Equipment Description ADS main steam line c safety relief valve 5. Is the anchorage configuration consistent with plant documentation?

YEI N[-] UI- N/AZ (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Y[-I NEI- UI-potentially adverse seismic conditions?

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

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y[ N[-] U-- N/AD-YO NDI UD- N/AD-Y[ ND-7 U-- N/AD-YE ND:] UM Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 17 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 4 Status: YZ NE] UI-Seismic Walkdown Checklist (SWC) SWELl-012 Equipment ID No. 02RV-71E Equip. Class Pneumatic-operated valves Equipment Description ADS main steam line c safety relief valve Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could YZ ND1 UDI adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

None.P~a OQAg.2&PI:,h hk o Pi,,-

Date: 9-28-12 Alan Porch 9-2842 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 18 of 573 ATrACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: YE NR UI--Seismic Walkdown Checklist (SWC) SWELl-012 Equipment ID No. 02RV-71E Equip. Class Pneumatic-operated valves Equipment Description ADS main steam line c safety relief valve Photographs Note: 02RV-71E, 3-Stage SRV Note: 02RV-71E, 3-Stage SRV Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 19 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 1 of 4 Status: Y[ NEI UE-'Seismic Walkdown Checklist (SWC) SWELl-032 Equipment ID No. 03AOV-126 (HCU Equip. Class' 07-Pnuematic Operated Valve 19)Equipment Description HCU Inlet Scram Air Operated Valve Location:

Bldg. RB Floor El. 272' Room, Area RB East, Col. 5. Line Y Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one Y[-] No of the 50% of SWEL items requiring such verification)?

The evaluated item in this SWC is not part of the 50% of the SWEL items requiring anchorage configuration verification.

2. Is the anchorage free of bent, broken, missing or loose hardware?Bottom of valve is anchored by an angle plate, attached to a skid which supports multiple tanks and other AOV components in the area.3. Is the anchorage free of corrosion that is more than mild surface oxidation?

Anchorage is free of corrosion that is more than mild surface oxidation.

4. Is the anchorage free of visible cracks in the concrete near the anchors?The equipment is anchored to a steel skid.YN NEI UEl N/AE1 YJZ NE UE1 N/AE YE- NE] UEl N/A[I Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 20 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: YZ NE UR Seismic Walkdown Checklist (SWC) SWELl-032 Equipment ID No. 03AOV-126 (HCU Equip. Class 07-Pnuematic Operated Valve.19)Equipment Description HCU Inlet Scram Air Operated Valve 5. Is the anchorage configuration consistent with plant documentation?

YE-- NE] UL N/A[Z (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Item is not one of the 50% for which an anchorage configuration verification is required.6. Based on the above anchorage evaluations, is the anchorage free of YN NE UE potentially adverse seismic conditions?

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

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

There arer no soft targets on the, equipment.

8. Are overhead equipment, distribution systems, ceiling tiles and lighting,.

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

The overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls are not likely to collapse onto the equipment.

9. Do attached lines have adequate flexibility to avoid damage?The lines attached to the SWEL item have adequate flexibility to avoid damage.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Based on the above seismic interaction evaluations, the equipment is free of potentially adverse seismic interaction effects.YE:] NEI UE-I N/AZ YZ NEI UE- N/A YO NE: UE- N/AE-YZ N[: UE Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 21 of 573 0 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 4 Status: Y[ NE] U[-Seismic Walkdown Checklist (SWC) SWELl-032 Equipment ID No. 03AOV-126 (HCU Equip. Class 07-Pnuematic Operated Valve 19)Equipment Description HCU Inlet Scram Air Operated Valve Other Adverse Conditions

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

No other seismic conditions that could adversely affect the safety functions of the equipment in the area were found.Comments (Additional pages may be added as necessary)

No additional comments.Evaluated by: Harpreet Ghuman Date: 09/23/2012 Yaroslav Losev 0923201 0912312012 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 22 of 573 ATrACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: YZ NEI ULI Seismic Walkdown Checklist (SWC) SWELl-032 Equipment ID No. 03AOV-126 (HCU Equip. Class 07-Pnuematic Operated Valve 19)Equipment Description HCU Inlet Scram Air Operated Valve Photographs Note: Picture of equipment 03AOV-126.

Valve 03AOV-126 is on the left.Note:

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 23 of 573 0 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet I of 4 Status: Y] NEI UMI Seismic Walkdown Checklist (SWC) SWELl-033 Equipment ID No. 03AOV-127 (HCU Equip. Class' 07-Pnuematic Operated Valve 19)Equipment Description HCU Outlet Scram Air Operated Valve Location:

Bldg. RB Floor El. 272' Room, Area RB East, Col. 5, Line Y Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

The evaluated item in this SWC is not part of the 50% of the SWEL items requiring anchorage configuration verification.

2. Is the anchorage free of bent, broken, missing or loose hardware?Inline SWEL item, which does not contain anchorage.

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

Inline SWEL item, which does not contain anchorage.

4. Is the anchorage free of visible cracks in the concrete near the anchors?Inline SWEL item, which does not contain anchorage.

Y[-] NO Y[-- NEI U[-] N/A[Y[-] N[:] U-I N/A[YEI NE] U[] N/AO I Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 24 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: YZ NE UI-Seismic Walkdown Checklist (SWC) SWELl-033 Equipment ID No. 03AOV-127 (HCU Equip. Class 07-Pnuematic Operated Valve 19)Equipment Description HCU Outlet Scram Air Operated Valve 5. Is the anchorage configuration consistent with plant documentation?

YE- NE-] UE- N/AZ (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Inline SWEL item, which does not contain anchorage.

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

Inline SWEL item, which does not contain anchorage.

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

There are no soft targets on the equipment.

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

The overhead equipment, distribution systems; ceiling tiles and lighting, and masonry block walls are not likely to collapse onto the equipment.

9. Do attached lines have adequate flexibility to avoid damage?The lines attached to the SWEL item have adequate flexibility to avoid damage.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Based on the above seismic interaction evaluations, the equipment is free of potentially adverse seismic interaction effects.YN NEI UE- N/AE1 YC NE-- U-I N/Alit YN NEI UE1 N/AE-YN N[-] U--

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 25 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 4 Status: YZ NEI U-II Seismic Walkdown Checklist (SWC) SWELl-033 Equipment ID No. 03AOV-127 (HCU Equip. Class 07-Pnuematic Operated Valve 19)Equipment Description HCU Outlet Scram Air Operated Valve Other Adverse Conditions

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

No other seismic conditions that could adversely affect the safety functions of the equipment in the area were found.Comments (Additional pages may be added as necessary)

No additional comments.Evaluated by: Harpreet GhumanIHM

.Yaroslav Losev Date: 09/23/2012 09/23/2012 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 26 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: Y] NEI- U07 Seismic Walkdown Checklist (SWC) SWELl-033 Equipment ID No. 03AOV-127 (HCU Equip. Class 07-Pnuematic Operated Valve 19)Equipment Description HCU Outlet Scram Air Operated Valve Photographs Note: Picture of equipment 03AOV-127(HCU-02-19). 03AOV-127(HCU-02-19) is the valve on the right.Note:

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 27 of 573 0 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet I of 4 Status: YN NE] ULI Seismic Walkdown Checklist (SWC) SWELl-043 Equipment ID No. 03TK-125 (HCU Equip. Class' 21. Tanks and Heat Exchangers.

19)Equipment Description Water Accumulator Location:

Bldg. RB Floor El. 272' Room, Area RB East, Col. 5, Line Y Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YN NE]of the 50% of SWEL items requiring such verification)?

The item is one of the 50% of SWEL items requiring anchorage configuration verification.

2. Is the anchorage free of bent, broken, missing or loose hardware?The four (4), 1/2" shell anchors are free of bent, broken, missing or loose hardware.3.) Is the anchorage free of corrosion that is more than mild surface oxidation?

Anchorage is free of corrosion that is more than mild surface oxidation.

4. Is the anchorage free of visible cracks in the concrete near the anchors?Anchorage is free of visible cracks in the concrete.YEE NE] ur] N/A-]YZ NE] U-] N/A]-YE NErI UE N/A[]1 Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 28 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: YE NR UD Seismic Walkdown Checklist (SWC) SWELl-043 Equipment ID No. 03TK-125 (HCU Equip. Class 21. Tanks and Heat Exchangers.

19)Equipment Description Water Accumulator

5. Is the anchorage configuration consistent with plant documentation?

YE NEi U[-- N/A--(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

The 03TK-125 (HCU-02-19) is mounted to the same steel skid as 03TK-128 (HCU-02-19).

The configuration of the four (4), 1/2" anchors attaching the skid to the embedded steel frame is in accordance with the SEWS for equipment 03TK-125 (HCU-02-19), Rev. 0 and Drawing 11825-FC-22P, Rev. 2.6. Based on the above anchorage evaluations, is the anchorage free of YE NDI UD potentially adverse seismic conditions?

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

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

The soft targets are free from impact by nearby equipment or structures.

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

The overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls are not likely to collapse onto the equipment.

9. Do attached lines have adequate flexibility to avoid damage?The lines attached to the SWEL item have adequate flexibility to avoid damage.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Based on the above seismic interaction evaluations, the equipment is free of potentially adverse seismic interaction effects.YM NDi UD- N/ADJ Y0 NDl UD-7 N/AD-YZ NDI UD- N/AD-7 YN NDI UDý Attachmerit C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 29 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 4 Status: YZ N-] UI Seismic Walkdown Checklist (SWC) SWELI-043 Equipment ID No. 03TK-125 (HCU Equip. Class 21. Tanks and Heat Exchangers.

19)Equipment Description Water Accumulator Other Adverse Conditions

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

No other seismic conditions that could adversely affect the safety functions of the equipment in the area were found.Comments (Additional pages may be added as necessary)

No additional comments.Evaluated by: Harpreet Ghuman kI' -Yaroslav Lose v Date: 09/23/2012 09/23/2012 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 30 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: YZ NEI Ui-Seismic Walkdown Checklist (SWC) SWELl-043 Equipment ID No. 03TK-125 (HCU Equip. Class 21. Tanks and Heat Exchangers.

19)Equipment Description Water Accumulator Photographs 0 Note: Picture of equipment 03TK-125(HCU 19). 03TK-125(HCU-02-19) is on the left.Note:

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 31 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 1 of 4 Status: Y[ NE] UD-Seismic Walkdown Checklist (SWC) SWELl-044 Equipment ID No. 03TK-128 (HCU-02-19)

Equip. Class' 21. Tanks and Heat Exchangers.

Equipment Description Nitrogen Accumulator Location:

Bldg. RB Floor El. 272' Room, Area RB East, Col. 5. Line Y Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of YO NF]the 50% of SWEL items requiring such verification)?

The item is one of the 50% of SWEL items requiring anchorage configuration verification.

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

YO NE:] U[i: N/A[-]The four (4) 1/2" shell anchors are free of bent, broken, missing or loose hardware.3. Is the anchorage free of corrosion that is more than mild surface Y[ N[] U[:] N/A--]oxidation?

Anchorage is free of corrosion that is more than mild surface oxidation.

4. Is the anchorage free of visible cracks in the concrete near the anchors? YN N[] UE] N/AD Anchorage is free of visible cracks in the concrete.1 Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 I Rev. 0 Page 32 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: YE Nil! ULII Seismic Walkdown Checklist (SWC) SWELl-044 Equipment ID No. 03TK-128 (HCU Equip. Class 21. Tanks and Heat Exchangers.

19)Equipment Description Nitrogen Accumulator

5. Is the anchorage configuration consistent with plant documentation?

YO NE! UI- N/A[-](Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

The 03TK-128(HCU-02-19) is mounted to the same steel skid as 03TK-125(HCU-02-19).

The configuration of the four (4), 1/2w anchors attaching the skid to-the embedded steel frame is in accordance with the SEWS for equipment 03TK-125(HCU-02-19), Rev. 0 and Drawing 11825-FC-22P, Rev. 2.6. Based on the above anchorage evaluations, is the anchorage free of YO NEI ULI potentially adverse seismic conditions?

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

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

The soft targets are free from impact by nearby equipment or structures.

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

The overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls are not likely to collapse onto the equipment.

9. Do attached lines have adequate flexibility to avoid damage?The lines attached to the SWEL item have adequate flexibility to avoid damage.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Based on the above seismic interaction evaluations, the equipment is free of potentially adverse seismic interaction effects.YN NEI U[:] N/A-1 YN NE! U[i N/A[Z YE NE!I UE N/AZ-YE N[l UI-Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 33 of 573 S ATTACHMENT 9.6.Sheet 3 of 4 SEISMIC WALKDOWN CHECKLIST FORM Status: YN NEI UF-']Seismic Walkdown Checklist (SWC) SWELl-044 Equipment ID No. 03TK-128 (HCU Equip. Class 21. Tanks and Heat Exchangers.

19)Equipment Description Nitrogen Accumulator Other Adverse Conditions

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

No other seismic conditions that could adversely affect the safety functions of the equipment in the area were found.Comments (Additional pages may be added as necessary)

No additional comments.Evaluated by: Harpreet Ghuman " Yaroslav Losev Date: 09/23/2012 09/23/2012 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 34 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: YE NEI- UFi]Seismic Walkdown Checklist (SWC) SWELl-044 Equipment ID No. 03TK-128 (HCU Equip. Class 21. Tanks and Heat Exchangers.

19)Equipment Description Nitrogen Accumulator Photographs ICU-02-Note: IUIULU. r7ufij(i ui (4UIff!tuF i r UJ I r -O(r 19). 03TK-128(HCU-02-19) is on the left.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 35 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YE- NE- U0 Seismic Walkdown Checklist (SWC) SWELl-052 Equipment ID No. 09-3 Equip. Class, 20-Instruments and control panels Equipment Description Nuclear Station Main Control Board Location:

Bldg. CR Floor El. 300 Room, Area Col 10 Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one Y[ NEI of the 50% of SWEL items requiring such verification)?

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

No visible corrosion, Limited visibility.

4. Is the anchorage free of visible cracks in the concrete near the anchors?No visible cracks. Limited visibility.

Y-I "NE UN N/AE YE NEl UN N/A[--YE- NEI UN N/AF'Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 36 of 573 0 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YE] NE] U[Seismic Walkdown Checklist (SWC) SWELl-052 Equipment ID No. 09-3 Equip. Class 20-Instruments and control panels Equipment Description Nuclear Station Main Control Board 5. Is the anchorage configuration consistent with plant documentation?

Y[-] Nil U[D N/A[l (Note: This question only applies if the item is one of the 50% for which anchorage configuration verification is required.)

Reviewed SEWS for 09-3. Limited view inside the cabinet. Cannot verify anchorage configuration.

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

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

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

Latticed ceiling panels above 09-3 are tie-wrapped, but it was determined not to be an adverse seismic condition.

Lighting is above the ceifing panels.76ELB-CR-300T mounted securely to column FI O, adjacent to panel.9. Do attached lines have adequateflexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment.free of potentially adverse seismic interaction effects?YN NEI U[-- N/AEr YN NEI U[-] N/AE-]YN NE] UE- N/A[--YE'NEI u[

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 37 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YR- NEI] U Seismic Walkdown Checklist (SWC) SWELl-052 Equipment ID No. 09-3 Equip. Class 20-Instruments and control panels Equipment Description Nuclear Station Main Control Board Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

The back cover of the panel was removed but due to limited visibility, verification of the anchorage was not possible.

Visible plug welds appeared satisfactory.

Evaluated by: Rick Casella CQAA2&A. Porch Date: 11/01/2012 11/01/2012 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 38 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: Yr- NEI UN Seismic Walkdown Checklist (SWC) SWELl-052 Equipment ID No. 09-3 Equip. Class 20-Instruments and control panels Equipment Description Nuclear Station Main Control Board Photographs Note: Inside 09-3 Note: Inside 09-3 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 39 of 573 ATTACHMENT

9.6 Sheet

5 of 5 SEISMIC WALKDOWN CHECKLIST FORM Status: YO NEI U[Seismic Walkdown Checklist (SWC) SWELl-052 Equipment ID No. 09-3 Equip. Class 20-Instruments and control panels Equipment Description Nuclear Station Main Control Board Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 40 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 1 of 5 Status: Y[ N- ULI Seismic Walkdown Checklist (SWC) SWELl-053 Equipment ID No. 09-32 Equip. Class, 20 -Instrumentation and Control Panels Equipment Description Channel "A" RHRIRCIC Relay Panel Location:

Bldg. RR Floor El. 284.8 Room, Area Col. 9.5. Line F Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one Y[ NE]of the 50% of SWEL items requiring such verification)?

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

The anchorage is free of corrosion which is more than mild surface corrosion.

4. Is the anchorage free of visible cracks in the concrete near the anchors?Y[ NEI UE] N/A--Y[ NE] UM] N/Ar-YZ NM] ur1 N/A[-]1 Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 41 of 573 0 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YE NIZ U--Seismic Walkdown Checklist (SWC) SWELl-053 Equipment ID No. 09-32 Equip. Class 20- Instrumentation and Control Panels Equipment Description Channel "A" RHR/RCIC Relay Panel 5. Is the anchorage configuration consistent with plant documentation?

Y[ NEI UI-- N/A[:](Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

The anchorage configuration is consistent with SWES for 09-32 (Rev.0). The panels are bolted together and plug welded to embedded steel.09-32 is anchored to embedded steel with six Y" diameter plug welds to embedded steel -3 in the front and 3 in the back.6. Based on the above anchorage evaluations, is the anchorage free of YE ND UD]potentially adverse seismic conditions?

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

The soft targets are free from impact from nearby equipments.

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

The overhead equipments are adequately supported.

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

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

YN -NDI UDI N/AD-YM ND: UD- N/AD: YZ ND- UD- N/AD-YZ. NDI U[D7 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 42 of 573 0 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: Y[ NE] Ur-Seismic Walkdown Checklist (SWC) SWELl-053 Equipment ID No. 09-32 Equip. Class 20- Instrumentation and Control Panels Equipment Description Channel "A" RHRIRCIC Relay Panel Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Donald Koberg Pouria Pourphobadi Date: 9/24/12 9/24/12 Attachment C Engineering Report No. JAF-RPT- 12-00015 Rev. 0 Page 43 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YE NI UMI Seismic Walkdown Checklist (SWC) SWELl-053 Equipment ID No. 09-32 Equip. Class 20 -Instrumentation and Control Panels Equipment Description Channel "A" RHR/RCIC Relay Panel Photouraphs Note: Cabinet 09-32 Note: Cabinet Front Plug Weld Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 44 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YE NEI UEI-]Seismic Walkdown Checklist (SWC) SWELl-053 Equipment ID No. 09-32 Equip. Class 20- Instrumentation and Control Panels Eluipment DescriDtion Channel "A" RHR/RCIC Relav Panel Note: Spot Welds In The Back Of The Panel.Note:

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 45 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet I of 5 Status: YN NEI UD-Seismic Walkdown Checklist (SWC) SWELl-056 Equipment ID No. 09-45 Equip. Class, 20 -Instrumentation and Control Panels Equipment Description Auto Blowdown Relay Cabinet Location:

Bldg. RR Floor El. 284.8 Room, Area Col. 9.5, Line FG Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YM NE-]of the 50% of SWEL items requiring such verification)?

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

Anchorage is free of corrosion that is more than mild surface oxidation.

YM NEI U[E N/AD--YM ND IEU N/AE YZ NEI UE N/ADl 4.Is the anchorage free of visible cracks in the concrete near the anchors?Anchorage is free of visible cracks in the concrete near the anchors.'Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 46 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 5 Status: YE N-1 UD Seismic Walkdown Checklist (SWC) SWELl-056 Equipment ID No. 09-45 Equip. Class 20- Instrumentation and Control Panels Equipment Description Auto Blowdown Relay Cabinet 5. Is the anchorage configuration consistent with plant documentation?

YE NDl UM N/A[--(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

The anchorage configuration is consistent with SWES for 09-45 (Rev.0) and DWG. No. 1.83-10. The panels are bolted together and plug welded to embedded steel. 09-41, 45, 46, which are a total of 84" wide, are anchored by 7 plug welds -three in the front and four in the back.6. Based on the above anchorage evaluations, is the anchorage free of YE ND uD potentially adverse seismic conditions?

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

The soft targets are free from impact by nearby equipments and structures.

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

The overhead equipments and distribution systems are not likely to collapse onto the document.9. Do attached lines have adequate flexibility to avoid damage?The attached lines have adequate flexibility.

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?The equipment is free of potentially adverse seismic interaction effects.YN ND] U[D] N/A[D]YE NDJ UDl N/AD-YN NDI UD N/AD-YO ND-] UD Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 47 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 5 Status: YZ NM UF-Seismic Walkdown Checklist (SWC) SWELl-056 Equipment ID No. 09-45 Equip. Class 20- Instrumentation and Control Panels Equipment Description Auto Blowdown Relay Cabinet: Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Donald KoberM4# d_ _ _ _ _ Date- 9/24/12 Pouria Pourghobadi 9/41 9124112 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 48 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 5 Status: YE NOIl Uil Seismic Walkdown Checklist (SWC) SWELl-056 Equipment ID No. 09-45 Equip. Class 20- Instrumentation and Control Panels Equipment Description Auto Blowdown Relay Cabinet PhotoaraDhs Note: Cabinet 09-45 Note: Cabinet Plug Weld Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 49 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 5 of 5 Status: YE NI UMII Seismic Walkdown Checklist (SWC) SWELl-056 Equipment ID No. 09-45 Equip. Class 20- Instrumentation and Control Panels Equipment Description Auto Blowdown Relay Cabinet Note: Cabinet Plug Weld Note:

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 50 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet I of 4 Status: Y[ NE]" ULI Seismic Walkdown Checklist (SWC) SWELl-065 Equipment ID No. 1OAOV-68A Equip. Class Pneumatic-operated valves Equipment Description RHR A LPCI testable check valve Location:

Bldg. PC Floor El. 279 Room, Area Drywell, Azimuth 00 Col 5 Line R Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments: Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one Y[LI NE of the 50% of SWEL items requiring such verification)?

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

The item is an inline valve.4. Is the anchorage free of visible cracks in the concrete near the anchors?The item is an inline valve.YE] NEI U[:] N/A[YE- NEI U[: N/A[YE[ NE-] UE- N/As Attachment C Engineering Report No. JAF-RPT-12-0)015 Rev. 0 Page 51 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: YE NEi UE--Seismic Walkdown Checklist (SWC) SWELl-065 EquipmentID No. 1OAOV-68A Equip. Class Pneumatic-operated valves Equipment Description RHR A LPCI testable check valve 5. Is the anchorage configuration consistent with plant documentation?

YE NR ULI N/A[(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

The component is an infine valve.Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YN NEi UE- N/AEr YE NEi UEi N/AE1 YN NE UE1 N/AE1 YE NEI UE-Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 52 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 4 Status: YZ NRI UE-Z Seismic Walkdown Checklist (SWC) SWELl-065 Equipment ID No. IOAOV-68A Equip. Class Pneumatic-operated valves Equipment Description RHR A LPCI testable check valve Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

None.P t~~Evaluated by: Rick Casella Date: 9-28-12 Alan Phrr~h 9-28-12 Alan Pnrrh 9-28-12 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 53 of 573 0 ATrACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: YE NR-] UI-Seismic Walkdown Checklist (SWC) SWELl-065 Equipment ID No. 1OAOV-68A Equip. Class Pneumatic-operated valves Equipment Description RHR A LPCI testable check valve Photographs Note: IOAOV-68A (The date provided on the bottom right cornet is not correct the date that the picture was taken. Malfunction with camera setting)Note: IOAOV-68A (The date provided on the bottom right cornet is not correct the date that the picture was taken. Malfunction with camera setting)

Attachment C Engineering ReI5ort No. JAF-RPT-12-00015 Rev. 0 Page 54 of 573 ATTACHMENT

9.6 SEISMIC

WALKOOWN CHECKLIST FORM Sheet I of 4 Status: YE NEl Ui-Seismic Walkdown Checklist (SWC) SWELl-069 Equipment ID No. IOE-2A Equip. Class' 21-Tanks and Heat Exchangers Equipment Description RHR System Heat Exchan-gerA Location:

Bldg. RB Floor El. 272' Room, Area RB RHR Heat Exchange Rm, Col. 2.5, Line A Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YE NE-]of the 50% of SWEL items requiring such verification)?

The item is one of the 50% of SWEL items requiring anchorage configuration verification.

2. Is the anchorage free of bent, broken, missing or loose hardware?The twelve (12), 2" diameter anchors are free of bent, broken, missing or loose hardware.3. Is the anchorage free of corrosion that is more than mild surface oxidation?

Anchorage is free of corrosion that is more than mild surface oxidation.

4. Is the anchorage free of visible cracks in the concrete near the anchors?The equipment is anchored to structural steel members.YZ NE-] u[-] N/A[:]YZ NEI U[-E N/A[-YEr NEI uEr N/A[' Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 55 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: Y[ NE-- U-Seismic Walkdown Checklist (SWC) SWELl-069 Equipment ID No. IOE-2A Equip. Class 21-Tanks and Heat Exchangers Equipment Description RHR System Heat Exchanger A 5. Is the anchorage configuration consistent with plant documentation?

Y[0 NEI UDI N/A[D](Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

The IOE-2A is supported on a~steel ring. It was verified that there are (12), 2" anchors attaching the heat exchanger to the steel ring as stated in the SEWS for equipment IOE-2A, Rev. 0.6. Based on the above anchorage evaluations, is the anchorage free of Y[ Nn UE-I potentially adverse seismic conditions?

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

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

There are no soft targets on the equipment.

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

The overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls are not likely to collapse onto the equipment.

9. Do attached lines have adequate flexibility to avoid damage?The lines attached to the SWEL item have adequate flexibility to avoid damage.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Based on the above seismic interaction evaluations, the equipment is free of potentially adverse seismic interaction effects.YDI ND-- UD- N/AZ Y[ ND] UD- N/AD-YM ND: UD- N/AD-YZ NEI UDý Attachment C Engineering.

Report No. JAF-RPT-12-00015 Rev. 0 Page 56 of 573 0 ATTACHMENT 9.6 .. SEISMIC WALKDOWN CHECKLIST FORM Sheet 3 of 4 Status: YZ NI-- UR Seismic Walkdown Checklist (SWC) SWELl-069 Equipment ID No. IOE-2A Equip. Class 21-Tanks and Heat Exchangers Equipment Description RHR System Heat Exchanger A Other Adverse Conditions

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

No other seismic conditions that could adversely affect the safety functions of the equipment in the area were found.Comments (Additional pages may be added as necessary)

No additional comments.Evaluated by: Harpreet Ghuman k 4 , Yaroslav Losev Date: 09/26/2012 09/26/2012 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 57 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: YE NEI UI--Seismic Walkdown Checklist (SWC) SWELl-069 Equipment ID No. IOE-2A Equip. Class 21-Tanks and Heat Exchangers Equipment Description RHR System Heat Exchanger A Photographs 0 Note: Picture of equipment IOE-2A.Note:

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 58 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet I of 4 Status: Y] NE] UMI Seismic Walkdown Checklist (SWC) SWELl-079 Equipment ID No. 10MOV-12A Equip. Class' 08-Motor Operated Valves Equipment Description RHR Heat Exch. A Outlet lsol Valve Location:

Bldg. RB Floor El. 272' Room, Area RB RHR Heat ExchanQe Rm, Col. 2, Line A Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one of the 50% of SWEL items requiring such verification)?

The evaluated item in this SWC is not part of the 50% of the SWEL items requiring anchorage configuration verification.

2. Is the anchorage free of bent, broken, missing or loose hardware?Inline SWEL item, which does not contain anchorage.

YEi NO Y[--] NEI U-] N/AZ 3. Is the anchorage free of corrosion that is more than mild surface oxidation?

Inline SWEL item, which does not contain anchorage.

4. Is the anchorage free of visible cracks in the concrete near the anchors?Inline SWEL item, which does not contain anchorage.

YE-] NEI UE] N/AZ YEI NEI u[-] N/An I Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 59 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: YZ NE] UD1 Seismic Walkdown Checklist (SWC) SWELl-079 Equipment ID No. 1OMOV-12A Equip. Class 08-Motor Operated Valves Equipment Description RHR Heat Exch. A Outlet Isol Valve 5. Is the anchorage configuration consistent with plant documentation?

Y-I NEI UI-' N/AZ (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

Inline SWEL item, which does not contain anchorage.

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

Inline SWEL item, which does not contain anchorage.

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

There are no soft targets on the equipment.

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

The overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls are not likely to collapse onto the equipment.

9. Do attached lines have adequate flexibility to avoid damage?The lines attached to the SWEL item have adequate flexibility to avoid damage.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Based on the above seismic interaction evaluations, the equipment is free of potentially adverse seismic interaction effects.YEI N[D U'- N/A[YZ NDl UiD N/AD-Y[D NDI U[D- N/AD]Y[D NEI U"]

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 60 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 4 Status: YZ NEI UE Seismic Walkdown Checklist (SWC) SWELl-079 Equipment ID No. 10MOV-12A Equip. Class 08-Motor Operated Valves Equipment Description RHR Heat Exch. A Outlet Isol Valve Other Adverse Conditions

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

No other seismic conditions that could adversely affect the safety functions of the equipment in the area were found.Comments (Additional pages may be added as necessary)

No additional comments.Evaluated by: Harpreet Ghumanb -Date: 09/26/2012 Yaroslav Losev 09/26/2012 0912612012 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 61 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: YE NEI- U--Seismic Walkdown Checklist (SWC) SWELl-079 Equipment ID No. IOMOV-12A Equip. Class 08-Motor Operated Valves Equipment Description RHR Heat Exch. A Outlet Isol Valve Photographs 0 Note: Picture of equipment IOMOV-12A.

Note:

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 62 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet I of 4 Status: YE NE] U'-D Seismic Walkdown Checklist (SWC) SWELl-119 Equipment ID No. lOP-1A Equip. Classi 06-Vertical Pump Equipment Description RHR Service Water Pump A Location:

Bldg. SP Floor El. 255' Room, Area Pump Room Train A, Col. 26, Row B Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one Y[ NrE]of the 50% of SWEL items requiring such verification)?, The item is one of the 50% of SWEL items requiring anchorage configuration verification.

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

YM N[E UE- N/ADl The four (4) 1" CIP bolts are free of bent, broken, missing or loose hardware.3. Is the anchorage free of corrosion that is more than mild surface YE ND: UE1 N/A--oxidation?

Anchorage is free of corrosion that is more than mild surface oxidation.

4. Is the anchorage free of visible cracks in the concrete near the YS ND] Ur- N/AD anchors?There are no visible cracks in the concrete near the anchors.'Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 63 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: YZ NR ULI-]Seismic Walkdown Checklist (SWC) SWELl-119 Equipment ID No. lOP-1A Equip. Class 06-Vertical Pump Equipment Description RHR Service Water Pump A 5. Is the anchorage configuration consistent with plant documentation?

Y[" NE] UI- N/A[I (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

The anchorage configuration for the 1" CIP headed bolts is consistent with the SEWS documentation for equipment lOP-1A, Rev 0.6. Based on the above anchorage evaluations, is the anchorage free of Y[ N[i U[I potentially adverse seismic conditions?

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

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

There are no soft targets on the equipment.

YEI NEI UE- N/A9 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

The overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls are not likely to collapse onto the equipment.

9. Do attached lines have adequate flexibility to avoid damage?The lines attached to the SWEL item have adequate flexibility to avoid damage.10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Based on the above seismic interaction evaluations, the equipment is free of potentially adverse seismic interaction effects.Y[ NE] UE] N/AE]YO NEI UE1 N/AE]

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 64 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 4 Status: Y] NE] U'-I Seismic Walkdown Checklist (SWC) SWELl-119 Equipment ID No. lOP-IA Equip. Class 06-Vertical Pump Equipment Description RHR Service Water Pump A Other Adverse Conditions

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

No other seismic conditions that could adversely affect the safety functions of the equipment in the area were found.Comments (Additional pages may be added as necessary)

No additional comments.Evaluated by: Harpreet Ghumanb) AJl/-YaroslavLosev Date: 09/21/2012 09/21/2012 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 65 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: YZ NR Ur-Seismic Walkdown Checklist (SWC) SWELl-119 Equipment ID No. lOP-1A Equip. Class 06-Vertical Pump Equipment Description RHR Service Water Pump A Photoaraohs Note: I Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 66 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 1 of 4 Status: YZ N[] UMI Seismic Walkdown Checklist (SWC) SWELl-123 Equipment ID No. IOP-3A Equip. Class' 6- Vertical Pumps Equipment Description Residual Heat Removal Pump A Location:

Bldg. RB Floor El.. 227.6 Room, Area Col. 3. Line A Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one YZ N[:]of the 50% of SWEL items requiring such verification)?

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

Anchorage is free of corrosion that is more than mild surface oxidation.

4. Is the anchorage free of visible cracks in the concrete near the anchors?Anchorage is free of visible cracks in the concrete near the anchors.Y[ NO U-IE N/AF1 YZ N[il ULi N/Al]YE N[] UEi N/AlZ 1 Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 67 of 573 0 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: Y[ ND] UD Seismic Walkdown Checklist (SWC) SWELl-123 Equipment ID No. IOP-3A Equip. Class 6- Vertical Pumps Equipment Description Residual Heat Removal Pump A 5. Is the anchorage configuration consistent with plant documentation?

YZ NDi U[-- N/A--(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

The anchorage configuration is consistent with File No. 2.11-5 and the SWES for IOP-3A (Rev. 0). The pump is anchored with sixteen 1.75" CIP bolts.6. Based on the above anchorage evaluations, is the anchorage free of Y[ NDI UD-potentially adverse seismic conditions?

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

There are no soft targets on this item.8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

The overhead equipments and distribution systems are not likely to collapse onto the equipment.

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

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

YI' NDl uD- ,N/As YO NDl U-I N/AD-YE N[l U[i N/AD1 YE N[ U[-]

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 68 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 4 Status: YZ NEI ULI Seismic Walkdown Checklist (SWC) SWELI-123 Equipment ID No. 1OP-3A Equip. Class 6- Vertical Pumps Equipment Description Residual Heat Removal Pump A Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Donald Kober, Pouria Pourghobadi Date: 9/24/12 9/24/12 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 69 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: YE NF-'] Ur-Seismic Walkdown Checklist (SWC) SWELl-123 Equipment ID No. 1OP-3A Equip. Class 6- Vertical Pumps Equipment Description Residual Heat Removal Pump A Photographs Note: Pump IOP-3A Note:

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 70 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet I of 4 Status: YZ NEJ UR Seismic Walkdown Checklist (SWC) SWELl-124 Equipment ID No. IOP-3B Equip. Class' 6- Vertical Pumps Equipment Description Residual Heat Removal Pun"p B Location:

Bldg. RB Floor El. 227 Room, Area Col 3. Line D Manufacturer, Model, Etc. (optional but recommended) instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.Anchorage 1. Is the anchorage configuration verification required (i.e., is the item one Y[ Nn of the 50% of SWEL items requiring such verification)?

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

The anchorage is free of any corrosion.

4. Is the anchorage free of visible cracks in the concrete near the anchors?The anchorage is free of any visible cracks in the concrete.Y[ NEI UE- N/A[l YE NEI uE] N/AE-Y[ NEI U[l N/AE-' Enter the equipment class name from Appendix B: Classes of Equipment.

Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 71 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 2 of 4 Status: Y] NW- UW-Seismic Walkdown Checklist (SWC) SWELl-124 Equipment ID No. IOP-3B Equip. Class 6 -Vertical Pumps Equipment Description Residual Heat Removal Pump B 5. Is the anchorage configuration consistent with plant documentation?

YZ NEI uW- N/AE-(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

The anchorage configuration is consistent with SEWS for 1OP-3B which is identical to IOP-3A and DWG. No. 2.11-5 6. Based on the above anchorage evaluations, is the anchorage free of YZ NO U--potentially adverse seismic conditions?

The anchorage is free of potentially adverse seismic condition.

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

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

The overhead equipment and distribution system are not likely to collapse onto the equipment.

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

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?The equipment is free of potentially adverse seismic interaction effects.YW-] N[W] UW- N/A[YZ NW UW' N/AW Y[ NWI UWl N/AI-Y[ NEI UM Attachmeht C Engiheeling Report No. JAF-RPT-12-00015 Rev. 0 Page 72 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 3 of 4 Status: Y[ NO- UI'Seismic Walkdown Checklist (SWC) SWELl-124 Equipment ID No. IOP-3B Equip. Class 6 -Vertical Pumps Equipment Description Residual Heat Removal Pump B Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Donald Kobercq Date: 9/2/31/12 Pouria Pourqhobadi 9/23/12 Attachment C Engineering Report No. JAF-RPT-12-00015 Rev. 0 Page 73 of 573 ATTACHMENT

9.6 SEISMIC

WALKDOWN CHECKLIST FORM Sheet 4 of 4 Status: YE NR U-Seismic Walkdown Checklist (SWC) SWELl-124 Equipment ID No. IOP-3B Equip. Class 6 -Vertical Pumps Equipment Description Residual Heat Removal Pump B Photographs Note: 1OP-3B Residual Heat Removal Pump Note: S