LR-N14-0024, Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic

Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic

ML14056A345
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Site:	Hope Creek
Issue date:	01/29/2014
From:	Public Service Enterprise Group, Sargent & Lundy
To:	Office of Nuclear Reactor Regulation
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ML14056A365	List: LR-N14-0024, Report SL-011553, Revision 2, Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic ML14056A344
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SL Report No.: SL-01 1553 0 PSEG Rev. No. 2 January 29, 2014 NUCLEAR LLC Page No. vi Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report 6.3.2. ANCHORAGE VERIFICATION ............................................................ 13 6.3.3. POTENTIALLY ADVERSE SEISMIC CONDITIONS .................................... 14

7. LICENSING BASIS EVALUATIONS ................................................................ 16

8. IPEEE VULUNERABILITY RESOLUTION REPORT ...................................... 16

9. PEER REV IEW ............................................................................................ 16 9.1. REVIEW THE SELECTION OF SSCS INCLUDED ON THE SWEL ................ 16 9.2. REVIEW A SAMPLE OF THE CHECKLIST PREPARED FOR THE SEISMIC WALKDOWNS AND AREA WALK-BYS .............................................. 18 9.3. REVIEW THE LICENSING BASIS EVALUATIONS ................................. 19 9.4. REVIEW THE DECISIONS FOR ENTERING THE POTENTIALLY ADVERSE SEISMIC CONDITIONS INTO THE CAP PROCESS ........................................... 19 9.5. REVIEW THE SUBMITTAL REPORT ..................................................... 19

10. REFERENCES ............................................................................................. 20 ATTACHMENTS ATTACHMENT 1A - BASE LIST 1-SCREENING OF HOPE CREEK SEISMIC IPEEE COMPONENTS ATTACHMENT lB - BASE LIST 1-SHUTDOWN COMPONENT LIST (UFSAR TABLE 9A-2)

ATTACHMENT IC - BASE LIST 2-COMPONENTS ASSOCIATED WITH FUEL POOL COOLING ATTACHMENT 2 - -SEISMIC WALKDOWN EQUIPMENT LIST (SWEL)

ATTACHMENT 3 - AREA WALK-BYS CHECKLISTS (AWC) AND SEISMIC WALKDOWN CHECKLISTS (SWC)

ATTACHMENT 4 - -SEISMIC WALKDOWNS ENGINEER CERTIFICATIONS ATTACHMENT 5 - -CHECKLIST FOR PEER REVIEW OF SSC SELECTION ATTACHMENT 6 - WALKDOWNS PERFORMED DURING RFO18 JR2

SL Report No.: SL-011553 0 PSEG Rev. No.

November 21, 2012 1

NUCLEAR LLC Page No. v Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report Hope Creek Nuclear Generating Station Seismic Walkdown Report TABLE OF CONTENTS SECTION PAGE

1. INTRODUCTION ......................................................................................................................... 1

2. PURPOSE/OBJECTIVE ............................................................................................................... 1

3. SEISMIC LICENSING BASIS ................................................................................................. 1 3.1. SE ISM IC DE SIG N .......................................................................................................... I 3.2. SEISMIC CATEGORY I STRUCTURES AND EQUIPMENT .................................... 5 3.3. CODES AND STANDARDS ..................................................................................... 5

4. PERSONNEL QUALIFICATION .......................................................................................... 6

5. SELECTION OF SSCS ................................................................................................................. 8 5.1. METHODOLOGY ............................................................................. 8 5.2. SWEL 1 - SAMPLE OF REQUIRED ITEMS FOR THE FIVE SAFETY F U N C T IO N S ................................................................................................................... 8 5.2.1. SCREEN 1 THROUGH 3 - SEISMIC CATEGORY I, EQUIPMENT OR SYSTEMS, SUPPORT OF THE FIVE SAFETY FUNCTIONS ........................................ 8 5.2.2. SCREEN 4: SAMPLE CONSIDERATIONS ................................................ 9 5.3. SWEL 2 - SPENT FUEL POOL RELATED ITEMS ..................................... 10 5.3.1. SCREEN 1 - SEISMIC CATEGORY I ............................................................ 10 5.3.2. SCREEN 2 - EQUIPMENT OR SYSTEMS ................................................... 10 5.3.3. SCREEN 3 - SAMPLE CONSIDERATIONS ................................................... 11 5.3.4. SCREEN 4: RAPID DRAIN-DOWN ........................................................... 12 5 .4 . SW E L ............................................................................................................................ 12

6. SEISMIC WALKDOWNS AND AREA WALK-BYS ......................................................... 13 6.1. PR E PA RAT ION ............................................................................................................ 13 6.2. AREA WALK-BYS (AWB) AND SEISMIC WALKDOWNS .......................... 13 6.3. RE SU L T S .......................................................................................... 13 6.3.1. SEISMIC WALKDOWNS ................................................................... 13

SL Report No.: SL-01 1553 0PSEG Rev. No. 2 January 29, 2014 NUCLEAR LLC Page No. iv Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report PURPOSE/OBJECTIVE FOR REVISION 2 The purpose of revision 2 is to reflect completion of the Hope Creek Generating Station (HCGS) seismic walkdowns by providing the results of the seismic walkdowns that were performed during HCGS Refueling Outage 18 (RFO 18). The final results of the walkdowns are included in Attachment 6.

LIST OF AFFECTED PAGES FOR REVISION 2 The following pages were affected/revised by Revision 2: Cover Sheet (page i), page iii, page iv, page vi, page 8, pages 12-14, 16, Attachment Index Sheet, Attachment 2 (SWEL), Attachment 3 Area Walk-By Walkdown Checklist (AWB) HC-28 photographs The following pages were inserted by Revision 2: The SWC for component 1YF402 in Attachment 3, NTFF 2.3 Training Certificate for Joshua Hammel in Attachment 4, Attachment 6 R2

SUMMARY

OF REVISION 2 The table of contents and the attachment index sheet were revised to add Attachment 6. The main body of the report is revised to add the qualification and experience of Joshua Hammel and to reduce the total number of components from 104 to 103. The Seismic Walkdown Equipment List (SWEL) (Attachment 2) is revised to include a component substitution and the removal of component SV-3652B, both made during RFOI8. Attachment 3 is revised to show additional photos for AWB HC-28. Attachment 4 is revised to include the walkdown training certificate for Joshua Hammel. Attachment 6 is added to document the walkdowns conducted during RFO18.

RESULTS See Attachment 6 for the results of the walkdowns performed during RFO 18.

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H-ope Creek Nuclear Geneating 8Staio Sciamic Walkdown Repoi't ISSUSLf

SUMMARY

AND APPROVAL PACE This is to cert(iry that Revision 2 to the Seismic Walkdown Report has been prepared, reviewed and approved in accordance with Sargent & I.undy's Standard Operating Proceduie SOP-0405, which is based on ANSi/ISOj/ASSQC Qg001 Quality Management Systems, CONTI.IB15TOIRS)

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SL Report No.: SL-011553 0 PSEG Rev. No. 1 November 21, 2012 NUCLEAR LLC Page No. ii Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown ReportII LEGAL NOTICE This report "Seismic Walkdown Report" was prepared by Sargent & Lundy, L.L.C. ("S&L"), expressly for the sole use of PSEG Nuclear ("PSEG") in accordance with the agreement between S&L and PSEG. This Deliverable was prepared using the degree of skill and care ordinarily exercised by engineers practicing under similar circumstances. PSEG acknowledges: (1) S&L prepared this Deliverable subject to the particular scope limitations, budgetary and time constraints, and business objectives of the PSEG; (2) information and data provided by others may not have been independently verified by S&L; and (3) the information and data contained in this Deliverable are time sensitive and changes in the data, applicable codes, standards, and acceptable engineering practices may invalidate the findings of this Deliverable. Any use or reliance upon this Deliverable by third parties shall be at their sole risk.

o PSEG NUCLEAR LLC PSEG NUCLEAR (PSEG)

Hope Creek Nuclear Generating Station Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic Report SL-011553 Revision 2 R2 January 29, 2014 Project No. 12800-217 Nuclear Safety Related Prepared by Sargerut & L,,ruL°,

SL Report No.: SL-01 11553 0 PSEG Rev. No. 1 November 21, 2012 NUCLEAR LLC Page No. 1 of 20 R2 Hope Creek Nuclear Generating Station 12800-2 17 Seismic Walkdown Report

1. INTRODUCTION Following the accident at the Fukushima Daiichi nuclear power plant resulting from the March 11, 2011, Great Tohoku Earthquake and subsequent tsunami, the NRC established the Near Tenn Task Force (NTTF) in response to Commission direction. The NTTF issued a report that made a series of recommendations to the Commission. The Commission prioritized these recommendations in three tiers. Tier 1 recommendations were to be acted upon "without unnecessary delay."

Subsequently, the NRC issued a 50.54(f) Letter (Reference 10.2) that requests information to assure that these recommendations are addressed by the U.S. nuclear power plants. EPRI prepared Technical Report 1025286, entitled "Seismic Walkdown Guidance" (Reference 10.1), to provide guidance to conduct Seismic Walkdowns required in the 50.54(f)

Letter, Enclosure 3, Recommendation 2.3: Seismic. The seismic walkdowns are to identify and address degraded, non-conforming or unanalyzed conditions and to verify the current plant configuration with the current licensing basis.

2. PURPOSE/OBJECTIVE This report provides the results of the seismic walkdowns at PSEG, Hope Creek Nuclear Generating Station, performed in response to the NRC request for information pursuant to title 10 of the Code of Federal Regulations 50.54(f) letter dated March 12, "Enclosure 3, Recommendation 2.3: Seismic.

The approach and methodologies used in this report follows the EPRI seismic walkdowns guidance as documented in Ref.

10.1.

3. SEISMIC LICENSING BASIS 3.1. SEISMIC DESIGN Per Hope Creek UFSAR Section 3.2.1, "General Design Criterion (GDC) 2, of Appendix A to 10CFR50, requires that nuclear power plant structures, systems, and components important to safety be designed to withstand the effects of earthquakes without loss of capability to perform necessary safety functions. Appendix A to 10CFRl00 requires that all nuclear power plants be designed so that, if a safe shutdown earthquake (SSE) occurs, certain structures, systems, and components important to safety remain functional. These plant features are those necessary to ensure:

1. The integrity of the reactor coolant pressure boundary (RCPB)

2. The capability to shut down the reactor and maintain it in a safe condition.

3. The capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guideline exposures of 10CFR 100."

Per UFSAR Section 3.7, "all structures, systems, and components important to plant safety are designed to withstand a safe shutdown earthquake (SSE) and an operating basis earthquake (OBE)."

SL Report No.: SL-01 1553 0 PSEG Rev. No. 1 November 21, 2012 NUCLEAR LLC Page No. 2 of 20 R2 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report "The SSE is based on an evaluation of the maximum earthquake potential considering the regional and local geology, seismology, and specific characteristics of local subsurface material. The SSE produces the maximum vibratory ground motion for which Seismic Category I structures, systems, and components are designed to remain functional.

The OBE is an earthquake that, considering the regional and local geology, seismology, and specific characteristics of local subsurface material, could reasonably be expected to affect the plant site during the operating life of the plant.

Seismic Category I structures, systems, and components of the nuclear power plant necessary for continued operation without undue risk to the health and safety of the public are designed to remain functional and within applicable stress and deformation limits during the vibratory ground motion produced by an OBE."

Design Response Spectra Per Hope Creek UFSAR Sec. 3.7.1.1, "The design response spectra, which comply with the requirements of Regulatory Guide 1.60, are shown on, Figures 3.7-1 and 3.7-2 in both the horizontal and vertical directions, respectively, for the SSE. For the OBE, the design response spectral values are taken as half of the SSE values. Based on geological and seismological information, as discussed in Sections 2.5.2.6 and 2.5.2.7, the maximuml ground acceleration values for both horizontal and vertical components of the earthquake are 10 percent and 20 percent of gravity for an OBE and SSE, respectively."

"The vibratory ground motion (free field) produced by the seismic motion, as defined by the design response spectra, and the design time history are conservatively applied at the elevation that corresponds to the bottom of the structural foundation in the free field without the effect of the structures."

SL Report No.: SL-0l11553 0 PSEG Rev. No. I November 21, 2012 NUCLEAR LLC Page No. 3 of 20 R2 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Re-oort I Damping Values Used in Seismic Analysis From UFSAR Table 3.7-1, CRITICAL DAMPING RATIOS FOR ANALYSIS OF NSSS MATERIALS:

Percent Critical Damping Item OBE Condition SSE Condition Welded structural assemblies 1.0 2.0 Steel frame structures 2.0 3.0 Equipment 2.0 3.0 Bolted or riveted structural 4.0 7.0 Vital piping systems:

Diameter greater than 12 in. 2.0 3.0 Diameter less than or equal to 12 in 1.0 2.0 Reactor pressure vessel, shroud 2.0 4.0 Control rod drive (CRD) housings 1.0 2.0 Fuel assemblies 4.0 (vert.) 6.0 6.0 (horiz.)

CRD restraint bellows and stabilizer 2.0 4.0 Primary containment, RPV pedestal, 4.0 7.0 and biological shield wall

o PSEG

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November 21, 2012 NUCLEAR LLC Page No. 4 of 20 [ R2 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report From UFSAR Table 3.7-2, DAMPING VALUES FOR SEISMIC CATEGORY I STRUCTURES, SYSTEMS AND COMPONENTS (NON-NSSS):

Modal Damping Values, Percent of Critical Damping Structure or Component OBE SSE Equipment and large diameter piping 3 systems (pipe diameter in excess of 12 inches)(2)

Small diameter piping systems (pipe 1 2 diameter equal to or less than 12 inches)

Welded steel structures 2 4 Bolted steel structures 4 7 Prestressed concrete structures 2 5 Reinforced concrete structures 4 7

SL Report No.: SL-01 1553 0 PSEG Rev. No. 1 November 21, 2012 NUCLEAR LLC Page No. 5 of 20 ] R2 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report 3.2. SEISMIC CATEGORY I STRUCTURES AND EQUIPMENT Section 3 of the Hope Creek UFSAR, Ref. 10.3 documents the seismic licensing basis and criteria used to design the Seismic Category I structures, systems, and components (SSCs).

Mechanical Components Per UFSAR Section 3.9.2.4.1, all non-NSSS Seismic Category I mechanical equipment is designed to withstand the simultaneous horizontal and vertical accelerations caused by the OBE and SSE in conjunction with other normal operating loads.

Seismic qualification criteria used for the Seismic Category I mechanical equipment, with the exception of pumps and active valves, are in compliance with Regulatory Guide 1.100 and IEEE 344-1975.

Pumps Per UFSAR Section 3.9.3.2.7.1, non-NSSS pumps are seismically analyzed to ensure that they will be capable of operating both during and after OBE and SSE events.

Active Valves Per UFSAR Section 3.9.3.2.7.2, for all active valves with extended top works, an analysis is performed for static equivalent SSE loads applied at the extended structure's center of gravity. The maximum stress limits allowed in the analyses demonstrate structural integrity and are equal to the limits recommended by ASME for the particular ASME class of valve analyzed.

Instrumentation and Electrical Equipment Per UFSAR Section 3.10.1.2.2, seismic qualification criteria used for the Seismic Category I instrumentation and electrical equipment are in compliance with IEEE 344-1975 and Regulatory Guide 1.100.

All plant Seismic Category I instrumentation and electrical equipment are seismically qualified by one of the following methods:

1. Dynamic analysis

2. Testing under simulated seismic conditions

3. Combination of testing and analysis 3.3. CODES AND STANDARDS This section summarizes some of the code and standards for the seismic qualification of structures, systems and components at Hope Creek. A full list of these codes and standards is provided in sections 3 of the Hope Creek UFSAR.

SL Report No.: SL-01 11553 0 PSEG Rev. No. 1 November 21, 2012 NUCLEAR LLC Page No. 6 of 20 IR2 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report Reinforced concrete: ACI 318-1971, with 1974 supplement, Building Code Requirements for Reinforced Concrete Concrete Masonry Structures: ACI 531-1979, Specification for Structural Concrete for Building Steel Construction: AISC Manual of Steel Construction, 1969 with Supplements 1, 2, 3 Steel Containment: ASME B&PV,Section III, Subsection NE, Class MC Component, 1974 with Winter 1974 Addenda Electrical Equipment: IEEE Standard 344-1975, "Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations"

4. PERSONNEL QUALIFICATION The activities to be performed by qualified personnel and their responsibilities and qualifications are described in the EPRI guidance, Ref. 10.1. These responsibilities are:

• Selecting the SSCs that should be placed on the Seismic Walkdown Equipment List, as described in Section 3:

Selection of SSCs

• Performing the Seismic Walkdowns and Area Walk-Bys, as described in Section 4: Seismic Walkdowns and Area Walk-Bys

• Performing the seismic licensing basis evaluations, as described in Section 5: Seismic Licensing Basis Evaluation (Performed by PSEG)

• Identifying the list of plant-specific vulnerabilities identified during the IPEEE program and reporting the status of actions taken to eliminate or reduce them, as describe in Section 7: IPEEE Vulnerabilities

• Peer Review as described in Section 6: Peer Review.

Table 4-1 below summarizes the roles of personnel who participated in the implementation of NTTF 2.3 Seismic Walkdowns.

SL Report No.: SL-01 11553 0 PSEG Rev. No. 1 November 21, 2012 NUCLEAR LLC Page No. 7 of 20 R2 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report Table 4-1 Personnel Roles Equipment Seismic Name Selection Plant Walkdown IPEEE Peer Personnel Operations Engineer Reviewer Reviewer (SWE)

Arie Blum X X X John Skomorucha X X Jeffery Puskar X Alexander Coologeorgen X X X Joseph Baker Javad Moslemian (1) X Bryan Morgan X Notes: 1. Peer Reviewer Team Leader.

The qualification and experience of above personnel is listed below:

Arie Blum, Ph.D., PE: Dr. Blum is a Senior Project Associate in the S&L Wilmington, DE office with 37 years experience in the nuclear industry in various Design Engineering roles and responsibilities; including design and analysis of structures and components, environmental and seismic qualification programs, design change modifications, Steam Generator replacement Project and Dry Cask Storage Project.

John Skomorucha, PE: Mr. Skomorucha is a Senior Project Associate in the S&L office in Wilmington, DE office with 24 years of experience in the civil/structural field of which 14 years are associated with the nuclear industry. His experience includes; civil/structural lead for various PSEG Salem Unit 1 & 2 and Hope Creek projects. These projects were; ISFSI dry cask storage system, security and various other projects associated with design change modifications of structures and components..

Jeffery Puskar, PE: Mr. Puskar is a Senior Associate in the S&L Wilmington, DE office with 4 years experience in structural design and implementation of design change packages for several nuclear plants.

Alexander Coologeorgen: Mr. Coologeorgen is a Structural Associate in the S&L Chicago, IL office with 3 years of experience; he is currently involved with structural analysis efforts to support modification packages for the Entergy Corporation Palisades Nuclear Power Plant.

Bryan Mor2an, PE: Mr. Morgan is Senior Associate in the S&L Wilmington, DE office with 12 years experience in structural/civil engineering field of which 6 years are in the nuclear industry. His experience includes; lead structural engineer on the security upgrade project, various plant modification projects for PSEG.

0 PSEG NUCLEAR LLC SL Report No.: SL-0 11553 Rev. No. 2 January Page No.29, 2014 8 of 20 R2 IR Generating Hope Creek Nuclear Station 12800-217 Seismic Walkdown Report Joseph Baker: Mr. Baker is a currently licensed Senior Reactor Operator (SRO) at Hope Creek Generating Station. He has more than 28 years nuclear operation experience from equipment operator to control room supervisor. He was one of the operations work week coordinators prior to being assigned to the Fukushima Response Team.

Javad Moslemian: Mr. Moslemian is a Senior Manager in the S&L Chicago office with more than 29 years of experience in the analysis, design and construction of new and existing nuclear power plants. He has significant amount of experience in seismic analysis and design. He is a registered professional engineer in the state of Illinois and successfully completed Seismic Qualification Utility Group (SQUG) training in December of 2001. In addition, Mr. Moslemian is a member of the AISC N690 Code Committee TC 12 and a process owner responsible for several Sargent & Lundy engineering processes. Mr.

Moslemian is currently the structural engineering manager responsible for preparation of responses to NRC RAIs on Chapters 3.7 and 3.8 of South Texas Project (STP) Units 3 & 4. In his prior assignment as the structural engineering manager for STP Units 3 & 4, Mr. Moslemian was supervising the seismic analysis and design for all Seismic Category I structures.

Joshua Hammel. PE: Mr. Hammel is a Senior Associate in the S&L Wilmington, DE office with 5 years experience in structural design and implementation of design change packages for several nuclear plants. R2 The Seismic walkdowns personnel training certifications are included in Attachment 4.

5. SELECTION OF SSCS 5.1. METHODOLOGY The methodology and process used in the selection of SSCs and in the development of the Seismic Walkdown Equipment List (SWEL) follows the guidance provided in Section 3: "Selection of SSCs" of Ref. 10.1. The SWEL consists of samples from two groups of components. The first group, which is the largest group, contains a sample of components that satisfy the five safety functions described in Ref. 10.1 and is referred to as SWEL 1. The second group is a sample of components related to Spent Fuel Pool (SFP), referred to as SWEL 2. The components from SWEL I and from SWEL 2 are combined to establish the SWEL; defining the scope of the seismic walkdowns.

The development of the SWEL was performed by qualified personnel as described in Section 4.0 of this report.

5.2. SWEL 1 - SAMPLE OF REQUIRED ITEMS FOR THE FIVE SAFETY FUNCTIONS SWEL 1 is developed from the four screens identified in Section 3 of Ref. 10.1.

5.2.1. SCREENS 1 THROUGH 3 - SEISMIC CATEGORY I, EQUIPMENT OR SYSTEMS, SUPPORT OF THE FIVE SAFETY FUNCTIONS Screens 1 through 3 are used to select Seismic Category I equipment that support the five safety functions and do not undergo regular inspections. The equipment coming out of Screen 1 through 3 is referred to as "Base List 1".

Section 3 of Ref. 10.1 indicates that previously developed equipment lists can be used as a starting point for selecting component for SWEL 1. For Hope Creek, a base list of SSCs for reactor safe shutdown and containment function was previously developed for the Individual Plant Examination for External Events (IPEEE) Program, Ref. 10.2, and augmented with the Shutdown Component List developed for the Hope Creek Appendix R Program, Table 9A - 2 of Ref. 10.3. Together the IPEEE base list and the Appendix R

SL Report No.: SL-0 1155 3 0 PSEG Rev. No. 1 November 21, 2012 NUCLEAR LLC Page No. 9 of 20 IR2 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report Shutdown Component List comprise Base List 1 as defined in Ref. 10.1, which includes components associated with the five safety functions:

1. Reactor reactivity control 2 Reactor coolant pressure control 3 Reactor coolant inventory control 4 Decay heat removal 5 Containment function "Base Lists IA and 1B", for the selection of the sample of components for SWEL 1 are provided in Attachments 1A and lB.

5.2.2. SCREEN 4: SAMPLE CONSIDERATIONS FOR SWEL 1 The equipment selection personnel used the five sample selection considerations described in Ref. 10.1 to select components for SWEL 1:

1. A variety of systems A sample of components from the systems listed in Base Lists IA and 1B, Attachments IA and 1B, were selected. SWEL I includes equipment in a variety of systems such as Main Steam, Feedwater, High Pressure Injection, High Pressure Core Spray, Service Water, AC Power, and DC Power.

2. Major new and replacement equipment The SAP data base for Work Orders was used to identify new and replaced components are identified in the SWEL, Attachment 2.

3. A variety of types of equipment Appendix B of Ref. 10.1 provides the classes of equipment for the SSCs. The equipment selection personnel selected equipment classes based on the relative percentage of equipment classes in each system of the Base List 1. For example, SWEL 1 contains a large percentage of Motor Operated Valves (MOVs, Class 8) since there is a large percentage of MOVs in Base List 1.

At least one component from each equipment class was selected from each system listed in Base List 1. Upon completion of this process all equipment types have been represented except Air Compressors (Class 12) and Motor Generators (Class 13) because Hope Creek does not have any Seismic Category I equipment in these classes of equipment.

4. A variety of environment For each equipment type, as applicable, a variety of environments were selected: Harsh (e.g., some areas in the Reactor Bldg, Drywell), Mild (e.g. Control Room, Auxiliary Building), Outdoor/Intake Structure (e.g.

Service Water Intake Structure).

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5. Equipment enhanced due to vulnerability identified during the IPEEE pro-ram As stated in Ref. 10.2 and Section 8.0 of this report, "no vulnerabilities have been identified" as part of the IPEEE program. Consequently, SWEL I does not include equipment that meets this sampling consideration.

Utilizing the above sampling consideration, a preliminary SWEL 1 was developed and reviewed by a Hope Creek Licensed Operator. Items were selected or replaced based on a channelized work week process and in some cases items were added based on overall representation of equipment. In addition, some items were selected or rejected based on accessibility. For example, items were excluded that would require disassembling of equipment or an item was on a protected train, so the similar item on the non-protected train was selected. The review resulted in 17 components for which accessibility to perform the inspection were deferred to the HCGS 18 01Refueling Outage (RFO) scheduled for Fall 2013. Deferred components are located inside containment or are energized electrical equipment containing sensitive components.

5.3. SWEL 2 - SPENT FUEL POOL RELATED ITEMS The Seismic Walkdown Equipment List 2 (SWEL 2) is a sample of the Spent Fuel Pool (SFP) associated SSCs. The process for SWEL 2 development is defined in the Seismic Walkdown Guidance, Ref. 10.1 and consists of four screens:

• Screen 1: Seismic Category I

" Screen 2: Equipment or Systems

" Screen 3: Sample Considerations.

In addition, SWEL 2 also includes a screen that considers SFP SSCs that can cause rapid drain-down of the SFP.

Screen 4: Cause rapid drain-down The subsections below document the screening of SSCs for SWEL 2.

5.3.1. SCREEN 1- SEISMIC CA TEGORYI The Seismic Walkdown Equipment List 2 (SWEL 2) is a sample of the site Fuel Pool (SPF) associated SSCs.

This list was derived from the PSEG SAP data base of all Safety Class 1, Fuel Pool components from a variety of associated systems. The first items that were excluded in Screen 1 list were items that were not directly associated to the failure of the Spent Fuel System (HV) in a seismic event. These items included but not limited to pipe supports, snubbers and piping anchors 5.3.2. SCREEN 2- EQUIPMENT OR SYSTEMS From Screen 1, components were excluded that were not appropriate or readily accessible for seismic walkdowns. After Screen I & 2, a "Base List 2" is developed and included in Attachment IC. It is from this Base List 2 that a small sampling of SF components was selected in Screen 3.

SL Report No.: SL-0 11553 0 PSEG Rev. No.1I November 21, 2012 NUCLEAR LLC Page No. I Iof 20 R2 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report 5.3.3. SCREEN 3 - SAMPLE CONSIDERATIONS The equipment selection personnel used the following considerations described in Ref. 10.1 to select components for SWEL 2:

1. A variety of systems Sample of components from each of the system listed in Base List 2, Attachment 1B, were selected.

SWEL 2 includes equipment of several systems such as, Fuel Pool Cooling (EC), Torus Water Clean up (EE), Neutron Monitoring (SE) and Safety Turbine Aux Cooling (EG).

2. Major new and replacement equipment The SAP data base for Work Orders was used to identify new and replaced components as indicated in the SWEL, Attachment 2.

3. A variety of types of equipment Appendix B of Ref. 10.1 provides the classes of equipment for the SSCs. The equipment selection personnel selected equipment classes based on the relative percentage of equipment classes in each system of the Base List 2.

From each associated Spent Fuel Pool system, at least one component was selected. Most items in Base List 2 were pipe and piping systems. Emphasis was placed upon items that support the Fuel Pool Cooling system, such as Residual Heat Removal (RHR) (BC) and Safety and Turbine Aux Cooling (EG). The selection process eliminated similar or redundant items of a system (e.g. valves). Other eliminated items were pipe, indicators, and orifice plates. Ideally, Fuel Pool Cooling would be selected.

These items remaining such as cooling pumps and heat exchangers are inaccessible due to being located in high rad areas. The safety related components that were selected were a Fuel Pool Cooling Heat Exchanger valve, and a valve that is common for water from H 1EC - 1EC021 WOO 1, W002, W003 and W004.

4. A variety of environment It is expected to have each equipment type, as applicable, represent a variety of environments. For most SPF related components, the environment is mostly harsh.

5. Equipment enhanced due to vulnerability identified during the IPEEE program As stated in Ref. 10.6 and Section 8.0 of this report, "no vulnerabilities have been identified" as part of the IPEEE program. Consequently, SWEL 2 does not include equipment that meets this sampling consideration.

Utilizing the above sampling consideration, a preliminary SWEL 2 was developed and reviewed by a Hope Creek Licensed Operator. Items were selected or replaced based on a channelized work week process. In

SL Report No.: SL-01 1553 0 PSEG Rev. No. 2 January 29, 2014 R2 NUCLEAR LLC Page No. 12 of 20 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report addition, some items were selected or rejected based on accessibility in High Rad areas. The review resulted in the selection of 2 components and 2 AWBs.

The components are:

" RHR Loop A DSCH to FPCCs ISO Valve

" Fuel Pool Cooling HX SUP ISO Valve (MOV) 5.3.4. SCREEN 4: RAPID DRAIN-DOWN The fuel pool cooling systems takes suction from the skimmer surge tank and returns to the spent fuel pool vertically from above the water and is provided with the redundant vacuum breakers to prevent siphoning.

No connections to the spent fuel storage pool shall be made below the level of the gates. When the gates are installed, the 2 inch drain from between the gates will be open to provide leak detection and alarms to the control room and keep the area between the gates dry. Alarm Response Procedures are used to identify and isolate leakage from these drain lines. All other connections from the cask pit are normally closed manual isolation valves.

In addition, no penetrations below about 10 ft. above the top of the fuel assemblies were identified for Hope Creek. Per the guidance of Ref. 10.1, "if it is determined that there are no such penetrations, then no rapid drain-down items would be added to SWEL 2."

The SSCs included in the SWEL 2 after completing the screening process are as follows,

• RHR Loop A Discharge to Fuel Pool Cooling Isolation Valve

" Fuel Pool Cooling HX SUP Isolation Valve SWEL 2 components are identified on the SWEL via a reference to a note in the note column.

5.4. SWEL SWEL 1 and SWEL 2 were combined to establish the final SWEL, defining the scope of the seismic walkdowns.

The final SWEL for Hope Creek contains 103 components. The SWEL, Attachment 2, was reviewed to determine R2 the population of anchored components and ensure that at least 50% of these components have been selected for anchorage verification during the seismic walkdowns, in accordance with the EPRI guidance Ref. 10.1.

The SWEL identifies components that are potentially risk significant. The risk significance of a component was determined from the IPEEE report, Ref. 10.2, and utilizing the M-Rule criteria. The SWEL also identify the components applicable safety function for each component; this validates that components associated with all five functions are represented in the SWEL.

0 SL Report No.: SL-01 1155 3 PSEG Rev. No. 2 January 29, 2014 R2 NUCLEAR LLC Page No. 13 of 20 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report

6. SEISMIC WALKDOWNS AND AREA WALK-BYS 6.1. PREPARATION In preparation for the seismic walkdowns, the Seismic Walkdown Engineers identified the rooms that contained the SWEL items or (for large rooms) defined distinct areas of the plant within approximately 35 feet of each SWEL item.

The SWEs assigned a unique number for each room or area of the plant, e.g. Area Walk-Bys (AWB) #HC-01 to catalog each area with the associated Area Walk-By Checklist (AWC) and associated components Seismic Walkdown Checklist (SWCs) for components located in the area. For Hope Creek, a total of 46 areas were defined for the 103 SWEL items. The total number of components is reduced from 104 to 103, see section A.5 of Attachment 6. IR2 The walkdowns were scheduled based on a channelized work week and the protected equipment schemes. This resulted in some areas to be visited more than once to capture selected components from different channels.

Based on AWBs, walkdown packages were prepared. The walkdown packages included pertinent infornation about the components (e.g. design drawings, calculations, results from previous walkdowns) and the corresponding AWBs and SWCs.

6.2. AREA WALK-BYS (AWVB) AND SEISMIC WALKDOWN Seismic walkdowns were performed by a team of two SWEs in accordance with the EPRI guidance Ref. 10.1. The focus of the seismic walkdowns was to perform visual inspections to identify potentially adverse seismic conditions.

The SWEs relied upon their engineering judgmnent and training to identify potentially adverse anchorage conditions, adverse seismic spatial interactions, and any other adverse conditions as described in Ref. 10.1. The SWEs also verified that the anchorage configuration of at least 50% of the anchored components is consistent with the plant documentation.

Seismic walkdowns were performed for all 103 components on the final SWEL and for all 46 areas that contain R2 the components.

6.3. RESULTS 6.3.1. SEISMIC WALKDOWNS The results of the area walk-bys and the seismic walkdowns are documented on the associated AWC's and SWC's, which are contained in Attachment 3 and Attachment 6.

A total of 87 component walkdowns were completed before RFO18 in 2012. These components are R2 included in Attachment 3. A total of 16 components and 4 AWC's, that were deferred to the Hope Creek RFO118 in the fall of 2013, are included in Attachment 6. Components deferred to the RFO are identified in the SWEL (notes column).

6.3.2. ANCHORAGE VERIFICATION As required by the EPRI guidance Ref. 10.1 at least 50% of the anchored components require verification of the anchorage to ensure its seismic adequacy and to verify its configuration against design documents.

0 PSEG SL Report No.: SL-Ol 115 53 Rev. No. 2 January 29, 2014 R2 NUCLEAR LLC Page No. 14 of 20 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report The following is a summary of anchorage verification:

• Total number of anchored components = 72

" Total number of anchorage verified components = 40

• Percentage of verified anchorage = 56%

Based on the above no additional anchorage verification is required. However, during walkdowns R2 deferred to the Hope Creek RFOI 8, anchorage was verified for an additional component.

6.3.2. POTENTIALLY AD VERSE SEISMIC CONDITIONS Issues and concerns identified during the walkdowns have been documented on the applicable checklists.

Checklist boxes that have been checked "No" indicate a "potentially adverse seismic condition" may exist.

All potentially adverse seismic conditions were entered into the Corrective Action Program (CAP) prior to completing a detailed licensing basis evaluation of the condition. Table 6-1 summarizes the potentially adverse conditions and the status of the condition.

The potentially adverse seismic conditions that have been identified included issues associated with seismic interaction, for which corrective actions have been completed. Other issues were associated with adequacy of the as found anchorage configuration. An engineering technical evaluation has been completed as detailed in Sec. 7.0. Also included is an issue associated with corrosion that prevented inspection of the anchor bolt adequacy, for which a corrective action to wire brush the anchor bolt was completed and the SWC was completed. These issues are summarized in Table 6-1.

All non-seismic conditions identified during the walkdowns were brought to the attention of plant personnel and Notifications were written as necessary. An example of non-seismic conditions includes housekeeping items (e.g. trash or small tools left in plant areas). These items are not specifically documented in this report, but are available through the Plant CAP database.

o PSEG SL Report No.: SL-011553 Rev. No. 2 November 21, 2012 NUCLEAR LLC Page No. 15 of 20 1R2 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report Table 6-1: Hope Creek - Potentially Adverse Seismic Conditions Notification Date AWB No. jCreated N C No. SWC No. Description Status Comments SWIS panel CC581 Rescreen based on 20577885 10/08/2012 CC581 CLOSED anchorage Notification 20578051 Tech. Eval.

completed, revised SWIS panel CC581 20578051 10/10/2012 CC581 COMPLETED Calc 646-008 to anchorage reflect as-built condition Checklist Q. 3 was "No". After cleaning Bolts Wire SSW Traveling Screen off the corrosion the 20577886 10/08/2012 HC-07 Brushed Anchor Bolts inspection could be 10/11/2012 completed and Box was marked "Yes" Checklist Q. 7 was "No". After removing Tools have been items to alleviate the 20577503 10/05/2012 1 HC-02 SWIS Transient Loads removed seismic interaction, 10/05/2012 Box was marked "Yes" Checklist Q. 10 was "No". After Reattached reattaching hanging Abandon cable &

20578213 10/12/2012 1CC652 hanging cable cable to alleviate the Connector plug Closed 10/12/12 seismic interaction, Box was marked "Yes

& .L U L J .1

SL Report No.: SL-01 11553 PRev. No. 2 January 29, 2014 R2 NUCLEAR LLC Page No. 16 of 20 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report

7. LICENSING BASIS EVALUATIONS All potentially adverse seismic conditions identified during the walkdowns were entered into the site CAP for review and disposition in accordance with plant's existing process and procedures.

Licensing basis reviews were performed as part of the CAP process by PSEG personnel familiar with the seismic licensing basis and safety-functions of the equipment. Table 6-1 lists all potentially R2 adverse seismic conditions and status of each item in the CAP process.

The potentially adverse seismic condition associated with the adequacy of the anchorage configuration (Notification 20578051) resulted in an immediate corrective action. A technical evaluation demonstrates adequacy of the as-found anchorage configuration.

No plant design modifications resulted from the potentially adverse seismic conditions. Any corrective actions perforined to enhanced equipment are classified as repairs.

8. IPEEE VULUNERABILITY RESOLUTION REPORT In its response to GL 88-20 Ref. 10.2 PSEG states that "no vulnerabilities have been identified" and therefore no enhancements to address seismic vulnerability were required. Consequently, the SWEL does not include any equipment enhanced or updated per the IPEEE program.

9. PEER REVIEW Peer review was conducted in accordance with EPRI 1025286 guidance (Ref. 10.1). The peer review team consisted of two qualified individuals. The following peer reviews were performed:

- Review the selection of the SSCs included on the SWEL

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

- Review the licensing basis evaluations (Within the PSEG's CAP process)

- Review the decisions for entering the potentially adverse conditions into the CAP process

- Review the submittal report Each of the above peer review activities were performed by both members of the peer review team.

9.1. REVIEW THE SELECTION OF SSCS INCLUDED ON THE SWEL A peer review of the Seismic Walkdown List (SWEL) SSCs was performed to ensure the SSCs were selected in accordance with the guidance in Section 3: Selection of SSCs of the EPRI 1025286, Seismic Walkdown Guidance.

SL Report No.: SL-01 1553 0 PSEG Rev. No. 1 November 21 2012 NUCLEAR LLC Page No. 17 of 20 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report The peer review of the SWEL SSCs was conducted by performing the following steps:

- Verifying the basis for the "Base List 1" for SWEL I The base list of SSCs used to develop SWEL 1 was obtained using the list of items generated for the "Response to Generic Letter 88-20, Supplement 4, Individual Plant Examination for External Events (IPEEE) for Sever Accident Vulnerabilities - Hope Creek Generating Station" (Ref. 10.2) combined with the Appendix R Shutdown Component List.

Per Section 3: Selection of SSCs of the EPRI Seismic Walkdown Guidance, this is acceptable for establishing a base list.

- Verifying SSCs selected for SWEL 1 are Seismic Category I (Screen #1)

The items listed in the IPEEE list and Appendix R Shutdown Component list are Seismic Category I items and meet the criteria of Screen #1 as defined in Section 3: Selection of SSCs in the EPRI Seismic Walkdown Guidance.

- Verifying SSCs selected for SWEL 1 are equipment or systems (i.e. valves, pumps, panels, tanks, batteries) (Screen #2)

A review of SWEL 1 revealed no Seismic Category I Structures, Containment Penetrations or Seismic Category I Piping Systems were included. The list consists of mechanical and electrical equipment (i.e. pumps, valves, chillers, power supplies, tanks, MCCs) and therefore meets the criteria of Screen #2.

- Verifying SCCs selected for SWEL 1 support the 5 Safety Functions (Screen #3)

A review of SWEL 1 shows the items listed support the 5 Safety Functions. Some items support more than one Safety Function and some Safety Functions are supported by more than one item. Therefore, SWEL I meets the criteria for Screen #3.

- Verifying SSCs selected for SWEL 1 include a variety of types of systems, major new and replacement equipment, a variety of types of equipment, a variety of environments and equipment enhanced due to vulnerabilities identified during the IPEEE program (Screen #4)

• Items from each system listed in the Base List were chosen for SWEL 1.

• New or replaced items have been identified on SWEL 1.

• Items from all classes of equipment were selected for SWEL I with the exception of Class 12 (Air Compressors) and Class 13 (Motor Generators) as Hope Creek does not have any Seismic Category I equipment in these equipment classes.

SL Report No.: SL-011553 0 PSEG Rev. No. 1 November 21 2012 NUCLEAR LLC Page No. 18 of 20 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report Items were chosen that are located in harsh environments (Reactor Building, Drywell), mild environments (Control Room, Auxiliary Building) and outside buildings (Service Water Intake Structure).

Per "Response to Generic Letter 88-20, Supplement 4, Individual Plant Examination for External Events (IPEEE) for Severe Accident Vulnerabilities, Hope Creek Generating Station" (Ref. 10.2), no vulnerabilities owing to external event at Hope Creek'were found. Therefore, no IPEEE enhanced equipment was selected for SWEL 1.

As shown, SWEL I meets the criteria for Screen #4.

- Verifying SSCs selected for SWEL 2 relating to the Spent Fuel Pool (SFP) meet Screens #1

- #3 above for SWEL I as well as include items that could allow the SFP to drain rapidly (Screen #4)

SSCs associated with the SFP were identified using the SAP Database to create "Base List 2". The screening process in EPRI 1025286 was followed to develop SWEL 2.

No penetrations below about 10ft above the top of the fuel assemblies were identified for Hope Creek. Therefore, in accordance with Section 3: Selection of SSCs of the EPRI Seismic Walkdown Guidance, no rapid drain-down items were added to SWEL 2.

Therefore, SWEL 2 meets the criteria for Screen #4.

The lists for SWEL 1 and SWEL 2 were then combined to form the SWEL used for the Seismic Walkdowns.

No issues requiring resolution were found during the peer review of the selection of SSCs.

The SWEL meets all requirements set forth in Section 3: Selection of SSCs of the EPRI Seismic Walkdown Guidance.

Attachment F: Checklist for Peer Review of SSC Selection has been completed with all questions being answered yes. (See Attachment 5) 9.2. REVIEW A SAMPLE OF THE CHECKLIST PREPARED FOR THE SEISMIC WALKDOWNS AND AREA WALK-BYS Considering the experience and qualification of the Seismic Walkdown Engineers (SWEs), the peer review team selected 15% of the completed seismic walkdown and walk-bys for review. The selection included a number of components and areas with reported potential adverse seismic conditions. In addition the SWEs were interviewed by the peer review team to ensure that the seismic walkdowns and area walk-bys were conducted in accordance with EPRI 1025286 guidelines.

0 PSEG SL Report No.: SL-0l 11553 Rev. No. I November 21 2012 NUCLEAR LLC Page No. 19 of 20 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report The review resulted in a number of editorial comments for further clarity and consistency of the seismic walkdown and area walk-bys checklists. These editorial comments were satisfactorily resolved. The review did not result in identification of any new potentially adverse seismic conditions.

Based on this review and satisfactory resolution of peer review comments, it was concluded that the seismic walkdown of the components and area walk-bys were conducted properly in accordance with Section 4 of EPRI 1025286 guidance.

9.3. REVIEW THE LICENSING BASIS EVALUATIONS All potentially adverse seismic conditions identified during the seismic walkdown of components and area walk-bys were entered in the CAP program through creation of notifications in SAP for further evaluations. No licensing basis evaluations were performed outside the CAP process.

9.4. REVIEW THE DECISIONS FOR ENTERING THE POTENTIALLY ADVERSE SEISMIC CONDITIONS INTO THE CAP PROCESS During the Seismic Walkdowns and Area Walk-Bys, the following steps were taken when Potentially Adverse Conditions were identified:

- Any potentially adverse seismic conditions found in the field were noted on the AWCs and SWCs.

- Upon returning from the walkdown, the SWEs reported the issues and PSEG created the notification in CAP.

- As required these notifications were then reviewed by engineering which entailed reviewing the as- installed condition found in the field against Seismic Qualification Documentation (SQD),

i.e. calculation, to determine if the as-installed condition was consistent with the SQD and thereby the Current Licensing Basis (CLB).

- If the as-installed condition was determined to be consistent with the SQD, the notification was dispositioned stating that fact and no further action was taken. If the as-installed condition was determined not to be consistent with the SQD, a work order was created to perform further technical evaluations and any corrective actions require, i.e. revise calculations.

This process ensured any potential licensing basis issue was documented and reviewed by the appropriate personnel.

9.5. REVIEW THE SUBMITTAL REPORT The submittal report was reviewed in detail to ensure that the objectives and requirements of the 50.54(f) letter were met. The editorial comments provided by the peer review team were satisfactorily resolved and it was concluded that the report met the objectives and requirements of the 50.54(f) letter.

SL Report No.: SL-01 11553 0 PSEG Rev. No. 1 November 21 2012 NUCLEAR LLC Page No. 20 of 20 Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report

10. REFERENCES 10.1. EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, June 2012 10.2. PSEG Response to Generic Letter 88-20, Supplement 4, "Individual Plant Examination for External Events (IPEEE) for Severe Accident Vulnerabilities," Hope Creek Generating Station, Docket No. 50-354, Jul 31, 1997 10.3. Hope Creek UFSAR, Rev. 19 10.4. NRC Letter dated March 12, 2012, "Request for Information Pursuant to Title 10 of the Code of Federal regulations 50.54 (f), Recommendation 2.1, 2.3 and 9.3 of Near -Ternm Task Force Review of the Insights from the Fukushima Daiichi Accident", Enclosure 3, "Recommendation 2.3:

Seismic."

Hope Creek Nuclear Generating Station S&L Report No. SL-0 11553 Project No. 12800-217 Rev. 2 Seismic Walkdown Report ATTACHMENTS ATTACHMENT IA-BASE LIST IA-SCREENING OF HOPE CREEK SEISMIC IPEEE COMPONENTS ATTACHMENT I B - BASE LIST lB-SHUTDOWN COMPONENT LIST (UFSAR TABLE 9A-2)

ATTACHMENT IC - BASE LIST 2-COMPONENTS ASSOCIATED WITH FUEL POOL COOLING ATTACHMENT 2 - SEISMIC WALKDOWN EQUIPMENT LIST (SWEL)

ATTACHMENT 3 - AREA WALK-BYS CHECKLISTS (AWC) AND SEISMIC WALKDOWN CHECKLISTS (SWC)

ATTACHMENT 4 - SEISMIC WALKDOWNS PERSONNEL'S CERTIFICATIONS ATTACHMENT 5 - CHECK LIST FOR PEER REVIEW OF SSC SELECTION ATTACHMENT 6 - WALKDOWNS PERFORMED DURING RFO18 1R2

Hope Creek Nuclear Generating Station S&L Report No. SL-0 11553 Project No. 12800-217 Rev. I Seismic Walkdown Report ATTACHMENT 1A - BASE LIST 1A- SCREENING OF HOPE CREEK SEISMIC IPEEE COMPONENTS

HOPE CREEK GENERATING STATION July 1997 Individual Plant Examination for External Events Table 3-4 Screening of Hope Creek Seismic IPEEE Components

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xxy,>x... .... ~

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ACP 10Y406 120 VAC CONTROL POWER BUS 10Y406 Control 5101 54' No 5 C-293 Diesel ACP 1AJ481 CLASS 1E 120V PANEL 1AJ481/1CJ481 Control 5501 137' No 5 Diesel ACP IBJ481 CLASS IE 120V PANEL 1BJ481/1DJ481 Control 5448 124' No 3,5 Diesel ACP 1BJ484 120 VAC CNTRL RM PWR-UPS- BUS I BJ484 Control 5624 163' Yes C-251,252 Diesel ACP IAJ482 CLASS IE 120V PANEL I1AJ482/1CJ482 Control 5616/ 163' No 5 Diesel 5613 ACP I CJ483 FUSE PANEL YF407-120 VAC BUS I CJ483 Control 5102 54' Yes C-258 Diesel ACP IBJ482 CLASS IE 120V PANEL 1BJ482/1DJ482 Control 5607 163' No 41 C-Diesel 253,254,25 5

ACP IOA401 CLASS IE 4.16KV BUS IOA401- DIV A/10A402-DIV Control 5411 130' No 52 C-148,149 B/10A403-DIV C/10A404 DIV D Diesel ACP 10B411 CLASS 1E 480VAC MCC 10B411 DIV A/0OB421 DIV B/ Control 5411 130' No 5 C-145 10B431 DIV C/10B441 DIV D Diesel ACP 108410 CLASS 1E480VAC UNITSUBST 10B410-A/10B420- Control 5411 130' No 4 iB/i0B430-C/f10B440-D Diesel ACP 108451 CLASS IE 480VAC MCC IOB451 DIV A/IOB461 DIV Control 5411 130' No 5 B/10B471 DIV C/10B481 DIV D Diesel ACP 1OB450 CLASS 1E 480VAC UNIT SUBST 10B450A/10B460- Control 5411 130' No 4,5 B/10B470-C/10B480-D Diesel ACP 1OB553 480V AC BUS 1OB553/563/573/583 SWIS SWIS 102' No 42,5 C-152 ACP IAD481 IAD481 & 1AD482 AUCTNEERNG ClRC INCL. Control 5501 137' No 1, 2 C-234, 235 INVERTER,STATIC SWITCH LOGIC CIRCUIT, 480-130 Diesel AC-DC VOLT RECT. I I 3 - 59

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July 1997 HOPE CREEK GENERATING STATION Individual Plant Examination for External Events Table 3-4 Screening of Hope Creek Seismic IPEEE Components 100 Idt ACP 1BD481 1BD481 & 1BD482 AUCTNEERNG CIRC INCL. Control 5448 124' No 2 INVERTER,STATIC SWITCH LOGIC CIRCUIT, 480-130 AC- Diesel DC VOLT RECT.

ACP 1CD481 1CD481 & 1CD482 AUCTNEERNG CIRC INCL. Control 5501 137' No 2 C-236, 237 INVERTER,STATIC SWITCH LOGIC CIRCUIT, 480-130 AC- Diesel DC VOLT RECT.

ACP I DD481 1DD481 & 1DD482 AUCTNEERNG CIRC INCL. Control 5448 124' No 2 INVERTER,STATIC SWITCH LOGIC CIRCUIT, 480-130 AC- Diesel DC VOLT RECT.

ACP 10B212 1E 480 VAC MCC 10B212 DIVA/ 10B222 DIV B/ Reactor 4201 / 77'! No 6,5 C-27, 73, 10B232 DIV C/ 10B242 DIV D 4303 102' 74 ACP 10B252 NON I E 480VAC MCC Reactor 4215 77' No 7, 5 C-75 10B252A/10B262B/10B272/10B282 272 DIV C/ 10B282 DIV D I ACP 10B313 NON IE 480VAC MCC 1OB313 DIV A/ 10B323 DIV B Reactor 3602 153' No 42,5 C-262,263,26 4,265,26 ACP 10B474 NON 1E DIV C 480VAC MCC 1OB474 Control 5619 160' No 42, 5 C-260.261 Diesel ACP 1AC421 LOCL GEN CNTRL PNL 1AC421 / 1BC421 / 1CC421/ Control 4304 / 102' No 7, 5 C-1DC421 Diesel 4307 93,94,95,9

_ 1_ 6 ACP 1AC422 REM GEN CNTRL PNL 1AC422/1 BC422/1 CC422/ Control 5410 130' No 5 C-IDC422 Diesel 139,140,19 7,198 ACP lA-C423 DIESEL PANELS - 1A/B/C/D - C423 Control 5412 130' No 8 C-148, 149 Diesel ACP 1A-C428 D/G LOAD SEQUENCE PANEL I A/B/C/D - C428 Control 5410 130' No 43, 5 C 137,138, Diesel I I I , 1141,196,20 3 - 60

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July 1997 HOPE CREEK GENERATING STATION Individual Plant Examination for External Events Table 3-4 Screening of Hope Creek Seismic IPEEE Components

• ..~~~~~.. ~~ .

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ACP 1AC652 PNL 1AC652/1 BC652/ ICC652/1 DC652 Control 5302 102' No 5 C-292 Diesel ACP 10B263 NON-1E 480V MCC 10B263 Reactor 4307 102' No 2 C-5 ACP IAX-400 TRANSFORMER 1AX/BX/CX/DX-400 Control 5411 130' Yes Diesel ACP 1AX-401 TRANSFORMER 1AX/BX/CX/DX-401 Control 5411 130' Yes Diesel ADS AT210 ADS SRV FO13A/B/C/D/E AIR ACCUMULATOR - Reactor 4202 77' Yes A/B/C/D/ET210 ADS 3652A ADS SRV FO13A SOY 'A' - 3652A/ SOV'B' -3652B Reactor 4202 77' Yes ADS 3653A ADS SRV F013B SOV 'A' - 3653A/ SOV'B' -3653B Reactor 4202 77' Yes ADS 3654A ADS SRV F013C SOV A' -3654A /SOV'B' -3654B Reactor 4202 77' Yes ADS 3655A ADS SRV FO13D SOV 'A' - 3655A / SOV'B' -3655B Reactor 4202 77' Yes ADS 3665A ADS SRV F013E SOV 'A' - 3665A/SOV'B' -3665B Reactor 4202 77' Yes ADS FO13A ADS SRV F013A /B/C/D/E Reactor 4202 77' Yes CAC HV-4956 AOV-HV-4956/4958/4964/4979 Reactor 4321/ 102' No 44 4102 CAC SV-4956 SOLENOID VALVE 4956/ 4958/ 4964/ 4978/ 4979 Reactor 4321/ 102' Yes 4102 CAC 4964 ACCUMULATOR 4964/49XX Reactor 4220 102' Yes 51 CAC HV-4950 HV-4950, 4951, 4952, 4962, 4963, 4980 Reactor 4410/, 132' Yes C-121, 122, 275 CONTAINMENT ISOLATION VALVES 4411 3 - 61

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HOPE CREEK GENERATING STATION

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July 1997 Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components k- .91 fuid

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CAC 1GSHV-4978 N2 SUPPLY ISOLATION VALVE Reactor 4317 102' Yes C-291 CAC 1GSHV-1 1541 TORUS VENT ISO MANUAL OPERATION FOR AOV- Reactor 4102 77' No 46 C-275, 289 11541 1 CAC 1GSHV- OUTBOARD CONTAINMENT ISOLATION MANUAL Reactor 4317 102' No 46 C-275 4962/4964 OVERRIDE CAC HV-4956 AOV-HV-4956/4958/4964/4979 Reactor 4321/ 102' No 44 4102 CAC SV-4956 SOLENOID VALVE 4956/ 4958/ 4964/ 4978/ 4979 Reactor 4321/ 102' Yes 4102 CAC 4964 ACCUMULATOR 4964/49XX Reactor 4220 102' Yes 51 CAC HV-4950 HV-4950, 4951,4952, 4962, 4963, 4980 Reactor 4410/, 132' Yes C- 121. 122, CONTAINMENT ISOLATION VALVES 4411 275 CAC 1GSHV-4978 N2 SUPPLY ISOLATION VALVE Reactor 4317 102' Yes C-291 CAC 1GSHV- 11541 TORUS VENT ISO MANUAL OPERATION FOR AOV- Reactor 4102 77' No 46 C-275. 289 S11541 CAC 1GSHV- OUTBOARD CONTAINMENT ISOLATION MANUAL Reactor 4317 102' No 46 C-275 4962/4964 OVERRIDE I CAC 11558A/B/C TORUS VENT ISO N2 ACCUM 1KBPCV1 1558A/B/C Reactor 4317 102' Yes C-290 CHC TV9634A AOV TV9634A/B Control 5605 171' Yes C-181,182 Diesel CHC TV9637A AOV TV9637A /B Control 5602/ 155' Yes Diesel 5630 CHC AK-400 CNTRL AREA CHILLER AK-400/ BK-400 Control 5602 155' No 9 C-210,224 Diesel I CHC AP-400 RECIRC PUMP AP-400 / BP400 Control 5630 155' No 10 CHS TV9667A AOV TV9667A /B Diesel Control 5620 162 Yes FC-208 I___ _Diesel I 3 - 62

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HOPE GREEK GENERATING STATION

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July 1997 Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components CHS AK-403 CNTRL AREA CHILLER AK-403/BK-403 Control 5704 178' Yes C-183 Diesel CHS AP-414 RECIRC PUMP AP-414 / BP-414 Control 5704 178' Yes C-I Diesel 183,184 CHS VH316A/B REMOTE SHUTDOWN PANEL ROOM UNIT Control 5501 137' No 5 C-294 VH316A/VH316B Diesel CHS VH314A/B TECH SUPPORT CENTER A/C UNITS Aux/Rad 3613 152' No 5 C-295 VH314A/314B CHS AT413 CHS EXPANSION TANKS A/BT413 Control 5704 178' Yes C-287 Diesel CNS HV F01 1A MOV HV-F01 1A /B Reactor 4220 120' Yes C-195 CRH FOO2B CRH FLOW CONTROL VALVE AOV-FOO2B Reactor 4317 102' Yes C-36

/.FOO2A CRH AF201 CRH PUMP SUCTION FILTER AF201/ BF201 Reactor 4202 77' Yes C-71 CRH AF204 DRIVE WATER FILTER AF204 / BF204 Reactor 4319 102' Yes C-37 CRH AP207 DRIVE WATER PUMP AP207 / BP207 Reactor 4202 77' Yes C-72 CRH HV-4005 ISOLATION VLV MOV-HV-4005 Reactor 4104 54' Yes _ C-125 CRH HV-F003 PCV CONTROL VLV MOV-HV-FO03 Reactor 4317 102' Yes CRH CRDACCUM SAMPLING OF CRD ACCUMULATORS Reactor 4319 102' Yes C-33,34 CRH XV-126 SAMPLING OF CRD SCRAM INLET AND Reactor 4317 102' No 47 C-35,267 OUTLET VALVES 3 - 63

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HOPE CREEK GENERATING STATION July 1997 Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components 14__________

w' c~T& ~t ~Do ~ 4w ~ 5 ~~'~~~&N CSS AP206 CSS PUMP A/B/C/D P206 Reactor 4116 54' No 12 C-106,107,108, 110,11 CSS FO31A MOV F031A /B Reactor 4102 54' Yes C-45 CSS F005A MOV F005A /B Reactor 4329/4321 102' Yes C- 180, C-300 CSS IF004A MOV F004A/B Reactor 4329/4321 102' Yes IC-299 CSS F001A MOV FOOIA/B/C/D Reactor 4102 054' Yes DCP 10D410 CLASS 1E 125VDC BUS 10D410 DIV Control 5411 130' No 13 C-146,147 A/10D420 DIV B/ 10D430 DIV C/ Diesel 10D440 DIV D DCP 10D436 CLASS 1E 125VDC BUS 10D436 DIV Control 5607 160' No 14 C/10D446 DIV D Diesel DCP 1AD318 NON lE 125VDC DISTR PNL Aux/ 3449 124' No 34 C-307 IAD318/1 BD318/1 CD318/1DD318318 Rad I DCPI IAD417 125VDC IE PWR TO LOADS IN PNL Control 5411 130' No 15,5 C-143,144 1AD417/I BD417/ ICD417/I DD417 Diesel DCP IOD251 250 VDC MCC 1OD251/ 10D261 Reactor 4112/4108 54' No 16 C-57,67,68 DCP IOD450 CLASS 1E 25OVDC BUS IOD450 DIV A/ Control 5128(near) 54' No 7,5 IOD460 DIV B Diesel DCP IOD421 250 VDC BAT IOD421/ 10D431-DIV A Control 5104 54' Yes C-240,241 Diesel DCPI IAD411 125 VDC BAT IAD41 1-DIV A/I BD41 - Control 5539 146' No 18 C-129,131,132 DIV B/ ICD41 I-DIV C/I DD41 I-DIV D Diesel DCP ICD447 125 VDC BAT 1CD447-DIV C/ IDD447- Control 5614 163' Yes C-239 DIV D Diesel DCP 10D423 250 VDC BAT CHGR 10D423 /10D433 Control 5128(near) 54' No 20 C-242 Diesel . I 3 - 64

( ( (

July 1997 HOPE CREEK GENERATING STATION Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components x ' s $ : ~ . $: . s:.< y ~~~~~~~~...

DCP 1CD444 125 VDC BAT CHGR 1CD444/1 DD444 Control 5613/5607 163' Yes 5 C-238. C-296 Diesel DCPI 1AD413/1AD 125 VDC BAT CHGR 1A/B/C/DD413I Control 5538 146' No 19 C-126,127 414 1A/B/C/DD414 Diesel DCP! 10D422 FUSE SWTCH BOX 10D422-25OVDC A Control 5128(near) 54' Yes Diesel DCP 10D432 FUSE SWTCH BOX 10D432-25OVDC B Control CORDR 5128 54' Yes Diesel DCP 1AD412 FUSE SWTCH BOX 1AD412-125VDC A/l BD412-B/ Control multiple 146' Yes C-128 1CD412-C/ 1DD412-D Diesel DCP 1CD448 FUSESWTCH BOX 1CD448-125VDC C/ 1DD448-D Control 5613 160' Yes Diesel DGS 1AG400 DIVISION A DIESEL 1AG400/I BG400/1 CG400/ Control 5303 102' Yes C-89,90 1DG400 Diesel DGS I A-C420 EXCITER PANELS, 1A/B/C/D C420 Control 5303/5305 102' No 7 C-97 I Diesel I DGS AT403 FUEL STORAGE TANKS, A-HT403 Control 5110 54' Yes C-100 Diesel DGS HL-7530A SDG A/B/C/D DAYINK LVL SWTCH - Control 5303 102' Yes C-81,82 LSHL7530A/B/C/D Diesel DGS 1AP401 SDG A/B/C/D FOTPI 1AP401/ IBP401/ 1CP401/ Control 5107 54' Yes C-101 I 1DP401/1EP401 / 1FP401 / 1GP401 Diesel DGS IAP402 SDG A/B/C/D ELEC FUEL PMP 1AP402/ 1BP402/ Control 5303 102' Yes C-91 l1CP402/ 1DP402 Diesel 3 - 65

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July 1997 HOPE CREEK GENERATING STATION Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components PS7508A FUEL OIL PRESS SWTCH PSL7508A /B/C/D DG skid 5303 102' Yes DGS DGS 7534A EDLOS SOV7534A /B/C/D Control 5303 102' Yes C-88 Diesel I DGS 7535A SDG A SOV 7535A/B/C/D Control 5304/5307 102' Yes Diesel DGS 7536A SDG A SOV 7536A /B/C/D Control 5304/5307 102' Yes I_ Diesel DGS TV6606A ,-iERMSTAT CNTRL VLV TV 6606A/B/C/D Control 5303/5305 102' No 45, 46 Diesel DGS TV6618A THERMSTAT CNTRL VLV TV 6618A/B/C/D Control 5303/5305 102' No 45,46 C-276 Diesel DGS TV7722A THERMSTAT CNTRL VLV TV 7722AB/C/D Control 5303/5305 102' No 45, 46 C-92 Diesel DGS AT404 SDG A/B/C/D DAYTANK - AT404/ BT404/ CT404/ Control 5305 102 Yes C-79,80,83 DT404 Diesel DGS AT406 EDLOS MAKEUP TANK -AT406/1BT406/ CT406/ Control 5305 102' Yes DT406 Diesel DGS AT407 SDG A/B/C/D JWCL EXPANSION TNK -AT407/ Control 5303 102' Yes C-86,87 BT407/ CT407/ DT407 Diesel DGS AT408 SDG A/B/C/D START AIR RECEIVER - Control 5303 102' No 21 C-84,85 AT/BT/CT/DT/ET/FT/GT/HT 408 Diesel DGS 1DG403 NEUTRAL GROUNDING AND TFM - Control 5304 102' Yes c-98,99 t1A/B/C/DG403 Diesel I I 3 - 66

/

HOPE ,ýREEK GENERATING STATION

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July 19g97 Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components ESF :L1402A LEVEL XMTER SA-LI-402AB/E/F Reactor 4215 77' Yes ___C-269 ESF LINO9.1 A LEVEL XMTER BB-LI-N09,,A_/B/C/D/E/F/G/H LEVEL L2 Reactor 4215 77' Yes -269 C__

ESF LINO95B LEVEL XMTER BB-LI-N095B/D LEVEL L2 Reactor 4215 77' Yes 0-269 ESF PSNO5BA :PRESS SENSOR/XMTER E1 1-N058A/B/C/D Reactor 4215 77' Yes ESF PSNO9OA *PRESS SENSOR/XMT*ER B21-N090A /BIEIF/J/KIN/P Reactor 4215 77' Yes ESF PT4O3A PRESS .XMTERSA-PT-403A/B/E/!.F, Reactor 4215 77' Yes -269 C__

ESF PTNO94A IpRESS XMTER BB-PT.:N094A/B/C/D/E/F/G/H DW PRESS. Reactor 4605 162' Yes -38,41 C__

HPI 8278 MOV HV-8278 Reactor 4316 102' Yes HPI FOOl MOV HV-FOO1 Reactor 4111 54' Yes -62 C__

HPI F006 MOV HV-F006 Reactor 4329 102' Yes 0-174 HPI F042 iMOV HV-F042 Reactor 4102 54' Yes __

HPI 4880 MOV FV-4880 Reactor 4111 54' Yes HPI 4879 MOV FV-4879 Reactor 4111 54' Yes HPI F002 N.O. MOY HV-F002 Reactor 4220 102' Yes HPI FO03 N.O. MOV HV-F003 Reactor 4327 102' Yes 0-298 HPI F004 MOV HV-F004 Reactor ,4111 54' Yes ___

HPI F059 MOV HV-F059 Reactor 4111 54'i Yes 0-60 HPI F007 N.O. MOV HV-F007 Reactor 411 1 54' Yes -176 C__

HPI F071 N.O. MOV HV-F071 Reactor 4102 77' Yes HPI 0P204 HPCI TDP CR204, (cinl. pmop 0F21 7 & turbine 0S2 11) Reactor 4111 54' Yes 0-297 HPI LT4805 BJLT-4.805-1/2, SUPPRESSION POOL LEVEL TRANSMITTER Reactor 4115 54' Yes 0C-51,52 lAS P0V7668 SELF-CONTAINED VALVE P0V7668 Reactor 4317 102' Yes -268 C__

lAS 10-T106 EMERGENCY lAS AIR RECEIVER TANK Turbine 1401 120' No 34 ____

lAS 10-F104 IAS AIR DRYER Turbine 1401 120' No 34 ____

lAS I A-Ti 32 lAS AIR RECEIVER TANK Turbine 1401 120' No 34 ___

3 - 67

( J July 1997 HOPE CREEK GENERATING STATION Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components IGS 5125 AIR OPERATED VALVE 5125 Reactor 4413 132' Yes C-1 18 IGS AK202 COMPRESSOR AK202./.B.K202 Reactor 4413 132' Yes C-1 17 IGS 15126A MOV 5126 A/B Reactor 4329/4321 102' Yes IGS 5152A MOV 5152A/B. Reactor 4220 110' Yes C-301 IGS 5160A MOV 5160A/B Reactor 4412 132' Yes C-1 19 IGS BT-201 IGS RECEIVER BT-201 Reactor 4412 132' Yes C-42 IGS IAT-201 IGS RECEIVER AT-201 Reactor 4413 132' Yes IC-42 IGS AE-214 AFTERCOOLER MOISTURE SEPARATOR AE- Reactor 4413 132' Yes IGS AS-208 214/BE-214 IGS AIR DRYERS A.S-2./BS-208 Reactor 4413 132' Yes IGS IAF-216 IGS OUTLET FILTERS AF-216/BF-216 Reactor 4412/4413 132' Yes IGS AF-215 IGS INLET FILTERS AF-215/BF-215 Reactor 4412/4413 132' Yes IGS 5124A MOV 5124 A/B Reactor 4220 1203 Yes C-306 IGS 1A-C213 1A/B-C213, A AND B IGS CONTROL PANELS Reactor 4413 132' No 17 C-120 PCS HV-F028A HVFO28A/B/C/D - MAIN STEAM LINE Reactor /4316 102' Yes PCS HV-F022A ISOLATION VALVEI HVF022A/B/C/D - MAIN STEAM LINE Reactor 4220 102' Yes RAC 2601I AOV-2601 VALVE ISOLATION Reactor 4209-4210 77' Yes C-2 RAC 2617 AOV TV-2617 Reactor 4209 77' Yes C-78 RAC AE-214 ACOOLAE-217/ BE-217 Reactor 4211 77' No 30 C-77,270e271 RAC AP-209 RACS PUMP AP-209 / BP-209 Reactor 4209 77' No 24 C-1 3 - 68

( ( J.

HOPE CREEK GENERATING STATION July 1997 Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components RCI F010 MOV F010 Reactor 4110 54' Yes C-17 RCI F013 MOV F013 Reactor 4316 102' Yes RCI F031 MOV F031 Reactor 4102 54' Yes C-45 RCI F045 MOV F045 Reactor 4110 54' Yes _ C-19 RCI 4282 N.O. MOV HV-4282 Reactor 4110 54' Yes C-20 RCI 4283 MOV HV-4283 Reactor 4110 54' Yes C-21 RCI F008 N.O. MOV HV-F008 Reactor 4319 102' Yes RCI F012 N.O. MOV HV-F012 Reactor 4110 54' Yes C-18 RCI F059 N.O. MOV HV-F059 Reactor 4102 77' Yes RCI V012 TEST ISOLATION MOV IBDV-012 (FO02) Reactor 4203 77' Yes C-180 RCI 4405 SOV 4405 Reactor 4102 54' Yes RCI F019 SOV F019 Reactor 4102 54' Yes RCI 0F209 SUCTION STRAINER 0F209 Reactor Torus 54' Yes RCI OP203 TURBINE-DRIVEN PUMP- 0P203 (includes Reactor 4110 54' Yes C-16 Turbine 0S212)

RHS F075 MOV F075 Unknown 4208 93' Yes RHS AE 205 RHS HEAT EXCHANGER A/B E205 RHR Heat 4113/4109 54' Yes C-178,179 Exchanger Room RHS I A-P202 RHS PUMP A/B/C/D P202 Reactor 4115 54' No 25 C-48,55 RHS FO15A RHS MOV F015A/B Reactor 4321/4329 102' Yes C-174 RHS FO16A RHS-MOV-FO16A/B Reactor 4329 102' Yes C-175 RHS F017A RHS MOV FO17A /B/C/D Reactor 4321/4329 102' Yes RHS F021A RHS-MOV-FO21A/B Reactor 4329 102' Yes 3 - 69

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HOPE CREEK GENERATING STATION July 1997 Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components RHS F024A RHS MOV F024A /B Reactor 4102 54' Yes RHS F027A RHS MOV F027A /B Reactor 4102 77' Yes RHS F047A RHS MOV F047A /B Reactor 4214/4208 77' Yes C-177 RHS F006A RHS MOV F006A/B Reactor 4109 54' Yes C-176 RH$ FOO7A RHS MOV F007A /B/C/D Reactor 4102 54' Yes RHS FO08 RHS MOV F008 Reactor 4329 102' Yes C-175 RHS F009 RHS MOV F009 Reactor 4220 100' Yes RHS F048A RHS MOV F048A/B Reactor 4208 77' Yes RHS F004A RHS MOV F004A /B /C /D Reactor 4102 54' Yes RHS A-F211 RHS SUCTION STRAINER A/B/C/D-F211 Reactor Torus 54' Yes RHS F010 RHS RETURN TEST VALVES, HV-FO10A/B Reactor 4114/4107 54' Yes C-49 RWC FOO RWCU ISOLATION VALVE-F001 Drywell 4220 145' Yes SAC 2290A AOV HV2290A/B/C/D/E/F/G/H (RHR) Reactor 4113/4214/ 54' No 26 C-47 SAC 2292A AOV HV2292A /B (HPCI) Reactor 4111 54' Yes C-61 SAC 2293A AOV HV2293A/B (RCIC) Reactor 4110 54' No 27 C-63 SAC 2325A AOV HV2325A/B/C/D/E/F/G/H (CSS) Reactor 4116/4118 54' No 28 C-46,44,109,113,116 SAC 2395A AOV HV2395A/B/C/D (SAC) Control Diesel 5210/5211 77' Yes C-243 SAC 2398A AOV HV2398A /B/C/E,'E/F/G/H Control Diesel 5211 77' Yes C-103, 279, 280 SAC 2520A AOV 2520A/B/C/D Reactor 4113/4109 54' Yes C-50,54 SAC A1 E-201 HX A1/B1 E-201 Reactor 4307 102' Yes C-3,4,29 SAC A2E-201 HX A2/B2E-201 Reactor 4307 102' Yes C-3,4,29 SAC AP-210 SACS PUMP AP-210/ BP-210/ CP-210/ Reactor 4309 102' Yes C-6 I _ __ __ DP-210 I I I SAC 12512A MOV 2512A/B Reactor 4208 77' Yes Yes 4208 77' 3 - 70

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July 1997 HOPE CREEK GENERATING STATION Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components SAC 2520A SOV 2520A/B/C/D Reactor 4107/4114 54' Yes SAC AT205 SAC EXPANSION TANKS A/BT205 Reactor 4710 201' No 30 C-302 SAC 2496A-D TACS RETURN ISOLATION VALVES HV- Reactor 4307 102' Yes C-9 2496A-D SAC 2522A-D TACS SUPPLY ISOLATION VALVES HV- Reactor 4309 102' Yes C-10 2522A-D SAC A-BE-202 FUEL POOL HEAT EXCHANGERS Reactor 4627 162' Yes SAC IAC201 SAC CONTROL PANELS, 1A/B/C/D- Reactor 4309 102' No 34 C-C201 7.84272,273,2 74 SWS AP-502 SWS PUMP AP-502/ BP-502/ CP-502/ SWIS 208 93' Yes C- 155 DP-502 SWS AP-507 SWS-TWS PUMP AP-507 / BP-507/ CP- SWIS SWIS 77' Yes C-156 507/ DP-507 SWS 2197A STRNR MOV HV-2197A /B/C/D SWIS 0204 102' Yes SWS 2198A SWS MOV HV-2198A /B/C/D SWIS 0204 93', 102' Yes SWS 2225A SWS MOV HV-2225A/B/C/D SWIS 0204 93', 102' Yes SWS 2355-A MOV 2355-A /B Reactor 4307/4309 102' Yes C-30 SWS 2371-A MOV 2371 -A/B Reactor 4307/4309 102' Yes C-31 SWS HV-2207 AOV HV-2207 (RACS HX) Reactor 4309 102' Yes SWS HV-2346 MOV HV-2346 (RACS HX) Reactor 4211 77' Yes SWS HV-2203 SWS MOV HV-2203 Reactor 4309 102' Yes C-32 SWS HV-2204 SWS MOV HV-2204 Reactor 4307 102' Yes SWS SV-2247A SWS SV-2247A/B/C/D SWIS SWIS 102' Yes C-157 SWS AF-509 FILTER AF/BF/CF/DF-509 SWIS 99BYD 93' Yes C-154 SWS OT-543 TANK OT-543/545 SWIS SWIS 122' Yes SWS EP-AS501 SWS-TWS EP- SWIS SWIS 122' Yes

_AS501 /BS501 /CS501/DS501 I I 3 - 71

HOPE CREEK GENERATING STATION

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July 1997 Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components SWS F073 SW-RHR VALVES HV-F073/HV-F075 Reactor 4102/4209 77' Yes C-124 SWS PMPCNTRL SW PUMP CONTROL PANELS SWIS SWIS 110' No 5 C-165 SWS AC/EC 581 SWIS HVAC CONTROL PANEL AC/EC SWIS SWIS 93' No 8 581 SWS 1AC515/C SWTS CONTROL PANEL SWIS 0292 107' No 53 C515 1AC515/CC515 I SWS 1DC514 SW PUMP LUBE OIL CONTROL PANEL SWIS SWIS 102 Yes 1DC514 VAS AVH208AH HT EXCH A/BVH208 RCIC UNIT Reactor 4110 54' Yes C-64,65 1U COOLERS VAS AVH209AH HT EXCH A/BVH209 HPCI UNIT Reactor 4111 54' Yes U COOLERS VAS AVH210AH HT EXCH A/B/C/D/E/F/G/HVH210 Reactor 4107 54' Yes U RHR UNIT COOLERS I VAS AVH2 11 AH HT EXCH A/B/C/D/E/F/GVH211 CSS Reactor 4116/4118 54' Yes C-1 11,112 U UNIT COOLERS VAS AVH214AH HT EXCH A/B/C/DVH214 SACS UNIT Reactor 4307/4309 102' Yes U COOLERS VAS AVH208FA FAN A/BVH208 RCIC UNIT COOLER Reactor 4110 54' Yes N FANS VAS AVH209FA FAN A/BVH209 HPCt UNIT COOLER Reactor 4111 54' Yes IN FANS VAS AVH21OFA FAN A/B/C/D/E/F/G/HVH210 RHR Reactor 4107/4109 54' Yes C-53 N

_ UNIT COOLER FANS VAS AVH211 FA FAN A/B/C/D/E/F/GVH211 CSS UNIT Reactor 4116/4118 54' Yes C-111,I 12 iN COOLER FANS I VAS AVH214FA FANS A/B/C/DVH214 SACS UNIT Reactor 4309 102' Yes N COOLER FANS VAS TEMPSENS ITEMP. SENSORS FOR ROOM COOLER Reactor 4107/4110 54' Yes iC-1 14 3 - 72

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HOPE CREEK GENERATING STATION

( (

July 1997 Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components Z1.40.". J~ " --

VCA AVH400AHU CONTROL ROOM EMERGENCY FILTER Control Diesel 5602/ 155' Yes C-211,212,213 SYSTEMS AHU AVH400/BVH400 5630 VCA AVH407AHU CONTROL EQUIP. ROOM SUPPLY AHU Control Diesel 5703 178' Yes C-281,282,287 AVH407/BVH407 VCA AVH403AHU CONTROL ROOM SUPPLY SYSTEM AHU Control Diesel 5602/ 155' Yes AVH403/BVH403 5630 VCA AVH403FAN CONTROL ROOM SUPPLY SYSTEM FANS Control Diesel 5602/ 155' Yes AVH403/BVH403 5630 VCA AV415FAN CONTROL ROOM SUPPLY SYSTEM FANS Control Diesel 5630 155' Yes C-215 AV415/BV415 VCA AV400FAN CONTROL ROOM EMERGENCY FILTER Control Diesel 5602 155' Yes C-211,213 SYSTEM FANS AV400/BV400 VCA AVH403F FILTER AVH403/BVH403 Control Diesel 5602/ 155' Yes 5630 VCA AVH40ODF DOWNSTREAM FILTER AVH400/ BVH400 Control Diesel 5602/ 155' Yes 5630 VCA AVH40OUF UPSTREAM FILTER AVH400/BVH400 Control Diesel 5602/ 155' Yes 5630 VCA AVH407F FILTER A/BVH407 Control Diesel 5703 178' Yes C-283 VCA AVH400CF CHARCOAL FILTER AVH400 Control Diesel 5602 155' Yes VCA BVH400CF CHARCOAL FILTER BVH400 Control Diesel 5630 155' Yes VCA HD9593A DAMPER HD9593A/B Control Diesel 5630 155' No 32 C-227 VCA HD9594A DAMPER HD9594A/B Control Diesel 5630 155' No 32 C-218,219,226 VCA HD9588AA DAMPER HD9588AA/AB/BA/BB Control Diesel 5630 155' No 32 C-220 VCA HD9589A1 DAMPER HD9589AI / A2/B IB/B2 Control Diesel 5630 155' No 33 C-I_ I_ 1_ 1 1187,188,189,190 VCA HD9603A1 DAMPER HD9603A3 CNTRL EQUIP AREA Control Diesel 5703 178' No 48 C-I I I_ I I 92,193,284,285 3 - 73

f

( (

July 1997 HOPE CREEK GENERATING STATION Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components

" ft.. c c 't ~ . . ".~.% ~  :':~'

VCA HD9603B1 DAMPER HD9603B1/ B2/ B3 Control Diesel 5703 178' No 48 C-194 CNTRL EQUIP AREA VCA FD9589A DAMPER FD9589A/B Control Diesel 5602/5630 155' Yes VCA AVH407 FAN UNIT AVH407/ BVH407 Control Diesel 5703 178' Yes C-281,282 VCA FD9595A DAMPER FD9595A/B Control Diesel 5630 155' Yes C-214.225 VCA HD9595A DAMPER HD9595A /B Control Diesel 5630 155' Yes VCA PDD9587A DAMPER PDD9587A & B Control Diesel 5602 /5630 155' Yes C- 186,191 VDG AE412 HEAT EXCHANGER Control Diesel 5211 77' No 49 C-104 AE412/BE412/CE412/DE412/

EE412/FE412/GE412/HE412 I VDG D472A DAMPER Control Diesel Unknown 77' Yes C-278 D472A/D472B/D472C/D472D

/D472E/D472F/D472G/D472 H

VDG AV412 FAN Control Diesel 5208 77' Yes C-102 AV412/BV4I2/CV412/DV412

/EV412/FV412/GV412/HV412 VIS DS03A DAMPER DS03A SWIS SWIS 122' Yes

/D503B/D503CID503D VIS D504A DAMPER SWIS SWIS 122' Yes D504A/D504B/D504C/D504D III_

VIS AV503 FAN AV503 SWIS SWIS 122' No 30

/BVS03/CVS03/DV503 I I I 3 - 74

HOPE (A,EEK GENERATING STATION July 1997 Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components

. XMC

.. g "--- "."

VIS AV504 FAN AV5n0 BV504/CV504/DV504 SWIS SWIS 122' No 30 VlS 9773AI DAMPER TD9773A1I/B1I/C I/D1I SWIS SWlS, 122' Yes VIS 9773A3 DAMPER TD9773A3/B3/C3V./D3 SWIS SWIS 122' Yes VPR AVH408AH COOLING COIL AVH408/BVH408 Control Diesel 5620 163' Yes C-256 U

VPR GM497A DAMPER GM497A/B Control Diesel 5620 163' Yes VPR GM498A DAMPER GM498A /B Control Diesel 5620 163' Yes C-257 VPR GM499A DAMPER GM499A/B Control Diesel 5704 178' Yes VPR AVH408FA FAN AVH408 /BVH408 Control Diesel 5620 163' No 35 N I VPR AV416 FAN AV416/BV416 Control Diesel 5704 178' No 17 C-166 VPR AVH408F FILTER AVH408/BVH408 Control Diesel 5620 163' Yes C-256 VPR 9558A1 DAMPER HD9558A1/B1 Diesel 5620 160' Yes C-207 Generator Room VPR 9558A DAMPER FD9558A/B Diesel 5620 160' Yes Generator Room VSW AVH401AA HT EXCH Control Diesel 5606 163' Yes HU AVH401 A/BVH401 A/CVH401 A/DV H401 A VSW AVH401 BA HT EXCH Control Diesel 5606 163' Yes C-203A,259 HU AVH401 B/BVH401 B/CVH401 B/DV H401B (COIL B)

VSW AVH401FA FAN Control Diesel 5606 160' Yes C-158,204 N AVH401 /BVH401/CVH401 /DVH40

_______ ______________________ _______ _________________________________________________1___

3 - 75

( ( (

July 159~7 HOPE CREEK GENERATING STATION Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components zg M A.0 ..

VSW AV406FAN FAN AV4061BV406/CV406/DV406 Control Diesel 5606 160' No 11 C-206

_BATTERY ROOM VSW AVH401 F FILTER Control Diesel 5606 163' Yes C-259 AVH401 /BVH401 /CVH401 /DVH40 I

VSW 9547A DAMPER HD9547A /B/C/D Control Diesel 5606 160' Yes C-205 BATTERY ROOM VSW 9549A DAMPER HD9549A/B/C/D Control Diesel 5606 160' Yes C-203B VTS D505A DAMPER D505A SWIS TS Area 122' Yes VTS AV558FAN FAN AV558/BV558 SWIS TS Area 122' Yes VTS 9774AI DAMPER TD9774A1/B1/A2/B2 SWIS TS Area 122' Yes AP 1(T522 CONDENSATE STORAGE TANK YARD N/A GRADE No 36 C-151 1YF401 120V AC FUSE PANELS, IYF401-4 Control Diesel 5302 102' No 30 C-249,250 1OC620 HPCI RELAY VERTICAL BOARD Control Diesel 5302 102' No C-247,248 (H1 -P620)

IOC617 RHR&CS RELAY BOARDS (10-C617- Control Diesel 5302 102' No 5 C-245,246

41) ._

1OC621 RCIC RELAY VERTICAL BOARD Control Diesel 5302 102' No IOC628 ADS RELAY VERTICAL BOARDS Control Diesel 5302 102' No 5 10C399 AUXILIARY SHUTDOWN PANEL Aux/Rad 3579 137' No 39 C-i172,173 MISC 10651A-E OPERATORS CONSOLE Control Diesel 5510 137' No 5 MISC CEILING SUSPENDED CEILING Control Diesel 5510 137' Yes C-169,170 MISC INSTRUMRACKS INSTRUMENT RACKS Various N/A VARIOUS Yes C-69, 70, 269 STRUCTURES SEISMIC CATEGORY I CIVIL _ -- GRADE No --

STRUCTURES AND TURBINE

_BUILDING I 3 - 76

Hope Creek Nuclear Generating Station S&L Report No. SL-0 11553 Project No. 12800-217 Rev. 1 Seismic Walkdown Report ATTACHMENT 1B - BASE LIST 1B-SHUTDOWN COMPONENT LIST (UFSAR TABLE 9A-2)

TABLE 9A-2 SHUTDOWN COMPONENT LIST (BY SYSTEM)

Elec Mech. Room System Component Function Div. Div. No. P&ID IE Panel Room Chilled Water A GJ-AC487 Panel 5704 89-1 1E Panel Room Chilled Water A GJ-AK403 Control Area Chiller 5703 90-1-3 IE Panel Room Chilled Water A GJ-AP414 Chiller N20 Pump 5602 90-1-3 lE Panel Room Chilled Water A GJ-FT-9666Al Chw Loop A AK403 Outlet 5703 90-1-3 lE Panel Room Chilled Water A GJ-TV-9667A 1E Pnl Rm Clr AVH408 Byp 5620 90-1-1 IE Panel Room Chilled Water A GJ-TV-9768A RSP Room OOVH316 coolino Coll 5101 90-1-3 1E Panel Room Chilled Water B GJ-BC487 Panel 5704 P9-I IE Panel Room Chilled Water B GJ-BK403 Control Area Chiller 5703 90-1-3 1E Panel Room Chilled Water B GJ-BP414 Chilled H20 Pump 5703 90-1-3 IE Panel Room Chilled Water B GJ-FT-9666EI Chw Loop B BK403 Outlet 5703 90-1-3 1E Panel Room Chilled Water B GJ-TV-96675 1E Pnl Rm Clr BVH4081 Byp 90-1-3

+/-E Panel Room Chilled Water B GJ-TV-97686 RSP Room 00VH316 Cooling Coil 5501 90-1-3 1E Panel Room HVAC A GM-AC486 Control Panel 5620 88-1-1 1E Panel Room HVAC A 5,620 8x8-1-2 GM-AVH408 Supply Fan 5620 IE Panel Room HVAC A GM-FD-9558A Inlet Vanes 8R-1-2 1E Panel Room HVAC A 620 GM-FSL-9558A2 Air flow lE Panel Room HVAC A GM-FT-9558A Air Flow lE Panel Room HVAC A GM-HD-9558A1 Outside Air S8-1-2 1E Panel Room HVAC A GM-TE-9558A Discharge Temperature IE Panel Room HVAC A 5620 620 88-1-2 GM-TY-9558A Heater Control 88-1-2 lE Panel Room HVAC B 56U0 GM-BC486 Control Panel 88-1-I lE Panel Room HVAC B GM-BVH408 Supply Fan 5620 88-1-2 1E Panel Room HVAC B GM-FD-9558B Inlet Vanes 88-1-2 lE Panel Room HVAC B 5620 GM-FSL-9558B2 Air Flow 88-1-2 IE Panel Room HVAC B GM-FT-9558B Air Flow 5620 98-1-2 IE Panel Room HVAC B 5620 GM-HD-9558B1 Outside Air 96-I1-2 88-1-2 I Panel Room HVAC B 5620 GM-TE-9558B Discharge Temperature 5620 88-1-2 88-1-2 lE Panel Room HVAC B GM-TY-9558B Heater Control Control Area Chilled Water A GJ-AC490 Panel 5602 5602 90-1-1 Control Area Chilled Water A GJ-AK400 Control Area Chiller 5602 90-1-1 Control Area Chilled Water A GJ-AP400 Chilled H 2 0 Pump 90-1-1 Control Area Chilled Water 5602 A GJ-FT-9648A2 Cont Room Chiller Loop A 90-1-i Control Area Chilled Water A GJ-TE-9652AI Chilled Water Temp 5602 90-1-1 Control Area Chilled Water A GJ-TV-9634A Cont Equip Rm Clr AVH407 Bye 5602 90-1-1 Control Area Chilled Water A GJ-TV-9637A Cent Room Clr AVH403 Byp 5630 90-1-1 Control Area Chilled Water B GJ-BC490 Panel 5630 90-1-2 Control Area Chilled Water B GJ-BK400 Control Area Chiller B 5630 90-1-2 Control Area Chilled Water GJ-BP400 Chilled H20 Pump 90-1-2 Control Area Chilled Water B 5630 GJ-FT-9648B2 Cont Room Chiller Loop B 90-1-2 Control Area Chilled Water B GJ-TE-9652B1 Chilled Water Temp 5630 90-1-2 Control Area Chilled Water B GJ-TV-9634B Cont Equip Rm Clr BVH407 Byp 5703 90-1-2 1 of 16 HCGS-UFSP3 Revision 0 April I, 1988

TABLE 9A-2 (Cont)

Elec Mech. Room System Component Function Div. Div. No. P&ID Control Area Chilled Water B GJ-TV-9637B Cont Room Clr BVH403 Byp 5630 90-1-2 Control Area HVAC A GK-ABH407 Control Equip Supply 5703 89-1 Control Area HVAC A GK-FSL-9603A2 CERS AVH407 Discharge Air 5703 89-1 Control Area HVAC A GK-FT-9603A CERS AVH407 Supply Air 5703 89-1 Control Area HVAC A GN-HD-9603AI CERS AVH407 Outside Air 5703 89-1 Control Area HVAC A GK-HD-9603A2 CERS AVH407 Supply Air 5703 89-1 Control Area HVAC A GK-HD-9603A3 CERS AVH407 Return Air 5703 89-i Control Area HVAC A GK-TE-9603A CERS AVH407 Supply Air 5704 89-i Control Area HVAC A GK-TT-9603A CERS AVH407 Supply Air 5704 89-1 Control Area HVAC A GK-TY-9603A CERS AVH407 Supply Air 5703 89-i Control Area HVAC B GK-BVH407 Control Equip Supply 5703 89-1 Control Area HVAC B GK-FSL-9603B2 CERS BVH407 Discharge Air 5703 89-1 Control Area HVAC B GK-FT-9603B CERS BVH407 Supply Air 5703 89-1 Control Area HVAC B GK-HD-9603BI CERS BVH407 Outside Air 5703 89-1 Control Area HVAC B GK-HD-9603B2 CERS BVH407 Supply 5703 89-1 Control Area HVAC B GK-HD-9603B3 CERS BVH407 Return Air 5703 89-1 Control Area AVAC B GK-TE-9603B CERS BVH407 Supply Air 5703 69-1 Control Area HVAC B GK-TT-9603B CERS BVH407 Supply Air 5703 89-1 Control Area HVAC B GK-TY-9603B CERS BVH407 Supply Air 5703 89-1 Control Room HVAC A GE-AC485 Control Area HVAC Panel 5602 89-1 Control Room HVAC A GK-AV415 Control Room Exhaust Fan A 5602 89-1 Control Room HVAC A GK-AVH4 03 Control Room Supply 5602 89-1 Control Room HVAC A GK-FD-9598A Fan Inlet Vanes 5602 89-1 Control Room HVAC A GK-FSL-9587A Control Room AV415 Air Flow 5602 89-1 Control Room HVAC A GK-FSL-9589 A2 CRS AVH403 Heating Coil 5602 89-1 Control Room HVAC A GK-FT-9589A CRS AVH403 Supply air 5602 89-1 Control Room HVAC A GK-HD-9589Al MCR Exhaust Damper 5602 89-1 Control Room HVAC A GK-HD-9589A1 CRS AVH403 Return Air 5602 89-1 Control Room HVAC A GK-HD-9569A2 MCR Supply Damper 5602 89-1 Control Room HVAC A GK-PDD-9587A CRS AVH403 Pressure Control 5602 89-1 Control Room FVAC A GK-PDT-9587A CRS Fan Inlet Dif Pressure 5602 89-1 Control Room HVAC A GK-SV-9588AA Control Room Isol Ch C 5602 89-1 Control Room HVAC A GK-SV-9588AB Control Room Isol Ch D 5602 89-1 Control Room HVAC A GK-TE-9589A CRS AVH403 Supply Air 5602 89-1 Control Room HVAC A GK-TE-9589Al CRS AV4403 Supply Air 5510 89-1 Control Room HVAC B GK-BC485 Control Area HVAC Panel 5630 89-1 Control Room HVAC B GK-BV4]5 Control Room Exhaust Fan B 5630 89-I Control Room EVAC B GK-BVH403 Control Room Supply 5630 89-1 Control Room HVAC B GK-FD-9598B Fan Inlet Vanes 5630 89-i Control Room HVAC B GK-FSL-9587B Control Room BV415 Air Flow 5630 89-1 Control Room HVAC B GK-FSL-9589B2 CRS HVH403 Heating Coil 5630 89-1 Control Room HVAC B GK-FT-95898 CRS BVH403 Supply Air 5630 89-1 Control Room HVAC B GK-HD-9569BI MCR Exhaust Damper 5630 89-1 Control Room HVAC B GK-HD-9589BI CRS BVH403 Return Air 5630 89-i Control Room HVAC B GK-RD-958922 MCR Supply Damper 5630 89-1 2 of 16 HCGS-UFSAR Revision 6 October 22, 1994

TABLE 9A-2 (Cont)

Elec Mech. Room System Component Function Div. Div. No. P&ID Control Room HVAC B GK-PDD-9587B CRS BVH403 Pressure Control 5630 89-1 Control Room HVAC B GK-PDT-9587B CRS Fan Inlet Dif Pressure IT 5630 89-2 Control Room HVAC B GK-SV-9588BA Control Room Isol Ch C TI 5630 89-1 Control Room HVAC B GK-SV-9588BB Control Room Isol Ch D 5630 89-1 Control Room HVAC B GK-TE-9589B CRS BVI4403 Supply Air II 5630 09-1 Control Room HVAC B GK-TE-9589B1 CRS BVH403 Supply Air II 5510 89-1 Core Spray Loop I BE-AP206 Core Spray Pump A 4118 52-1 Core Spray Loop I BE-CP206 Core Spray Pump C 411C Core Spray Loop I 52-1 BE-FT-NO03A Loop I Flow 4116 Core Spray Loop ! BE-HV-FO0IA Pump A Torus Suction 4102 Core Spray Loop I BE-HV-FCO3C Pump C Torus Suction II 52-1 4102 Core Spray Loop I BE-HV-FO04A Loop I Injection I 52-1 4102 Core Spray Loop I BE-HV-FOOSA Loop I Injection IIT1 I2-1 4329 52-3 Core Spray Loop I BE-HV-POI5A Test return to Torus I 4102 Core Spray Loop I BE-HV-F031A Min Flow Bypass I 52-1 4102 Core Spray Loop II BE-SP206 Core Spray Pump B I IPSI 52-1 4104 Core Spray Loop II BE-DP206 Core Spray Pump D I 52-1 4105 Core Spray Loop Ii BE-FT-NO03B Loop II Flow IT 52-1 4105 Core Spray Loop II BE-HV-FO01B Pump B Torus Suction IT 52-1 4102 Core Spray Loop II BE-HV-F0O1D Pump D Torus Suction I1 52-i 4102 Core Spray Loop II BE-HV-FO04B Loop II Injection II 52-1 4321 Core Spray Loop II Loop II Injection II 52-1 BE-HV-F005B 4321 Core Spray Loop II BE-HV-F015B Test return to Torus I 52-1 4102 Core Spray Loop It BE-EV-FO3lB Min Flow Bypass II 52-1 4104 CRD Hydraulics BF-SV-117 Pilot Scram Valve (Type of 93) II 52-1 4328 47-1 CRD Hydraulics BF-SV-117 Pilot Scram Valve (Type of 92) 4320 47-1 DG Room Recirc Sys A iI GK-AC483 Panel 5704 DG Room Recirc Sys A IiI 88-1-1 GM-AV412 Diesel Gen Room Recirc Fan 5211 DG Room Recirc Sys A GM-EV412 Diesel Gen Room Recirc Fan II 88-1-1 5211 DG Room Recirc Sys A GM-FSL-9557A Air Flow Low ItS 88-1-1 5307 DG Room Recirc Sys A GM-FSL-9557E Air Flow Low RPSI 5307 86-1-1 Room Recirc DG Room Sys A DG Recirc Sys A GM-TS-9557A Diesel Room Temperature II 5307 88-1-i DG Room Recirt Sys B GM-TS-9557E Diesel Room Temperature II 5307 88-1-1 Dr Room Recirc Sys B GK-BC483 Panel 86-1-1 5703 DG Room Recirc Sys B GM-BV412 Diesel Gen Room Recirc Fan 66-1-1 II 5209 DG Room Recirc Sys B GM-FSL-9557B Air Flow Low 5209 88-1-1 I 69-i-1 DG Room Recirc Sys B GM-FSL-9557F Air Flow Low 5209 DG Room Recirc Sys B GM-FV412 Diesel Gen Room Recirc Fan I 8R-1-1 5209 DG Room Recirc Sys B GM-TS-9557B Diesel Room Temperature 5305 88-1-1 DG Room Recirc Sys C GM-TS-9557F I! 8R-1-1 Diesel Room Temperature 5305 DG Room Recirc Sys C GK-CC483 Panel 5704 88-1-i DG Room Recirc Sys C GM-CV412 Diesel Gen Room Recirc Fan 5210 86-1-1 DG Room Recirc Sys C GM-FSL-9557C Air Flow Low 5306 DG Room Recirc Sys C GM-FSL-9557G Air Flow Low 5306 88-1-1 66-1-1 GM-GV4!2 Diesel Gen Room Recirc Fan 5210 88-1-1 3 of 16 HCGS-UFSAR Revision 0 April 11, 16q0

TABLE 9A-2 (Cont)

Elec Mech. Room System Component Function Div. Div. No. P&I D DG Room Recirc Sys C GM-TS-9557C Diesel Room Temperature 5306 88-1-i DG Room Recirc Sys C GM-TS-9557G Diesel Room Temperature 5306 88-1-i DG Room Recirc Sys D GK-DC483 Panel 5703 88-1-i DG Room Recirc Sys 0 GM-DV412 Diesel Gen Room Recirc Fan 52D8 88-1-1 130-DG Room Recidr Sys D CM-FSL-9557D Air Flow Low 5208 38-1-1 DG Room Recirc Sys D GM-FSL-9557H Air Flow Low 5208 88-1-1 DG Room Recirc Sys D GM-HV412 Diesel Gen Room Recire Fan 5208 88-1-1 DG Room Recirc Sys D GM-TS-9557D Diesel Room Temperature 5304 88-1 DG Room Recirc Sys D GM-TS-9557H Ciesel Room Temperature 5304 88-1 Diesel Generators -A KJ-1AC422 Generator Panel 5416 30-1 Diesel Generators -A KJ-1AC423 Diesel Panel 5416 30-1 Diesel Generators -A KJ-AG400 DG and Auxiliaries 5307 30-1 Diesel Generators -A KJ-AP401 Fuel Transfer Pump 5110 30-1 Diesel Generators -A KJ-BP401 Fuel Transfer Pump 5110 30-1 Diesel Generators -B KJ-1BC422 Generator Panel 5412 30-i Diesel Generators - B KJ-lBC423 Diesel Panel 5412

-B 30-1 Diesel Generators -B KJ-BG4 00 DG and Auxiliaries 5305 Diesel Generators KJ-CP401 Fuel Transfer Pump 5108 30-1 Diesel Generators -B KJ-DP401 Fuel Transfer Pump 5108 30-1 Diesel Generators -C KJ-1CC422 Generator Panel 5414 30-1 Diesel Generators -C KJ-1CC423 Diesel panel 5414 30-1 Diesel Generators -C KJ-CG400 DG and Auxiliaries 5306 30-1 Diesel Generators -C KJ-EP401 Fuel Transfer Pump 5109 30-1 Diesel Generators -C KJ-FP401 Fuel Transfer Pump 5109 30-1 Diesel Generators -D KJ-IDC422 Generator Panel 5410 30-1 Diesel Generators -D KJ-IDC423 Diesel Panel 5410 30-1 Diesel Generators -D KJ-DG400 DG and Auxiliaries 5304 30-1 Diesel Generators -D KJ-GP401 Fuel Transfer Pump 5107 30-1 Diesel Generators -D KJ-HP401 Fuel Transfer Pump 5107 Electrical Power - Div I PB-10A401 4.16 kV Swgr 5417 NA Electrical Power - Div I PB-I0A403 4.16 kV Swgr 5415 NA Electrical Power - Div I PH-10B212 480 V MCC 4309 NA Electrical Power - Div I PH-10B232 480 V MCC 4310 NA Electrical Power - Div I PG-10B410 480 V Swgr 5417 NA Electrical Power - Div I PH-10B411 480 V MCC 5417 NA Electrical Power - Div I PG-10B430 480 V Swgr 5415 NA Electrical Power - Div I PH-10B431 480 V MCC 5415 NA Electrical Power - Div I PG-10B450 480 V Swgr 5417 NA Electrical Power - Div I PH-100451 480 V MCC 5417 NA Electrical Power - Div I PG-10B470 480 V Swgr 5415 NA Electrical Power - Div I PH-105471 480 V MCC 5415 NA Electrical Power - Div I PH-10B553 480 V MCC 203 NA Electrical Power - Div I PH-10B573 480 V MCC 203 NA Electrical Power - Div I PJ-10D251 250 V DC MCC 4112 NA Electrical Power - Div I PK-10D410 125 V DC Swgr 5417 N-A 4 of 16 HCGS-UFSAR Revision 0 April 11, 1981

TABLE 9A-2 (Cont)

Elec Mech. Roos System Component Function Div. Div. No. PtID Electrical Power - Div PJ-10D421 250 V DC Batteries 5104 NA Electrical Power - Div PJ-10D423 250 V DC Battery Chargers 5129 NA Electrical Power - Div PX-10D430 125 V DC Swgr 5415 NA Electrical Power - Div PK-10D436 125 V DC Swgr 5613 NA Electrical Power - Div PJ-10D450 250 V DC Swgr 5129 NA Electrical Power - Div PK-1AD411 125 V DC Batteries 5545 NA Electrical Power - Div PK-lAD413 125 V DC Battery Chargers 5544 NA Electrical Power - Div PK-IAD414 125 V DC Battery Chargers 5544 NA Electrical Power - Div PK-1AD417 125 V DC Dist Panel 5417 NA Electrical Power - Div PN-IAD481 120 V AC Power 5501 NA Electrical Power - Div PN-lAD482 120 V AC Power 5616 14A Electrical Power - Div PN-1AJ481 120 V AC UPS Dist Pnl 5501 NA Electrical Power - Div PN- IAJ4 82 120 V AC UPS Dist Pnl 5616 NA Electrical Power - Div PK-1CD411 125 V DC Batteries 5543 NA Electrical Power - Div PK-ICD4!3 125 V DC Battery Chargers 5542 NA Electrical Power - Div PK-ICD414 125 V DC Battery chargers 5542 NA Electrical Power - Div PK-ICD417 125 V DC Dist Panel 54i5 NA Electrical Power - Div PK-ICD444 125 V DC Battery Chargers 5613 NA Electrical Power - Div PK-ICD447 125 V DC Batteries 5614 NA Electrical Power - Div PN-1CD481 120 V AC Power 5501 NA Electrical Power - Div PN-ICD482 120 V AC Power 5613 NA Electrical Power - Div PN-ICJ7481 120 V AC UPS Dist Pni 550i NA Electrical Power - Div PN-ICJ482 120 V AC UPS Dist Pnl 5613 NA Electrical Power - Div P1-1 FF4l01 120 V AC Fuse Pnl 5302 NA Elec~rical Power - Div PN-IYF403 120 V AC Fuse PnI 5302 NA Electrical Power - Div PB-IOA402 4.16 kV Swgr 5413 NA Electrical Power - Div PB-i0A404 4.16 kV Swgr 5411 NA Electrical Power - Div P2-10B222 480 V MCC 4303 NA Electrical Power - Div PH-10B242 480 V MCC 4201 NA Electrical Power - Div PG-10B420 480 V Swgr 5413 NA Electrical Power - Div PH-10421 480 V MCC 5413 NA Electrical Power - Div PG-10B440 480 V Swgr 5411 NA Electrical Power - Div PH-IOB441 480 V MCC 5411 NA Electrical Power - Div PG-10460 480 V Swgr Electrical Power - Div 5413 NA PH-10B461 480 V MCC 5413 Electrical Power - Div NA PG-10B480 480 V Swgr 5411 Electrical Power - Div NA PH-10B481 480 V MCC 5411 Electrical Power - Div NA PH-10B563 480 V MCC 207 Electrical Power - Div 207 NA PH-10B583 480 V MCC Electrical Power - Div NA PJ-10D261 250 V DC MCC 4108 Electrical Power - Div NA PK-10B420 125 V DC Swgr Electrical Power - Div 5413 NA PJ-10D431 250 V DC Batteries 5128 Electrical Power - Div N'A PJ-10D433 250 V DC Battery Chargers 5130 Electrical Power - Div NA PK-10D440 125 V DC Swgr 5411 Electrical Power - Div NA PK-10D446 125 V DC Swgr 5607 5 of 16 HCGS-UFSAR Revision C April 11, 1988

TABLE 9A-2 (Cont) lec Hech. Room System Component Function Div. Div. No. P&IL' Electrical Power - Div II PJ-10D460 250 V DC Swgr 1- II 5130 NA Electrical Power - Div II PK-iBD411 125 V DC Batteries Ii Ii 5541 NA Electrical Power - Div IT PK-IBD413 125 V DC Battery Chargers II II 5540 NA Electrical Power - Div II PK-IBD414 125 V DC Battery Chargers IT II 5540 NA Electrical Power - Div II PK-IBD417 125 V DC Dist Panel LI LI 5413 NA Electrical Power - Div II PN-1BD481 120 V AC power II LI 5448 NA Electrical Power - Div II PN-IBD482 120 V AC power II LI 5615 NA Electrical Power - Div II PN-IBJ481 120 V AC UPS Dist Pnl II LI 5448 NA.

Electrical Power - Div II PN-1BJ482 120 V AC UPS Dist Pnl I1 II 5615 NA Electrical Power - Div II PK-IDD411 125 V DC Batteries II ii 5539 NA Electrical Power - Div II PK-1DD413 125 V DC Battery chargers II iI 5538 NA Electrical Power - Div II PK-1DD414 125 V DC Battery chargers II II 5538 NA Electrical Power - Div II PK-IDD417 125 V DC Dist Panel II II 5411 NA Electrical Power - Div II PK-1DD444 125 V DC Battery Chargers Ii II 5607 NA Electrical Power - Div II PK-IDD447 125 V DC Batteries I1 II 5609 NA Electrical Power - Div II PM-IDD481 120 V AC Power Ii IL 5448 NA Electrical Power - Div II PN-IDD482 120 V AC Power II IH 5607 NA Electrical Power - Div Ii PN-IDJ481 120 V AC UPS Dist Pno II II 5448 NA Electrical Power - Div Ii PN-1DJ482 120 V AC UPS Dist Pno II Ii 5607 NA Electrical Power - Div Ii PN-IYF402 120 V AC Fuse Pnl II I! 5302 NA Electrical Power - Div II PN-IYF404 120 V AC Fuser Pnl II II 5302 NA Feedwater AE-HV-F011A FW Iso Inside Containment I 1 4220 41-1-1 Feedwarer AE-HV-FO11B FW Iso Inside Containment I I 4220 41-1-1 Feedwater AE-HV-4144 FW Line Cross Tie Isol Vlv I I 4316 41-1-1 HPCI BJ-0204 Main HPCI Pump I I 4111 56-1 HPCI BJ-DP217 HPCI Booster pump I I 4111 56-1 HPCI BJ-AP228 HPCI Jockey pump I I 4111 56-1 HPCI BJ-HV-8278 HPCI Injection to FW I L 4316 55-1 HPCI BJ-HV-F004 Suction from CST I 1 4111 55-1 HPCI BJ-HV-F006 HPCI Injection to CS I T 4329 55-1 HPCI BJ-HV-F007 HPCI Pump Discharge Vlv I T 41i1 55-1 HPCI BJ-IIV-F008 Test return to CST I i 4203 s5-1 HPCI BJ-HV-FO12 Min Flow Bypass 2 1 4102 55-HPCI BJ-HIV-F042 Suction from Torus 1 1 4102 55-1 HPCI BJ-HV-F059 Water to HPCI Condenser I I 4111 55-I HPCI eJ-PT-N050 Pump Discharge Pressure I I 4112 55-1 HPCI BJ-PT-N053 HPCI Pump Suction Pressure I I 411i 55-i HPCI - Leak Detection SK-TE-N025A Pipe Tunnel I I 4327 HPCI - Leak Detection SK-TE-N025C Pipe Tunnel I I 4227 25-1-2 HPCI - Leak Detection SK-TE-N025E Torus Area I 1 4102 1 HPCI - Leak Detection SK-TI-N025G Torus Area I I 4102 25-1-2 HPCI - Leak Detection SK-TI-N025J Torus Area 1 1 4102 25-1-2 HPCI - Leak Detection SK-TE-N025L Torus Area I 1 410 5-HPCI - Leak Detection SK-TE-N025N Tcrus Area I I 4102 25-1-3 HPCI - Leak Detection SK-TE-N025R Torus Area I I 4102 ,5-1-2 1PCI - Leak Detection SK-TE-N028A Supply Duct 11 4111 25--2 HPCI - Leak Detection SK-TE-N028C Supply Duct I 2 4111 25-1-2 6 of 16 HCGS-UFSAR Revision 18 May 10, 2011

TABLE 9A-2 (Cant)

Elec mech. Room System Component Function Div. Div. P5o. P&ID HPCI - Leak Detection SK-TE-NO29A Exhaust Duct 4111 25-1-2 HPCI - Leak Detection SK-TE-N029C Exhaust Duct 4111 25-1-2 HPCI - Leak Detection SK-TE-NC30A Energ Unit Cooler 4111 25-1-2 HPCI - Leak Detection SK-TE-N030C Energ Unit Cooler 4111 25-i-2 HPCI Steam 4111 FD-OP215 Condensate Pump 56-1 HPCI Steam 41i1 FD-0P216 Vacuum Pump 56-1 (PCI Steam FD-OS211 HPCI Turbine 4111 56-1 HPCI Steam FD-FT-14003 HPCI Pump Disch Flow 4112 55-1 HPCI Steam FD-FV-4879 HPCI Turb Control Valve 4111 56-1 HPCI Steam FD-EV-4880 HPCI Turb Stop Valve 4111 56-1 F(PCI Steam FD-NV-F00I HPCI Steam Isol Valve 4111 51-1 HPCI Steam FD-HV-F002 HPCI Steam Isol Valve 44 220 Ill 55-1 HPCI Steam FD-HV-F003 HPCI Steam Isol Valve 4327 55-1 HPCI Steam FD-f-V-POll HPCI Steam Exh Tsol Valve 4102 55-1 HPCI Steam FD-HV-FO75 HPCI Vacuum Isol Valve 4102 55-1 HPCI Steam FD-HV-F079 HPCI Vacuum Isol Valve 4102 55-1 HPCI Steam FD-PDT-NOS7A High Steam Flow 4215 55-1 HPCI Steam FD-PDT-N057C High Steam Flow 4219 55-I HPCI Steam FD-PT-NO55A Turb Exhaust Vent 4209 56-1 HPCI Steam FD-PT-N055C Turb Exhaust Vent 4209 56-i HPCI Steam FD-PT-NO55E Turb Exhaust Vent 4209 56-1 HPCI Steam FD-PT-NO55G Turb Exhaust Vent 4209 16-1 HPCI Steam FD-PT-N056A Exhaust High Pressure 56-1 4112 HPCI Steam ED-PT-NO56E Exhaust High Pressure 4112 56-1 HPCI Steam 4315 ED-PT-NOS8A HPCI Steam Pressure Trip 4215 55-1 HPCI Steam FD-PT-NM58C HPCI Steam Pressure 5S-i 511-i HPCI Steam FD-PT-N058E HPCI Steam Pressure 4215 55-1 HPCI Steam FD-PT-N058G HPCI Steam Pressure 42A9 Main Steam - Div I AB-SV-3673B For Inboard MSIV AB-HV-F022A 4220 Main Steam - Div I AB-SV-3675B 41-1-1 For Inboard NSTV AB-HV-P022B 4120 Main Steam - Div I AB-SV-3677B For Inboard MSIV AB-HV-F022C 41-1-1 4220 Main Steam - Div i AB-SV-3679B For Inboard MSiV AB-HV-PO2ID 4220 4 1-1-1 Main Steam - Div II AB-SV-3674B For Outboard MSIV AB-HV-FO28A 41-1-2 4316 Main Steam - Div II AB-SV-36760 For Outboard MSIV AS-HV-FO2PB 4 1-1-1 4316 Main Steam - Div II AB-SV-3678B For Outboard MSIV AB-HV-F028C 4 1-1-1 4316 Main Steam - Div II AB-SV-3680B For Outboard MSIV AB-HV-FO28BD 41-1-1 4316 Nuclear Boiler AB-HV-F016 Inboard MSIV Drain 41-1-2 4220 41-1-1 Nuclear Boiler AB-HV-F019 Inboard MSIV Drain 41-1-1 4316 Nuclear Boiler Inst (RSP) BB-LT-7854 Reactor Level 4105 42-1-1 Nuclear Boiler Inst (RSP) BB-PT-7853A Reactor Pressure 4215 4 2-1-i Nuclear Boiler Inst (RSP) BB-PT-7853D Reactor Pressure 4202 Nuclear Boiler Inst (RSP) BB-LT-7854-1 Reactor Level 42-1-1 Nuclear Boiler Inst - I BB-LR-R623A Reactor Level Ch A 4203 42-1-1 5510 Nuclear Boiler Inst - I BB-LT-N091A Reactor Level 4215 4 215 I

Nuclear Boiler Inst - I BB-LT-3682A Reactor Level Nuclear Boiler Inst - I 4 2-1-1 42-1-1 BB-LR-3682A-1 Reactor Level Ch A 5510 Nuclear Bailer Inst - I 5510 4 2-1-1 BB-LI-3682A Reactor Level Ch A 7 of 16 HCGS-UFSAR Revision 18 May 10, 2011

TABLE 9A-2 (Cont)

Elec Mech. Room System Component Function Div. Div. No. P&ID Nuclear Boiler Inst - I Nuclear Boiler inst - I Nuclear Boiler Tnst - I Nuclear Boiler Inst - I BB-PT-3684A BB-PI-3684A BB-PR-R623A BB-PT-N078A Reactor Pressure Reactor Pressure Ch A Reactor Pressure Ch A Reactor Pressure 4215 5510 5510 4215 42-1-1 42-1-1 42-1-1 42-1-I I

Nuclear Boiler inst - II BB-LR-R623B Reactor Level Ch B 5510 42-1-1 Nuclear Boiler Inst - II BB-LT-N091B Reactor Level 4203 42-1-1 Nuclear Boiler Inst - II BB-PR-R623B Reactor Pressure Ch B 5510 42-1-1 Nuclear Boiler Inst - II BB-PT-N078B Reactor Pressure 4203 42-1-1 Pri Cont Ins- Gas - Div I KL-EV-5126A Supply Header Outboard Isln 4329 59-1-1 Pri Cont inst Gas - Div I KL-HV-5152A Supply Header Inboard Isin 4220 59-1-1 Pri Cont Inst Gas - Div II KL-HV-5126B Supply Header Outboard Isln 4321 59-1-1 Pri Cont Inst Gas - Div II KL-HV-5152B Supply Header Inboard Isln 4220 59-1-1 PCIC BD-OP203 RCIC pump 4110 50-i RCIC BD-BP228 RCIC Jockey pump 4110 50-1 RCIC BD-HV-F010 Suction From CST 4110 49-1 RCIC BD-HV-F012 Pump Disch 4110 49-1 RCIC BD-HV-F013 RCIC Injection Valve 4316 49-1 RCIC BD-HV-F022 RCIC Return to CST 4106 49-1 RCIC BD-HV-F031 Suppression Pool Suction 4102 49-1 RCIC BD-HV-F046 Water to RCIC Condenser 4110 50-1 RCIC BD-PT-NO50 To PTSH-N650 4108 49-1 RCIC BD-PT-N053 To PISH-N653 4210 50-RCIC BD-SV-F019 Min Flow Valve 4102 49-1 RCIC - Leak Detection SK-TE-ND21B Supply Duct 4110 25-1-?

RCIC - Leak Detection SK-TE-N021D Supply Duct 4110 5 RCIC - Leak Detection SK-TE-N022B Exhaust Duct 4110 RCIC - Leak Detection SK-TE-N022D Exhaust Duct 4110 25-1-2 RCIC - Leak Detection SK-TE-N0D23B Energ Unit Cooler 41i0 RCIC - Leak Detection SK-TE-N023D Energ Unit Cooler 4110 25-1-2 RCIC - Leak Detection SK-TE-N025B Pipe Tunnel 25-1-2 RCIC - Leak Detection SK-TE-N025D Pipe Tunnel 41.02 5-19 RCIC - Leak Detection SK-TE-N025F Torus area 4102 45- 1 RCIC - Leak Detection SK-TE-ND25H Torus Area RCtC - Leak Detection SK-TE-N025K Torus Area 4102 50 10 RCIC - Leak Detection SK-TE-N025M Torus Area 4102 49 RCOC - Leak Detection SK-TE-N05P Torus Area 4102 RCIC - Leak Detection SK-TE-N0255 Torus Area 4102 RCIC Steam FC-OP219 RCIC Gland Seal Pump 4110 RCiC Steam FC-OP220 RCIC Condensate Pump 4110 50- 1 RCIC Steam FC-OS212 RCIC Turbine 4110 RCIC Steam FC-FT-NO03 RCIC Pump Discharge Flow 4108 RCTC Steam FC-HV-4282 RCIC Turbine Trip/Thrtl Valve 4110 RCTC Steam FC-HV-4283 RCIC Turbine Gay Valve 4110 RCTC Steam FC-HV-F007 Inboard Iso Steam 4 2 -)D RCIC Steam FC-HV-F008 Outboard Iso Steam 4319 PCIC Steam FC-HV-F045 RCIC Turbine Steam Stop Vlv 4110 50-1 RCIC Steam FC-HV-F059 RCIC Steam Exh Isol Valve 4102 49-1 RCIC Steam FC-HV-F060 RCIC Vac Pump Discharge Valve 4102 49-1 8 of .16 HCGS-UFSAR Revision 18 May 10, 2011

TABLE 9A-2 (Cont)

Elec Mech. Room System Component Function Div. Div. No. P&aD RCIC Steam FC-HV-F062 RCIC Vac Brkr Isol Valve 4i02 49-1 RCIC Steam FC-HV-F076 Iso Valves Bypass 49-1 4220 RCIC Steam FC-HV-FO84 RCIC Vac Brkr Iso] Valve 4102 49-1 RCIC Steam FC-PT-NO55B Vent Pressure Trip 4205 50-1 RCIC Steam FC-PT-NO55D Vent Pressure Trip 4202 50-1 RCIC Steam FC-PT-N055F Vent Pressure Trip 4203 50-1 RCIC Steam FC-PT-NO55H Vent Pressure Trip 4201 50-I RCIC Steam FC-PT-NO56B RCIC Turbine Exhaust Press 4108 50-1 RCIC Steam FC-PT-N4056F RCIC Turbine Ezhaust Press 4108 50-1 RCIC Steam PC-PT-NO57B Steam High Flow 4203 49-1 RCIC Steam FC-PT-N051D Steam High Flow 4202 49-1 RCIC Steam FC-PT-NO58B Steam Low Pressure Trip 4203 49-1 RCIC Steam FC-PT-NO58D Steam Low Pressure Trip 4202 49-1 RCIC Steam FC-PT-NO58F Steam Low Pressure Trip 4203 49-1 RCIC Steam FC-PT-N058H Steam Low Pressure Trio 4202 49-1 Reactor Bldg Unit Coolers GU-AC281 Unit Cooler Control Panel 4309 83-1 Reactor Bldg Unit Coolers GR-AVH209 HPCI Unit Cooler 4111 83-1 Reactor Bldg Unit Coolers GR-AVH210 RHR Unit Cooler 4113 83-1 Reactor Bldg Unit Coolers GR-AVR211 Core Spray Unit Cooler 4118 83-1 Reactor Bldg Unit Coolers GR-AVH214 SACS Unit Cooler 4309 83-1 Reactor Bldg Unit Coolers GR-BVH209 HPCI Unit Cooler 4111 83-1 Reactor Bldg Unit Coolers GU-CC281 Unit Cooler Control Panel 4310 83-1 Reactor Bldg Unit Coolers GR-CVH210 RHR Unit Cooler 4114 83-1 Reactor Bldg Unit Coolers GR-CVH211 Core Spray Unit Cooler 4117 83-1 Reactor Bldg Unit Coolers GR-CVH2!4 SACS Unit Cooler 4309 83-1 Reactor Bldg Unit Coolers GR-EVH210 RHR Unit Cooler 4214 83-1 Reactor Bldg Unit Coolers GR-EVH211 Core Spray Unit Cooler 4 3.18 83-1 Reactor Bldg Unit Coolers GR-FSL-9385AI SACS Air Flow Switch 41309 Reactor P!dg Unit Coolers GR-FSL-9385C1 SACS Air Plow Switch 4 309 83-1 Reactor Bldg Unit Coolers GR-GVH210 RHR Unit Cooler 4114 Reactor Bldg Unit Coolers GR-GVH211 Core Spray Unit Cooler 4117 Reactor Bldg Unit Coolers GR-TE-9382A 9PCI Room Temp 4111 Reactor Blog Unit Coolers GR-TE-9382B HPCI Room Temp 4111 83-1 Reactor Bldg Unit Coolers GR-TE-9383A 5CR A Room Temp 4111 Reactor Bldg Unit Coolers GR-TE-9383C PHR C Room Temp 4 114 Reactor Bldg Unit Coolers GR-TE-9383E RHR A Room Temp 4214 Reactor Bldg Unit Coolers GR-TE-9383G RHR C Room Temp 4114 83-1 Reactor Bldg Unit Coolers GR-TE-9384A Core Spray Room Temp 4118 83-1 Reactor Bldg Unit Coolers GR-TE-9384C Core Spray Room Temp 4117 83-1 Reactor Bldg Unit Coolers GR-TE-9384E Core Spray Room Temp 4118 83-1 Reactor Bldg Unit Coolers GR-TE-9384G Core Spray Room Teap 4117 83-1 Reactor Bldg Unit Coolers GR-TE-9385A SACS A&C Room Temp 4309 83-1 Reactor Bldg Unit Coolers GR-TE-9385C SACS A&C Room Temp 4309 83-1 Reactor Bldg Unit Coolers GR-AVH208 RCIC Unit Cooler 4110 83-1 Reactor Bldg Unit Coolers GU-BC281 Unit Cooler Control Panel 4303 9 of 16 HCGS-UFSAR Revision 0 April 11, 1988

TABLE 9A-2 (Cont)

Elec Mech. Room System Component Function Div. Div. No. P&ID Reactor Bldg Unit Cooleers It GR-BVH208 RCIC Unit Cooler 4110 83-1 Reactor Bldg Unit Cooleers It GR-BVH210 RHR Unit Cooler 4109 83-1 Reactor Bldg Unit Cool ers It GR-BVH211 Core Spray Unit Cooler 4104 83-1 Reactor Bldg Unit Cooli ers It GR-BVH214 SACS Unit Cooler 4307 83-1 Reactor Bldg Unit Cooli ers II GU-DC281 Unit Cooler Control Panel 4202 83-1 Reactor Bldg Unit Cooli era Irs II II GR-DVH210 RHR Unit Cooler 4107 83-1 Reactor Bldg Unit Coole GR-DVh211 Core Spray Unit Cooler 4105 83-1 Reactor Bldg Unit Cooleers TI GR-DVH214 SACS Unit Cooler 4307 83-I Reactor Bldg Unit CooleIrs TI GR-FSL-9385BI SACS Air Flow Switch 4307 83-1 Reactor Bldg Unit Cooleers II GR-FSL-9385DI SACS Air Flow Switch 4307 83-1 Reactor Bldg Unit Coole trsII GR-FVH210 RHR Unit Cooler 4208 83-1 Reactor Bldg Unit COOlIeIrs II GR-FVH211 Core Spray Unit Cooler 4104 83-1 Reactor Bldg Unit Cooli Irs II GR-HVH210 RHR Unit Cooler 4107 83-1 Reactor Bldg Unit Cooleers Ix GR-HVH211 Core Spray Unit 4105 83-1 Reactor Bldg Unit Cool ors II GR-TE-9381A RCIC Room Temp 4110 83-1 Reactor Its II Bldg Unit Cooleera GR-TE-9381B RCIC Room Temp 4110 83-1 Reactor Bldg Unit Cool ors It GR-TE-9383B RHR B Room Temp 4109 83-1 Reactor Bldg Unit Cool ers II GR-TE-9383D RHR D Room Temp 4107 83-1 Reactor Bldg Unit Cool! ers It GR-TE-9333F RHR B Room Temp 4208 83-1 Reactor Bldg Unit Cool ors It GR-TE-9383H RHR D Room Temp 4107 83-1 Reactor Bldg Unit Cool ers Ii GR-TE-9384B Core Spray Room Temp 4104 Reactor Bldg Unit Cooli ors II GR-TE-9384D Core Spray Room Temp 4105 83-83-1 Reactor Bldg Unit Cooli ers II GR-TE-9384F Core Spray Room Temp 4104 Reactor Bldg Unit Cooli ers It GR-TE-9384H Core Spray Room Temp 4105 ers Reactor Bldg Unit Cool ers IT GR-TE-9385B SACS BaD Room Temp 4307 81-i1-1 Reactor Bldg Unit Cool II GR-TE-9385D SACS B&D Room Temp 4307 So ý 3-i Reactor Protection Sys (RSP) SB-TE-3647J-2 Suppression Pool Temperature 4102 4' 1-Reactor Protection Sys (RSP) SB-TE-3647L-2 Suppression Pool Temperature 4.10Q Reactor Protection Sys (RSP) SB-TE-3647M-2 Suppression Pool Temperature 4102 Reactor Protection Sys (RSP) SB-TE-3647Q-2 Suppression Pool Temperature 4102 Reactor Protection Sys (RSP)

Reactor Protection Sys SB-TT-3647J-2 Suppression Pool Temperature 5605 Suppression Pool Temperature 5605 Reactor Protection Sys (RSP) SB-TT-3647L-2 41-1-2 41-!1 Reactor Protection Sys (RSP) SB-TT-3647M-2 Suppression Pool Temperature 1605 41-1-2 Reactor Protection Sys -(RSP) SB-TT-3647Q-2 Suppression Pool Temperature 5605 41-1-2 I SB-TE-3647A-1 Suppression Pool Temperature Reactor Protection Sys - I 4102 SB-TE-3647C-l Suppression Pool Temperature 4102 Reactor Protection Sys - I 41 2 SB-TE-3647E-l Suppression Pool Temperature 4102 Reactor Protection Sys - I SB-TE-3647H-l Suppression Pool Temperature 4102 41-1-2 Reactor Protection Sys - I 4 1 '32 SB-TE-3647K-l Suppression Pool Temperature 4102 41-1-2 Reactor Protection Sys -3I Reactor Protection Sys - I SB-TE-3647N-l Suppression Pool Temperature 4102 41-1-2 Reactor Protection Sys -3I SB-TE-3647P-l Suppression Pool Temperature 4 1 02 4102 Reactor Protection Sys -tI SB-TE-3647R-l Suppression Pool Temperature 4 102 41 2 Reactor Protection Sys - I SB-TE-3648A-l Suppression Pool Temperature 4102 4102 41 - -2 41-1-2 Reactor Protection Sys - I SB-TE-3648B-1 Suppression Pool Temperature 41-1-2 SB-TE-364BC-i Suppression Pool Temperature 10 of 16 HCGS-UFSAR Revision 0 April 11, 1988

TABLE 9A-2 (Cont)

Elec Mech. Room System Component Function Div. Div. No.

Reactor Protection Sys - II SB-TE-3647B-I Suppression Pool Temperature II 4102 41-1-2 Reactor Protection Sys - IT SB-TE-3647D-I Suppression Pool Temperature II 4102 Reactor Protection Sys - II SB-TE-3647F-I Suppression Pool Temperature iI 4102 41-1-2 Reactor Protection Sys - II SB-TE-3647G-1 Suppression Pool Temperature 4102 41-1-2 Reactor Protection Sys - 22 SB-TE-3647J-l Suppression Pool Temperature II 4102 4 t-t-2 Reactor Protection Sys - II SB-TE-3647L-l Suppression Pool Temperature It 4102 41-1-2 Reactor Protection Sys - II SB-TE-3647M-1 Suppression Pool Temperature II 4102 41-1-2 Reactor Protection Sys - II Suppression Pool Temperature SB-TE-3647Q-1 I 4102 41-1-2 Reactor Protection Sys - II SB-TE-3643D-1 Suppression Pool Temperature I 4102 41-1-2 Reactor Recirculation A BB-HV-F031A React Recric Pump Disch 4220 43-1-1 II Reactor Recirculation B BB-EV-F031B React Recirc Pump Disch 4220 43-1-1 RHR BC-HV-FO08 Shutdown Cooling Outside Cont 4329 51-1-1 RHR BC-HV-F009 Shutdown Cooling Inside Cont 4220 51-1-i RHR BC-HV-F040 To Radwaste 4102 51-1-I I I RHR BC-HV-F049 To Radwaste 4102 II PER A BC-AP202 RHR Pump A 4213 RHR A BC-FT-NC15A RPHR Flow A I I/I RHR A BC-HV-FO03A RHR HX Outlet 413 RHR A BC-HV-FOO4A Torus Suction 4102 RHR A BC-HV-FO06A Shutdown Suction to A loop 4113 RHR A BC-HV-FO07A Min Flow Line 4102 RHR A BC-HV-F015A Shutdown Rezurn i/! 4329 51-1-1 RPR A BC-HV-F0G6A Containment Spray 51 - -1 4329 51-1-1 RHR A BC-RV-F017A 5'-12 LPCI Injection 51-i-i RHR A BC-HV-F024A Supp Pool Return II 5! 4102 RHR A BC-HV-F027A Torus Spray b51-I-1 RHR .A BC-HV-F047A RHR HX A inlet 4214 51 RHR A BC-HV-F048A REP EX A Bypass SI 4214 51-1-2 51 RHR A BC-PDT-NO58A Interlock to 017A 421, 51-1-1 1-1-1 51-!-1 RHR B BC-BP202 RHR Pump B II 4109 r51 RPR B BC-FT-4435 RSP Flow Indication Ii 4201 51 RHR B BC-FT-NO15B RHR Flow B 4201 4109 51-1-2 RHR B BC-WV-F003P PHR EX Outlet II 51-1-1 RHR B BC-HV-F004B Torus Suction tI 4102 51-1-1 RHR B BC-HV-FO06B Shutdown Suction to B Loco 4109 SI RHR B BC-HV-F007B Min Flow Line 4102 II 51-I-1 RHR B BC-HV-FP15B Shutdown Return 4321 iI RHR B BC-HV-VO16B Containment Spray 4402 51-1-2 II RHR B BC-HV-F017B LPCI Injection 4321 51-I-RHR B BC-HV-F024B Supp Pool Return 4102 II II RHR B BC-HV-F027B Torus Spray 4102 IZ RHR B BC-HV-F047B RHR HX B Inlet 4208 II RHR B BC-EV-FO48B RHR HX B Bypass TI 4208 RHR B BC-PDT-N058B Interlock to F017B II 4205 RHR C BC-CP202 RHR Pump C 4114 11 of 16 HCGS-UFSAR Revision 15 October 27, 2006

TABLE 9A-2 (Cont)

Elec Mech. Room System Component Function Div. Div. No. &ID RHR C BC-FT-NO15C RHR Flow C I I 4114 51-1-2 RHR C BC-HV-FO04C Torus Suction i 1 4102 51-1-2 RHR C BC-HV-F007C Min Flow Line I I 4102 51-1-1 RHR C BC-HV-FOIOA Supp pool Return I I 4114 51-1-2 RHR C BC-HV-F017C LPCI Injection i I 4329 51-1-2 RHR C BC-PDT-N4058C Interlock to F017C I I 4218 51-1-1 RHR D BC-DP202 RHR Pump D II It 4107 51-1-1 RHR D BC-FT-NO15D RHR Flow D II TI 4107 51-1-1 RHR D BC-HV-FO04D Torus Suction II II 4102 51-1-1 RHR D BC-HV-FO07D Min Flow Line II II 4102 51 RHR D BC-HV-FOIOB Suop Pool Return II II 4107 51-1-2 RHR D BC-HV-F0]7D LPCR Injection IT iI 4321 51-i-1 RHR D BC-PDT-N05D Interlock zo F017D Ii II 4202 51-1-1 RSP Supply Unit GL-0VH316 RSP Room Supply Non TE RSP 5101 93-0-2 RSP Supply Unit GL-SV-9768 RSP Room Supply Kon iE RSP 5501 93-0-2 RWCU BG-HV-FOOl Inboard Cont Isolation I 1 4220 44-1 RWCU BG-HV-F004 Outboard Cont iscl TI T' 4501 44-1 SACS - Div I EA-AC201 SACS Control Panel I 1 4309 1 i-I-I SACS - Div I EG-AP210 SACS Pump I I 4309 11-1-1 SACS - Div I EA-CC201 SACS Control Panel i f 4309 ii-I-!

SACS - Div I EG-CP210 SACS Pump I  ! 4309 11 SACS - Div I EG-FT-2549Al SACS Loop I Flow I 1 4309 SACS - Div I EG-HV-2491A HX AlI2I1 Inlet I 1ii-i-4 30 SACS - Div I EG-HV-2494A HX A2E20D Inlet I i 30 z 1-1-1 SACS - Div I EG-HV-2512A RPR HX AE205 Isol Valve I i 421l I!-i-I SACS - Div I EG-SV-2290A RHR Pump A Room Unit Cooler A I I 4113 1i-1-2 SACS - Div I EG-SV-2290C RHR Pump C Room Unit Cooler C I I 411 11-4 SACS - Div I £G-SV-2290E RHR Pump A Room Unit Cooler E I 1113 1 SACS - Div I EG-SV-2290G RHR Pump C Room Unit Cooler G I 1 4114 11 SACS - Div I EG-SV-2292A HPCI Pump Room Unir Cooler A I I 411i 11-1-2 SACS - Div I EG-SV-2292B HPCI Pump Room Unit Cooler B I I 411 11-1-1 SACS - Div I EG-SV-2325A CS Pump Room A Unit Cooler A I 1 4118 11-1-2 SACS - Div I EG-SV-2325C CS Pump Room C Unit Cooler C I I 4116 11-1-2 SACS - Div I EG-SV-2325E CS Pump Room A Unit Cooler E I I 4318 11-1-2 SACS - Div I EG-SV-2325C- CS Pump Room C Unit Cooler G 2 i 4116 1i-1-2 SACS - Div I EG-SV-2395A DG A HXS Cooling Water 1 1 5211 12-1-1 SACS - Div I EG-SV-2395C DG C CXS Cooling Water I I 5210 12-1-1 SACS - Div I EG-SV-2398A DG A Room Unit Cooler A I 1 5211 12-1-1 SACS - Div I EG-SV-2398C DG A Room Unit Cooler C I I 5210 12-1-1 SACS - Div I EG-SV-2398E DG A Room Unit Cooler E I I 5211 12-1-1 SACS - Div I EG-SV-2398G DG C Room Unit Coolor G 2 1 5210 12-1-1 SACS - Div I EG-SV-2520A RHR Pump AP202 Cooling Coil I I 4113 11-1-1 SACS - Div I EG-SV-2520C RHR Pump CR202 Cooling Coil I I 4114 11-1-1 SACS - Div I EG-TE-2535A SACS A!/A2 HX Bypass Temp. I I 4309 11-1-i SACS - Div I EG-TE-NOOSA RHR HX A SACS Temp. I I 4113 11-1-1 12 of 16 HCGS-UFSAR Revision 16 May 15, 2008

TABLE 9A-2 (Cont)

Elec Mach. Room System Component Function Div. Div. No. P&ID SACS - DIV II EA-BC201 SACS Control Panel 4307 11-1-1 SACS - DIV II EG-BP210 SACS Pump 43C7 SACS - DIV II 11-1-1 EA-DC201 SACS Control Panel 4307 SACS - DIV II 12-1-1 EG-DP210 SACS Pumo 4307 SACS - DIV II 11-1-1 EG-FT-2549BI SACS Loop IT Flow 4307 SACS - DIV II 12-1-I EG-HV-2491B HZ B2E201 Inlet 4307 SACS - DIV II 12-1-1 EG-HV-2494B HX B2E201 Inlet 4307 SACS - DIV I1 EG-HV-2512B RHR HX BE205 Isol Valve SACS - DIV II 11-1-2 EG-SV-2290B RHR Pump B Room Unit Cooler B 4109 SACS - DIV TI 41-1 EG-SV-2290D RHR Pump D Room Unit Cooler 0 4107 SACS - Div It 11-1-2 EG-SV-2290F RHR Pumo B Room Unit Cooler F 4109 SACS - DIV IT Unit Cooler N Room Unit 11 -2 EG-SV-2290H RHR Pump DRoom RCIC Puma Cooler A 4 107 SACS - DIV II EG-SV-2293A RCIC Pump Room Unit Cooler S 41 10 SACS - DIV I1 EG-SV-2293B CS Pump Room B Unit Cooler B 4104 SACS - DIV It EG-SV-2325B CS Pump Room B Unit Cooler C 4105 SACS - DIV i1 EG-SV-2325D CS Pump Room D Unit Cooler F 4104 SACS - DIV Ii EG-SV-2325F CS Pump Room 3 Unit Cooler F SACS - DIV II EG-SV-2325H 4105 SACS - DIV Ii EG-SV-2395B DG B HxS Cooling Wauer 5209 SACS - DIV II 520 8 Ii- -

EG-SV-2395D DG D HXS Cooling Mater SACS - DIV II EG-SV-2398B DG S Room Unit Cooler C 5209 SACS - DIV II EG-SV-2398D DG 0 Room Unit Cooler D 52H8 SACS - DIV II EG-SV-2398F DG S Room Unit Cooler F 5209 SACS - DIV II SG-SV-2398534 DG D Room Unit Cooler H 52,08 SACS - DIV TI 4109 1ii--

EG-SV-2520B RHR Pump BP202 Cooling Coil 4107 41-1-2 SACS - DIV II EG-SV-2 52 0D RHR Pump DP202 Coolino Coil 41-1-2 4 307 41-1-2 SACS - DIV II EG-TE-2535B SACS B!/B2 HX Bypass Temp. 412--1 4109 41-1-2 SACS - DIV II EG-TE-N005B RHR HX B SACS Temp. 412-1-2 4107 4207 41-1-2 SACS - RSP EG-FT-254923 SACS Loop II Flow - RSP ind 41 11-i-2 41-1-2 Safety Relief Valves SN-SV-3652A PSV-FO13A Safety Relief Valve 4109 11-1-1 Safety Relief Valves SN-SV-36522 PSV-FO1I3A Safety Relief Valve 4120 41-1-2 11-1-1 Safety Relief Valves SN-SV-3653A PSV-FO13B Safety Relief Valve 4220 41-1-2 41-1-1 Safety Relief Valves 4220 12-1-2 SN-SV-3653B PSV-FOI3B Safety Relief Valve 4220 41-1-I Safety Relief Valves SN-SV-3654A PSV-FO1I3C Safety Relief Valve Safety Relief Valves 4220 41-1-2 SN-SV-3654B PSV-FOI3C Safety Relief Valve 4220 Safety Relief Valves 41-1 -2 SN-SV-3655A PSV-FO13D Safety Relief Valve Safety Relief Valves 4220 41-1-2 SN-SV-3655B PSV-FOI3D Safety Relief Valve Safety Relief Valves 4220 4 1-1-2 AS-SV-3656A PSV-FOI3J Safety Relief Valve Safety Relief Valves 4220 41-1-2 AS-SV-3657A PSV-FO13F Safety Relief Valve Safety Relief Valves AB-SV-3658A PSV-FO13G Safety Relief Valve 4220 Safety Relief Valves 4220 41-1-2 AB-SV-3659A PSV-FO13H Safety Relief Valve Safety Relief Valves 4220 41-1-2 AB-SV-3660A PSV-FO13R Safety Relief Valve 4120 Safety Relief Valves 41-1-2 AB-SV-3661A PSV-FO13K Safety Relief Valve 4220 Safety Relief Valves AB-SV-3662A PSV-FO1I3L Safety Relief Valve 4220 Safety Relief Valves Safety Relief Valves AB-SV-3663A AB-SV-3664A PSV-FO13M Safety Relief Valve PSB-FOl3P Safety Relief Valve 4220 I

13 of 16 HCGS-UFSAR Revision 12 May 3, 2002

TABLE 9A-2 (Cont)

Flec Mech. Room System Component Function Div. Div. No. P&ID Safety Relief Valves SN-SV-3665A PSV-FO13E Safety Relief Valve 4220 41-1-2 Safety Relief Valves SN-SV-3665B PSV-FO13E Safety Relief Valve 4220 41-I-2 Service Water - Div I EA-AC515 Traveling Screen Panel 204 10-1-1 Service Water - Div I EA-AC5I6 Service Water Pump Panel 204 10-1-i Service Water - Div I EA-AP502 Service Water Pump 204 10-i-1 Service Water - Div I EA-AS501 Traveling Screen TS RM 10-!-I Service Water - Div I EA-CC515 Traveling Screen Panel 2Od 10-1-1 Service Water - Div I EA-CC516 Service Water Pump Panel 2I4 10-1-1 Service Water - Div T EA-CP502 Service Water Pump TS.3- 10-I-I Service Water - Div I EA-CS501 Traveling Screen '04 10--11 Service Water - Div I EA--HV-2197A Strainer Disch To Fish Trouch 204 10-1-1 Service Water - Div I EA-HV-2197C Strainer Dish to Fish Trough Service Water - Div i EA-HV-2198A Puma A Discharge Valve i07 Service Water - Div I EA-HV-2198C Pump C Discharge Valve 107 Service Water - Div I EA-HV-2355A SACS A2 Disch 4 10 q 4309 Service Water - Div 1 &Ak-HV-2371A SACS Al Discharge '30e 10-1-1 Service Water - Div I EA-PDT-2354A SACS HX Al DP 4309 Service Water - Div I EA-PDT-2373A SACS HX A2 OP 4 309 10-1-1 Service Water - Div II EA-EC515 Traveling Screen Panel 10-1-1 Service Water - Div It EA-BCSI6 Service Water Pump Panel Service Water - Div II EA-BP502 Service Water Pump DSRM 208 Service Water - Div II EA-BS501 Traveling Screen 208 80-1-2 Service Water - Div II EA-DCSI5 Traveling Screen Pane! 80-1-1 Service Water - Div II EA-DCSI6 Service Water Pump Panel TS RM 208 10-!-1 10-1-i Service Water - Div !I FA-DP502 Service Water Pump 10-i-1 80-1-1 Service Water - Div II EA-DSSIO Traveling Screen TI RH 10-1-I 10-1-1 Service Water - Div II EA-HV-2197B Strainer Disch to Fish trough 10-2-1 Service Water - Div II EA-HV-2197D Strainer Disch to Fish trough 10-1-I Service Water - Div II EA-HV-2198B Pump B Discharge Valve 110 10-1-2 Service Water - Div II EA-HV-2198D Pump D Discharge Valve 110 10-1-2 Service Water - Div II EA-HV-2204 Loop B RA.CS 1X Header Valve 430-7 Service Water - Div II I EA-HV-2355B SACS B2 Discharge 4307 Service Water - Div II EA-NV-2371B SACS 81 Discharge 4207 10-1-2 Service Water - Div II EA-PDT-2354B SACS HX 81 DP 4307 10-1-2 Service Water - Div II EA-PDT-2373B SACS HX B2 DP 4307 5F12 88-1-1 Switchgear Room Unit Cooler A GM-AVR401 Switchgear Pm Unit Cooler 5629

-306 88-1-!

Switchgear Room Unit Cooler A GM-HD-9549A Outside Air 5612 88-1-1 Switchgear Room Unit Cooler B GM-BVH401 Switchgear Rm Unit Cooler 5629 5606 88-1-1 Switchcear Room Unit Cooler B GM-HD-9549B Outside Air 5605 88-1-1 Switchgear Room Unit Cooler C GM-CVH401 Switchgear Rm Unit Cooler 1629 88-1-1 Switchgear Room Unit Cooler C GM-HD-9549C Outside Air 5612 88-1-1 Switchgear Room Unit Cooler D GM-DVH401 Switchgear PR Unit Cooler 5606 88-1-1 Switchgear Room Unit Cooler D GM-HD-9549D Outside Air 5605 SWS HVAC Supply a Exhaust A GQ-AC581 Intake Stru HVAC Panel 204 95-0 SWS HVAC Supply & Exhaust A GQ-AVS03 Intake Struc Supply Fan 307 95-0 SWS HVAC Supply & Exhaust A GQ-AV504 Intake Struc Exhast Fan 305 95-0 14 of 16 HCGS-UFSAR Revision 18 Way 10, 2011

TABLE 9A-2 (Cont)

Elec Mech. Room System Component Function Div. Div. No.

Pl 0 SWS HVAC Supply & Exhaust A GQ-TD-9773Al Outside Air Damper I 306 915-0 SWS HVAC Supply & Exhaust A GQ-TD-9773IAA Damper Actuator I 306 95-0 SWS HVAC Supply & Exhaust A GQ-TD-9773AIB Damper Actuator 30F 4.5 -

SWS HVAC Supply & Exhaust A GQ-TD-9773A2 Intake Stru Return Air 301 95-0 SBS HVAC Supply & Exhaust A GQ-TD-9773A3 Intake Stru Exhaust Air 304 SWS HVAC Supply &

95-C0 5- 0 Exhaust A GQ-TE-9773A Intake Stru AGC Room Tems C41 SWS HVAC Supply & Exhaust S GQ-BC581 Intake Stru HV/AC Panel 95 -0 SWS HVAC Supply & Exhaust B GQ-BV50 Intake Struc Supply Fan 312 c5-0 SWS HVAC Supply & Exhaust B GQ-BV504 Intake Struc Exhaust Fan 311 95-0 SLS HVAC Supply & Exhaust B DQ-TD-9773BI Outside Air Damper -112 SWS HVAC Supply & Exhaust 2 GQ-TD-9773BIA Damper Actuator 95-0 SWS HVAC Supply & Exhaust B GQ-TD-9773BlB Damper Actuator 95-0 SWS HVAC Supply & Exhaust B GQ-TD-9773B2 Intake Stru Return Air 95-0 SWS HVAC Supply & 310 95-1 Exhaust B GQ-TD-9773B3 Intake Stru Exhaust Air SWS WVACSupply & Exhaust B GQ-TE-97732 Intake Stru B&D Room Temp 208 95-0 SWS HVAC Supply & Exhaust C GQ-CC581 Intake Stru HVAC Panel 204 95-0 SWS HVAC Supply & Exhaust C GQ-CVS03 Intake Struc Intake Fan 306 95-0 SWS HVAC Supply & Exhaust C GQ-CV504 Intake Struc Exhaust Fan 305 95-0 SWS HVAC Supply & 91-0 95-0)

Exhaust C GQ-TD-9773CI Outside Air Damper 306 SWS HVAC Supply & 95-0 Exhaust C GQ-TD-9773CIA Damper Actuator 30f SWS HVAC Supply & 95-0 Exhaust C GQ-TD-9773CIB Damper Actuator 306 SWS HVAC Supply & 95-0 Exhaust C GQ-TD-9773C2 Intake Stru Return Air 305 SWS HVAC Supply & 95-0 Exhaust C GQ-TD-9773C3 Intake Stru Exhaust Air 304 SWS RVAC Supply & 95-0 Exhaust C GQ-TE-9773C Intake Stru A&C Room Temo 204 95-0 SWS HVAC Supply & Exhaust D GQ-DC581 Intake Stru HVAC Panel 208 SWS HVAC Supply & 95-0 Exhaust D GQ-DV503 Intake Struc Intake Fan 312 95-0 SWS HVAC Supply & Exhaust D GQ-DV504 Exhaust Struc Intake Fan 311 SWS HVAC Supply & 95-0 Exhaust D GQ-TD-9773BI Outside Air Damper 312 SWS HVAC Supply & 95-0 Exhaust D GQ-TD-9773DIA Damper Actuator 312 SWS HVAC Supply & 95-0 Exhaust D GQ-TD-9773DIB Damper Actuator 311 SWS HVAC Supply & 95-0 Exhaust D GQ-TD-9773D2 Intake Stru Return Air 311 SWS HVAC Supply & 95-0 Exhaust D GQ-TD-9773D3 Intake Stru Exhaust Air 310 SWS HVAC Supply & 95-0 Exhaust D GQ-TE-9773D Intake Stru B&D Room Teme 208 Tray Screen Motor 95-0 Rm HVAC A GQ-QAV558 Traveling Screen Rm Fan TS RM 95-0 Trav Screen Motor 95-0 Rm HVAC A GQ-TD-9774AI Trav Screen Room Return Air TS RM 95-0 Tray Screen Motor 95-0 Rm HVAC A GQ-TD-9774A2 Tray Screen Room Outside Air TS RM Tray Screen Motor Rm HDIACA 95-0 GQ-TE-9774A Tray Screen Room Air Temp TS RM Tray Screen Motor Rm 10JAC B GQ-OBV558 Traveling Screen Rm Fan TS RM Tray Screen Motor Rm HACG B GQ-TD-9774BI Tray Screen Room Return Air T RM 15 of 16 HCGS-UFSAR Revision 0 April 11, 1988

TABLE 9A-2 (Cont)

Elec Mech. Room System Component Function Div. Div. No. PV&I Tray Screen Motor Rm HVAC B GQ-TD-9774B2 Trae Screen Room Outside Air II TI TS RM 95-0 Tray Screen Motor Rm HVAC B GQ-TE-9774B Trae Screen Room Air Temp 11 iI TS RM 95-0 16 of 16 HCGS-UFSAR Revision 0 April 11, 1988

Hope Creek Nuclear Generating Station S&L Report No. SL-01 1553 Project No. 12800-217 Rev. 1 Seismic Walkdown Report ATTACHMENT IC - BASE LIST 2-COMPONENTS ASSOCIATED WITH FUEL POOL COOLING

Attachment 1C - Hope Creek - Ba ise List 2 - Components Associated VVith Fuel Pool Cooling Functional loc. Description Catalog profile SEISMIC CLASS H1BJ -1BJLT-4801 *HPCI SUPPRESSION POOL LEVEL CB NU-TMTR Seismic Class 1 (I)

H1BJ -1BJLT-4805-1 *SUPPRESSION POOL NU-TMTR Seismic Class 1 (I)

Hi BJ -1 BJLT-4805-2 *SUPPRESSION POOL NU-TMTR Seismic Class 1 (I)

H1BJ -1BJLT-N062A-E41 *HPCI SUPPR POOL LEVEL NU-TMTR Seismic Class 1 (I)

H1BJ -1BJLT-N062E-E41 *HPCI SUPPR POOL LEVEL NU-TMTR Seismic Class 1 (I)

H1 EA 212221 MOV EA-HV2234 FUEL POOL CLG NU-PAN Seismic Class 1 (I)

H1EA 212222 MOV EA-HV2236 FUEL POOL CLG NU-PAN Seismic Class 1 (I)

HIEC EC-V008 FUEL POOL PMP AP211 DSCH VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V016 FUEL STOR POOL DIFF ISLN VLV NU-VLV Seismic Class 1 (I)

H1 EC EC-V017 FUEL STOR POOL DIFF ISLN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V018 DRYER/SEP POOL FILL/DRN ISLN V NU-VLV Seismic Class 1 (I)

H1EC EC-V022 DRY SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V023 DRYER SEP POOL DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V035 FUEL POOL PMP AP211 VNT VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V036 FUEL POOL PMP AP211 CASING DRN NU-VLV Seismic Class 1 (I)

H1EC EC-V037 FUEL POOL PMP BP211 VNT VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V038 FUEL POOL PMP BP211 CASING DRN NU-VLV Seismic Class 1 (I)

H1EC EC-V039 FUEL POOL PMP BP211 SUCT VLV NU-VLV Seismic Class 1 (I)

H1 EC EC-V041 FUEL POOL PMP BP211 DSCH VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V053 FUEL STOR POOL GT SEAL DRN VLV NU-VLV Seismic Class 1 (I)

H 1EC EC-V054 SPENT FUEL POOL LINER DRN ISO NU-VLV Seismic Class 1 (I)

HIEC EC-V055 CASK POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H 1EC EC-V102 DRY SEP POOL LNR DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V103 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V104 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V105 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1 EC EC-V106 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V1 08 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V1 09 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V110 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

HIEC EC-V111 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

HIEC EC-V112 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V113 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V114 CASK POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V115 CASK POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V116 CASK POOL LINER DRAIN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V135 CASK POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V136 SPENT FUEL POOL SUMP ISLN NU-VLV Seismic Class 1 (I)

H1 EC EC-V137 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1 EC EC-V138 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1 EC EC-V152 RHR TO FUEL STOR POOL HDR VT V NU-VLV Seismic Class 1 (I)

H1 EC EC-V153 RHR TO FUEL STOR POOL HDR VT V NU-VLV Seismic Class 1 (I)

H1 EC EC-V154 RHR TO FUEL STOR POOL HDR DRN NU-VLV Seismic Class 1 (I)

H1 EC EC-V155 RHR TO FUEL STOR POOL HDR DRN NU-VLV Seismic Class 1 (I)

H1EC EC-V1 56 RHR TO FUEL STOR POOL HDR VNT NU-VLV Seismic Class 1 (I)

H1EC EC-V1 57 RHR TO FUEL STOR POOL HDR VT V NU-VLV Seismic Class 1 (I)

HIEC EC-V158 RHR TO FUEL STOR POOL HDR DRN NU-VLV Seismic Class 1 (I)

H1EC EC-V1 59 RHR TO FUEL STOR POOL HDR DRN NU-VLV Seismic Class 1 (I)

Attachment 1C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional loc. Description Catalog profile SEISMIC CLASS H1EC EC-V183 FUEL POOL F/D DSCH HDR VNT VLV NU-VLV Seismic Class 1 (I)

HiEC -1A-E-202 HEAT EXCH- FUEL POOL NU-1HX Seismic Class 1 (1)

H1EC -1A-P-211 A' FUEL POOL COOLING PUMP NU-PMP Seismic Class 1 (I)

H1EC -1B-E-202 HEAT EXCH- FUEL POOL NU-1HX Seismic Class 1 (I)

H1EC -1B-P-211 B' FUEL POOL COOLING PUMP NU-PMP Seismic Class 1 (I)

H1EC -1ECEIS-AC652120 FM - FUEL POOL CLG PMP AP 211 NU-MNTR Seismic Class 1 (I)

HIEC -1ECEIS-AC652120 FM - FUEL POOL FILTER DEMIN ISOL VLV HV NU-MNTR Seismic Class 1 (I)

H1EC -1 ECEIS-AC652120 FM - FUEL POOL FILTER DEMIN BYPASS VLV NU-MNTR Seismic Class 1 (I)

H1 EC -1 ECEIS-BC652120 FM - FUEL POOL COOLING PUMP BP211 NU-MNTR Seismic Class 1 (I)

H1EC -1ECFAL-4649A FUEL POOL CLG PMP A DISCH NU-ALRM Seismic Class 1 (I)

H1EC -1 ECFE-4682 *FUEL POOL CLG SYS FLOW NU-ELEM Seismic Class 1 (I)

HI EC -1 ECHS-4689B2 FUEL POOL FILTER DEMIN BYPASS REF. DA NU-SW Seismic Class 1 (I)

H1 EC -1 ECHS-4693A2 FUEL POOL CLG PMP AP211 REF. DATA NU-SW Seismic Class 1 (I)

H1EC -1ECHS-4693B2 FUEL POOL CLG PUMP BP211 REF. DATA NU-SW Seismic Class 1 (I)

H1EC -1 ECKY-A212 FUEL POOL CLG PMP AP211 NU-TIMR Seismic Class 1 (I)

H 1EC -lECKY-B212 FUEL POOL CLG PP BP 211 NU-TIMR Seismic Class 1 (I)

H1EC -1ECLSL-4667 FUEL STORAGE POOL LEVEL NU-SW Seismic Class 1 (I)

H1EC -1ECLT-4667 *FUEL STORAGE POOL LEVEL NU-TMTR Seismic Class 1 (I)

H1 EC -1 ECPSV-4674A *FUEL POOL HTX AE202 RELIEF VALVE NU-SRV Seismic Class 1 (1)

H1 EC -1 ECPSV-4674B *FUEL POOL HTX BE202 NU-SRV Seismic Class 1 (I)

H1EC -1 ECPT-4669A *FUEL POOL CLG PMP A SUCT NU-TMTR Seismic Class 1 (I)

H1EC -1ECPT-4669B *FUEL POOL CLG PMP B SUCT NU-TMTR Seismic Class 1 (I)

HIEC -1ECSX-4692 *FUEL POOL HT EXCH OUT NU-ELEM Seismic Class 1 (I)

HIEC -1ECTE-4683 *FUEL POOL CLG PMP DISCH HDR SEE ENC- NU-ELEM Seismic Class 1 (I)

H1EC -1ECTI-4683 FUEL POOL CLG DISCH HDR REF. DATA NU-IND Seismic Class 1 (I)

H1 EC -1 ECTR-4683 FUEL POOL OUTLET TEMP NU-REC Seismic Class 1 (I)

H1EC -1ECTSH-4683 FUEL POOL CLG DISCH HDR NU-SW Seismic Class 1 (I)

H1EC -1 ECTT-4683-1 FUEL POOL CLG DISCH HDR NU-TMTR Seismic Class 1 (I)

H1EC -1ECTT-4683-2 FUEL POOL CLG DISCH HDR REF. DATA NU-TMTR Seismic Class 1 (I)

H 1EC -1 ECV-170 LP B EMERG MAKEUP TO FUEL POOL NU-MOV Seismic Class 1 (I)

H1EC -1ECXIS-AC652120 LM - FUEL POOL CLG PMP AP 211 NU-LOGC Seismic Class 1 (I)

HIEC -1ECXIS-AC652120 LM - FUEL POOL CLG PMP AP 211 NU-LOGC Seismic Class 1 (I)

H1EC -1ECXIS-AC652120 LM - FUEL POOL FILTER DEMIN ISOL VLV HV. NU-LOGC Seismic Class 1 (I)

H1EC -1ECXIS-AC652120 LM - FUEL POOL FILTER DEMIN BYPASS VLV NU-LOGC Seismic Class 1 (I)

HIEC -1ECXIS-BC652120 LM - FUEL POOL COOLING PUMP BP211 NU-LOGC Seismic Class 1 (I)

H1EC -1ECXIS-BC652120 LM - FUEL POOL COOLING PUMP BP211 NU-LOGC Seismic Class 1 (I)

H1EC -1ECZS-4676A *FUEL POOL HTX OUTLET NU-SW Seismic Class 1 (I)

H1EC -1ECZS-4676B *FUEL POOL HTX OUTLET NU-SW Seismic Class 1 (I)

HI EC -1 ECZS-4678 *FUEL POOL FILT DEMIN INLET NU-SW Seismic Class 1 (I)

H1EC 212103 PMP,FUEL POOL CLG 1AP211 NU-PAN Seismic Class 1 (I)

HIEC 212254 MOV EC-HV4647 FUEL POOL M/U A NU-PAN Seismic Class 1 (I)

H1EC 222103 PMP,FUEL POOL CLG 1BP211 NU-PAN Seismic Class 1 (I)

H1EC 222154 MOV EC-HV4648 FUEL POOL M/U B NU-PAN Seismic Class 1 (I)

H1EC 222244 MOV EC-HV4689B FUEL POOL DM NU-PAN Seismic Class 1 (I)

H1 EC -HS-4647 FUEL POOL CLG HV-4647 C/SW NU-SW Seismic Class 1 (I)

H1EC -HS-4648 FUEL POOL CLG HV-4648 C/SW NU-SW Seismic Class 1 (I)

H1EC -HS-4676A FUEL POOL CLG HV-4676A C/SW NU-SW Seismic Class 1 (I)

H1EC -HS-4676B FUEL POOL CLG HV-46768 C/SW NU-SW Seismic Class 1 (I)

Attachment 1C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional loc. Description Catalog profile SEISMIC CLASS H1 EC -HS-4678 FUEL POOL CLG HV-4678 C/SW NU-SW Seismic Class 1 (I)

H 1EC -H S-4689A FUEL POOL CLG HV-4689A C/SW NU-SW Seismic Class 1 (I)

H1EC -HS-4689B1 FUEL POOL CLG HV-4689B C/SW NU-SW Seismic Class 1 (I)

H1EC -HS-4693A1 FUEL POOL CLG PMP AP211 C/SW NU-SW Seismic Class 1 (I)

H1EC -HS-4693B1 FUEL POOL CLG PMP BP211 C/SW NU-SW Seismic Class 1 (I)

H 1EE 212233 MOV EE-HV4652 SUPP POOL ISO NU-PAN Seismic Class 1 (I)

H1EE 212241 MOV EE-HV4680 SUPP POOL ISO NU-PAN Seismic Class 1 (I)

H1EE 222212 MOV EE-HV4679 SUPP POOL ISO NU-PAN Seismic Class 1 (I)

HWEE 222221 MOV EE-HV4681 SUPP POOL ISO NU-PAN Seismic Class 1 (I)

H1EE -EE-HV-4652 OPNO02 SUP POOL RET INBD ISLN 52-21223: NU-MO Seismic Class 1 (I)

H1 EE -EE-HV-4679 OPNO01 SUP POOL RET OTBD ISLN 52-22221 NU-MO Seismic Class 1 (I)

H1EE -EE-HV-4680 OPNO03 SUP POOL SPLY INB ISLN 52-212241 NU-MO Seismic Class 1 (I)

H1EE -EE-HV-4681 OPNO04 SUP POOL SPLY OTBD ILN 52-22222 NU-MO Seismic Class 1 (I)

H1EG EG-V768 FUEL POOL HX AE202 SACS OUTLET VLV NU-VLV Seismic Class 1 (I)

HMEG EG-V769 FUEL POOL HX BE202 SACS OUTLET VLV NU-VLV Seismic Class 1 (I)

H1 EG EG-V945 FUEL POOL HX AE202 SUP VNT VLV NU-VLV Seismic Class 1 (I)

H1EG EG-V946 FUEL POOL HX AE202 RNT VNT VLV NU-VLV Seismic Class 1 (I)

H1 EG EG-V947 FUEL POOL HX BE202 SUP VNT VLV NU-VLV Seismic Class 1 (I)

H1 EG EG-V948 FUEL POOL HX BE202 RTN VNT VLV NU-VLV Seismic Class 1 (I)

H1 EG -1 EGHS-2314A2 FUEL POOL HX AE202 REF. DATA NU-SW Seismic Class 1 (I)

H1EG -1EGHS-2314B2 FUEL POOL HX BE202 REF. DATA NU-SW Seismic Class 1 (I)

H1EG -1EGHS-2317A2 FUEL POOL HX AE202 REF. DATA NU-SW Seismic Class 1 (I)

H1EG -1EGHS-2317B2 FUEL POOL HX BE202 REF. DATA NU-SW Seismic Class 1 (I)

HIEG -1EGHS-7921A2 FUEL POOL HX AE202 REF. DATA NU-SW Seismic Class 1 (I)

HIEG -1EGHS-7921B2 FUEL POOL HX BE202 REF. DATA NU-SW Seismic Class 1 (I)

H1EG -1EGHS-7922A2 FUEL POOL HX AE202 REF. DATA NU-SW Seismic Class 1 (I)

H1 EG -1 EGHS-7922B2 FUEL POOL HX BE202 REF. DATA NU-SW Seismic Class 1 (I)

H1EG -1EGPDSL-2529A FUEL POOL HEAT EXCH A NU-SW Seismic Class 1 (I)

H1EG -1EGPDSL-2529B FUEL POOL HEAT EXCH B NU-SW Seismic Class 1 (I)

H1EG -1EGPDT-2529A *FUEL POOL HEAT EXCH A NU-TMTR Seismic Class 1 (I)

H1EG -1EGPDT-2529B *FUEL POOL HEAT EXCH B NU-TMTR Seismic Class 1 (I)

HI EG -1 EGPSV-2530A *FUEL POOL HX AE202 NU-SRV Seismic Class 1 (I)

• FUEL POOL HX BE202 SACS SIDE RELIEF VI HiEG -1EGPSV-2530B NU-SRV Seismic Class 1 (I)

HIEG -1EGTW-2315A *FUEL POOL HX AE202 NU-ELEM Seismic Class 1 (I)

H1EG -1 EGTW-2315B *FUEL POOL HX BE202 NU-ELEM Seismic Class 1 (I)

H1EG -1 EGV-1 38 VLV/HV2314A FL- POOL CLG HX A SACS ISLr NU-MOV Seismic Class 1 (I)

HIEG -1EGV-545 FUEL POOL COOLING HX SACS INLET X-TIE ' NU-MOV Seismic Class 1 (I)

H1EG -1EGV-547 FUEL POOL COOLING HX SACS CROSS TIE I' NU-MOV Seismic Class 1 (I)

HIEG -EG-HV-2317A OPN544 FUEL POOL HX A X-CONN 52-21212 NU-MO Seismic Class 1 (I)

H1EG -EG-HV-2317B OPN545 FUEL POOL HX B X-CONN 52-22212 NU-MO Seismic Class 1 (I)

H1 EG -EG-HV-7922A OP/V546 FUEL POOL HX A X-CONN 52-21212. NU-MO Seismic Class 1 (I)

H1EG -EG-HV-7922B OPN547 FUEL POOL HX B X-CONN 52-22212. NU-MO Seismic Class 1 (I)

HIEG -HS-2314A1 FUEL POOL CLG HV-2314A C/SW NU-SW Seismic Class 1 (i)

HIEG -HS-2314B1 FUEL POOL CLG HV-2314B C/SW NU-SW Seismic Class 1 (I)

HIEG -HS-2317A1 FUEL POOL CLG HV-2317A1 C-SW NU-SW Seismic Class 1 (I)

H1EG -HS-2317B1 FUEL POOL CLG HV-2317B C/SW NU-SW Seismic Class 1 (I)

HIEG -HS-7921A1 FUEL POOL CLG HV-7921A C/SW NU-SW Seismic Class 1 (I)

HIEG -HS-7921B1 FUEL POOL CLG HV-7921B C/SW NU-SW Seismic Class 1 (I)

Attachment 1C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional loc. Description Catalog profile SEISMIC CLASS HIEG -HS-7922A1 FUEL POOL CLG HV-7922A C/SW NU-SW Seismic Class 1 (I)

HIEG -HS-7922B1 FUEL POOL CLG HV-7922B C/SW NU-SW Seismic Class 1 (I)

HIKE S-2009 SPENT FUEL POOL GATES NU-MISCM Seismic Class 1 (I)

HOEC -P-EC-V9945 INST ROOT VLV FOR SX-4692 NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9946 INST ROOT VLV FOR FT-4682 LO NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9949 INST ROOT VLV FOR LT-4667 NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9950 INST ROOT VLV FOR FT-4682 HI NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9951 INST ROOT VLV FOR FT-4649A NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9952 INST ROOT VLV FOR FE-4649A NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9953 INST ROOT VLV FOR PT-4672A__& PI-4673A NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9954 INST ROOT VLV FOR PT-4662A NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9955 INST ROOT VLV FOR PT-4669A NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9956 INST ROOT VLV FOR PT-4669B NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9957 INST ROOT VLV FOR PT-4662B NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9958 INST ROOT VLV FOR PT-4672B_& PI-4673B NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9959 INST ROOT VLV FOR FT-4649B NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9960 INST ROOT VLV FOR FT-4649B NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9961 INST ROOT VLV FOR LT-4661B NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9962 INST ROOT VLV FOR LT-4660 NU-RTVL Seismic Class 1 (I)

HOEC -P-EC-V9963 INST ROOT VLV FOR LT-4661A NU-RTVL Seismic Class 1 (I)

H1EC EC-V005 SKIMMER SRG TK OTL HDR ISLN NU-VLV Seismic Class 1 (I)

H1EC EC-V006 FUEL PL PMP AP211 SUCT VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V008 FUEL POOL PMP AP211 DSCH VLV NU-VLV Seismic Class 1 (I)

HIEC EC-V009 HX AE202 INLET VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V010 HX AE202 OTL VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V016 FUEL STOR POOL DIFF ISLN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V017 FUEL STOR POOL DIFF ISLN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V018 DRYER/SEP POOL FILL/DRN ISLN V NU-VLV Seismic Class 1 (I)

H1EC EC-V020 RX WELL DR HDR-FPCC PMP SUC HDRISO V NU-VLV Seismic Class 1 (I)

H1EC EC-V022 DRY SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

HIEC EC-V023 DRYER SEP POOL DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V024 RX WELL DIFF ISLN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V025 RX WELL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V027 RX WELL DIFF ISLN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V029 RX WELL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V030 RX WELL GRTES DRN HDR ISLN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V031 RX WELL GRTES DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V032 FUEL CASK STOR PIT FILL/DRN V NU-VLV Seismic Class 1 (I)

H1EC EC-V035 FUEL POOL PMP AP211 VNT VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V036 FUEL POOL PMP AP211 CASING DRN NU-VLV Seismic Class 1 (I)

H1EC EC-V037 FUEL POOL PMP BP211 VNT VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V038 FUEL POOL PMP BP211 CASING DRN NU-VLV Seismic Class 1 (I)

H1EC EC-V039 FUEL POOL PMP BP211 SUCT VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V041 FUEL POOL PMP BP211 DSCH VLV NU-VLV Seismic Class 1 (I)

H 1 EC EC-V046 F/D OUT HDR TEST CONN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V047 CONN FILL/DRN HDR XCONN TO FD NU-VLV Seismic Class 1 (I)

H I EC EC-V050 SKIM SURGE TK OUT XCONN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V051 FUEL CASK STOR PIT DIFF ISLN V NU-VLV Seismic Class 1 (I)

Attachment 1C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional loc. Description Catalog profile SEISMIC CLASS H1EC EC-V052 FUEL CASK STOR PIT GT SEAL DRN NU-VLV Seismic Class 1 (I)

H1EC EC-V053 FUEL STOR POOL GT SEAL DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V054 SPENT FUEL POOL LINER DRN ISO NU-VLV Seismic Class 1 (I)

H1 EC EC-V055 CASK POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V056 SKIM SURGE LT4661A ISLN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V057 COND TO FUEL CAST STOR PIT ISO NU-VLV Seismic Class 1 (I)

H1EC EC-V060 RHR TO FUEL STOR PL DIFF ISLN NU-VLV Seismic Class 1 (I)

H1EC EC-V061 RHR TO FUEL STOR PL DIFF ISLN NU-VLV Seismic Class 1 (I)

HIEC EC-V081 HX BE202 INLET VLV NU-VLV Seismic Class 1 (I)

H 1 EC EC-V082 HX BE202 OTL VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V084 FPCCS HX BYPASS VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V093 SKIM SURGE TK OTL HDR TO RHR CB NU-VLV Seismic Class 1 (I)

HIEC EC-V101 F/D INL HDR DRN VLV NU-VLV Seismic Class 1 (I)

HIEC EC-V102 DRY SEP POOL LNR DRN VLV NU-VLV Seismic Class 1 (I)

H1 EC EC-V103 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V104 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V105 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V106 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V1 07 REACTOR WELL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V108 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V109 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V110 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V111 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V112 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V113 SPENT FUEL POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V114 CASK POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V115 CASK POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V116 CASK POOL LINER DRAIN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V1 32 F/D OUT HDR DRN VLV NU-VLV Seismic Class 1 (I)

HIEC EC-V1 35 CASK POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

HIEC EC-V136 SPENT FUEL POOL SUMP ISLN NU-VLV Seismic Class 1 (I)

H1EC EC-V137 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V1 38 DRYER SEP POOL LINER DRN VLV NU-VLV Seismic Class 1 (I)

HIEC EC-V1 39 HX AE202 OUT DRN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V140 HX BE202 OUT DRN VLV NU-VLV Seismic Class 1 (I)

H1 EC EC-V141 COND FILL/DRN HDR XCONN TO FD NU-VLV Seismic Class 1 (I)

H1 EC EC-V142 SKIM SURG TK OUT HDR TO RHR NU-VLV Seismic Class 1 (I)

H1EC EC-V143 RX WELL DRN ISLN VLV NU-VLV Seismic Class 1 (I)

H1 EC EC-V149 SKIM SURGE TK OTL TI RHR VNT V NU-VLV Seismic Class 1 (I)

H1 EC EC-V150 SKIM SURG TK OTL TO RHR FLUSH CONN VI NU-VLV Seismic Class 1 (I)

H1 EC EC-V152 RHR TO FUEL STOR POOL HDR VT V NU-VLV Seismic Class 1 (I)

H1EC EC-V1 53 RHR TO FUEL STOR POOL HDR VT V NU-VLV Seismic Class 1 (I)

H1EC EC-V1 54 RHR TO FUEL STOR POOL HDR DRN NU-VLV Seismic Class 1 (I)

HIEC EC-V1 55 RHR TO FUEL STOR POOL HDR DRN NU-VLV Seismic Class 1 (I)

H1EC EC-V1 56 RHR TO FUEL STOR POOL HDR VNT NU-VLV Seismic Class 1 (I)

H1EC EC-V1 57 RHR TO FUEL STOR POOL HDR VT V NU-VLV Seismic Class 1 (I)

HIEC EC-V1 58 RHR TO FUEL STOR POOL HDR DRN NU-VLV Seismic Class 1 (I)

HIEC EC-V1 59 RHR TO FUEL STOR POOL HDR DRN NU-VLV Seismic Class 1 (1)

Attachment 1C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional Ioc. Description Catalog profile SEISMIC CLASS H1EC EC-V161 SKIM SURG TK LT-4661 B ISLN VLV NU-VLV Seismic Class 1 (I)

HIEC EC-V162 F/D OTL HDR TST CONN LN DRN V NU-VLV Seismic Class 1 (I)

H1EC EC-V1 63 FPCCS HX OTL HDR LN VT VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V166 FUEL PMP AP211 SUCT DRN V NU-VLV Seismic Class 1 (I)

H1EC EC-V1 67 FUEL PMP BP211 SUCT LN DRN V NU-VLV Seismic Class 1 (I)

H1EC EC-V172 FUEL PMP AP211 SUCT FLSH CONN NU-VLV Seismic Class 1 (I)

H1EC EC-V173 FUEL PMP AP211 DSCH FLSH CONN NU-VLV Seismic Class 1 (I)

H1EC EC-V1 74 FUEL PMP BP211 SUCT FLSH CONN NU-VLV Seismic Class 1 (I)

H1EC EC-V175 FUEL PMP BP211 DSCH FLSH CONN NU-VLV Seismic Class 1 (I)

H1EC EC-V176 HX AE202 DSCH FLUSH CONN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V177 HX AE202 DSCH FLUSH CONN VLV NU-VLV Seismic Class 1 (I)

HiEC EC-V178 HX BE202 INLET FLUSH CONN VLV NU-VLV Seismic Class 1 (I)

HIEC EC-V179 HX BE202 DSCH FLUSH CONN VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V1 80 COND TO FUEL CSK STOR LN DRN V NU-VLV Seismic Class 1 (I)

H1EC EC-V182 FUEL CSK STOR GT SL DRN LN VT NU-VLV Seismic Class 1 (I)

H1EC EC-V1 83 FUEL POOL F/D DSCH HDR VNT VLV NU-VLV Seismic Class 1 (I)

H1EC -1A-E-202 HEAT EXCH- FUEL POOL NU-1HX Seismic Class 1 (I)

H1EC -IA-P-211 A' FUEL POOL COOLING PUMP NU-PMP Seismic Class 1 (I)

H1EC -1B-E-202 HEAT EXCH- FUEL POOL NU-1HX Seismic Class 1 (I)

H1EC -1B-P-211 B' FUEL POOL COOLING PUMP NU-PMP Seismic Class 1 (I)

H1EC -1ECEIS-AC652120 FM - FUEL POOL CLG PMP AP 211 NU-MNTR Seismic Class 1 (I)

H1EC -1ECEIS-AC652120 FM - FUEL POOL FILTER DEMIN ISOL VLV HV NU-MNTR Seismic Class 1 (I)

H1EC -1ECEIS-AC652120 FM - FUEL POOL FILTER DEMIN BYPASS VLV NU-MNTR Seismic Class 1 (I)

H1EC -1ECEIS-AC652120 FM - CLEAN-UP VALUE HV-4647 NU-MNTR Seismic Class 1 (I)

HIEC -1ECEIS-AC652120 FM - CLEAN-UP PROT INTLK IN TEST NU-MNTR Seismic Class 1 (I)

H1EC -1ECEIS-AC652120 FM - ISOLATION VLVS OVLD/PWR MONTR NU-MNTR Seismic Class 1 (I)

H1EC -1 ECEIS-BC652120 FM - FUEL POOL COOLING PUMP BP211 NU-MNTR Seismic Class 1 (I)

H1EC -1 ECEIS-BC652120 FM - FP CLG FLTR DEMIN BP HV-4689B NU-MNTR Seismic Class 1 (I)

H1EC -1ECEIS-BC652120 FM - FP FLTR DEMIN ISLN VLV HV-4676B NU-MNTR Seismic Class 1 (I)

H1EC -1ECEIS-BC652120 FM - FP CLG + TORUS WTR VLV HV-4648 NU-MNTR Seismic Class 1 (I)

H1EC -1 ECEIS-BC652120 FM - FP CLG-TORUS WTR CU PROT INTLK NU-MNTR Seismic Class 1 (I)

H1EC -1 ECEIS-BC652120 FM - FP CLG OVLD/PWR FAIL MONITOR NU-MNTR Seismic Class 1 (I)

Hi EC -1 ECFAL-4649A FUEL POOL CLG PMP A DISCH NU-ALRM Seismic Class 1 (I)

H1EC -1ECFAL-4649B PUMP BP-211 DISCH NU-ALRM Seismic Class 1 (I)

H1EC -lECFE-4649A *PUMP AP-211 DISCH NU-ELEM Seismic Class 1 (I)

H1EC -1ECFE-4649B *PUMP BP-211 DISCH NU-ELEM Seismic Class 1 (I)

H1EC -1ECFE-4682 *FUEL POOL CLG SYS FLOW NU-ELEM Seismic Class 1 (I)

H1EC -1ECFSL-4649A PUMP AP-211 DISCH NU-SW Seismic Class 1 (I)

H1EC -1ECFSL-4649B PUMP BP-211 DISCH NU-SW Seismic Class 1 (I)

H1EC -1 ECFT-4649A *PUMP AP-211 DISCH NU-TMTR Seismic Class 1 (1)

H1EC -1 ECFT-4649B *PUMP BP-211 DISCH NU-TMTR Seismic Class 1 (I)

HiEC -1ECHS-4689B2 FUEL POOL FILTER DEMIN BYPASS REF. DA NU-SW Seismic Class 1 (I)

H1 EC -1 ECHS-4693A2 FUEL POOL CLG PMP AP211 REF. DATA NU-SW Seismic Class 1 (I)

HI EC -1 ECHS-4693A3 MCC KEYSWITCH FOR 1A-P-211 NU-SW Seismic Class 1 (I)

H1 EC -1 ECHS-4693B2 FUEL POOL CLG PUMP BP211 REF. DATA NU-SW Seismic Class 1 (I)

H1EC -1ECHS-4693B3 MCC KEYSWITCH FOR 1B-P-211 NU-SW Seismic Class 1 (I)

H 1EC -1ECKY-4649A PUMP AP-211 LOW DISCH FLOW TIME DELAM NU-RELYI Seismic Class 1 (I)

H1EC -1ECKY-4649B PUMP BP-211 LOW DISCH FLOW TIME DELAM NU-TIMR Seismic Class 1 (I)

Attachment 1C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional loc. Description Catalog profile SEISMIC CLASS H 1EC -1 ECKY-A212 FUEL POOL CLG PMP AP211 NU-TIMR Seismic Class 1 (I)

H1EC -1ECKY-B212 FUEL POOL CLG PP BP 211 NU-TIMR Seismic Class 1 (I)

H1EC -1EC LR-4661B SKIMMER SURGE TANK B NU-REC Seismic Class 1 (I)

H1EC -1ECLSHH-4660 SKIMMER SURGE TANK "B" LEVEL SWITCH (( NU-SW Seismic Class 1 (I)

H1EC -1ECLSHL-4660 SKIMMER SURGE TANK "B" LEVEL SWITCH (( NU-SW Seismic Class 1 (I)

H1EC -1ECLSL-4667 FUEL STORAGE POOL LEVEL NU-SW Seismic Class 1 (I)

H1EC -1ECLSLL-4661A SKIMMER SURGE TK B NU-SW Seismic Class 1 (I)

H1EC -1ECLSLL-4661B SKIMMER SURGE TANK B NU-SW Seismic Class 1 (I)

H1EC -1EC LT-4660 *SKIMMER SURGE TANK "B" LEVEL CONTROl NU-TMTR Seismic Class 1 (I)

H1EC -1ECLT-4661A *SKIMMER SURGE TANK B NU-TMTR Seismic Class 1 (I)

HiEC -1ECLT-4661B *SKIMMER SURGE TANK B NU-TMTR Seismic Class 1 (I)

H1EC -1 ECLT-4667 *FUEL STORAGE POOL LEVEL NU-TMTR Seismic Class 1 (I)

H1EC -1ECLV-4660 *SKIMMER SURGE TK B MAKE-UP SUPPLY LI NU-VO Seismic Class 1 (I)

HIEC -1ECPSL-4669A INAK PER CP 80081223 NU-SW Seismic Class 1 (I)

H1EC -1ECPSL-4669B INAK PER CP 80081223 NU-SW Seismic Class 1 (I)

H1 EC -1ECPSV-4674A *FUEL POOL HTX AE202 RELIEF VALVE NU-SRV Seismic Class 1 (I)

HI EC -1ECPSV-4674B *FUEL POOL HTX BE202 NU-SRV Seismic Class 1 (I)

HIEC -1ECPT-4669A *FUEL POOL CLG PMP A SUCT NU-TMTR Seismic Class 1 (I)

H1EC -1ECPT-4669B *FUEL POOL CLG PMP B SUCT NU-TMTR Seismic Class 1 (I)

HIEC -1ECSV-4660 SKIMMER SURGE TNK LVL CNTRL / 1ECLV-4E NU-SV Seismic Class 1 (I)

H1EC -1 ECSV-4676A FOR HV-4676 A NU-SV Seismic Class 1 (I)

H1EC -1 ECSV-4676B FOR HV-4676 B NU-SV Seismic Class 1 (I)

H1EC -1 ECSV-4678 FOR HV-4678 NU-SV Seismic Class 1 (I)

H1EC -1ECSX-4692 *FUEL POOL HT EXCH OUT NU-ELEM Seismic Class 1 (I)

H1EC -1ECTE-4683 *FUEL POOL CLG PMP DISCH HDR SEE ENC NU-ELEM Seismic Class 1 (I)

H1EC -1ECTI-4683 FUEL POOL CLG DISCH HDR REF. DATA NU-IND Seismic Class 1 (I)

H1EC -1 ECTR-4683 FUEL POOL OUTLET TEMP NU-REC Seismic Class 1 (I)

H1EC -1ECTSH-4683 FUEL POOL CLG DISCH HDR NU-SW Seismic Class 1 (I)

H1EC -1 ECTT-4683-1 FUEL POOL CLG DISCH HDR NU-TMTR Seismic Class 1 (I)

H1EC -1 ECTT-4683-2 FUEL POOL CLG DISCH HDR REF. DATA NU-TMTR Seismic Class 1 (I)

H1EC -1ECV-007 "A" FUEL COOLING PUMP DISCHARGE CHEC NU-CKVL Seismic Class 1 (I)

HiEC -1ECV-011 FLTR DEMIN INLET OUTBD ISLN NU-AOV Seismic Class 1 (I)

HIEC -1ECV-012 FLTR DEMIN INLET INBD ISLN NU-AOV Seismic Class 1 (I)

H1EC -1ECV-013 *VALVE CLASS: HBC NU-MOV Seismic Class 1 (I)

H1EC -1ECV-014 *VALVE CLASS: HCC NU-AOV Seismic Class 1 (I)

H1EC -1ECV-015 *VALVE CLASS: HCC NU-CKVL Seismic Class 1 (I)

H1EC -1ECV-040 *VALVE CLASS: HBC NU-CKVL Seismic Class 1 (I)

HIEC -1ECV-100 *VALVE CLASS: HBC NU-MOV Seismic Class 1 (I)

H1EC -1ECV-169 *VALVE CLASS: CCA NU-MOV Seismic Class 1 (I)

H1EC -1 ECV-1 70 LP B EMERG MAKEUP TO FUEL POOL NU-MOV Seismic Class 1 (I)

H1EC -1 ECXAL-1 803 RSP TAKEOVER ALM LTS NU-IND Seismic Class 1 (I)

H1EC -1ECXAL-1 807 RSP TAKEOVER ALM LTS NU-IND Seismic Class 1 (I)

H1EC -1ECXAL-4600A AP211 INTLK IN TEST ALM NU-IND Seismic Class 1 (I)

H1EC -1ECXAL-4600B BP211 INTLK IN TEST ALM NU-IND Seismic Class 1 (I)

H1EC -1ECXIS-AC652120 LM - FUEL POOL CLG PMP AP 211 NU-LOGC Seismic Class 1 (I)

H1 EC -1 ECXIS-AC652120 LM - FUEL POOL CLG PMP AP 211 NU-LOGC Seismic Class 1 (I)

H1 EC -1 ECXIS-AC652120 LM - FUEL POOL FILTER DEMIN ISOL VLV HV. NU-LOGC Seismic Class 1 (I)

H1 EC -1 ECXIS-AC652120 LM - FUEL POOL FILTER DEMIN BYPASS VLV NU-LOGC Seismic Class 1 (I)

Attachment 1C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional loc. Description Catalog profile SEISMIC CLASS H1EC -1ECXIS-AC652120 LM - CLEAN-UP VALUE HV-4647 NU-LOGC Seismic Class 1 (I)

H1EC -1ECXIS-AC652120 LM - CLEAN-UP PROT INTLK IN TEST NU-LOGC Seismic Class 1 (I)

H1EC -1ECXIS-AC652120 LM - ISOLATION VLVS OVLD/PWR MONTR NU-LOGC Seismic Class 1 (I)

H1EC -1 ECXIS-AC652120 LM - ISOLATION VLVS OVLD/PWR MONTR NU-LOGC Seismic Class 1 (I)

H1EC -1ECXIS-BC652120 LM - FUEL POOL COOLING PUMP BP211 NU-LOGC Seismic Class 1 (I)

H1EC -1ECXIS-BC652120 LM - FUEL POOL COOLING PUMP BP211 NU-LOGC Seismic Class 1 (I)

HIEC -1ECXIS-BC652120 LM - FP CLG FLTR DEMIN BP HV-4689B NU-LOGC Seismic Class 1 (I)

H1EC -1ECXIS-BC652120 LM - FP FLTR DEMIN ISLN VLV HV-4676B NU-LOGC Seismic Class 1 (I)

HIEC -1ECXIS-BC652120 LM - FP FLTR DEMIN ISLN VLV HV-4678 NU-LOGC Seismic Class 1 (I)

H1EC -1ECXIS-BC652120 LM - FP CLG + TORUS WTR VLV HV-4648 NU-LOGC Seismic Class 1 (I)

H IEC -1ECXIS-BC652120 LM - FP CLG-TORUS WTR CU PROT INTLK NU-LOGC Seismic Class 1 (I)

HIEC -1ECXIS-BC652120 LM - FP CLG OVLD/PWR FAIL MONITOR NU-LOGC Seismic Class 1 (I)

H1EC -1ECXIS-BC652120 LM - FP CLG OVLD/PWR FAIL MONITOR NU-LOGC Seismic Class 1 (I)

H1EC -1 ECXV-4662A EFCV FOR PT-4662A NU-CKVL Seismic Class 1 (I)

HIEC -1ECXV-4662B EFCV FOR PT-4662B NU-CKVL Seismic Class 1 (I)

H1EC -1ECXV-4673A EFCV FOR PT-4672A & PI-4673A NU-CKVL Seismic Class 1 (I)

H1EC -1ECXV-4673B EFCV FOR PT-4672B & PI-4673B NU-CKVL Seismic Class 1 (I)

H1EC -1ECXV-4682A EFCV FOR FT-4682 LO NU-CKVL Seismic Class 1 (I)

HiEC -1ECXV-4682B EFCV FOR FT-4682 HI NU-CKVL Seismic Class 1 (I)

H1EC -1ECZS-4676A *FUEL POOL HTX OUTLET NU-SW Seismic Class 1 (I)

HIEC -1ECZS-4676B *FUEL POOL HTX OUTLET NU-SW Seismic Class 1 (I)

H1EC -1ECZS-4678 *FUEL POOL FILT DEMIN INLET NU-SW Seismic Class 1 (I)

HIEC 212103 PMP,FUEL POOL CLG 1AP211 NU-PAN Seismic Class 1 (I)

H1EC 212244 MOV EC-HV4689A FP FLTR DM BYP NU-PAN Seismic Class 1 (I)

H1EC 212254 MOV EC-HV4647 FUEL POOL M/U A NU-PAN Seismic Class 1 (I)

H1EC 222103 PMP,FUEL POOL CLG 1 BP211 NU-PAN Seismic Class 1 (I)

H1EC 222154 MOV EC-HV4648 FUEL POOL M/U B NU-PAN Seismic Class 1 (I)

H1EC 222244 MOV EC-HV4689B FUEL POOL DM NU-PAN Seismic Class 1 (I)

H1EC -EC-HS-4660 H& SWT FOR EC-HV-4660 TBPE NU-SW Seismic Class 1 (I)

H1EC -EC-HV-4647 OP/1 -V1 69 SPNT FUEL STOR PL FL 52-212254 NU-MO Seismic Class 1 (I)

H1EC -EC-HV-4648 OP/1-V170 SPNT FUEL STOR PL FL 52-222154 NU-MO Seismic Class 1 (I)

H1EC -EC-HV-4676A OP/1-V011 F/D OUTBD INL ISLN NU-AO Seismic Class 1 (I)

H1 EC -EC-HV-4676B OP/1-VO12 F/D INBD INL ISLN NU-AO Seismic Class 1 (I)

H1 EC -EC-HV-4678 OP/1-VO14 F/D OTL ISLN AOV NU-AO Seismic Class 1 (I)

H1 EC -EC-HV-4689A OP/1-V013 F/D BYPASS MOV 52-212244 NU-MO Seismic Class 1 (I)

H1EC -EC-HV-4689B OP/1-V100 F/D BYPASS MOV 52-222244 NU-MO Seismic Class 1 (I)

H1EC -HS-4647 FUEL POOL CLG HV-4647 C/SW NU-SW Seismic Class 1 (I)

HIEC -HS-4648 FUEL POOL CLG HV-4648 C/SW NU-SW Seismic Class 1 (I)

H1 EC -HS-4676A FUEL POOL CLG HV-4676A C/SW NU-SW Seismic Class 1 (I)

H1E C -HS-4676B FUEL POOL CLG HV-4676B C/SW NU-SW Seismic Class 1 (I)

HIEC -HS-4678 FUEL POOL CLG HV-4678 C/SW NU-SW Seismic Class 1 (I)

H1EC -HS-4689A FUEL POOL CLG HV-4689A C/SW NU-SW Seismic Class 1 (I)

H1EC -HS-4689B1 FUEL POOL CLG HV-4689B C/SW NU-SW Seismic Class 1 (I)

HIEC -HS-4693A1 FUEL POOL CLG PMP AP211 C/SW NU-SW Seismic Class 1 (I)

HIEC -HS-4693B1 FUEL POOL CLG PMP BP211 C/SW NU-SW Seismic Class 1 (I)

H1GU -1GUPDR-EC141 SPARE, BLUE SCALE NU-REC Seismic Class 1 (I)

HIKJ -1A-G-400-FUEL IN. EMERGNCY DIESEL GENERATOR FUEL INJE, NU-GEN Seismic Class 1 (I)

HIKJ -1AC420-RECT-ASEA EDG RECTIFIER ASSEMBLY SELECTOR SVA NU-MISCE Seismic Class 1 (I)

Attachment 1C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional loc. Description Catalog profile SEISMIC CLASS H1 KJ -1 B-G-400-FUEL IN, EMERGNCY DIESEL GENERATOR FUEL INJE' NU-GEN Seismic Class 1 (I)

H1KJ -1BC420-RECT-ASc B EDG RECTIFIER ASSEMBLY SELECTOR SV NU-MISCE Seismic Class 1 (I)

H1KJ -1C-G-400-FUEL IN, EMERGNCY DIESEL GENERATOR FUEL INJEiNU-GEN Seismic Class 1 (I)

H1KJ -1CC420-RECT-ASE C EDG RECTIFIER ASSEMBLY SELECTOR SV NU-MISCE Seismic Class 1 (I)

H1KJ -1D-G-400-FUEL IN, EMERGNCY DIESEL GENERATOR FUEL INJE'NU-GEN Seismic Class 1 (I)

H1KJ -1DC420-RECT-AS5 D EDG RECTIFIER ASSEMBLY SELECTOR SV' NU-MISCE Seismic Class 1 (I)

H1SE -1SEVR-271RMEC5, IRM E VOLTAGE PRE REGULATOR NU-SGCD Seismic Class 1 (I)

H1SE -1SEVR-291RMEC5, IRM E VOLTAGE REGULATOR NU-CONT Seismic Class 1 (I)

H1SE -1SEXI-M1IRMEC51 IRM E POWER INDICATOR NU-IND Seismic Class 1 (I)

H1SE -1SEXY-Z131REC51 MEAN SQ ANAL. MOD. IRM E NU-SGCD Seismic Class 1 (I)

H1BC BC-V094 RHR LOOP B DSCH TO FPCCS ISO V CB NU-VLV Seismic Class 1 (I)

H1BC BC-V626 B RHR TO FPCC VENT NU-VLV Seismic Class 1 (I)

H1BC BC-V627 B RHR TO FPCC VENT NU-VLV Seismic Class 1 (I)

H1BC BC-V628 A RHR TO FPCC VENT NU-VLV Seismic Class 1 (I)

H1BC BC-V629 A RHR TO FPCC VENT NU-VLV Seismic Class 1 (I)

H1EA EA-V584 SERV WTR M/U TO FPCCS DRN VLV NU-VLV Seismic Class 1 (I)

H 1 EA- 1 -EA-V585 SERV WTR M/U TO FPCCS VNT VLV NU-VLV Seismic Class 1 (I)

H 1 EC EC-V020 RX WELL DR HDR-FPCC PMP SUC HDRISO V NU-VLV Seismic Class 1 (I)

H1EC EC-V084 FPCCS HX BYPASS VLV NU-VLV Seismic Class 1 (I)

H1EC EC-V163 FPCCS HX OTL HDR LN VT VLV NU-VLV Seismic Class 1 (I)

H1EG -1EGSX-2578A A' FPCC HTX SACS DR PT SACS GRAB SMPL NU-ELEM Seismic Class 1 (I)

H1EG -1EGSX-2578B B FPCC HTX SACS DR PT SACS GRAB SMPL NU-ELEM Seismic Class 1 (I)

H1 EG -EG-HV-2314A OPN138 F/POOL CLG HX SUP ISLN 52-21212 NU-MO Seismic Class 1 (I)

H1EG -EG-HV-2314B OPN140 F/POOL CLG HX SUP ISLN 52-22212' NU-MO Seismic Class 1 (I)

H1EC -1 EC021 W001 WATER FROM VALVES BC-V023 & BC-V094 T, NU-WELD Seismic Class 1 (I)

H1EC -1EC021W002 WATER FROM VALVES BC-V023 & BC-V094 Ti NU-WELD Seismic Class 1 (I)

H1EC -1EC021W003 WATER FROM VALVES BC-V023 & BC-V094 T, NU-WELD Seismic Class 1 (I)

H1EC -1EC021W004 WATER FROM VALVES BC-V023 & BC-V094 T, NU-WELD Seismic Class 1 (I)

Hope Creek Nuclear Generating Station S&L Report No. SL-01 1553 Project No. 12800-217 Rev. 1 Seismic Walkdown Report ATTACHMENT 2 - SEISMIC WALKDOWN EQUIPMENT LIST (SWEL)

SL Report No.: SL-011553 Hope Creek - Seismic Walkdown Equipment List Rev. No. 2 (SWEL)

January 29, 2014 (Sorted by EQ. Class)

EQsk Safety New orr Ne IPEEE Anchored Concrete or to Risk No. AWB # Comp. ID System EQ. Component Description Bldg. Elev. Room NO. Significant Replaced Notes Class Function Enhanced Structure (Y/N/NA) (Y) (Y=11N0) 1 HC-04 TD-9773A1 GQ 0 SW Fan Intake Damper SWIS 122 306 3,4,5 1 2 HC-07 AS501 EA 0 Traveling Screen SWIS 102 TS RM 3,4,5 Y 1Nerif.

3 HC-12 10S212 FC 0 RCIC Steam Turbine Reactor 54 4110 Y 2,3 1 4 HC-24 1-BC-V023 BC 0 RHR Loop A DSCH to FPCCs ISO V Reactor 102 4329 4 0 (1)

Control 5 HC-39 PR-R623A BB 0 Recorder-Reactor Pressure CH A 137 5510 2 0 Diesel Control 6 HC-40 FSL-9587A GK 0 Switch-Control Room AV415 Air Flow Diesel 155 5602 1,2,3,4,5 1/Verif.

_____________ _______Diesel _____

Control 7 HC-40 HD-9589A1 GK 0 CRS AVH403 Return Air Damper Diesel 155 5602 Y 1,2,3,4,5 1 8 HC-43 FSL-9558B2 GM 0 Switch-DAPRS AV408 Air Flow Control 155 5620 1,2,3,4,5 iNerif.

Diesel 9 HC-01 10B553 PH 1 Intake Structure 480V MCC SWIS 93 203 Y 3,4,5 1 Defer to RFO IR2 10 HC-21 10B212 PH 1 480V MCC Reactor 102 4309 Y 1,3,4,5 1 Defer to RFO Control 11 HC-37 10B411 PH 1 Backup Power Supply 480V MCC Diesel 130 5417 Y 3,4,5 1 Defer to RFO 12 HC-28 10D450 PJ 2 250V DC SWGR Channel A Control 54 5129 Y 2,3,4 1 Defer to RFO

_____ ~~Diesel ____

13 HC-37 10B410 PG 2 Substation 480V SWGR Control 130 5417 Y 2,3,4,5 1 Defer to RFO

____ ______ Diesel ____

Control 14 HC-37 10B450 PG 2 Substation 480V SWGR Diesel 130 5417 Y 2,3,4,5 1 Defer to RFO 15 HC-37 10D410 PK 2 125VDC Bus SWGR Control 130 5417 Y 2,3 1 Defer to RFO 16 HC-37 10A401 PB 3 4.16kV SWGR CHN A

~~Diesel Control 130 5417 Y 3,4,5 1 Defer to RFO 16 HC-37 ~Diesel ____

17 HC-36 1AX400 PG 4 Transformer 4.16KV to 480V Control 130 5417 Y 3,4,5 1iNerif.

Diesel ____ _____

18 HC-12 10P203 BD 5 Turbine-Driven Pump RCIC Reactor 54 4110 2,3 iNerif.

19 HC-12 10P219 FC 5 RCIC Gland Seal Pump Reactor 54 4110 2,3 0 20 HC-12 BP228 BD 5 RCIC ECCS Jockey Pump Reactor 54 4110 3 iNerif.

21 HC-13 10P204 BJ 5 Main HPCI Pump Reactor 54 4111 2,3,4, iNerif.

22 HC-13 AP228 BJ 5 "A"ECCS Jockey Pump Reactor 54 4111 3 iNerif.

23 HC-21 AP210 EG 5 SACS Pump A Reactor 102 4309 4 1 Control 24 HC-40 AP400 GJ 5 CR Chilled Water Recirc Pump Diesel 155 5602 Y 1,2,3,4,5 iNerif.

Control 25 HC-46 AP414 GJ 5 ATSC Chilled Water Pump Diesel 178 5704 Y 1,2,3,4,5 iNerif.

26 HC-47 AP401 JE 5 Diesel Fuel Transfer Pump Control 54 5110A Y 3,4,5 iNerif.

___ ________________________ ieel ___ ______ _______ ______ _____Diesel____

P1

SL Report No.: SL-011553 Hope Creek - Seismic Walkdown Equipment List Rev. No. 2 (SWEL)

January 29, 2014 (Sorted by EQ. Class)

EQsk Safety Re or IPEEE Anchored Concrete or to No. AWB # Comp. ID System EQ Component Description Class Bldg. Elev. Room NO. Significant (YNN) Function Replaced y) E Enhanced Strcre Structure Notes

(/NINA) F n (Y) (Y=I/N=O) 27 HC-47 BP401 JE 5 Diesel Fuel Transfer Pump Control 54 5110A 3,4,5 1/Verif.

_____________Diesel___________

28 HC-02 AP502 EA 6 SWS Pump SWIS 93 204 V 3,4,5 1/Verif.

29 HC-02 CP502 EA 6 C Service Water Pump SWIS 93 204 Y 3,4,5 Y 1Nerif.

30 HC-13 10P215 FD 6 Condensate Pump Reactor 54 4111 2,3,4 0 31 HC-14 CP202 BC 6 RHR Pump C Reactor 54 4114 Y 3,4 1 32 HC-15 1AP202 BC 6 RHR Pump A Reactor 54 4113 Y 3,4,5 INerif.

R/Core 33 HC-16 AP206 BE 6 Core Spray Pump A Spray 54 4118 Y 3 INerif.

34 HC-13 HV-2292A EG 7 AOV HV2292A (HPCI) Reactor 54 4111 2,3,4 0 35 HC-16 HV-2325A EG 7 AOV HV2325A (CSS) Reactor 54 4118 V 3 0 36 HC-21 HV-2522A EG 7 TACS Supply Isolation Valve Reactor 102 4309 3,4,5 0 Control 37 HC-30 HV-2395C EG 7 DG C Aux HXs Return Isolation-AOV 77 5209A 3,4 0 Diesel Control 38 HC-43 TV-9667A GJ 7 AOV-1E Pnl Rm CIr AVH408 Bypass Diesel 155 5620 1,2,3,4,5 0 39 HC-02 HV-2197A EA 8 MOV-Strainer Discharge to Fish Trough SWIS 93 204 3,4,5 0 R/Torus 40 HC-08 HV-F062 FC 8 MOV-RCIC Vac Brkr Isolation Valve 77 4102 Y 3,5 0 Area 41 HC-08 HV-F075 ED 8 MOV-Vacuum Isolation Valve R/Torus 77 4102 Y 3,5 0 Area 42 HC-44 HV-F031B BE 8 MOV-CS Loop B Min Flow Bypass R/CS Pmp 7 4102 43 HC-11 HV-F006B BC 8 MOV-RHR PMP Suction to B Loop R/B RHR m 54 4109 4 0

______ ___________________Pmp Rm 44 HC-12 HV-4282 FC 8 MOV-RCIC Turbine Trip/Thrtl Valve Reactor 54 4110 3 0 45 HC-12 SV-2293A EG 8 SOV-RCICPump Room Unit Cooler A Reactor 54 4110 3 V 0 46 HC-13 HV-F001 FD 8 MOV HPCI Turb Supply VLV Reactor 54 4111 Y 2,3,4 0 47 HC-13 HV-F004 BJ 8 MOV-PMP Suction From CST Reactor 54 4111 13, 0 R/RHR HX 48 HC-19 HV-2512A EG 8 MOV-RHR HX AE201 Isolation VLV RRm 77 4214 Y 3,4,5 0 Reactor/Dr 49 HC-20 HV-FO1 1A AE 8 MOV-FW Isol. VLV Inside Cont'nt well 130 4220 3,5 0 Defer to RFO AE 8 MOV-FW Iso. VLV Inside Cont'nt Reactor/Dr 10 423,0 DertoRO R2 50 HC-20 HV-F011B ywell , 4 Reactor/Dr 51 HC-20 HV-F016 AB 8 MOV-Inboard MSIV Drain Reactor/Dr ywellII 102 4220 Y 2 0 Defer to RFO Reactor/Dr 52 HC-20 HV-F076 FC 8 MOV-RCIC STM Warmup Isol VLV yell 102 4220 Y 3,5 0 Defer to RFO

_____________________ ______________________ ywell ____ I_____ I_____ I_____ I____ ______

I____________

P2

SL Report No.: SL-011553 Hope Creek - Seismic Walkdown Equipment List Rev. No. 2 (SWEL)

January 29, 2014 (Sorted by EQ. Class)

EQ. Risk Saey New or IPE Anchored Coceer to No. AWB # Comp. ID System EQ. Component Description Bldg. Elev. Room NO. Significant Safeut Replaced IPEEE Concrete or Notes Class (Y/N/NA) Function Enhanced Structure (Y)(Y=1/N)

- HG---20 8V-362B S4 8 PSV F01 3A ADS Le*ic SOV R 4-02 4220 -Y 2,4 Y 0 Note 2 Reactor/Dr 53 HC-20 SV-3665B SN 8 PSV-F013E ADS Logic D SOV Hywell 130 4220 Y 2,4 Y 0 Defer to RFO R/Steam 54 HC-22 HV-F013 BD 8 MOV-RCIC FW Isol. VLV Tunnel Tunnel C_ 125 4316 Y 3 0 Defer to RFO R/CRD 55 HC-23 BFSV-139117Cl BF 8 SRV-Pilot Scram Valve (Type of 93) 102 4328 1 0 Alley 56 HC-34 HV-2225A EA 8 SWS MOV SWIS 79 204 3,4,5 0 57 HC-38 SV-9768 GL 8 SOV-RSP Room OVH316 Control 137 5501 2,3,4,5 0

_____Diesel R/Torus 58 HC-48 HV-F04A BC 8 MOV-RHR PMP A Torus Suction 54 4102 Y 3,5 0 Area H 59 HC-49 HV-2314A EG 8 Fuel Pool Cooling HX SUP Isol. MOV Reactor 162 4608 4 0 (1) 60 HC-30 CV412 GM 9 Diesel Gen Room Recirc Fan Control Disl 7i20 ,, /erif.

_____ ~~~Diesel Control

~ 51 ,,

61 HC-30 GV412 GM 9 Diesel Gen Room Recirc Fan Diesel 77 5210 Y 3,4,5 1/erif.

62 HC-09 FVH211 GR 10 Core Spray PMP Rm Unit Cooler Fan Reactor 54 4104 3 1 63 HC-12 AVH208 GR 10 RCIC PMP Rm Unit Cooler Fan Reactor 54 4110 3 1 64 HC-12 BVH208 GR 10 RCIC PMP Rm Unit Cooler Fan Reactor 54 4110 3 1 65 HC-13 AVH209 GR 10 HTEXCH A HPCI Unit Cooler Reactor 54 4111 2,3,4 1/Nerif. R2 66 HC-14 CVH210 GR 10 RHR Pmp Rm Unit Cooler Fan Reactor 54 4114 3,4 1 Control 67 HC-38 VH316 GL 10 Remote Shutdown PNL Rm Air Handler Diesel 137 5501 Y 2,3,4,5 1Nerif.

______Diesel Control 68 HC-43 AVH408 GM 10 Supply Fan-Diesel Area Diesel 155 5620 Y 1,2,3,4,5 1Nerif.

Control 69 HC-40 AK400 GJ 11 Control Area Chiller Diesel 155 5602 Y 1,2,3,4,5 1Nerif.

Diesel ___

Control 70 HC-46 AK403 GJ 11 Control Area Chiller Diesel 178 5704 Y 3,4,5 1Nerif.

71 HC-32 1YF402 PN 14 120VAC Fuse Panel Control 102 5302 Y 2,3,4,5 1 Diesel ____________

Control 72 HC-38 1AJ481 PN 14 120VAC UPS Distribution Panel Diesel 137 5501 Y 1,2,3,4,5 1 Defer to RFO Diesel 73 HC-26 10D421 PJ 15 250VDC Station Battery Control 54 5104 Y 3 Y 1 73 HC26 10421Diesel 74 HC-27 10OD431 PJ 15 iBatteries Channel B Diesel Control 54 54 5128 12 Y 1,2,3,4,5 1,3451 1 P3

SL Report No.: SL-011553 Hope Creek - Seismic Walkdown Equipment List Rev. No. 2 (SWEL)

January 29, 2014 (Sorted by EQ. Class)

Risk Saey New or IPEEE Anchored Concrete or to Noe No. AWB # Comp. ID System Component Description Bldg. Elev. Room NO. Significant Replaced Notes Class Function Enhanced Structure (Y/N/NA) (Y) (Y=I/N=O) 75 ~~~~Control 15 51 ,

75 HC-42 1CD447 PK 15 125V DC Channel C Batteries el Diesel 155 5614 34 1 76 HC-28 10D423 PJ 16 HPCI 250V DC Battery Charger Control 54 5129 Y 2,3,4 1Nerif.

Diesel __________

77 ~~~~Control 54 53234 77 HC-29 10D433 PJ 16 Battery Charger Channel B Diesel 54 5130 2,3,4 1 Control 78 HC-38 1AD481 PN 16 480V to 130V Inverter 137 5501 Y 1,2,3,4,5 1/Verif. Defer to RFO Diesel 1 Control 79 HC-41 1CD444 PK 16 125V DC Channel C Battery Charger Diesel 155 5613 Y 3,4,5 I/Verif.

80 HC-33 1AG400 KJ 17 Division A Diesel Control 102 5307 Y 2,3,4,5 1Nerif.

Diesel 81 HC-18 LT-7854 BB 18 Xmtr-Reactor Water level. R/Corr'dr 77 4203 1,2,3 0 82 HC-40 FT-9589A GK 18 Xmtr-CRS AVH403 Supply Air Diesel 155 5602 1,2,3,4,5 INerif.

83 HC-43 FT-9558A GM 18 Xmtr-Air Flow Low Control 155 5620 2,3,4,5 1/Nerif.

Diesel Control 84 HC-46 FT-9666A1 GJ 18 Xmtr-Chw Loop A AK403 Outlet Diesel 178 5704 2,3,4,5 Y iNerif.

85 HC-16 TS9384A GR 19 To UC AVH211-Temp Switch R/Core 54 4118 3 Y 1 Spray Rm 86 HC-16 TS9384E GR 19 To UC AVH211-Temp Switch R/Core 54 4118 3 Y 1 R2

_________Spray Rm 87 HC-50 TS-9774A GQ 19 Intake Struct Pump A&C Rm-Temp Switch SWIS TS Room 3,4,5 1 88 HC-02 CC581 GQ 20 Intake Struc HVAC Control Panel SWlS 93 204 3,4 1 89 HC-03 CC516 EA 20 Service Water Pump Panel SWIS 107 204 3,4 1/Verif.

90 HC-10 1CC652 RL 20 1-E Solid State Logic Cabinet Channel C ontrol 102 5302 Y 1,2,3,4,5 1 Soli LgicCabiet Stte hannl C Diesel R/CRD 91 HC-17 DC281 GU 20 Unit Cooler Control Panel PmpRm Pmp Rm 77 4202 3,4 1Nerif.

92 HC-21 AC201 EA 20 SACS Control Panel Reactor 102 4309 Y 3,4 1/Verif.

93 HC-21 AC281 GU 20 Unit Cooler Control Panel Reactor 102 4309 3,4 INerif.

Control 94 HC-32 10C620 BJ 20 HPCI Relay Vertical Board & Relay Pan Diesel 102 5302 Y 2,3,4 1 95 HC-35 1CC422 KJ 20 DG Remote Control Generator Panel Control 130 5414 2,3,4,5 1/Verif.

Diesel P4

SL Report No.: SL-011553 Hope Creek - Seismic Walkdown Equipment List Rev. No. 2 (SWEL)

January 29, 2014 (Sorted by EQ. Class)

EQRisk New or Anchored to No. AWB # Comp. ID System Component Description Bldg. Elev. Room NO. Significant Safety Replaced IPEEE Concrete or Notes Class Function Enhanced Structure (Y/N/NA) (Y) (Y=I/N=O)

Control 96 HC-36 1AC423 KJ 20 DG Remote Panel Diesel 130 5416 Y 2,3,4,5 1Nerif.

_______ ~~Diesel______

Control 13 54623451er.

97 HC-36 AC422 KJ 20 Rem Gen Cntr Panel Diesel 10 51 ,,, Nrf Control Diesel 98 HC-A3 AC486 GM 20 Panel-Diesel Area HVAC Auxiliary Diesel 155 5620 3,4,5 1Nerif.

R2 Control 100 HC-46 CC483 GM 20 Panel-Diesel Area HVAC Diesel 178 5704 3,4,5 1/erif.

101 HC-21 A1E201 EG 21 HX A1E201SACS Reactor 102 4309 Y 3,4 1ferif.

102 HC-25 AT205 EG4- 21 SAC Expansion Tank Reactor 201 4706 Y 3,4 1 103 HC-46 AT413 GJ 21 CHS Expansion Tank Control 178 5704 3,4 1

________ ___________________ Diesel I ____

I_____ I____ I____ I__ I__I Notes: 1. SWEL 2 component

2. Component is removed from SWEL. See Section A.6.3.1.

3. The numbering sequence for components 54 to 104 were renumbered 53 to 103 respectively due to the removal of SV-3652B.

3. The elevations of items 9, 49 & 50 were revised to match the SWC's. I R2 P5

Hope Creek Nuclear Generating Station S&L Report No. SL-011553 Project No. 12800-217 Rev. I Seismic Walkdown Report ATTACHMENT 4 - SEISMIC WALKDOWNS ENGINEER CERTIFICATIONS

'I 1) 4 dii s

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~17 (Trtufitatr of Ar4iflurmrnt

/1 941is is to (1rrtifij tiatt 0')

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14as jormpteteb tits §QU(6 walkbouwn §rrrnming anb-53,eismir Evaluation Tratining Tourser

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8 T.e'rb §-epeMberr 14-1, 4A-- ý-. 7c~r Neil P. Smith, Comn ionwealth Edison SQUG Chairman David A. Freed, MPR Associates Robert P. gassawarea. EPRI SQUG Training Coordinator SQUG Program Maneager

Certificate of Completion Alex Coologeorgen Training on Near Term Task Force Recommendation 2.3

- Plant Seismic Walkdowns June 27, 2012 Date

/?,t,.0KW,34ýý Robert K. Kassawara EPRI Manager, Structural Reliability & Integrity

a i- ELECTRICPOWER ETSEARCH INSTITUTE Certificate of Completion John Skomorucha Training on Near Term Task Force Recommendation 2.3

- Plant Seismic Walkdowns June 21, 2012 /f, A? 914ýý Date Robert K. Kassawara EPRI Manager, Structural Reliability & Integrity

ef~ra I RESEARCH IH5IITUIE Certificateof Completion Jeffrey Puskar Training on Near Term Task Force Recommendation 2.3

- Plant Seismic Walkdowns June 21, 2012 cf44#.

• Date Robert K. Kassawara EPRI Manager, Structural Reliability & Integrity

CERTFICAEOACIVMT THIS is TO CERTIFYT THAT HAS COMPLUTED THE SQUG WAKDOWNV  :".:-.. . .

AND SEISMIC EVALUATION. T-RA ING COU RSE DECEMBEER10-4 2001 Richard G. Starck", MPR *ssociates John K* Richards, Duke Energy

', SQUG Training Coordinator SQUG Chairman Robert P. Kassa EPRI..

ii~ - QUG Program Manager

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• ,,, *l* "'"l~*,l , *.l l ,, .*,,, "",, l, , .ll b* ,,, *,* , , *, ll l l, ' ,. , iJ",

Certificateof Completion Joshua Hammel Training on Near Term Task Force Recommendation 2.3

- Plant Seismic Walkdowns October 11, 2013 Date Jdon Skomorucha Sargent & Lundy

Hope Creek Nuclear Generating Station S&L Report No. SL-0l11553 Project No. 12800-217 Rev. 1 Seismic Walkdown Report ATTACHMENT 5 - CHECKLIST FOR PEER REVIEW OF SSC SELECTION

Sheet I of 2 Peer Review Checklist for SWEL Instructions for Completing Checklist This peer review checklist may be used to document the review of the Seismic Walkdown Equipment List (SWEL) in accordance with Section 6: Peer Review. The space below each question in this checklist should be used to describe any findings identified during the peer review process and how the SWEL may have changed to address those findings. Additional space is provided at the end of this checklist for documenting other comments.

1. Were the five safety functions adequately represented in the SWEL 1 selection? YZ NO

2. Does SWEL 1 include an appropriate representation of items having the following sample selection attributes:

a. Various types of systems? YZ NEI

b. Major new and replacement equipment? YZ NO

c. Various types of equipment? YZ NO All classes of equipment were included in the SWEL except for Class 12 and Class

13. HCGS does not have any Seismic Category I equipment in these equipment classes.

d. Various environments? YZ NR

e. Equipment enhanced based on the findings of the IPEEE (or equivalent) program? YZ NO Per "PSEG Response to Generic Letter 88-20, Supplement 4, Individual Plane Examination for External Events (IPEEE) for Severe Accident Vulnerabilities, Hope Creek Generating Station, Docket No. 50-534", Section 7.1, no vulnerabilities were found owing to external events at HCGS. Therefore, no IPEEE enhanced equipment was included in the SWEL.