Text

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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0 PSEG NUCLEAR LLC Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report SL Report No.: SL-01 1553 Rev. No. 2 January 29, 2014 Page No. vi 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.

REFERE NCES.............................................................................................

20 ATTACHMENTS ATTACHMENT 1

ATTACHMENT lB ATTACHMENT IC ATTACHMENT 2 -

ATTACHMENT 3 ATTACHMENT 4 -

ATTACHMENT 5 -

ATTACHMENT 6 -

A -

BASE LIST 1-SCREENING OF HOPE CREEK SEISMIC IPEEE COMPONENTS

- BASE LIST 1-SHUTDOWN COMPONENT LIST (UFSAR TABLE 9A-2)

- BASE LIST 2-COMPONENTS ASSOCIATED WITH FUEL POOL COOLING

-SEISMIC WALKDOWN EQUIPMENT LIST (SWEL)

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

-SEISMIC WALKDOWNS ENGINEER CERTIFICATIONS

-CHECKLIST FOR PEER REVIEW OF SSC SELECTION WALKDOWNS PERFORMED DURING RFO18 JR2

SL Report No.: SL-011553 0 PSEG Rev. No. 1 November 21, 2012 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 D E 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.

S W E L............................................................................................................................

12

6.

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

13 6.1.

PR E PA R A T IO N............................................................................................................

13 6.2.

AREA WALK-BYS (AWB) AND SEISMIC WALKDOWNS.......................... 13 6.3.

R E 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

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 R2 See Attachment 6 for the results of the walkdowns performed during RFO 18.

o: SEG NUCLEAR LLC i-lope Creek Nuclear Genierating Station 12800-217 Seismnic Walkdown Report S

R.port No.: SLr011553 Rev. No. 2 January.29, 2014 Page No. iii PSEG Nucloer (IPSEG)

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)

Rev,, 2 Prepared by:

Date, Prow0edt Aýsociate O: e -,b y

i....-.-

Sfkpmorucha t SeniorProject Associ at*e J5] M'.os~lemian Senior Manager Approved by:

N.T Shotv 1,129,/20,14 D~tt:

Date zote Program ManagCr

0 PSEG NUCLEAR LLC Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report SL Report No.: SL-011553 Rev. No. 1 November 21, 2012 Page No. ii II 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

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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."

0 PSEG NUCLEAR LLC Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Re-oort SL Report No.: SL-0l11553 Rev. No. I November 21, 2012 Page No. 3 of 20 R2 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.

Diameter less than or equal to 12 in Reactor pressure vessel, shroud Control rod drive (CRD) housings Fuel assemblies CRD restraint bellows and stabilizer Primary containment, RPV pedestal, and biological shield wall 2.0 1.0 2.0 1.0 3.0 2.0 4.0 2.0 6.0 4.0 7.0 4.0 (vert.)

6.0 (horiz.)

2.0 4.0

o PSEG NUCLEAR LLC Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report

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[ R2 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 systems (pipe diameter in excess of 3

12 inches)(2)

Small diameter piping systems (pipe diameter equal to or less than 1

2 12 inches)

Welded steel structures Bolted steel structures 2

4 2

4 7

5 Prestressed concrete structures Reinforced concrete structures 4

7

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] 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

Joseph Baker X

X 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.

SL Report No.: SL-0 11553 0

PSEG Rev. No. 2 January 29, 2014 R2 NUCLEAR LLC Page No. 8 of 20 IR Hope Creek Nuclear Generating 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 I R2 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 01 Refueling 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.

SL Report No.: SL-01 1155 3 0 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. I R2 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.

SL Report No.: SL-Ol 115 53 0 PSEG 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 NUCLEAR LLC Hope Creek Nuclear Generating Station 12800-217 Seismic Walkdown Report SL Report No.: SL-011553 Rev. No. 2 November 21, 2012 Page No. 15 of 20 1 R2 Table 6-1: Hope Creek - Potentially Adverse Seismic Conditions Notification Date AWB N C SWC No.

Description Status Comments No.

jCreated No.

20577885 20578051 20577886 20577503 20578213 10/08/2012 10/10/2012 10/08/2012 HC-07 CC581 CC581 1 CC652 SWIS panel anchorage SWIS panel CC581 anchorage SSW Traveling Screen Anchor Bolts SWIS Transient Loads CC581 CLOSED COMPLETED Bolts Wire Brushed 10/11/2012 Tools have been removed 10/05/2012 Reattached hanging cable Closed 10/12/12 Rescreen based on Notification 20578051 Tech. Eval.

completed, revised Calc 646-008 to reflect as-built condition Checklist Q. 3 was "No". After cleaning off the corrosion the inspection could be completed and Box was marked "Yes" Checklist Q. 7 was "No". After removing items to alleviate the seismic interaction, Box was marked "Yes" Checklist Q. 10 was "No". After reattaching hanging cable to alleviate the seismic interaction, Box was marked "Yes

10/05/2012 1 HC-02 10/12/2012 Abandon cable Connector plug

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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.

SL Report No.: SL-0l 115 53 0 PSEG 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 Fukushima Near-Term Task Force Recommendation 2.3: Seismic, June 2012 of 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 I A-BASE LIST I A-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 1 R2

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

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

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2 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 1 BJ484 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 I E 480VAC MCC IOB451 DIV A/IOB461 DIV Control 5411 130' No 5

B/10B471 DIV C/10B481 DIV D Diesel ACP 1OB450 CLASS 1 E 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

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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 1 BD481 1 BD481 & 1 BD482 AUCTNEERNG CIRC INCL.

Control 5448 124' No 2

INVERTER,STATIC SWITCH LOGIC CIRCUIT, 480-130 AC-Diesel DC VOLT RECT.

ACP 1 CD481 1 CD481 & 1 CD482 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 1 DD481 & 1 DD482 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 1 AC421 LOCL GEN CNTRL PNL 1 AC421 / 1 BC421 / 1 CC421/

Control 4304 /

102' No 7, 5 C-1 DC421 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-I DC422 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 1 A-C428 D/G LOAD SEQUENCE PANEL I A/B/C/D - C428 Control 5410 130' No 43, 5 C 137,138, Diesel I

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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 1 AC652 PNL 1 AC652/1 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 Individual Plant Examination for External Events

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July 1997 Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components k-

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ng~$~h ~CM CAC 1GSHV-4978 N2 SUPPLY ISOLATION VALVE Reactor 4317 102' Yes C-291 CAC 1 GSHV-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 11 558A/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 Diesel F

CHS TV9667A AOV TV9667A /B Control 5620 162 Yes C-208 I_

_Diesel I

3 -

62

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HOPE GREEK GENERATING STATION Individual Plant Examination for External Events

(

July 1997 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 1 A /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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July 1997 HOPE CREEK GENERATING STATION Individual Plant Examination for External Events Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components 14__________

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~~'~~~&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 I AD318/1 BD318/1 CD318/1DD318318 Rad I

DCPI IAD417 125VDC I E 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 1 E 25OVDC BUS IOD450 DIV A/

Control 5128(near) 54' No 7,5 I OD460 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/ I CD41 I-DIV C/I DD41 I-DIV D Diesel DCP I CD447 125 VDC BAT 1 CD447-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

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HOPE CREEK GENERATING STATION Individual Plant Examination for External Events

(

July 1997 Table 3-4 (continued)

Screening of Hope Creek Seismic IPEEE Components

~~~~~~~~...

x ' s $ : ~

s:.<

y DCP 1 CD444 125 VDC BAT CHGR 1 CD444/1 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 1 A/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 1 CD412-C/ 1DD412-D Diesel DCP 1CD448 FUSESWTCH BOX 1CD448-125VDC C/ 1DD448-D Control 5613 160' Yes Diesel DGS 1 AG400 DIVISION A DIESEL 1 AG400/I BG400/1 CG400/

Control 5303 102' Yes C-89,90 1DG400 Diesel DGS I A-C420 EXCITER PANELS, 1 A/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

HOPE CREEK GENERATING STATION Individual Plant Examination for External Events

(

July 1997 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 1 DG403 NEUTRAL GROUNDING AND TFM -

Control 5304 102' Yes c-98,99 t 1 A/B/C/DG403 Diesel I

I 3 -

66

/

HOPE,ýREEK GENERATING STATION Individual Plant Examination for External Events

(

July 19g97 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 C__

-269 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

.XMTER SA-PT-403A/B/E/!.F, Reactor 4215 77' Yes C__

-269 ESF PTNO94A IpRESS XMTER B B-PT.:N094A/B/C/D/E/F/G/H DW PRESS.

Reactor 4605 162' Yes C__

-38,41 HPI 8278 MOV HV-8278 Reactor 4316 102' Yes HPI FOOl MOV HV-FOO1 Reactor 4111 54' Yes C__

-62 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 C__

-176 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 C__

-268 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 214/BE-214 IGS AS-208 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 ISOLATION VALVEI PCS HV-F022A HVF022A/B/C/D - MAIN STEAM LINE Reactor 4220 102' Yes I

ISOLATION VALVE RAC 2601 AOV-2601 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

(

HOPE CREEK GENERATING STATION Individual Plant Examination for External Events

(

J.

July 1997 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

(

HOPE CREEK GENERATING STATION Individual Plant Examination for External Events

(

July 1997 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 4208 77' Yes 3 -

70

(

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 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 Individual Plant Examination for External Events

(

July 1997 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 1 AC515/C SWTS CONTROL PANEL SWIS 0292 107' No 53 C515 1 AC515/CC515 I

SWS 1DC514 SW PUMP LUBE OIL CONTROL PANEL SWIS SWIS 102 Yes 1 DC514 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

(

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

Screening of Hope Creek Seismic IPEEE Components July 1997 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

(

HOPE CREEK GENERATING STATION Individual Plant Examination for External Events

(

July 159~7 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 1 YF401 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 (H 1 -P620)

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

C-245,246

41) 1 OC621 RCIC RELAY VERTICAL BOARD Control Diesel 5302 102' No IOC628 ADS RELAY VERTICAL BOARDS Control Diesel 5302 102' No 5

1 0C399 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 Project No. 12800-217 Seismic Walkdown Report S&L Report No. SL-0 11553 Rev. 1 ATTACHMENT 1B - BASE LIST 1B-SHUTDOWN COMPONENT LIST (UFSAR TABLE 9A-2)

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

System IE Panel Room Chilled Water A 1E Panel Room Chilled Water A IE Panel Room Chilled Water A lE Panel Room Chilled Water A lE Panel Room Chilled Water A IE Panel Room Chilled Water A 1E Panel Room Chilled Water B IE Panel Room Chilled Water B 1E Panel Room Chilled Water B IE Panel Room Chilled Water B 1E Panel Room Chilled Water B

+/-E Panel Room Chilled Water B 1E Panel Room HVAC A 1E Panel Room HVAC A IE Panel Room HVAC A 1E Panel Room HVAC A lE Panel Room HVAC A lE Panel Room HVAC A 1E Panel Room HVAC A IE Panel Room HVAC A lE Panel Room HVAC B

lE Panel Room HVAC B 1E Panel Room HVAC B lE Panel Room HVAC B

IE Panel Room HVAC B IE Panel Room HVAC B I

Panel Room HVAC B

lE Panel Room HVAC B Control Area Chilled Water A Control Area Chilled Water A Control Area Chilled Water A Component GJ-AC487 GJ-AK403 GJ-AP414 GJ-FT-9666Al GJ-TV-9667A GJ-TV-9768A GJ-BC487 GJ-BK403 GJ-BP414 GJ-FT-9666EI GJ-TV-96675 GJ-TV-97686 GM-AC486 GM-AVH408 GM-FD-9558A GM-FSL-9558A2 GM-FT-9558A GM-HD-9558A1 GM-TE-9558A GM-TY-9558A GM-BC486 GM-BVH408 GM-FD-9558B GM-FSL-9558B2 GM-FT-9558B GM-HD-9558B1 GM-TE-9558B GM-TY-9558B GJ-AC490 GJ-AK400 GJ-AP400 GJ-FT-9648A2 GJ-TE-9652AI GJ-TV-9634A GJ-TV-9637A GJ-BC490 GJ-BK400 GJ-BP400 GJ-FT-9648B2 GJ-TE-9652B1 GJ-TV-9634B 1 of 16 Function Panel Control Area Chiller Chiller N20 Pump Chw Loop A AK403 Outlet 1E Pnl Rm Clr AVH408 Byp RSP Room OOVH316 coolino Coll Panel Control Area Chiller Chilled H 20 Pump Chw Loop B BK403 Outlet 1E Pnl Rm Clr BVH4081 Byp RSP Room 00VH316 Cooling Coil Control Panel Supply Fan Inlet Vanes Air flow Air Flow Outside Air Discharge Temperature Heater Control Control Panel Supply Fan Inlet Vanes Air Flow Air Flow Outside Air Discharge Temperature Heater Control Panel Control Area Chiller Chilled H2 0 Pump Cont Room Chiller Loop A Chilled Water Temp Cont Equip Rm Clr AVH407 Bye Cent Room Clr AVH403 Byp Panel Control Area Chiller Chilled H2 0 Pump Cont Room Chiller Loop B Chilled Water Temp Cont Equip Rm Clr BVH407 Byp Elec Mech.

Room Div.

Div.

No.

5704 5703 5602 5703 5620 5101 5704 5703 5703 5703 5501 5620 5,620 5620 620 5620 620 56U0 5620 5620 5620 5620 5620 5620 5602 5602 5602 5602 5602 5602 5630 5630 5630 5630 5630 5703 P&ID 89-1 90-1-3 90-1-3 90-1-3 90-1-1 90-1-3 P9-I 90-1-3 90-1-3 90-1-3 90-1-3 90-1-3 88-1-1 8x8-1-2 8R-1-2 S8-1-2 88-1-2 88-1-2 88-1-I 88-1-2 88-1-2 88-1-2 98-1-2 88-1-2 96-I1-2 88-1-2 88-1-2 90-1-1 90-1-1 90-1-1 90-1-i 90-1-1 90-1-1 90-1-1 90-1-2 90-1-2 90-1-2 90-1-2 90-1-2 90-1-2 Control Area Chilled Water Control Area Chilled Water Control Area Chilled Water Control Area Chilled Water Control Area Chilled Water Control Area Chilled Water Control Area Chilled Water A

A A

A B

BB Control Area Chilled Water B Control Area Chilled Water B Control Area Chilled Water B HCGS-UFSP3 Revision 0 April I, 1988

TABLE 9A-2 (Cont)

Elec Mech.

Room Div.

Div.

No.

System Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Area Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room Control Room HCGS-UFSAR Chilled Water B HVAC A HVAC A HVAC A HVAC A HVAC A HVAC A HVAC A HVAC A HVAC A HVAC B HVAC B HVAC B HVAC B HVAC B HVAC B AVAC B HVAC B HVAC B HVAC A HVAC A HVAC A HVAC A HVAC A HVAC A HVAC A HVAC A HVAC A HVAC A HVAC A FVAC A HVAC A HVAC A HVAC A HVAC A HVAC B HVAC B EVAC B HVAC B HVAC B HVAC B HVAC B HVAC B HVAC B HVAC B Component GJ-TV-9637B GK-ABH407 GK-FSL-9603A2 GK-FT-9603A GN-HD-9603AI GK-HD-9603A2 GK-HD-9603A3 GK-TE-9603A GK-TT-9603A GK-TY-9603A GK-BVH407 GK-FSL-9603B2 GK-FT-9603B GK-HD-9603BI GK-HD-9603B2 GK-HD-9603B3 GK-TE-9603B GK-TT-9603B GK-TY-9603B GE-AC485 GK-AV415 GK-AVH4 03 GK-FD-9598A GK-FSL-9587A GK-FSL-9589 A2 GK-FT-9589A GK-HD-9589Al GK-HD-9589A1 GK-HD-9569A2 GK-PDD-9587A GK-PDT-9587A GK-SV-9588AA GK-SV-9588AB GK-TE-9589A GK-TE-9589Al GK-BC485 GK-BV4]5 GK-BVH403 GK-FD-9598B GK-FSL-9587B GK-FSL-9589B2 GK-FT-95898 GK-HD-9569BI GK-HD-9589BI GK-RD-958922 Function Cont Room Clr BVH403 Byp Control Equip Supply CERS AVH407 Discharge Air CERS AVH407 Supply Air CERS AVH407 Outside Air CERS AVH407 Supply Air CERS AVH407 Return Air CERS AVH407 Supply Air CERS AVH407 Supply Air CERS AVH407 Supply Air Control Equip Supply CERS BVH407 Discharge Air CERS BVH407 Supply Air CERS BVH407 Outside Air CERS BVH407 Supply CERS BVH407 Return Air CERS BVH407 Supply Air CERS BVH407 Supply Air CERS BVH407 Supply Air Control Area HVAC Panel Control Room Exhaust Fan A Control Room Supply Fan Inlet Vanes Control Room AV415 Air Flow CRS AVH403 Heating Coil CRS AVH403 Supply air MCR Exhaust Damper CRS AVH403 Return Air MCR Supply Damper CRS AVH403 Pressure Control CRS Fan Inlet Dif Pressure Control Room Isol Ch C Control Room Isol Ch D CRS AVH403 Supply Air CRS AV4403 Supply Air Control Area HVAC Panel Control Room Exhaust Fan B Control Room Supply Fan Inlet Vanes Control Room BV415 Air Flow CRS HVH403 Heating Coil CRS BVH403 Supply Air MCR Exhaust Damper CRS BVH403 Return Air MCR Supply Damper 5630 5703 5703 5703 5703 5703 5703 5704 5704 5703 5703 5703 5703 5703 5703 5703 5703 5703 5703 5602 5602 5602 5602 5602 5602 5602 5602 5602 5602 5602 5602 5602 5602 5602 5510 5630 5630 5630 5630 5630 5630 5630 5630 5630 5630 P&ID 90-1-2 89-1 89-1 89-1 89-1 89-1 89-i 89-i 89-1 89-i 89-1 89-1 89-1 89-1 89-1 89-1 69-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-1 89-I 89-1 89-i 89-1 89-1 89-1 89-1 89-i 89-1 2 of 16 Revision 6 October 22, 1994

TABLE 9A-2 (Cont)

System Control Room HVAC B Control Room HVAC B Control Room HVAC B Control Room HVAC B Control Room HVAC B Control Room HVAC B Core Spray Loop I Core Spray Loop I Core Spray Loop I Core Spray Loop !

Core Spray Loop I Core Spray Loop I Core Spray Loop I Core Spray Loop I Core Spray Loop I Core Spray Loop II Core Spray Loop II Core Spray Loop Ii Core Spray Loop II Core Spray Loop II Core Spray Loop II Core Spray Loop II Core Spray Loop II Core Spray Loop It CRD Hydraulics CRD Hydraulics DG Room Recirc Sys A DG Room Recirc Sys A DG Room Recirc Sys A DG Room Recirc Sys A DG Room Recirc Sys A DG Room Recirc Sys A DG Room Recirc Sys A DG Room Recirt Sys B Dr Room Recirc Sys B DG Room Recirc Sys B DG Room Recirc Sys B DG Room Recirc Sys B DG Room Recirc Sys B DG Room Recirc Sys B DG Room Recirc Sys C DG Room Recirc Sys C DG Room Recirc Sys C DG Room Recirc Sys C DG Room Recirc Sys C Component GK-PDD-9587B GK-PDT-9587B GK-SV-9588BA GK-SV-9588BB GK-TE-9589B GK-TE-9589B1 BE-AP206 BE-CP206 BE-FT-NO03A BE-HV-FO0IA BE-HV-FCO3C BE-HV-FO04A BE-HV-FOOSA BE-HV-POI5A BE-HV-F031A BE-SP206 BE-DP206 BE-FT-NO03B BE-HV-FO01B BE-HV-F0O1D BE-HV-FO04B BE-HV-F005B BE-HV-F015B BE-EV-FO3lB BF-SV-117 BF-SV-117 GK-AC483 GM-AV412 GM-EV412 GM-FSL-9557A GM-FSL-9557E GM-TS-9557A GM-TS-9557E GK-BC483 GM-BV412 GM-FSL-9557B GM-FSL-9557F GM-FV412 GM-TS-9557B GM-TS-9557F GK-CC483 GM-CV412 GM-FSL-9557C GM-FSL-9557G GM-GV4!2 3 of 16 Function CRS BVH403 Pressure Control CRS Fan Inlet Dif Pressure Control Room Isol Ch C Control Room Isol Ch D CRS BVI4403 Supply Air CRS BVH403 Supply Air Core Spray Pump A Core Spray Pump C Loop I Flow Pump A Torus Suction Pump C Torus Suction Loop I Injection Loop I Injection Test return to Torus Min Flow Bypass Core Spray Pump B Core Spray Pump D Loop II Flow Pump B Torus Suction Pump D Torus Suction Loop II Injection Loop II Injection Test return to Torus Min Flow Bypass Pilot Scram Valve (Type of 93)

Pilot Scram Valve (Type of 92)

Panel Diesel Gen Room Recirc Fan Diesel Gen Room Recirc Fan Air Flow Low Air Flow Low Diesel Room Temperature Diesel Room Temperature Panel Diesel Gen Room Recirc Fan Air Flow Low Air Flow Low Diesel Gen Room Recirc Fan Diesel Room Temperature Diesel Room Temperature Panel Diesel Gen Room Recirc Fan Air Flow Low Air Flow Low Diesel Gen Room Recirc Fan Elec Mech.

Room Div.

Div.

No.

IT TI IT1 II II IPSI II I

I I

I IT IT I1 II II I

II II I

iI iI II ItS RPSI II II II I

I I!

5630 5630 5630 5630 5630 5510 4118 411C 4116 4102 4102 4102 4329 4102 4102 4104 4105 4105 4102 4102 4321 4321 4102 4104 4328 4320 5704 5211 5211 5307 5307 5307 5307 5703 5209 5209 5209 5209 5305 5305 5704 5210 5306 5306 5210 P&ID 89-1 89-2 89-1 89-1 09-1 89-1 52-1 52-1 52-1 52-1 I2-1 52-3 52-1 52-1 52-1 52-1 52-1 52-i 52-1 52-1 52-1 52-1 52-1 47-1 47-1 88-1-1 88-1-1 88-1-1 86-1-1 88-1-i 88-1-1 86-1-1 66-1-1 88-1-1 69-i-1 8R-1-1 88-1-1 8R-1-1 88-1-i 86-1-1 88-1-1 66-1-1 88-1-1 HCGS-UFSAR Revision 0 April 11, 16q0

TABLE 9A-2 (Cont)

System DG Room Recirc Sys DG Room Recirc Sys DG Room Recirc Sys DG Room Recirc Sys DG Room Recidr Sys DG Room Recirc Sys DG Room Recirc Sys DG Room Recirc Sys DG Room Recirc Sys Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Diesel Generators Electrical Power -

Electrical Power -

C C

D 0

D D

D DD

-A

-B

- B

-B

-C

-D

-D Div I Div I Div I Div I Div I Div I Div I Div I Div I Div I Div I Div I Div I Div I Div I Div I Component GM-TS-9557C GM-TS-9557G GK-DC483 GM-DV412 CM-FSL-9557D GM-FSL-9557H GM-HV412 GM-TS-9557D GM-TS-9557H KJ-1AC422 KJ-1AC423 KJ-AG400 KJ-AP401 KJ-BP401 KJ-1BC422 KJ-lBC423 KJ-BG4 00 KJ-CP401 KJ-DP401 KJ-1CC422 KJ-1CC423 KJ-CG400 KJ-EP401 KJ-FP401 KJ-IDC422 KJ-IDC423 KJ-DG400 KJ-GP401 KJ-HP401 PB-10A401 PB-I0A403 PH-10B212 PH-10B232 PG-10B410 PH-10B411 PG-10B430 PH-10B431 PG-10B450 PH-100451 PG-10B470 PH-105471 PH-10B553 PH-10B573 PJ-10D251 PK-10D410 4 of 16 Function Diesel Room Temperature Diesel Room Temperature Panel Diesel Gen Room Recirc Fan Air Flow Low Air Flow Low Diesel Gen Room Recire Fan Diesel Room Temperature Ciesel Room Temperature Generator Panel Diesel Panel DG and Auxiliaries Fuel Transfer Pump Fuel Transfer Pump Generator Panel Diesel Panel DG and Auxiliaries Fuel Transfer Pump Fuel Transfer Pump Generator Panel Diesel panel DG and Auxiliaries Fuel Transfer Pump Fuel Transfer Pump Generator Panel Diesel Panel DG and Auxiliaries Fuel Transfer Pump Fuel Transfer Pump 4.16 kV Swgr 4.16 kV Swgr 480 V MCC 480 V MCC 480 V Swgr 480 V MCC 480 V Swgr 480 V MCC 480 V Swgr 480 V MCC 480 V Swgr 480 V MCC 480 V MCC 480 V MCC 250 V DC MCC 125 V DC Swgr Elec Mech.

Room Div.

Div.

No.

5306 5306 5703 52D8 5208 5208 5208 5304 5304 5416 5416 5307 5110 5110 5412 5412 5305 5108 5108 5414 5414 5306 5109 5109 5410 5410 5304 5107 5107 5417 5415 4309 4310 5417 5417 5415 5415 5417 5417 5415 5415 203 203 4112 5417 P&I D 130-88-1-i 88-1-i 88-1-i 88-1-1 38-1-1 88-1-1 88-1-1 88-1 88-1 30-1 30-1 30-1 30-1 30-1 30-i 30-1 30-1 30-1 30-1 30-1 30-1 30-1 30-1 30-1 30-1 30-1 30-1 30-1 NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA N-A HCGS-UFSAR Revision 0 April 11, 1981

TABLE 9A-2 (Cont)

System Electrical Power - Div Electrical Power -

Div Electrical Power -

Div Electrical Power - Div Electrical Power -

Div Electrical Power -

Div Electrical Power - Div Electrical Power -

Div Electrical Power -

Div Electrical Power - Div Electrical Power -

Div Electrical Power - Div Electrical Power - Div Electrical Power - Div Electrical Power -

Div Electrical Power -

Div Elec~rical Power -

Div Electrical Power -

Div Electrical Power - Div Electrical Power -

Div Electrical Power -

Div Electrical Power - Div Electrical Power - Div Electrical Power -

Div Electrical Power -

Div Electrical Power - Div Electrical Power - Div Electrical Power -

Div Electrical Power -

Div Electrical Power - Div Component PJ-10D421 PJ-10D423 PX-10D430 PK-10D436 PJ-10D450 PK-1AD411 PK-lAD413 PK-IAD414 PK-1AD417 PN-IAD481 PN-lAD482 PN-1AJ481 PN-IAJ4 82 PK-1CD411 PK-ICD4!3 PK-ICD414 PK-ICD417 PK-ICD444 PK-ICD447 PN-1CD481 PN-ICD482 PN-ICJ7481 PN-ICJ482 P1-1 FF4l01 PN-IYF403 PB-IOA402 PB-i0A404 P2-10B222 PH-10B242 PG-10B420 PH-10421 PG-10B440 PH-IOB441 PG-10460 PH-10B461 PG-10B480 PH-10B481 PH-10B563 PH-10B583 PJ-10D261 PK-10B420 PJ-10D431 PJ-10D433 PK-10D440 PK-10D446 5 of 16 Function 250 V DC Batteries 250 V DC Battery Chargers 125 V DC Swgr 125 V DC Swgr 250 V DC Swgr 125 V DC Batteries 125 V DC Battery Chargers 125 V DC Battery Chargers 125 V DC Dist Panel 120 V AC Power 120 V AC Power 120 V AC UPS Dist Pnl 120 V AC UPS Dist Pnl 125 V DC Batteries 125 V DC Battery Chargers 125 V DC Battery chargers 125 V DC Dist Panel 125 V DC Battery Chargers 125 V DC Batteries 120 V AC Power 120 V AC Power 120 V AC UPS Dist Pni 120 V AC UPS Dist Pnl 120 V AC Fuse Pnl 120 V AC Fuse PnI 4.16 kV Swgr 4.16 kV Swgr 480 V MCC 480 V MCC 480 V Swgr 480 V MCC 480 V Swgr 480 V MCC 480 V Swgr 480 V MCC 480 V Swgr 480 V MCC 480 V MCC 480 V MCC 250 V DC MCC 125 V DC Swgr 250 V DC Batteries 250 V DC Battery Chargers 125 V DC Swgr 125 V DC Swgr Elec Mech.

Roos Div.

Div.

No.

5104 5129 5415 5613 5129 5545 5544 5544 5417 5501 5616 5501 5616 5543 5542 5542 54i5 5613 5614 5501 5613 550i 5613 5302 5302 5413 5411 4303 4201 5413 5413 5411 5411 5413 5413 5411 5411 207 207 4108 5413 5128 5130 5411 5607 PtID NA NA NA NA NA NA NA NA NA NA 14A NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA N'A NA NA 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 1 1 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)

System HPCI -

Leak Detection HPCI -

Leak Detection HPCI Steam HPCI Steam (PCI Steam HPCI Steam HPCI Steam HPCI Steam F(PCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam HPCI Steam Main Steam -

Div I Main Steam -

Div i Main Steam -

Div II Main Steam -

Div II Nuclear Boiler Nuclear Boiler Nuclear Boiler Inst (RSP)

Nuclear Boiler Inst (RSP)

Nuclear Boiler Inst -

I Nuclear Boiler Inst -

I Nuclear Bailer Inst -

I Component SK-TE-NO29A SK-TE-N029C SK-TE-NC30A SK-TE-N030C FD-OP215 FD-0P216 FD-OS211 FD-FT-14003 FD-FV-4879 FD-EV-4880 FD-NV-F00I FD-HV-F002 FD-HV-F003 FD-f-V-POll FD-HV-FO75 FD-HV-F079 FD-PDT-NOS7A FD-PDT-N057C FD-PT-NO55A FD-PT-N055C FD-PT-NO55E FD-PT-NO55G FD-PT-N056A ED-PT-NO56E ED-PT-NOS8A FD-PT-NM58C FD-PT-N058E FD-PT-N058G AB-SV-3673B AB-SV-3675B AB-SV-3677B AB-SV-3679B AB-SV-3674B AB-SV-36760 AB-SV-3678B AB-SV-3680B AB-HV-F016 AB-HV-F019 BB-LT-7854 BB-PT-7853A BB-PT-7853D BB-LT-7854-1 BB-LR-R623A BB-LT-N091A BB-LT-3682A BB-LR-3682A-1 BB-LI-3682A Function Exhaust Duct Exhaust Duct Energ Unit Cooler Energ Unit Cooler Condensate Pump Vacuum Pump HPCI Turbine HPCI Pump Disch Flow HPCI Turb Control Valve HPCI Turb Stop Valve HPCI Steam Isol Valve HPCI Steam Isol Valve HPCI Steam Isol Valve HPCI Steam Exh Tsol Valve HPCI Vacuum Isol Valve HPCI Vacuum Isol Valve High Steam Flow High Steam Flow Turb Exhaust Vent Turb Exhaust Vent Turb Exhaust Vent Turb Exhaust Vent Exhaust High Pressure Exhaust High Pressure HPCI Steam Pressure Trip HPCI Steam Pressure HPCI Steam Pressure HPCI Steam Pressure For Inboard MSIV AB-HV-F022A For Inboard NSTV AB-HV-P022B For Inboard MSIV AB-HV-F022C For Inboard MSiV AB-HV-PO2ID For Outboard MSIV AB-HV-FO28A For Outboard MSIV AS-HV-FO2PB For Outboard MSIV AB-HV-F028C For Outboard MSIV AB-HV-FO28BD Inboard MSIV Drain Inboard MSIV Drain Reactor Level Reactor Pressure Reactor Pressure Reactor Level Reactor Level Ch A Reactor Level Reactor Level Reactor Level Ch A Reactor Level Ch A Elec mech.

Room Div.

Div.

P5o.

4111 4111 4111 4111 4111 41i1 4111 4112 4111 4111 4111 4 Ill 4 220 4327 4102 4102 4102 4215 4219 4209 4209 4209 4209 4112 4112 4315 4215 4215 42A9 4220 4120 4220 4220 4316 4316 4316 4316 4220 4316 4105 4215 4202 4203 5510 4215 4 215 5510 5510 P&ID 25-1-2 25-1-2 25-1-2 25-i-2 56-1 56-1 56-1 55-1 56-1 56-1 51-1 55-1 55-1 55-1 55-1 55-1 55-1 55-I 56-1 56-i 56-1 16-1 56-1 56-1 55-1 5S-i 511-i 55-1 41-1-1 41-1-1 4 1-1-1 41-1-2 4 1-1-1 4 1-1-1 41-1-1 41-1-2 41-1-1 41-1-1 42-1-1 4 2-1-i 42-1-1 42-1-1 42-1-1 4 2-1-1 4 2-1-1 I 7 of 16 HCGS-UFSAR Revision 18 May 10, 2011

TABLE 9A-2 (Cont)

System Nuclear Boiler Inst -

I Nuclear Boiler inst -

I Nuclear Boiler Tnst -

I Nuclear Boiler Inst -

I Nuclear Boiler inst -

II Nuclear Boiler Inst -

II Pri Cont Ins-Gas -

Div I Pri Cont inst Gas -

Div I Pri Cont Inst Gas -

Div II Pri Cont Inst Gas -

Div II PCIC RCIC RCIC RCIC RCIC RCIC RCIC RCIC RCIC RCIC RCIC RCIC -

Leak Detection RCIC -

Leak Detection RCtC -

Leak Detection RCIC -

Leak Detection RCOC -

Leak Detection RCIC -

Leak Detection RCIC Steam RCiC Steam RCIC Steam RCIC Steam RCTC Steam RCTC Steam RCTC Steam RCIC Steam PCIC Steam RCIC Steam RCIC Steam Component BB-PT-3684A BB-PI-3684A BB-PR-R623A BB-PT-N078A BB-LR-R623B BB-LT-N091B BB-PR-R623B BB-PT-N078B KL-EV-5126A KL-HV-5152A KL-HV-5126B KL-HV-5152B BD-OP203 BD-BP228 BD-HV-F010 BD-HV-F012 BD-HV-F013 BD-HV-F022 BD-HV-F031 BD-HV-F046 BD-PT-NO50 BD-PT-N053 BD-SV-F019 SK-TE-ND21B SK-TE-N021D SK-TE-N022B SK-TE-N022D SK-TE-N0D23B SK-TE-N023D SK-TE-N025B SK-TE-N025D SK-TE-N025F SK-TE-ND25H SK-TE-N025K SK-TE-N025M SK-TE-N05P SK-TE-N0255 FC-OP219 FC-OP220 FC-OS212 FC-FT-NO03 FC-HV-4282 FC-HV-4283 FC-HV-F007 FC-HV-F008 FC-HV-F045 FC-HV-F059 FC-HV-F060 Function Reactor Pressure Reactor Pressure Ch A Reactor Pressure Ch A Reactor Pressure Reactor Level Ch B Reactor Level Reactor Pressure Ch B Reactor Pressure Supply Header Outboard Isln Supply Header Inboard Isin Supply Header Outboard Isln Supply Header Inboard Isln RCIC pump RCIC Jockey pump Suction From CST Pump Disch RCIC Injection Valve RCIC Return to CST Suppression Pool Suction Water to RCIC Condenser To PTSH-N650 To PISH-N653 Min Flow Valve Supply Duct Supply Duct Exhaust Duct Exhaust Duct Energ Unit Cooler Energ Unit Cooler Pipe Tunnel Pipe Tunnel Torus area Torus Area Torus Area Torus Area Torus Area Torus Area RCIC Gland Seal Pump RCIC Condensate Pump RCIC Turbine RCIC Pump Discharge Flow RCIC Turbine Trip/Thrtl Valve RCIC Turbine Gay Valve Inboard Iso Steam Outboard Iso Steam RCIC Turbine Steam Stop Vlv RCIC Steam Exh Isol Valve RCIC Vac Pump Discharge Valve Elec Mech.

Room Div.

Div.

No.

4215 5510 5510 4215 5510 4203 5510 4203 4329 4220 4321 4220 4110 4110 4110 4110 4316 4106 4102 4110 4108 4210 4102 4110 4110 4110 4110 41i0 4110 41.02 4102 4102 4102 4102 4102 4110 4110 4110 4108 4110 4110 4 2 -)D 4319 4110 4102 4102 P&ID 42-1-1 42-1-1 42-1-1 42-1-I 42-1-1 42-1-1 42-1-1 42-1-1 59-1-1 59-1-1 59-1-1 59-1-1 50-i 50-1 49-1 49-1 49-1 49-1 49-1 50-1 49-1 50-49-1 25-1-?

25 2 5-1 25-1-2 25-1-2 5-19 50 49 10 45-1 50- 1 50-1 49-1 49-1 I

8 of.16 HCGS-UFSAR Revision 18 May 10, 2011

TABLE 9A-2 (Cont)

System RCIC Steam RCIC Steam RCIC Steam RCIC Steam RCIC Steam RCIC Steam RCIC Steam RCIC Steam RCIC Steam RCIC Steam RCIC Steam RCIC Steam RCIC Steam RCIC Steam RCIC Steam Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor P!dg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Blog Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Reactor Bldg Unit Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Coolers Component FC-HV-F062 FC-HV-F076 FC-HV-FO84 FC-PT-NO55B FC-PT-NO55D FC-PT-N055F FC-PT-NO55H FC-PT-NO56B FC-PT-N4056F PC-PT-NO57B FC-PT-N051D FC-PT-NO58B FC-PT-NO58D FC-PT-NO58F FC-PT-N058H GU-AC281 GR-AVH209 GR-AVH210 GR-AVR211 GR-AVH214 GR-BVH209 GU-CC281 GR-CVH210 GR-CVH211 GR-CVH2!4 GR-EVH210 GR-EVH211 GR-FSL-9385AI GR-FSL-9385C1 GR-GVH210 GR-GVH211 GR-TE-9382A GR-TE-9382B GR-TE-9383A GR-TE-9383C GR-TE-9383E GR-TE-9383G GR-TE-9384A GR-TE-9384C GR-TE-9384E GR-TE-9384G GR-TE-9385A GR-TE-9385C GR-AVH208 GU-BC281 9 of 16 Function RCIC Vac Brkr Isol Valve Iso Valves Bypass RCIC Vac Brkr Iso] Valve Vent Pressure Trip Vent Pressure Trip Vent Pressure Trip Vent Pressure Trip RCIC Turbine Exhaust Press RCIC Turbine Ezhaust Press Steam High Flow Steam High Flow Steam Low Pressure Trip Steam Low Pressure Trip Steam Low Pressure Trip Steam Low Pressure Trio Unit Cooler Control Panel HPCI Unit Cooler RHR Unit Cooler Core Spray Unit Cooler SACS Unit Cooler HPCI Unit Cooler Unit Cooler Control Panel RHR Unit Cooler Core Spray Unit Cooler SACS Unit Cooler RHR Unit Cooler Core Spray Unit Cooler SACS Air Flow Switch SACS Air Plow Switch RHR Unit Cooler Core Spray Unit Cooler 9PCI Room Temp HPCI Room Temp 5CR A Room Temp PHR C Room Temp RHR A Room Temp RHR C Room Temp Core Spray Room Temp Core Spray Room Temp Core Spray Room Temp Core Spray Room Teap SACS A&C Room Temp SACS A&C Room Temp RCIC Unit Cooler Unit Cooler Control Panel 4i02 4220 4102 4205 4202 4203 4201 4108 4108 4203 4202 4203 4202 4203 4202 4309 4111 4113 4118 4309 4111 4310 4114 4117 4309 4214 4 3.18 41309 4 309 4114 4117 4111 4111 4111 4 114 4214 4114 4118 4117 4118 4117 4309 4309 4110 4303 Elec Mech.

Room Div.

Div.

No.

P&aD 49-1 49-1 49-1 50-1 50-1 50-1 50-I 50-1 50-1 49-1 49-1 49-1 49-1 49-1 49-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 HCGS-UFSAR Revision 0 April 11, 1988

TABLE 9A-2 (Cont)

System Reactor Bldg Unit Coole Reactor Bldg Unit Coole Reactor Bldg Unit Cool Reactor Bldg Unit Cooli Reactor Bldg Unit Cooli Reactor Bldg Unit Cooli Reactor Bldg Unit Coole Reactor Bldg Unit Coole Reactor Bldg Unit Coole Reactor Bldg Unit Coole Reactor Bldg Unit Coole Reactor Bldg Unit COOlIe Reactor Bldg Unit Cooli Reactor Bldg Unit Coole Reactor Bldg Unit Cool Reactor Bldg Unit Coole Reactor Bldg Unit Cool Reactor Bldg Unit Cool Reactor Bldg Unit Cool!

Reactor Bldg Unit Cool Reactor Bldg Unit Cool Reactor Bldg Unit Cooli Reactor Bldg Unit Cooli Reactor Bldg Unit Cooli Reactor Bldg Unit Cool Reactor Bldg Unit Cool Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys Reactor Protection Sys ers ers ers ers ers era Irs ers Irs ers trs Irs Irs ers ors Its era ors ers ers ors ers ors ers ers ers ers It It It It II II II TI TI II II II II Ix II II It II It It Ii II II It IT II Component GR-BVH208 GR-BVH210 GR-BVH211 GR-BVH214 GU-DC281 GR-DVH210 GR-DVh211 GR-DVH214 GR-FSL-9385BI GR-FSL-9385DI GR-FVH210 GR-FVH211 GR-HVH210 GR-HVH211 GR-TE-9381A GR-TE-9381B GR-TE-9383B GR-TE-9383D GR-TE-9333F GR-TE-9383H GR-TE-9384B GR-TE-9384D GR-TE-9384F GR-TE-9384H GR-TE-9385B GR-TE-9385D SB-TE-3647J-2 SB-TE-3647L-2 SB-TE-3647M-2 SB-TE-3647Q-2 SB-TT-3647J-2 SB-TT-3647L-2 SB-TT-3647M-2 SB-TT-3647Q-2 SB-TE-3647A-1 SB-TE-3647C-l SB-TE-3647E-l SB-TE-3647H-l SB-TE-3647K-l SB-TE-3647N-l SB-TE-3647P-l SB-TE-3647R-l SB-TE-3648A-l SB-TE-3648B-1 SB-TE-364BC-i 10 of 16 Function RCIC Unit Cooler RHR Unit Cooler Core Spray Unit Cooler SACS Unit Cooler Unit Cooler Control Panel RHR Unit Cooler Core Spray Unit Cooler SACS Unit Cooler SACS Air Flow Switch SACS Air Flow Switch RHR Unit Cooler Core Spray Unit Cooler RHR Unit Cooler Core Spray Unit RCIC Room Temp RCIC Room Temp RHR B Room Temp RHR D Room Temp RHR B Room Temp RHR D Room Temp Core Spray Room Temp Core Spray Room Temp Core Spray Room Temp Core Spray Room Temp SACS BaD Room Temp SACS B&D Room Temp Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Elec Mech.

Room Div.

Div.

No.

4110 4109 4104 4307 4202 4107 4105 4307 4307 4307 4208 4104 4107 4105 4110 4110 4109 4107 4208 4107 4104 4105 4104 4105 4307 4307 4102 4.1 0Q 4102 4102 5605 5605 1605 5605 4102 4102 4102 4102 4102 4 1 '32 4102 4102 4 1 02 4 102 4102 4102 P&ID 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-I 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-1 83-So 1

-1 ý 4' 1 81-i 3-i 4 1-1-2 41-1-2 41-1-2 41-!1 41 2 41-1-2 41-1-2 41-1-2 41 2 41 -

-2 41-1-2 41-1-2 (RSP)

(RSP)

I I

I

-3I I

-3I

-tI I

I HCGS-UFSAR Revision 0 April 11, 1988

TABLE 9A-2 (Cont)

Elec Mech.

Room Div.

Div.

No.

System Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor RHR RHR RHR RHR PER A RHR A RHR A RHR A RHR A RHR A RHR A RPR A RHR A RHR A RHR A RHR.A RHR A RHR A RHR B RPR B RHR B RHR B RHR B RHR B RHR B RHR B RHR B RHR B Protection Sys -

Protection Sys -

Recirculation A Recirculation B II IT II II 22 II II II II Component SB-TE-3647B-I SB-TE-3647D-I SB-TE-3647F-I SB-TE-3647G-1 SB-TE-3647J-l SB-TE-3647L-l SB-TE-3647M-1 SB-TE-3647Q-1 SB-TE-3643D-1 BB-HV-F031A BB-EV-F031B BC-HV-FO08 BC-HV-F009 BC-HV-F040 BC-HV-F049 BC-AP202 BC-FT-NC15A BC-HV-FO03A BC-HV-FOO4A BC-HV-FO06A BC-HV-FO07A BC-HV-F015A BC-HV-F0G6A BC-RV-F017A BC-HV-F024A BC-HV-F027A BC-HV-F047A BC-HV-F048A BC-PDT-NO58A BC-BP202 BC-FT-4435 BC-FT-NO15B BC-WV-F003P BC-HV-F004B BC-HV-FO06B BC-HV-F007B BC-HV-FP15B BC-HV-VO16B BC-HV-F017B BC-HV-F024B BC-HV-F027B BC-HV-F047B BC-EV-FO48B BC-PDT-N058B BC-CP202 11 of 16 Function Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature Suppression Pool Temperature React Recric Pump Disch React Recirc Pump Disch Shutdown Cooling Outside Cont Shutdown Cooling Inside Cont To Radwaste To Radwaste RHR Pump A RPHR Flow A RHR HX Outlet Torus Suction Shutdown Suction to A loop Min Flow Line Shutdown Rezurn Containment Spray LPCI Injection Supp Pool Return Torus Spray RHR HX A inlet REP EX A Bypass Interlock to 017A RHR Pump B RSP Flow Indication RHR Flow B PHR EX Outlet Torus Suction Shutdown Suction to B Loco Min Flow Line Shutdown Return Containment Spray LPCI Injection Supp Pool Return Torus Spray RHR HX B Inlet RHR HX B Bypass Interlock to F017B RHR Pump C II II iI II It II I

I II i/!

I II I/I I

II SI II Ii II tI SI II iI II II IZ 4102 4102 4102 4102 4102 4102 4102 4102 4102 4220 4220 4329 4220 4102 4102 4213 413 4102 4113 4102 4329 4329 4102 4214 4214

421, 4109 4201 4201 4109 4102 4109 4102 4321 4402 4321 4102 4102 4208 4208 4205 4114 41-1-2 41-1-2 41-1-2 4 t-t-2 41-1-2 41-1-2 41-1-2 41-1-2 43-1-1 43-1-1 51-1-1 51-1-i 51-1-I 51-1-1 51-1-1 51-i-i b51-I-51-1-2 51-1-1 51-!-1 51-1-2 51-1-1 51-1-1 51-I-1 51-1-2 51 -

-1 5'-12 5! 1 51 51 1-1-1 r51 51 51-I-I RHR RHR RHR RHR RHR RHR B

B B

C II IITI II 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 R HR 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

4 0

3 1ii-i-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

1 113 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)

System SACS -

SACS -

SACS SACS -

SACS -

SACS SACS -

SACS -

SACS SACS -

SACS -

Safety Safety Safety Safety Safety Safety Safety Safety Safety Safety Safety Safety Safety Safety Safety Safety Safety DIV II DIV II DIV II DIV II DIV II DIV II DIV II DIV I1 DIV II DIV TI Div It DIV IT DIV II DIV I1 DIV It DIV i1 DIV Ii DIV II DIV Ii DIV II DIV II DIV II DIV II DIV II DIV TI DIV II DIV II DIV II RSP Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Relief Valves Component EA-BC201 EG-BP210 EA-DC201 EG-DP210 EG-FT-2549BI EG-HV-2491B EG-HV-2494B EG-HV-2512B EG-SV-2290B EG-SV-2290D EG-SV-2290F EG-SV-2290H EG-SV-2293A EG-SV-2293B EG-SV-2325B EG-SV-2325D EG-SV-2325F EG-SV-2325H EG-SV-2395B EG-SV-2395D EG-SV-2398B EG-SV-2398D EG-SV-2398F SG-SV-2398534 EG-SV-2520B EG-SV-2 52 0D EG-TE-2535B EG-TE-N005B EG-FT-254923 SN-SV-3652A SN-SV-36522 SN-SV-3653A SN-SV-3653B SN-SV-3654A SN-SV-3654B SN-SV-3655A SN-SV-3655B AS-SV-3656A AS-SV-3657A AB-SV-3658A AB-SV-3659A AB-SV-3660A AB-SV-3661A AB-SV-3662A AB-SV-3663A AB-SV-3664A Elec Mach.

Room Div.

Div.

No.

Function SACS Control Panel SACS Pump SACS Control Panel SACS Pumo SACS Loop IT Flow HZ B2E201 Inlet HX B2E201 Inlet RHR HX BE205 Isol Valve RHR Pump B Room Unit Cooler B RHR Pump D Room Unit Cooler 0 RHR Pumo B Room Unit Cooler F RHR Puma D Room Unit Cooler N RCIC Pump Room Unit Cooler A RCIC Pump Room Unit Cooler S CS Pump Room B Unit Cooler B CS Pump Room B Unit Cooler C CS Pump Room D Unit Cooler F CS Pump Room 3 Unit Cooler F DG B HxS Cooling Wauer DG D HXS Cooling Mater DG S Room Unit Cooler C DG 0 Room Unit Cooler D DG S Room Unit Cooler F DG D Room Unit Cooler H RHR Pump BP202 Cooling Coil RHR Pump DP202 Coolino Coil SACS B!/B2 HX Bypass Temp.

RHR HX B SACS Temp.

SACS Loop II Flow -

RSP ind PSV-FO13A Safety Relief Valve PSV-FO1I3A Safety Relief Valve PSV-FO13B Safety Relief Valve PSV-FOI3B Safety Relief Valve PSV-FO1I3C Safety Relief Valve PSV-FOI3C Safety Relief Valve PSV-FO13D Safety Relief Valve PSV-FOI3D Safety Relief Valve PSV-FOI3J Safety Relief Valve PSV-FO13F Safety Relief Valve PSV-FO13G Safety Relief Valve PSV-FO13H Safety Relief Valve PSV-FO13R Safety Relief Valve PSV-FO13K Safety Relief Valve PSV-FO1I3L Safety Relief Valve PSV-FO13M Safety Relief Valve PSB-FOl3P Safety Relief Valve 4307 43C7 4307 4307 4307 4307 4307 4109 4107 4109 4 107 41 10 4104 4105 4104 4105 5209 520 8 5209 52H8 5209 52,08 4109 4 107 4 307 4109 4107 4207 4109 4120 4220 4220 4220 4220 4220 4220 4220 4220 4220 4220 4220 4120 4220 4220 4220 P&ID 11-1-1 11-1-1 12-1-1 11-1-1 12-1-I 12-1-1 11-1-2 41-1 11-1-2 11

-2 41-1-2 41-1-2 41-1-2 41-1-2 41-1-2 41-1-2 41-1-2 12-1-2 41 Ii-1ii--

41-1-2 412--1 412-1-2 11-i-2 11-1-1 11-1-1 41-1-1 41-1-I 41-1-2 41-1 -2 41-1-2 4 1-1-2 41-1-2 41-1-2 41-1-2 41-1-2 I

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

TABLE 9A-2 (Cont)

Flec Mech.

Room Div.

Div.

No.

System Safety Relief Valves Safety Relief Valves Service Water -

Div I Service Water -

Div I Service Water - Div I Service Water -

Div I Service Water -

Div T Service Water -

Div I Service Water -

Div i Service Water -

Div I Service Water -

Div 1 Service Water -

Div I Service Water -

Div II Service Water -

Div It Service Water -

Div II Service Water -

Div !I Service Water -

Div II Service Water -

Div II Switchgear Room Unit Cooler Switchgear Room Unit Cooler Switchgear Room Unit Cooler Switchcear Room Unit Cooler Switchgear Room Unit Cooler Switchgear Room Unit Cooler Switchgear Room Unit Cooler Switchgear Room Unit Cooler SWS HVAC Supply a Exhaust A SWS HVAC Supply & Exhaust A SWS HVAC Supply & Exhaust A Component SN-SV-3665A SN-SV-3665B EA-AC515 EA-AC5I6 EA-AP502 EA-AS501 EA-CC515 EA-CC516 EA-CP502 EA-CS501 EA--HV-2197A EA-HV-2197C EA-HV-2198A EA-HV-2198C EA-HV-2355A

&Ak-HV-2371A EA-PDT-2354A EA-PDT-2373A EA-EC515 EA-BCSI6 EA-BP502 EA-BS501 EA-DCSI5 EA-DCSI6 FA-DP502 EA-DSSIO EA-HV-2197B EA-HV-2197D EA-HV-2198B EA-HV-2198D EA-HV-2204 EA-HV-2355B EA-NV-2371B EA-PDT-2354B EA-PDT-2373B GM-AVR401 GM-HD-9549A GM-BVH401 GM-HD-9549B GM-CVH401 GM-HD-9549C GM-DVH401 GM-HD-9549D GQ-AC581 GQ-AVS03 GQ-AV504 Function PSV-FO13E Safety Relief Valve PSV-FO13E Safety Relief Valve Traveling Screen Panel Service Water Pump Panel Service Water Pump Traveling Screen Traveling Screen Panel Service Water Pump Panel Service Water Pump Traveling Screen Strainer Disch To Fish Trouch Strainer Dish to Fish Trough Puma A Discharge Valve Pump C Discharge Valve SACS A2 Disch SACS Al Discharge SACS HX Al DP SACS HX A2 OP Traveling Screen Panel Service Water Pump Panel Service Water Pump Traveling Screen Traveling Screen Pane!

Service Water Pump Panel Service Water Pump Traveling Screen Strainer Disch to Fish trough Strainer Disch to Fish trough Pump B Discharge Valve Pump D Discharge Valve Loop B RA.CS 1X Header Valve SACS B2 Discharge SACS 81 Discharge SACS HX 81 DP SACS HX B2 DP Switchgear Pm Unit Cooler Outside Air Switchgear Rm Unit Cooler Outside Air Switchgear Rm Unit Cooler Outside Air Switchgear PR Unit Cooler Outside Air Intake Stru HVAC Panel Intake Struc Supply Fan Intake Struc Exhast Fan 4220 4220 204 204 204 TS RM 2Od 2I4 TS.3-

'04 204 i07 107 4 10 q 4309

'30e 4309 4 309 DSRM 208 208 TS RM 208 TI RH 110 110 430-7 4307 4207 4307 4307 5629 5F12

-306 5629 5612 5606 5605 1629 5612 5606 5605 204 307 305 P&ID 41-1-2 41-I-2 10-1-1 10-1-i 10-i-1 10-!-I 10-1-1 10-1-1 10-1-1 10-I-I 10--11 10-1-1 10-1-1 10-1-1 80-1-2 80-1-1 10-1-i 80-1-1 10-1-1 10-!-1 10-i-1 10-1-I 10-2-1 10-1-I 10-1-2 10-1-2 10-1-2 10-1-2 88-1-1 88-1-!

88-1-1 88-1-1 88-1-1 88-1-1 88-1-1 88-1-1 95-0 95-0 95-0 I

A A

B B

C C

D D

14 of 16 HCGS-UFSAR Revision 18 Way 10, 2011

TABLE 9A-2 (Cont)

System SWS HVAC Supply &

SWS HVAC Supply &

SBS HVAC Supply &

SWS HVAC Supply &

SLS HVAC Supply &

SWS HVAC Supply &

SWS WVAC Supply &

SWS HVAC Supply &

SWS RVAC Supply &

SWS HVAC Supply &

Tray Screen Motor Trav Screen Motor Tray Screen Motor Tray Screen Motor Tray Screen Motor Tray Screen Motor Exhaust A Exhaust A Exhaust A Exhaust A Exhaust A Exhaust A Exhaust S Exhaust B Exhaust B Exhaust B Exhaust 2 Exhaust B Exhaust B Exhaust B Exhaust B Exhaust C Exhaust C Exhaust C Exhaust C Exhaust C Exhaust C Exhaust C Exhaust C Exhaust C Exhaust D Exhaust D Exhaust D Exhaust D Exhaust D Exhaust D Exhaust D Exhaust D Exhaust D Rm HVAC A Rm HVAC A Rm HVAC A Rm HDIAC A Rm 10JAC B Rm HACG B Component GQ-TD-9773Al GQ-TD-9773IAA GQ-TD-9773AIB GQ-TD-9773A2 GQ-TD-9773A3 GQ-TE-9773A GQ-BC581 GQ-BV50 GQ-BV504 DQ-TD-9773BI GQ-TD-9773BIA GQ-TD-9773BlB GQ-TD-9773B2 GQ-TD-9773B3 GQ-TE-97732 GQ-CC581 GQ-CVS03 GQ-CV504 GQ-TD-9773CI GQ-TD-9773CIA GQ-TD-9773CIB GQ-TD-9773C2 GQ-TD-9773C3 GQ-TE-9773C GQ-DC581 GQ-DV503 GQ-DV504 GQ-TD-9773BI GQ-TD-9773DIA GQ-TD-9773DIB GQ-TD-9773D2 GQ-TD-9773D3 GQ-TE-9773D GQ-QAV558 GQ-TD-9774AI GQ-TD-9774A2 GQ-TE-9774A GQ-OBV558 GQ-TD-9774BI Function Outside Air Damper Damper Actuator Damper Actuator Intake Stru Return Air Intake Stru Exhaust Air Intake Stru AGC Room Tems Intake Stru HV/AC Panel Intake Struc Supply Fan Intake Struc Exhaust Fan Outside Air Damper Damper Actuator Damper Actuator Intake Stru Return Air Intake Stru Exhaust Air Intake Stru B&D Room Temp Intake Stru HVAC Panel Intake Struc Intake Fan Intake Struc Exhaust Fan Outside Air Damper Damper Actuator Damper Actuator Intake Stru Return Air Intake Stru Exhaust Air Intake Stru A&C Room Temo Intake Stru HVAC Panel Intake Struc Intake Fan Exhaust Struc Intake Fan Outside Air Damper Damper Actuator Damper Actuator Intake Stru Return Air Intake Stru Exhaust Air Intake Stru B&D Room Teme Traveling Screen Rm Fan Trav Screen Room Return Air Tray Screen Room Outside Air Tray Screen Room Air Temp Traveling Screen Rm Fan Tray Screen Room Return Air Elec Mech.

Room Div.

Div.

No.

I I

306 306 30F 301 304 C41 312 311

-112 310 208 204 306 305 306 30f 306 305 304 204 208 312 311 312 312 311 311 310 208 TS RM TS RM TS RM TS RM TS RM T

RM Pl 0 915-0 95-0 4.5 -

95-0 95-C0 5- 0 95 -0 c5-0 95-0 95-0 95-0 95-0 95-1 95-0 95-0 95-0 95-0 95-0) 91-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 95-0 15 of 16 HCGS-UFSAR Revision 0 April 11, 1988

TABLE 9A-2 (Cont)

System Tray Screen Motor Rm HVAC B Tray Screen Motor Rm HVAC B Component GQ-TD-9774B2 GQ-TE-9774B Function Trae Screen Room Outside Air Trae Screen Room Air Temp Elec Mech.

Room Div.

Div.

No.

PV&I II TI TS RM 95-0 11 iI TS RM 95-0 16 of 16 HCGS-UFSAR Revision 0 April 11, 1988

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

Functional loc.

H1BJ -1BJLT-4801 H1BJ -1BJLT-4805-1 Hi BJ -1 BJLT-4805-2 H1BJ -1BJLT-N062A-E41 H1BJ -1BJLT-N062E-E41 H1 EA 212221 H1EA 212222 HIEC EC-V008 H1EC EC-V016 H1 EC EC-V017 H1EC EC-V018 H1EC EC-V022 H1EC EC-V023 H1EC EC-V035 H1EC EC-V036 H1EC EC-V037 H1EC EC-V038 H1EC EC-V039 H1 EC EC-V041 H1EC EC-V053 H 1 EC EC-V054 HIEC EC-V055 H 1 EC EC-V102 H1EC EC-V103 H1EC EC-V104 H1EC EC-V105 H1 EC EC-V106 H1EC EC-V1 08 H1EC EC-V1 09 H1EC EC-V110 HIEC EC-V111 HIEC EC-V112 H1EC EC-V113 H1EC EC-V114 H1EC EC-V115 H1EC EC-V116 H1EC EC-V135 H1EC EC-V136 H1 EC EC-V137 H1 EC EC-V138 H1 EC EC-V152 H1 EC EC-V153 H1 EC EC-V154 H1 EC EC-V155 H1EC EC-V1 56 H1EC EC-V1 57 HIEC EC-V158 H1EC EC-V1 59 C - Hope Creek - Ba List 2 - Components Associated V Fuel Pool Cooling Description

HPCI SUPPRESSION POOL LEVEL

SUPPRESSION POOL

SUPPRESSION POOL

HPCI SUPPR POOL LEVEL

HPCI SUPPR POOL LEVEL MOV EA-HV2234 FUEL POOL CLG MOV EA-HV2236 FUEL POOL CLG FUEL POOL PMP AP211 DSCH VLV FUEL STOR POOL DIFF ISLN VLV FUEL STOR POOL DIFF ISLN VLV DRYER/SEP POOL FILL/DRN ISLN V DRY SEP POOL LINER DRN VLV DRYER SEP POOL DRN VLV FUEL POOL PMP AP211 FUEL POOL PMP AP211 FUEL POOL PMP BP211 FUEL POOL PMP BP211 FUEL POOL PMP BP211 FUEL POOL PMP BP211 VNT VLV CASING DRN VNT VLV CASING DRN SUCT VLV DSCH VLV FUEL STOR POOL GT SEAL DRN VLV SPENT FUEL POOL LINER DRN ISO CASK POOL LINER DRN VLV DRY SEP POOL LNR DRN VLV DRYER SEP POOL LINER DRN VLV DRYER SEP POOL LINER DRN VLV DRYER SEP POOL LINER DRN VLV DRYER SEP POOL LINER DRN VLV SPENT FUEL POOL LINER DRN VLV SPENT FUEL POOL LINER DRN VLV SPENT FUEL POOL LINER DRN VLV SPENT FUEL POOL LINER DRN VLV SPENT FUEL POOL LINER DRN VLV SPENT FUEL POOL LINER DRN VLV CASK POOL LINER DRN VLV CASK POOL LINER DRN VLV CASK POOL LINER DRAIN VLV CASK POOL LINER DRN VLV SPENT FUEL POOL SUMP ISLN DRYER SEP POOL LINER DRN VLV DRYER SEP POOL LINER DRN VLV ise Vith Catalog profile CB NU-TMTR NU-TMTR NU-TMTR NU-TMTR NU-TMTR NU-PAN NU-PAN NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV SEISMIC CLASS Seismic Class 1 (I)

Seismic Class 1 (I)

RHR TO RHR TO RHR TO RHR TO RHR TO RHR TO RHR TO RHR TO FUEL STOR POOL HDR VT V FUEL STOR POOL HDR VT V FUEL STOR POOL HDR DRN FUEL STOR POOL HDR DRN FUEL STOR POOL HDR VNT FUEL STOR POOL HDR VT V FUEL STOR POOL HDR DRN FUEL STOR POOL HDR DRN C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional loc.

Description Catalog profile H1EC EC-V183 FUEL POOL F/D DSCH HDR VNT VLV NU-VLV HiEC -1A-E-202 HEAT EXCH-FUEL POOL NU-1HX H1EC -1A-P-211 A' FUEL POOL COOLING PUMP NU-PMP H1EC -1B-E-202 HEAT EXCH-FUEL POOL NU-1HX H1EC -1B-P-211 B' FUEL POOL COOLING PUMP NU-PMP H1EC -1ECEIS-AC652120 FM - FUEL POOL CLG PMP AP 211 NU-MNTR HIEC -1ECEIS-AC652120 FM - FUEL POOL FILTER DEMIN ISOL VLV HV NU-MNTR H1EC -1 ECEIS-AC652120 FM - FUEL POOL FILTER DEMIN BYPASS VLV NU-MNTR H1 EC -1 ECEIS-BC652120 FM - FUEL POOL COOLING PUMP BP211 NU-MNTR H1EC -1ECFAL-4649A H1EC -1 ECFE-4682 HI EC -1 ECHS-4689B2 H1 EC -1 ECHS-4693A2 H1EC -1ECHS-4693B2 H1EC -1 ECKY-A212 H 1EC -lECKY-B212 H1EC -1ECLSL-4667 H1EC -1ECLT-4667 H1 EC -1 ECPSV-4674A H1 EC -1 ECPSV-4674B H1EC -1 ECPT-4669A H1EC -1ECPT-4669B HIEC -1ECSX-4692 HIEC -1ECTE-4683 H1EC -1ECTI-4683 H1 EC -1 ECTR-4683 H1EC -1ECTSH-4683 H1EC -1 ECTT-4683-1 H1EC -1ECTT-4683-2 H 1EC -1 ECV-170 FUEL POOL CLG PMP A DISCH NU-ALRM

FUEL POOL CLG SYS FLOW NU-ELEM FUEL POOL FILTER DEMIN BYPASS REF. DA NU-SW FUEL POOL CLG PMP AP211 REF. DATA NU-SW FUEL POOL CLG PUMP BP211 REF. DATA NU-SW FUEL POOL CLG PMP AP211 NU-TIMR FUEL POOL CLG PP BP 211 NU-TIMR FUEL STORAGE POOL LEVEL NU-SW

FUEL STORAGE POOL LEVEL NU-TMTR

FUEL POOL HTX AE202 RELIEF VALVE NU-SRV

FUEL POOL HTX BE202 NU-SRV

FUEL POOL CLG PMP A SUCT NU-TMTR

FUEL POOL CLG PMP B SUCT NU-TMTR

FUEL POOL HT EXCH OUT NU-ELEM

FUEL POOL CLG PMP DISCH HDR SEE ENC-NU-ELEM FUEL POOL CLG DISCH HDR REF. DATA NU-IND FUEL POOL OUTLET TEMP NU-REC FUEL POOL CLG DISCH HDR NU-SW FUEL POOL CLG DISCH HDR NU-TMTR FUEL POOL CLG DISCH HDR REF. DATA NU-TMTR SEISMIC CLASS Seismic Class 1 (I)

Seismic Class 1 (1)

Seismic Class 1 (I)

Seismic Class 1 (1)

Seismic Class 1 (I)

LP B EMERG MAKEUP TO FUEL POOL H1EC -1ECXIS-AC652120 LM - FUEL POOL CLG PMP AP 211 HIEC -1ECXIS-AC652120 LM - FUEL POOL CLG PMP AP 211 NU-MOV NU-LOGC NU-LOGC H1EC -1ECXIS-AC652120 LM - FUEL POOL FILTER DEMIN ISOL VLV HV. NU-LOGC H1EC -1ECXIS-AC652120 LM - FUEL POOL FILTER DEMIN BYPASS VLV NU-LOGC HIEC -1ECXIS-BC652120 LM - FUEL POOL COOLING PUMP BP211 NU-LOGC H1EC -1ECXIS-BC652120 LM - FUEL POOL COOLING PUMP BP211 NU-LOGC H1EC -1ECZS-4676A H1EC -1ECZS-4676B HI EC -1 ECZS-4678 H1EC 212103 HIEC 212254 H1EC 222103 H1EC 222154 H 1 EC 222244 H1 EC -HS-4647 H1EC -H S-4648 H1EC -HS-4676A H1EC -HS-4676B

FUEL POOL HTX OUTLET

FUEL POOL HTX OUTLET

FUEL POOL FILT DEMIN INLET PMP,FUEL POOL CLG 1AP211 MOV EC-HV4647 FUEL POOL M/U A PMP,FUEL POOL CLG 1 BP211 MOV EC-HV4648 FUEL POOL M/U B MOV EC-HV4689B FUEL POOL DM FUEL POOL CLG HV-4647 C/SW FUEL POOL CLG HV-4648 C/SW FUEL POOL CLG HV-4676A C/SW FUEL POOL CLG HV-46768 C/SW NU-SW NU-SW NU-SW NU-PAN NU-PAN NU-PAN NU-PAN NU-PAN NU-SW NU-SW NU-SW NU-SW

Functional loc.

H1 EC -HS-4678 H 1 EC -H S-4689A H1EC -HS-4689B1 H1EC -HS-4693A1 H1EC -HS-4693B1 H 1 EE 212233 H1EE 212241 H1EE 222212 HWEE 222221 H1EE -EE-HV-4652 H1 EE -EE-HV-4679 H1EE -EE-HV-4680 H1EE -EE-HV-4681 H1EG EG-V768 HMEG EG-V769 H1 EG EG-V945 H 1 EG EG-V946 H1 EG EG-V947 H1 EG EG-V948 H1 EG -1 EGHS-2314A2 H1EG -1EGHS-2314B2 H1EG -1EGHS-2317A2 H1EG -1EGHS-2317B2 HIEG -1EGHS-7921A2 HIEG -1EGHS-7921B2 H1EG -1EGHS-7922A2 H1 EG -1 EGHS-7922B2 H1EG -1EGPDSL-2529A H1EG -1EGPDSL-2529B H1EG -1EGPDT-2529A H1EG -1EGPDT-2529B HI EG -1 EGPSV-2530A HiEG -1EGPSV-2530B HIEG -1EGTW-2315A H1EG -1 EGTW-2315B H1EG -1 EGV-1 38 HIEG -1EGV-545 H1EG -1EGV-547 HIEG -EG-HV-2317A H1EG -EG-HV-2317B H1 EG -EG-HV-7922A H1EG -EG-HV-7922B HIEG -HS-2314A1 HIEG -HS-2314B1 HIEG -HS-2317A1 H1EG -HS-2317B1 HIEG -HS-7921A1 HIEG -HS-7921B1 C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Description Catalog profile FUEL POOL CLG HV-4678 C/SW NU-SW FUEL POOL CLG HV-4689A C/SW NU-SW FUEL POOL CLG HV-4689B C/SW NU-SW FUEL POOL CLG PMP AP211 C/SW NU-SW FUEL POOL CLG PMP BP211 C/SW NU-SW MOV EE-HV4652 SUPP POOL ISO NU-PAN MOV EE-HV4680 SUPP POOL ISO NU-PAN MOV EE-HV4679 SUPP POOL ISO NU-PAN MOV EE-HV4681 SUPP POOL ISO NU-PAN OPNO02 SUP POOL RET INBD ISLN 52-21223: NU-MO OPNO01 SUP POOL RET OTBD ISLN 52-22221 NU-MO OPNO03 SUP POOL SPLY INB ISLN 52-212241 NU-MO OPNO04 SUP POOL SPLY OTBD ILN 52-22222 NU-MO FUEL POOL HX AE202 SACS OUTLET VLV FUEL POOL HX BE202 SACS OUTLET VLV FUEL POOL HX AE202 SUP VNT VLV FUEL POOL HX AE202 RNT VNT VLV FUEL POOL HX BE202 SUP VNT VLV FUEL POOL HX BE202 RTN VNT VLV FUEL POOL HX AE202 REF. DATA FUEL POOL HX BE202 REF. DATA FUEL POOL HX AE202 REF. DATA FUEL POOL HX BE202 REF. DATA FUEL POOL HX AE202 REF. DATA FUEL POOL HX BE202 REF. DATA FUEL POOL HX AE202 REF. DATA FUEL POOL HX BE202 REF. DATA FUEL POOL HEAT EXCH A FUEL POOL HEAT EXCH B

FUEL POOL HEAT EXCH A

FUEL POOL HEAT EXCH B

FUEL POOL HX AE202

FUEL POOL HX BE202 SACS SIDE RELIEF VI

FUEL POOL HX AE202

FUEL POOL HX BE202 VLV/HV2314A FL-POOL CLG HX A SACS ISLr NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-SW NU-SW NU-SW NU-SW NU-SW NU-SW NU-SW NU-SW NU-SW NU-SW NU-TMTR NU-TMTR NU-SRV NU-SRV NU-ELEM NU-ELEM NU-MOV SEISMIC CLASS Seismic Class 1 (I)

Seismic Class 1 (I)

Seismic Class 1 (i)

Seismic Class 1 (I)

FUEL POOL COOLING HX SACS INLET X-TIE ' NU-MOV FUEL POOL COOLING HX SACS CROSS TIE I' NU-MOV OPN544 FUEL POOL HX A X-CONN 52-21212 NU-MO OPN545 FUEL POOL HX B X-CONN 52-22212 NU-MO OP/V546 FUEL POOL HX A X-CONN 52-21212. NU-MO OPN547 FUEL POOL HX B X-CONN 52-22212. NU-MO FUEL POOL CLG HV-2314A C/SW NU-SW FUEL POOL CLG HV-2314B C/SW NU-SW FUEL POOL CLG HV-2317A1 C-SW NU-SW FUEL POOL CLG HV-2317B C/SW NU-SW FUEL POOL CLG HV-7921A C/SW NU-SW FUEL POOL CLG HV-7921B C/SW NU-SW C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional loc.

HIEG -HS-7922A1 HIEG -HS-7922B1 HIKE S-2009 HOEC -P-EC-V9945 HOEC -P-EC-V9946 HOEC -P-EC-V9949 HOEC -P-EC-V9950 HOEC -P-EC-V9951 HOEC -P-EC-V9952 HOEC -P-EC-V9953 HOEC -P-EC-V9954 HOEC -P-EC-V9955 HOEC -P-EC-V9956 HOEC -P-EC-V9957 HOEC -P-EC-V9958 HOEC -P-EC-V9959 HOEC -P-EC-V9960 HOEC -P-EC-V9961 HOEC -P-EC-V9962 HOEC -P-EC-V9963 H1EC EC-V005 H1EC EC-V006 H1EC EC-V008 HIEC EC-V009 H1EC EC-V010 H1EC EC-V016 H1EC EC-V017 H1EC EC-V018 H1EC EC-V020 H1EC EC-V022 HIEC EC-V023 H1EC EC-V024 H1EC EC-V025 H1EC EC-V027 H1EC EC-V029 H1EC EC-V030 H1EC EC-V031 H1EC EC-V032 H1EC EC-V035 H1EC EC-V036 H1EC EC-V037 H1EC EC-V038 H1EC EC-V039 H1EC EC-V041 H 1 EC EC-V046 H1EC EC-V047 H I EC EC-V050 H1EC EC-V051 Description FUEL POOL CLG HV-7922A C/SW FUEL POOL CLG HV-7922B C/SW SPENT FUEL POOL GATES INST ROOT VLV FOR SX-4692 INST ROOT VLV FOR FT-4682 LO INST ROOT VLV FOR LT-4667 INST ROOT VLV FOR FT-4682 HI INST ROOT VLV FOR FT-4649A INST ROOT VLV FOR FE-4649A INST ROOT VLV FOR PT-4672A__& PI-4673A INST ROOT VLV FOR PT-4662A INST ROOT VLV FOR PT-4669A INST ROOT VLV FOR PT-4669B INST ROOT VLV FOR PT-4662B INST ROOT VLV FOR PT-4672B_& PI-4673B INST ROOT VLV FOR FT-4649B INST ROOT VLV FOR FT-4649B INST ROOT VLV FOR LT-4661B INST ROOT VLV FOR LT-4660 INST ROOT VLV FOR LT-4661A SKIMMER SRG TK OTL HDR ISLN FUEL PL PMP AP211 SUCT VLV FUEL POOL PMP AP211 DSCH VLV HX AE202 INLET VLV HX AE202 OTL VLV FUEL STOR POOL DIFF ISLN VLV FUEL STOR POOL DIFF ISLN VLV DRYER/SEP POOL FILL/DRN ISLN V RX WELL DR HDR-FPCC PMP SUC HDRISO V DRY SEP POOL LINER DRN VLV DRYER SEP POOL DRN VLV RX WELL DIFF ISLN VLV RX WELL LINER DRN VLV RX WELL DIFF ISLN VLV RX WELL LINER DRN VLV RX WELL GRTES DRN HDR ISLN VLV RX WELL GRTES DRN VLV FUEL CASK STOR PIT FILL/DRN V FUEL POOL PMP AP211 VNT VLV FUEL POOL PMP AP211 CASING DRN FUEL POOL PMP BP211 VNT VLV FUEL POOL PMP BP211 CASING DRN FUEL POOL PMP BP211 SUCT VLV FUEL POOL PMP BP211 DSCH VLV F/D OUT HDR TEST CONN VLV CONN FILL/DRN HDR XCONN TO FD SKIM SURGE TK OUT XCONN VLV FUEL CASK STOR PIT DIFF ISLN V Catalog profile NU-SW NU-SW NU-MISCM NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-RTVL NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV SEISMIC CLASS Seismic Class 1 (I)

Seismic Class 1 (I)

Functional loc.

H1EC EC-V052 H1EC EC-V053 H1EC EC-V054 H1 EC EC-V055 H1EC EC-V056 H1EC EC-V057 H1EC EC-V060 H1EC EC-V061 HIEC EC-V081 H 1 EC EC-V082 H1EC EC-V084 H1EC EC-V093 HIEC EC-V101 HIEC EC-V102 H1 EC EC-V103 H1EC EC-V104 H1EC EC-V105 H1EC EC-V106 H1EC EC-V1 07 H1EC EC-V108 H1EC EC-V109 H1EC EC-V110 H1EC EC-V111 H1EC EC-V112 H1EC EC-V113 H1EC EC-V114 H1EC EC-V115 H1EC EC-V116 H1EC EC-V1 32 HIEC EC-V1 35 HIEC EC-V136 H1EC EC-V137 H1EC EC-V1 38 HIEC EC-V1 39 H1EC EC-V140 H1 EC EC-V141 H1 EC EC-V142 H1EC EC-V143 H1 EC EC-V149 H1 EC EC-V150 H1 EC EC-V152 H1EC EC-V1 53 H1EC EC-V1 54 HIEC EC-V1 55 H1EC EC-V1 56 H1EC EC-V1 57 HIEC EC-V1 58 HIEC EC-V1 59 C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Description Catalog profile FUEL CASK STOR PIT GT SEAL DRN NU-VLV FUEL STOR POOL GT SEAL DRN VLV NU-VLV SPENT FUEL POOL LINER DRN ISO NU-VLV CASK POOL LINER DRN VLV NU-VLV SKIM SURGE LT4661A ISLN VLV NU-VLV COND TO FUEL CAST STOR PIT ISO NU-VLV RHR TO FUEL STOR PL DIFF ISLN NU-VLV RHR TO FUEL STOR PL DIFF ISLN NU-VLV HX BE202 INLET VLV NU-VLV HX BE202 OTL VLV NU-VLV FPCCS HX BYPASS VLV NU-VLV SKIM SURGE TK OTL HDR TO RHR CB NU-VLV F/D INL HDR DRN VLV NU-VLV DRY SEP POOL LNR DRN VLV NU-VLV DRYER SEP POOL LINER DRN VLV NU-VLV DRYER SEP POOL LINER DRN VLV NU-VLV DRYER SEP POOL LINER DRN VLV NU-VLV DRYER SEP POOL LINER DRN VLV NU-VLV REACTOR WELL LINER DRN VLV NU-VLV SPENT FUEL POOL LINER DRN VLV NU-VLV SPENT FUEL POOL LINER DRN VLV NU-VLV SPENT FUEL POOL LINER DRN VLV NU-VLV SPENT FUEL POOL LINER DRN VLV NU-VLV SPENT FUEL POOL LINER DRN VLV NU-VLV SPENT FUEL POOL LINER DRN VLV NU-VLV CASK POOL LINER DRN VLV NU-VLV CASK POOL LINER DRN VLV NU-VLV CASK POOL LINER DRAIN VLV NU-VLV F/D OUT HDR DRN VLV NU-VLV CASK POOL LINER DRN VLV NU-VLV SPENT FUEL POOL SUMP ISLN NU-VLV DRYER SEP POOL LINER DRN VLV NU-VLV DRYER SEP POOL LINER DRN VLV NU-VLV HX AE202 OUT DRN VLV NU-VLV HX BE202 OUT DRN VLV NU-VLV COND FILL/DRN HDR XCONN TO FD NU-VLV SKIM SURG TK OUT HDR TO RHR NU-VLV RX WELL DRN ISLN VLV NU-VLV SKIM SURGE TK OTL TI RHR VNT V NU-VLV SKIM SURG TK OTL TO RHR FLUSH CONN VI NU-VLV RHR TO FUEL STOR POOL HDR VT V NU-VLV RHR TO FUEL STOR POOL HDR VT V NU-VLV RHR TO FUEL STOR POOL HDR DRN NU-VLV RHR TO FUEL STOR POOL HDR DRN NU-VLV RHR TO FUEL STOR POOL HDR VNT NU-VLV RHR TO FUEL STOR POOL HDR VT V NU-VLV RHR TO FUEL STOR POOL HDR DRN NU-VLV RHR TO FUEL STOR POOL HDR DRN NU-VLV SEISMIC CLASS Seismic Class 1 (I)

Seismic Class 1 (I)

Seismic Class 1 (1)

Functional Ioc.

H1EC EC-V161 HIEC EC-V162 H1EC EC-V1 63 H1EC EC-V166 H1EC EC-V1 67 H1EC EC-V172 H1EC EC-V173 H1EC EC-V1 74 H1EC EC-V175 H1EC EC-V176 H1EC EC-V177 HiEC EC-V178 HIEC EC-V179 H1EC EC-V1 80 H1EC EC-V182 H1EC EC-V1 83 H1EC -1A-E-202 H1EC -IA-P-211 H1EC -1B-E-202 H1EC -1B-P-211 C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Description SKIM SURG TK LT-4661 B ISLN VLV F/D OTL HDR TST CONN LN DRN V FPCCS HX OTL HDR LN VT VLV FUEL PMP AP211 SUCT DRN V FUEL PMP BP211 SUCT LN DRN V FUEL PMP AP211 SUCT FLSH CONN FUEL PMP AP211 DSCH FLSH CONN FUEL PMP BP211 SUCT FLSH CONN FUEL PMP BP211 DSCH FLSH CONN HX AE202 DSCH FLUSH CONN VLV HX AE202 DSCH FLUSH CONN VLV HX BE202 INLET FLUSH CONN VLV HX BE202 DSCH FLUSH CONN VLV COND TO FUEL CSK STOR LN DRN V FUEL CSK STOR GT SL DRN LN VT FUEL POOL F/D DSCH HDR VNT VLV HEAT EXCH-FUEL POOL A' FUEL POOL COOLING PUMP HEAT EXCH-FUEL POOL B' FUEL POOL COOLING PUMP Catalog profile NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-1HX NU-PMP NU-1HX NU-PMP NU-MNTR H1EC -1ECEIS-AC652120 FM - FUEL POOL CLG PMP AP 211 H1EC -1ECEIS-AC652120 FM - FUEL POOL FILTER DEMIN ISOL VLV HV NU-MNTR H1EC -1ECEIS-AC652120 FM - FUEL POOL FILTER DEMIN BYPASS VLV NU-MNTR H1EC -1ECEIS-AC652120 FM - CLEAN-UP VALUE HV-4647 HIEC -1ECEIS-AC652120 FM - CLEAN-UP PROT INTLK IN TEST H1EC -1ECEIS-AC652120 FM - ISOLATION VLVS OVLD/PWR MONTR H1EC -1 ECEIS-BC652120 FM - FUEL POOL COOLING PUMP BP211 H1EC -1 ECEIS-BC652120 FM - FP CLG FLTR DEMIN BP HV-4689B H1EC -1ECEIS-BC652120 FM - FP FLTR DEMIN ISLN VLV HV-4676B H1EC -1ECEIS-BC652120 FM - FP CLG + TORUS WTR VLV HV-4648 H1EC -1 ECEIS-BC652120 FM - FP CLG-TORUS WTR CU PROT INTLK H1EC -1 ECEIS-BC652120 FM - FP CLG OVLD/PWR FAIL MONITOR NU-MNTR NU-MNTR NU-MNTR NU-MNTR NU-MNTR NU-MNTR NU-MNTR NU-MNTR NU-MNTR NU-ALRM NU-ALRM NU-ELEM NU-ELEM NU-ELEM NU-SW NU-SW NU-TMTR NU-TMTR SEISMIC CLASS Seismic Class 1 (I)

Seismic Class 1 (I)

Seismic Class 1 (1)

Seismic Class 1 (I)

Hi EC -1 ECFAL-4649A H1EC -1ECFAL-4649B H1EC -lECFE-4649A H1EC -1ECFE-4649B H1EC -1ECFE-4682 H1EC -1ECFSL-4649A H1EC -1ECFSL-4649B H1EC -1 ECFT-4649A H1EC -1 ECFT-4649B HiEC -1ECHS-4689B2 H1 EC -1 ECHS-4693A2 HI EC -1 ECHS-4693A3 H1 EC -1 ECHS-4693B2 H1EC -1ECHS-4693B3 H 1EC -1ECKY-4649A H1EC -1ECKY-4649B FUEL POOL CLG PMP A DISCH PUMP BP-211 DISCH

PUMP AP-211 DISCH

PUMP BP-211 DISCH

FUEL POOL CLG SYS FLOW PUMP AP-211 DISCH PUMP BP-211 DISCH

PUMP AP-211 DISCH

PUMP BP-211 DISCH FUEL POOL FILTER DEMIN BYPASS REF. DA NU-SW FUEL POOL CLG PMP AP211 REF. DATA NU-SW MCC KEYSWITCH FOR 1A-P-211 NU-SW FUEL POOL CLG PUMP BP211 REF. DATA NU-SW MCC KEYSWITCH FOR 1B-P-211 NU-SW PUMP AP-211 LOW DISCH FLOW TIME DELAM NU-RELYI PUMP BP-211 LOW DISCH FLOW TIME DELAM NU-TIMR

Functional loc.

H 1EC -1 ECKY-A212 H1EC -1ECKY-B212 H1EC -1EC LR-4661B H1EC -1ECLSHH-4660 H1EC -1ECLSHL-4660 H1EC -1ECLSL-4667 H1EC -1ECLSLL-4661A H1EC -1ECLSLL-4661B H1EC -1EC LT-4660 H1EC -1ECLT-4661A HiEC -1ECLT-4661B H1EC -1 ECLT-4667 H1EC -1ECLV-4660 HIEC -1ECPSL-4669A H1EC -1ECPSL-4669B H1 EC -1 ECPSV-4674A HI EC -1 ECPSV-4674B HIEC -1ECPT-4669A H1EC -1ECPT-4669B HIEC -1ECSV-4660 H1EC -1 ECSV-4676A H1EC -1 ECSV-4676B H1EC -1 ECSV-4678 H1EC -1ECSX-4692 H1EC -1ECTE-4683 H1EC -1ECTI-4683 H1EC -1 ECTR-4683 H1EC -1ECTSH-4683 H1EC -1 ECTT-4683-1 H1EC -1 ECTT-4683-2 H1EC -1ECV-007 HiEC -1ECV-011 HIEC -1ECV-012 H1EC -1ECV-013 H1EC -1ECV-014 H1EC -1ECV-015 H1EC -1ECV-040 HIEC -1ECV-100 H1EC -1ECV-169 H1EC -1 ECV-1 70 H1EC -1 ECXAL-1 803 H1EC -1 ECXAL-1 807 H1EC -1ECXAL-4600A H1EC -1ECXAL-4600B C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Description Catalog profile FUEL POOL CLG PMP AP211 NU-TIMR FUEL POOL CLG PP BP 211 NU-TIMR SKIMMER SURGE TANK B NU-REC SKIMMER SURGE TANK "B" LEVEL SWITCH (( NU-SW SKIMMER SURGE TANK "B" LEVEL SWITCH (( NU-SW FUEL STORAGE POOL LEVEL NU-SW SKIMMER SURGE TK B NU-SW SKIMMER SURGE TANK B NU-SW

SKIMMER SURGE TANK "B" LEVEL CONTROl NU-TMTR

SKIMMER SURGE TANK B

SKIMMER SURGE TANK B

FUEL STORAGE POOL LEVEL

SKIMMER SURGE TK B MAKE-UP SUPPLY INAK PER CP 80081223 INAK PER CP 80081223

FUEL POOL HTX AE202 RELIEF VALVE

FUEL POOL HTX BE202

FUEL POOL CLG PMP A SUCT

FUEL POOL CLG PMP B SUCT NU-TMTR NU-TMTR NU-TMTR LI NU-VO NU-SW NU-SW NU-SRV NU-SRV NU-TMTR NU-TMTR SKIMMER SURGE TNK LVL CNTRL / 1ECLV-4E NU-SV FOR HV-4676 A NU-SV FOR HV-4676 B NU-SV FOR HV-4678 NU-SV

FUEL POOL HT EXCH OUT NU-ELEM

FUEL POOL CLG PMP DISCH HDR SEE ENC NU-ELEM FUEL POOL CLG DISCH HDR REF. DATA NU-IND FUEL POOL OUTLET TEMP NU-REC FUEL POOL CLG DISCH HDR NU-SW FUEL POOL CLG DISCH HDR NU-TMTR FUEL POOL CLG DISCH HDR REF. DATA NU-TMTR "A" FUEL COOLING PUMP DISCHARGE CHEC NU-CKVL FLTR DEMIN INLET OUTBD ISLN NU-AOV FLTR DEMIN INLET INBD ISLN NU-AOV

VALVE CLASS: HBC NU-MOV

VALVE CLASS: HCC NU-AOV

VALVE CLASS: HCC NU-CKVL

VALVE CLASS: HBC NU-CKVL

VALVE CLASS: HBC NU-MOV

VALVE CLASS: CCA NU-MOV LP B EMERG MAKEUP TO FUEL POOL NU-MOV RSP TAKEOVER ALM LTS NU-IND RSP TAKEOVER ALM LTS NU-IND AP211 INTLK IN TEST ALM NU-IND BP211 INTLK IN TEST ALM NU-IND SEISMIC CLASS Seismic Class 1 (I)

Seismic Class 1 (I)

H1EC -1ECXIS-AC652120 LM - FUEL POOL CLG PMP AP 211 NU-LOGC H1 EC -1 ECXIS-AC652120 LM - FUEL POOL CLG PMP AP 211 NU-LOGC H1 EC -1 ECXIS-AC652120 LM - FUEL POOL FILTER DEMIN ISOL VLV HV. NU-LOGC H1 EC -1 ECXIS-AC652120 LM - FUEL POOL FILTER DEMIN BYPASS VLV NU-LOGC C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional loc.

Description H1EC -1ECXIS-AC652120 LM - CLEAN-UP VALUE HV-4647 H1EC -1ECXIS-AC652120 LM - CLEAN-UP PROT INTLK IN TEST H1EC -1ECXIS-AC652120 LM - ISOLATION VLVS OVLD/PWR MONTR H1EC -1 ECXIS-AC652120 LM - ISOLATION VLVS OVLD/PWR MONTR H1EC -1ECXIS-BC652120 LM - FUEL POOL COOLING PUMP BP211 H1EC -1ECXIS-BC652120 LM - FUEL POOL COOLING PUMP BP211 HIEC -1ECXIS-BC652120 LM - FP CLG FLTR DEMIN BP HV-4689B H1EC -1ECXIS-BC652120 LM - FP FLTR DEMIN ISLN VLV HV-4676B HIEC -1ECXIS-BC652120 LM - FP FLTR DEMIN ISLN VLV HV-4678 H1EC -1ECXIS-BC652120 LM - FP CLG + TORUS WTR VLV HV-4648 H IEC -1ECXIS-BC652120 LM - FP CLG-TORUS WTR CU PROT INTLK HIEC -1ECXIS-BC652120 LM - FP CLG OVLD/PWR FAIL MONITOR H1EC -1ECXIS-BC652120 LM - FP CLG OVLD/PWR FAIL MONITOR H1EC -1 ECXV-4662A HIEC -1ECXV-4662B H1EC -1ECXV-4673A H1EC -1ECXV-4673B H1EC -1ECXV-4682A HiEC -1ECXV-4682B H1EC -1ECZS-4676A HIEC -1ECZS-4676B H1EC -1ECZS-4678 HIEC 212103 H1EC 212244 H1EC 212254 H1EC 222103 H1EC 222154 H 1 EC 222244 H1EC -EC-HS-4660 H 1 EC -EC-HV-4647 H 1 EC -EC-HV-4648 H 1 EC -EC-HV-4676A H 1 EC -EC-HV-4676B H1 EC -EC-HV-4678 H 1 EC -EC-HV-4689A H1EC -EC-HV-4689B H1EC -HS-4647 HIEC -HS-4648 H1 EC -HS-4676A H 1 E C -H S-4676B HIEC -HS-4678 H 1 EC -HS-4689A H1EC -HS-4689B1 HIEC -HS-4693A1 HIEC -HS-4693B1 H1GU -1GUPDR-EC141 EFCV FOR PT-4662A EFCV FOR PT-4662B EFCV FOR PT-4672A & PI-4673A EFCV FOR PT-4672B & PI-4673B EFCV FOR FT-4682 LO EFCV FOR FT-4682 HI

FUEL POOL HTX OUTLET

FUEL POOL HTX OUTLET

FUEL POOL FILT DEMIN INLET PMP,FUEL POOL CLG 1AP211 MOV EC-HV4689A FP FLTR DM BYP MOV EC-HV4647 FUEL POOL M/U A PMP,FUEL POOL CLG 1 BP211 MOV EC-HV4648 FUEL POOL M/U B MOV EC-HV4689B FUEL POOL DM H& SWT FOR EC-HV-4660 TBPE Catalog profile NU-LOGC NU-LOGC NU-LOGC NU-LOGC NU-LOGC NU-LOGC NU-LOGC NU-LOGC NU-LOGC NU-LOGC NU-LOGC NU-LOGC NU-LOGC NU-CKVL NU-CKVL NU-CKVL NU-CKVL NU-CKVL NU-CKVL NU-SW NU-SW NU-SW NU-PAN NU-PAN NU-PAN NU-PAN NU-PAN NU-PAN NU-SW SEISMIC CLASS Seismic Class 1 (I)

Seismic Class 1 (I)

OP/1 -V1 69 SPNT FUEL STOR PL FL 52-212254 NU-MO OP/1-V170 SPNT FUEL STOR PL FL 52-222154 NU-MO OP/1-V011 F/D OUTBD INL ISLN NU-AO OP/1-VO12 F/D INBD INL ISLN NU-AO OP/1-VO14 F/D OTL ISLN AOV NU-AO OP/1-V013 F/D BYPASS MOV 52-212244 NU-MO OP/1-V100 F/D BYPASS MOV 52-222244 NU-MO FUEL POOL CLG HV-4647 C/SW NU-SW FUEL POOL CLG HV-4648 C/SW NU-SW FUEL POOL CLG HV-4676A C/SW NU-SW FUEL POOL CLG HV-4676B C/SW NU-SW FUEL POOL CLG HV-4678 C/SW NU-SW FUEL POOL CLG HV-4689A C/SW NU-SW FUEL POOL CLG HV-4689B C/SW NU-SW FUEL POOL CLG PMP AP211 C/SW NU-SW FUEL POOL CLG PMP BP211 C/SW NU-SW SPARE, BLUE SCALE NU-REC HIKJ -1A-G-400-FUEL IN. EMERGNCY DIESEL GENERATOR FUEL INJE, NU-GEN HIKJ -1AC420-RECT-ASEA EDG RECTIFIER ASSEMBLY SELECTOR SVA NU-MISCE C - Hope Creek - Base List 2 - Components Associated With Fuel Pool Cooling Functional loc.

Description Catalog profile H1 KJ -1 B-G-400-FUEL IN, EMERGNCY DIESEL GENERATOR FUEL INJE' NU-GEN H1KJ -1BC420-RECT-ASc B EDG RECTIFIER ASSEMBLY SELECTOR SV NU-MISCE H1KJ -1C-G-400-FUEL IN, EMERGNCY DIESEL GENERATOR FUEL INJEiNU-GEN H1KJ -1CC420-RECT-ASE C EDG RECTIFIER ASSEMBLY SELECTOR SV NU-MISCE H1KJ -1D-G-400-FUEL IN, EMERGNCY DIESEL GENERATOR FUEL INJE'NU-GEN H1KJ -1DC420-RECT-AS5 D EDG RECTIFIER ASSEMBLY SELECTOR SV' NU-MISCE H1SE -1SEVR-271RMEC5, IRM E VOLTAGE PRE REGULATOR NU-SGCD H1SE -1SEVR-291RMEC5, IRM E VOLTAGE REGULATOR NU-CONT H1SE -1SEXI-M1IRMEC51 IRM E POWER INDICATOR NU-IND H1SE -1SEXY-Z131REC51 MEAN SQ ANAL. MOD. IRM E NU-SGCD H1BC BC-V094 H1BC BC-V626 H1BC BC-V627 H1BC BC-V628 H1BC BC-V629 H1EA EA-V584 H 1 EA-1 -EA-V585 H 1 EC EC-V020 H1EC EC-V084 H1EC EC-V163 H1EG -1EGSX-2578A H1EG -1EGSX-2578B H1 EG -EG-HV-2314A H1EG -EG-HV-2314B H1EC -1 EC021 W001 H1EC -1EC021W002 H1EC -1EC021W003 H1EC -1EC021W004 RHR LOOP B DSCH TO FPCCS ISO V CB NU-VLV B RHR TO FPCC VENT B RHR TO FPCC VENT A RHR TO FPCC VENT A RHR TO FPCC VENT SERV WTR M/U TO FPCCS DRN VLV SERV WTR M/U TO FPCCS VNT VLV RX WELL DR HDR-FPCC PMP SUC HDRISO FPCCS HX BYPASS VLV FPCCS HX OTL HDR LN VT VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV NU-VLV V NU-VLV NU-VLV NU-VLV SEISMIC CLASS Seismic Class 1 (I)

Seismic Class 1 (I)

A' FPCC HTX SACS DR PT SACS GRAB SMPL NU-ELEM B FPCC HTX SACS DR PT SACS GRAB SMPL NU-ELEM OPN138 F/POOL CLG HX SUP ISLN 52-21212 NU-MO OPN140 F/POOL CLG HX SUP ISLN 52-22212' NU-MO WATER FROM VALVES BC-V023 & BC-V094 T, NU-WELD WATER FROM VALVES BC-V023 & BC-V094 Ti NU-WELD WATER FROM VALVES BC-V023 & BC-V094 T, NU-WELD WATER FROM VALVES BC-V023 & BC-V094 T, NU-WELD

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

SL Report No.: SL-011553 Rev. No. 2 January 29, 2014 Hope Creek - Seismic Walkdown Equipment List (SWEL)

(Sorted by EQ. Class)

Risk New or Anchored to EQsk Safety Ne r

IPEEE Concrete or 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 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

~~Diesel 16 HC-37 10A401 PB 3

4.16kV SWGR CHN A 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____

IR2 P1

SL Report No.: SL-011553 Rev. No. 2 January 29, 2014 Hope Creek - Seismic Walkdown Equipment List (SWEL)

(Sorted by EQ. Class)

Anchored to EQsk Safety Re or IPEEE Concrete or No.

AWB #

Comp. ID System EQ Component Description Bldg.

Elev.

Room NO.

Significant Replaced E

Strcre Notes Class (YNN)

Function y)

Enhanced Structure

(/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 54 4109 m

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 R

77 4214 Y

3,4,5 0

Rm 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 50 HC-20 HV-F011B AE 8

MOV-FW Iso. VLV Inside Cont'nt Reactor/Dr 10 423,0 DertoRO R2 ywell 4

Reactor/Dr 51 HC-20 HV-F016 AB 8

MOV-Inboard MSIV Drain Reactor/Dr 102 4220 Y

2 0

Defer to RFO ywellII 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____________

P2

SL Report No.: SL-011553 Rev. No. 2 January 29, 2014 Hope Creek - Seismic Walkdown Equipment List (SWEL)

(Sorted by EQ. Class)

Anchored to EQ.

Risk Saey New or IPE Coceer No.

AWB #

Comp. ID System EQ.

Component Description Bldg.

Elev.

Room NO.

Significant Safeut Replaced IPEEE Concrete or Notes Class Function Enhanced Structure (Y/N/NA)

(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 130 4220 Y

2,4 Y

0 Defer to RFO Hywell R/Steam 54 HC-22 HV-F013 BD 8

MOV-RCIC FW Isol. VLV Tunnel 125 4316 Y

3 0

Defer to RFO Tunnel C_

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)

Control 60 HC-30 CV412 GM 9

Diesel Gen Room Recirc Fan Disl 7i20

/erif.

~~~Diesel

~

51 Control 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.

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 Control 54 12 1,3451 Diesel 54 5128 Y

1,2,3,4,5 1

R2 P3

SL Report No.: SL-011553 Rev. No. 2 January 29, 2014 Hope Creek - Seismic Walkdown Equipment List (SWEL)

(Sorted by EQ. Class)

Anchored to Risk Saey New or IPEEE Concrete or 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 155 5614 34 1

Diesel 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

_________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 Stte LgicCabiet hannl C Diesel R/CRD 91 HC-17 DC281 GU 20 Unit Cooler Control Panel PmpRm 77 4202 3,4 1Nerif.

Pmp Rm 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 R2 P4

SL Report No.: SL-011553 Rev. No. 2 January 29, 2014 Hope Creek - Seismic Walkdown Equipment List (SWEL)

(Sorted by EQ. Class)

Anchored to EQRisk New or 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 Diesel Control 98 HC-A3 AC486 GM 20 Panel-Diesel Area HVAC Auxiliary Diesel 155 5620 3,4,5 1 Nerif.

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 R2 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 Project No. 12800-217 Seismic Walkdown Report S&L Report No. SL-011553 Rev. I ATTACHMENT 4 - SEISMIC WALKDOWNS ENGINEER CERTIFICATIONS

'I

1) 4 dii S QuC s

j

~17

/1 Ii A

(Trtu fi tatr of Ar4iflurmrnt 941is is to (1rrtifij tiatt 0')

Arti iT~tun I))

'14

((/8 14as jormpteteb tits §QU(6 walkbouwn

§rrrnming anb-53,eismir Evaluation Tratining Tourser T.e'rb §-epeMberr 14-1, 4A--

ý-. 7c~r Neil P. Smith, Comn SQUG Chairman Robert P. gassaware SQUG Program Mane ionwealth Edison David A. Freed, MPR Associates SQUG Training Coordinator

a. EPRI ager

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

- Plant Seismic Walkdowns June 27, 2012 Date

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

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

- Plant Seismic Walkdowns June 21, 2012 Date

/f, A? 914ýý 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 Date cf44#.

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 "1

/.-....* *,,, l* ' l~

, J -', l %,,..f, * " " *, 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 Project No. 12800-217 Seismic Walkdown Report S&L Report No. SL-0l11553 Rev. 1 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?

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.

YZ NO

d. Various environments?

YZ NR

e. Equipment enhanced based on the findings of the IPEEE (or equivalent) program?

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.

YZ NO

v t e Letter Sequence Other
TAC:MF0132, (Open)
Initiation Acceptance... Administration Questions Answers 2 December 2013 Results Approval... Other: 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, ML14127A006
MONTHYEAR2014-01-29 [Table View]

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

Text

SUMMARY

SUMMARY

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