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Limerick, Unit 1, MPR-3796, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Revision 1, Part 1 of 12
	ML12342A103
Person / Time
Site:	Limerick
Issue date:	11/06/2012
From:	Schlaseman C S; Exelon Generation Co, MPR Associates
To:	; Office of Nuclear Reactor Regulation
References
	RS-12-171 MPR-3796, Rev 1
	Download: ML12342A103 (169)
	v • d • e

U.S. Nuclear Regulatory Commission 180-Day Response to 50.54(f) Letter NTTF Recommendation 2.3: Seismic November 19, 2012 Page 5 Enclosure 1 Seismic Walkdown Report In Response To The 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the Limerick Generating Station, Unit 1, Report Number: MPR-3796, Revision 1 (681 pages)

SEISMIC WALKDOWN REPORT IN RESPONSE TO THE 50.54(f) INFORMATION REQUEST REGARDING FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC for the LIMERICK GENERATING STATION UNIT I 3146 Sanatoga Road, Pottstown, PA 19464 Facility Operating License No. NPF-39 NRC Docket No. STN 50-352 Correspondence No.: RS-12-171"-w Exelon Exelon Generation Company, LLC (Exelon)PO Box 809398 Chicago, IL 60680-5398 Prepared by: MPR Associates, Inc.320 King Street, Alexandria, VA 22314 Report Number. MPR-3796, Revision 1 Preparer: Reviewer: Approver: Peer Review Team Leader: Lead Responsible Engineer: Branch Manager: Senior Manager Design Engineering:

Corporate Acceptance:

Printed Name Caroline Schlaseman Moitaba Oghbaei John Simons Patrick Butler Brian Wehrman Grea Wallace Signatir~ oAW Date 111612012 11/6/2012 1116/2012 11/6/2012 111/i71 16 h?SW~I¶~E --~Wayne Lewis Jeffrey Clark UMPR ASSOCIATES INC.ENGINE E R S NTTF 2.3 Seismic Walkdown of Limerick Generating Station Unit 1 MPR-3796 Revision 1 November 2012 QUALITY ASSURANCE DOCUMENT This document has been prepared, reviewed, and approved in accordance with the Quality Assurance requirements of 10CFR50 Appendix B and/or ASME NQA-1, as specified in the MPR Nuclear Quality Assurance Program.Prepared by: Caroline S. Schlaseman Reviewed by: _ _ _ 0 _______Mojtaba (ghbaei Approved by: Q- W.

-.Peer Review ,OVi.Team Leader: ____,__Patrick J. Butler Principal Contributors Mojtaba Oghbaei Craig B. Swanner James N. Wiggin Thomas C. King Prepared for Exelon Generation Company, LLC w.-"w Exelon, 320 KING STREET ALEXANDRIA, VA 22314-3230 703-519-0200 FAX: 703-519-0224 hftp:\\www.mpr.com RECORD OF REVISIONS Revision Affected Pages Description 0 1 All All Initial Issue Added IR numbers and milestone dates to Table E-2 for three items; updated Executive Summary for this change.Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 Contents Tables ..........................................................................................................................................

iii Executive Sum m ary ...................................................................................................................

iv 1 Introduction

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1-1 1 .1 B a c kg ro u n d .............................................................................................................

1-1 1.2 Plant Overview ........................................................................................................

1-1 1 .3 A p p ro a c h .................................................................................................................

1-1 2 Seism ic Licensing Basis ................................................................................................

2-1 2.1 Safe Shutdown Earthquake (SSE) ..........................................................................

2-1 2.2 Design of Seismic Category I SSCs ........................................................................

2-1 3 Personnel Qualifications

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3-1 4 Selection of SSCs ...........................................................................................................

4-1 4.1 SW EL Development Overview ...............................................................................

4-1 4.2 SWEL 1 -Sample of Required Items for the Five Safety Functions

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4-1 4.3 SW EL 2 -Spent Fuel Pool Related Items ..............................................................

4-5 4.4 Composite SW EL ....................................................................................................

4-7 5 Seism ic W alkdowns and Area W alk-Bys ......................................................................

5-1 5 .1 O v e rv ie w .................................................................................................................

5 -1 5.2 Seismic W alkdowns ................................................................................................

5-1 5.3 Area W alk-Bys ........................................................................................................

5-3 6 Licensing Basis Evaluations

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6-1 7 IPEEE Vulnerabilities Resolution Report .....................................................................

7-1 8 Peer Review ....................................................................................................................

8-1 8 .1 O v e rv ie w .................................................................................................................

8 -1 8.2 Review of SW EL .....................................................................................................

8-1 8.3 Review of Sample Seismic Walkdown and Area Walk-By Checklists

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8-1 8.4 Review of Licensing Basis Evaluations

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8-2 8.5 Review of Submittal Report .....................................................................................

8-2 Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 Contents (cont'd.)9 R eferences

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9-1 Appendices A Project Personnel Resumes and SWE Certificates

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A-1 B Equipment Lists .............................................................................................................

B-1 C Seismic Walkdown Checklists (SWCs) ..................................................................

C-1 D Area Walk-By Checklists (AWCs) ...........................................................................

D-1 E Plan for Walkdown of Inaccessible Equipment and Assessment of Electrical Cabinet Internal Inspections

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E-1 F Peer Review Report ..................................................................................................

F-1 Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 ii Tables T able 3-1. P ersonnel R oles ...................................................................................................

.3-1 Table 4-1. Base List IPEEE Classes vs. EPRI Seismic Walkdown Guidance Equipment C la s s e s ...................................................................................................................

4 -4 Table 5-1. Anchorage Configuration Confirmation

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5-2 Table 5-2. Issues Identified during Seismic Walkdowns

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5-2 Table 5-3. Issues Identified during Area Walk-Bys ....................................................................

5-3 T able B -1. S W E L for U nit 1 .....................................................................................................

B -83 Table B-2. SW EL for Unit 0 (com m on) ...................................................................................

B-87 Table B-3. Deferred to RFO: Inaccessible, or Requires Removal of Insulation to see A n ch o ra g e ............................................................................................................

B -8 8 Table C-1. Unit 1 Seismic Walkdown Checklists (SWCs) .........................................................

C-2 Table C-2. Unit 0 Seismic Walkdown Checklists (SWCs) .....................................................

C-356 Table D-1. Unit 1 Area Walk-By Checklists (AWCs) ............................................................

D-1 Table D-2. Unit 0 Area Walk-By Checklists (AWCs) ...............................................................

D-87 Table E-1. Summary of Inaccessible Equipment

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E-1 Table E-2. Assessment of Unit 1 Electrical Cabinet Internal Inspections

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E-3 Table E-3. Assessment of Unit 0 Electrical Cabinet Internal Inspections

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E-4 Limerick Generating Station Unit 1 iii MPR-3796, Revision 1 Correspondence No.: RS-12-171 Executive Summary PURPOSE This report documents the seismic walkdowns performed at Limerick Generating Station Unit 1 in response to NRC 50.54(f) letter dated March 12, 2012, Enclosure 3, Recommendation 2.3: Seismic. Exelon committed to perform this work in accordance with the NRC-endorsed Seismic Walkdown Guidance document (Electric Power Research Institute (EPRI) Technical Report 1025286, Reference 1).SCOPE OF WORK In addition to defining the qualifications of personnel performing this work, the EPRI Seismic Walkdown Guidance identifies the following key activities: " Selection of Systems, Structures, and Components (SSC) to be included in the sample scope of the seismic walkdowns.

Screening criteria are applied to obtain an informed sample of electrical and mechanical equipment that are required to perform the four reactor safety functions and containment function, and address NRC concerns about Spent Fuel Pool related equipment. (see Section 4 of this report)" Seismic Walkdowns and Area Walk-Bys are performed by trained, two-person teams of Seismic Walkdown Engineers (SWEs), who document their inspections on structured checklists included in the EPRI Guidance. (see Section 5 of this report)* Seismic Licensing Basis Evaluations are performed for issues identified as"potentially adverse seismic conditions," and all deficiencies are included in the Corrective Action Program (CAP) so that standard plant processes can be used to address the issue. (see Section 6 of this report)* IPEEE Vulnerabilities Resolution Report is required for plants who identified seismic vulnerabilities during their IPEEE program and made commitments to resolve them. (See Section 7 of this report)* Peer Review is required by a team comprised of at least two individuals for each of the key activities of this project. (see Section 8 of this report)RESULTS The Seismic Walkdown Equipment List (SWEL) for Limerick Unit 1, including the items selected that are common to both Units 1 and 2, e.g., spray pond equipment, is comprised of 102 items. Of this list, 92 equipment items were walked down during the 180-day window of completion of the initial scope of work required by the 50.54(f) letter.Walkdowns for the remaining 10 items were deferred to the Unit 1 Refueling Outage Limerick Generating Station Unit 1 iv MPR-3796, Revision 1 Correspondence No.: RS-12-171 (RFO) due to accessibility issues, e.g., location inside primary containment.

Additionally, confirmation that equipment anchorage is consistent with plant design documentation is required for 50% of the SWEL items having anchorage (e.g., not line-mounted).

A total of 45 anchorage configurations were confirmed to be installed in accordance with the design documentation.

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

Tables E-2 (for Unit 1) and E-3 (for common equipment) list all electrical items that require assessment.

As shown in Tables E-2 and E-3, three internal inspections of electrical cabinets are required for Limerick Unit 1, which are being tracked in the plant's Corrective Action Program (CAP).None of the issues identified during the walkdowns of Limerick Unit 1 equipment and nearby areas required formal seismic licensing basis evaluations because none of the issues ultimately were assessed to be adverse seismic conditions.

Smaller issues, however, such as a loose retaining bar bolt on gas bottle storage rack, were identified and entered into the plant's CAP. A total of 10 Issue Reports (IRs) were issued, and the status of IR resolutions is provided in Tables 5-2 and 5-3 for issues identified during equipment walkdowns and area walk-bys, respectively.

As described in Section 7 of this report, no IPEEE seismic vulnerabilities were identified for Limerick Unit 1 due to the conservatism of its original design.CONCLUSIONS

1. As confirmed in the Peer Review Report (see Appendix F), all activities required by the 50.54(f) letter were conducted in accordance with the NRC-endorsed EPRI Seismic Walkdown Guidance, except for the following items: " Ten (10) inaccessible equipment items are scheduled to be walked down during the next Unit 1 RFO in 2014." Three (3) electrical cabinets will need to be opened for an internal inspection for "other adverse seismic conditions" in accordance with NRC expectations that were provided to industry after these walkdowns were completed.

These inspections are scheduled for the next available electrical outages.2. None of the 92 equipment items included in the walkdowns have conditions that would prevent them from performing their safety-related functions following a licensing basis seismic event. Additionally, a sample of more than 50% of equipment with anchorage was confirmed to be consistent with design basis documentation.

3. The ten (10) anomalies or discrepant conditions identified during the equipment walkdowns or area walk-bys have been assessed in accordance with the plant corrective action program (CAP), and their resolutions are being tracked for timely closure.Limerick Generating Station Unit 1 v MPR-3796, Revision 1 Correspondence No.: RS-12-171 1 Introduction

1.1 BACKGROUND

In response to Near-Term Task Force (NTTF) Recommendation 2.3, the Nuclear Regulatory Commission (NRC) issued a 10CFR50.54(f) letter on March 12, 2012 requesting that all licensees perform seismic walkdowns to identify and address plant degraded, non-conforming, or unanalyzed conditions, with respect to the current seismic licensing basis. The Nuclear Energy Institute (NEI), through the Electric Power Research Institute (EPRI), prepared industry guidance to assist licensees in responding to this NRC request. The industry guidance document EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012 (Reference 1), was endorsed by the NRC on May 31, 2012.This report documents the technical basis for Exelon's response to the 10CFR50.54(f) request to conduct seismic walkdowns at Limerick Generating Station Unit 1.1.2 PLANT OVERVIEW The Limerick Generating Station (LGS) consists of two boiling water reactor (BWR)generating units, located in southeastern Pennsylvania.

Both units have GE Mark II containments, are rated at 3515 MWt power, and were designed and constructed by Bechtel (LGS Updated Final Safety Analysis Report (UFSAR) (Reference 2), Section 1.1). Limerick Unit 1 received its full-power license in October 1984 (Facility Operating License No. NPF-39 (Reference 16)).1.3 APPROACH The EPRI Seismic Walkdown Guidance (Reference

1) is used for the Limerick Generating Station Unit 1 engineering walkdowns and evaluations described in this report. In accordance with Reference 1, the following topics are addressed in the subsequent sections of this report:* Seismic Licensing Basis* Personnel Qualifications" Selection of SSCs* Seismic Walkdowns and Area Walk-Bys* Licensing Basis Evaluations

IPEEE Vulnerabilities Resolution Report* Peer Review Limerick Generating Station Unit 1 1-1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 2 Seismic Licensing Basis 2.1 SAFE SHUTDOWN EARTHQUAKE (SSE)The LGS site design response spectra for the SSE are normalized to a maximum horizontal ground acceleration of 15% of gravity. The values for the vertical component of the design response spectra are 2/3 of the horizontal design response spectra. The response spectra are based on data developed from records of previous earthquake activity and represent an envelope of motion expected at a sound rock site from a nearby earthquake (Reference 2, Section 3.7.1.1).2.2 DESIGN OF SEISMIC CATEGORY I SSCs Generic Letter 87-02 issued on February 19, 1987 and Supplement No. 1 issued May 22, 1992, do not list Limerick Unit 1 as an USI A-46 Plant because seismic qualification was addressed during initial operating licensing review (Reference 2, Section 1.12.3).Seismic Category I mechanical and electrical equipment were originally qualified according to the criteria in IEEE 344-1971, but the qualification methods and procedures for qualification were re-assessed to Standard Review Plan (SRP) 3.10 Seismic Qualification Review Team (SQRT) requirements including IEEE 344-1975, and Reg.Guides 1.100 and 1.92. The SQRT reassessment concluded that the seismic and dynamic qualification program meets the intent of IEEE 344-1975 and Reg. Guides 1.100 and 1.92 (Reference 2, Sections 3.9.2.2 and 3.10.2.1).

Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 2-1 3 Personnel Qualifications Table 3-1 below summarizes the names and corresponding roles of personnel who participated in the NTTF 2.3 Seismic Walkdown effort.Table 3-1. Personnel Roles Equipment Seismic Licensing IPEEE Peer Name Selection Plant Walkdown Basis ieer Reer Engineer Operations Engineer Reviewer Reviewer Engineer (SWE) Reviewer T. King X X X X C. Swanner X X x(note 1)M. Oghbaei X X J. Wiggin X X C. Schlaseman X(note 2) X P. Butler x(note 3)B. Shultz X (Exelon)Notes: 1. Peer Review Team member for SWEL review.2. SWE team member for three seismic walkdowns and three area walk-bys; therefore did not act as Peer Reviewer of this portion of the walkdowns.

3. Peer Review Team Leader.A description of the responsibilities of each Seismic Walkdown participant's role(s) is provided in Section 2 of the EPRI Seismic Walkdown Guidance (Reference 1).Resumes provided in Appendix A provide detail on each person's qualifications for his or her role.The SWEL preparer, Thomas King does not have prior experience with the IPEEE program, which was performed during the 1990s. The Peer Reviewers, however, do have experience with IPEEE. For SWEL preparation, Mr. King was provided with the plant's IPEEE submittal report and NRC requests for additional information (RAI)responses, as well as the NRC Safety Evaluation (SE) on the IPEEE program.Mr. King's review of these documents, combined with the reviews by the Peer Reviewers, was sufficient to meet the intent of the guidance in Reference 1 that Equipment Selection Personnel "should also have knowledge of the IPEEE program." Limerick Generating Station Unit 1 3-1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 In addition to the MPR personnel listed above, Exelon Plant Operations, Brandon Shultz, reviewed the SWEL. Mr. Shultz is currently a licensed Senior Reactor Operator (SRO)at Limerick Station. Station personnel also provided support to the SWEL preparer in identifying major equipment or system modifications, equipment and systems located in different environments, and equipment and systems that would be accessible for inspection during the plant walkdowns, in accordance with Reference 1.Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 3-2 4 Selection of SSCs 4.1 SWEL DEVELOPMENT OVERVIEW The EPRI Seismic Walkdown Guidance (Reference

1) defines the process used to develop the Seismic Walkdown Equipment List (SWEL) for Limerick Generating Station Unit 1.In accordance with Reference 1, a SWEL is comprised of two groups of items: 1. SWEL 1 is a sample of items needed to safely shut down the reactor and maintain containment integrity 2. SWEL 2 is a list of spent fuel pool related items 4.2 SWEL I -SAMPLE OF REQUIRED ITEMS FOR THE FIVE SAFETY FUNCTIONS The Limerick Unit I Seismic Individual Plant Examination for External Events (IPEEE)Success Path Component Lists (SPCL) (Reference

3) is considered the "Base List" and is provided in Appendix B of this report. To ensure the SPCL Base List meets the EPRI Seismic Walkdown Guidance, the SPCL was compared with the screens described in the following sections.4.2.1 Screen #1 -Seismic Category I As described in Reference 1, only items that have a defined seismic licensing basis are to be included in SWEL 1. The seismic classification was identified for each item on the IPEEE SPCL, and items that were not Seismic Category I were removed from consideration for inclusion in SWEL 1. Seismic classification was determined through a review of current design and licensing basis documentation.

4.2.2 Screen

2 -Equipment or Systems This screen narrowed the scope of items to include only those that do not regularly undergo inspections to confirm that their configuration is consistent with the plant licensing basis. This screen removed Seismic Category I Structures, Containment Penetrations, Seismic Category I Piping Systems, cable/conduit raceways and HVAC ductwork from consideration for inclusion in SWEL 1.Limerick Generating Station Unit 1 4-1 MPR-3796, Revision 1 Correspondence No.: RS-12-171

4.2.3 Screen

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

1. Reactor Reactivity Control 2. Reactor Coolant Pressure Control 3. Reactor Coolant Inventory Control 4. Decay Heat Removal 5. Containment Function The first four functions are associated with bringing the reactor to a safe shutdown condition.

The fifth function is associated with maintaining containment integrity.

As described in Reference 3, the safety function for each item on the SPCL was identified.

Items on SWEL 1 which perform a specific safety function(s) are considered frontline systems. Items with a safety function described in the SPCL as 'Auxiliary

&Support,'

'Electrical Systems,'

or 'Racks & Panels' are considered either a frontline or support system.4.2.4 Screen #4 -Sample Considerations The items selected from the Base List SPCL for inclusion in SWEL 1 are shown in Tables B-1 through B-3 of this report. As described in Reference 1, Screen #4 is intended to result in a SWEL 1 that sufficiently represents a broad population of plant Seismic Category I equipment and systems to meet the objectives of the NRC 50.54(f)Letter. The following attributes were considered in selecting items from the SPCL for inclusion in SWEL 1: 1. A variety of types of systems The equipment included on SWEL 1 is a representative sample of several systems that perform one or multiple safety functions.

Further, the systems represented include both frontline and support systems as listed in Reference 1 Appendix E: Systems to Support Safety Function(s).

Examples include Emergency Diesel Generators and related systems, Emergency Core Cooling systems (Residual Heat Removal, Reactor Core Isolation Cooling, Core Spray, High Pressure Coolant Injection), power systems (125 VDC, 120 VAC, 480 VAC), and Ultimate Heat Sink (Spray Pond). Note, however, that the Reference 1 Appendix E table of generic BWR safety function systems includes some systems that are not applicable for Limerick Unit 1 because the IPEEE SPCL was not required to include all potential shutdown paths, and some systems, e.g., Isolation Condenser, do not exist at Limerick.2. Major new and replacement equipment The equipment included on SWEL 1 includes some items that have been modified or replaced over the past several years. Each item on SWEL 1 that is new or Limerick Generating Station Unit 1 4-2 MPR-3796, Revision 1 Correspondence No.: RS-12-171 replaced is identified.

Due to the plant vintage, Limerick Unit 1 has not made significant modifications to Seismic Category I equipment.

Accordingly, there is not a large number of new and replacement components.

3. A variety of types of equipment The equipment class is identified for each item on SWEL 1. The equipment included on SWEL 1 is a representative sample from each of the classes of IPEEE equipment used in the Base List, which are based on the equipment classes from EPRI NP-6041-SL "A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1)" (Reference 4). The IPEEE classes used in the Base List can be correlated to the classes of equipment cited in Reference 1, Appendix B. Table 4-1 at the end of this section shows the correlation between the two equipment classification systems. As shown in Table 4-1, at least one piece of equipment from each IPEEE class is included on SWEL 1, except for Class 11, "Motor Generators." No Seismic Category I motor generators were included in the IPEEE SPCL, and none have been identified that support the five Safety Functions included in this project.4. A variety of environments The location for each item is identified on SWEL 1. The equipment included on SWEL 1 is a representative sample from a variety of environments (locations) in the station. These environments include the Spray Pond Pump House (common to both units), Diesel Oil Storage Tank Underground Structure, Reactor Building, Control Structure and Drywell.5. Equipment enhanced due to vulnerabilities identified during the IPEEE program As discussed in Section 7 of this report, no IPEEE seismic-related plant improvements were implemented, or were committed to be implemented, for Limerick Unit 1.6. Contribution to risk In selecting items for SWEL 1 that met the attributes above, some items with similar attributes were selected based on their higher risk-significance.

To determine the relative risk-significance, the Risk Achievement Worth (RAW) and Fussell-Vesely (F-V) importance for a Loss of Off-Site Power (LOOP) scenario, Reference 20, from the internal plant PRA were used. The LOOP scenario from the internal plant PRA includes those pieces of equipment and events that result in either a F-V importance greater than 1 E-3 or a RAW greater than 2.0. Additionally, the list of risk-significant components for the LOOP PRA, Reference 20, were compared with the draft SWEL 1 to confirm that a reasonable sample of risk-significant components (relevant for a seismic event) were included on SWEL 1.In accordance with Reference 1, components in lower dose areas were selected for the walkdown sample instead of the same component in a different train, but located in a higher dose area.Limerick Generating Station Unit 1 4-3 MPR-3796, Revision 1 Correspondence No.: RS-12-171 Table 4-1. Base List IPEEE Classes vs. EPRI Seismic Walkdown Guidance Equipment Classes Total U1 and U0 Base List IPEEE EPRI Seismic S Ltem per Equipment Class Name Equipment Walkdown EPRI G e Class Guidance Class Class Class Other; Not Specifically Identified 0 0 2 Motor Control Centers 1 1 7 Low Voltage Switchgears 1 2 2 Medium Voltage Switchgears 1 3 1 Transformers 2 4 4 Horizontal Pumps 3 5 3 Vertical Pumps 4 6 5 Fluid (Air/Hyd.)

Operated Valves 5 7 9 Motor Operated Valves 6 8 7 Solenoid Operated Valves 7 8 1 Fans 8 9 3 Air Handlers 8 10 7 Chillers 9 11 1 Air Compressors 10 12 1 Motor Generators 11 13 0 Distribution Panels 12 14 3 Battery and Racks 13 15 2 Battery Chargers and Inverters 14 16 2 Engine Generators 15 17 1 Instrument on Racks 16 18 5 Local Instrument (not on rack) 17 18 9 Temperature Sensors 17 19 2 Control Panels and Cabinets 18 20 15 Vertical Tanks or Heat Exchangers 19 21 5 Horizontal Tanks or Heat 20 21 5 Exchangers Total: 102 Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 4-4 4.3 SWEL 2- SPENT FUEL POOL RELATED ITEMS In accordance with Reference 1, four screens are used to select the SSCs to be included on the second Seismic Walkdown Equipment List (SWEL 2), as described in the following sections.4.3.1 Screen #1 -Seismic Category I Only Seismic Category I SSCs, or SSCs that could result in rapid drain-down of the SFP (see Screen #4 below), are to be considered for inclusion in SWEL 2. As described in Reference 1, the adequacy of SFP structures is assessed by analysis and is not included in the scope of these walkdowns.

The review of the design and licensing basis documentation for the SFP identified no Seismic Category I equipment for Limerick Unit 1, except for the Residual Heat Removal (RHR) cross-tie, Emergency Service Water (ESW) make-up supply line, and the Spent Fuel Pool Skimmer Tank. Considerations for these components are discussed below.1. RHR Cross-Tie The RHR cross-tie is separated from the Fuel Pool Cooling and Clean-up (FPCC)System via valves 051-1007 and 051-1023 per References 6 through 9. Valves 051-1007 and 051-1023 are manual valves which are line mounted in Seismic Category I piping. Additionally, the interconnecting piping between the RHR system and FPCC system is provided via one of two spool pieces: either one with blind flanges for normal operation, or one open spool piece for when the cross-tie is required (Reference 2, Section 9.1.3.2.3).

2. ESW Make-Up Supply Line The ESW make-up supply line is separated from the FPCC System via valve 053-1093.

Per Reference 6, this is a manual valve located in Seismic Category I piping.3. Spent Fuel Pool Skimmer Tanks The Spent Fuel Pool Skimmer Tanks are located in 24 ft deep, narrow pits between the reactor cavity and the spent fuel pool on the 352 ft elevation (References 10, 11, 12). The skimmer tanks are 6 ft in diameter, and the clearance around each tank varies between one and three feet. According to Limerick Station personnel, these tanks are in a high radiation field and are not accessible during normal operation or during RFOs.4.3.2 Screen #2 -Equipment or Systems This screen considers only those items from Screen #1 that are appropriate for an equipment walkdown process. Specifically, 1. Manual Valves and Spool Pieces--These components are inherently rugged, do not have active safety functions, and are included within their safety-related, ASME Code piping systems.Limerick Generating Station Unit 1 4-5 MPR-3796, Revision 1 Correspondence No.: RS-12-171

2. SFP Skimmer Tanks--These tanks are in an extremely high radiation field, and the only way to view the anchorage of the tanks would be with a remote camera due to physical constraints of the tank location.

Even if a remote, camera-based inspection were performed, significant dose would be involved in getting access for the camera.Therefore, no Seismic Category I items are included in SWEL 2.4.3.3 Screen #3- Sample Considerations Sample considerations do not apply because no Seismic Category I items were selected in Screen #2.4.3.4 Screen #4- Rapid Drain-Down This screen identifies items that could allow the spent fuel pool to drain rapidly. Rapid drain-down is defined as lowering of the water level to the top of the fuel assemblies within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the earthquake.

Consistent with Reference 1, the scope of items included in this screen is limited to the hydraulic lines connected to the SFP and the equipment connected to those lines. For the purposes of this program, the SFP gates are considered to be installed and the SFP cooling system is in its normal alignment for power operations.

The SFP gates are passive devices that are integral to the SFP. As such, they are considered capable of withstanding a design basis earthquake and do not allow for a rapid drain-down of the SFP.Based on review of the Limerick Unit 1 SFP design information, the following penetrations were identified:

Skimmer surge tank intakes to the Spent Fuel Pool Cooling System are less than 2 feet below the normal surface level of the SFP (Reference 10).* RHR return line penetrations are less than 4 feet below the normal surface level of the SFP (Reference 2, Section 9.1.3.3, and Reference 12).FPCC System Return line penetrations are less than 2 feet below the normal surface level of the SFP (Reference 12).There is approximately 23 feet of water above the fuel during normal operation (Reference 2, Section 9.1.2.2.2.1), and a minimum of 19 feet of water between the top of the fuel and the penetrations.

Therefore, there is no penetration within 10 ft above the top of the SFP fuel assemblies, and consistent with Reference 1, a rapid drain-down evaluation is not required.In addition to penetration locations, the possibility of siphoning through piping that runs down into the SFP below the water level was evaluated.

The FPCC return lines are non-safety related piping that enter the SFP at an elevation of 351'. After entering the SFP, both FPCC return lines run vertically, to an elevation of 328'-5.875", where the pipe ends (Reference 15). During normal operation, and a SFP level of approximately 38', the terminations of these pipes are within 10 feet of the top of the fuel. To prevent lowering of the SFP resulting from siphoning, two 1-1/4 inch anti-siphoning holes have been drilled in the piping at an elevation of 349'-2" (Reference 15), which is not within 10 feet Limerick Generating Station Unit 1 4-6 MPR-3796, Revision 1 Correspondence No.: RS-12-171 of the top of the fuel. As a result, no siphoning effect would occur that could cause rapid drain down of the SFP and no items need to be included in SWEL 2 for Limerick Unit 1.4.4 COMPOSITE SWEL As described in Section 4.1 above, the final Seismic Walkdown Equipment List (SWEL)for Limerick Unit 1 is the combined SWEL 1 and SWEL 2. For Limerick Unit 1, there are no items of equipment in SWEL 2, so the composite SWEL is the same as SWEL 1.Appendix B includes the composite SWEL.Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 4-7 5 Seismic Walkdowns and Area Walk-Bys 5.1 OVERVIEW Seismic Walkdowns and Area Walk-Bys were conducted by 2-person teams of trained Seismic Walkdown Engineers, in accordance with the EPRI Seismic Walkdown Guidance (Reference 1). The Seismic Walkdowns and Area Walk-Bys are discussed in more detail in the following sections.5.2 SEISMIC WALKDOWNS An overview of the Seismic Walkdowns is shown on the Limerick Unit 1 SWEL and Unit 0 (common equipment with Unit 2) SWEL in Appendix B, Tables B-1 and B-2, respectively.

A Seismic Walkdown Checklist (SWC) from Appendix C of Reference 1 was completed for each item on the SWEL, except for the deferred items identified at the end of the SWEL. Additionally, photos are included with each SWC to provide a visual record of the item and any significant comment noted on the SWC. Drawings and other plant design documents are cited in most of the SWCs, but they are not included with the SWCs because they are readily available in the plant's electronic document management system. Seismic Walkdowns were completed for 77 of the 87 items on the Limerick Unit 1 SWEL, plus all 15 items on the Unit 0 (common) SWEL, for a total of 92 items, not including the 10 deferred.5.2.1 Anchorage Configuration Confirmation As required by Reference 1 (page 4-3), the anchorage for at least 50% of the items were confirmed to be consistent with design drawings.

The second to last column of Tables C-1 and C-2 in Appendix C document the anchorage confirmation.

Specifically, items that are line-mounted (and therefore do not count in the anchorage confirmation total)are marked "N/A," items that were confirmed to be consistent with design drawings are marked "Y," and items for which anchorage drawings were not identified are marked"N.". See Table 5-1 below for the accounting of the 50% anchorage configuration confirmations, and the individual SWC forms in Appendix C for the specific drawings used in each confirmation.

Limerick Generating Station Unit 1 5-1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 Table 5-1. Anchorage Configuration Confirmation Unit I or Unit 0 No. of SWEL NIA Items Required to Items Items Confirm?(Common)? (A) (B) (A-B)I2 Confirmed 1 77 14 32 39 0 15 6 5 6 Totals 92 20 37 45 5.2.2 Issue Identification None of the anomalies or issues identified by the SWEs during the equipment walkdowns were ultimately judged to be "Potentially Adverse Seismic Conditions" because in all cases it was concluded the anomaly or issue would not prevent the equipment from performing its safety-related function.

Additionally, based on the IRs for each issue, all equipment affected by the as-found condition was determined to be functional.

Table 5-2 provides a summary of the issues identified during the Seismic Walkdowns as provided in Reference 19.Table 5-2. Issues Identified during Seismic Walkdowns Actions Item ID Description of Issue AComplete Request ID YIN(Notes 1, 2)1BS252-1 A loose bolt was identified in a nitrogen bottle IR 01394912 Yes retaining bar. The retaining bar bolts are supposed to be snug tight.PSL-012- The pressure switch was supposed to be installed IR 01395230 No 102A with 3 bolts. However, two of the three bolts were not engaged with the pressure switch.1AV512 Two of the 16 bolts connecting the air intake funnel IR 01395457 No for the fan were not engaged.10X109 An issue with the grout pad of a transformer was IR 01396431 No identified.

Several vertical cracks were identified and a small amount of grout was missing around the back left anchor bolt.00B519 A gap of approximately 1/8 to 1/4 inch was identified IR 01395937 Yes in the base plate for a lateral brace for an MCC.10C027 Lead shielding inside of 24" sliding exclusion zone IR 01416573 Yes not in compliance with NE-048, Rev. 2.Notes: 1.2."Yes" indicates that corrective actions resulting from the issue are complete."No" indicates that corrective actions resulting from the issue are NOT complete.

Actions are tracked by the IR number in the station Corrective Action Program.Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 5-2 5.3 AREA WALK-BYS In accordance with Reference 1, Area Walk-bys were performed for each room or area which included one or more items on the SWEL. The last column of Tables C-1 and C-2 show the number of unique Area Walk-By Checklists (AWCs) completed during the walkdowns for Limerick Unit 1 and Unit 0 (common).

AWC identifiers with asterisks

(*)indicate the second or subsequent SWEL item included with a specific Area Walk-By.All completed AWCs are included in Appendix D. Photos are not included with the AWC forms because they are part of the SWC package of the identified equipment item. A total of 43 AWCs were completed for Unit 1, plus 9 for Unit 0 (common).None of the anomalies or issues identified by the SWEs during the Area Walk-Bys were judged to be "Potentially Adverse Seismic Conditions" because in all cases the anomaly or issue would not prevent surrounding equipment from performing its safety-related function.

Additionally, based on the IRs for each issue, all equipment affected by the as-is condition was determined to be operable.Table 5-3 at the end of this section provides a summary of the issues identified in the Area Walk-Bys as provided in Reference 19.Table 5-3. Issues Identified during Area Walk-Bys Actions Item Action cons Description of Issue Complete IDIArea Request ID y/N(Notes 1, 2)AWC-U1- A ladder was identified leaning against a cart, IR 01395707 Yes 01 unsecured.

AWC-U1- Two issues related to ladder storage were IR 01395494 Yes 18 and identified.

The first involved an unsecured ladder AWC-U1-7 that was stored on its side in the HPCI room. The second involved unsecured ladders stored on top of a scaffold storage rack.AWC-UO- A terminal box was identified with only one bolt IR 01395982 No 02 securing it door when there were supposed to be three. Further the single bolt was loose.AWC-U1- A small gap was identified in a nitrogen bottle IR 01397658 No 36 support bar. The support bars are supposed to be snug tight.Notes: 1. "Yes" indicates that corrective actions resulting from the issue are complete.2. "No" indicates that corrective actions resulting from the issue are NOT complete.

Actions are tracked by the IR number in the station Corrective Action Program.Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 5-3 6 Licensing Basis Evaluations As noted in Sections 5.2.2 and 5.3, the issues identified during the Seismic Walkdowns and Area Walk-Bys were not determined to be "Potentially Adverse Seismic Conditions" because in all cases the anomaly or issue would not prevent the equipment from performing its safety-related function.

Therefore, no formal Licensing Basis Evaluations were necessary and none were performed.

Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 6-1 7 IPEEE Vulnerabilities Resolution Report The Individual Plant Examination of External Events (IPEEE) report for Limerick Generating Station (Reference

13) and the NRC Safety Evaluation on the IPEEE report (Reference 14), do not identify any seismic vulnerabilities.

This was attributed to the conservative nature of the original design, which is a reflection of the relatively new vintage of the plant. Therefore, no seismic-related plant improvements were implemented, or were committed to be implemented, for Limerick Unit 1.Although there were no equipment-related modifications, the IPEEE report (Reference

13) did commit to improve the seismic housekeeping of the plant. A station housekeeping procedure (Reference

17) and a guidance procedure for storage and housekeeping (Reference

18) are both active to ensure good housekeeping practices at the site.As noted above, there are no Design Basis vulnerabilities identified for Limerick Generating Station Unit 1 and Unit 0 (common).Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 7-1 8 Peer Review 8.1 OVERVIEW In accordance with the EPRI Seismic Walkdown Guidance (Reference 1), a peer review of this project was performed during the preparation of the Seismic Walkdown Equipment List (SWEL), during implementation of the seismic walkdowns and area walk-bys, and following completion of the issue resolutions.

Specifically, the peer review addresses the following activities:

Review of the selection of the structures, systems, and components, (SSCs)that are included in the Seismic Walkdown Equipment List (SWEL),* Review of a sample of the checklists prepared for the Seismic Walkdowns

&Walk-Bys,* Review of any licensing basis evaluations,* Review of the decisions for entering the potentially adverse conditions in to the plant's Corrective Action Program (CAP), and* Review of the final submittal report.The complete Peer Review Report is included in Appendix F.8.2 REVIEW OF SWEL The peer review checklist for SWEL is included as an attachment to the Peer Review Report. This checklist was used to ensure that the SWEL 1, SWEL 2, and composite final SWEL meet the criteria of Reference

1. All peer review comments on the SWEL were resolved.8.3 REVIEW OF SAMPLE SEISMIC WALKDOWN AND AREA WALK-BY CHECKLISTS Approximately 28% of the Seismic Walkdown packages, i.e., SWC forms, photographs, and drawings (where applicable) were reviewed by the peer review team. Additionally, interviews were conducted with both teams of Seismic Walkdown Engineers to ensure that the seismic walkdowns and area walk-bys were performed in accordance with Reference 1.The peer review team recommended that some clarifications be added to the SWC and AWC forms reviewed.

Additionally, one technical question was posed about whether a Limerick Generating Station Unit 1 8-1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 wheeled cart with lead shielding blankets would slide or tip over during a seismic event.This issue was addressed in IR 01416573 and has been closed as shown in Table 5-2.8.4 REVIEW OF LICENSING BASIS EVALUATIONS As discussed in Sections 5 and 6 of this report, the issues identified during the seismic walkdowns and area walk-bys did not threaten the ability of Seismic Category I equipment for perform its safety functions.

The specific items that have been entered in the Limerick Corrective Action Program (CAP) were reviewed, and no concerns with the assessments or proposed resolutions were identified.

8.5 REVIEW

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

Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 8-2 9 References Reference drawings related to the walkdown of SWEL items are documented on the Seismic Walkdown Checklists (SWCs) in Appendix C, and if applicable, on the Area Walk-By Checklists (AWCs) in Appendix D.1. EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012.2. Limerick Generating Station Updated Final Safety Analysis Report (UFSAR), Revision 16.3. PECO Document No. N-OOE-1 17-00010, Success Path Components List (SPCL) for Limerick Generating Station Unit 1 and Common, Revision 0.4. EPRI NP-6041-SL, A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1), dated August 1991.5. L-S-52, Spent Fuel Pool Cooling and Cleanup System, Revision 4.6. Drawing M-0053, Sheet 1, P&ID Fuel Pool Cooling & Cleanup (Unit 1 & Common), Revision 48.7. Drawing M-0053, Sheet 2, P&ID Fuel Pool Cooling & Cleanup (Unit 1), Revision 48.8. Drawing M-0051, Sheet 1, P&ID Residual Heat Removal (Unit 1), Revision 65.9. Drawing M-0051, Sheet 3, P&ID Residual Heat Removal (Unit 1), Revision 67.10. Drawing No. C-0246, Sheet 1, Reactor Building Units 1 & 2 Pool Liners and Accessories Surge Tank Section & Details, Revision 13.11. Drawing No. M-01 22, Equipment Location Reactor Enclosure Unit 1 Plan At EL.352'-O", Revision 17.12. Drawing No. C-0234, Reactor Building Unit 1 Pool Liners and Accessories Spent Fuel Pool Wall Liner Elevations, Revision 22.13. PECO Energy Company, Limerick Generating Station Units 1 and 2, Individual Plant Examination for External Events, June 1995.14. NRC Letter (B. C. Buckley) to PECO (J. A. Hutton), Review of Individual Plant Examination of External Events (IPEEE) Submittal, Limerick Generating Station, Units 1 and 2, (TAC NOS. M83636 AND M83637), dated February 23, 2000.Limerick Generating Station Unit 1 9-1 MPR-3796, Revision 1 Correspondence No.: RS-12-171

15. Drawing HCC-1 01-6, Isometric

-Reactor BLDG. Fuel Pool Cooling, Clean-up &Filter Demin. -Unit #1, Revision 20.16. Facility Operating License No. NPF-39.17. Procedure MA-AA-716-026, Station Housekeeping/Material Condition Program, Revision 10.18. Procedure MA-LG-716-026-1001, Additional Guidance for In-Plant/Yard Storage and Housekeeping at Limerick, Revision 15.19. Email from R. Wehrman (Exelon) to C. Schlaseman (MPR), Subj: Limerick Walkdown IRs, 9/28/12, 11:34 AM.20. Limerick Generating Station Document No. LG-MISC-008, Limerick Risk Importance Listings to Support Development of the Seismic Walkdown Equipment List (SWEL), Revision 0.Limerick Generating Station Unit 1 9-2 MPR-3796, Revision 1 Correspondence No.: RS-12-171 A Project Personnel Resumes and SWE Certificates Resumes and SWE certificates are included for the team of engineers, followed by the resume for the Peer Review Team Lead, Patrick Butler.Thomas King Craig Swanner Mojtaba Oghbaei James Wiggin Caroline Schlaseman Patrick Butler A-2 A-5 A-8 A-11 A-14 A-17 Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 A-1 UMPR ASSOCIATES INC.EN G I NE E R S Thomas C. King EXPERIENCE

SUMMARY

2002 -present MPR Associates, Inc.Since joining MPR Associates, Mr. King has been involved in a variety of engineering tasks related to Navy Shipboard Systems, Damage Control, and power plant systems. Examples of his work include: ACCOMPLISHMENTS

SUMMARY

Power Plants Performed plant walk-downs and analysis for structural items, flooding concerns, and plant equipment upgrades.Site Support Oversaw schedule, safety, and environmental issues during a plant modification, including the addition of a storm water detention basin.Commercial Grade Dedication Performed project manager, cognizant engineer, and project quality engineer duties for commercial graded dedication of various electrical and I&C components for nuclear plant and testing, inspection, and calibration services.Project Quality Engineer Performed quality assurance duties for various nuclear industry projects.

Projects include commercial graded dedication of electrical equipment, detailed analyses projects and reports, as well as audits of commercial suppliers.

Fire Hazard I Hazard Assessment Prepared preliminary fire hazard assessments for the next generation destroyers and amphibious transport ships.Alkali-Silica Reactions (ASR)Performed duties as a project quality engineer and Level I mechanical inspector for anchor pullout and breakout testing to support short-term assessment of degraded concrete exhibiting ASR degradation.

Activities witnessed include calibration of M&TE and anchor pullout and breakout testing.ASME Code Analysis and Design Prepared and checked hydraulic calculations for nuclear steam and service water piping systems and ASME design calculations for both Section III and VIII vessels.Fire Protection Design and System Review Performed review of fire protection system designs for support ship classes including TAO and AS.CVN78 Program Provided independent review and technical oversight of AFFF, Firemain, and the Machinery Control Systems for CVN 78, including piping, power, and controls.

Includes providing experience learned from previous jobs to shipyard personnel.

Chilled Water Automation System & Make-up Water Controller Lead Test Engineer Prepared and executed the Verification and Validation Plan and test Procedures for the DDG 51 Chilled Water Automation System and Make-up Water Controller, including testing at the Land Based Demonstrator in Philadelphia.

The testing validated the computer software / valve firmware, and the interaction with the mechanical equipment.

Solenoid operated pilot valve replacement Developed and validated design requirements for the replacement of solenoid operated pilot valves for Navy use. The requirements included mechanical, system interface, and I&C requirements for integration with the existing piping and I&C infrastructure aboard the ship.EDUCATION Pennsylvania State University at Erie, The Behrend College, B.S. Mechanical Engineering, 2002 University of Maryland, College Park, M. E. Mechanical Engineering, 2007.Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.orrP.nnndPnr.

PNn* RR-19-171 A-2 Thomas C. King Page 2 QUALIFICATIONS AND TRAINING Seismic Qualification Utility Group (SQUG) course for Seismic Capability Engineers, as defined by the NRC's Unresolved Safety Issue (USI) A-46 Program, 2012 EPRI Seismic Walkdown Engineer (SWE) training, 2012 Level I Inspector (Mechanical, I&C, Electrical), 2011 Lead Auditor, 2009 MEMBERSHIPS Member, American Society of Mechanical Engineers (ASME)Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrmnnnrlPnr.P.

Nn ' RR-17-171 A-3 I ELECTRIC POWER RESEARCH INSTITUTE Certificate of Completion Thomas King Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns July 3, 2012 Date Caroline S. Schlaseman, P.E.Instructor MPR-3796, Revision 1 Correspondence No.: RS-12-171 MMPR ASSOCIATES INC.EN GIN EERS Craig B. Swanner, P.E.EXPERIENCE

SUMMARY

1994 -present MPR Associates, Inc.Mr. Swanner joined MPR in 1994. He has worked extensively in project engineering, licensing, design of BWR reactor internals repairs, design and structural analyses of ASME Boiler and Pressure Vessel Code components, instrumentation

& control and motor-operated valves.ACCOMPLISHMENTS

SUMMARY

Seismic Qualification Managed the structural and seismic design of replacement electrical cabinets for safety related emergency diesel generators at multiple units and multiple sites. Seismic qualification included dynamic time history evaluation of cabinet response as well as seismic shake table testing.Seismic qualification satisfied requirements of IEEE Std 344.BWR Core Shroud Repair Design Designed a repair to structurally replace all circumferential welds in five BWR core shrouds.Performed design analyses to demonstrate the adequacy of the repair. Specific analyses performed included:

repair assembly ASME Code Section III stress analysis, static load definition, evaluation of the effects of flow-induced vibration and shroud vibration on the repair, assessment of the effects of the repair on core downcomer flow characteristics, and evaluation of repair assembly thermal expansion.

Project Engineering Provided project engineering support to various nuclear utilities on multi-million dollar, emergent critical path tasks. Responsibilities included resolution of emergent issues, supervision of procurement and receipt of safety-related components, interface with the design organization, plant management, work planning and the field. Experiences provided first hand, working level knowledge of practical application of all aspects of 1 OCFR50 Appendix B and how it is applied at different utilities.

BWR In-Vessel Piping Repairs Designed first-of-a-kind repair clamps to structurally replace cracked welds in a BWR in-vessel feedwater sparger and a core spray line.Designed and managed fabrication of the tooling to remotely install feedwater sparger repair clamps from refueling bridge above vessel.Design Basis Information Review Provided management direction for a program to demonstrate the adequacy and availability of design basis information.

Assisted preparation of the utility response to the NRC's 10 CFR 50.54(f)Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrP'qnnnriP'ni Nn -R.-12-171 request. Prepared the engineering self-assessment report, which provided the supporting information for the conclusions drawn in the response.

The program included vertical slice reviews of seven risk significant systems, a comprehensive review of engineering programs including Individual Plant Examination of External Events (IPEEE), Environmental Qualification, and Fire Protection, a UFSAR review, and a Technical Specification review. The reviews assessed the adequacy of the configuration control program in maintaining the design and licensing basis documents in conformance with operations, maintenance, and surveillance procedures and the physical plant configuration.

Evaluated the discrepancies identified in the reviews for overall areas of weakness and recommended appropriate corrective actions.ABWR Licensing Served as the Engineering Procurement Construction (EPC) Team Licensing Lead for Digital Instrumentation and Control (DI&C) and Human Factors Engineering (HFE) for the first domestic ABWR construction project. Supported COLA Revisions, responses to USNRC Requests for Additional Information, and USNRC Inspections.

Provided leadership in strategy development for the closure process of Design Acceptance Criteria (DAC)-related Inspection Test Analyses Acceptance Criteria (ITAAC).Pressure Locking and Thermal Binding Analyzed valves at several nuclear units to determine the bonnet pressurization due to valve heatup. The model utilized accounts for expansion of the bonnet with pressure and temperature.

These analyses formed part of the utility's formal submittal in response to NRC Generic Letter 95-07.A-5 Craig B. Swanner Page 2 Pump Modification for Debris Laden Fluid Designed pump modification to prevent plugging of hydrostatic bearing during post accident operation when suction is taken from containment sump.Developed and designed mockups of pump close clearances to be used in wear testing with debris laden process fluid. Managed fabrication of mockups and pump modification.

Supervised safety-related wear testing and provided field engineering support and inspection activities during installation of design in safety-related pump.BWR Safety Relief Discharge Vacuum Breaker Design Modification Developed modification to repair failed hinge arm of swing check valve installed as a vacuum breaker in the safety valve relief discharge lines at a BWR.Performed root cause evaluation to identify magnitude of pressure transient resulting in failure.Managed project to develop modification to prevent damage to hinge arm. The project included development of a design change package complete with design drawings, supporting analyses, and installation instructions.

The modification was successfully installed on twelve vacuum breakers during a refueling outage.Managed MOV Calculation Upgrade Effort Implemented a program to upgrade calculations for 112 MOVs within the scope of Generic Letter 89-10 at one nuclear unit. Managed entire project to meet critical path outage window. Ensured input parameters from other organizations were in place to minimize the need for revision and field re-work.Recommended modifications to ensure operability of all MOVs after refurbishment.

Calculations include seismic/weak link, evaluation of required thrust using EPRI PPM, DC motor stroke time, and MOV torque and thrust setup using AltraMOV.Final calculations received NRC approval, removing MOVs as an obstacle for restart of the unit.Software Development for Bolted Closures Managed a project to upgrade a computer software package used for the analysis of bolted closures.Identified and implemented the necessary code changes for the upgrade. Developed a software validation plan and supervised the final verification and validation of the software.

Wrote the software users manual.EDUCATION Virginia Tech, B.S. Aerospace Engineering, 1994 Minors in Physics and Mathematics (Summa Cum Laude)REGISTRATION Registered Professional Engineer, Commonwealth of Virginia TRAINING Seismic Capability Engineer, SQUG Training Seismic Walkdown Engineer, EPRI NTTF 2.3 Seismic Walkdown Training Course PUBLICATIONS Knittle, P., Swanner, C., et al. "Modification of BWR Relief Valve Discharge Line Vacuum Breakers to Prevent Damage Due to Cyclic Loading," Proceedings of the Eighth EPRI Valve Technology Symposium.

Electric Power Research Institute, 2001.Limerick Generating Station Unit 1 MPR-3796, Revision 1..nrrPqnnndpnrP.

Nn

R.-12-171 A-6 ELECTRIC POWER E(PI Certificate ELECTRIC POWER RESEARCH INSTITUTE of Con ipletion Craig Swanner Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns July 3, 2012 Date Caroline S. Schlaseman, P.E.Instructor MPR-3796, Revision 1 Correspondence No.: RS-12-171

MPR ASSOCIATES INC.ENGINEERS Mojtaba Oghbaei EXPERIENCE

SUMMARY

January 2006 -Present MPR Associates, Inc.Mr. Oghbaei joined MPR in 2006. He has had significant experience in development of advanced analytic techniques and their application to specific practical problems.

Particular subjects worked on include: two-phase thermal hydraulics; fluid transients in piping systems including waterhammer, two-phase flow, the effect of trapped voids, fluid structure interaction, and analysis of structures subjected to fluid transients.

A large part of the engineering involved computer simulations using numerical methods.Mr. Oghbaei has also significant experience in ASME Code evaluation of pressure vessels and piping systems as well as structural evaluation of components.

The focus has been on evaluating the structural adequacy of components in nuclear applications such as heat exchangers, tanks, strainers, valves, and piping. He has also worked in seismic evaluation of components such as tanks and heat exchangers.

Specific examples of Mr. Oghbaei 's work include: ACCOMPLISHMENTS

SUMMARY

Nuclear Power Plant Transient Analyses Evaluated transient two-phase flow conditions in nuclear power plants. This work included using of transient analysis computer programs for the detailed analysis of power plant components such as heat exchangers, pumps, and associated piping.Column Closure Waterhammer Analyses Performed analyses to simulate column closure waterhammer events in nuclear power plants. These events typically occur after a loss of power to the pumps causes the water in piping systems to drain forming a void. Upon restart, the accelerating water columns cause void condensation and collision between the columns..Simulation of Fast Transients Performed analyses to evaluate fast transients in piping systems that include rapid valve closure/opening, pump start/stop to calculate hydraulic loads on piping.Effect of Entrapped Air on Pumps Startup Analyzed the effect of trapped air upstream of a pump on the startup characteristics of the pump. The analysis involved prediction of the amount of air trapped in the piping upstream of the pump that would be transported to the pump, and its effect on the pump performance based on industry accepted criteria.

Analyses using the technique indicate successful startup of a pump with entrapped air is dependent on piping and pump geometry as well as on the temperature of the water being pumped.Nuclear Power Plant Piping Analyses Analyzed piping systems in nuclear power plants subjected to deadweight, thermal, and seismic loading. Performed piping and support stress analysis to determine support configuration modification required to ensure adequate capacities.

Nuclear Power Plant Containment Analyses Involved in preparation and review of postulated High Energy Line Break (HELB) and Post-LOCA heatup scenarios using GOTHIC software for containment, turbine building, auxiliary building and control room.The analysis results and recommendations were used for Equipment Qualification (EQ) purposes.Analyses of reactor Coolant Pump Seals Performed thermal hydraulic analyses to simulate reactor coolant pump seals. When the cooling water flow to the seals is lost, the hot reactor coolant starts flowing to the seals. The increased temperature can cause the seals to rotate open due to differential thermal expansion.

Since the seals are the primary hydraulic resistance in the system, the seal rotation increases loss of reactor coolant inventory.

ASME B&PV Code Evaluation of Pressure Vessels Performed Section III and Section VIII ASME B&PV Code evaluation of several heat exchangers, tanks, strainers, valves, and piping systems. This includes structural evaluation of pressure boundary and internal components using both hand calculation and finite element evaluations.

Piping Crack Evaluation using Fracture Mechanics Analytical Methods Performed piping crack analyses to determine structural adequacy and provide inputs for leak-before-break (LBB) evaluations for primary and secondary piping systems.Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrPqnnnPnrlP.p Nn' RR-19-171 A-8 Mojtaba Oghbaei Page 2 MOV Analysis for Required Stem Thrust and Weak Link Evaluation Performed required thrust evaluation of MOVs under different system conditions using the EPRI PPM Methodology and reviewed vendor weak link analyses as part of NRC Information Notice 92-18.EDUCATION B.S., M.S. and Ph.D. in Mechanical Engineering.

Rensselaer Polytechnic Institute, Ph.D. in Mechanical Engineering, December 2005.QUALIFICATION AND TRAINING Seismic Qualification Utility Group (SQUG) course for Seismic Capability Engineers, as defined by the NRC's Unresolved Safety Issue (USI) A-46 Program, 2012 EPRI Seismic Walkdown Engineer (SWE) training, 2012 PUBLICATIONS A State-Time Formulation for Dynamic Systems Simulation Using Parallel Computing Resources, Nonlinear Dynamics, 39(3), pp. 305-318, Feb. 2005.Limerick Generating Station Unit 1 MPR-3796, Revision 1 Nn

R;-19-171 A-9 RELECTRIC POWER* II I RESEARCH INSTITUTE Certificate of Completion Mojtaba Oghbaei Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns July 3, 2012 Date Caroline S. Schlaseman, P.E.Instructor

--IIIUr .-1 Ifl .o' Ti" L..- -I n[ --.U MPR-3796, Revision 1 Correspondence No.: RS-12-171 RMPR ASSOCIATES INC.ENGINEER S James N. Wiggin EXPERIENCE

SUMMARY

2006 -2007 2008 -present FEV Engine Technology MPR Associates, Inc.Mr. Wiggin joined MPR Associates in 2008. Previously he performed finite element analyses of power train components for an engine design and development company. Since joining MPR, Mr. Wiggin has developed expertise in the following diverse technical areas: stand-by AC power sources; power plant procedures and system modifications; commercial grade dedication; inspection and procurement of nuclear safety-related equipment; component

& system design basis analysis; balance-of-plant system operations; motor-operated valves; and centrifugal pump operation.

ACCOMPLISHMENTS

SUMMARY

Stand-by AC Power Mr. Wiggin has experience with the following aspects of emergency AC power generation:

engine signature analysis (ESA), root cause investigation, preventive maintenance, condition-based maintenance, ultra-low sulfur diesel (ULSD)effects, fuel economy, power up-rates and regulatory compliance.

Examples of some of these disciplines include: " Performed ESA for several nuclear power industry clients on a variety of diesel engine types. Also taught an ESA course to members of the Korean Electric Power Research Institute." Conducted engine maintenance reviews for nuclear power plants and reviewed EDG mechanical calculations for planned engine power up-rates." Performed past-operability analyses, EDG reliability and vulnerability studies and fuel oil/lube oil compatibility evaluations for nuclear power plants.Design Basis Analysis Mr. Wiggin has evaluated the design basis of balance-of-plant components including valves, pumps, system piping, dampers and doors for possible safety classification upgrades and plant simulator programs.

Reviews involved study of process flow diagrams, P&IDs, logic diagrams, vendor technical manuals and related licensing basis documentation.

He wrote a plant procedure for future component quality reviews/determination.

He has also performed environmental qualification evaluations for component materials within containment for GSI-191 studies and reviewed design basis calculations for seismic adequacy and power up-rates.Equipment Procurement Mr. Wiggin has written and reviewed procurement specifications for nuclear safety-related applications including: " Evaluated EDG replacement engine fuel oil and lube oil consumption and storage requirements and developed portions of a new EDG procurement specification." Performed technical review of procurement specifications for EDG auxiliary components including pumps, tanks, strainers and fill stations." Led procurement effort for safety-related service water strainer backwash pumps.Developed pump procurement specification and collaborated with plant personnel to establish licensing criteria, performance requirements and debris tolerance characteristics.

Coordinated with pump vendors and testing facility for pump delivery and testing schedules." Evaluated potential vendors for current and future technical capability to manufacture a small modular reactor design.Considered nuclear project history, ability to expand current capabilities, market position and personnel qualifications.

Commercial Grade Dedication

& Inspection Mr. Wiggin has completed several commercial grade dedication (CGD) projects and is a certified ANSI Level II Mechanical Inspector.

He led a time-critical CGD effort of a wire replacement order and has inspected various components for CGD efforts, including a large order of high pressure fuel injection lines for replacement and spares on four EDGs. He has developed CGD plans, inspection procedures, test Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrqnnnrlPnr'.

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RR-19-171 A-11 James N. Wiggin Page 2 procedures, acceptance records, inspection records and non-conformance reports.He has been a client representative for factory acceptance testing as well as a manufacturing expediter, ensuring high quality while meeting customer schedule demands.Motor-Operated Valves Mr. Wiggin has performed design-basis valve set-point calculations for safety-related motor-operated valves (MOVs) in critical systems such as safety injection, containment spray and reactor heat removal. He has experience using the EPRI Performance Prediction Methodology (PPM) and plant-specific, proprietary MOV analysis software.He has performed analyses for gate, globe and butterfly valves and evaluated gate valves for pressure-locking and thermal binding effects as well as the newly discovered disc-pinching effect.Power Plant Procedures

& Modifications Mr. Wiggin has written and revised procedures for power plant operations and has experience with design, review, testing and implementation of major plant modification projects.He has written and reviewed calculations and technical reports in support of engineering change (EC) packages and performed technical reviews of ECs for design basis set-point changes, power up-rates, new installations and compensatory measures for regulatory compliance.

Life Cycle Management Mr. Wiggin has performed reviews of individual components (reactor coolant pump bonnet bolts)and complete systems (emergency power) for the purpose of evaluating ability to meet the licensed design life and for license extension analyses.These reviews included analyzing current component conditions, maintenance practices, management commitments to plant sustainability and ease of procedure use. Provided recommendations for future maintenance based on industry and regulatory guidance.EDUCATION Pennsylvania State University, B.S. in Aerospace Engineering, 2005 Professional Engineer license granted 6/2012 QUALFICATION AND TRAINING Seismic Qualification Utility Group (SQUG) course for Seismic Capability Engineers, as defined by the NRC's Unresolved Safety Issue (USI) A-46 Program, 2012 EPRI Seismic Walkdown Engineer (SWE) training, 2012 PUBLICATIONS Humphrey, Amie N. et al., "Debris Laden Backwash Pump Performance Evaluation," Proceedings of the ASME 2011 Power Conference, Denver, Colorado, July 12-14, 2011, ASME.Limerick Generating Station Unit 1 MPR-3796, Revision 1.nrrP'qnnndrnr.P Nn

RR-19-171 A-12 1 I 1 1 POWER Erma I RESEARCH INSTITUTE Certificate of Completion James Wiggin Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns July 3, 2012 Date Caroline S. Schlaseman, P.E.Instructor MPR-3796, Revision 1 Correspondence No.: RS-12-171 WMPR ASSOCIATES INC.ENGINEERS Caroline S. Schlaseman, P.E.EXPERIENCE

SUMMARY

Since joining MPR in 1981, Ms. Schlaseman has performed a broad spectrum of technical work, including work in her primary area of expertise, structural mechanics.

This work includes supervisory and management responsibilities in several areas, including projects for existing U.S. commercial and DOE nuclear plants, new-build U.S. nuclear power plants, fossil-fueled power plants, and non-power generation clients.ACCOMPLISHMENTS

SUMMARY

Project Management Managed several conceptual design projects for a 2 unit BWR, including alternatives analysis and conceptual design for upgrading the feedwater heater level controls, modifying the turbine supervisory instrumentation, and resolving a dozen operational problems with the condensate demineralizer system.Managed a task to redesign a BWR drywell penetration to ASME Code Class MC requirements, including Code Design Report and other supporting calculations.

The task was performed during a four-day critical path period with no advance planning.Managed test program to re-qualify packages used to transport radioactive sources under the rules for normal and accident conditions specified in 1 0CFR71 for Type B Transport packages.

The project included preparation of initial package assessments to select impact test orientations predicted to inflict the greatest damage, test plan preparation and response to NRC questions, test report and final Safety Analysis Report preparation.

Managed project to confirm that small-bore piping in an older BWR meets its code requirements for deadweight, seismic and thermal loadings.Developed screening criteria and performed walkdowns of samples of piping and tubing in nine safety-related system, including piping inside the drywell. Supervised finite element piping analyses of lines that did not meet screening criteria.Managed tasks to modify the design and perform structural code evaluations of two valve types used in shipboard nuclear plant applications.

Coordinated and participated in seismic adequacy walkdowns and evaluations of approximately 600 equipment items required for safe shutdown of a single-unit BWR. Coordination of these walkdowns included scheduling, tracking, and interfacing with outage management, health physics, craft support, QA, and the client's project engineer.Responsible for seismic and thermal cycling test program to qualify three sizes of solenoid operated valves intended for nuclear service.U.S. New-Build Nuclear Plants Supported licensing of a 2-unit ABWR in the U.S.by writing portions of a significant revision to a Combined License (COL) application, responding to U.S. NRC Requests for Additional Information (RAIs), meeting with the NRC to resolve technical questions, and making presentations to the NRC's Advisory Committee on Reactor Safeguards (ACRS).Member of NEI Construction Inspection Program (CIP) ITAAC Task Force, which meets periodically with NRC to establish processes for addressing ITAAC provisions in 10 CFR Part 52. Contributing author for NEI 08-01.Structural Design and Analysis Performed ASME Code Case evaluations, including potential flaw growth due to fatigue and evaluation of weld shrinkage, to support a weld overlay repairs for BWR recirc piping and a heat exchanger nozzle. Prepared report providing the technical basis for the submittal to the NRC.Analyzed stresses in piping subjected to hydrodynamic loadings generated within a BWR toroidal suppression chamber during a postulated LOCA. Evaluated impact of replacement in-torus strainer volume and mass on piping, nozzle and transition stresses.Performed thermal and stress analysis of a PWR primary system bolted-flange connection to evaluate the leak tightness of existing and proposed designs.Performed leak-before-break failure analysis for selected piping systems under normal, seismic, and accident loading conditions.

Designed supports and provided field support for installation of a new high temperature and pressure tubing system during a forced outage at a BWR.Installation of the new tubing system was required before the BWR could be brought back on line.Designed hardware modifications to piping branch connections and pipe supports, in accordance with ASME and AISC Code criteria.Limerick Generating Station Unit 1 MPR-3796, Revision 1 Nn

RRI19-171 A-14 Caroline S. Schlaseman Page 2 Nuclear Plant Design Basis Prepared the topical design criteria document for seismic classification of structures, systems, and components for an older BWR's design basis reconstitution program. Prepared detailed scope/plan document for nonseismic external events (e.g., flooding) design criteria document, and independently reviewed this document prepared by others. Evaluated current design requirements for seismic, flooding, tornado and other extreme external events, and the effect of these requirements on older, operating nuclear units. Participated in an NRC safety system functional inspection audit of a BWR, including preparation of calculations to document the design basis of audited systems. Researched and documented an older plant's sources, indexes, and methodologies for retrieval of design basis information by engineers.

License Renewal and Material Condition Assessments Developed the approach and managed a comprehensive aging management assessment of an older DOE test reactor.Assessed the adequacy of a PWR's existing programs to manage the effects of potential age-related degradation mechanisms on component supports within the scope of license renewal.Performed inspections and evaluations of the material condition of auxiliary equipment in fossil-fueled generating stations as part of material condition/life extension studies.BWR Suppression Pool Suction Strainers Performed the evaluation of options for resolving NRC Bulletin 96-03 issues for an operating BWR, including scoping calculations for debris source term and debris transport, analyses to evaluate the impact of the postulated debris on the ECC system components entering the existing piping at the torus suction, scoping stress analyses for possible new suction strainer impact on penetration locations, in accordance with Mark I criteria, and cost benefit evaluations for each of the candidate options.Performed evaluations for another operating plant to determine the maximum size and weight replacement strainers that could be installed without exceeding Mark I stress criteria for torus nozzle penetrations, transitions, and attached piping. Strainers with significantly more surface area were successfully installed based on these analyses.Nuclear Plant Seismic Adequacy Assessment (USI A-46)Performed seismic adequacy walkdowns of several hundred mechanical and electrical equipment items at two BWRs, and at a two-unit PWR. Work was performed in accordance with the NRC-approved Generic Implementation Procedure (GIP), and included screening walkdowns and seismic capacity calculations for equipment anchorages.

Supported seismic relay evaluations at a BWR by assisting in establishment of appropriate seismic demands for relays mounted in a variety of enclosures, e.g., control room panels and switchgear.

Primary author of USI A-46 Seismic Evaluation Reports for three plants' NRC submittals.

Co-instructor for Seismic Qualification Utility Group (SQUG) training course for performing equipment screening walkdowns in accordance with the GIP.EDUCATION Duke University, B.S. Civil/Structural Engineering (Magna Cum Laude), 1981 REGISTRATION Registered Professional Engineer, Commonwealth of Virginia OTHER Co-Principal Investigator, Electric Power Research Institute (EPRI) document 1025286, "Seismic Walkdown Guidance:

For Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic," EPRI, Palo Alto, CA: 2012.Successfully completed the Seismic Qualification Utility Group (SQUG) course for Seismic Capability Engineers, as defined by the NRC's Unresolved Safety Issue (USI) A-46 Program, 1993, and EPRI Seismic Walkdown Engineer (SWE) training, 2012.Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrPAnnndPnr.P Nn -RR-19-171 A-1 5 EILRECTRIC POWER I~II2 IESEARCH INSTITUTE Certificate of Completion Caroline Schlaseman Training on Near Term Task Force Recommendation 2.3-Plant Seismic Walkdowns June 21, 2012 Date Robert K. Kassawara EPRI Manager.Structural Reliability

& Integrity CIIt 3,I.OllyOpi~

i I MP-3796. Revision 1 Correspondence No.: RS-12-171

MPR ASSOCIATES INC ENGINE E R S Patrick J. Butler, P.E.EXPERIENCE

SUMMARY

1986 -present MPR Associates, Inc.Since joining MPR in 1986, Mr. Butler has acquired experience in engineering related to nuclear and fossil electrical generating facilities including project management, analysis, design, and economic evaluation.

Specific areas of work include design and on-site support of major modifications and testing, stress analysis, controls, thermal hydraulics, seismic engineering, and machine design as described below: ACCOMPLISHMENTS

SUMMARY

Equipment Seismic Qualification Developed guidelines and procedures for the Seismic Qualification Utility Group (SQUG) for using the Generic Implementation Procedure (GIP)for assessing the seismic adequacy of new and replacement equipment installed in Unresolved Safety Issue A-46 power plants. Involved in development of licensing guidelines for incorporation of the GIP Methodology into USI A-46 Plants. Developed and taught course for SQUG training Seismic Capability Engineers (SCE) in used of GIP for new and replacement equipment.

Has received SQUG training to be certified as a SCE. Performed seismic qualification evaluations for control room equipment modifications in accordance with IEEE Standard 344-1975, including analyses of several modified equipment cabinets, as well as development and documentation of a detailed analysis procedure.

Involved in project to develop experience-based seismic qualification methodology for select equipment types within Advanced Light Water Reactors.

Performed equivalent static and response spectrum analysis for numerous replacement ASME Code Section III components for nuclear plants. Compared the ANCHOR and EBAC equipment anchorage seismic evaluation computer codes which included performing example evaluations and comparing code algorithms.

Prepared procedure for evaluation and resolution of seismic licensing basis violations discovered during USI A-46 reviews. Assisted walkdown engineers in SQUG USI A-46 pilot plant assessment by performing anchorage qualification calculations and equipment seismic evaluations.

Has also performed finite element dynamic analyses of piping systems.BWR Reactor Internals Repairs Lead MPR Engineer responsible for design and analysis of shroud components, development of installation requirements, interface with installation vendor and on-site support of installation of the MPR Shroud Repair Design at Oyster Creek in 1994, FitzPatrick in 1995 and Vermont Yankee in 1996, Hamaoka 3 in 2005 and Hamaoka 4 in 2006.The repairs, while not N-stamped were designed to meet the requirements of the ASME Boiler and Pressure Vessel Design Code, Subsection NG.Specific responsibilities included design of repair hardware, analysis of the effect of the repair on the core spray piping, development of the installation specification for the repair, development of the installation process with the installation vendor, oversight of installation tooling development and qualification and lead MPR site engineer supporting installation of the repair. Lead MPR Engineer responsible for design of repairs for BWR Core Spray Piping inside vessels at Vermont Yankee and at Brunswick Unit 2. Awarded 5 U.S.Patents for repair hardware and tooling associated with BWR reactor vessel internals repairs.ASME Code Section III Design and Analysis Lead MPR Engineer responsible for interface with N-Stamp holding fabrication partner. Prepared and certified design specifications and ASME Code Design Reports for numerousSection III replacement vessels, heat exchangers, pump blocks, filter housings and strainers to support fabrication partner. Responsible for preparation and certification of ASME Code Section III design specifications for replacement once-through steam generators and attached hot leg piping and elbows for utility client.Decay Heat Removal Valve Repair Lead MPR engineer responsible and project manager for design and analysis of a valve modification involving welding of a canopy over a leaking pressure seal bonnet to create a new ASME Code pressure boundary.

The modification involved ASME Section III, Subsection NB analyses of the canopy and adjacent valve body and bonnet areas that the canopy was welded. In addition, MPR performed an extensive Section Xl reconciliation of ASME Section III, Subsection NB to the code of construction for the valve. MPR produced the fabrication drawings for the canopy and performed the finite element analysis of the canopy, valve bonnet and body, providing all deliverables on time and on budget. The modification was implemented during a forced Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrpqnnndrPnr-.

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RR-17-171 A-1 7 Patrick J. Butler, P.E.Page 2 outage this spring. The innovative approach implemented in this modification allowed the utility to repair the valve with the decay heat system in-service. Alternate repair options involving rework or replacement of the valve would have required complete core off load. The utility estimated that implementation of the innovative canopy modification saved them on the order of $10 million.Three Mile Island Defueling and Sample Removal Involved in design, testing and in-vessel use of special tooling for removal of fuel assemblies from the damaged Three Mile Island Unit 2 reactor vessel. Also was involved in an NRC project to remove metallurgical samples from bottom head of the Three Mile Island Unit 2 reactor vessel.Specific activities included tool design and fabrication supervision, qualification testing, personnel training and supervision of on-site sampling activities.

Acted as lead engineer responsible for two sampling tool systems and was responsible for shift sampling operations in the support of the Project Manager. During thirty days of in-vessel activities, thirty-one samples were removed for NRC evaluation.

The project was completed on schedule and within fixed cost budget limits. Assisted the Smithsonian Institute in developing an exhibit depicting the sample removal project which is included in the "Science in American Life" exhibit in the National Museum of American History.Vessel Penetration Repair and Analysis Developed and implemented hydrostatic testing program for a mechanical seal developed as a contingency repair for damaged BWR reactor vessel control rod drive penetrations.

Specific tasks included test plan development, re-design of seal components, and design, fabrication management and testing of seal installation tooling.Component Design Basis Inspection Support Lead MPR Engineer responsible for providing support for NRC Component Design Basis Inspections.

Mr. Butler has managed several teams of MPR engineers involved in performing focused area self assessments in preparation of the CDBI inspection as well as teams providing support during the actual inspection.

Mr. Butler has been the lead MPR engineer for six inspections for three different nuclear plants.EDUCATION Virginia Polytechnic Institute and State University, B.S. Mechanical Engineering, 1986 PUBLICATIONS"GIP Methodology for New and Replacement Equipment and Parts," with S. J. Eder and R. P. Kassawara presented at the Fifth Symposium on Current Issues Related to Nuclear Power Plant Structures Equipment and Piping, Orlando, FL: December 14-16, 1994"Application of the GIP Methodology for Demonstrating Seismic Adequacy of New and Replacement Equipment and Parts In USI A-46 Plants," with S. J. Eder and R. P. Kassawara presented at the 1994 ASME Pressure Vessels and Piping Conference, Minneapolis, MN: June 19 23, 1994"Seal Enclosure Modification for Crystal River Unit 3 Decay Heat Removal Valve DHV-3," with Andrew Dewhurst to be presented at the 2001 EPRI Valve Symposium, Baltimore, MD, August 14-16, 2001 REGISTRATIONS Registered Professional Engineer, State of Virginia, (Registration Number 23815)Registered Professional Engineer, State of Kansas (Registration Number 18757)PATENTS"Method for Detecting Changes in Preload in a Tie Rod Installed as Part of a Core Shroud Repair in a Boiling Water Reactor, " U.S. Patent No. 5,589,640"Method of Preventing Separation of Feedwater Sparger End Bracket Assemblies," U.S. Patent No.7,505,546."Apparatus and Method for Mechanically Reinforcing the Welds Between Riser Pipes and Riser Braces in Boiling Water Reactors," U.S. Patent 7,185,798.

Limerick Generating Station Unit 1 MPR-3796, Revision 1 C.nrroqnnndsnr.P Nn

RR-19-171 A-1 8 Patrick J. Butler, P.E.Page 3"Apparatus for Detecting Changes in Preload on a Tie Rod Installed as Part of a Core Shroud Repair in Boiling Water Reactors," U.S. Patent 5,809,100."Clamp for Feedwater Sparger End Bracket Assemblies and Method of Preventing Separation of Feedwater End Bracket Assemblies," U.S. Patent 7,492,851 Limerick Generating Station Unit 1 MPR-3796, Revision 1 Nn

R,-19-171 A-1 9 B Equipment Lists The following documents are included in this appendix:* Base List (SPCL cover sheet plus 79 pages)* SWEL Signature Page* Table B-1: SWEL for Unit 1* Table B-2: SWEL for Unit 0 (common)Note that there are no items in the SWEL 2 for Limerick Unit 1.* Table B-3: Deferred to RFO: Inaccessible or Requires Removal of Insulation to see Anchorage Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 B-1 SUCCESS PATH COMPONENT LIST (SPCL)FOR LIMERICK GENERATING STATION UNIT lAND COMMON ATTACHMENT A Composite Success Path Component List (SPCL) sorted by Equipment ID 79 Pages Document No. 0067-00085-D002 Revision I timefrik GenerffIifg SialhwbtJfiV:&73.

MPR-3796 Revision 1 .'.: S.. -". ~-' %U.74'q =7 -12 o, G):5 ii Page 1 Dote: 619195 M-11, 1 LIMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCL)Documnmt No. WN O.A112chmentA Revision 1 Train Class Equp ID System Equip Oesaption Drawing No. Room No. Norm slate Molve power Support System Supp Sys dwg Unit Eveo Reqd Room Elev Equip Elev Line No. Functlon PIMS ID Notes ROB Mother C'np Building Rea'd Stale Con-r power 3 1 008131 480V D134-R-E REACTOR AREA SAFEGUARD E-28 402 ENERGIZED 106203 1 S 410V MCC 10-B223 ZC 253 253 8719 ACTIVE D134-R-E REACTOR ENERGIZED N/R ENCLOSURE 3 1 009132 480V CONTROL ENCLOSURE SAFEGUARD E-28 619E ENERGIZED 10204 1 S 440V MCC 00.8132 ZD 304 304 8319 ACTIVE 0144-C-B CONTROL ENERGIZED NIR STRUCTURE 3 1 008519 480V0 D114-S-L SPRAY POND AREA E-28 1000 ENERGIZED 109201 I S SAFEGUARD 44nV MCC OD-B5119 ZA 288 258 8125 ACTIVE D114-S-L SPRAY POND PUMP ENERGIZED NIR STRUCTURE 3 1 008520 480V D124-S-L SPRAY POND AREA E-28 1005 ENERGIZED 108202 1 5 SAFEGUARD 440V MCC 00-8520 ZB 268 268 8225 ACTIVE D124-S-L SPRAY POND PUMP ENERGIZED NMR STRUCTURE 3 1 00B522 480V D244-S-L SPRAY POND AREA E-29 1005 OPERABLE 20B204 Common S SAFEGUARD 480V MCC 00-8522 ZO 258 268 8819 ACTIVE 0244-S-L SPRAY POND PUMP OPERABLE NMR STRUCTR 3 18 00C681 N/A PANEL HEATING a VENTILATING N/A 533 OPERABLE N/A Common S CONSOLE 259 269 9163 PASSIVE 00-Ce8a CONTROL OPERABLE N/A STRUCTURE 3 18 00C692 NIA PANEL SUPP POOL TEMP. & CONT. N/A 533 OPERABLE NWA Common S ATMOS MONITORING 269 269 9159 PASSIVE 00-C692 CONTROL OPERABLE N/A STRUCTURE 3 2 01X566 120V AC DIV I SPRAY PCNI PUMP STRUCTURE E-30. Sih 3 1000 OPERABLE 006519 Common S 120VAC INSTRUMENT PANEL XFMR 268 8129 ACTIVE 01-1556 SPRAYPOND PUMP OPERABLE NIR STRUCTURE 3 12 011Y01 120V AC DIV. I SPRAY POND 120 VAC INST. E-30, ShI 3 1000 ENERGIZED 00B519, 01X588 Common S PANEL 01-YS01 SERVICE DISC. SW. 268 288 8130 ACTIVE 01-Y501 SPRAYPONDPUMP ENERGIZED NIR STRUCTURE 3 2 02X566 IZOVAC DIVISION 11 SPRAY POND PUMP E-30, Sht 3 1005 OPERABLE 00B520 Common STRUCTURE 120VAC INSTRUMENT 8231 n PANELT 268 8231 ACTIVE 02-X566 SPRAYPONDPUMP OPERABLE NIR STRUCTURE 3 12 02Y501 123V'AC DIV. 2 SPRAY POND 120 VAC INST. E-30, SI 3 1005 ENERGIZED 008520, 02X566 Common S PANEL 02-Y501 SERVICE DISC. SW. 268 28 8229 ACTIVE 02-Y501 SPRAY POND PUMP ENERGIZED NMR STRUCTURE 3 18 0AC564 WA CONTROL PANEL SPRAY POND PUMP WA 1000 OPERABLE N/A Common S STRUCTURE AIR SUPPLY FAN 268 268 9160 PASSIVE OA-C564 SPRAY Po"4 PUMP OPERABLE N/A STRUCTURE Filter. Unit ="1 or Unit = "Common" Sorted By Equip ID Page 2 Date: 619/95 Train* unit Urn No.3 Common 9164 Common 5571 I* Common S 4501 I Common 5500 3 Common 3 Common 9161 3 Common 9165 2 Common 5645 2 Common 4601 2 Common 5600 3 Common 5750 3 Common 9166 I I m Class Eval Reced Fuinction 18 S PASSIVE 9 S PASSIVE 4 SR ACTIVE 4 SR ACTIVE a SR ACTIVE 18 S PASSIVE 18 S PASSIVE 9 S PASSIVE 4 SR ACTIVE 4 SR ACTIVE a SR ACTIVE 18 S PASSIVE Equip I0 PIMS ID OACS67 OAKI 12 OA-KI12 OAPSOB CA-PS06 CAPS48 CA-P548 OAV543 OA-V543 OBC564 OM-564 139CS67 OB-CC67 05BK112 05-1(112 OB13506 OB-Psos UBP548 OB-PS48 GBV543 OB-VS43 OCC567 OC-C857 UMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)System Equip Descnption Drawing No. Room No. Norm state Room Elev EquipElev Notes ROB Mother Camp Buidtrim Reqd Slate NIA EMERGENCY SERF ICE WATER DIVISION NWA 533 OPERABLE I CONTROL PANEL 269 269 CONTROL OPERABLE STRUCTURE CONTROL ENCL CONT. ENCL. CHILLER DAK1 12 (CHILLER M-1 1, Sht 2 258 NfA CHILLED WATER A) 200 200 CONTROL NIA STRUCTURE RHRSW "A"RHR SERVICE WATER PUMP 0APS06 -12 1000 OFF (PUMP A) 268 2B0 SPRAY POND PUMP ON STRUCTURE ESW A EMERGENCY SERVICE WATER PUMP M-11. Sh 1 1000 OFF 0AP548 (PUMP A) 268 280 SPRAY POND PUMP ON STRUCTURE MISC. A" SPRAY POND PP- STRUCTURE AIR M-81. Sh1 1 ¶000 OFF STRUCTURES

-SUPPLY FAN 268 268 HWAC SPRAY POND PUMP OPERABLE STRUCTURE NIA CONTROL PANEL SPRAY POND PUMP NIA 1005 OPERABLE STRUCTURE AIR SUPPLY FAN 268 268 SPRAY POND PUMP OPERABLE STRUCTURE NIA EMERGENCY SERVICE WATER DIVISION WA 533 OPERABLE II CONTROL PANEL 269 269 CONTROL OPERABLE STRUCTURE CONTROLENCL CONT. ENCL CHILLER 01KI12 (CHILLER M-11. Sht 2 263 NWA CHILLED WATER I) 200 200 CONTROL N/A STRUCTURE RHRSW I"BRHR SERVICE WATER PUMP 0BP506 M-12 1005 OFF (PUMP B) 268 265 SPRAY POND PUMP ON STRUCTURE rESW 8 EMERGENCY SERVICE WATER PUMP M-"1, Shl 1 1005 OFF 0BP548 (PUMP B) 268 285 SPRAY POND PUMP ON STRUCTURE MISC. E SPRAY POND PP. STRUCTURE AIR M-81. Shl 1 1005 OFF STRUCTURES-SUPPLY FAN 258 268 HVAC SPRAY POND PUMP OPERABLE STRUCTURE NA EMERGENCY SERVICE WATER DIVISION WA 5M OPERABLE III CONTROL PANEL 269 269 COITRM. OPERABLE STRUCTURE Docmnte No. 00 0SUCS00 AtLadiment A Revision 1 Motive power Support System Supp Sys dwg Contr power WA NIA NIA NWA 1Al15 SPPV M-81, Sh1.10AII5, IADI02 10A115 SPPV M-76 IOAI 15, 1AD102 00B519 ESW M-11 00B519 NWA MIA WA NIA NIA NIA 10A116 SPPV M-81, Sh. 1 10A116. 160102 10AI1S SPPV M-76 10Al16, 180102 008520 ESW M-11 005520 NIA NIA Filter Unit = 1" or UnIt -'Common" Sorted By Equip ID Page 3 Date: 6W9/95"03 in ,. Train; o* Unit Line No.Ln Common 2. 4503 Common 5501 3 Common 9162 b. 2 Common 4603* 12-~ Common 3113 1 I 1 3114 I; 1 I' 1 3301 3 I : 1 8100 3 I* 8101 3 81*" 8102 Class Evel Reqd Function 4 SR ACTIVE 4 SR ACTIVE 18 S PASSIVE 4 SR ACTIVE 4 SR ACTIVE 32 S PASSIVE 32 S PASSIVE 32 S PASSIVE 32 S PASSIVE 1 SR ACTIVE I ER ACTIVE 1 BR ACTIVE Equip ID PIMS ID GCP506 OC-PSOG DrP548 OC-P548 013CB67 O0.C667 0OP506 OD-P506 ODPS48 OD-P548 101 P209 101 P209 10IF210 101 P2I0 10217209 102F209 102F210 102F2iO 1 OAI 15 D111 IOAI 15(02)D11-BUS-02 I DA 15S(03)01 1-BUS-03 Syszem Notes RHRSW ESW WA RHRSW ESW RCIC HPCI RCIC HPCI 4KV 4KV 4KV 0 ULNENIIC GENERA'rNG STATION IPEEE PROJECT UNIT I&COMMON SUCCESS PATH COMPONENT UST(SPCL)Equip Description Drawing No. Room No. Norm state Room Elav Equ;p Elev ROB Mother Camp Buitdirig Reqid State'C RHR SERVICE WATER PUMP 0CPS06 M-12 1000 OFF (PUMP C) 268 268 SPRAY POND PUMP ON STRUCTURE C EMERGENCY SERVICE WATER PUMP M.11. Shi 1 1000 OFF OCP548 (PUMP C) 268 268 SPRAY POND PUMP ON STRUCTURE EMERGENCY SERVICE WATER DMSION N/A 533 OPERABLE IV CONTROL PANEL 269 269 CONTROL OPERABLE STRUCTURE"0" RHR SERVICE WATER F UMP GDP5O6 M-12 1005 OFF (PUMP D) 268 268 SPRAY POND PUMP ON STRUCTURE D EMERGENCY SERVICE WATER PUMP M.11, Sht I 1005 OFF (PUMP 0) 268 268 SPRAY PN PJUMP ON STRUCTURE RCIC SUPPRESSION POOL SUCTION M-49. Sht 1 101 OPERABLE STRAINER 182 177 REACTOR OPERABLE ENCLOSURE HPCI SUPPRESSION POOL SUCTION M-55, SHT 1 101 OPERABLE STRAINER 182 181 REACTOR OPERABLE ENCLOSURE RCIC SUPPRESSION POOL SUCTION M.49, Sht 1 101 OPERABLE STRAINER 182 181 REACTOR OPERABLE ENCLOSURE HPCI SUPPRESSION POOL SUCTION M-S5. SIHT 1 101 OPERABLE STRAINER 182 181 REACTOR OPERABLE ENCLOSURE SWITCHGEAR.

SAFEGUARD E-15 435 OPERABLE METALCLAD, 4.16KV. 3PH, 3 WIRE, 60HZ 239 239 CONTROL OPERABLE STRUCTURE 201-011 SAFEGUARD XFMR, BREAKER E-15 435 OPERABLE (CB400W8) 239 239 1DAl15 CONTROL OPERABLE STRUCTURE"A" RI-IR. SERVICE WATER PUMP DAP506 E-15 435 OPERABLE 152-11503 (CR4020) 239 239 10A11S CONTROL OPERABLE STRUOTURE Doctamen No. 00S?,400UO,,l AtadcmenI A Revision 1 Motive power Support SystemT) Supp Sys dwg Coamr power 20A115 SPPV` M-81. Sh. 1 20A1 I5. 2AD102 20A117 SPPV M-76 20A117, 2C0102 N/A NIA 20A!18 SPPV M-1. Sh 1 20A156, 280102 20A118 SPPV M-76 20A1 18, 20D102 N/A WA N/A NIA NI'A N/A N/A N/A 1AG501 1AD1M IAGSO1 1AD102 lAGE01 IAD102 Filter. Unit = ""orUn.t = "Common" Sorted By Equip ID U2 DC 1!43'Am<It it '1 0 LIMERICK GENERATING STATION IPEEE PROJECT UNnTI & COMMON SUCCESS PATH COMPONENT UST(SPCL)Document No. 00osl6 msa ARedevem A Revision I Page 4 Data: EM9/95 Train Cleass Equip ID System Equip Desoiption Drawing No Room No Norm state Motive power Support System Supp Sys dwg Unit Eva) Recad Room Elav Equip Elev Line No. Funclion PIMS It Notes ROB Mother Comp Building Rflid Stale Con" power 3 1 IOAlt5(04) 4)0,1 IARIHR PP. 1AP202152-11504 (CB4034) E-15 435 OPERABLE IAGS01 I BR 239 239 8103 ACTIVE DI1-BUS-04 10Al15 CONTitROIL OPERABLE 1AD102 SIRUCTURE 3 1 ItA11S(05) 4KV D114 SAFEGUARD LC XFMR IOX201 E-15 435 OPERABLE IAG.O0 1 BR (084017) 239 239 8104 ACTIVE DI1-BUS.05 10Al1S CONTROL OPERABLE 1AD102 STRUCTURE 3 1 1OAIIS(07) 4KV DIESEL GEN IAG501 (CB4036) E-15 435 OPERABLE IAGS01 I BR 239 239 8105 ACTIVE Dll-BUS-07 1OAl11 CONTROL OPERABLE 1AD102 STRUCTURE 3 1 10AItS(OB) 4KV WA SWPUMP GAP548152-11508 (C84043) E-15 435 OPERABLE 1AS501 I BR 239 239 a106 ACTIVE D1..BUS-0 1l15 CONTROL OPERABLE 1AD102 STRUCTURE 3 1 10A115(09) 4KV 101-1l1 SAFEGUARD XFMR BREAKER E-15 430 OPERABLE IAG501 1 BR (C84009) 239 239 8107 ACTIVE D11-BUS-09 iOA11 CONTROL OPERABLE 1AD002 STRUC.TURE 3 1AlS 4K'V SVWTCHGEAR.

SAFEGUARD E-15 433 OPERABLE 18GS01 I SR METALCLAD.

4.16KV, 3PH, 3 WIRE. 60HZ 239 239 8200 ACTIVE 012 CONTROL OPERABLE 18DI102 STRUCTURE 3 10A1 18(02) 4KV 201-012 SAFEGUARD XFMR BREAKER E-15 433 OPERABLE tRGS01 1 BR (CB4040) 239 239 8201 ACTIVE D12-BUS.02 IAlI16 CONTROL OPERABLE 15D102 STRUCTURE 3 1 10AI16(03) 4KV W"RHR SERVICE WATER PUMP OBP506 E-15 433 OPERABLE 156501 I BR 152-11603 (CB4021) 239 239 0202 ACTIVE D12-BUS-03 1OAl11 CONTROL OPERABLE 16D102 STRUCTR 3 1 t0A118C04) 4KV 18 RHR PP. 18P202 152-11604 (CB4004) E-15 433 OPERABLE 15G501 I SR 239 239 8203 ACTIVE 012-BUS-04 IDA116 CONTROL OPERABLE 160102 6-RUC7URE 3 1 10A116(05) 4KV D124 SAFEGUARD LC XFMR 1OX202 E-15 433 OPERABLE 151501 I BR (054002) 239 239 8204 ACTIVE 012-BUS-05 I1A116 CONTROL OPERABLE 1BD102 STRUCTURE 3 1 10AT16(07) 4KV DIESEL GEN 18G501 (C04028) E-i5 433 OPERABLE 1BG501 i BR 239 239 8205 ACTIE D12-BUS-07 IDA116 CONTROL OPERABLE 1BD102 STRUCTURE 3 1 1OA11(0B) 4KV OB ESW PUMP OBP548 152-11608 E-15 433 OPERABLE 180501 IBR (C54041) 239 239 8206 ACTIVE- 012-BUS-08 10A118 CONTROL OPERABLE 16D002 STRUCTURE Filler. Unil = 1"or Unit "Common" Sorted By Equip ID 41.I.I.i IC; ,..I'i I: I!.". 1i Page 5 Dsit: 6(9195 U Occuimat No. -oo0s-XXsau Altadhmeni A Revisin I UMEICK GENERATING STATION IPEEE PROJECT UNIT I &COMMON SUCCESS PATH COMPONENT LIST (SPOL)Train Class Equip ID Syat'm Equip Desaiption Drawing No. Room No. Norm state Motive power Support System bupp Sys dwe Unit EvaI Riqd Roam 2ev Equip Elev Line No. Ftnadion PIM$ [D Notes ROB Mother Camp Buadng Reqd State Conir power 3 1 1CAI16(09) 4KV 101012 SAFEGUARD XFMR BREAKER F-15 433 OPERABLE 108501 1 BR 0CB4013) 239 239 8207 ACTIVE D12-BUS-09 1AI1S CONTROL OPERABLE IBD102 STRUCTURE 3 1 10Al17 4KV SWITCHGEAR.

SAFEGUARD.

METAL E-15 434 OPERABLE 1CG501 1 SR CLAD. 4.16KV. 3PH, 3 WRE. 6OHZ 239 239 8700 ACTIV On3 CONTROL OPERABLE 1C0102 61RUCTURE 3 1 10A117(02) 4KV 201-013 SAFEGUARD XFMR BREAKER E-15 434 OPERABLE 1CG501 I OR (C84027) 239 239 8701 ACTIVE 0134-US-02 10A117 CONTROL OPERABLE IC0t02 STRUCTURE 3 1 10A117(04) 4KV 1C RHR PP. BM 1CP202 152-11704 E-15 434 OPERABLE ICG501 IBR (C84024) 239 239 8702 ACTIVE D13-BUS-04 I1A117 CONTROL OPERABLE ICD102 STRUCTURE 3 1 0A117(05) 4KV 0134 SAFEGUARD LC XFMR (CB4006) E-1B 434 OPERABLE 1CG501 I BR 239 239 8703 ACTIVE D13-BUS-05 10A17 CONTROL OPERABLE 10102 bTRUCTURE 3 1 10A117(07) 4KV 013 DIESEL GEN 1CG501 (C04010) E-15 434 OPERABLE 1CG.501 I BR 239 239 8704 ACTIVE DI3-BUS-07 I0AI17 CONTROL OPERABLE 1CD102 STRUCTURE 3 1 10A117(09) 4KV 101-013 SAFEGUARD XFMR BREAKER E-15 434 OPERABLE 1CG501 1 BR (C04011) 239 239 8705 ACTIVE D13-BUS-09 10A117 CONTROL OPERABLE 1CD102 STRUtJCTURE 3 1 10A117(11) 4KV 0C EMER SERVICE WATER PUMP OCPS4B E-15 434 OPERABLE 1CG501 I BR (C04023) 239 239 870a ACTIVE D13-BUS-11 10A117 CONTROL OPERABLE 10102 STRLUCTURE 3 1 1,I18 4K[V SWITCHGEAR, SAFEGUARD METAL E-15 432 OPERABLE 10G501 I SR CLAD, 4.18KV, 3PF, 3 WIRE, 60HZ 239 239 8300 ACTIVE D14 CONTROL OPERABLE 10D102 STRUCTURE 3 1 10A118(02) 4KV 201-014 SAFEGUARD XFMR BREAKER E-15 432 OPERABLE 1DG501 1 BR (854029) 239 239 M301 ACTIVE D14-BUS-02 10AI18 CONTROL OPERABLE 100102 STRUCTURE 3 I1AII(04) 4KV I0 RHR PP BORE R lDP202 (C84018) E-15 432 OPERABLE 103501 1 BR 239 239 8302 ACTIVE 014-BUS-04 10A`11 CONTROL OPERABLE DD1002 STRUCTURE 3 1 10A118(05) 4KV D144 SAFEGUARD LCXFMR (CB402S) E-15 432 OPERABLE 10G501 I OR 239 239 8303 ACTIVE 014-BUS-05 IDAIIS CONTROL OPERABLE IDD102 SM -CT1JRF Filter, Unit c -I- or Unit = Comnmon" Sorted By Equip ID_ _ _ _-' ." -' ' ." " ". ; " -r : " " ' ' ": : -" -:.: i: ' .-;.. ..:.; .- .I:.'. .' -;

Page 6 Date: 0455 Train Und_ine No.3 I 8304 8305 3 1 8306 3 8128 3 1 8109 3 r 820e 3 870B 3 8308 3 1 8126 3 8226 3 f 8122 ,. .am Class Eval Recfd Function I BR ACTIVE I BR ACTIVE I BR ACTIVE 1 WA ACTIVE I SR ACTIVE$ACTIVE I SR ACTIVE I S ACTIVE$ACTIVE I S ACTIVE I S ACTIVE Equip ID PIMS ID 10A118(07)

D14-BUS-07 1AI 18(09)D14-BUS-09 10Al18(11) 014-BUS-11 108129 Dlt14-G-D 108201 D114 108202 D124 108203 0134 105204 D144 108211 D1 14-R-G 108212 D124-R-G 10B213 D1 14-R-C 108214 D124-R-C System Notes 4KV 4KV 4KV 480V 38 4BlV 480V 480V 480V 480V 480V 411V 480V 9 LIMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST(SPCL)

Equip Description Drawing No. Room No.Room Elev ROB Mother Comp Building 014 DIESEL GEN 10G501 (CR4022) E-15 432 239 10A118 CONTROL STRUCTURE 101-D14 SAFEGUARD XFMR BREAKER E-15 432 (C4006) 239 1AIl18 CONTROL STRUCTURE OD EMER SERVICE WATER PUMP ODP548 E-15 432 (CR4003) 239 1oA118 CONTROL GENERATOR AREA 480V MCC (10-8129)

E-28 648 2A9 TURBINE BUJILDING ENCLOSURE D114 REACTOR AREA SAFEGUARD LOAD E-28 6(J2W CENTER (10-6201) 313 REACTOR ENCLOSURE REACTOR AREA 480V SAFEGUARD LOAD E-28 602E CENTER 10-4202 ZB 313 REACTOR ENCLOSURE REACTOR AREA SAFEGUARD LOAD E-21 402W CENTER 10-8203 ZC 253 REACTOR ENCLOSURE REACTOR AREA 480V SAFEGUARD LOAD E-28 50SE CENTER 110-8204 ZD 283 REACTOR ENCLOSURE REAC AREA SFGD 440V MCC E-28 304W 10-8211 ZA 217 REACTOR ENCLOSURE D124-R-G REACTOR AREA SAFEGUARD E-20 304E 40V MOO 0O-8520 ZB 217 REACTOR ENCLOSURE 0114-R-C REACTOR AREA SAFEGUARD E-28 5WSW 4BOVMOTOR CONTROL CENTER 283 REACTOR ENCLOSURE D124-R-C REACTOR AREA SAFEGUARD E-28 5068 4150V MCC 10-"214 ZO 283 REACTOR ENCLOSURE Nonm stale Equip Elev Reqd Stale OPERABLE 239 OPERABLE OPERABLE 239 OPERABLE OPERABLE 239 OPERABLE ENERGIZED 269 ENERGIZED OPERABLE 313 OPERABLE OPERABLE 313 OPERABLE OPERABLE 253 OPERABLE OPERABLE 283 OPERABLE OPERABLE 217 OPERABLE OPERABLE 268 OPERABLE OPERABLE 283 OPERABLE OPERABLE 2B3 OPERABLE a Document No. 0067-1OOMBZ-0 AI, ndIralt A Revision 1 Motive power Support System Supp Sys dwg Contr power IDG501 1DD102 1DG501 1DD102 1DG501 1D0102 100201 NIR ,1AI1S,10X201 1AD102 10AlS6, 10X202 1B0102 10All, 101X203 1C0102 WA118, 10X204 100D102 108201 NIR 108202 NfR 108201 NIR 108202 NWR Filem Unit = ""or Unit = "Common" SoWed By Equip ID I Page 7 Data: 6/S915 a) : Unit M Line12o.3 812?3 8227 8716 3 i 8316 3 1 8123 3 8718 3 1 7 8718 3 j.t: 831a 8124 3 1 8124 3 8224 3 1 8717 3 1 8317 W UMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCL)W Document No. 007=740085 Attachitent A Revision I CLass Equip ID System Equip Description Thawing No. Room No. Norm state Motive power Support System Supp Sys dwg Eval Req'd Room Etev Equp Elev Function PIMS id Notes ROB Mother Comp Building Refld State Contr power A ACTIVE 1 ACTIVE I S ACTIVE 1 ACTIVE I S ACTIVE I 8 ACTIVE A ACTIVE A ACTIVE S ACTIVE ACIE S ACTIVE S ACTIVE 1OB215 D1 14-R-G1 108216 D124oR-G1 10B217 0134-R-H 109218 D144-R-H 105219 D114-R-C1 103220 D124-R-C1 108223 D134-R-E 105224 D1 14-R-E 108515 D114-0.G 10B516 D124-0-G 108517 D134-D-G 108518 D144-0-G 480V 480V 480V 480V 4BaV 480V 480V 480V 480V 480V 480V REACTOR AREA SAFEGUARD 440/ MCC E-20 10-B215 ZA REACTOR AREA SFGD 440V MCC 10-"216 E-28 ZB D134-R-H REACTOR AREA SAFEGUARD E-28 480V MCC 10-8217 ZC 0144-R-H REACTOR AREA SAFEGUARD E-28 480V MCC 10-B218 ZO DI 14-R-C1 REACTOR AREA SFGD 440V E-28 MCC 10-B219 ZA D124-R-Cl REACTOR AREASPGD44OV E-28 MCC 10-8220 ZB D134-R-E REACTOR AREA SAFEGUARD E-28 480V MCC O-B223 ZC 0144-R-E REACTOR AREA SFGD 480V E-28 MCC 104224 2D D114-D-G DIESEL GEN AREA E-28 SAFEGUARD 480V MCC 10-9515 ZA D124-D-G DIESEL GEN AREA E-28 SAFEGUARD 480V MCC 10-8516 ZB DI34-D-G DIESEL GEN AREA E-28 SAFEGUARD 4BV MCC 1048517 ZC D144-D-G DIESEL GEN AREA E-28 SAFEGUARD 48OV MCC 10-B518 ZD 304 OPERABLE 217 217 REACTOR OPERABLE ENCLOSURE 304E OPERABLE 217 217 REACTOR OPERABLE ENCLOSURE 200 OPERABLE 201 201 REACTOR OPERABLE ENCLOSURE 207 OPERABLE 201 201 REACTOR OPERABLE ENCLOSURE 602 OPERABLE 313 313 REACTOR OPERABLE ENCLOSURE 602 OPERABLE 313 313 REACTOR OPERABLE ENCLOSURE 402 OPERABLE 253 253 REACTOR OPERABLE ENCLOSURE 402E OPERABLE 253 253 REACTOR OPERABLE ENCLOSURE 311A OPERABLE 217 217 n]ESELGENERATOR OPERABLE ENCLOSURE 311B OPERABLE 217 217 DIESEL GENERATOR OPERABLE ENCLOSURE 311C OPERABLE 217 217 DIESE. GENERATOR OPERABLE ENCLOSURE 3110 OPERABLE 217 217 DIESEL GENERATOR OPERABLE ENCLOSURE 108211 N/R 10B212 NIR 108203 NR 1082G4 N/R IOB213 NIR 108214 N/R 109203 NM 10B204 N/R 10B201 NMR 10B202 NIR 10B203 N/R 108204 NIR 2" Filter. Unit = " or Unit = Common" Sored By Equip 1D c)C (0(UMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Docurnmtt No. 00S74C5O Revision 1 Page 8 Dat; 6819/95 Train Class Equip ID System EquIp Description Drawing No. Room No. Norm state Motive power Support System Supp Sys dwg Unit Eval Req'd Room Elov Equip Elev, Line No. Function PIMS ID Notes ROB Mother Camp Bu,,dding Recqd State Contr power 3 18 0C001 NIA DIVISION I CORE SPRAY SYSTEM NEA 304W OPERABLE NWA I INSTRUMENT RACK 217 217 9100 PASSIVE I"COol REACTOR OPERABLE NEA 3 16 10C004 WA RX WATER LEVEL & PRESSURE INST N/A 402W OPERABLE NIA I S RACK -LOCATED BEHIND THE HOU'S 253 253 9101 PASSIVE 10-C004 REACTOR OPERABLE WIA ENCLOSURE 3 16 IOC005 NIA DMSION III REACTOR VESSEL LEVEL & wA 402E. 402W OPERABLE NlA I S PRESSURE INSTRUMENT RACK 253 253 9102 PASSIVE 10-C005, RACTOR OPERABLE NZA ENCLOSURE 3 16 10C014 N/A DIVISION II HIGH PRESSURE COOLANT W1A 109 OPERABLE NIA I S INJECTION INSTRUMENT RACK 177 177 9!03 PASSIVE 10-C014 REACTOR OPERABLE WA ENCLOSURE 3 16 10C018 WA HPCI LEAK DETECTION LOCAL RACK NIA 304W OPERABLE NIA 1 S 217 217 9104 PASSIVE 10-C001 REACTOR OPERABLE NIA ENCLOSURE 3 16 10C017 NIA DIVISION I REACTOR CORE ISOLATION WIA 200 OPERABLE WIA 1 S COOLING INSTRUMENT RACK 201 201 9105 PASSIVE 10-C017 REACTOR OPERABLE WA ENCLOSURE 3 16 100018 /WA RESIDUAL HEAT REMOVAL INSTRUMENT WA 200 OPERABLE N/A I S RACK 201 201 91.06 PASSIVE 10-C018 REACTOR OPERABLE WA ENCLOSURE 3i 10019 WIA DIVISION 1i CORE SPRAY SYSTEM N/A 304 OPERABLE IVA 1 3 INSTRUMENT RACK 21? 217 9107 PASSIVE 10-C019 CONTROL OPERABLE N/A 91TRUCTURE 3 16 10C021 N/A RESIDUAL HEAT REMOVAL INSTRUMENT WA 207 OPERABLE N/A I S RACK 201 201 9108 PASSIVE 10-C021 REACTOR OPERABLE N/A ENCLOSURE 3 is 10C026 W/A RPV LEVEL AND PRESSURE NWA 402E, 402W OPERABLE N/A I S INSTRUMENT RACK 253 253 9109 PASSIVE 10-CO26 REACTOR OPERABLE WIA ENCLCOURE 3 16 10C027 NIA LOCATED BEHIND THE HCU'S NEXT TO NIA 402E OPERABLE NIA 1 S THE DRYWELL PERSONNEL ENTRANCE 253 253 9110 PASSIVE 10C0027 REACTOR OPERABLE NIA ENCLOSURE 3 16 10C035 W/A DIVISION I RCIC LEAX.DETECTION NWA 304E OPERABLE N/A 1 S INSTRUMENT RACK 217 217 9111 PASSIVE 10-C035 REACTOR OPERABLE NWA ENCLOSURE Filtr. Undt -"1 or Unit= "Common' Sorted By Eqp4 ID ,L %,7:7.. ....... Fý .7 777T-7.777ý

-7 Page 9 Date: 619195 Tram r Unit Line No.Co B o 1 c 9112 3 I 9113 3 1 9114 3* ; 9116 a q31: 9117 3-i 1 1-i1 9118 3 9119 3 110 3 1 1107 3¶-12 Class Evat Rectd Function 16 S PASSIVE 16 S PASSIVE 16 S PASSIVE 16 S PASSIVE 16 S PASSIVE 16 S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 SR ACTIVE 18 S PASSIVE Equip ID PIMS ID 100036 10-C036 10C038 10-0C38 10C075 10-C075 100076 1D-C075 100077 10-C077 100070 10-0078 100201 10-0201 1oCo601 104C601 100603 10-0603 100606 10-C606 100608 D0-C008 10C609 I0-C0T0 System Notes NIA WIA NWA NIA NIA NIA MIA N/A NIA NWA LPRh't 35 NIA U UIMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCL)Equip Description Drawing No. Room No.Room Elav ROB Molher Camp Building DIVISION II HPCI LEAK DETECTION WA 304W INSTRUMENT RACK 217 REACTOR ENCLOSURE DIVISION [II RCIC LEAK DETECTION NIA 304E INSTRUMENT RACK 217 REACTOR ENCLOSURE DIV RHR & DIV 1 ADS LOCAL RACK NWA 200 201 REACTOR ENCLOSURE DIV 2 RHR & DIV 3 ADS LOCAI RACK NIA 118 177 REACTOR ENCLOSURE DIV 3 RHR a DIV 1 ADS LOCAL RACK NWA 200 201 REACTOR ENCLOSURE DIV 4 RHR & DIV 3 ADS LOCAL RACK NZA 118 177 REACTOR ENCLOSURE REMOTE SHUTDOWN VERTICAL BOARD NWA 640 289 CONTROL STRUCTURE PANEL RX a CONTAwrMENT COOLING & N/A 533 ISOLATION VERTICAL BRD NUC BLR 259 CONTROL STRUCTURE REACTOR CONTROL CONSOLE N/A 533 269 CONTROL SMTRUCTURE"A Rad Monilor Instrument Panel RPS Al & NIA 542 A289 CONTROL STRUCTURE POWER RANGE NEUTRON MONITORING E-120 542 VERTI 289 CONTROL STRUCTURE RPS CHANNEL A VERTICAL BOARD N/A 542 289 CONTROL STRUCTURE Norm stabl Equip Elev Req'd State OPERABLE 217 OPERABLE OPERABLE 217 OPERABLE OPERABLE 201 OPERABLE OPERABLE 177 OPERABLE OPERABLE 201 OPERABLE OPERABLE 177 OPERABLE OPERABLE 289 OPERABLE OPERABLE 269 OPERABLE OPERABLE 269 OPERABLE OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE U Document No. 0067-0000S-502 Altsdvý*tA Revision 1 Molivae power Support System Supp Sys dwg Contr power NIA NWA WA N/A N/A NIA NIA N/A N/A WA NIA N/A NIA N/A NfA NWA N/A NWA NIA NWA NIA NWA NWA N/A Filter Unit = ""or Unit "Common" Sorted By Equip 10 I1 z Page 10:o* Date: 81J9/9M Train Unit L Une No.3 c4. 1 9123 3 9124-9127 3 I 9124 3*. l , 12¶t I 9120 3-" 1: -9131 3 912 I, 9132 3 I 9133* .... ____________

r I IIII Class Eval Reqd Function 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE 1I S PASSIVE IB S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE Equip ID PIMSID 10C612 10-C612 10C613 iaciv 10-C617 IOC6'17 10-C817 10.0818 10C620 10-C620 10C621 10-C621 1CC"22 10-C622 10C623 10-C,23 10C626 10-=626 10CS28 10-082 10C031 10-C631 10-633 113-C633 System Notes NWA MIA N/A NIA WA N/A MIA N/A NtA WA N/A N/A UM.ERICK GENERAlING STATION IPEEE PROJECT UNIT 1 & COMMON SUCCESS PATH COMPONENT LIST(SPCL)

Equip Descnption Drawing No. Room No.Room Elev ROB Mother Comp Building FEEDWATER AND RECIRCULATION WA 542 INSTRUMENT RACK 259 CONTROL STRUCTURE PROCESS INSTRUMENTATION CABINET WA 642 289 CONTROL STRUCTURE DMSION I RHR RELAY VERTICAL BOARD WA 542 269 CONTROL STRUCTURE DIVISION I RHR RELAY VERTICAL WA 542 BOARD 289 CONTROL STRUCTURE HPCI RELAY VERTICAL BOARD N/A 542 289 CONTROL STRUCTURE RCIC RELAYVERTICAL BOARD MIA 542 239 CONTROL STRUCTURE PRIMARY CONTAINMENT INBOARD NWA 542 VALVE RELAY VERT BOARD PANEL 289 CONTROL STRUCTURE PRIMARY CONTAINMENT OUTBOARD WA 542 VALVE RELAY VERT BOARD PANEL 289 CONTROL STRUCTURE ADS a MSIV LEAKAGE CONTROL NfA 533 269 CONTROL STRUCTURE DIV I AUTO DEPRESS RELAY VERTICAL N/A 542 80 289 CONTROL STRUCTURE DIV III AUTO DEPRESS RELAY VEPTICAL N/A 542 BOARD 289 CONTROL STRUCTURE"" Rad Monrtorhn0 Instrument Panel RPS 82 WIA 542& 81 289 CONTROL STRUCTURE Norm state Equip Elev Reqd State OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE OPERABLE 269 OPERABLE OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE Document No. 00874NOO54OCW Attechrent A Revision 1 Motive power Support System Contr power N/A WIA NWA N/A WA W/A WA WA NIA N/A MIA N/A MIA N/A N/A MIA N/A N/A NWA N/A N/A N/A NJA N/A Sump Sys dw9 Filter. Unit = "1 or Unit -"Common" Sorted By Equip ID m: I Page 11 S Date: 619/95 TCI M Train!5. Unit Eo = Line No.3 9134 3 S1 9136 3 I 9161 3 9137 3 1 913B 3 1108 3* 1 9139* 3* 9140 3 9163 3 9155 Class Eval Reld Function 18 PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S ACTIVE 18 S PASSIVE 15 S PASSIVE 18 PASSIVE 18 PASSIVE 18 S PASSP,/E Equip ID PIMS to 10C640 10-CS40 10C641 10-C641 10C644 10-C644 10C646 10-C646 10C647 10-C847 IOC648 10-C548 10C649 10-C649¶0C679 10-CO79 10C681 10-C881 10C689 10-CS89 10C690 10-C690 10C730 10-C730 Systen Notes W/A NIA NIA NIA NIA N/A LPRM 29 WA N/A N/A NIA N/A LIMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Equip Description Drawing No. Room No.Room Erev ROB Mother Camp Building DIVISION I, RHR & CORE SPRAY RELAY NWA 542 VERTICAL BOARD 289 CONTROL STRUCTURE DIVISION IV. RHR & CORE SPRAY RELAY NIA 542 VERTICAL BOARD 289 CONTROL STRUCTURE MSIV LEAKCAGE CONTROLDIV II NA 542 289 CONTROL StRUCTURE MSIV LEAKAGE CONTROL DIV It WA 542 289 CONTROL STRUCTURE PANEL HPCI VERTICAL BOARD NIA 533 269 CONTROL STRUCTURE RCIC VERTICAL BOARD N/A 533 269 CONTROL STRUCTURE ROD STATUS DISPLAY VERTICAL BOARD C51-1080-E 533 269 CONTROL STRUCTURE PROCESS INSTRUMENTATION PANEL NIA 542 289 CONTROL STRUCTURE HEATING AND VENTILATING CONSOLE N/A 533 269 CONTROL STRUCTURE PANEL LOOSE PARTS MONITORING N/A 533 SYSTEM CABINET UNIT 1 269 CONTROL STRUCTURE G PANEL SAFETY RELIEF VALVE NWA 533 POSITION INDICATION PANEL 269 CONTROL STRUCTURE CONDENSATE

& AUXTERMINAL WA 542 CABINET 289 CONTROL STRUCTURE Documeot No. D007,aS1011-OM Attachment A Revision 1 Norm state Motive power Support 5ystem Supp Sysdwg Equip E6ev Raq'd State Contr power OPERABLE N/A 289 OPERABLE NWA OPERABLE NWA 289 OPERABLE N/A OPERABLE NWA 289 OPERABLE NIA OPERABLE NWA 289 OPERABLE NWA OPERABLE WA 269 OPERABLE NZA OPERABLE NIA 289 OPERABLE N/A OPERABLE NWA 269 OPERABLE N/A OPERABLE NWA 289 OPERABLE N/A OPERABLE N/A 269 OPERABLE N/A OPERABLE N/A 269 OPERABLE NWA OPERABLE NIA 289 OPERABLE NIA OPERABLE NIA 289 OPERABLE N/A Filer. Unit ="1"or Unit ="Comnmonr Sorted By Equip ID-: ...o -o .. ....... ....

C Page 12 Dala 6&9195 W UMERICK GENERATING STATION IPEEE PROJECT UNIT I A COMMON SUCCESS PATH COMPONENT UST (SPCL)V Document No. OW7400064 MAdecneir A Revision 1 Tramn Class Equip 10 System Equip Description Drawing No. Room No. Norm state Mobve power Support System Supp Sys dwg unit Eval Req'd Room Elay Equip Eley Line No. Function PIMS ID Notes ROB Mother Comp Building Reqd State Conyr power 3 1i 10C787 LPRM POWER RANGE TERMINAL CABINET E-120 542 OPERABLE N/A 1 S 289 289 1106 PASSIVE 10-C787 CONTROL OPERABLE NIA STRUCTURE 3 18 I0C788 N/A PANEL PROC RAD MON.JETPUMP 9 NWA 542 OPERABLE NIA I S OUTED VLVS. TERMINAL CABINET 289 289 9167 PASSIVE 10-C788 CONTROL OPERABLE NIA STRUCTURE 3 18 100790 NIA PANEL RADIATION MONITORING CHB N/A 542 OPERABLE NIA I S TERMINAL CABINET 289 289 9168 PASSV 10-C790 CONTROL OPERABLE MIA STRUCTURE 3 18 10C791 N/A DIVISION I EGOS TERMINAL CABINET NWA 542 OPERABLE NfA 1 S 289 289 9169 PASSIVE 10-C791 CONTROL OPERABLE N/A STRUCTURE 3 18 10C792 N/A OIVISION II ECCS TERMINAL CABINET NWA 542 OPERABLE N/A I S 289 289 9172 PASSIVE 10-C792 CONTROL OPERABLE N/A STRUCTURE 3 18 10C793 N/A INBOARD VALVE 9 CRD POSITION N/A 542 OPERABLE NIA 1 S TERMINAL CABINET PANEL 289 289 9175 PASSIVE 10-C793 CONTROL OPERABLE WA STRUCTURE 3 1 'OD201 DC 250V DC MCC 10-D201 E-33. Sht I 1304W OPERABLE IADIOS I S 217 217 8118 ACTIVE 1DA REACTOR OPERABLE N/R ENCCLOSURE 3 1 100202 DC REACTOR ENCLOSURE 250V CC MOTOR E-3, Sht 2 304E OPERABLE 19D105 1 S CONTROL CENTER 10-0202 ZB 217 217 8218 ACTIVE 1D0-1 REACTOR OPERABLE NR ENCLOSURE 3 1 10D203 EPS REACTOR ENCLOSURE 250V DC MOTOR E-33, SHT 2 304E OPERABLE 1BDI05 I S CONTROL CENTER 1040203 ZB 217 217 8234 ACTIVE 10-D203 REACTOR OPERABLE N/A ENCLOSURE 1 20 10E209 RCIC RCIC TURBINE BAROMETRIC M-50, Sht 1 108 OPERABLE N/A 1 S CONDENSER 177 177 3109 PASSIVE 10-E209 REACTOR OPERABLE N/A ENCLOSURE 1 20 10F,210 F4PCI HPCI TURBINE BAROMETRIC M-56. S-T 1 109 OPERABLE NIA 1 S CONDENSER 177 177 3336 PASSIVE 10-E210 REACTOR OPERABLE NIA ENCLOSURE 1 21 10E212 RCIC RCIC TUR3INE LUBE OIL COOLER M-5O, Shl 1 108 OPERABLE NIA 1 B 177 177 3120 PASSIVE 10-E212 10S212 REACTOR OPERABLE NIA ENCLOEURE Filter. Unit = 1"or Ur.it = "Common" Sorted By Equip 10 Page 13 Date. 6W5195 Train Unit Line No..1 1338 3 1 8239.4 3117 3305 S 1 11 3306 3337 3 3137 1 3107 3 1100 3 110* 1101 Class Eval Reqd 21 B PASSIVE 30 S ACTIVE 30 ACTIVE 3 S ACTIVE 3 S ACMTE 3 S ACTIVE 3 BR ACTIVE 25 S PASSIVE 3 S ACTIVE 3 S ACTIVE 25 SR ACTIVE 27 S ACTIVE Equip ID PIMS ID I DE213 10-E213 IONAD160 10-NAD160 IONBD160 10-NO0150 1OP203 10-P203 iOP204 ID-PZ04 1OP204 10-P204 IDP215 1043'215 l0S201 10-6201 10S2111 10-S211 lDS212 1D-S212 IDS224 10-S224 106299 10-S299 0 UMERICK GENERAING STATION IPEEE PROJECT UNITI & COMMON SUCCESS PATH COMPONENT LIST (SPCL)System Equip Dascription Drawing No. Room No.Room Elev Notes ROB Mother Comp Building HPCi HPCI TURBINE LUBE OIL COOLER M.56. SHT 1 109 177 10S211 REACTOR ENCLOSURE EPS STATIC INVERTER tAD1O E-32, SlT 1 452 BYPASSI[SOLATION SW 254 CONTROL STRUClMRE EPS STATIC INVERTER 1BD160 E-32. SHT 1 452 BYPASSIISOLATION SW 254 CONTROL SrRuC'URE RCIC RCLC PUMP M-50. Sht 1 108 177 REACTOR ENCLOSURE HPCI HPCI BOOSTER PUMP 10P204 M-5E. SHT 1 109 177 REACTOR ENCLOSURE HPCI HPCl BOOSTER PUMP M-.56, SHT 1 109 177 REACTOR ENCLOSURE HPCI HPCI VACUUM TANK CONDENSATE M-56, SIlT 1 109 PUMP 177 lOE210 REACTOR ENCLOSURE NUCLEAR BOILER REACTOR VESSEL 72 FT-GIN HEIGTH, M-1 400 22FT-61N DIA 237 REACTOR ENCLOSURE HPCI HPC1 TURBINE M-56. SW 1 109 177 REACTOR ENCLOSURE RCIC RCIC TURBINE M-50, St 1 108 177 REACTOR ENCLOSURE CR0 CRD HYD CONTROL UNIT (rYP OF 185) M-47. SHT 1 402 253 28 REACTOR ENCLOSURE CRD CONTROL ROD DRIVE (TYP OF 185) M-47. SHT 1 400 237 REACTOR ENCLOSURE II Norm state Equip Elev Ra'd Stats OPERABLE 177 OPERABLE OPERABLE 254 OPERABLE OPERA.LE 254 OPERABLE OFF 177 ON OFF 177 OPERABLE OFF 177 ON OFF 177 OPERABLE OPERABLE 352 OPERABLE OFF 177 OPERABLE OPERABLE 177 OPERABLE OPERABLE 253 OPERABLE OPERABLE 253 OPERABLE 0 Document No.

Revbsion I Motve power Support System Supp Sys dag Contr power N/A N1A 1ADIS1 NIA 1RD160 NIA NIR NIR N/A N/A WA WA 1EBD202 1812202 NWA WA WA NIA NIR NIR NIR N/R NMR NMI Filter Unit= "P"or Unit -Common" Sorted By Equip IDB Al~ Z

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Page 14 3 ae: G6/9W95 ,,G Train Unit 0* 31 ,.-. 1105 3 9176 3 j3 1 9177 3 9178 3 1 3 9181 9183 3 I* 9184 3 1 913 3 1 914 Class Eval Req'd Funcrfon 17 B ACTIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE 18 S PASSIVE R WA PASSIVE R WA PASSIVE R NWA PASSIVE R WA PASSIVE R WA PASSIVE 18 BR ACTIVE 18 BR ACTIVE Equip to PIMI5 t 10S400 10-S400 IOTS-053 106T"-53 I OT&-054 10-TO-054 10T"55S 10-TB-05 l0OT-05E 10-T5458 10TH-401 10-TS-401 IOT8-402 1O-T8-402 I OTO-405 10-T8-405 1078-406 10-TB-408 IOTB-407 10-TB-407 IOT13-HPCIEGM 10-TB-KPCIEGM 1OTB-H-PCrrERM 10-TB-HPCITERM System Noles LPRM 30 N/A WA N/A NIA WA WA N/A N/A IVA W/A N/A Equip Description ROe Mother Comp LPRM DETECTOR ASS 10S201 RACK/PANEL (TERMIN RACK/PANEL (TERMiN RACK/PANEL (TERMIN RACK/PANEL (TERMIN RACK/PANEL (TERMIN RACK/PANEL (TERMIN RACKIPANEL CiERMIN RACK/PANEL (TERMIl RACK/PANEL (TERMIN INSTRUMENT PANEL 10S211 INSTRUMENT PANEL* 0 UMERICK GENERAliNG STATION IPEEE PROJECT Document No. 0067-01.0 4 UNITI & COMMON AllemimntA SUCCESS PATH COMPONENT UST (SPCL) Revisli I Drawing No. Room No. Norm state Motive power Support System Supp Sys dwg Room Elev Equip Elev Building Req'd State Contrpower Y E-120 40O OPERABLE NfA 237 253 REACTOR OPERABLE 1AY18i ,1BYI185 ENCLOSURE IOY101 AL BOX) WA 311A OPERABLE NIA 217 DIESEL GENERATOR OPERABLE WA AL BOX) IVA 3f1B OPERABLE WA 217GENERATOR OPERABLE NIA AL BOX) IVA 311C OPERABLE WA 217 OIE GENERATOR OPEP-ABLF WA AL BOX) NIA 311D OPERABLE N/A 217 DIESEL GENEIRATOR OPERABLE WA AL BOX) IVA 400 OPERABLE N/A 237 REACTOR OPERABLE NWA ENCLOSUFE AL BOX) MIA 400 OPERABLE WA 237 REACTOR OPERABLE WA ENCLOSURE AL BOX) NIA 400 OPERABLE WA 237 REACTOR OPERABLE NWA ENCLOSURE AL BOX) N/A 400 OPERABLE WA 237 REACTOR OPERABLE WA ENCLOSURE BOX) NIA 400 OPERABLE NIA 237 REACTOR OPERABLE NIA ENCLOSURE WA 109 OPERABLE WA 177 REACTOR OPERABLE N/A ENCLOSURE NIA 109 OPERABLE NIA 177 REACTOR OPERABLE WA ENCLOSURE 106211 Filler: Unit ="1 or Unit = "Common" Sorted By Equip ID 77 0G It Page 15 Dale: 61995 Revision I UMERICK GENERAflNG STAIION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Train Class Equip ID System Equip Description Drawing No. Room No. Norm state Motive power Support System Supp Sys dwg Unit Eval Req'd Room Elev Equip Elov Line No. Funciion PIMS to Notes ROB Mother Camp Building Reqd Stale Conir power 3 Is 1OTB-RCICEGM N/A INSTRUMENT PANIEL M/A 108 OPERABLE WA I SR 177 9143 ACTIVE 10-TB-RCICEGM 105212 REACTOR OPERABLE N/A ENCLOSURE 3 Is 1OTB-RCICTERM MA INSTRUMENT PANEL N/A 108 OPERABLE N/A I BR 177 9185 ACTIVE 10-TB.RCICTERM 105212 REACTOR OPERABLE N/A ENCLOSURE 3 2 OXI06 120V AC DIVISION I4KV SWITCHGEAR ROOM E-30, Sht 3 435 OPERABLE 108211 1 S 120VVAC INSTRUMENT PANEL 1OY1 01 239 239 8131 ACTIVE 10-X10i CONTROL OPERABLE MR STRUCTUJRE 3 2 10X107 120V AC DIV 14KV SWGR RM 120V AC IN STR E-30, Sht3 433 OPERABLE 10B212 I S PANEL 10YI02XFMR 239 239 8228 ACTIVE 10-X107 CONTROL OPERABLE N/R STRUCTURE 3 2 1OX108 120VAC DIVISION II 4KV SWITCHGGEAR ROOM E-30. Sht 3 434 OPERABLE 108223 1 120VAC INSTRUMENT PANEL 10Y103 238 239 1 S XFMR 8721 ACTIVE 10-X1oa CONTROL OPERABLE NMR STRUCTURE 3 2 1OX109 120V AC DIVISION IV 4KV SWTCHGEAR ROOM E-30, ShI 3 432 OPERABLE 108224 1 S 120V AC INSTRUMENT PANEL 239 239 8321 ACTIVE 110-)109 CONTROL OPERABLE NMR 8TRUCTURE 3 2 1OX110 120V AC TURB AREA 120V AC INSTR PNL E-30, Sht 1 438 OPERABLE 108129 1 MA 10Y105XFMR 239 239 8134 ACTIVE I0-XI10 3S TURBINE BUILDING OPERABLE N/R ENCLOSURE 3 2 10X182 120V AC A MAIN CONTROL ROOM STRUCTURE E-26. Sht I s19W OPERABLE 00B131 I S HVAC 120VAC DISTRIBUTION PANEL 304 304 8723 ACTIVE 10-Xle2 CONTROL. OPERABLE NR STRUCTURE 3 2 10X183 120V AC B MAIN CONTROL ROOM STRUCTURE E-26. Sht 1 619 OPERABLE 006132 1 S HVAC 120V AC DIST. PANEL XFMR 304 304 8322 ACTIVE 10-X183 CONTROL OPERABLE NIR STRUCTURE 3 2 10X201 450V 4KV -480V TRANSFORMER E-2B 602W OPERABLE 10Al1S I S 313 8108 ACTIVE D114_XFMR REACTOR OPERABLE N/R ENCLOSURE 3 2 I0X202 4KV 4KV -480V SAFEGUARD LOAD CENTER E-28 602E OPERABLE 10A116 I S TRANSFORMER 313 028 ACTIVE D124_XFMR REACTOR OPERABLE NMR ENCLOSURE 3 2 10X203 4KV 41V -480V TRANSFORMER E-28 402 OPERABLE 1A1117 1 S 253 8707 ACTIVE 0134_XFMR REACTOR OPERABLE NJR ENCLOSURE Filter~ Unit "1"or Unit= "Commonf Sowteday Equip ID Dr oC j.1-"A- V Popg 16 Date: 6,W95 0 Document No.

Afladunenl A Revision I lIMERIK GENERATING STATION IPEEE PROJECT UNIT I a COMMON SUCCESS PATH COMPONENT UST (SPCL)Train Class Equp ID System Equip Desziptimi Dtawttg No. Room No. Norm sCate Mobve power Support Syste- Supp Sys dkvg unit Eval Req'd Room Elov Equip Elev Linte No. Function POSS ID Notes ROB Mother Camp Beltlng Rec'd State Cont power 3 2 10X204 4KV 4KV -480V TRANSFORMER E-28 506E OPERABLE 10A118 1 S 283 8307 ACTIVE D144XFMR REACTOR OPERABLE N/R ENCLOSURE 3 2 10X207 EPS REAC AREA 120V INSTR PNL 1OY201 E-30, SHiT 1 506E OPERABLE 10B223 I S XFMR 283 283 8325 ACTIVE 10-X207 REACTOR OPERABLE N/A ENCLOSURE 3 2 10X281 120V AC A REACTOR ENCLOSURE HVAC 120V AC E-26. Sht 1 619W OPERABLE 10B213 I S DISTRIBUTION PANEL TRANSFORMER 304 304 8138 ACTIVE 10-X281 CONTROL OPERABLE MiR STRUCTURE 3 2 10X282 120V AC B REACTOR ENCLOSURE HVAC 120V AC E-2s, Sht 1 819 OPERABLE 108214 1 S DISTRIBUTION PANEL TRANSFORMER 304 304 8232 ACTIVE 10-X282 CONTROL OPERABLE N/R STRUCTURE 3 12 IOY105 120V AC DIV. I S.F.G.D 120 VAC INST. PANEL E-30. Sht 3 435 ENERGIZED 10211. 1X11OS 1 S 1OY10 SERVICE DISC. 239 239 8132 ACTIVE 10-Y101 CONTROL ENERGIZED WiR STRUCTURE 3 12 10Y102 120V AC DIV. II S.F.G.D. 120 VAC INST. PANEL E-30, Sht3 433 ENERGIZED 101212. 10X107 I S 10Y102 SERVICE DISC. 239 239 8230 ACTIVE 10-Y102 CONTROL ENERGIZED WiR STRUCTURE 3 12 10Y103 120V AC DIV. III S.F.G0D 120 VAC INST. PANEL E-30. Sht 3 434 ENERGIZED 10B223, 10X108 I S IOY103 SERVICE DISC. 239 239 8720 ACTIVE 10-Y103 CONTROL ENERGIZED N/R STRULIOJRE 3 12 10Yt04 120V AC DIV. IV S.F.G.D 120 VAC INST. PANEL E-30, Sht3 432 ENERGIZED 10B224, 10X109 1 S 10Y104 SERVICE DISC. 239 239 5320 ACTIVE 10-Yi14 CONTROL ENERGIZED N/R STRUCTURE 3 12 lOYlos 12OVAC TURBINE ENCLOSURE 120VAC E-30, Sht 1 438 ENERGIZED 10B129, 10Xl10 1 N/A INSTRUMENT PANEL 239 239 8133 ACTIl 1D-Yo05 38 TURBINE BUILDING ENERGIZED N/R ENCLOSURE 3 12 10YI63 120V AC A MAIN CONTROL ROOM STRUCTURE E-26, Shl 1 819W ENERGIZED 006131. 101182 I S HVAC 120VAC DISTRIBUTION PANEL 304 304 8722 ACTIVE 1D-Y183 CONTROL ENERGIZED N/R STRUCTURE 3 12 10Yl64 120V AC B MAIN CON"rROL ROOM STURCTURE E-26. Sht 1 619E ENERGIZED 00B132. 101183 1 S HVAC 120V AC DISTRIBUTION PANEL 304 304 8323 ACTIVE 10-Y164 CONTROL ENERGIZED N/R STRUCTURE 3 12 10Y201 EPS REACTOR ENCLOSURE 120VAC E-30, SHT 1 506E OPERABLE 10)(207 1 S INSTRUMENT P'PMEL 283 283 8324 ACTIVE 10-Y201 REACTOR OPERABLE NMA ENCLOSURE-I..I: Filter Unit ='1"or Unit = "Common" Soned By Equip ID Page 17 Date: 619195 Train Unit Line No.8135 3 8233 4 1 I Common 5570 2 Common 5%44 2 S Common: .Common 1 5569 1 I 1 5533 2 2 1 5639* 2 5652' I Common 5579 45 1 3 3 8113 v UMERICK GENERATING STATION IPEEE PROJECT UNIT 1 & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Document No. 0087.0DU5.O49 M~mA Revision I Class Equip ID System Equip Desciplion Drawing No. Room No. Norm state Moave power Support System Supp Sys dwg Evel Req'd Room EFev Equip Efev Function PIMS ID Notes 12 S ACTIVE 12 S ACTIVE R MIA PASSIVE R WA PASSIVE R NWA PASSIVE R N/A PASSIVE R NIA PASSIVE R NfA PASSIVE R NIA PASSIVE R N/A PASSIVE R WA PASSIVE 13 S ACTIVE 10Y206 10-Y206 10Y207 10-Y207 11 -0033A 011-0033A 11-0033B 011-0133B 11-0052 011-0062 11-O063 011-4063 11-1011 all-loll 11-1012 011-1012 11-1044 011-1044 11-2011 011-2011 12-1009 012-1009 1AID101 1A1I3ATTERY 120VAC 12CV AC ESW ESW ESW ESW ESW ESW ESW ESW RHRSW DC ROB Mother Comp A REACTOR ENCLOSURE HVAC 120V AC E-26, SM 1 DISTRIBUTION PANEL B REACTOR ENCLOSURE HVAC 120VAC E-26. Shi 1 DISTRIBUTION PANEL CONTROL ROOM CHILLER A U/2 SW M-il, Sht 2 LOOP A SUPPLY CHECK VALVE CONTROL RM CHILLER' t U12 SW LOOP M-1 1, Sht 2 B SUPPLY CHECK VALVE SW SUPPLY TO HPCI ROOM COOLERS M-1, Shlt I EMERGENCY SERVICE WATER SUPPLY M-11, Sht5 TO UNIT COOLERS 2AV-208 & 28V-208 NORMAL SW SUPPLY TO PUMP ROOM M-11, Sht 2 COOLER NORMAL SW SL'PPLYTO PUMP ROOM M-1 1. Sht 3 COOLER ESW TO REACTOR ENCLOSURE HTf'S M-11, Shlt 3 NORMAL SWSUPPLYTO PUMP ROOM M-ti-l, Sht4 COOLER ESW'B' RETURN FROM UNWI TECW HX M-12 CK VLV 125V DC BATTERY E-33, Sht I Building 619W 304 CONTROL STRUCTURE 619E 304 CONTROL STRUCTURE 258A 200 CONTROL STRUCTURE 263A 200 CONTROL STRUCTURE 203 201 REACTOR ENCLOSURE 281 201 REACTOR ENCLOSURE NR 207 201 REACTOR ENCLOSURE NR REACTOR ENCLOSURE 284 201 REACTOR ENCLOSURE NR REACTOR ENCLOSURE 436 239 CONTROL STRUCIURE Req'd State ENERGIZED 304 ENERGIZED ENERGIZED 283 ENERGIZED OPERABLE 200 OPERAOLE OPERABLE 200 OPERABLE OPERABLE 201 OPERABLE OPERABLE 201 OPERABLE OPERABLE 201 OPERABLE OPERABLE 201 OPERABLE OPERABLE 201 OPERABLE OPERABLE 2131 OPERABLE OPERABLE 217 OPERABLE OPERABLE 239 OPERABLE Cont power 10B213. 10X281 NIR 105214.10X282 NIR NWA N/A NIA NWA NIA NIA NIA MIA N/A N/A N/A NIA N/A NWA NWA N/A IWA NIA N/R NR Flter. Unit = '1" or Unit = "Common' Sorted By Equip ID

-W, Page Is Date: SWWS V LIMERICK GENERA71NG STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCLI Documentf No. 0067400154=

Att~dhtteWA Ravision 1 Train Class Equip ID System Equip Description Drawing No. Room No. Norm state Motive power Support System Supp Sys dwg Unit Eval Reqd Room Etav Equip Elev Line No. Function PIMS ID Notse ROB Mother Comp Building Rsqd State Contrpower 3 14 IA10103 DC 125V DC BATTERY CHARGER IA1D103 E-33. Sh 1 436 OPERABLE 109211 1 S1E- D114-R-G-36) 239 239 8110 ACTIVE lBCAl CONTROL OPERABLE NIR STRUCIURE 1 32 1A1F211 RHR RHR SUPPRESSION POOL SUCTION M-51, Sm 1 101 OPERABLE N/A 1 S STRAINER 162 181 4100,4700 PASSIVE 1A1F211 REACTOR OPERABLE WA ENCLOSURE 1 32 1A1F575 SOG FUEL OIL FILTER M-20. Sht 3 311A OPERABLE NIA 1 B 217 5101 PASSIVE NWA IAGS01 OIESELGENERATOR OPERABLE WA ENCLOSURE 1 10 1A1K513 FUEL OIL A DIESEL GENERATOR STARTING AIR M-20. Shl 3 311A WA WR I S TRANSFER COMPRESSOR At 217 217 5117 PASSIVE IA1KI13 OIESF-LCEN.RATOR WA NIR ENCLOSURE 1 19 IA1T558 FUEL OIL A DIESEL GENERATOR STARTING AIR M-20, Sht 3 3111A OPERABLE NA 1 S TRANSFER RESERVOIR Al 217 221 5116 PASSIVE IA1TS58 DIESELGENERATOR OPERABLE WA ENCLOSURE 3 13 IA2D101 DC 12SV DC BATTERY E-33. Sht 1 436 OPERABLE NR 1 S 239 239 6112 ACTIVE 1A2 BATTERY CONTROL OPERABLE NR STRUCTURE 3 14 1A20103 DC 125V DC BATTERY CHARGER 1AD103 E-33, Sht 1 436 OPERABLE I0B2¶l I S (1E-A, D114.R-G-37) 239 239 8111 ACTIVE 1BCA2 CONTROL OPERABLE NMR STRUCTURE 1 32 1A2F211 RHR RHR SUPPRESSION POOL SUCTION M-51, Sihtl 101 OPERABLE WZA 1 8 STRAINER 182 181 4101.4701 PASSIVE 1A2F211 REACTOR OPERABLE NA ENCLOSURE 1 32 1A2F575 SDG FUEL OIL FILTER M-20. Sht 3 311A OPERABLE WA 1 B 217 5104 PASSIVE WZA 1AGS01 DIESELGENERATOR OPERABLE NWA ENCLOSURE 1 10 1A2N513 FUEL OIL A DIESEL GENERATOR STARTING AIR M-20, Sht 3 311A WA NIR 1 S TRANSFER COMPRESSOR , 217 217 5119 PASSIVE 1A2K513 DIESELGENERATOR WA NIR ENCLOSURE 1 19 A2""558 FUE'. OIL A DIESEL GENERATOR STARTING AIR M-20, Sht 3 31 1A OPERABLE N/A S TRANSFER RESERVOIR A2 217 217 5118 PASSIVE 1A2T558 DIESE.GENERATOR OPERABLE WA ENCLOSURE 3 18 1AC208 WA UNFT COOLERS CONTROL PANEL N/A 200 OPERABLE N!A 1 S 201 201 9144 PASSIVE IA-C208 REACTOR OPERABLE NWA ENCLOSUREUnit =1" or Unit "Common" Sorted By Equip ID R- , .............. ..... ....: r ..

Pego 19 Dale: 6095 a 3 Train* Unkt G : Line No.3I 8140 o 1 S 9186 2. 3 I 3 9187 1 9145 3 8116g189 3 4 1* 8119 3 1 I! 8117 3 i 1 8114 3 I ¶8114 3 1 8142* 3 81 8121 Class Eval Req'd Function 18 S ACTIVE 18 S PASSIVE 18$PASSIVE 1i S PASSIVE 18 S ACTIVE 18 S PASSIVE 12 S ACTIVE 18 S ACTIVE 12 S AC.TIVE 18 S ACTIVE 14 S ACTIVE 12 S ACTIVE Eqiup ID PIMS ID IAC248 I1A-C248 iAC466 IA-C466S IACS14 IA-C514 IACS63 IA-C583 1ACS6S IA-C66 IAC696 IA-CO96 IAD102 1PPAI 1AD104 1A IADICS IFA 1A0106 1A-OlOG 1AD16D 1A-0160 IAD162 IPPA3 System Notis EPS N/A N/A NZA 4AV N/A DC DC DC DC EPS DC LIMERICK GENERATING STATION IPE!r PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCL)Equip Description Drawtng No. Room No. Norm state Room Elev Equip F6ev ROB Mother Comp Bnlling Rea'd State 1A REACTOR PROTECTION SYSTEM E-32, SHT 1 452 OPERABLE BREAKER PANEL 254 254 CONTROL OPERABLE STRUCTURE DIVISION I ERFOS MULTIPLEXER NEA 533 OPERABLE CABINET 269 269 CONTROL OPERABLE STRUCTURE A DIESEL GENERATOR ELEC INSTR NIA 311A OPERABLE CONTROL BOARD 217 217 DIESELGENERATOR OPERABLE ENCLOSURE DIESEL GENERATOR ENCLOSURE HVAC W/A 3liA OPERABLE CONTROL PANEL 217 225'-8" OIESL GENERATOR OPERABLE ENCLOSURE PANEL A.AFEGUARD SYSTEM E-33. Sht 1 533 OPERABLE VERTICAL BOARD 269 269 CONTROL OPERABLE STRUCTURE IACLG WTR SUPPLY VLV HV-57-110A N/A 533 OPERABLE 259 269 CONTROL OPERABLE STRUCTURE TURBINE ENCLOSURE 125V DC POWER E-33. Sht 1 435 OPERABLE DISTRIBUTION PANEL 1AD102 239 239 CONTROL OPERABLE STRUCTURE 125i250V DO GROUND DETECTION E-33, Sht 1 436 OPERABLE CABINET 1AD1O4 (1E-A SAFEGUARD) 239 239 CONTROL OPERABLE STRUCTURE 1251250V DC FUSE BOX 1AD15 (1E-A) E-33. Shl 1 438 OPERABLE 239 239 CONTROL OPERABLE STRUCTURE 1251250VDC .URRENTTRANSDUCER E-33. Sht 1 435 OPERABLE PANEL 239 239 CONTROL OPERABLE STRUCTURE A RPS & UPS DISTRIBUTION PANEL E-32, SHT 1 452 OPERABLE STATIC INVERTER 254 254 CONTROL OPERABLE STRUCTURE 125V DC PWR DISTRIBUTION PANEL E-33, Sht 1 435 OPERABLE 1A-D162 239 239 CONTROL OPERABLE STRUCTURE Docutmeit No. 0067.091 0114 Attachment A Revision I Motive power support System Supp Sys dwg Cordr power 10NAD160 NfA NIA N/A N/A NIA NIA W/A 1ADIOS EVR N/A N/A 1AD105 NMR lAD105 MR IAlDIDI, NIR IAD105 EVR 100201 W/A IAD105 EVR Filer. Unit "" or Unit "Common* Sorted By Equip ID, -..... ..:.. ... .. ....... .._ .............

7 Page 20 a 3 Date: 6I99J5 0 Docun No. Mo.w0w4sinlM Revision I LIMERICK GENERATING STATION IPEEE PROJECT UNITI & COMMON SUCCESS PATH COMPONENT LIST (SPCL)i Train Class Equip ID System Equip Desciption Drawing No. Room No. Norm state Motive power Support System Supp Sys dwg Unit Eval Req'd Roam Elev Equip Elev o

Line No. Function PIMS ID Notes ROB Mother Comp Building Reqd Slate Contr power" 3 14 iADB EPS A APRM UPS INVERTER (ALTERNATE E-32, SHT 2 542 OPERABLE IAYV60 ,1p FEED:lAY160-03) 289 289' 1CONTROL OPERABLE NIA 8138 CTIVESTRUCTURE 3 12 lADS0I DC DIESEL GENERATOR 125V DC POWER E-33, Sht 1 311A OPERABLE lAD1OS I S DISTRIBUTION PANEL 1AD501 ZA 217 217 DIESELGENERATOR OPRLE N 0120 ACTIVE IPPA2 OPERABLE NIR ENCLOSURE 1 19 IAE205 RHR A RESIDUAL HEAT REMOVAL HEAT M-S1, Sht 2 102 OPERABLE WA RHRSW M-12 1 S EXCHANGER 177 177 4117.4314.4508, PASSIVE 1A-E205 REACTOR OPERABLE WA 4713 ENCLOSURE 1 20 IAE218 ESW A RHR PUMP SEAL COOLER M-I , Sht2 102 OPERABLE NIA I B 177 177 5542 PASSI1E IA-E218 IAP202 REACTOR OPERABLE NIA ENCLOSURE 1 20 1AE220 ESW A RHR PUMP MOTOR OIL COOLER M-11. Sh! 2 102 OPERABLE NIA*'1 1 B177 177 5543 PASSIVE lA-E220 1AP202 REACTOR OPERABLE N/A ENCLOSURE__ 1 20 lAESO6 4KV&DIESELGEN.

A DIESEL GENERATOR I.UBE OIL M-11, Sht I 311A OPERABLE NfA 1 COOLER 217 217 5504 PASSIVE IA-ES06 1AG501 DIESELGENERATOR OPERABLE NWA ENCLOSURE 1 20 IAESO7 41(V&DIESELGEN.

A DIESEL GENERATOR JACKET WATER M-11, Sht 1 31IA OPERABLE N/A I B. HEAT EXCHANGER 217 217* 5505 PASSIVE 1A-EO?7 IAG501 DIESEL GENERATOR OPERABLE N/A ENCLOSURE"- ." 503 20 lAE58 B PASSIVE lA-E58S 4KV &DIESEL GEN. A DIESEL GENERATOR INTERCOOLER M-1 1. Sht I WATER HEAT EXCHANGER DIESEL GEN 1AGESl 31 IA OPERABLE N/A 217 217 DIESELGENERATOR OPERABLE N/A ENCLOSURE 1 32 IAF574 FUEL OIL A DIESEL ENGINE INLET AIR FILTER M-20. Sh! 3 311A OPERABlE N/A 0GEV M 51 Sk 1 1 S TRANSFER 217 217 51l3 PASSIVE IA-F574 DIESELGENERATOR OPERABLE N/A ENCLOSURE I 1s 1AG501 4KV SYS & DIESEL DIESEL GENERATOR ENGINE M-20. Sht 3 311A OPERABLE N/R ESW.OGEV M-11. Sh 1; "-S1, I SR GEN 217 217ACTIVE IA-GS01-DR DIESF..LGOENERATOR OPERABLE 1AD1O2, 1AD50i ENCLOTSURE 3 18 IAGS02 N/A D0I DIESEL GENERATOR POT TRANS N/A 311A OPERABLE NIA I S AND EXCITATION EQUIPMENT 217 217 9190 PASSIVE 1A-G502 DIESELGENERATOR OPERABLE N/A ENCLOSURE 3 25 1AP201 NUCLEAR BOILER 1A RECIRC PUMP M-43 400 OPERABLE N/I 1 3138 S PASSIVE 1A-P201 237 253 REACTOR N/A N/IR ENCLOSURE Filter. Unit = w""or Unit = CComman" Sorted By Equip a)

I~r lb abC'In 4 A I I A ii ft I,:4 I-. A Peg. 21 Date. 5W9/95 UMERICK GENERATING STATION IPEEE PROJECT UNIT I &COMMON SUCCESS PATH COMPONENT LIST (SPCL)Doaument No. 005740015430M ARmision A Revision I Train Class Equip ID System Equip Desrlpflon Drawing No. Room No. Norm state Motive power Support System Supp Sys flg Unhi Eval Rectd Room E0ev Equip Mlev Line No. Function PimS ID Notes ROB Mother Comp Building Req'd State Contr power 1 4 1AP202 RHR IA RESIDUAL HEAT REMOVAL (RHR) M-51, Slt 1 102 OFF 10Al15 ESW, REV M-11; M-76 1 SR PUMP 177 177 4104, 4305,4704 ACTIVE IA-P202 REACTOR ON 10Al5. 1AD102 ENCLOSURE 1 4 AP14 FUELOIL A DIESEL GENERATOR DIESEL OIL M-20, Sht 3 YARD OFF 10B515 I SR TRANSFER TRANSFER PUMP N/A 20B 5109 ACTIVE 1A-P514 YARD ON 108515 1 3 IAPS37 FUEL OIL STORAGE A DIESEL GENERATOR FUEL OIL PUMP M-20, Sit 3 311A OPERABLE N/R 1 6 217 5102 ACTIVE IA-PS37 IAG501 DIESEL GENERATOR OPERABLE N/R ENCLOSURE 1 3 lAP538 FUEL OIL A DIESEL GENERATOR AUXILIARY FUEL M-20, Shl 3 311A OPERABLE 1ADS0I I BR TRANSFER OIL PUMP 217 5105 ACTIVE IA-PESM 6 lAGSO DIESEL GENERATOR OPERABLE NIR ENCLOSURE 1 20 1ASS75 FUEL OIL A DIESEL GENERATOR EXHAUST M-20. Sht 3 311A OPERABLE N/A SAS TRANSFER SILENCER 217 217 114 PASSIVE IA-$575 -DIESEL GENERATOR OPERABLE NIA ENCLOSURE 3 is 1AS921 N/A MAIN STEAM RELIEF VALVES POSITION N/A 402W OPERABLE WIA I a TRANSMIT'ERS'PRE-AMP 253 253 914S PASSIVE IA-$921 REACTOR OPERABLE N/A ENCLOSURE 1 22 1AT527 FUEL OIL A DIESEL GENERATOR DIESEL OIL M-20. Slit 3 YARD OPERABLE N/A 1 8 TRANSFER STORAGE TANK N/A 198 5110 PASSIVE 1A-T527 YARD OPERABLE NIA 1 is IATS28 FUEL OIL A DIESEL GENERATOR DAYTANK M-2. Shlt 3 312A OPERABLE NIA I a TRANSFER 217 217 5107 PASSIVE 1A-T528 DIESEL GENERATOR OPERABLE NIA 1 20 IATS31 FUEL OIL A DIESEL GENERATOR DIRTY DIESEL M-20, Sht 3 311A OPERABLE NIA 1 a TRANSFER FUEL DRAIN TANK 217 216 5111 PASSIVE 1A-TS31 6 lAG501 0t:6F-L GENERATOR OPERABLE WA 1 20 IAT564 FUEL OIL A DIESEL GENERATOR JACKET WATER M-20, Stu3 311A OPERABLE N/A 1 a TRANSFER EXPANSION TANK 217 234 5112 PASSIVE 1A-T584 DI27ELGENERATOR OPERABLE N2A ENCLOSURE 3 lB IATB-AGS0I N/A RACKJPANEL (TERMINAL BOX) N/A 311A OPERABLE NIA 1 217 9223 PASSIVE 1A-TB-AGS01 IAGS01 "IESEL .GENERATOR OPERABLE NIA ENCLOSURE 3 18 IATB-BG-5i N/A RACK/PANEL (TERMINAL BOX) N/A 3118 OPERABLE NIA 1 i 217 9224 PASSIVE 1A-TB-BG501 1BGS01 DIESEL GIEERATOR OPERABLE N/A E.NCLOSUREUnit =l "or Unit = "Common"r Sorted By ID

-o Page 22 LIMERICK GENERATING STATION IPEEE PROJECT Document No. 0067.0008.6O

o ,-oUNIT I & COMMON Alachm~tAM

= Date: SIMReisin5-e e- SUCCESS PATH COMPONENT UST (SPCL)_ Trin Clasi Equip ID System Equip Dosuiptio Drawmi No. Room No. Norm stats Motive power Suppul System Supp Sys dwg 0 Uni Eval Reqd Room Elev Equip Elev In Line No. Fundlon PIMS ID Notes ROB Mother Camp Building Req'd State Conr powm 3 l8 1ATB-CGS01 NIA RACK/PANEL (TERMINAL BOX) N/A 311C OPERABLE NIA 1 8 217 9225 PASSIVE 1A-TB-CGSI iCG50l DIESEL GENERATOR OPERABLE NIA ENCLOSURE 3 is IATB-OG501 WA RACK/PANEL (TERMINAL BOX) N/A 311D OPERABLE N/A 1 B 217 9226 PASSIVE IA-TB-DG501 1DG501 DIESEL GENERATOR OPERABLE NWA ENCLOSURE 3 R 1ATR001 NIA RACK/PANEL N/A NR OPERABLE MIA 1 WA* 9192 PASSIVE IA-T"OI1 OPERABLE WA 3 R 1ATB079 N/A RACK/PANEL N/A NR OPERABLE NIA I 1 NWA.9193 PASSIVE 1A-TB079 OPERABLE NIA 3 R IATBO81 WA RACK/PANEL N/A NR OPERABLE WA r-.,.. 1 N/A 9194 PASSIVE 1A-TBDB1 OPERABLE N/A 3 R IATBO94 NWA TERMINAL BOX -MTD ON WALL NEAR NWA 309W OPERABLE N/A WEST END 1 NIA 217 9197 PASSIVE 1A-TB094 REACTOR OPERABLE NIA ENCLOSURE 3 R 1ATB095 NIA RAt.WKPANEL N/A NR OPERA/I3 F NIA I N/A 9195 PASSIVE 1A-TB095 OPERABLE WIA 3 R 1ATU096 NWA RACK/PANEL NWA NR OPERABLE WA I .M1 IA 9196 PASSIVE 1A-TB096 OPERABLE N/A 3 R 1AT6122 NWA RACK/PANEL N/A NR OPERABLE WIA I NIA 9198 PASSIVE 1A-TO122 OPERABLE NWA 3 18 IATB123 NIA RACK/PANEL (TERMINAL BOX) N/A 108 OPERABLE N/A 1 S 177 177 9199 PASSIVE IA-TB123 REACTOR OPERABLE NIA ENCLOSURE 3 R IATB124 NIA RACKPANEL NIA NR OPERABLE N/A I N/A 9200 PASSIVE 1A-TB124 OPERABLE NWA 3 R IATB125 NIA RACK/PANEL NfA NR OPERABLE WA 1 WNA 9201 PASSIVE IA-TB125 OPERABLE WA Filter. Unit = "Ior Unit ="Common' Soiled By Equip ID Po Pg23 Date. 61"9s* Train Class' iv-Unit Eval Req'dLine No. Function o 3 R a. I N/A 1NI 9202 PASSIVE i~ 1 SR 5554 ACTIVE 2: 1 SR 5634 ACTIVE' I a' I SR S.- 5534 ACTIVE¶ 8 a.3 12;- 1 5R 5139 ACTIVE: 3 12 8137 NTA.B137 ACTIVE 3 13: I S" -213 ACTIVE 3 14 8210 ACTIVE 2 32 4200,4400,4800 PASSIVE 2 32 5201 PASSIVE 0 LUERICK GENERATING STATION IPEEE PROJECT UNITI &COMMON SUCCESS PATH COMPONENT UST (SPCL)Document No.

A Rnoom I Equip ID System Equip Desciption Drawing No. Room No. Norm state Motive power Support System 5upp Sys dwg Room Elev Equip Flev PIMS ID IATBl26 1A-TB125 IAV208 lA-V20D IAV209 1A-V209 IAV210 IA-V210 1AV211 IA-V21 1 IAV512 IA-V512 IAY16O IA-YI60 IAY185 IA-YISS 1B10101 IBIRATrERY 1810103 1CBI'BIF211 IBIF211 Notes ROB Mother Camp N/A RACK/PANEL N/A REACTOR ENCL RCIC PUMP & TURBINE ROOM UNIT M-1 1, Sht 2 HVAC & SGTS COOLERA REACTOR ENCL HPCI PUMP & TURBINE ROOM UNIT M-11, Shl 2 HVAC & SGTS COOLER A REACTOR ENCL A & C RHR PUMP ROOM UNIT COOLER A M-Il. Sit 2 HVAC & SGTS REACTOR ENCL A CORE SPRAY PUMP ROOM UNIT M-11, Sh12 IVAC & SGTS COOLERA MISC. A DIESEL GENERATOR VENTILATION M-81, Silt STRUCTURES-AIR EXHAUST FAN A XVAC EPS ARPS & UPS 120VAC DISTRIBUTION E-32, SHT 1 PANEL (ALT FEED.5.2-40104

&EPS A AVERAGE POWER RATE MONITOR E-32, SHT 2 UPS 120VAC DISTRIBUTION PANEL 36 DC 125V DC BATTERY E-33, ShIt2 DC 125V DC BATTERYCCHARGER 181DI03 E-33. Sht 2 (1E-8)RHR RHR SUPPRESSION POOL SUCTION M-51, Slh 3 STRAINER Building NR 108 190 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 102 191 REACTOR ENCLOSURE 110 190 REACTOR ENCLOSURE 311A 217 DIESEL GENERATOR ENCLOSURE 542 289 CONTROL STRUCTURE 542 289 CONTROL STFIUC1U.RE 425 239 CONTROL STRUCTURE 425 239 CONTROL STRUCTURE 101 182 REACTOR ENCLOSURE Retd Slate OPERABLE OPERABLE OFF 190 OPERABLE OFF 177 OPERABLE OFF 191 OPERABLE N/A 190 N/A OFF 217 OPERABLE OPERABLE 289 OPERABLE OPERABLE 289 OPERABLE OPERABLE 239 OPERABLE OPERABLE 239 OPERABLE OPERABLE 161 OPERABLE Conyr power NIA N/A 100211 106211 108212 103212 108211 108211 N/A NIA 105515 10B515, ioYi01 1AD160 N/A lADIE5 N/A NWR NMR 100212 IfR N/A N/A 1BIF675 SDG FUEL OIL FILTER M-20, Sht4 3118 OPERABLE N/A 217 N/A 6 1BG501 [IESB. GENERATOR OPERABLE N/A ENCLOSURE Filer Unit= "1"or Unit = "Common" Sorted By Equip ID Page 24 LIMERICK GENERATING 8TATION IPEEE PROJECT la3 5UNITI & COMMON Xo M Date:" 6/9/95 SUCCESS PATH COMPONENT LIST (SPOL)Train Class Equip I0 System Equip Description Drawing No. Room No.Unlt Eval Reqd Room Elav 5

Line No. FuncEion PIMS ID Notes ROB Moiher Comp Building 2 10 11IK513 FUEL OIL B DIESEL GENERATOR STARTING AIR M-20, Sht 4 3118 S TRANSFER COMPRESSOR B1 217 S217 PASSIVE 1810513 ENCSEL GEN ENCLOSUR 2 is 11TS5R FUEL OIL B DIESEL GENERATOR STARTING AIR M-20, Sht 4 311B STRANSFER RESERVOIR I 217 J 216 PASSIVE ENCLOSURE 3 13 1820101 DC 125V DC BATTERY E-33, Sht 2 425 I S 239 8212 ACTIVE 102LBATTERY CONTROL STRUCTURE 3 14 182D103 DC 125V DC BATTERY CHARGER 1120103 E-33. Sht 2 425 1 S (1E-B) 239 I m I11 ACTIVE 19C92 CONTROL" ... STRUCTURE: " 2 32 182F211 RH4R RHR SUPPRESSION POOL SUCTION M.S1. Slt3 101 1 S STRAINER 182'i 4201,.4401,4801 PASSIVE 132F211 REACTOR 2 32 1B2F575 SDG FUEL OIL FILTER M-20, Slit 4 3116 I a 217 6204 PASSIVE WA S 191350t DIESEL GENER.ENCLOSURE 2 10 182K513 FUEL OIL B DIESEL GENERATOR STARTING AIR M-20. Sh14 311B 1 $ TRANSFER COMPRESSOR 82 217 5219PASIVE IBZS13DIESEL GENERA 5219 PASSIVE 102K(513 IENCLOSURE 2 1' E82T558 FUEL OIL S DIESEL GENERATOR STARTING AIR M-0J. Sht 4 3118 I TRANSFER RESERVOIR 82 217 5218 PASSIVE 1621'558 OISSELGENSR ENCLOSURE , 3 18 1BC208 N/A UNIT COOLERS CONTROL PANEL N/A 207 S 1S 201 9147 PASSIVE 18-C208 REACTOR 9.ENCLOSURE 3 18, 18C248 EPS 11 REACTOR PROTECTION SYSTEM E-32, SHT 1 452! 1 SBREAKER PANEL 254 1 8238 ACTIVE 18-C248 CONTROL STRUCTURE is3 l1 1BC467 NWA DMISION I1 ERFOS MULTIPLEXER NWA 533 , S CABINET 269 9203 PASSIVE 1B-0457 CONTROL STRUCTURE 3 1 1EC514 WA B DIESEL GENERATOR ELEC INSTR N/A 3118 1.18-0514CONTROL BOARD 217 9204 PASSIVE 15-C514 DESEL GENERA ENCLOSURE Fitter Unit = 1 or Unit = "Common" Soied By Equip ID S.*~--... Norm satle Equip Elev Reqd Slate WA 217 kTOR WA OPERABLE 217 ATOR OPERABLE OPERABLE 239 OPERABLE OPERABLE 239 OPERABLE OPERABLE 181 OPERABLE OPERABLE LTOR OPERABLE N/A 217 XOR NWA OPERABLE 217 JOR OPERABLE OPERABLE 201 OPERABLE OPERABLE 254 OPERABLE OPERABLE 269 OPERABLE OPERABLE 217 CTOR OPERABLE Motive power Contr power NIR NIR NIA WA NMR NIR 108212 NIR WA NWA N/A NZA NIR NMR N/A IVA N/A WA 1ONBD160 N/A NIA WA WA WA AfsdmwA A Revision I Support SYsleM SulppSys dwg

04 oC~(DCD= CO C Page 25 Date: 61995 UMERICK GENERATING STATION IPEEE PROJECT Um"r I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Dooumert NO. ow0WF400C8 Revision I Train Class Equip ID System Equip Description Drawing No Room No Norm Sote Motive power Support System Supp Sys dwg Unit Eve] Reqfd Room Elev Equip Elav Line No. Rinction PIMS ID Notes ROB Mother Comp Building Raq'd State Crnir power 3 18 180C563 NZA DIESEL GENERATOR ENCLOSURE HVAC N/A 311B OPERABLE N/A 1 S CONTROL PANEL 217 225'.8" 9148 PASSIVE iB-C563 OESL GENERATOR OPERABLE N/A ENCLOSURE 3 18 180661 4KV PANEL B-SAFEGUARD SYSTEM E-33, Stu 2 533 OPERABLE 180105 S 21 S VERTICAL BOARD 269 269 1"" 216 ACTIVE 8-661 CONTROL OPERABLE N/R 8TRUCTURE 3 is 10C667 NIA INSTRUMENT PANEL N/A 533 OPERABLE N/A 1 S 269 9149 PASSIVE 18-0667 CONTROL OPERABLE N/A STRUC1URI!

3 12 1D0102 DC TURBINE ENCLOSURE 12.cV DC POWER E-33, Sht 2 452 OPERABLE 1BDI05 1 S DISTRIBUTION PANEL 160102 7% 254 254 8219 ACTIVE iPPB1 CONTROL OPERABLE N/R STRUCTURE 3 is 1BD104 DC 125/2SV DC GROUND DETECTION E-33. Sht 2 425 OPERABLE 180105 CABINET 1BD104 (IE-B SAFEGUARD)

I ! S *239 239 S 8217 ACTIVE isCONTROL OPERABLE NIR 8217 ACTIVEURE 3 12 180105 DC 125'250V DC FUSE BOX 1BD105 (1E-B) E-33, Std 2 425 OPERABLE IBID101t.8214 S 239 239.A. 8214 ACTIVE FB CONTROL OPERABLE NIR*USTURE 3 18 18D106 Dc 125/250V DC CURRENTTRANSDUCER E-33, Slt 2 425 OPERABLE 100105 1 5 PANEL 239 239 8215 ACTIVE IB-D105 CONTROL OPERABLE NR STRUCTURE 3 14 100160 EPS B RPS & UPS DISTRIBUTION PANEL E-32, SHT 1 452 OPERABLE 100203 1 S STATIC INVERTER 254 254 8240 ACTIVE 18.D160 CONTROL OPERABLE N/A STRUCTURE 3 12 10D162 DC 12-VDC DISTRIBUTION PANEL 1i.0162 E-33. ShI 2 425 OPERABLE 100105 I S 239 239 8221 ACTIVE iPPB3 CONTROL OPERABLE WR.1/2 KSTRUCTURE 1 3 14 18D185 EPS B ARPM UPS INVERTER (ALTERNATE E-32, SHT2 542 OPERABLE I1Y160 1 NIA FFED. 18Y160.C3) 289 289 23ACIE B138 6COiTO OPERABLE NIA* 23 ACTV 1,B.065 35N,! STRUCTURE 3 12 18D501 DC 125VD0C DISTRIBUTION PANEL 1B-D501 E-33. Sht 2 3110 OPERABLE 1BD105.1 S 217 217 08220 ACTIVE PP2 DIESEL GENERATOR OPERABLE N/R S 80TPENCLOSURE 2 19 1BE205 RHR B RESIDUAL HEAT REMOVAL HEAT M-51. Sht 4 103 OPERABLE N/A RHRSW M.12 1 EXCHANGER 177 177 4216.4416, 4607. PASSIVE 10-E205 REACTOR OPERABLE N/A 4816 ENCLOSURE Flteer Unit = "1 or Unit = "Common" Sortod By Equip ID Gi)OW M1 st EnU Page 26 Dale: Saw W UIMERICK GENERATING STATION IPEEE PROJECT UNIT 1 & COMMON SUCCES3 PATH COMPONENT LST (SPCL)'F Docmfit No. O170001S~OO Alladu tutA Revision I Train Class Equip ID System Equip Descriptin Drawing No. Room No. Norno state Motive wer Support Syseem Supp Sys dw9 Unit Evat Req'd Room Elev Equip Elav Una No. Function PIMS ID Notes ROB Mother Comp Building Reld State Corlr power 2 20 1B218 ESW B RHR PUMP SEAL COOLER M-11. Sht3 103 OPERABLE NIA 1 B 177 177 5663 PASSIVE 1B-E218 2 1 5664 2 5619 2 1 5620 2 1 5621 2 1 5213 2 1 5200 3 1 9206 3 1 3139 20 B PASSIVE 20 B PASSIVE 20 B PASSIVE 20 B PASSIVE 32 S PASSIVE is SR ACTIVE 18 S PASSIVE 25 S PASSIVE 1BE220 18-6220 196506 IB-ESOS 1BE507 18-ES07 165586 1B-E58S 19F574 iB-FS74 IBG501 11-0-G1OI-R 1BG502 1B-0502 19P2otI 1 B-P201 6 1BP202 5SW B RHR PUMP MOTOR OIL COOLER M-11, Sht 3 6 1BP202 4KV & DIESEL GEN B DIESEL GENERATOR LURE OIL M-11. Sht 1 COOLER IBG501 4KV & DIESEL GEN 8 DIESEL GENERATOR JACKET WATER M-11, Sht 1 HEAT EXCHANGER 1BG501 4KV&DIESELGEN B DIESEL GENERATOR INTERCOOLER M-11, Sht WATER HEAT EXCHANGER D22 DIESEL 1BG501 FUEL OIL B DIESEL ENGINE INLETAIR FILTER M-20. Shit 4 TRANSFER 4 KV SYS & DIESEL D1ESEL GENERATOR ENGINE M-20. Sht 4 GEN NIA 012 DIESEL GENERATOR POT TRANS N/A AND EXCITATION EQUIPMENT NUCLEAR BOILER 1B RECIRC PUMP M-43 RHR 16 RESIDUAL HEAT REMOVAL (RHR) M-51, Sht 3 PUMP FUEL OIL B DIESEL GENERATOR DIESEL OIL M-20. Slht 4 TRANSFER TRANSFER PUMP FUEL OIL STORAGE B DIESEL GENERATOR FUEL OIL PUMP M-20. Sht 4 6 1BG531 103 OPERABLE 177 177 REACTOR OPERABLE ENCLOSURE 3116 OPERABLE 217 217 DIESEL GENERATOR ENCLOSURE 311B OPERABLE 217 217 DIESELGENERATOR OPERABLE ENCLOSURE 311B OPERABLE 217 217 DIESEL GENERATOR OPERABLE ENCLOSURE 311B OPERABLE 217 217 DIESFIL GENERATOR OPERABLE ENCLOSURE 311B OPERABLE 217 217 lESEL GENERATOR OPERABLE ENCLOSURE 311B OPERABLE 217 217 DIESEL GENVF.ATOR OPERABLE ENCLOSURE 400 OPERABLE 237 253 REACTOR N/A ENCLOSURE REACTOR OPERABLE WA ENCLOSURE WA WA N/A NIA N/A NIA N/A N/A NIA NIA NIR IBD1C2.IBDO51 N/A N/A N/R N/R 0GEV ESW, DGEV M-8, S~tt i M-1 1. Sh. 11; M-81.2 4 16P202 I SR 4203.4403, 4803 ACTIVE 1B-P202 2 4 IBPS14 I SR 5209 ACTIVE 1B-P514 2 3 IBPS37 1 8 5202 ACTIVE 1B-P537 103 OFF 10AIIS ESW, REV M-11: M-76 177 177 REACTOR ON 1IAl16, 180102 ENCLOSURE YARD OPERABLE 103516 N/A 205 YARD OPERABLE 103516 311B OPERABLE NIR 217 DIESELGNERATOR OPERABLE N/R ENCLOSIURE Filter Unite 1 or UnIt: "Common' Sorted By Equip ID: .. : .... .......

Page 27* Date: 61110<.)Lime No.2 520 2 6105 2 2 6107 2 5214 9150 2 510 2 52: 207 2 5211 2 1 5212 3* 1* 22 3 I 9228@Class Eval Recd Function 3 BR ACTIVE 19 S PASSIVE 19 S PASSIVE 19 S PASSIVE 20 S PASSIVE 18 S PASSIVE 22 S PASSIVE 19$PASSIVE 20 B PASSIVE 20 S PASSIVE 18 B PASSIVE 1P B PASSIVE EWuAp ID PUNS ID 1BP531 1B-P538 1BS252-1 18-252-1 1BS252-2 1B-S252-2 1BS252-3 1B-S252-3 1BS"75 1B-5575 1BS921 I ST527 18-TS27 1BT528 IB-T528 1BT531 19-T531 1 BTS54 I B-T564 1 BTB-AGSOI I B-TB-AGS01 I BTB-BGSOI 1B-T'T-BGSOI System Noles FUEL OIL TRANSFER 6 PCIG PCIG PCIG FUEL OiL TRANSFER NIA FUEL OIL TRANSFER FUEL OIL TRANSFER FUEL OIL TRANSFER 6 FUEL OIL TRANSFER NIA N/A UMERICK GENERATING STATION IPSEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCL)Equip Description Drawing No, Room No. Norm state Room Elev Equip Elev ROB Mother Comp Building Recad State B DIESEL GENERATOR AUXILIARY FUEL M-20. S314 311B OPERABLE OIL PUMP 217 217 15G501 DIESEL GENERATOR OPERABLE ENCLOSURE B PCIGIADS NITROGEN BOTTLES M-59. SHT I 304E OPERABLE 217 217 REACTOR OPERABLE ENCLOSURE B PCIG/ADS NITROGEN BOTTLES M-59, SHT 1 304E OPERABLE 217 217 REACTOR OPERABLE ENCLOSURE B PCIGIADS NITROGEN BOTTLES M-59, SHT 1 304E OPERABLE 217 217 REACTOR OPERABLE ENCLOSURE B DIESEL GENERATOR EXHAUST M-20. Sht 4 311B OPERABLE SILENCER 217 217 DIESEL GENERATOR OPERABLE ENCLOEURE MAIN STEAM RELIEF VALVES POSITION N/A 402E OPERABLE TRANSMFnTERS`PRE-AMP 253 253 REACTOR OPERABLE ENCLOSURE B DIESEL GENERATOR DIESEL OIL M-20. Sht 4 YARD OPERABLE STORAGE TANK N/A 195 YARD OPERABLE B DIESEL GENERATOR DAY TANK M-20, Sht 4 3128 OPERABLE 217 220 DIESEL GENERATOR OPERABLE B DIESEL GENERATOR DIRTY DIESEL M-20, Shl 4 311B OPERABLE FUEL DRAIN TANK 217 217 1BGS01 DIESELGENERATOR OPERABLE ENCLOSURE B DIESEL GENERATOR JACKET WATER M-20, Sht4 3110 OPERABLE EXPANSION TANK 217 234 DIESELGENERATOR OPERABLE ENCLOSURE RACK/PANEL t'TERMINAL BOX) NIA 311A OPERABLE 217 IAGS01 DIESELGENERATOR OPERABLE ENCLOSURE RACKIPANEL (TERMINAL BOX) NIA 311B OPERABLE 217 1BG501 DIESEL GENERATOR OPERABLE ENCLOGURE Dacmemut No. 0S7010SI(I115411110 Attachimmnt A Revision 1 Motive power Support System Contr power IBD501 N/R MIA NIA N/A NIA N/A NIA NIA NIA N/A N/A N/A NWA WA NIA NIA NIA WA MIA NIA NWA NZA N/A Supp Sys dwg Filter. Unit = I or Unit = "Common" Sorted By Equip ID Page 28 Date: SIM/98 W UMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)MW Documsnl No. ioa7.MI.D11 2 Altsdtnenl A Revlson I 030;o M Train Class Equip ID System Equip Descrption Drawing No. Room No. Notrn state Motive power Support System SuPP Sys dwg unit Eva] Raq'd Room Elev Equpo Eev Line No. Function PIMS ID Notes ROB Mother Camp Building Req'd State Cant, power 3 18 1BTB-CGSI NIA RACK/PANEL (TERMINAL BOX) NWA 311C OPERABLE N/A 1 B 217 9229 PASSIVE 1B-TB-CG901 1CG501 DIESEL CGNERATOR OPERABLE N/A ENCLOSURE 3 18 IB7-0DG501 NIA RACK/PANEL (TERMINAL BOX) NIA 3110 OPERABLE N/A 1 a 217 9230 PASSIVE 1e-mr-OGS01 1DGst CMSELGENERATOR OPERABLE N/A ENCLOSURE 3 R 18T8011 NIA RACK/PANEL N/A NR OPERABLE NIA I WA 9208 PASSIVE 18-T4011 OPERABLE WIA 3 18 1MT8094 NIA RACK/PANEL (TERMINAL BOX) WA 309W OPERABLE NWA I S 217 217 9210 PASSIVE 1B-TB094 REACTOR OPERABLE NWA ENCLOSURE 3 R IBTBO96 N/A RACK/PANEL NWA NR OPERABLE WVA I WA 9209 PASSIVE 18-TB096 OPERABLE N/A 3 R 19T9122 NWA RACK/PANEL WA NR OPERABLE N/A I W/A 9211 PASSIVE 1848122 OPERABLE NIA 3 R 18TB123 N/A RACK/PANEL N/A NR OPERABLE N/A 1 NIA 9212 PASSIVE IB-T1t23 OPERABLE N/A 1 51 BV208 REACTOR ENCL RCIC PUMP &TURBINE ROOM UNIT M-11, Sht 2 108 OFF 108211 I SR HVAC & SGTS COOLER 8 183 1183 5555 ACTIVE 18-V209 REACTOR OPERABLE 106F211 ENCLOSURE 2 8 18V2z9 REACTOR ENCL HPCI PUMP & TURBINE ROOM UNIT M-11. Shl 2 109 OFF 10B212 I S HVAC & SGTS COOLER B 177 177.335 ACTIVE 1s-V209 REACTOR OPERABLE 108212 ENCLOSRE 2 8 1BV210 REACTOR ENCL B&D RHR PUMP ROOM UNITCOOLERB M-11,5ht3 103 OFF 109212 1 SR HVAC a SOTS 191 191 5855 ACTIVE 18-V210 REACTOR OPERABLE 109212 ENCLOSURE 2 a I BV211 REACTOR ENCL B CORE SPRAY PUMP ROOM UNIT M- 1, Sh 3 117 NIA NIA I S .NVAC & SGTS COOLER B 190 190 5640 PASSIVE 1B-V211 REACTOR N/A N/A ENCLOSURE 2 8 1V512 MISC. B DIESEL GENERATOR VENTILATION M-81, ShM 1 3119 OFF 108516 SR STRUCTURES

-AIR EXHAUST FAN B 217 217 I SR H/AC 5950 ACTIVE 19-V512 DIESELG,'ERATCR OPERABLE 109516, 1DY102 ENCLOSURE F-br. Unt= "1"orUnit t"Commnon" Sorted yEquIplD a i G).Pago 29 Data: 619/95 UI11MERICK GENERATG STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST(SPCL)Docurmart No. 00674amo Pheo a A Revision I Train Class Equip ID System Equip Description Drawing No. Room No. Norm sdate Motive power Support System Supp Sys dwg Unit Eval Reqd Room Elv Equip Elev Line No. Function PIMS ID Notes ROB Mother Comp Building Req'd State Conlr power 3 12 IBYI60 EPS B RPS & UPS 120V AC DISTRIBUTION E-32. SliT 542 OPERABLE 1BC248 1 S PANEL (ALT FEED:52-401 10 & 289 289 8237 ACTIVE 1B-Y160 CONTROL OPERABLE N/A STRUCTURE 3 12 1BYIS5 EPS B AVERAGE POWER RATE MONITOR E-32, SHT 2 542 OPERABLE 16D185 1 N/A UPS 120V AC DISTRIBUTION PANEL 289 289 8235 ACTIVE 1B-Y185 36 CONTROL OPERABLE NfA ETRUJCJRE 2 32 ICTF21i RHR RHR SUPPRESSION POOL SUCTION M-51. SHT 1 101 OPERABLE N/A I S STRAINER 182 181 3400 PASSIVE ICIF211 REACTOR OPERABLE NWA ENCLOSURE 1 32 1ClF575 SDG FUEL OIL FILTER M-20. Sh,5 311C OPERABLE MA 1 B 217 S,,, PASSIVE NIA 1CG501 DIESEL GENERATOR OPERABLE N/A ENCLOSURE 1 10 11CK513 FUEL OIL C DIESEL GENERATOR STARTING AIR M-20. Sht5 311C N/A NMR 1 S TRANSFER COMPRESSOR C1 217 217 5317 PASSIVE ICIK513 DIESEL GENERATOR N/A NMR ENCLOSURE 1 19 ICIT558 FUEL OIL C DIESEL GENERATOR STARTING AIR M-20. ShI 6 311C OPERABLE NIA 1 S TRANSFER RESERVOIR C1 217 217 5316 PASSIVE 1CIT558 DESEL EE'OR OPERABLE N/A ENCLOSURE 2 32 1C2F211 RHR RiH SUPPRESSION POOL SUCTION M-51. SHT 1 101 OPERABLE N/A 1 3 STRAINER 182 181 3401 PASSIVE 1C2F211 REACTOR OPERABLE N/A ENCLOSURE 1 32 1C2F575 SOC FUEL OIL FILTER W,3. Sht S 311C OPERABLE MIA 1 B 217 5304 PASSIVE NIA ICG501 n2ESEL GENERATOR OPERABLE NA ENCLOSURE 1 10 1C2K513 FUEL OIL C DIESEL GENERATOR STARTING AIR M-20, Si 5 311C N/A N/R 1 S TRANSFER COMPRESSOR C2 217 217 5319 PASSIVE 1C21(513 DIESEL GENERATOR NIA NWR ENCLOSURE 1 19 1C2TSS8 FUEL OIL C DIESEL GENERATOR STARTING AIR M-20. Sht 5 311C OPERABLE IWA 1 S TRANSFER RESERVOIR C2 217 217 5318 PASSIVE IC2TS58 DIESEl.GENERATOR OPERABLE N/A ENCLOSURE 3 Is I CC208 N/A UNIT COOLERS CONTROL PANEL N/A 20D OPERABLE N/A 1 S 201 201 9151 PASSIVE 1C-C208 REACTOR OPERABLE N/A ENCLOSURE 3 18 ICC514 N/A DIESEL GENERATOR ELEC INSTR N/A 311C OPERABLE N/A 1 S CONTROL BOARD 217 217 9213 PASSIVE 1C-C514 DIESELGENERATOR OPERABLE NIA ENCLOSURE Faw. UniL =1"or Unit ="Comrnon" Sorted By Equip ID Pase 30-t Dsle: 619/M5 S Document No- 00674141.84M Revision I UMERICK GENERATING STATION IWERE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCLJ oiO= Co Train ClaS Equip tO System Equip Descrplion Drawing No. Room No. Nnrm stats Moth's power Support System Supp Sys dwg unit Eval Reqd Room Elev Equip Elev Line No. Function PIMB ID Not1s ROB MotherComp Building Req/d State Contr power 3 1s 1CC563 WA DIESEL GENERATOR ENCLOSURE NVAC NIA 311C OPERABLE NWA I S CONTROL PANEL 217 2256-8" 9152 PASSIVE 1C-=5D3 GENRATOR OPERABLE NWA 3 18 1CC661 WA PANEL C-SAFEGUARD SYSTEM WA 533 OPERABLE NIA 1 VERTICAL BOARD 269 269 9214 PASSIVE 1C-C661 CONTROL OPERABLE MIA STRUCTURE 3 18 .CC667 WA INSTRUMENT PANEL NIA 533 OPERABLE N/A 1 S 269 9153 PASSIVE IC-CS67 CONTROL OPERABLE NWA S r I: STRUCTURE 3 13 iCo101 0C 125V DC BATTERY E-33, Sht 1 324 OPERABLE NIR 1 3 217 am9 ACTIVE 1C,_BAT'RY CONTROL OPERABLE NMR STRUCTURE 3 12 ICD102 DC TURBINE ENCLOSURE 125 VOC POWER E-33, Sht 1 434 OPERABLE 1CD105 1 S DIST PANEL ICD102 239 239 8713 ACTIVE IPPCI CONTROL OPERABLE NMR STRUCTURE 3 14 1CD103 0C 125V DC BATTERY CHARGER I C0103 E-33. Sht 1 324 OPERABLE 10B223 1 S (E-C) 217 217 8710 ACTIVE 18BCC CONTROL OPERABLE NMR STRUCTURE 3 lB ICD104 DC 12SVDC GROUND DETECTION CABINT E-33, Shl 1 324 OPERABLE 1C0105 1 S 1CD104(1=-C SAFEGUARD) 217 217 8712 ACTIVE 1C CONTROL OPERABLE NMR STRUCTURE 3 12 1C0105 CC 125VDC FUSE BOX ICD1O5 E-33 Sht 1 324 OPERABLE ICD101. ICOI3 1 S 217 217 8711 ACTIVE iFG CONTROL OPERABLE N.R STRUCTURE 3 12 IC0162 DC 1C-D162125VOC PWR DISTRIBUTION E-33, Sht 1 434 OPERABLE 1CD102 I S PANEL 239 239 8715 ACTIVE IPPC3 CONTROL OPERABLE NMR STRUCTURE 3 12 1CD501 DC 125V C DIST. PNL E-33, Shtl 311C OPERABLE ICD105 1 S 217 217 8714 ACTIVE 1PPC2 DtESEL GENERATOR OPERABLE NMR ENCLOSURE 1 20 ICE218 ESW C RHR PUMP SEAL COOLER M-11. Sht 2 102 OPERABLE WA I B 177 177 5544 PASSIVE 1 C-F218 1CP202 REACTOR OPERABLE NWA ENCLOSURE 1 20 ICE220 ESW C RHR PUMP MOTOR OIL COOLER M-11. SIt 2 102 OPERABLE WA I B 177 177 5545 PASSIVE 1C-E220 1CP202 REACTOR OPERABLE NWA ENCLOSURE Filler. Unit = "1or Unit = 'Common' Sorted By Equip ID.,,

Page 31 Date. 6/9/95 Train Unit Una No.5512 1 5512 1 5512 5313* I 53OO 3 1 9215 2 1 3404 I 5309 5302 5314 5310 ciass Eval Rsq'd Function 20 a PASSIVE 20 B PASSIVE 20 B PASSIVE 32 S PASSIVE 15 SR ACTIVE 18 S PASSIVE 4 SR ACTIVE 4 SR ACTIVE 3 B ACTIVE 3 BR ACTIVE 20 S PASSIVE 22 S PASSIVE Equip ID PIMS ID 1CE50fi iC-E5O7 iCE507 IC-E507 ICE585 IG-E586 1CF574 1C-F574 1CG501 IC-CS01-DR I CG502 IC.0S02 ICP202 IC.P202 1CP514 1C-P514 1CPS37 1C-P537 I CP538 ic-P538 105575 IC-S575 ICTS27 I C-T527 LIMERICK GENERATING STATION IPEES PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCL)System Equip Description Drawing No. Room No. Norm. state Room Elev Equip Elev Notes ROB Mcther Camp Building Raq'd Slate 41KV& DIESEL GEN. C DIESEL GENERATOR LUBE OIL W1I1. Sht I 311C OPERABLE COOLER 217 217 ICGS01 D- GENERATOR OPERABLE ENLURE 4KV & DIESEL GEN. C DIESEL GENERATOR JACKET WATER M-11. Sht 1 311C OPERABLE HEAT EXCHANGER 217 217 ICGSOI DIESEL GENERATOR OPERABLE ENCLOSURE 4)V/& DIESEL GEN C DIESEL GENERATOR INTERCOOLER M-1 1. Sin I 311C OPERAB!E WATER HEAT EXCHANGER DIESEL GEN 217 217 ICG501 DIESFLGENERATOR OPERABLE ENCLOSURE FUELOIL C DIESEL ENGINE INLET AIR FILTER M-20, Sht 5 311C OPERABLE TRANSFER 217 217 DIESELGENERATOR OPERABLE ENCLOSURE 4KV SYS & DIESEL DIESEL GENERATOR ENGINE M-20, Sh! 5 311C OPERABLE GEN 217 217 OIESELGENERATOR OPERABLE ENCLOSURE NIA D13 DIESEL GENERATOR POT TRANS N/A 311C OPERABLE AND EXCITATION EQUIPMENT 217 217 DIESEL GENERATOR OPERABLE ENCLOSURE RHR IC RESIDUAL HEAT REMOVAL (RHR) M-51, SHT 1 102 OFF PUMP 177 177 REACTOR ON ENCLOSURE FUEL OIL C DIESEL GENERATOR DIESEL OIL M-20. Shlt 5 YARD OPERABLE TRANSFER TRANSFER PUMP N/A 206 YARD OPERABLE FUEL OIL C DIESEL GENERATOR FUEL OIL PUMP M-20, Sh 5 NR OPERABLE TRANSFER OPERABLE FUEL OIL C DIESEL GENERATOR AUXILIARY FUEL M-20, Sht 5 31 IC OPERABLE TRANSFER OIL PUMP 217 217 ICG501 DIESEL GENERATOR OPERABLE FUEL OIL C DIESEL GENERATOR EXHAUST M-20, Sh 5 311C OPERABLE TRANSFER SILENCER 217 217 DIESEL GENERATOR OPERABLE ENCLOSURE FUEL OIL C DIESEL GENERATOR DIESEL OIL M-20. Sht 5 YARD OPERABLE TRANSFER STORAGE TANK NIA 198 YARD OPERABLE 0 DOO~MS No.

AlftactentA Revision 1 Moiva power Support System Supp SyS "wg Confirpower N/A N/A NIA N/A N/A NIA NZA DGEV M-81, Sh. 1 NIA NIR ESW.DGEV M- 1, Sh. 1: M-81.ICD102.ICD5OI N/A N/A 10A117 REV. ESW M-76, M-1I1 IA117. ICD102 10B517 108517 ICD50I 1/JR NIA NIA NIA NIA Filer. Unit = 1" or Unit = "Common" Sorted By Equip ID.-. ....... .......:. ...., ............

~0'5 Page 32 Daoe: 6/9S95 Documnt~ No. 0D7410085CO Revison I UMIECK GENERATING STATION IPEEi PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Train Class Equip ID System Equip Description DnraN No. Room No. Norm state Motive power Support System Supp Sys dwg Unit EvaI Req'd Room Elav Equip EBlv Line No. Function PIMS ID Notes ROB Mother Comp Building Reqd State Cont" power 1 19 1CT528 FUEL OIL C DIESEL GENERATOR DAYTANK M-20. Shlt 312C OPERABLE NIA 1 S TRANSFER 217 217 5307 PASSIVE 1C-T528 DIESELGENERATOR OPERABLE NIA 1 20 1CTS31 FUEL OIL CDIESEL GENERATOR DIRTY DIESEL M-20, Sh 5 311C OPERABLE NIA 1 B TRANSFER FUEL DRAIN TANK 217 217 5311 PASSIVE 1C-T531 6 ICG50I DIESEL GENERATOR OPERABLE WA ENCLOSURE 1 20 1CT564 FUEL OIL C DIESEL GENERATOR JACKET WATER M-20. Sht 5 311C OPERA3LE N/A I S TRANSFER EXPANSION TANK 217 234 5312 PASSIVE IC-TS64 DIESEL GENERATOR OPERABLE NWA ENCLOSURE 3 18 1CTB.AGS01 NIA RACK/PANEL (TERMINAL BOX) I/A 311A OPERABLE NWA I B 217 9231 PASSIVE IC-TS-AGS0I lAG501 DIESEL GENERATOR OPERABLE NIA ENCLOSURE 3 1e 1CTB-BG501 NIA RACK/PANEL (TERMINAL BOX) NIA 311a OPERABLE NWA I B 217 9232 PASSIVE IC-TB-65S01 1BGSD1 DIEMIL GENERATOR OPERABLE WA ENCLOSURE 3 is ICTB-CGSO1 N/A RACK/PANEL (TERMINAL BOX) WA 311C OPERABLE WIA I B 217 9233 PASSIVE 1C-TB-CG501 1CGSM1 DIESEL GENERATOR OPERABLE NWA ENCLOSURE 3 is 1CTB-DGW0" WA RACK/PANEL (TERMINAL BOX) WA 3110 OPERABLE WA 1 B 217 9234 PASSIVE 1C-TB-DG501 10G501 DIESEL GENERATOR OPERABLE WA ENCLOSURE 3 R ICTB122 N/A RACK/PANEL WIA NR OPERABLE NWA 1 NWA 9217 PASSIVE 1C.TB122 OPERABLE IVA 1 B 1CV210 REACTOR ENCL A &C RHR PUMP ROOM UNffCOOLERC M-11. Sht2 102 OFF 105217 1 S HVAC & SGTS 191 191 5536 ACTIVE 1C-V210 REACTOR OPERABLE 10B217 ENCLOSURE 1 B 1CV211 REACTOR ENCL C CORE SPRAY PUMP ROOM UNIT M-11, Sh1 2 113 WA NWA 1 S HVAC & SGTS COOLER C 190 ISO 65564 PASS IVE IC-V'211 REACTOR NWA NWA ENCLOSURE 1 a 1CV512 MiSC. C DIESEL GENERATOR VENTILATION M-81. Sht I 311C OFF 10B517 1 SR STRUCTURES-AIR EXHAUST FAN C 217 217 1 SR HVAC 5906 ACTIVE 1C-V512 DIESELGENERATOR OPERABLE 10E517. 10YI03 ENCLOSURE 2 32 1DIF211 RHR RHR SUPPRESSION POOL SUCTION M-51. Shl 3 101 OPERABLE N/A 1 S STRAINER 152 151 3200 PASSIVE 101F211 REACTOR OPERABLE NWA ENCLOSURE Fifter. Unit a 1" or Unit = "Common" Sfled By EquIp ID

-0 3 8~ I an Page 33 Data, 619/5 11 LIMERICK GENERATINO STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST{SPCL)

Doaznsrd No. 0007-006005)0 Aftedimrent A Rwbison 1 Train Class Equip ID System Equip Descrption Drawing No Room No Nnrm satoe Motive power Support System Supp Sys dwg Unit Eval Recd Room Elev Equip Elav Line No. Fnction PIMS ID Notes ROB Mother Comp Bulding Reqfd State Conir power 2 32 1D1FS75 SDG FUEL OIL FILTER M-20, Sht 6 3110 OPERABLE N/A 1 B 217 5401 PASSIVE N/A 6 1DG501 OIESELGENERATOR OPERABLE NIA ENCLOSURE 2 10 1DIK513 FUEL OIL D DIESEL GENERATOR STARTING AIR M-20, Sht 6 3110 N/A N/R 1 S TRANSFER COMPRESSOR 01 217 217 5417 PASSIVE IDIK513 DIESEL GENERATOR WA N/R EN17.OSU.KRE 2 19 ID1T558 FUEL OIL D DIESEL GENERATOR STARTING AIR M-20. Sht6 311D OPERABLE NWA I S TRANSFER RESERVOIR D0 217 217 S416 PASSIVE 1DIT558 :ESF. GENERATOR OPERABLE NIA ENCLOSURE 2 32 102F211 RHR RHR SUPPRESSION POOL SUCTION M-51. Sht 3 101 OPERABLE NIA I S STRAINER 182 181 3201 PASSIVE ID2F211 REACTOR OPERABLE NWA ENCLOSURE 2 32 1D2F575 SOG FUEL OIL FILTER M-20, SM 6 311D OPERABLE MA I B 217 540q PASSIVE N/A 6 1DG501 DIESEL- ENERATOR OPERABLE NWA ENCLOSURE 2 10 1D21(513 FUEL OIL D DIESEL GENERATOR STARTING AIR M-20. Sht 6 3110 N/A N/R I S TRANSFER COMPRESSOR 02 217 217 5419 PASSIVE 1D2K513 DIESEL GENERATOR WA MR ENCLOSURE 2 19 1D2T558 FUEL OIL 0 DIESEL GENERATOR STARTING AIR M-20. SWt 6 3110 OPFRABLE NIA 1 5 TRANSFER RESERVOIR D2 217 217 5418 PASSIVE 102TS58 DIESEL GENERATOR OPERABLE WA ENCLOSURE 3 18 IDC209 N/A UNIT COOLERS CONTROL PANEL NWA 207 OPERABLE N/A I S 201 201 9154 PASSIVE 1D-=208 REACTOR OPERABLE NIA ENCLOSURE 3 Is 1DC514 N/A D DIESELGENERATOR ELECTRIC NWA 311D OPERABLE NWA 1 S INSTRUMENT CONTROL BOARD 217 217 9218 PASSIVE 1D-C514 DIE. GENIERATOR OPERABLE WA ENCLOSURE 3 13 1DC563 NWA DIESEL GENERATOR ENCLOSURE HVAC WA 311D OPERABLE WA I S CONTROL PANEL 217 226'-8S 9155 PASSIVE 1D-C53 DIES.GENERATOR OPERABLE N/A ENCLOSURE 3 1i 1DC661 N/A PANEL D-SAFEGUARD SYSTEM N/A 533 OPERABLE N!A 1 5 VERTICAL BOARD 259 259 9219 PASSIVE ID-61 CONTROL OPERABLE NIA 3 13 1DD101 DC 12SV DC BATTERY E-33, Sht 2 323 OPERABLE N/R S 217 8309 ACTIVE 1DLBA'TTERY CONTROL OPERABLE NWR STRUCTURE Is FUter. Unit = 'lor Unit ="Common" Sorted By Equip ID..-. .,. .. j .... ... , ..-, ,.-- ---.--------

Page 34_. Date:SI* -a Gi TraIn Z' Unit-@. Linm No.4 cn DC 3 8313 3 8310 3 8312 3 8311 3 3 8314 2 5653 2-S*1 4 U UMERICK GENERATING STATION IP!EE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCL)Dacuntrd Na. OO'7-000SI-CC Attadimetd A Revision I Class Equip ID Sy1stm Equip Description Drawing No. Room No. Norm state Maotiv power Support System Supp Sys dwg Eval Req'd Room Elav Equip Elev Function PIMS ID 12 S ACTIVE 14 S ACTIVE 18 S ACTIVE 12 S ACTIVE 12 S ACTIVE 12 S ACTIVE 20 B PASSIVE 20 B PASSIVE IDD102 1PPD1 1D00103 19CD 1DD104 1D 1DD105 1FD 1DD162 1PPD3 10D0501 1PPD2 1DE218 1D-E218 1DE220 1D-E220 Notes ROB Mother Comp DC IPPDI 125VDC DIST PANEL (¶D-0102)

E-33. Sht 2 0C 125V DC BATTERY CHARGER E-33, Sht 2 IDD103(IE-D) 0C 125V DC GROUND DETECTION CABINET E-33, Sht 2 1DD104(1E-D SAFEGUARD) 0C 125V DOC FUSE BOX lDD105 E-33, Sht 2 00 ID-0162125VOC DISTPNL E-33 Sht 2 DC 1D-D501 125 VDC DISTRIBUTION PANEL E-33. Sht 2 ESW D RHR PUMP SEAL COOLER M-11, Sht 3 6 10P202 ESW O RHR PUMP MOTOR OIL COOLER M-11, Shl 3 6 IDP202 Building 452 254 CONTROL STRUJCTlURE 323 217 CONTROL STRUCTURE 323 217 CONTROL STRUCTURE 323 217 CONTROL STRUCTURE 425 239 CONTROL STRUCTURE 311D 217 DIESEL GENERATOR ENCLOSURE 103 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE Reqd State OPERABLE 254 OPERABLE OPERABLE 217 OPERABLE OPERABLE 217 OPERABLE OPERABLE 217 OPERABLE OPERABLE 239 OPERABLE OPERABLE 217 OPERABLE OPERABLE 177 OPERABLE OPERABLE 177 OPERABLE Contt power 1DD105 NMR 105224 NfR 1DD105 NMR 1D0101, IDD103 NIR 1DD105 NMR 1D0105 NMR NIA NWA NIA NIA 2 20 10ESD5 4KV&DIESELGEN D DIESEL GENERATOR LUBE OIL M-11. Sht 1 311D OPERABLE NWA I B COOLER 217 217 5622 PASSIVE 11-ES06 10G501 DIESEL GENERATOR OPERABLE NWA ENCLOSURE 2 20 1DE507 4KV & DIESEL GEN D DIESEL GENERATOR JACKET WATER M-i1, Sht I 311D OPERABLE N/A I a HEAT EXCHANGER 217 217 5523 PASSIVE 10-5507 106501 DIFSELOENERATOR OPERABLE WA ENCLOSURE 2 20 10E5BG 4KV&DIESELGEN O DIESEL GENERATOR INTERCOOLER M- 1, Shl 1 3110 OPERABLE NWA 1 B WATER HEAT EXCHANGER 124 DIESEL 217 217 5624 PASSIVE 10-E586 1DG0Q1 DIESEL GENERATOR OPERABLE WA ENCLOSURE 2 32 1DF574 FUEL OIL D DIESEL ENGINE INLET AIR FILTER M-20, 5h$ 6 3110 OPERABLE NWA DGEV M-81, Sh. 1 I S TRANSFER 217 217 5413 PASSIVE 10-FS74 DIESEL GENERATOR OPERABLE N/A ENCtLOSURE FIlter Unit ="1"ior Unit :"Commo" Sorted By Equip I0

-UN:00 0)0 00 5.-Si= Ic In S* Page 3S Date. 619195 W U LIMERICK GENERATING STA'iON IPEE PROJECT UNIT I L COMMON SUCCESS PATH COMPONENT UST(SPCL)U Doajment No. 00WSSDE.Nn Attchmrent A Revision I Train Class Equip ID System Equip Descripton Drawing No. Room No. Norm sate Motive power Support System Supp Sys diwg jUnit Eval Retld Room Elav Equip Etev Line No. Function PIMS ID Notes ROB Mother Camp Building Reqd Stale Contr power 2 15 1DG501 4KV SYS & DIESEL DIESEL GENERATOR ENGINE M-20. Shl 6 311D OPERABLE HER ESWDGEV M-1 1. Sh. 1; M-81, 1 SR GEN 217 217 xi 5400 ACTIVE 10D501-DR DIESEL GENERATOR OPERABLE D101OZIDD501 ENCLOSURE 3 18 100502 NWA DI4 DIESEL GENERATOR POT TRANS WA 3110 OPERABLE WA AND EXCITATION EQUIPMENT 217 217 922 PASSIVE ID-GS02 DIESELGENERATOR OPERABLE NIA ENCLOSURE 2 4 IDP202 RHR tD RESIDUAL HEAT REMOVAL (RHR) M-51, Sht 3 103 OFF I0Al1 EGW. REV M-11. M-76PUMP I SR 177 177 3203 ACTIVE REACTOR ON 10Al1s, 10D102 ENCLOSURE 2 4 1DP514 FUELOIL DOIESEL GENERATOR DIESEL OIL M-20, Sht 8 YARD OPERABLE 108518 I SR TRANSFER TRANSFER PUMP NA 208 5409 ACTIVE 1D-P514 YARD OPERABLE 100518-: 2 1DP537 FUELOIL D DIESEL GENERATOR FUEL OIL PUMP M-20. Sht 6 311D OPERABLE N/R"TRANSFER 1 B 217 217 5402 ACTIVE 1D-537 6 1DG,501 DIESEL OPERABLE NHR ENCLOSURE SIDP538 FUEL OIL D DIESEL GENERATOR AUXILIARY FUEL M-20, Sht 6 3110 OPERABLE 1DD501 BR TRANSFER OIL PUMP 217 217 5405 ACTIVE ID-P538 6 IDG501 DIESEL TOR OPERABLE NIR.4.JEICLOSURE 2 20 1D5575 FUEL OIL D DIESEL GENERATOR EXHAUST M-20. Sh9 6 3110 OPERABLE N/A TRANSFER SILENCER 1 5 217 217 5414 PASSIVE 1D-$5`5 DIESEL GENERATOR OPERABLE N/A ENCLOSURE! 2 22 1DT527 FUZL OIL 0 DIESEL GENERATOR DIESEL OIL M-20, ShtS YARD OPERABLE WA TRANSFER STORAGE TANK I S N/A 198-5410 PASSIVE 1D-T527 YARD OPERABLE WA 2 19 1DT528 FUEL OIL 0 DIESEL GENERATOR DAY TANK M-20, Sht 6 3120 OPERABLE NWA f 1 S TRANSFER 217 217: 5407 PASSIVE ID-T528 DIESEL GENERATOR OPERABLE WA 2 20 10T531 FUEL OIL D DIESEL GENERATOR DIRTY DIESEL M-20. Shlt 6 3110 OPERABLE N/A S 1 aTRANSFER FUEL DRAIN TANK 217 217 5411 PASSIVE iD-T531 6 1DGS01 DIESEL GENERATOR OPERABLE N/A ENCLOSURE 2 20 1DT564 FUEL OIL D DIESEL GENERATOR JACKET WATER M-20, Sht 6 3110 OPERABLE N/A 1 S TRANSFER EXPANSION TANK 217 2E E 5412 PASSIVE 1D-T564 DIESEL GENERATOR EA 3 R 1DTB122 N/A RACK/PANEL NWA NR OPERABLE NWA I I N/A 922= PASSIVE 1D-T5122 OPERABLE NWA Filter. Unit = "1' or Unit nComoni Sorted By Equip ID... .7,- 7 .,,

W LMERICK GEWERATl4G STATiON IPSEE PROJECT UNI I & COMMON SUCCESS PATH COMPONENT UST (SPCL)w Oocurner No. 00674SM5 AlWhOA Revision I Page 36 Date: 6/9195 a 3 R-G 0) G Tmri Class Equip ID System Equip Description Drawing No. Room No. Norm state Motive power Support System Supp Sys dwg Unit Eval rteqd Room Elys Equip Elev Una No. Function PIMS ID Notes ROB Mother Comp Building Req'd State Contr power 2 a 1DV210 REACTORENCL B &9D RHR PUMP ROOM UNIT COOLER D M-11. Sht3 103 OFF 1I0215 1 SR HVAC & SGTS 191 191 5656 ACTIVE ID-V210 REACTOR OPERABLE 1053218 ENCLOSURE 2 l 1DV211 REACTOR ENCL D CORE SPRAY PUMP ROOM UNIT M-11, Sh 3 114 WA WA I S HVAO & SGTS COOLER O 19D 190 6641 PASSIVE ID-V211 REACTOR WA WA ENCLOSURE 2 8 IDV512 MISC. D DIESEL GENERATOR VENTILATION M-81. Sht I 311D OFF 10B518 STRUCTURES

-AIR EXHAUST FAN 0 217 217 1 SR HVAC DEE EEAO 058 Ol'5956 ACTIVE 1D-V512 DtESEL GENERATOR OPE 100510,E1Y104 ENCLSR 2 20 1ET003 NUCLEAR BOILER E MAIN STEAW RELEF VALVE (MSRV) M-41. Sht 2,3 400 OPERABLE N/A PCIG M-59. S.L I 1 S ACCUMULATOR TANK 237 256 2114 PASSIVE 1E-T003 REACTOR OPERABLE NWA ENCLOSURE 3 1e 1ETB-AG50t NIA INSTRUMENT PANEL WA 31IA OPERABLE NWA 1 B 217 9156 PASSIVE IE-TBGAG5 IAG5OI DtESEL GENERATOR OPERABLE WA ENCLOSURE 3 ia IETB-"GE01 WA INSTRUMENT PANEL NWA 311B OPERABLE NIA I a 217 9157 PASSIVE IE-TB-BG501 1B3501 OPERABLE NIA ENCLOSURE 3 18 tETB-CG50i NIA INSTRUMENT PANEL WA 311C OPERABLE NIA 1 B 217 9158 PASSIVE IE-TB-CG501 1CG501 ESE. G ,ENERATOR OPERABLE WA ENCLOSURE 3 18 1ETB-DGS0I N/A INSTRUMENT PANEL NWA 3110 OPERABLE NIA 1 B 217 9159 PASSIVE 1E-TB.OG0l lDGE501 DISSELGENERATOR OPERABLE N/A ENCLOSURE I IEV210 REACTOR ENCL A&CRHRPUMPROOM UNITCOOLERE M-11. Sh12 102 OFF 10B211 I SR HVAC & SGTS 183 163 5535 ACTIVE 1 E-V210 REACTOR OPERABLE 103211 ENCLOSURE 1 8 IEV211 REACTOR ENCL A CORE SPRAY PUMP ROOM UNIT M-11. Sht2 110 N/A NIA 1 S HVAC & SGTS COOLER E 177 177 5563 PASSIVE 1E-V211 REACTOR NIA NWA ENCLOSURE 1 a 1EV512 MIsC. A DIESEL GENERATOR VENTILATION M-81, Shl 1 311A OFF 108515 1 SR STRUCTURES-AIR EXHAUST FAN E 217 217 1 SR HVAC 3903 ACTIVE 1E-V512 0A.DES GENERATOR OPERABLE 109516, 10Y0lI ENCLOSURE 3 1I IFTB-AGC01 N/A RACK/PANEL (TERMINAL BOX) WA 311A OPERABLE N/A 1 B 217 9235 PASSIVE 1F-TB-AG501 lAG50 DIESEL GENERATOR OPERABLE NWA ENCLOSURE Filer. Urni "or Unit "Commorn" Sorted By Equip ID... ... -.... ... ..

~Page 37 Date: 6/9M 0 9 DooImenl No. 0067-,0M854 A Revision I UMERICK GENERATING STATION IPEEE PROJECT LINnT & COMMON SUCCESS PATH COMPONENT UST(SPCL)), Train Class qqup IO Systew Equip Description Drawing No. Room No. Noim lte Move power Support System rupp Syt:gys.Unit Evul Req'd Room Elev Equip Elev i: Lina No. Function PIMS 10 Notes ROBMotherComp Building Req'd Slate Conyr power 3 18 IFTB-BG501 NIA RACKIPANEL (TERMINAL BOX) WA 3118 OPERABLE N/A o 217 9236 PASSIVE IF-TB-BGS0I IBGSOI rESNCLOSNEATOR OPERABLE NAENCLOSURE 3 18 1FTB-CG501 NIA RACK/PANEL (TERMINAL BOX) WA 311C OPERABLE NIA 1 1 217 9237 pASSIVE= 1F-TB-CGSO1 lCO51 DIESEL GENERATOR OPERABLE WA 9VENCLOSURE 3 1FTB-DGS01 WA RACK/PANEL (TERMINAL BOX) N/A 311D OPERABLE WA 1 B 217 9238 PASSIVE IF-TB-OGSOI 1D0501 DIESELGENERATOR OPERABLE NfA ENCLOSURE 2 B IFV210 REACTOR ENCL B&D RHR PUMP ROOM UNITCOOLERF M-11.Sht3 103 OFF 10B212 I SR HVAC,&SGTS 13 18 RATIVE-Tr OPERABLE 10E212 2 8 1FV211 REACTOR ENCL B CORE SPRAY PUMP ROOM UNfI M-11. Sht3 117 WA WA HVAC& SGTS COOLERF 177 177 5642 PASSIVE 1F-V211 ENCLOSURE N/A WA 28 1FV512 MISC. B DIESEL GENERATOR VENTILATION M-81. Shit 1 3118 OFF 101516 SR STRUCTURES-AIR EXHAUST FAN F 217 217 5953 ACTIVE 1F-VS12 DIESELOENERATOR OPERABLE 10B51., 10Y102 ENCLOSURE 3 18 IGTB-AG501 WA RACK/PANEL WA 311A OPERABLE NWA 1 8 217 9235 PASSIVE 1G-TB-AG501 lAGS01 DIESEL GENERATOR OPERABLE NIA ENCLOSURE 3 18 IGTB-BG01 NZA RACK/PANEL (TERMINAL BOX) NWA 311B OPERABLE NWA 1 217 92PASSIVE 1G-TB-BG01 16501 DIESEL GENERATOR OPERABLE NWA 924 ASSIE I-Te-1351 IB501ENCLOSLRE 3 18 IGTB.CGS01 NIA RACK/PANEL N/A 311C OPERABLE NWA 1 a 217 9241 PASSIVE 1G-TB.CGS01 ICG501 DIESELGENERATOR OPERABLE NWA ENCLOSURE 3 18 1GTB.DGS01 N/A RACK/PANEL (TERMINAL BOX) N/A 311D OPERABLE NIA' 1 2 17 1G-TB-DG501 IOGS01 DIESEL GENERATOR OPERABLE NWA 924 PASV ENCLOSU~RE 8 GV210 REACTOR ENCL A&CRHRPUMPIROOMUNITCOOLERG M-11, ht2 102 OFF 106217 SAC & SGTS 183 183 ,, 5537 AOG-V210 RE OPERABLE 10B217 a1 GV211 REACTOR ENCL C CORE SPRAY PUMP ROOM UNIT M-11. ,51112 113 NIA N/A S HVAC & SGTS COOLER G 177 177 5565 PASSIVE 1G-V211 REACTOR NIA N/A.PENCLOSURE Filter. Unit = " or Unit =o"Cnmon" Sorltd By Equip 10 Cr1-OS 0 tOW S. S N tO cii C Paeg 38 Date: 699 Train Class Equip ID Unit Eval Reqd Une No. Function PIMS in 1 8 1GVS12 1 SR 5909 ACTIVE 1G-V512 0 LIMERICIC GENERATlNG STATION 04EB PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Documant No. 0067-0001541 AftandugNA Resi~owi System Equip Description Drawing No.Notes ROB Mother Comp MISC_ C DIESEL GENERATOR VENTILATION M-eI. Shit 1 STRUCTURES

-AIR EXHAUST FAN G WVAC Room No. Norm slte Motive power Support System Supp Sys dwq Room Elev Equip Elev Builrg PReqd State Contr power 311C OFF 108517 217 217 DIESEL GENERATOR OPERABLE 10B517, 10Y103 ENCLOSURE 2 20 1HY003 NUCLEAR BOILER H MAIN STEAM RELIEF VALVE (MSRV) M-41. Shi 2, 3 400 OPERABLE NWA PCIG M-59, el. 1 1 S ACCUMULATOR TANK 237 285 2115 PASSIVE 11-T003 REACTOR OPERABLE NWA ENCLOSURE 2 8 1HV210 REACTOR ENCL B&D RIRPUMP ROOM UNrTCOOLER H M-11.Sht 3 103 OFF 108210 1 SR HVAC & SGTS 183 183 5658 ACTIVE 1H-V210 REACTOR OPERABLE 108218 ENCLOSURE 2 B 1HV211 REACTOR ENCL D CORE SPRAY PUMP ROOM UNIT M-11. Sht 3 114 N/A N/A 1 $ NVAC & SGTS COOLER H 177 177 5643 PASSIVE lH-V21I REACTOR WA WA ENCLOSURE 2 1 1IV512 MISC. D DIESEL GENERATOR VENTILATION M-81, Sht 1 311,13 OFF 10B518 I SR STRUCTURES-AIR EXHAUST FAN H 217 217 5959 ACTIVE 1H-V512 HVAC DIESELOENERATOR OPERABLE 10B518, 10Y104 ENCLOSURE 2 20 1KT003 NUCLEAR BOILER K MAIN STEAM RELIEF VALVE (MSRV) M-41. Sd Z 3 400 OPERABLE N/A PCIG M-59, SH. I 1 S ACCUMULATOR TANK 237 273 2116 PASSIVE I K-T003 REACTOR OPERABLE N/A ENCLOSURE 2 20 1MTO03 NUCLEAR BOILER M MAIN STEAM RELIEF VALVE (MSRV) M-41. Shi 2,3 400 OPERABLE N/A PCIG M-59. SH. 1 1 S ACCUMULATOR TANK 237 273 2117 PASSIVE IM-T003 REACTOR OPERABLE NWA ENCLOSURE 2 20 1ST003 NUCLEAR BOILER SMAIN STEAM RELI.F VALVE (MSRV) M-41. .,h 2. 3 400 OPERABLE NWA PCIG M,-59, SH. 1 1 2115 3 1 2205 3 1 2206 1 1 3131 3 1 2214 S PASSIVE R WA PASSIVE R R PASSIVE R WA PASSIVE R NIA PASSIVE 1S-TO03 41-IFOIOA 041-I FOIOA 41-IF010B 041-4FO10B 44-1054 044-1064 48-1027 048-1027 ACCUMULATOR TANK NUCLEAR BOILER 24" A INBRO F DWTR CHECK TO M-41, SHT 1 REACTOR VESSEL PCfV NUCLEAR BOILER 24"B INBRD FDWTR CHECK TO M-41, SHT 1 REACTOR VESSEL PCIV RCIC MRR 174228 00 HOLD RWCU TO M-44, SHT 2 FEEDWATER STANDBY LIQUID SLC INJECTION LINE M-48, Sha" CONTROL 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 40O 237 REACTOR ENCLOSURE 507 283 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 273 OPERABLE OPERABLE 216 OPERABLE OPERABLE 286 OPERABLE OPERABLE 283 OPERABLE OPERABLE 216 OPERABLE NIA N/A NIA WA NIA WA NIA WA NIA Riter. Unit = 't" or Unit = "Common" Sorted By Equ;p ID 0 LIMERICK GENERATING STATION IPEEE PROJECT UNITI & COMMON SUCCESS PATH COMPONENT UST (SPCL)Pag4 39 Date: 6/9W95 Oocurrent No. 000874KIN5002 Atteciimelt A Revision I Train Class Equip ID System Equip Desciption Drawing No. Room No. Norm Mate Unit Evsl Room Eley Equip Elev Line No. Function PIMS ID Notes 3122 1 1 3125 1 1 3133 4121.4325.

4725 2 1 4222. 4421. 4819 4110, 4307, 4706 2 1 4209,4409,4809 2 1 3407 2 1 3206 2 1 4219.4419, 4820 1 1 4124, 4322,4723 2 1 4221, 4425, 4825 R NIA PASSIVE R N/A PASSIVE R N/A PASSIVE R WA PASSIVE R NIA PASSIVE R NIA PASSIVE R NZA PASSIVE R N/A PASSIVE R NtA PASSIVE R NZA PASSIVE R NZA PASSIVE R N/A PASSIVE 49-1032 049-1032 49-IFOES 049-1F06S 50-1 F047 050-1F047 51-1032A 051-1032A 51-10328 051-1032B 51-1115A 051-1115A 51-1115B 051-11156 51-1115C 051-1115C 51-11I15D 051-1115t 51 -1 F078 051-1 F078 51-IFOS0A 051-11O9OA 51-1F0906 051-1F09OB RCIC RCIC RCIC RHR RNR RHR RHR RHR RHR RHR RHR RHR RHR ROOB MC.0er Comp SAFEGUARD PIPING FILL PUMP ATO RCIC FILL FROM CONDENSATE TRANS TO RCIC P DISCHARGE LINE OFF BAROMETRIC CONDEN CONDENSATE FILL FOR INJECTION LINE T CONDENSATE FILL FOR INJECTION LINE T SAFEGUARD PIPING FILL TO RHR PUMP D1 SAFEGUARD PIPING FILL TO RHR PUMP 0]SAFEGUARD PIPING FILL TO RHR PUMP DI SAFEGUARD PIPING FILL TO RHR PUMP DI RHR SERVICE WATER CROSS TIE CONDENSATE FILL TO RHR INJECTION LIN CONDENSATE FILL TO RHR INJECTION LIN M-49. SItd I M-49. Sht I M-50. SHT 1 M-51, Slt 1 M-51, sht3 M-51, Sht 1 M-51, Sit 3 M-51, SKIT 1 M-51. ShM 3 M-61, St 4 M-61, Sht I M-51. Sht 3 eundvng NR REACTOR ENCLOSURE 518 279 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 309 217 REACTOR ENCLOSURE 309 217 REACTOR ENCLOSURE 102 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE 102 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE 204 201 REACTOR ENCLOSURE 511 283 REACTOR ENCLOSURE 508 213 R-ACIOR ENCLOSURE Reqd State OPERABLE 177 OPERABLE OPERABLE OPERABLE OPERABLE 177 OPERABLE OPERABLE 217 OPERABLE OPERABLE 217 OPERABLE OPERABLE 177 OPERABLE OPERABLE 177 OPERABLE OPERABLE 177 OPERABLE OPERABLE 177 OPERABLE OPERABLE 201 OPERABLE OPERABLE 2e3 OPERABLE OPERABLE 283 OPERABLE Motive power Support System Conr power N/A N/A N/A NIA NIA NIA NIA N/A N/A N/A WA N/A WA N/A NIA WA N/A NIA N/A N/A N/A N/A NWA Suipp Sys dgm Filter, Unit = "1" or Unit ="Common" Sorted By Equip ID Page 40"Dole Blew Train Unit Line No.vi 2 3410 2 3M0 1 3304 3310 610B 2 6110 s1lo 2 1 6 30B 2 5408"" 3106 W lMERICK GENERATING STATION IPEE= PROIECT UNIT 1 & COMMON SUCCESS PATH COMPONENT UST (SPCL)w Document No. 0057-000154 Aboiut A Revision1 I CAMS5 Equip ID System Equip Desciption Drawing No. Room No. Norm sIe Molvem power Support Systen Supp Sys dwo Eva] Reqd Rome Elev Equip Eov Function PIMS ID Noles R NWA PASSIVE R WA PASSIVE R N/A PASSIVE R N/A PASSIVE R N/A PASSIVE R N/A PASSIVE R N/A PASSIVE 51-IFOS9C 051-1 F0gWC 51-IFOSOD 051-11F0901) 55-iFO1 055-IF019 55-1 F078 055-1 F078 59-1122 059-1122 59-1131E 059-1131E 59-1131K 059-1131K RHR RHR HPCI HPCI PCIG Polo PCIG ROB Mother Camp CONDENSATE FILL TO RHR INJECTION M-51, SHT 1 LIN CONDENSATE FILL TO RHR INJECTION M-51. Sht 3 LIN HPCI PUMP SUCTION FROM CST M-55. SHT 1 CONDENSATE TRANSFER TO HPCI M-55, SHT 1 PUMP DIS INST AIR SUPPLY ISOL ITF 00345 M-59. S~ir 1 CLEANUP INST AIR SUPPLY ITF 00345 CLEANUP M-59. SHT I INST AIR SUPPLY nlF 00345 CLEANUP M-59. SHT I FUEL OIL FILTER M-20. Sht 3 FUEL OIL FILTER M-20, Sht 4 FUEL OIL FILTER M-20, Shi 5 FUEL OIL FILTER M-20. Sht6 FUEL OIL FILTER M-20. Sht 3 IAGS51 599 283 REACTOR ENCLOSURE 506 283 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE SOB 283 REACTOR ENCLOSURE 304 217 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE Building Req'd State Contr power OPERABLE NIA 283 OPERABLE N/A OPERABLE N/A 283 OPERABLE WA OPERABLE N/A 177 OPERABLE N/A OPERABLE N/A 283 OPERABLE N/A OPERABLE NIA 217 OPERABLE N/A OPERABLE WA 288 OPERABLE N/A OPERABLE N/A 273 OPERABLE N/A 32 RS-122A FUEL OIL S TRANSFER PASSIVE NIA 311A OPERABLE NIA 217 32 S PASSIVE 32 S PASSIVE 32 S PASSIVE 32 B PASSIVE BS-122B NIA BS-122D KEA SS-122D NIA BS-124A-i N/A FUEL OIL TRANSFER FUEL OIL TRANSFER FUFIL OIL TRANSFER FUEL OIL TRANSFER ODESEL GENERATOR OPERABLE NIA ENCLOSURE 311B OPERABLE NIA 217 DIESEL GENERATOR OPERABLE N/A ENCLOSURE 311C OPERABLE N/A 217 DIESEL GENERATOR OPERABLE N/A ENCLOSURE 3110 OPERABLE N/A 217 DIESEL GENERATOR OPERABLE N/A ENCLOSURE 3111A OPERABLE N/A 217 DIESEL GENERATOR OPERABLE NIA ENCLOSURE Filter. Unit = 1"ror Unit = "Common" Sorted By Equip ID d Page 41 J Date; WS9 0,'Tramin unit D LiUe No.1 E 1 5103 2 5206 2 ,1 52M3¶¶-c 5306 5303 2*, 1 5406 I) 5403 5115 2 1 515 5315 2 i " 1 5416 3103 0 Document No. O067s000aus=

Revision I UMERICK GENERATING STATION IPEE PROJECT UNIT 1 & COMMON SUCCESS PATH COMPONENT UST (SPCL)Class Equip ID System Equip Desoxptlon Omwing No. Room No. Norm state Motive power Support System Supp Sys dwg Eva] Req'd Funtion PIMS ID Notes 32 B PASSIVE 32 B PASSIVE 32 B PASSIVE 32 B PASSIVE 32 B PASSIVE 32 B PASSIVE 32 B PASSIVE 19 S PASSIVE 19 S PASSIVE 19 S PASSIVE 19 S PASSIVE 20 S PASSIVE BS-124A-2 NIA BS-124B-1 NIA 85-1248-2 N/A BS-124C-1 NIA BS-124C-2 N/A BS-124D-I NIA 11-1240-2 N/A DRAN POT N/A DRAIN POT N/A DRAIN POT N/A DRAIN POT N/A DRAIN POT N/A FUEL OIL TRANSFER FUEL OIL TRANSFER FUEL OIL TRANSFER FUEL OIL TRANSFER FUEL OIL TRANSFER FUEL OIL TRANSFER FUEL OIL TRANSFER SDG SDG SOG SDG RCIC ROB Moath-r Comp FUEL OIL BASKET STRAINER 1AG501 FUEL OIL FILTER 161501 FUEL OIL FILTER 1BG501 FUEL OIL FILTER 1CG501 FUEL OIL FILTER lCG5Ol ,-UEL OIL FILTER 1DG501 FUEL OIL FILTER 1013501 DRAIN POT DRAIN POT DRAIN POT DRAIN POT DRAIN POT M-20, Sht 3 M-20, Sht 4 M-20, Std4 M 20, Sht 5 M-20, Sht 5 M-20, Sht S M-20. Sht 6 M-20. SMA 3 M-20, Sht 4 M-20, Sit 5 M-20, Shi 6 M-49, Sht 1 Room ESav Equip Elav Building Riqd State Coc*r power 311A OPERABLE N/A 217 DIESEL GENERATOR OPERABLE N/A ENCLOSURE 3115 OPERABLE N/A 217 DIESELOGNERATOR OPERABLE WA ENCLOSURE 311B OPERABLIF N/A 217GENERATOR OPERABLE N/A ENCLOSURE 311C OPERABLE N/A 217 DIESELGENERATOR OPERAEBIE NIA ENCLOSURE 311C OPERAELE NIA 217 DIESELGENERATOR OPERABLE N/A ENCLOSURE 311D OPERABLE NWA 217 DIESEL GENERATOR OPERABLE I/A ENCLOSURE 3110 OPERABLE NZA 217 DIESEL GENERATOR OPERABLE N/A ENCLOSURE 311A OPERABLE NWA 217 DIESEL GENERATOR OPERABLE WA ENCLOSURE 311B OPERABLE N/A 217 DIESEL GENERATOR OPERABLE WA ENCLOSURE 311C OPERABLE N/A 217 DIESEL GENERATOR OPERABLE NfA ENCLOSURE 311D OPERABLE WA 217 OPERABLE WA ENCLOSURE 105 OPERABLE WA 177 177 REACTOR OPERABLE N/A ENCLOSURE Filer. Unit -1" or Unit = "Common" Sorted By Equip IC Page 42 Date: 6/9/95 Train oG)

Unai Line No.C.)3108 I I_2 3327 333 SSW 3100 1 3320 3 9500 3 1 9501 3-1' 9502 3 3* 505 ...9506 Class Eval Reqtd Function 20 S PASSIVE 20 S PASSIVE 20 S PASSIVE 24 S PASSIVE 24 S PASSIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE Equip ID PIMS ID DRAIN POT NIA DRAIN POT NIA DRAIN POT NIA FE-49-IN016 FE-049-1N016 FE-55-,N032 FE-O55-1N032 FT-S1-1N001 FT-051-INOI FT-SI14NOISA FT-051-1N015A FT-51-1N015B Fr-051-1N0ISB FT-51-INO15C FT-051-1NO16C FT-51-tNOISD FT-051-1NO15D FT-51-1N052A FT-051-1N052A FT-51-1N052B FT-OS1-1N0528 System Notes RCIC HPCI HPCI RCIC HPCI WA N/A N/A N/A NIA NIA NZA Equip Description ROB Mother Camp EXHAUST LINE DRAIN HPCI TURBINE STEAM IPCI TURBINE EXHAU RCIC PUMP TURBINE HPCI TURBINE STEAM RHR NTX A & PUMPA RHR KTXA & PUMP A RHR HTX 8 & PUMn B RHR PUMP C DISCH F.RHR PUMP D DISCH FL RHRHTXA& PUMPA RHR HTX B a PUMP B%w LIMERICK GENERATING STAllON IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST(SPCL)Drawing No. Room No.Room Elev Building POT M-60. Sht 1 108 177 REACTOR ENCLOSURE SUPPLYDRAIN M-,55, SHT 1 109 177 REACTOR ENCLOSURE ST DRAIN M-56. SlT 1 109 177 REACTOR ENCLOSURE STEAM M-49. Sht 1 101 253 REACTOR ENCLOSURE SUPPLY M-SS, SHT 1 101 253 REACTOR ENCLOSURE DISCH FLOW N/A 304W 217 REACTOR ENCLOSURE DISCH FLOW NIA 304W 217 REACTOR ENCLOSURE DISCH FLOW NfA 304E 217 REACTOR ENCLOSURE LOW N/A 304W 217 REACTOR ENCLOSURE LOW N/A 304E 217 REACTOR ENUILOSURE DISCH FLOW N/A 304W 217 REACTOR ENCLOSURE CISCH FLOW N/A 304E 217 REACTOR ENCLOSURE Norm state Equip Elav Reld State OPERABLE OPERABLE OPERABLE OPERABLE OPERABLE OPERABLE OPERABLE 256 OPERABLE OPE-ABLE 255 OPERABLE OPERABLE OPERABLE OPERABLE 217 OPERABLE OPERABLE 217 OPERABLE OPERABLE 217 OPERABLE OPERABLE 217 OPERABLE OPERABLE 217 OPERABLE OPERABLE 217 OPERABLE w DocurueM No. 0057-OOOSSCO Revision I Motive power Support System Supp Sys dwg Conrw power N/A WA N/A NZA NIA NIA N/A NIA N/A N/A N/A NIA NIA NWA N/A ICA NIA NIA MA NIA WA MIA N/A N/A Filter- Urd -I"or UnaComnmon" Sorted By Equipl10 Page 43 K C Dale: 6MJJ5%

Train R unit V

UnaeNo.0' 3=-i 1 9507 3 9508 3 1 9509 3 1 9510 3106 I 3219 3 2320 3 2314 Common 5701 3 Common 5751 3 Common 5702 Class Eval Req'd Function 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 a ACTIVE 5 DR ACTIVE a OR ACTIVE 5 BR ACTIVE 6 R PASSIVE 6 SR PASSIVE 6 B ACTIVE 6 B ACTIVE B B ACTIVE Equip ID PIMS ID FT-51-1 N05ZC FT-O51-lNO52C FT-51-I N052D FT-O51-INO52D FT-S5-iN00B FT-055'l1N008 FT-55-IN051 FT-0SS-INOSI FV-5n- 113 FV-050-113 FV-56-1 11 FV-O561 11 FV-56-112 FV-056-112 FV-C-DO -101A FV-C-DO-101A rV-C-DO-101B FV-C-DO-lOl B HO-S1-041A HO-081-041A 1-0-81-0416 HD4-081-041B HD--81-042A HO-081-042A Syste.im Notes N/A N/A WA N/A RCIC HPCI HPOl POST LOCA RECOMBINER S POST LOCA RECOMBINER 5 MISC.STRUCTURES

-YVAC MISC.STRUCTURES

-YVAC Mic.MISC.STRUCTURES

-HVAC 5 Equip Description ROB Mother Comp RHR PUMP C DISCH N RHR PUMP D DISCH F HPC1 PUMP LOOP FLC HPCI PUMP LOOP FLX STEAM SUPPLY TO RI 1JS212 HPCITURO CONTROL 10.211 HPCI TURB STOP VALI 10S211 A CNTMT H2 RECOMB PCIV (OUTBRD SUCTI'8 CNTMT H2 RECOMB PCIV (OUTBD SUCTIOJ SPRAY POND AIR SUP 0AV543 SPRAY POND AIR SUP nBV543 SPRAY POND AIR SUP CAV543 UUERIOK GENERATING STATION IPEEE PROJECT coomen No. 0O6?-COS8ODC2 UNIT I & COMMON Alt AU'UA SUCCESS PATH COMPONENT LIST (SPCLJ Revision I Drawing No. Room No. Norm slate Moive power Supporl System Supp Sys dwg Room Elov Equip Etar Building Reqd Slate Conh" power LOW N/A 304W OPERABLE NA 217 217 REACTOR OPERABLE NIA ENCLOSURE LOW N/A 304E OPERABLE N/A 217 217 REACTOR OPERABLE NIA ENCLOSURE 4W N/A Ill OPERABLE N/A 177 177 REACTOR OPERABLE N/A ENCLOSURE W NWA 111 OPERABLE N/A 177 177 REACTOR OPERABLE N/A ENCLOSURE CIC TURBINE M-51, Sht 1 108 OPEN NIR 177 177 REACTOR THROTTLING NIR ENCLOSURE VALVE M-56, SHT 1 109 CLOSED N/A 177 177 REACTOR THROTTLING NfA ENCLOSURE/E M-S56, SHT 1 109 CLOSED NIA 177 17 REACTOR OPEN 1BD102 ENCLOSURE INLET OUTBRD M-57, SI-T 2 NR CLOSED N/R ON) D134-R-H-0B 283 REACTOR CLOSED NIR ENCLOSURE INLET OUT"RD M-57. SHT 1 506 CLOSED N/R N) D244-R-H-C6 283 283 REACTOR CLOSED NIR ENCLOSURE'FAN OAV543 M-81, Sht 5 1000 WA nIYS01 268 SPRAY POND FUMP OPEN/CLOSED OIY50l STRUCTURE FAN 06V543 M-81, Sht 1 1005 N/A 02Y501 268 S-RAY POND PUMP OPEN/CLOSED 0ZYSO1 SIRUCTURE FAN OAV543 M-81, Sht 1 1000 N/A DYS,01 265 SPRAYPONOPUMP OPEN/CLOSED 0IY50I STRUCTURE Fifter Unit = "1" or Unit -"Common' Sorled By Equip ID r r r ..- -.-. ... ................., Wi?;. *

-OR 2.0 ULIERICK GENERAVING STAl:ON WUE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Doeumerrt No. 9O6740008am tehmeiint A Resieon I Page 44 Oate: S6BBS Train Class Equip ID System Equip Description Drawing No. Room No. Norm state Motive power Support Syr'tm Supp SYS dWg Unit Eval Ret'd Room Elev Equip Rlev Line Nix Function PIMS 1D Notes 3 Common 5752 Common 5531 2 Common 581 Common 5532 2 Common 5632 1 Common 5575 1 Common 5690 1 Common 5637 2 Common 5649 1 Common 5582 2 Common 5688 Common 5587 S B ACTIVE a R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE S SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE S SR ACTIVE 5 SR ACTIVE HD-81-0425 HD.-081-0425 HV-11-O11A HV-011-0IIA HV-11-0118 NV-011-0Cl18 NV-11-OISA HV-011-015A WV-11-0155 HV-011-015B HV-11-041 WV-O-104 HV-1 14342 WV-011-042 W-110-43 HV-O1l-43 HV-11-044 WV-011-044 HV-11-046 HV-011-046 NV-11-047 HV-0tl-047 HV-11-448 HV-011-048 MISC.STRUCTURES

-ESW ESW ESW ESW 22 ESW 10 ESW ESW 23 E5W 24 ESW 25 ESW ROB Mother Comp SPRAY POND AIR SUC FAN 0RV543 0RV/543 ESW "A DISCH. TO SPRAY PONDOCLG TOWER (PONDJTOWER RETURN A)ESW LOOP'B' DISCH. TO RHRISW LOOP A (POND/TOWER RETURN B)ESW A" DISCH. TO SPRAY PUNDICLG, TOWER (POND/TOWER RETURN C)ESW'"B" DISCH. TO SPRAY PONDICLG.TOWER (POND/TOWER RETURN D)UNIT 1 Oh/I SFG0 EQUIP A RET (UNIT 1 RETURN)HPCI PP RM. CLIA RET. TO ESW LOOP B" (UNIT I RET LOOP B)HPCI PP RM CLR RET TO SERV WATER (UNIT I RETUIh SW" UNIT I DIV 2 SFGD EQUIP ESW"B" RET.(UNIT I RETURN)A LOOP ESWRRET FROM UD2 SFGD EQUIP RM CLRS (UNIT 2 RETURN)B LOOP ESW RET FROM UR2 SFG0 EQUIP RM CLRS (UNIT 2 RETURN)U12 RCIC RM CLR SW RET (UNIT 2 RET ur2 Sw)M-I,81.1Sil M-I1, Ste 1 M-11. Sht 1 M-11, Slit I M-11, Sht I M. 1, Sht 2 M-1l. Shit2 M-11. Sht 2 M-11. Sidt3 M-1 1. Sht 4 M-11, Shl 5 M-1l, Sht 5 Building 1005 268 SPRAY POND PUMP STRUCTURE 202 198 REACTOR ENCLOSURE 202 198 REACTOR ENCLOSURE 202 198 REACTOR ENCLOSURE 202 108 REACTOR ENCLOSURE 203 201 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 207 201 REACTOR ENCLOSURE 284 201 REACTOR ENCLOSURE 281 201 REACTOR ENCLOSURE 279 201 REACTOR ENCLOSURE Reqfd State N/A OPENICLOSED OPEN 201 OPEN OPEN 201 OPEN OPEN 201 OPEN OPEN 201 OPEN CLOSED 201 OPEN CLOSED 177 OPEN OPEN 17n CLOSED CLOSED 201 OPEN CLOSED 201 OPEN CLOSED 201 OPEN OPEN 201 CLOSED Contr power 02Y501 02Y1SOI NIR NIR N/R N/R N/R NMR NIR N/R N/R 10Y101 N/R 10Y102 N/R 10Y102 NMR 10Y102 NIR 2DY101 NIR 2OY102 NMR 20Y101 Filter. Unit ="1 or Unit = tCammon" Sorted By Equip ID Ts M M1 0 LIMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST ESPCL)a Document Noe.an A Revision 1 Page 45 Dole: 60095 Train Closs Equip ID Sys:am Equip Oescriptin Drawing No- Room No. Norm state Motive power Support System Supp Sys dwg Unit Eval Reqd Room Elav Equip Elav Line No. Function PINS IM Notes ROB Mother Comp Butnig Req'd State Contr power 1 5 HV-11-O49 ESW U/2 RCIC RM CLR ESW RET LOOP A M-1 1, Sht S 279 CLOSED NIR Common SR (UNIT 2 RET LOOP A) 201 201 5585 ACTIVE V.011-049 21 REACTOR OPEN 20Y101 ENCLOSURE 5 HV-11-OSIA ESW CONT. RM. CHILLER A RET TO UNIT 2 M-11. Sh 2 268 CLOSED N/R Common R SERV WATER (RETURN UNIT 2 SWM 200 200 5573 PASSIVE HV-011-OSIA 7 CONTROL CLOSED NMR 5TRUCTURE 2 5 HV-11-OS5B ESW CONT. R. CHILLERS RET. TO UNIT2 M-11, Sht 2 253 CLOSED MR Common R SERV WATER (RETURN UNIT 2 SW) 200 200 5646 PASSIVE HV-O11-051B 3 CONTROL CLOSED NMR STRUCTUJRE 15 HV-11-055A ESW CONT. RM. CHILLER A RET. TO UNIT 2 M-11. Sht 2 258 CLOSED NIR Common R SERVICE WATER 200 200 5572 PASSIVE HV-01It-055A 7 CONTROL CLOSED NR STRUCTURE 2 5 HV-11-0558 ESW CONT. RM. CHILLER BRET. TO SERVICE M-11tSht2 258 CLOSED NMR Common R WATER (RETURN UNIT 2 SW) 200 200 5647 PASSIVE NV-O11-055B 3 CONTROL CLOSED N!R STRUCTURE 1 5 NV-1 1-071 ESW UNIT 1 DIV I SFGD EQUIP ESW"A" RET. M-11, SN 2 203 CLOSED N/R Common SR (UNIT 1 RETURN) 201 201 5577 ACTIVE HV-011-4171 22 REACTOR OPEN 10Y103 ENCLOSURE 1 5 HV-11-072 ESW HPCI PP RM. CLR. RET TO ESWLOOP M-11, Sht 2 109 CLOSED NIR Common SR '8" (UNIT 1 RET LOOP B) 177 177 5691 ACTIVE HV-011-072 REACTOR OPEN 10Y104 ENCLOSURE 1 5 HV-1 1-73 ESW HPCl PP RM. CLR RET. TO SERV. M-1 1. Sht 2 109 OPEN N/R Common SR WATER (UNIT I RET UII SW) 177 177 5635 ACTIVE HV-011-073 10 REACTOR CLOSED 10Y104 ENCLOSURE 2 5 HV-11-074 ESW UNIT i DIV 2 SFGD. EQUIP ESW"B" M-11. Sht 3 207 CLOSED NMR Common ,SR RET. (UNIT 1 RETURN) 201 201 5648 ACTIVE HV-011-074 23 REACTOR OPEN 10Y104 ENCLOSURE 1 5 HV-11-076 ESW A LOOP ESW RET FROM U/ SFGD M-11, Sht 4 284 CLOSED NMR Common SR EQUIP RM CLRS (UNIT 2 RETURN) 201 201 5583 ACTIVE HV-011-076 24 REACTOR OPEN 20Y103 ENCLOSURE 2 5 HV-11-077 ESW B LOOP ESW RET FROM U/2 SFCO M-11. ShI 5 281 CLOSED N/R Common SR EQUIP RM CLRS (UNIT 2 RETURN) 201 201 5687 ACTIVE HV-011-077 25 REACTOR OPEN 20Yt04 ENCLOSURE 1 5HV-11-078 ESW U2 RCIC RM CLR SW RET (UNIT 2 RET M-11. Sht 5 279 OPEN N/R Common SR U2 SVf 201 201 5588 ACTIVE W-011-"71 R REACTOR CLOSED 20Yt03 ENCLOSURE Filer. Unit= "1"or Unit: "Common" Sorted By Equip ID 03.rc .: .I-mV Page 46 Date: WMS9 mV IMERICK GENERATING STAlION IPEEE PROJECT UNIT1 & COMMON SUCCESS PATH COMPONENT LIST (SPCL)WV Docmet No. OW4000-CG1 AttachmaenIA Revision I Tain Class Equip ID System Equip Descriplion Drawing No. Room No. Norm slate Unit Eval Re'd Room Elev Equip Elev iUne No. Function PIMS ID Notes I Common 6692 5693¶1 5659 5592 2 1 5551 2 1 5661 5593 2 1 5662 5 SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE S SR ACTIVE S SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE S SR ACTIVE 5 SR ACTIVE S SR ACTIVE V-1 1-079 NV.-11-079 NV-11-103A NV-a 1-103A NV-11-103B WV-011-103B NV-i 1-104A HV-011-104A V-I-I-104B HV-011-1043 WV-ii-104C HV-011- 040 HV-11 -104D WV-0l1-104D NV-11t-104E HV-011-104E WV-11-104F NV-011-104F WV-11-104G HV-011-104G HV-11-104H WV-.l11-104H ESW 21 ESW ESW ESW ESW ESW ESW ESW ESW ESW ESW ROB Mother Comp UI2 RCIC RM CLR ESW RET LOOP A (UNrT2RETLOOPA)

I.OCI PP RM CLR A SUP VLV HPCI PP RM ULR B SUP VLV RHR PP RM CLR A SUP VLV RHR PP RM CLR B SUP VLV RHR PP RM CLR C SUP VLV`RHR PP RM CLR O SUP VLV RI-HR PP RM CLR E SUP VLV RHR PP RM CLR F SUP VLV RHR PP RM CLR G SUP VLV RHR PP RM CLR H SUP VLV M-1l. ShI S M-11. Sh12 M-11, SN 2 M-11,Sht2 M- 1. Shlt 3 M-1 1. Sh12 M-11, Sh 3 M-1 1. Sill2 M-1 1. Shi 3 M-11, Shl 2 M-1.- Sht 3 Building 279 201 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 102 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSx1RE 102 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE 102 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE 102 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE Req'd Slate CLOSED 201 OPEN CLOSED 177 OPEN CLOSED 177 OPEN CLOSED 177 OPEN CLOSED 177 OPEN CLOSED 177 OPEN CLOSED 177 OPEN CLOSED 177 OPEN CLOSED 177 OPEN CLOSED 177 OPEN CLOSED 177 OPEN Motive power Support System Conr" power NIR 2OY103 NMR 101212 NIR 105212 NIR 10B211 NMR 10H212 NR 10B217 NMR 105218 N/R 10B211 NMR 10B212 NIR 105217 N/R 106218 Supp Sys ding s HV-11-106A ESW RCIC PP RM CLR A SUP VLV M-11. Sht 2 10i CLOSED N/R 1 SR 177 177 5556 ACTIVE HV-011-10oA REACTOR OPEN 10B211 ENI COW RE" Jtar Unit'"orUn=CommorC SmlodByEquipIO r.-."

UMERICK GENERA11NG IOR IPWEED PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCL)Doaumt No. w 4i=som AttReacnltA Revision I Page 47 Dale: 6199.5 Train Class Equip ID System Equip Descripton Drawing No. Room No. Norm slate Moltve power Support System Supp Sys dw9 Unit Eval Reqid Room Elev Equip Elev Line No. Functlon PIMS ID Noles 1 5557 5502 5575 1 5574 2 1 5651 2 1 2 1 5638 5 SR ACTIVE 6 R PASSIVE 5 SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE 5 R PASSIVE V-11-106B HV'-011-1068 WV-11-l07 NV-011-107 W'V-11-121 I-IV011-121 KV-11-123'V-011-123 HV-11-125 NV-011-125 NV-11-126 NV-011-126 WV-11-128 HV-011-128 ESW ESW ESW 8 ESW a ESW 13 ESW 13 E-W ROB Mother Comp RCIC PP RM CLR B SUP VLV ESW'A"TO UNIT 1 TECW HEAT EXCHANGER (UNIT I SUPPLY)ESW LOOP "A" RETURN TO UNIT I SERV WATER (UNIT 1 RET UlI SW)E5W LOOP "A RETURN TO UNIT I SERVICE WATER (UNIT 1 RET UI1 SW)ESW LOOP "B RETURN TO UNIT 1 SERVICE WATER (UNIT I RET UI1 SW)ESW LOOP "B" RETURN TO UNIT 1 SERVICE WATER (UNIT I RET U11 SW)ESW"BrTO UNIT I RECW HEAT EXCHANGER (UNIT 1 SUPPLY)ESWTO DIESEL GEN HTXS ESW TO DIESEL GEN HTXS ESW TO DIESEL GEN tT.VS ESW TO DIESEL GEN IT-'S 1A DIESEL GEN A LOOP A ESWOUT Building Req'd State Cony power M-1i1, S1 2 M-1 1, Sit 1 M-11. Sht2 M-1l. Sht2 M--Il. Shlt3 M-1 1, Sht3 M-11. Shl 3 108 177 REACTOR ENCLOSURE HR 203 201 REACTOR ENCLOSURE 203 201 REACTOR ENCLOSURE 207 201 REACTOR ENCLOSURE 207 201 REACTOR ENCLOSURE 207 2DI REACTOR ENCLOSURE CLOSED 177 OPEN CLOSED CLOSED OPEN 201 CLOSED OPEN 201 CLOSED OPEN 201 CLOSED OPEN 201 CLOSED CLOSED 201 CLOSED MIR 10B211 NMR NMR NMR 1GY101 MIR 10Y103 NIR 10YI02 N/fR 1OY104 N/R NIR 3 6 HV-11-131A ESW I R 5506 PASSIVE WV-011-131A 12 M-11, Sht 1 311A OPEN NMR 217 217 DISELGENERATOR OPEN IRr ENCLOSURE 3 1 5603 3 1 5513 3 1 56O4 3 5508 6 R PASSIVE a R PASSIVE B R PASSIVE 6 R PASSIVE NV-1 1-131B WV-O11-131B HV-11-131C H-V-OII-13tC HV-11-131D HV-01l-131D-W-I 1-132A NV-O11-I32A ESW 12 MSW 12 ESW 12 ESW M-1 1. Silt 1 M-11, Shlt 1 M-11. Shtl 1 M-1l, Shl 1 311B 217 DIESEL GENERATOR ENCLOSURE 311C 217 DIESEL GENERATOR ENCLOSURE 311D 217 DIESELOGEERATOR ENCLOSURE 311A 217 DIESE. GENERATOR ENCLOSURE CLOSED 217 CLOSED OPEN 217 OPEN CLOSED 217 CLOSED OPEN 217 OPEN N/R N/FR WR N/ft NMR MR N/R NMR NMR Filter Unit = "1"or Unit = Common" Sorted By Equip ID U Page 40 Date: 6W195 Train 5 : Unit E Line No.S 3 67 3 I 5606 3 511 5507 3 S14 5611 3 11 5509 3-1.' 5615 3 1 616 Common 4500 2 Common 4600 Common 4502 0 UMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Docuamtrt No. 00174D0UCONW Atladonlin A RevWsio I Class Equip ID System Equip Description Drawing No. Room No. Norm state Motive power Support System Supp Sys dwg Evel Reqd Room Elav Equip Elev Function PIMS ID Notes ROB Mother CompPiMS ID Notes ROB Mother Comp 6 NZA PASSIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE 26 R PASSIVE 26 R PASSIVE 26 R PASSIVE HV-11-132B HV-011-1328 HV-11-132D HV-01 1-1320 WV-11433A HV-t 1-133A HV-I 1-1338 HV-1 1-1338 NV-I 1-133C HV-011-133C-V-11-i 33D HV-O11-133D KV-11-134A HV-011-134A HVW11-134B HIV--i1-1340 WV-11-134D HV-011-134D NV-12-003A WN-012-003A NV-12-0039 HV-012-03B HV-12-003C WV-012-003C ESW ESW ESW 12 ESW 12 ESW 12 ESW 12 ESW ESW ESW RHRSW RHRSW RHRSW 15 DIESEL GEN B LOOP A ESW OUT 1D DIESEL GEN 0 LOOP A ESW OUT ESWTO DIESEL GEN HTXS ESWTO DIESEL GEN HTX'S ESWTO DIESEL GEN HTX'S ESW TO DIESEL GEN HTXS 1A DIESEL GEN A LOOP ESW OUT I DIESEL GEN B LOOP B ESW OUT ID DIESEL GEN D LOOP B ESW OUT RHR SW/ESW WETWELL INLET GATE A (GATE A)RHR SW/ESW WETWELL INLET GATE B (GATE 8)RHR SW/ESW WETWELL INLET GATE C (GATE C)M-11, Shl I M-1 1. Sh 1 M-11I, Shl I M-1 1, Sht 1 M-11, Shtl 1 M-11. Sht I M-11. Sht I M-11, Sirt 1 M-11, Shli 1 M-12 M-12 M-12 Bulding Req'd State 3118 CLOSED 217 217 DIESEL GENERATOR CLOSED ENCLOSURE 3110 CLOSED 217 217 DIESEL GENERATOR CLOSED ENCLOSURE 311A CLOSED 217 217 DIESELGE?4ERATOR CLOSED ENCLOSURE 311B OPEN 217 217 DIESEL OENERATOR OPEN ENCLOSURE:11C CLOSED 217 217 DIESEL GENERATOR CLOSED 3110 OPEN 217 217 DIESEL GENERATOR OPEN ENCLOSURE 311A CLOSED 217 217 DIESEL GENERATOR CLOSED ENCLOSURE 3118 OPEN 217 217 DIESEL GENERATOR OPEN ENCLOSURE 311D OPEN 217 217 DIESEL GENERATOR OPEN ENCLOSURE 1000 OPEN 268 273 SPRAY POND PUMP OPEN STRUCTURE 1005 OPEN 268 273 SPRAY POND PUMP OPEN STRUCTURE 1000 OPEN 268 273 SPRAY POND PUMP OPEN STRUCTURE Contr power N/R N/R NaR NIR I, R N/R NIR NaR N/R NIR N/R NIR N/R N/R N/R Nat NIR N/R N/R NIR NR NR NIR NIR Filter Unit = 1"or Unit= "Common' Sorted By Equip ID

-US , Page 4S-. .. Datar SIM/_. Tran Unit In LineNo.2Common* 4802 Common 4515 2 Common 4614.: 1 Common 4516 2" Com-ron 4615 Common 4517 2 Common 4516 1 Common S 4518 Common 4610 1!! Common 4519 2 Common 4617-Common* 4520, 4619 III lClass Eval Reqcd Function 26 R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 SR ACTIVE 6 SR ACTIVE 6 R PASSIVE 6 R PASSIVE 6 SR ACTIVE 6 SR ACTIVE 6 SR ACTIVE S SR ACTIVE 6 N/A PASSIVE Equip ID PIMS ID HV-12,OOSD HV-012-0030 HV-12-017A HV.012-O17A HV-12-017B HV-012-017B HV-12-031A IV-012-031A HV-12-031B HV-012-031 B HV-12-031C HV-012-031C HV-12-031D HV-O12O031D WV-12-032A HV-012-032A HV-12-032B HV-012-032B HIV-12-032C HV-012-032C HV-12-032D HV-012-032D HV-12-034A HiV-012-034A System Notes RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW RHRSW 26 RHRSW RHRSW 6 0 LIMERICK GENERATING STATION WEEIE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Equip Description Diwing No. Room No.Room Elav ROB Mother Camp Building RHR SW/ESWWETWELL INLET GATE D M-12 1005 (GATE D) 26 SPRAY POND PUMP STRUCTURE RHR SWTO CLGTWRS CROSSTIE M-12 1010 (TWR 1 R -'R 2) 251 SPRAY POND PUMP STRUCTURE RHR SWTO CLG. TOWER CROSSTIE M4I2 1015 ('rlRl -TWR2) 251 SPRAY POND PUMP STRUCTURE SPRAY NOZZLES A & C BYPASS (SPRAY M-12 1010 BYPASS A/C) 251 SPRAY POND PUMP STRUCTURE SPRAY NOZZLES B & D BYPASS (SPRAY M-12 1015 BYPASS B/D) 251 SPRAY POND PUMP STRUCTURE SPRAY NOZZLES A S C BYPASS (SPRAY M-12 1010 BYPASS AC) 251 SPRAY POND PUMP STRUCTURE SPRAY NOZZLES B & D BYP.ASS (SPRAY M-12 1015 BYPASS BID) 251 SPRAY POND pUMP STRUCTURE SPRAY NOZZLES A INLET (SPRAY INLET M-1:" 1010 A) 251 SPRAY POND PUMP UTRUCTURE SPRAY NOZZLES B INLET (SPRAY INLET M-12 1015 B) 251 SPRAY POND PUMP STRUCTURE SPRAY NOZZLES C INLET(SPRAY INLET M-12 1010 C) 251 SPRAY POND PUMP STRUCTURE SPRAY NOZZLES D INLET (SPRAY INLET M-12 1015 D) 251 SPRAY POND PUMP STRUCTURE RHR SWTO SPRAY NOZZLES M-12 NR CROSSTIE (SPRAY A/C SPRAY BID)0 Document No. 0067re t-0 AitUsin IA Reision 1-.-j Norm state Equip Elav Reqd State OPEN 273 OPEN CLOSED CLOSED CLOSED CLOSED OPEN 258 OPEN/CLOSED OPEN 256 OPEN/CLOSED OPEN 256 OPEN OPEN 255 OPEN CLOSED 256 OPEN/CLOSED CLOSED 256 OPENICLOSED CLOSED 256 OPEN/CLOSED CLOSED 256 OPEN/CLOSED CLOSED 256 CLOSED Motive power Support System Conr power NIR NMR NR NIR NMR N/R 008519 008519, 1AD162 008520 008520 N/R N/R N/R NOR 008519 005519, 1AD162 00B520 008520 005521 0OBS21, 2CD162 0B522 000522 N/IR N/R Supp Sys dwg Filter: Unit c"1oOr Unit ="Common" Sorted By Equip ID Page 50~02G;ur Train<,@, , Unit viC B.'s : Line No.0o.)4514.3 I 2400 3*1 2201 j,,* 3* 2201 3 2202 3 2202 ,S b i.-:-I r3127 3 2208 3 2209 3 ,_,, ., 2202 312 2210 3 1-2211 1 UIMECK GENERATING STATION IPEE PROJECT UNIT I & COMMON SUCCESS PATh COMPONENT LIST (SPCL)Donusmeo No. 00074 RevIsion I Class Equip ID System Equip Description Drawing No. Room No. Norm state Motive power Support System Supp Sys dwg Eval Re.d Room SFlv Equip Elev Function 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 NIA PASSIVE 6 R PASSIVE 5 R PASSIVE 6 R PASSIVE S SR ACTIVE 5 SR ACTIVE S SR ACTIVE PIMS ID Notes ROB Mother Comp hV-12-111 RHRSW RHR S/W TO UNIT 1 CLG TOWER (IWR M-12 I RETURN)HV-012-111 HV-40-IFODIB MSIV-LCS 1B MStV LEAK CONT INBRD BLEED PCIV M-40, Sht I (A)-V.040-1FOOIB HV-40-1F00IF MSIV-LCS IF MSIV LEAK CONT tNBRD BLEED PCIV M-40. Sht 1 (B)HV-040-1FOM1F HV-40-1F001K MSIV-LCS 1K MSIV LEAK CONT INDRO BLEED PCIV M-40, Sht 1 (C)HV-040-IFOOIK HV-40-1FOO1P MSIV-LCS IF MSIV LEAK CONT INBRD BLEED PCIV M40, Sht I ID)KV-040-1FOO1P HV-41-1098 NUCLEAR BOILER I B RX FD WTR LINE FLUSHING PCIV (B) M-41, Shti 1 HV-041-109B 1I HV-41-11F001 NUCLEAR BOILER NUCLEAR BOILER SYSTEM HEAD VENT M-41, SHT I VALVE (RAD WASTE)WV-041-IFOD1 HV-41-1F0t18 NUCLEAR BOILER IB RX FW INSRO. MAINTENANCE VLV. (B) M-41, Sit 1 HV-041-1FOl1B 20 HV-41 .1 FO16 NUCLEAR BOILER MAIN STM LINE DRAIN INBOARD PCIV M-41. SHT 2 (STEAM DRAINS INBOARD)HV-041-1 FO16 HV-41-1F022A NUCLEAR BOILER 'A MAIN STM ]SOL VLV INBD PCIV (MAIN M4l1, SHT 2 STEAM INBOARD A)HVk041-1F022A HV-41-1F022B NUCLEAR BOILER 'B' MAIN STM ISOL VLV INSD PCIV (MAIN M-41, SHT 2 STEAM INBOARD B)WV-041-1F022B V-41 -1F022C NUCLEAR BOILER 'C' MAIN STM ISOL VLV INK' PCIV (MAIN M-41, SNT2 STEAM INBOARD C)HV.O41-1F022C Building NR 407 253 REACTOR ENCLOSURE 407 253 REACTOR ENCLOSURE 407 253 REACTOR ENCLOSURE 407 253 REACTOR ENCLOSURE 518 279 REACTOR ENCLOSURE 40D 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE Req'd CLOSED CLOSED CLOSED 272 CLOSED CLOSED 272 CLOSED CLOSED 272 CLOSED CLOSED 272 CLOSED CLOSED 2a3 CLOSED CLOSED 313 CLOSED OPEN 286 OPEN CLOSED 253 CLOSED OPEN 273 CLOSED OPEN 273 CLOSED OPEN 273 CLOSED Corr power N/R NMR NIR NIB NM N/R NIR NIR NMR NMR NIR NMR NMR N/R NIR N/R NMR NMR NIR NM NIR NfR NIR NIR Filter. Unit :"ior Unit = "Common" Sorted By Equip ID DPage ,51 Co : Date.' SMIF95-p Train unit ULne No.9" 3 2212 3128* 1 3129 3* 1i 2213 3101.,-. 1* 3102 3123-3125 3121 3124.. I 3116 3115 Document No. ODS7-ONa -cmm ARelsl n A Rev~sion 1 UMERICK GENERATING STATION IPEEE PROJECT UNITI & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Class Equip ID Systam Equip Descriptlon Drawing No. Roorm No. Norm state Motive power Support System Supp Sys dwg Eval Req'd Room Eltv Equip E1ev Function 5 SR ACTIVE 6 SR PASSIVE 5 SR PASSIVE S S ACTIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 SR ACTIVE 6 SR ACTIVE S PASSIVE S SR ACTIVE 6 SR ACTIVE PIMS ID Noles ROB Moiher Camp HV-41-1F022D NUCLEAR BOILER 'D' MAIN STM ISOL VLV INBD PCIV (MAIN MA. SHT 2 STEAM INBOARD D)HV-041-IF022D WV-41-1F0321 NUCLEAR BOILER LOOP B FD WTR INLET CHECK PCIV M-Al, Sht 1 (INLET S)HV-041-1 F0328 12 HV-41-1F0745 RtCC 'B' FEEDWATER LOOP SUPPLY OUTBRD M41. Sht I PCIV (CHECKB)HV-041-1F074B HVA4-1 F001 RWCU RX WTR CLEANUP INBOARD PCIV M-44. Sht I (INBOARD)WV-044-1 FOOl HV-49-1FO07 RCIC RCIC MAIN STEAM SUPPLY INBRD PCIV M-49, Shl 1 (INBOARD)HV-049-1FOO7 HV-49-1F008 RCIC RCIC STEAM LINE OUTBOARD PCIV M-49, Sht 1 (OUTBOARD)

WV-049-IFOOS WV-49-1F012 RCIC RCIC PP. DISCH. OUTBOD. ISOLVLV, M-49, Sht 1 (DISCHARGE)

V-49-1FI 012 HV-49-1F013 RCIC RCIC PP. DISCH INHRD PCIV (FEED) M-49, Sht 1 HV-049-1F`013 HV-49-IF019 RCIC RCIC PUMP MIN FLOW PCIV (MIN FLOWj M-AS. Sht 1 HV-049-1 F01 9 HV.4-1F022 RCIC RCIC FULL FLOW TEST VLV. (TEST ISOL) M-49 Sht I MV-049-1F022 WV-IS-1F029 RCIC RCIC PP. SUCTION FROM M-49. Sht I SUPPRESSION POOL (SUPP POOL SUCTION)HV-049-1F`029 WV-.4-IF031 RCIC RCIC PUMP SUCTION FROM SUPP POOL MA-9, Sh ¶PCIV (SUPP POOL)WV-049-1F031 Building 400 237 REACTOR ENCLOSURE 518 279 REACTOR ENCLOSURE 518 279 REACTOR ENCLOSURE 400 237 REACTOR ENCLOEU.e 400 237 REACTOR ENCLOSURE 309E 217 REACTOR ENCLOSURE 200 201 REACTOR ENCLOSURE 407 253 REACTOR ENCLOSURE 203 201 REACTOR ENCLOSURE 200 2131 REACTOR ENCLOSURE 108 177 REACTOR ENCLOSURE 108 177 REACTOR ENCLOSURE Rarfd State OPEN 273 CLOSED CLOSED 279 CLOSED OPERABLE 279 OPERABLE OPEN 286 CLOSED OPEN 238 OPEN OPEN 217 OPEN OPEN 201 OPEN CLOSED 279 OPEN CLOSED 201 OPENICLOSED CLOSED 201 CLOSED CLOSED 177 OPEN CLOSED 181 OPEN Conlr power NMR NIR NIR NIR NR NR 10B211 10B211 NR NIR NR NIR NR NMR 100201 10D201, 1AD102 10D201 10D201, 1ADI02 NrR NMR 10D201 100201, 1AD102 10D201 100201, 1AD102 Filter Unit = "l"o Unit = 'Common" SortedByEquip1D

.rý LIMERICK GENERAIING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCL)Page 52 Date; 6J/S95 Documiel N40 0067ve111=0 Aftaclanisit A Revisin I Train Class Equip ID System Equip DescnpLion Drawing No. Room No. Norm state Unit Eval Req'd Room Elnv Equip Etev Line No. Funcion 3110 1 1 3111 1 1 3118 1 1 31205 4104 1 3114 2 1 3406 1 311 1 2 1 4200.4840 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE S SR ACTIVE 6 SR ACTIVE 6 SR ACTIVE 5 R PASSIVE S R PASSIVE B R PASSIVE 6 R PASSIVE PIMS ID HV-49-1F060 HV-049-1 FO00 HV-049-1 FOs HV-49-F18034 HV-049-1FP084 HV-50-112 HV-050-112 WV-50-I F045 V-050-1F045 HV-S0-1F046 HV-050-IFU46 KV-51-1OSA HV-01-1OSA WV-51-105B HV-SI-105B XV-051-1DSB HV-51-125A HV-OS1-125A HV-51-125B HV-051-125B H-V.51-153A HV-01-ISSA HV-S1-153B HV-0S1-153B Notes RClC RCIC RCIC RCIC RCIC RCIC RHR RHR RHR RHR HPCI B HPCI 6 ROe Mother Comp RCIC TURBINE EXH PCTV (EXHAUST)RCAC TURB EXHAUST LINE VAC. BlKR PCIV (OUTBOARD)

RCIG TURB EXHAUST VACUUM BREAKER PC (IVNBHOARD)

REACTOR CORE ISOLATION COOUNG TURBINE TRIP THROTTLE VALVE RCIC STM. SUPPLY VLV. (INLET)RCIC LUBE OIL CLG WrR. SUPPLY VLV.(COOLING WATER)IC RHR PP. MIN. FLOW BYPASS PCFV (MIN FLOW C SHUTOFF)1D R14R PP. MIN. FLOW BYPASS PCIV (MIN FLOW D SHUTOFF)RJR LOOPS A & C FULL FLOWTEST$)0 PCIV (RETURN)RHR LOOPS 8 & D FULL FLOWTEST S3O PCIV (RETURN)HPCI STM. TO 'IA RHR H'XI BPV (SUPPLY BYPASS)HPCI STIL TO 'IBW RHR HTX. BPV (SUPPLY BYPASS)M49. Shl 1 M-49. Sthl M40. Shl I M-50. Sht I M-S0. Sht 1 M-50. Sht I M-51, SHT 1 M-51. Sht 3 M-S1. Sht l M-51. Sht 3 M-51, SHT2 M-S1,SHT4 Buiding 269 201 REACTOR ENCLOSURE 203 201 REACTOR ENCLOSURE 203 201 REACTOR ENCLOSURE 108 177 REACTOR ENCLOSURE 108 177 REACTOR ENCLOSURE 105 177 REACTOR ENCLOSURE 203 201 REACTOR ENCLOSURE 204 201 REACTOR ENCLOSURE 3D4W 217 REACTOR ENCLOSURE 304E 217 REACTOR ENCLOSURE 309W 217 REACTOR ENCLOSURE 309W 217 REACTOR ENCLOSURE Reld State OPEN 201 OPEN OPEN 201 OPEN OPEN 201 OPEN OPEN 177 OPEN CLOSED 177 OPEN CLOSED 177 OPEN OPEN 201 OPEN OPEN 201 OPEN OPEN 217 OPEN OPEN 217 OPEN Motive power Supporl System Contr power NIR NUR N/fR N/R NfR NhR 101201 10D201, IAD102 10D20l 100201, 1AD102 100201 100201, 1A1=02 NIR NfR NIR N/R NIR NMR N/fR NR NfR NM NIR NIR Supp Sys dwg 3 6 N/A 3323.2220, 4116. PASSIVE 4313,4712 3 R I N/A 3325. 2221, 4215. PASSIVE 441S.4815 CLOSED 217 CLOSED CLOSED 217 CLOSED Pter. Unit= orUnit -"Commorn Sorted By Equip ID

.. ..- .. ...-............ ..... ..

cnG ii Page 53 i* Date: OW9S* Train Unit ULineN.~45DS'- 2¶ 1 4W6 340B, 4113,4310, 4709 2 1 3207.4212.

4412.4812 4119.4317.4716 4218,4418,4818 4102.4304.

4703 2 4202 4402. 4802 2-1 3402 2 , 1 3202.! 4103.4303 4302 LIhIERICK GENERAThG SAiON IPEEE PROJECT UNIT I &COMMON SUCCESS PATH COMPONENT LIST (SPCL)Class Equip ID SytAm Equip Description Drawing No. Room No. Norm state Eval Reqd Room Elev Equip Elav Dcaument No. m0"4011164w Reviasio 1 Function PIMS ID Notes 5 R PASSIVE 5 R PASSIVE 6 NIA PASSIVE 6 N/A PASSIVE 6 R PASSIVE 6 R PASSIVE 6 SR PASSIVE a R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 SR ACTIVE a R PASSIVE HV-51-157A HV-051-157A HV-St-157B HV-O51-157B HV-51-182A HV-OS1-182A WV-51-1 825 HVO51-182B HV-51-1i FI3A HV.O51-1FO3A NV-51-IFDO3B HV-051-1F0035 HV-51-1F04A HV-0S1-1FOO4A HV-51-IF0040 HV-O1-1F0048 WV-51-IFD04C HV-O51-1F(04C NV-51-1FO34D HV-O51-IF004D V-514-OMA V-051 -1iFOSA WV-51-1iFD0B HV-051-IF0065 RHR RHR RHR S RHR RHR RHR RHR RHR RHR Is RNR ROB Mothsr Comp 1A RHR HTX TUBE SIDE FLUSH INLET VLV.16 RHIR H-IX TUBE SIDE FLUSH INLET VILV.IA RHR HTX INLET FROM IC RHR PUMP ID RHR PP. DISCHARGE TO 1B RHRVV.1A RHR HTX. SHELL SIDu OUTLET VLV.(OUTLET)1B RHR HTX SHELL SIDE OUTLETVLV.(OUTLET)1A RHR PUMP SUCTION PCIV (SUCTION A)10 RHR PUMP SUCTION PCIV (SUCTION B)IC RHR PUMP SUCTION PCIV (SUCTION C)1D RHR PUMP SUCTION PCIV (SUCTION D)1A RHR PP. SO1 CLG. SUCT. INTERTIE VLV. (LOOP A SUCTION)18 RHR PP. S/D CLG SUCT. VLV. (LOOP B SUCTION)M-51. Sht 2 M-51, Sd 4 M-51, Sli 1 M-51, Sh! 3 M-51, Sl 2 M-51, Shl4 M-51. Sht I M-51. Sht 3 M-51, SNiT I M-51. Sht 3 M-51. Sht I wa-S, Sht 3 Building 203 201 REACTOR ENCLOSURE 204 201 REACTOR ENCLOSURE 309W 217 REACTOR ENCLOSURE 30EE 217 REACTOR ENCLOSURE 203 201 REACTOR ENCLOSLUFE 204 201 REACTOR ENCLOSURE 102 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE 102 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE 102'177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE Req'd Sta CLOSED 201 CLOSED CLOSED 201 CLOSED CLOSED 217 CLOSED CLOSED 217 CLOSED OPeN 201 OPEN OPEN 201 OPEN OPEN 177 OPEN/CLOSED OPEN 177 OPEN OPEN 177 OPEN OPEN 177 OPEN CLOSED 177 OPEN/CLOSED CLOSED 177 CLOSED Moaive power Support Systam Cont power NIR NMR NIR NIR NIR NMR NMR NMR N/R NIR N/R NMR 10B211 10B211,10Y101 N/R NMR NIR NMR NMR MR 10B211 10B211,1DY101 N/R NMR Supp Sys dwg ca Filter. Unit s "a or Unit = "Common" Sorted By Equip ID$: i77-- -- 7-P8ge 54 Data 8J/5is V UMERICK GENIERATING STATION WEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Document No. o0074S.CMON A iadimeo A Revision I TrCnlass Equi ID System Equip OaSeapllon Drhawkv No. Room No Norm stla Mo"ve power Support System Supp Sys dwg Unft Eva] Room Elav Equip Elev Line No. Function PIMS ED Notes ROB Mother Camp Builting Req'd Slate Coenr power 4105,4306, 4705 2 1 4204,4404.

4804 2 1 3405 2 1 3204 1 1 4301,4702 430M 2222 2 1 3409,4108, 4722 2 1 3208,4207, 4407, 4807 1 1 4106.4315,4714 2 1 4205.4405,4805 4504 2 1 4605 s SR ACTIVE 6 SR ACTIVE 8 SR ACTIVE 6 SR ACTIVE a SR ACTIVE 6 SR ACTIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE 6 R PASSIVE S SR ACTIVE 6 SR ACTIVE HV-51-1FOO7A HV-051 -1F007A HV-51-iFO07B HV-051-4FOO7B HV-S1-1F007C HV-O51-IFO07C HV-51-1F007D HV-O51-1FOOZD HV-51-1FO08 HV-,51-IFOOB HV-51-1F009 WV-O51-IF009 HV-S1-1 1FO1A HV-051-IFO10A HV-51-1FO10B HV-051-1F0108 HV-51-IF01 IA HV-O51-11F011A HV-S1-F1011B HV-O51-lFOIIB HV-51-4FO14A HV-051-I1F014A HV-5-1 F0148 HV-051-'F014B RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR IA RHR PP. MIN FLOWVLV. (MIN FLOW A)18 RHR PP. mIu. FLOW VALVE (MIN FLOWS)IC RHR PP. MIN- FLOWVLV (MIN FLOW C)1D RHR PP MIN FLOWVLV. (MIN FLOW D)RHR SHUTDOWN CLG SUCTION OUTBRD PCO (OUTBOARD)

RHR SHUTDOWN CLG SUCTION INERD PCIV (INBOARD)IC RHR PP. FULL FLOW TEST RETURN VLV. (FLOWTESTC) 10 RHR PP. FULL FL OWTEST RETURN VLV. (FLOWTEST D)iA RHR HTX FLUSH LINE TO SUPP POOL (TO SUPP POOL RETURN)18 RHR HTX. FLUSH LINE TO SUPP.POOL VLV. (TO SUPP POOL RETURN)IA RHR HIX. RHR S.W. INLET VLV. (IA)13 RHR HTX S.W. INLET VLV. (18)M-S1, Sht 1 M-51, Sht 3 M-Si. SHIT 1 M-51. Sht 3 M-51, ShN 1 MN-i. Shl 3 M-51. SKT I M-51. Sht 3 M-51, SId 2 M-5, Sht 4 M-SI, Sht 2 M-51, Shl 4 102 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE 102 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE 309E. 309 217 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSUR 304W 217 REACTOR ENCLOSURE 304E 217 REACTOR ENCLOSURE 203 201 REACTOR ENCLOSURE 204 201 REACTOR ENCLOSURE 203 201 REACTOR ENCLOSURE 214 201 REACTOR ENCLOSURE OPEN 177 OPENICLO OPEN 177 OPENICLO: OPEN 177 OPENICLO.O OPEN 177 OPEN/CLO-CLOSED 217 OPEN/CLOt CLOSED 253 OPEN/CLOt CLOSED 217 CLOSED CLOSED 217 CLOSED CLOSED 201 CLOSED CLOSED 181 CLOSED CLOSED 201 OPEN CLOSED 201 OPEN 10B215 SED 108215, 10YI01 10B216 SED 108216 108217 550 108217 108218 SED 10B218 100216 BED 108216.10Y102 108211 BED 10B211010Yt01 NIR N/R NVR NR N/R N/A 108211 108211, lOY1I0 100212 10B212 Filter Unit = "'"or Unit = "Common" Sorted By EQLUp ID Page 55 E Data: 6/9/95-0 3 P m) Train Class/ Unit Eval Req'd Line No. Function cn E 1 6 1 SR4122. 4326. 472 ACTIVE 2 6 I SR 4220.4420.

4821 ACTIVE 1 6 1 SR 4123,4319,4718 ACTIVE 2 6 1 SR 4224.4424,4823 ACTIVE I 6 I SR 4125,4323,4724 ACTIVE 2 6 1 SR 4223,4426, 4826 ACTIVE 2 6 1 SR 3411 ACTIVE 2 I SR 3210 ACTIVE 1 6 1 SR 4719 ACTIVE 2 e 1 SR 4824 ACTIVE 1 6 I SR 4107,4320.

4720 ACTIVE 2 a I SR 426, 4406.4806 ACTIVE LIMERICK GENRiN STTIN4MEPROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL3 u-wet No. 0067 00GU1111 AResiontA Revision 1 Equip ID Systam Equip Description Drawing No. Room No. Norm state Moaive power Support System Supp Sys dwg Room Efav PIMS ID Notes IV-51-1F015A RHR HV-051-IFOISA 14 HV-51-iF0158 RHR IV-051-1FO15B 17 HV-51-1F016A RHR HV-0S1-1FDlA HV-51-1F016B RHR HV-0St-1F01-B HV-51 -IFO17A RHR HV-O51-IFC17A 16 NV-5i-1F017B RHR HV-0Sl-1FO178 18 WV-51-IF017C RHR HV-051-1F017C WV-.1-1F0170 RHR HV-OS1-IF017D HV-51-1F021A RHR W-OSI1-1FO21A HV-51-1F021R RHR HV-051-1FO21B HV-S1-1F024A RHR WV-051-1 F024A HV-51-1 F024B RHR K.V-051-1F024B POB Mother Comp 1A SHUTDOWN CLG INJECTION PCIV M-51. Sht I (OUTBOARD) 1B RHR SHUTDOWN CLG INJECTION M-51, ShI3 PCIV (OUTBOARD) 1A RHR CNTMT SPRAY LINE OUTBOARD M-51. Sht 1 PCIV (OUTBOARD) 1B RHR CNTMT SPRAY LINE OUTBOARD M-51, Sht 3 PCIV (OUTBOARD)

IA RHR LPCI INJ PCIV (OUTBOARD A) M-51. Sht 1 1B RHR LPCI INJ PCIV (OUTBOARD B) M-51, Sht 3 1C RHR LPCI INJ PCI (OUTBOARD C) M,51, SI"T I ID RHR LPCI INJ PCIV (OUTBOARD D) M-S1. Sht 3 1A RHR CNTMT SPRAY LINE INBOARD M-51. SNT 1 PCW (INBOARD)1B RHR CNTMIT SPRAY LINE INBOARD M-51. S3T 3 PCIV (INBOARD)IA RHR PP. FULL FLOWTEST RETURN M-Si, Sht I VLV. (SUPP POOL CLGA)18 RHR PP. FULL FLOWTEST RETURN M-S1, Sht 3 VLV. (SUPP POOL CLGB)Builing 309W 217 REACTOR ENCLOSURE 30ME 217 REACTOR ENCLOSURE 501 283 REACTOR ENCLOSURE 523 295 REACTOR ENCLOSURE 510 283 REACTOR ENCLOSURE 599 283 REACTOR ENCLOSURE 510 283 REACTOR ENCLOSURE 599 283 REACTOR ENCLOSURE So" 283 REACTOR ENCLOSURE 523 295 REACTOR ENCLOSURE 304W 217 REACTOR ENCLOSURE 304E 217 REACTOR ENCLOSURE Equip Sley Req'd State Cntr power CLOSED 108212 217 CLOSED 15212. 10Y102 CLOSED NWA 217 OPENICLOSED NIA CLOSED N/A 283 OPEN NIA CLOSED N/A 283 CLOSED NWA CLOSED N/A 283 OPEN/CLOSED NWA CLOSED 10B214 283 OPEN/CLOSED 105214 CLOSED 108223 283 OPEN 109223 CLOSED 108224 283 OPEN 10=224 CLOSED 108213 283 OPEN NWA CLOSED 105214 283 OPEN 10B214 CLOSED 10B211 227 OPEN/CLOSED 108211, 10YI01 CLOSED 10B212 227 OPEN/CLOSED 109212 Filter Unit "1"or Undt= "Common Sorted By Equip ID Page 56 Data. 619/95 Tramin Class S , Unit EvaIReq'd Line No. Funclion (0 1 6.1 R-.4 411B,4318.4715, PASSIVE 3134 2 6I P 4217, 4417.4817.

PASSIVE 6 R 4126.4321.

4721 PASSIVE 1ýA 2 6 I R 4225.4422.42 PASSIVE* 1j6 R 4120. 4312.4717 PASSIVE 1 5 4324.2221.341 PASSIVE-5 3 6* I S 4324,2224 PASSIVE 3 S I 1 4112 4427, 2224 PAS SIVE* 2215,3412 PASSIVE 3 5 3211.2225 PASSIVE: 1 5 I R 4112.4309,4708 PASSIVE* 2 6 I R* 4210.4411.4811 PASSIVE 1 5 I RS 4327.2228 PASSIVE 49 UMERICK IENERAI1NG STATION IPFfl PROJECT UNIT I &COMMON SUCCESS PATH COMPONENT UST(SPCL)0 Document No. 00674000500112 Atachinenit A Revision I Equip ID System Equip Descaihon Drawing No Room No. Norm state Motive power SuppWr System Supp Sys dwg Room Elev Equip Eley PIMS ID Notes ROB Mothar Comp Building Re*rd State Contr power HV-5i-IF02SA RHR W-V051-IF02A HV-S1-1FO26B RHR KV-051-1F026B HV-51-1F027A RHR HV-051-1F027A HV-51-1F0278 RHR HVWO51-1F0271 HV-51-1F040 RHR HV-0S1-1F040 WV-51-IF041A RHR HV-05141FO41A 15 NV-51-1F0415 RHR W-V051-1F041B HV-514F $041C RHR HV-O51-IF041C HV.51-IF041D RHR XV-051-1F041D

..1-S1- F047A RHR HV-051-1F047A HV-51 -1 F047B RHR HV-051-1F0478 KV-514-iFOSA RHR HV-051-1F0S0A 1A RHR HTX. OUTLET TO RCIC PP. M-51, Sht 2 SUCT. ISOL VLV. (TO RCIC)IB RHR HTX. OUTLET TO RCIC PP. M-51. Sht 4 SUCT. ISOL VLV. (TO RCIC)1A RHR SUPP POOL SPRAY LINE PCIV M-51, Shi 1 (SUPP POOL SPRAY)1B RHR SUPP POOL SPRAY LINE PCIV M-51. Sht3 (SUPP POOL SPRAY)'A' RHR DRAIN TO RNW OUTBOARD ISOL N-SI. Slt 2 VLV. (OUTBOARD)

IA LPCI INJ HOR TESTABLE CHK AND M-51. Sh I BYPASS PCIV (INBOARD CHECK A)IB LPCI INJ HOR TESTABLE CHECK AND M-51, Sht 3 BYPASS PCIV (tNBOARD CHECK S)IC LPCIINJ HDR TESTABLE CHK AND M-51, Sht 1 BYPASS PCIV (INBOARD CHECK C)ID LPCI INJ HOR TESTABLE CHK AND M-S1. Sht 3 BYPASS PCIV (INBOARD CHECK D)1A RHR HTX SHELL SIOE INLET VLV. M-51, Sht 1 (INLET)IB RHR MTX SHELL SIDE INLET VLV. M-51, Sht 3 (INLET)'A' LOOP SID CLG [NJ HDR TESTABLE MI-5, Shl I CHK & BYPASS PCIV 102 177 REACTOR ENCLOSURE 103 177 REACTOR ENCLOSURE 314W 217 REACTOR ENCLOSURE 304E 217 REACTOR ENCLOSURE 203 201 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 309W 217 REACTOR ENCLOSURE 309E 217 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE CLOSED 177 CLOSED CLOSED 177 CLOSED CLOSED 217 CLOSED CLOSED 217 CLOSED CLOSED 201 CLOSED OPERABLE 2e6 OPERABLE OPERABLE 296 OPEPABLE OPERABLE 296 OPERABLE OPERABLE 296 OPERABLE OPEN 217 OPEN OPEN 217 OPEN OPERABLE 253 OPERABLE N/M NR NR tim NIR NIR WR MRP NM NIR NMR NIR NIP NIR NMR NfR NR N/P NMI NfR NIR NMR Nm NMR-FMte.

Unit ="Common" Sorted By Equip ID r --w ,.-...

PageS?O Dale; 619M5 LUMERICK GENERATING STATION IFEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT ULST (SPCL)Docuiaint No. 009XCEnW=Affac~tlsentA RevIslon I m Train Class Equip ID System Equip Descrption Drawing No Room No Norm state Motive power Supporl Supp Sys dvg Unit Eval Reqd Room Elev Equip Elev Line No. Funmcion PIMS ID Notes ROB Mother Comp Building Reqed Slate Contr power 2 5 HV-51-1F050B RHR 'B' LOOP SID CLG INJ HDR TESTABLE M-51, Sht 3 400 OPERABLE MIR S CHECK& BYPASS PCIV (CHECK)4423.2227 PASSIVE HV-051.1F050B REACTOR OPERABLE NIR: ENCLOSURE 3 6 HV-51-1F052A HPCI HPCI STM. TO SHELL SIDE 1A RHR HTX M-51, SHT 2 309W CLOSED NIR 1 N/A VLV (STEAM SUPPLY) 217 3324,4115, 431Z PASSIVE -V-OS1.1F052A a REACTOR CLOSED NIR 4711.2225 ENCLOSUE 3 6 HV-51.1F052B HPCI HPCI STM. TO SHELL SIDE 1B RHR HTX M-51, SHT 4 309W CLOSED N/R 1 NWA VLV(STEAM SUPPLY) 217 33268 4214. 4414, PASSIVE IV-051-IFO52B 6 REACTOR CLOSED NMR 4814.22g -ENCOSURE I1 H V-51-1F06A RHRSW 1A RHR 1.X S.W. OUTET VLV. (IA) M.S1. Sht 2 203 CLOSED IO 7 I SR 201 201 1 4507 ACTIVE HV-051.1F068A REACTOR OPEN 101217. 10Y103ENCLOSURE 2 a HV-51-IF068B RHR IB RHR HTX S.W. OUTLET VLV (1B) M-51, Sht 4 204 CLOSED 1OB218 I SR 201 201 4608 ACTIVE HV-OS1-1F068B REACTOR OPEN 10B21B

2 6 H-51-1F073 RHR RHR SERVICE WATER CROSSTIE M-51, Sh 4 204 CLOSED NMR I R (CROSS TIE) 201 201 4603 PASSIVE -V-051-1F073 ENCTOR CLOSED MIR.EN.LOsuRE I 5 HV-52-108 HPCI 1B LOOP OUTBRD DISCH AO CHECK M-52, S1T 1 523 OPERABLE NMR 1 , PCIV (OUTBOARD CHECK) 295 283 3314 PASSIVE uV-O52s-IDS REACTOR OPERsABLE NIR ENCLOSURE 3 HV-52-139 CS. SP FILL LT-140RlH)

SUPP POOL LEVEL ROOT M-52, SHT I 110 OPEN NMR I R VALVE PCIV(SUPP POOL) 177 217 7200 PASSIVE HV-052-139 REACTOR OPEN MIR ENCLOSURE 3 5 HV-52-1 F00A CORE SPRAY IA LOOP TESTABLE CHECK PCIV M-52, Sft 1 400 OPERABLE NR 1 R (INBOARD CHECK) 237 286 2216 PASSIVE KV-052-1FODBA REACTOR OPERABLE NMR ENCLOSURE 3 5 HV-52-1 F006B CORE SPRAY lB LOOP TESTABLE CHECK PCIV M-52, Shl1 101 OPERABLE NIR ( R {INBOARD CHECK) 295 297 2217,3315 PASSIVE WV-052-IFO06B REACTOR OPERABLE NR ENCLOSURE 1 6 HV-52-1 F037 HPCI 16 LOOP INBOARD DISCH. VLV. M-52, SHT 1 523 CLOSED MR I R (INBOARD DISCHARGE) 295 283 3313 PASSIVE HV-052-1F037 REACTOR CLOSED NIR 3P I H 5FENCLOSURE 3 6 HV-55-120 HPCI LT-lN06B2,1N062F.115,116,LT-52-1408 SIP M-55, SHT 1 204 OPEN NMR i 1 R LVL RVIL PCIV(S/P) 201 201 7201 PASSIVE HV-055-120 REACTOR OPEN NIR ENCLOSURE Filter. UnuII=1"orUnit="Cominon' ScitedBy Equip ID rr Page 5a T3 Data; 60995 Gi)Train<. Unit 5 Lineaflo.3 7202 3 7203 3328 3 II 2218.3321 M322 1 3303 I* 3313 1 1: 1 1! I V 333 UMERICK GENERATING 3TAlnON IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SP1L)Documond No. 00 ?196 AltadmrennA Revisibn I Class Equip ID System Equip Descapbon Drawing No. Room No. Nom. state Mote powe& Suppoct !4 stem 'ys dwg Evat Reqfd Roon Elev Equip Else Funclion PIMS ID Notes ROB Mother Comp Building Req'd State Cow power 6 R PASSIVE 6 R PASSIVE B SR ACTIVE 6 SR ACTIVE a R PASSIVE 6 SR ACTIVE 6 R PASSIVE 6 R PASSIVE 6 SR PASSIVE 6 SR ACTIVE 6 SR ACTIVE 6 R PASSWIE HV-5S.121 HV-O55-121 HV-.55-126 HV-O55126 HV-55-1F001 HV-055-1 FO01 HV-55-1FO92 I'W-aOSS-IF002 NV-55-1F003 HV-055-1F003 HV-55-1 P006 HV-055-1 FO6 HV-55-IFOO7 HV-055-1F07 HV-55-1F008 HV-0S5-1FOGS HV-55-I FG12 HV-055-IFD12 HV-S.-1F`041 HV-OSS-1PF041 HV-5S-1F042 HV-055-1 F042 HV-SS-1F072 HV-055-1F072 HPCI SPI HPCI HPCI HPCI HPCI HPOI HPCI HPCI HPCI HPCI HPCI LT.-No62BLT-INGO2FLT-115LT-116SUPP M-E5. SlIT 1 POOL LVL ROOT SUPP POOL LEVEL INST ISOLATION M-55. SHT I VALVE HPCI TURBINE STEAM SUPPLY VLV. M-S5, SHT I (INLET)HPCI MAIN STEAM SUPPLY INBRD PCIV M-S5, SN1 i (INBOARD)HPCI MAIN STEAM SUPPLY OUTBRD M-55, SHT 1 PCIV (OUTBOARD)

HPCI PUMP DISCHARGE VALVE M-55, SHT 1 (INJECTION)

HPCI PUMP DISCHARGE VALVE M-ES, SHT 1 (DISCHARGE)

HPGI TEST LOOP SHUTOFF VALVE M-55, SlIT 1 (TEST ISOL)HPCl PUMP MIN FLOW PCIV (MIN FLOW) M-S5. SHT I HPCI PP. SUCT. FROM SUPP. POOL M-55, 81T 1 VALVE (SUPP POOL SUCTION)HPCI PUMP SUCTION FROM SUPP POOL M-S5, SHT 1 PCIV (SUPP POOL)HPCI TURB EXHAUST PCIV (EXHAUST)

M-55, SHT 1 2w4 201 REACTOR ENCLOSURE 204 201 OEA-TOR ENCLOSURE 109 177 REACTOR ENCLOSURE 101 253 REACTOR ENCLOSURE 309W 217 REACTOR ENCLOSURE 500 283 REACTOR ENCLOSURE 200 201 REACTOR ENCLOSURE 20D 201 REACTOR ENCLOSURE 268 201 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 288 201 REACTOR ENCLOSURE OPEN 201 OPEN OPEN 201 OPEN CLOSED 177 OPEN OPEN 245 OPEN OPEN 217 OPEN CLOSED 283 OPEN OPEN 201 OPEN CLOSED 201 THROTTLING CLOSED 201 OPENICLOSED CLOSED 177 OPEN OPEN 177 OPEN OPEN 201 OPEN MR NMR WR IMR 1D202 100202 108224 100224 NIR MR 100203 100203 MIR N/R MR NMR MIR NMR 10D202 10D202 10D202 100202 NMR MIR Filler Unit -=" or Unit ="Commoni Sorted By EquP ID LAN .C *ý-;M9 C :7-Page 59 UMERICK GENERATING STATION IPEEE PROJECT Document No. OO67.0UlE-

-5 UNIT I &COMMON AltaOeftlerdA D. a SUCCESS PATH COMPONENT UST (SPCL) Revisin I 0. 0 E Train Class R Ecp ID System Equip Desuiption Drawing No. Room No. qm state Mo.ve power Support System Supp Sys dw*Unit Eva] Recid Room Elev EupEa Ej'= .qup'le U Lne No. Function PIMS ID Notes ROB Mother Comp Building Reqd Slate Conir power 1 6 HV.55-1F093 HPCI HPCI TURB EXHAUST LINE VAC BKR M-55, SwIr 1 200 OPEN N/R I R PCIV (OUTBOARD) 201 201 3334 PASSIVE WV-055-1F093 REACTOR OPEN NIR ENCLOSURE 1 BWIV-55-IF095 HPCI HPCI TURB EXHAUST VACUUM BREAKER M-55. SHT I 288 OPEN WR 1 R PCN (INBOARD) 201 201 3335 PASSIVE HV-0S5-1F095 REACTOR OPEN NIR ENCLOSURE 1 6 HV-55-IF105 HPCI HPCI PUMP DISCHARGE PCIV (TO MAIN M-55, SHT 1 58 CLOSED N/R SR FEED A) 279 283 4 33M9 ACTIVE W-065-1FIOS REACTOR CLOSEDIOPEN N/R ENCLOSURE 1 6 HVSS--1F059 HPCI HPCI LUBE OIL COOLING WATER VLV. M-,5, SHT 1 109 CLOSED 10D202 S 1SR (COOLING WATER) 177 177.... 3340 ACTIVE F05uREACTOR OPEN 100202 ENCLOSURE 3 5 HV-57-104 CAC SUPP POOL PURGE TO SGTS INBD M-57. SHT 2 304 CLOSED NR I SR PCIV (SUPP POOL EXHAUST) 217 217 2328 PASSIVE HV-057-104 REACTOR CLOSED N/R ENCLOSURE 3 B HV-57-105 CAC SUPP POOL PURGE EXH BYPASS INBRD M-57. SHT 2 304 CLOSED N/R I R PCIV (SUPP POOL EXH BYPASS) 217 217 2327 PASSIVE HV-057-105 REACTOR CLOSED N/R ENCLOSURE 3 6 WV-57-109 CAC NITROGEN PURGE PCIV (PURGE M-57, SlT 1 309 CLOSED N/I SR ISOLATION) 217 240 2313 PASSIVE HV-057-109 REACTOR CLOSED N/R ENCILOSURE 3 6 WV-57-111 CAC ORYWELL PURGE EXH BYPASS INBRD M-37. SHT2 51S CLOSED N/R I SR PCIV (DRYWELL EXH BYPASS (INBD)) 283 283 2316 PASSIVE HV-057-1111 REACTOR CLOSED NIR ENCLOSURE 3 6 HV-57-112 CAC SUPP POOL PURGE AIR EXHAUST PCIV M-57,SIHT 2 304 CLOSED NIR I1 SR (EXHAUST ISOLATION) 217 217 2325 PASSIVE WV-357-112 REACTOR CLOSED NIR ENCLOSURE 3 5 HV-S7-114 CAC DRYWELL PURGE TO SGTS INBD. PCIV M-57. BHT 2 506 CLOSED NIR I SR (DRYWELL EXHAUST) 313 2317 PASSIVE HV057-114 REACTOR CLOSED N/R ENCLOSURE 3 6 HV-57-115 CAC DRYWELL PURGE AIR PCIV (EXHAUST M-57, SHT 2 506 CLOSED N/R 1 .I SR ISOLATION) 283 313 2315 PASSIVE W4-057-115 REACTOR CLOSED N/R ENCLOSURE 3 5 HVW-57117 GAG DAW PURGE TO EQUIP COMPT EXH M-57, SHT 2 510 CLOSED NIR ROUTD PCIV (TO RX ENCL FLTR1SR (OTD)283 2113" 2319 PASSIVE ,N-057-117 (OUTB0)) REACTOR CLOSED N/R ENCLOSURE' Filtec Unit =1or Unit "Common Sorted By Equip ID M M E5C 78.PaeB 60 Dater 6519g5 w ,ERCK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL]Tw Documen~t No. 00117490111114 uMNWAM Revision I Train Class Equip ID System Equip Description Drawng No. Room No. Nftr state Motwe power Support System Supp Sys dwg Unit Eval Req'd Room Elev Equip Bev Una No. Function PIMS 10 Notes ROB Molher Camp Building Req'd State Contr power 3 5 HV-57-118 CAC SUPP POOL PURGE TO EO COMPT EXH M-57. SHT 2 304 CLOSED NfR I SR OUTBD PCIV 217 217 2329 PASSIVE W4V-57-11B REACTOR CLOSED NIR ENCLOSURE 3 K-V-57-121 CAC ORYWELL NITROGEN PURGE INBRD M-57, SHT 1 309 CLOSED NfR I SR PCIV(DRYWELL PURGE) 217 240 2309 PASSIVE HV.057-121 REACTOR CLOSED NIR ENCLOSURE 3 5 HV-57.123 CAC DRYWELL AIR PURGE INBRD PCIV M-57, STr 1 309 CLOSED NWR I SR (DRYWELL VENT (INBD)) 217 240 2310 PASSIVE KV.057-123 REACTOR CLOSED NIR ENCLOSURE 3 5 HV-57-124 CAC SUPP POOL AIR PURGE INBO PCIV M-57, SHT 1 309 CLOSED NIR I SR (SUPP POOL VENT (INBD)) 217 217 2322 PASSIVE KV-057-124 REACTOR CLOSED NIR ENCLOSURE 3 5 HV-57-131 CAC SUPP POOL NITROGEN PURGE INORD M-57. SHT 1 309 CLOSED NIR 1 SR PCIV (SUPP POOL PURGE) 217 217 2311 PASSIVE HV.057-131 REACTOR CLOSED NIR ENCLOSURE 3 6 HV-57-135 CAC DRYWELL PURGE AIR INLET PCIV M-57. SiT 1 309 CLOSED N/R 1 RS (DRYWELL VENT (OUTED)) 217 217 2308 PASSIVE HV-057-135 REACTOR CLOSED NIR ENCLOSURE 3 6 HV-57-147 CAC SUPP POOL PURGE AIR INLET PCIV M-0., SHT 1 309 CLOSED NIR I SR (SUPP POOL VENT (OUTSD)) 217 217 2321 PASSIVE ItV-0t57-147 REACTOR CLOSED NIR ENCLOSURE 3 6 MV-57-161 CAD A CONTMIT HYD RECOMB INBRD INLET M-57, SlT 2 506 CLOSED NIR 1 SR PCIV 283 313 2318 PASSIVE HV-057-161 REACTOR CLOSED NIR ENCLOSURE 3 6 HV-57-162 CAC A CONTMT HYD RECOMB IN1RD M-57, SHT 2 304 CLOSED NIR I SR OUTLET PCIV 217 217 2326 PASSIVE HV-057-162 REACTOR CLOSED NI.ENCLOSURE 3 RHV-57-153 CAC B CONTMT HYD RECOMB INBRO INLET M-57, SHT 1 309 CLOSED NIR I SR PCIV 217 240 2312 PASSIVE HV-057-163 REACTOR CLOSED NIR ENCLOSURE 3 6 KV-57-164 CAC B CONTMTIHYD RECOMB INBRD M-57. SHT 1 309 CLOSED W/R I SR OUTLET PCIV 217 217 2323 PASSIVE HV-DS7-154 REACTOR CLOSED HIR ENCLOSURE 3 6 HV-57-16S CAC A CNTMT HYD RECOMB OUTBRD M-57, SHT 2 3D4 CLOSED N/R I SR OUTLET PCIV 217 217 2330 PASSIVE -IV-057-166 REACTOR CLOSED NIR ENCLOSURE Filler. Unit = "1" or Unit ="Common" Sorted By Equip ID CE ciC)S. ii or a UNEK GENERATING STATION IPEE! PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST(SPCL]Doaunti No. 0OW4as08s4 Aftecmet A Revislon I V Page 61 Date: 619195 Train Unit Une No.3-1 2324 2* 5100-3 2331 3 2332 3 3 2334 I 4111.4308.

4707 2 I 4211.4410, 4810 3 7204 3 1* 7208 3 7206 3 7207 Class Equip ID System Equip Desamption Drawing No. Room No. Norm state Motive poww Support System Supp Sys dwg Eval Req'd Room Elev Equip Bev Function 6 SR PASSIVE 5 R PASSIVE 5 SR ACTIVE S R PASSIVE S SR ACTIVE 5 R PASSIVe 6 SR ACTIVE 6 SR ACTIVE 17 BR ACTIVE 17 BR ACTIVE 17 BR ACTIVE PIMS ID W-i-57-169 HV-W-169 NV-59-ISIS HV-059-151B NV-6I-110 HV-O1-110 NV-61-111 HV-061 -111 HV-61-130 HV-061-130 WV-61-131 HVO061-131 HV-C51-IF04DA HV-C-051-1FO48A HV-C5t-1F048B HV-C-O51-IF048B Li-52-140A L1-052-140A LI-52-140B LI-052-14DB LI-SS-115-1 Notes CAC PCIG UQUID RADWASTE COLLECTION LIQUID RADWASTE COLLECTION LIQUID RADWASTE COLLECTION LIQUID RADWASTE COLLECTION RHR RHR CS, SP FILL CS. SP FILL SPI ROB Mother Comp 1 CNTMT H2 HYD RECOMS OUTBRD OUTLET PCIV ADS INSTRUMENT GAS PCIV (B)DAW FLOOR URN SUMP PCIV (INBOARD)PEN-X231A DIWFLOOR URN SUMP PCIV (OUTBOARD)

DAN EQUIP URN SUMP PCIV (INBOARD)PEN-X231B D0W EQUIP URN TANK PCIV (OUTBOARD) 1A RHR HTX SHELL SIDE BYPASS VLV.(HEAT EXCH BYPASS)IB RHR HTX. SHELL SIDE BYPASS VLV.(HEAT EXCH BYPASS)SUPPRESSION POOL LEVEL 10C848 SUPPRESSION POOL LEVEL 10C648 SUPPRESSION POOL LEVEL M-57. 51T 1 M-59. SHT 1 M-61. SNT I M-61. SHT 1 M-61, 8NT I M.-1. SHT 1 M-51, Sht 1 M-51. Sl 3 M-52, SHT I M-52, SHT 1 M-55. SHT 1 Building Reqd State 309 217 REACTOR ENCLOSURE 304E 241 REACTOR ENCLOSURE 209 201 REACTOR ENCLOSURE 209 201 REACTOR ENCLOSURE 209 201 REACTOR ENCLOSURE 209 201 REACTOR ENCLOSURE 309W 217 REACTOR ENCLOSURE 3O9E 217 REACTOR ENCLOSURE 533 269 CONTROL STRUCTURE 533 269 CONTROL STRUCTURE 533 269 CONTROL STRUCTURE CLOSED 217 CLOSED OPEN 217 OPEN OPEN 208 CLOSED CLOSED 201 CLOSED OPEN 208 CLOSED CLOSED 201 CLOSED OPEN 217 CLOSED OPEN 217 CLOSED OPERABLE 269 OPERABLE OPERABLE 269 OPERABLE OPERABLE 269 OPERABLE Contr power N/R N/fR N/fR NtR N/R N/fR N/R N/R NUR N/R NMR NMR 1DS211 10B211. 10Y11 10B212 10B212 N/A IOY11, 1AD102 N/A IOYI02 NIA lOYI05 LI-l5 `15-1 17 U-55-115-2 SPI SUPPRESSION POOL LEVEL INDICATOR M-55, SHT 1 540 OPERABLE N/A BR (LV) 289 269 ACTIVE LI-055-115-2 10C201 CONTROL OPERABLE lOY10s STRUCTURE Filler. Unit = 1" or Unit "Common" Sorted By Equip ID 10 C.Page 62 Date: 6/9W95 UfJhUCK GENERATINO STATION IPNE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST(SPCL)Document No. W0&.U M ANl111ew A Revision I Train Class Equip ID System Equip Description Drawing No. Room No. Norm state Motive power Support System Supp Sys dwo Unit Eval Req'd Room Elev Equip Elav Lin No. Function PIMS 1D Notes ROB Mother Comp Butld-ig Raqd State Conk power 3 17 L1-55-141 SPI SUPPRESSION POOL LEVEL INDICATOR M-f55. SHT 1 540 OPERABLE N/A 1 OR (LV) 289 289 Ma ACTIVE L1405-141 1OC201 CONTROL OPERABLE l1ADlO2 STRUCTURE 3 17 LSH-49-I1NO1 RCIC RCIC STM UNE DRAIN POT WA 108 OPERABLE N/A 1 S 177 177 9511 ACTIVE LSH-049-4NO10 REACTOR OPERABLE N/A ENCLOSURE 3 17 LSH-50-120 NWA RCIC GLAND SEAL COND VAC TANK NWA 108 OPERABLE N/A 1 B 177 177 9512 ACTIVE LSH.050-120 10E209 REACTOR OPERABLE N/A ENCLOSURE 3 17 LSH.55-1N014 N/A HPCI STEAM LINE DRAIN POT N/A 109 OPERABLE N/A 1 S 177 177 9513 ACTIVE LISH-055-1N014 REACTOR OPERABLE WA ENCLOSURE 3 17 LSHL-20-121A N/A DIESEL OIL DAY TANK 1AT520 START & N/A 312A OPERABLE N/A 1 0 STOP XFER PUMP 217 217 951f- ACTIVE LSHL.020-121A 1ATS28 CIESEL.GENERATOR OPERABLE N/A 3 17 LSHL-20-1210 WA DIESEL OIL DAY TANK IUTS2B START & WA 312B OPERABLE NWA 1 a STOP XFER PUMP 217 217 9515 ACTIVE LSHL-020-1218 1BT528 DIESELOENERATOR OPERABLE NIA 3 17 LSHL-20-121C N/A DIESEL OIL DAY TANK 1CT528 START & WA 312C OPERABLE N/A 1 B STOP XFER PUMP 217 217 9516 ACTIVE LSHL-020-121C ICT528 DIESEL GENERATOR OPERABLE NIA 3 17 LSHL-20-121D N/A DIESEL OIL DAY TANK IDT528 START & NWA 312D OPERABLE N/A 1 B STOP XFER PUMP 217 217 9517 ACTIVE LSHL-020-121D 1DT528 DIESEL GENERATOR OPERABLE N/A 3 17 LSHL-20-122A NIA DIESEL OIL DAY TANK 1AT528 HIGH 9 NWA 312A OPERABLE NIA 1 B LOW LEVELS 217 217 9518 ACTIVE LSHL-020-122A 1AT528 rIESELGENERATOR OPERABLE WA 3 17 LSHL-20-1228 NWA DIESEL OL DAY TANK 1STS28 HIGH & NWA 3128 OPERABLE N/A 1 0 LOW LEVELS 217 217 9519 ACTIVE LSKI-4,20-12211 1T528 DIESELGENERATOR OPERABLE NWA 3 17 LSHL-20-122C N/A DIESEL OIL DAY TANK 1CTS28 HIGH & WA 312C OPERABLE N/A 1 B LOWLEVELS 217 217 9520 ACTIVE LSHL-020-122C 1CTS28 DIESELOENERATOR OPERABLE WA 3 17 LSHL-20-122D NWA DIESEL OIL DAY TANK IDT528 HIGH & NIA 312D OPERABLE N/A 1 B LOW LEVELS 217 217 9521 ACTIVE LSNL-020-122D 1DT528 DIESELNG.ERATOR OPERABLE N/A Filter Unit = "1"or Unit = "Common" Sorted By Equip ID 03 CC, E5 Page 63 Date: 6SIM5 ULMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST ISPCL)Document No. 00P411111116 AftadtmintA Revision 1 Train Class Equip ID System Equip Descipbon Drawing No. Room No. Norm state MoLvS power Support System Supp Sys dwg Unit Eval Req'd Room Elev Equip Elev Line No. Function PIMS ID Notes ROB Mother Camp Bulding Req'd State Conltr power 3 17 LSLo20-127A WA DfG JACKET WrR EXPANS TANK 1AT564 N/A 31 1A OPERABLE WA 1 B 217 230 9522 ACTIVE LSL-020-127A 1AT564 DIESELGENERATOR OPERABLE N/A ENCLOSURE 3 17 LSL-2D-127B WA DIG JACKET WTR EXPANS TANK 1STS64 NA 3119 OPERABLE WA 11 217 230' 9523 ACTIVE LSL-020-127B 1BT564 OESEL GE..WOR OPERABLE WA ENCLOSURE-3 17 LSL-20-127C WA DIG JACKET W"R EXPANS TANKICTS54 NIA 311C OPERABLE WA I a 217 230 9524 ACTIVE LSL-020-127C 1CT564 DEJSELGENERATOR OPERABLE WA: : ENCLOSURE 3 17 LSL-20-127D WA D/G JACKET WTR EXPANS TANK IDT564 N/A 311D OPERABLE WA B1 217 217 9525 ACTIVE LSL-020-127D 1DT564 nIESELGENERATOR OPERABLE W/A ENCLOSURE 3 17 LSL-SO-121 WA RCIC GLAND SEAL COND VAC TANK NA 108 OPERABLE NIA 1 B 177 177 9526 ACTIVE LSL050.121 1OE209 REACTOR OPERABLE WA ENCLOSURE 3 17 LSL-56-121 N/A HPCI GLAND SEAL COND VAC TANK N/A 109 OPERABLE WA 1 B 177 177 9527 ACTIVE LSL-056-121 103210 REACTOR OPERABLE WA ENCLOSURE 3 17 LT-42-i ISA NUCLEAR BOILER REACTOR LEVEL M-42, SHT 1 402W OPERABLE NtR I S IST. 253 253 , 7100 ACTIVE LT.042-1ISA REACTOR OPERABLE N/R ENCLOSURE.3 17 LT-42-15B NUCLEAR BOILER REACTOR LEVEL M-42, BHT I 402E OPERABLE N/R 1 S IST. 253 253-t03 ACTIVE LT-042-1156 REACTOR OPERABLE NIP EIENCLOSURE 3 17 LT-49-1NO35A NIA RCIC PUMP SUCTION WA 200 OPERABLE N/A I S 201 201 9528 ACTIVE LT-049-1N035A REACTOR OPERABLE NZA ENCLOSURE 3 17 LT-49-1N035E N/A RCIC PUMP SUCTION WA 200 OPERABLE NWA 1 S 201 201 9529 ACTIVE LT-049-1ND35E REACTOR OPERABLE N/A ENCLOSURE 3 17 LT-52-140A CS. SP FILL SUPPRESSION POOL LEVEL NIA 118 OPERABLE WA i: 1 S 177 177 9530 ACTIVE LT-O52-1401A REACTOR OPERABLE N/A ENCLOSURE 3 17 LT-52-1400 CS, SP FILL SUPPRESSION POOL LEVEL NWA 11 OPERABLE WA I S 177 177 9531 ACTIVE LT-052-140B REACTOR OPERABLE N/A ENCLOSURE Filter. Unit = "1"or Unit = "Common" Sorted By Equip I1

-3)@W Page 64 Date: 6/9/95 LIMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Document No. 0067.80016-00 Altadlened A Revision I Trai Class Equip 1D System Equip Descrption Drawing No. Room No. Normn state Motive power Support System Supp, Sysdwg Ural Evae Req'd Room Elev Equip Elev Line No. Function PIMS ID Notes ROB Mother Comp dng Req'd State Conr power 3 17 LT-55-115 N/A SUPPRESSION POOL LEVEL WA 204 OPERABLE WA I S 201 201 9532 ACTIVE LT-SS-1l15 REACTOR OPERABLE WA ENCLOSURE 3 17 LT-55-141 NWA SUPPRESSION POOL LEVEL WA 203 OPERABLE WA 1 S 201 201 9533 ACTIVE LT-055-141 REACTOR OPERABLE WA ENCLOSURE 3 17 LT-55-1NO6IB NWA HPCI PUMP SUCTION WA 200 OPERABLE WA I S 201 201 9534 ACTIVE LT-055-1 N061 0 REACTOR OPERABLE WA ENCLOSURE 3 17 LT-55-1N0SIF WA HPCI PUMP SUCTION WIA 200 OPERABLE N/A I S 201 201 9535 ACTIVE L1-055-11N61F REACTOR OPERABLE N/A ENCLOSUIRE 3 17 LT-55-1N062B IA SUPPRESSION POOL LEVEL NfA 204 OPERABLE N/A 1 S 201 201 9538 ACTIVE LT-O55-1N062S REACTOR OPERABLE WA ENCLOSURE 3 17 LT-55-1N062F N/A SUPPRESSION POOL LEVEL WA 204 OPERABLE N/A I S 201 201 9537 ACTIVE LT-05S-1N1062F REACTOR OPERABLE NWA ENCL.OSURE 1 5 PCV-50-IFC15 RCIC RCIC PUMP 20P203 TO LUBE OIL M-S0. Slt 1 108 OPERABLE NIA 1 a COOLER 205212 177 177 3119 PASSIVE PCV-O5O-1F01S 106212 REACTOR OPERABLE N/A ENCLOSURE 1 S PCV-56-1F035 HIPCI HPCI BOOSTPUMP DISCH M5 SHT 1 200 OPERABLE NWA 1 S 177 177 3339 PASSIVE PCV-O56-1F035 REACTOR OPERABLE NIA ENCLOSURE 2 PCV-59-152B-1 PC0G ADS BACKUP N2 SUPPLY PRESSURE M-SS. SHT 1 304E OPEN NIA I S CONTROL VLV. 217 217 6102 PASSIVE PCV-O59-152B-1 REACTOR OPEN NIA ENCLOSURE 2 PCV-59-152B-2 PCIG ADS BACKUP N2 SUPPLY PRESSURE M-59, SBIT 1 304E OPEN NWA 1 S CONTROL VLV. 217 217 6103 PASSIVE PCV-059-152B-2 REACMOR OPEN N/A ENCLOSURE 2 5 PCV-S9-1526-3 PCIG ADS BACKUP N2 SUPPLY PRESSURE M-59. SHT 1 304E OPEN N!A 1 S CONTROL VLV. 217 217 6104 PASSIVE PCV-OS9-1523,3 REACTOR OPEN NWA ENCLOSURE 3 17 PD,059-106A NWA N2 SUPPLY TO ADS SYS N/A 402W OPERABLE NWA 1 S 253 253 9538 ACTIVE PDS-O59-106A REACTOR OPERABLE NWA ENCLOSURE Fitter Unit l"I"or Unit = "Commonn Sorted By Equip ID 3 Co Pane 65 Dale. 619195 Docunteri No. 00574MOEHM Anuwhr A Revision I UMERICK GENERATING STATION IPEEE PROJECT UNIT I &COMMON SUCCESS PATH COMPONENT UST (SPOL)Train Class Equip I1 System Equip Descriptilon Drawing No. Room No. Norm state Motive power Support System Supp Sys dwg Unit Eval Req'd Room Elev Equip Elev Line No. Function P1MS It) Notes ROB Mother Comp Bualding Reqad State Contr power 3 17 PDS-59-tORI NA N2 SUPPLY TOADS SYS N/A 402E OPERABLE MIA 1 S 253 253 9539 ACTIVE PDS.059-10B REACTOR OPERABLE NWA ENCLOSURE 3 17 PVSH-20-122A WIA DIG OIL XFER SUCTION N/A 311A OPERABLE NIA 1 S 217 9540 ACTIVE PDSH-020-122A DIESEL GENERATOR OPERABLE WA ENCLOSURE 3 17 PDSH-20-122B WIA DIG OIL XFER SUCTION NWA 311B OPERABLE W/A 1 S 217 9541 ACTIVE POSH-020-1228 DIESEL GENERATOR OPERABLE WA ENCL.OSURE 3 17 POSH-20-122C NIA ODG OIL XFER SUCTION WUA 311C OPERABLE N/A 1 S 217 9542 ACTIVE POSH-020-122C OI-SEL GE ERATOR OPERABLE WIA ENCLOSURE 3 17 POSH-20-122D N/A D/G OIL XFER SUCTION WIA 311D OPERABLE WIA 1 5 217 9543 ACTIVE PDSH-020-122D DIEEL RATOR OPERABLE NIA ENCLOSURE 3 17 PDSH-5O-101 N/A RCIC TURBINE OIL FILTER DIFF PRESS WA 108 OPERABLE NIA 1 S 177 177 9544 ACTIE PDSH-050-101 REACTOR OPERABLE WIA ENCLOSURE 3 17 PDT-51-INO0OA WIA LPCI LINES DIFFERENTIAL N/A 50SE OPERABLE WIA 1 9545 S ACTIVE PDTO051-1NO6OA 283 283 REACTOR OPERABLE ENCLOSURE M/A I.3 17 PDT.51-1N0605 N/A LPCI LINES DIFFERENTIAL W/A 402E OPERABLE WIA I S 253 253 9546 ACTIVE POT-051-INOBOD REACTOR OPERABLE WIA ENCLOSURE 3 17 PDT-52-1N056 WIA REACTOR CORE SPRAY OIFF PRESS W/A 506E OPERABLE NIA I S 283 283 9547 ACTIVE PDT-052-1N056 REACTOR OPERABLE NIA ENCLOSURE 1 W/A PSE-56-10003 HPCI HPCI TURBINE EXHAUST LINE VENT M-56.SIT1 200 OPERA3LE NIA I N/A 201 177 3341 PASSIVE PSE-056-10003 37 REACTOR OPERABLE WIA ENCLOSURE I NA PSE-56-1D004 HPCI XPCI TURBINE EXHAUST LINE VENT M-56, SHT 1 200 OPERABLE WIA I NZA 201 177 3342 PASSIVE PSE-056-ID004 37 REACTOR OPERABLE WIA EMCLOSURE 3 17 PSH-12-C04A W/A RHR SERVICE WATER PUMP OAP5056 WA Iwo0 OPERABLE NIA Common LOOP A 268 on= SSPRAY POND PUMP OPERABLE WIA 9631 ACTIVE PSH.012-004A STRUCTURA STRJClURE Filter Unit = "I" ot Unit = "Common" Sorted By Equip ID Page 66* Dalt: 619/95 C7r w UMERICKGENERA'ING STATION WPEEK PROJECT UNITI & COMMON SUCCESS PATH COMPONENT UST (SPCL)Oocument No. 0071CCOSSIC A Revision 1 u0 c, Train Class Equip ID System Equi Description Drawing No. Room No. NoArn state Motve power Support System Supp- Sys dwg Una Evhl Req'd Room EMea Equip Etwi Line No. Function PIMS ID Notes ROB Mother Comp Btutbio Rfld State Conrk power 3 17 PSH-12.0040 WA RHR SERVICE WATER PUMP 08PS06 N/A 1005 OPERABLE NIA Common S LOOP 0 268 9632 ACTIVE PSH-012-004B SPRAY POND PUMP OPERABLE NA STRUCTURE 3 17 PSH1.2.004N N WA RHR SERVICE WATER PUMP DCPS6 WA 1000 OPERABLE WA Common S LOOP A 288 9633 ACTIVE PSH-012-004IC SPRAY POND PUMP OPERABLE NIA STRUCTURE 3 17 PSH-12-004D N/A RHR SERVICE WATER PUMP 00P506 WA 1005 OPERABLE N/A Common $ LOOP B 268 9634 ACTIVE PSH-012-0040 SPRAY POND PP OPERABLE NWA STRUCTURE 3 17 PSH-50-121 NIA RCIC GLAND SEAL COND VAC TANK N/A 10 OPERABLE NWA 1 a 177 177 9548 ACTIVE PSH.-050-121 IOE209 REACTOR OPERABLE WA ENCLOSURE 3 17 PSH-56-120 NWA HPCI GLAND SEAL COND VAC TANK NWA 109 OPEPABLE NWA 1 B 177 177 Bug ACTIVE PSH-O56-120 IE210 REACTOR OPERABLE NWA ENCLOSURE 3 17 PSL-11-002A N/A ESWPUMPADISCHARGE WA 1000 OPERABLE WA Comumon S 268 9635 ACTIVE PSL-011-002A SPRAY POND PUMP OPERABLE WA STRUCTURE 3 17 PSL-11-0028 NWA ESW'PUMP B DISCHARGE NIA 1005 OPERABLE N/A Common S 268 9636 ACTIVE PSL-011-002B SPRAY POND PUMP OPERABLE WA STRUCTURE 3 17 PSL-11-O02C N/A ESW PUMP C DISCHARGE NWA 1000 OPERABLE WA Common S 268 9837 ACTIVE PSL-011-002C SPRAYPONDPUMP OPERABLE WA STRUCTURE 3 t7 PSL-11.0020 NIA ESW PUMP D DISCHARGE NIA 1005 OPERABLE NWA Common S 268 9638 ACTIVE PSL-011-0020 SPRAY POND PUMP OPERABLE WA STRUCTURE 3 17 PSL-12.-O1A NIA RHR SERVICE WATER PUMP OAPS06 MA 1000 OPERABLE NIA Common S LOOP A 253 9639 ACTIVE PSL-012-ODIA SPRAY POND PUMP OPERABLE NIA STRUCTURE 3 17 PSL-12-0016 NIA RHR SERVICE WATER PUMP 0BPS06 WA 10D5 OPERABLE N/A Common S LOOPB 268 g0 ACTIVE PbL-012.001B SPRAY POND PUMP OPERABLE NWA STRUCTURE 3 17 PSL-12-001C NZA RHR SERVICE WATER PUMP 0CPS06 WA 1000 OPERABLE N/A Common S LOOP A 20 941 ACTIVE PSL-012-001C SPRAY POND 26 OPERABLE NIA STRUCTURE Filer. Unit = "l'or Unit = "Common" Sorled By Equip ID.......... .......

0 Page 67 Date. 6/9195 Train unit Line No.3 Common 9642 3 9550 3 9551 3 1 9552 3 2100 3 2101 3 1 2102 3 1 2103 3 1 2104 3 1 2105 3 1 2106 3 1 2107 Class Eval Req'd Funcion 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 5 SR ACTIVE a SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE 5 SR ACTIVE Equip ID PIMS ID PSL-12-.001D PSL-012-O010 PSL-12-102A PSL-012-102A PSL-12-102B PSL-012-102B PSL-50-101 PSL-450-101 PSV-41-1F013A PSV-O41-1FC13A PSV-41-IF013B PSV-041-1F013B PSV41 -1 F013C PSV-041-IFO13C PSV-41 -1 FO13D PSV-041-1F0130 PSV-41-1F013E PSV-041-1FD13E PSV.41-1F013F PSV-.J41-1FOI3F PSV-41 -IF01 31 PSV-.41.1F013G PSV-41-1F013H PSV-041-1F01314 System Notes N/A N/A N/A N/A NUCLEAR BOILER NUCLEAR BOILER NUCLEAR BOILER NUCLEAR BOILER NUCLEAR BOILER 5 NUCLEAR BOILER NUCLEAR BOILER NUCLEAR BOILER 5 Equip Desciption ROB Molter Camp RHR SERVICE WATER LOOP a RHR SERV W'R PUMP HEAT EXCH A RHR SERVWE'R PUMP HEAT EXCH 8 RCIC TURBINE BEARD MAIN STEAM LINE S VALVE ON MSL"A MAIN STEAM UNE SAl VALVE ON MSL 'B'MAIN STEAM LINE SAP VALVE ON MSL'C'MAIN STEAM LINE SAF VALVE ON MSL 'D'MAIN STEAM LINE SAF VALVE ON MSL W MAIN STEAM LINE SAF VALVE ON MSLB'MAIN STEAM LINE SAW VALVE ON MSL 'C'MAIN STEAM LINE SAF VALVE ON MSL Z'UNERIICK GENERA'iNG STATION IPEEE PROJECT UNITI &COMMON SUCCESS PATH COMPONENT UST (SPCL)Drawing No- Room No.Room Elev Building PUMP ODP5S0 N/A 1005 268 SPRAY POND PUMP STRUCTURE'LOOP A TO RHR N/A 202 198 REACTOR ENCLOSURE LOOP B TO RHR N/A 202 198 REACTOR ENCLOSURE 4G OIL PRESS N/A 108 177 REACTOR ENCLOSURE ETY/RELIEF M-41, Sh 2, 3 400 237 REACTOR ENCLOSURE FETY/RELIEF M41. SHT 2. 3 400 237 REACTOR ENCLOSURE FETY/RELIEF M-41, Shlt 2,3 400 237 REACTOR ENCLOSURE ETY/RELIEF M,41. Sht 2, 3 400 237 REACTOR ENCLOSURE ETY/RELIEF MAt. Sht 2. 3 400 237 REACTOR ENCLOSURE ETY/RELIEF M-41, Sht 2. 3 400 237 REACTOR ENCLOSURE ETYIRELIEF M-41, Sht 2 3 400 237 REACTOR ENCLOSURE FETYRELIFF M-4. Shl 2, 3 400 237 REACTOR ENCLOSURE Norm slate Equip Elev Regd State OPERABLE OPERABLE OPERABLE 177 OPERABLE OPERABLE 177 OPERABLE OPERABLE 177 OPERABLE CLOSED 286 OPEN/CLOSED CLOSED 286 OPEN/CLOSED CLOSED 285 OPEN/CLOSED CLOSED 28S OPEN/CLOSED CLOSED 216 OPEN/CLOSED CLOSED 286 OPEN/CLOSED CLOSED 288 OPEN/CLOSED CLOSED 286 OPEN/CLOSED Dogamnet No. 0067-MW Atlacdimnt A Revision I Molive power Support System Supp Sys dwg Contrpower MIA N/A N/A N/A WA N/A N/A WA N/Al 1AD102 N/fl NIR NMR 1AD102 N/R N/R N/R PCIG M-59. SH 1 1AD102, 1CD102 NMR NMR NMR NfR N/R PCIG M-S9 SH. 1 1ADI02,100102 Filter Unit ="l"or Unit =Cermmon" Sorted By Equip ID...-.,.. ......

G~)V7 1A Paeg 68 UMERICK GENERAT1NG STATION IEE PROJECT.UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCL)Do~uarMf No. 001171100=

ANEKAM Revison I Train Class Equip ID System Equip Desriptlion Drawing No. Room No. Norm slate Motive power Support System Supp Sys dwg Unit Eval Req'd Room Erev Equip Elev Line No. Function PIMS ID Noles ROB MoIther Comp BullIn Reqd Slate Conr" power 3 5 PSV-41-1F013J NUCLEAR BOILER MAIN STEAM LINE SAFETYIRELIEF Ml41, Sht 2, 3: 400 CLOSED NIR I SR VALVE ON MSL'AI 237 273 2108 ACTIVE PSV-041-1FCI3J REACTR OPEN/CLOSED NIR ENCLOSURE 3 PSV-41.FO13K NUCLEAR BOILER MAIN STEAM UNE SAFETY/RELIEF M-41. Shl 2 3 400 CLOSED NIR PCIG M-59, SIR I I SR VALVE ON MSL 'W 237 273 2109 ACTIVE PSV-041-1Fa13K 5 MOTOR OPEN/CLOSED 1AD102. ICD102 ENCLOSURE.3 PSV-41-iF013L NUCLEAR BOILER MAIN STEAM UNE SAFETY/RELIEF M.41. Sht2. 3 400 CLOSED IR 1 SR VALVEON MSL C' 237 273 2110 ACTIVE PSV-041-1FO13L REACTOR OPEN/CLOSED NIR ENCLOSURE 3 PSV-41-IF013M NUCLEAR BOILER MAINSTEAM LINE SAFETY/RELIEF M41. St' 2,3 400 CLOSED NIR PCIG M59, SHL1 1. SR VALVE ON MSL 'D' 237 273 211.1 ACTIVE PSV-041-1FO13M 5 REACTOR OPEN/CLOSED 1AD102. 1CD102 ENCLOSURE.3 5 PSV-41.-IF013N NUCLEAR BOILER MAIN STEAM LINE SAFETYIRELIEF M-41. Sht2, 3 400 CLOSED N/R I SR VALVE ON MSL'B 237. 273 2112 ACTIVE. PSV-041-AFO13N REACTOR OPEN/CLOSED 1AD102 ENCLOSURE 3 5 PSV-41-1F0135 NUCLEAR BOILER MAIN STEAM LINE SAFE'TY1REUEF M-41. Sh.2, 3 400 CLOSED N/R PCIG M-59. SH. 1 I SR VALVE ON MSL , 237 273 2113 ACTIVE PSV-041-1F013S 5 REACTOR: OPEN/CLOSED lADIn2. ICD102 ENCLOSURE 3 1 3 1 2121.3 1 2123 3 1 2125 3 1 2127.3 1 2129 R N/A ACTIVE R N/A ACTIVE R N/A ACTIVE: R N/A ACTIVE R N/A: ACTIVE R N/A ACTIVE PSV-41*1F037A SRV SRV DISCHARGE LINE VACUUM BREAKER PSV-041-1F037A PSV41-1FD37B SRV SRV DISCHARGE LINE VACUUM BREAKER PSV-041-!F0378 PSV-41-IFD37C SRV SRV DISCHARGE LINE VACUUM.BREAKER PSV-041-1F037C PSV-41-1F037D SRV SRV.DISCHARGE L N E VACUUM BREAKER PSV-041-1F0370 PSV-41,1F037E SRV SRV DISCHARGE LINE VACUUM BREAKER PSV-041-1F037E PSV-41-1F037F SRV SRV DISCHARGE LINE VACUUM BREAKER PSV-041-IFO37F M-41. SHT2.M-41. SIT.2 M-41. SHT 2.M.41. SHT2 M-41. SHT2 M-41. SHT 2 400 237 REACTOR 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE 400 237 REACTOR ENCLOSURE OPERABLE N/A OPERABLE WA OPERABLE WA OPERABLE N/A OPERABLE NIA OPERABLE N/A OPERABLE WA OPERABLE N/A OPERABLE N/A OPERABLE N/A OPERABLE N/A OPERABLE N/A Filter Unit'= "1 or.Unit = "Common" Sorted By EqulplO.

Page 69 Date: BIStOB UMERICK GENERATING STATION IPM PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT UST (SPCL)Document No. 00871114114)1111 Attachment A Revision I Train Class Equip JD System Equip Description Drawing No. Room No. Norm state Mote power Support system Supp Sys dwg Unit Eva] Reqad Room Elev Equip Elov Line No. Functon PIM$ ID Notes ROE Mother Comp BuuIimyg Rec'd Slate Contr power 3 R PSV-41-1FO37G SRV SRV DISCHARGE LiNE VACUUM M-41. SHT2 400 OPERABLE IVA 1 NIA BREAKER 237 2131 ACTIVE PSV-O41-IF037G REACTOR OPERABLE NA ENCLOSURE 3 R PSV-41-F'037H SRV SRV DISCHARGE LINE VACUUM M-41. SHT 2 400 OPERABLE NIA 1 N/A BREAKER 2133 ACTIVE PSV-04141FO37H REACTOR OPERABLE NA ENCLOSURE 3 R PSV-41-1F037J SRV SRV DISCHARGE LINE VACUUM M-41, SHT 2 400 OPERABLE WA 1 NA BREAKER 237 2135 ACTIVE PSV-041-1F037J REACTOR OPERABLE NIA ENCLOSURE 3 R PSV-41.1F037K SRV SRV DISCHARGE LINE VACUUM M-41, SHT2 400 OPERABLE NIA I NIA BREAKER 237 2137 ACTIVE PSV-041-1FO37K REACTOR OPERABLE NIA ENCLOSURE 3 R PSV-41-1F037L SRV SRVDISCHARGE UNE VACUUM M-41, SHT2 4D0 OPERABLE N/A I NIA BREAKER 237 213t ACTIVE PSV-041-1F037L REACTOR OPERABLE NIA ENCLOSURE 3 R PSV-41-1F037M SRV SRV DISCHARGE LINE VACUUM M-41. SHT 2 400 OPERABLE NfA I N/A BREAKER 237 2141 ACTIVE PSV-041-1F037M REACTOR OPERABLE NA ENCLOSURE 3 R PSV-41-1F037N SRV SRV DISCHARGE LINE VACUUM M-41, SHT2 400 OPERABLE WA SNA BREAKER 237 2143 ACTIVE PSV-041-1Fo37N REACTOR OPERABLE N/A ENCLOSURE 3 R PSV-V41-4FO37S SRV SRVOISCHARGE LINE VACUUM M-41. SHT 2 400 OPERABLE WA I NWA BREAKER 237 2145 ACTIVE PSV-041-1F0375 REACTOR OPERABLE WA ENCLOSURE 3 R PSV-41-IF0I97A SRV SRV DISCHARGE LINE VACUUM M-41, SHT 2 400 OPERABLE WA 1 NIA BREAKER 237 2120 ACTIVE PSV-041-1F097A REACTOR OPERABLE WA ENCLOSURE 3 R PSV-41-1F0978 sRV SRV DISCHARGE LINE VACUUM M-41, SHT 2 400 OPERABLE WA I NIA BREAKER 237 2122 ACTIVE PSV.041-1FO97B REACTOR OPERABLE NWA ENCLOSURE 3 R PSV-41-1F097C SRV SRV DISCHARGE LINE VACUUM M-41, SHT 2 4D0 OPERABLE N/A SN/A BREAKER 237 2124 ACTIVE PSV-041-1F097C REACTOR OPERABLE WA ENCLOSURE 3 R PSV-41-lF097D SRV SRV DISCHARGE LINE VACUUM M.41. SHT2 400 OPERABLE NWA I NWA BREAKER 237 2128 ACTIVE PSV-041-IF0970 REACTOR OPERABLE N/A ENCLOSURE Filter~ Unt=Ic nt C0 SortedByEquiplD Pag 70 IMERICK GENEIG STAIN EE PROJECT OW UNIT I & COMMON Altadtment A:o Date: 6/9/95 SUCCESS PATH COMPONENT UST (SPCL) Revision 1 a Train Class Equip ID System Equip Description Drawing No. Room No. Nzrm state Mobve power Suppor System Supp Sys dwg@ Unit Eval Req'd Room Elev Equip Elev Line No. Funcfion PIMS ID Notes ROB Mother Comp Building Reqd Stale Contr power U,-3 R PSV-41-IF097E SRV SRV DISCHARGE LINE VACUUM M-41, SHT 2 400 OPERABLE WA.NWA EREAKER 237 2128 ACTIVE PSV-041-1 FO97E REACTOR OPERABLE NWA ENCLOS.RE 3 R PSV-41-1F097F SRV SRV DISCHARGE LINE VACUUM M-41, SHT2 400 OPERABLE NWA 1 N/A BREAKER 237 2130 ACTIVE PSV-041.1F0BF REACTOR OPERABLE NIA 3 R PSV-41-1FOB7G SRV SRVDISCHARGE LINE VACUUM M-41. SHT2 400 OPERABLE WA I NWA BREAKER 237 2132 ACTIVE PSV-041-1FO'7G ETOR OPERABLE WA A V ENCLOSURE I 3 R PSV-41-1FO97H SRV SRV DISCHARGE LINE VACUUM M-41. SHT2 400 OPERABLE WA W NIA BREAKER 237.: 2134 ACTIVE PSV-041-1F097H REACTOR OPERABLE WA ENCLOSURE 3 R PSV-1-1F097J SRV SRV DISCHARGE LINE VACUUM M-41, SHT 2 400 OPERABLE WA W..-,NA BREAKER 237 213U ACTIrV PSV-041-1F097J REACTOR OPERABLE NWA ENCLOSURE 3 R PSV-41-1F097K SRV SRV DISCHARGE LINE VACUUM M-41, SHT 2 400 OPERABLE N/A 1 WA BREAKER 237 2138 ACTIVE PSV.041-*F097K REACTOR OPERABLE WA ENCLOSURE 3 R PSV-41-1F07L SRV SRV DiSCHARGE LINE VACUUM M-41. SHT 2 400 OPERABLE WA 1 W/A BREAKER 237 2140 ACTIVE PSV-041-IF097L REACTOR OPERABLE NWA ENCLOSURE 3 R PSV-41-1F097M SRV SRV DISCHARGE LINE VACUUM M-41, SHT2 400 OPERABLE NWA S I WA BREAKER 237 2142 ACTIVE PSV-041-1FO97M REACTOR OPERABLE NWA ENCLOSURE 3 R PSV-41-1F097N SRV SRV DISCHARGE LINE VACUUM M-41, SHT 2 400 OPERABLE NIA 1BREAKER I NIA 237: 2144 ACTIVE PSV-041-FO97N REACTOR OPERABLE NIA ENCLOSURE 3 R PSV-41-IF097S SRV SRV DISCHARGE LINE VACUUM M-41, S14T2 400 OPERABLE WA 1 NA BREAKER 237 2146 ACTIVE PSV-041-1F097S REACTOR OPERABLE NWA ENCLOSURE I PSV-51-1F055A RAR IA RHR HEAT EXCHANGER INLET LINE M-51. Sht 2 309 OPERABLE NIA 1 WA RELIEF PCIV 217 217 4114,4311,4710 PASSIVE PSV-051-1F055A REACTOR OPERABLE NA ENCLOSURE* 2 5 PSV-51-1FJSSB RHR IS RHR HEAT EXCHANGER INLET LINE M-51, Sht 4 204 OPERABLE NWA I NWA RELIEF PCIV 201 217 4213.4413,4013 PASSIVE PSV.O51-1FOSSB REACTOR OPERABLE NWA ENCLOSURE FIlter Unit n"¶" or Unit = "Common" Sorted By Equip 10

0 H Page 71 0) C) Date: 6W9M9 Train S, Unit Line No.3135 3 2300 3 2301* 3 2302 3 2303 3 2304 3 2305 3* 2306 3 2307 3 i, 1i* 7101 3 1 710 SS UMERICK GENERATING STATION IPEEE PROJECT UNIT 1 & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Document No. 0067411084MU Attoat~arSA Revtson 1 Class Equip ID systam Equip Dosuxiption Drawng No. Room No. Norm slate Motive power Support System Supp Sys dwg Eval Req9d Room Elsv Equip Elev Function PIMS Io Notes ROB MoBter CORp Building 5 WfA PASSIVE R W/A PASSIVE R WA PASSIVE R WA PASSIVE R WA PASSIVE R MIA PASSIVE R WA PASSIVE R WA PASSIVE R NWA PASSIVE 17 S ACTIVE 17 S ACTIVE 17 B ACTIVE PSV-51-1F097 PSV.051-1F097 PSV.57-137A-1 PSV-057-137A-1 PSV-57-137A-2 PSV.05-137A.2 PSV-57-137B-1 PSV.057.1370-1 PSV-57-1 370-2 PSV-05741378-2 PSV-57*1 57C-1 PSV-W5-137C-1 PSV-57-1 37C-2 PSV.057-1370-2 PSV-57-1 37D-1 PS V-057-137D-i PSV-57-1370-2 PSV.057-137D-2 PT-42-103A PT7-042-103A PT-42-1 03B PT-042-1 038 PT-50-1N1,053 PT-USa-i N053 RHR CAC CAC CAC CAC CAC CAC CAC GAG NUCLEAR BOILER INST.NUCLEAR BOILER INST.MIA RHR HTXTO RCIC PP PSV PCIV VACUUM RELIEF VALVE ASSEMBLY A VACUUM REL1EFVALVE ASSEMBLYA VACUUM REUEF VALVE ASSEMBLY'B' VACUUM RELIEP VALVE ASSEMBLY 'B'VACUUM RELIEF VALVE ASSEMBLY 'C'VACUUM RELIEF VALVE ASSEMBLY 'C'VACUUM RELIEF VALVE ASSEMBLY 'I VACUUM RELIEF VALVE ASSEMBLY'

'REACTOR COOLANT PRESSURE REACTOR COOLANT PRESSURE RCIC PUMP SUCTION HDR IATB123 M-51, SHT 2 M-57. SHT 2 M-57, SHT 2 M-57, SHT2 M-57. SHT2 M-57, SBT 2 M-57, SHT2 M-57. SHT 2 M-57, SHT 2 M-42, SHT 1 M-42, SHT I WA 102 177 REACTOR ENCLOSURE 101 182 REACTOR ENCLOSURE 101 182 REACTOR ENCLOSURE 101 182 REACTOR ENCLOSURE 101 182 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 109 177 REACTOR ENCLOSURE 402W 253 REACTOR ENCLOSURE 402E 253 REACTOR ENCLOSURE 105 177 REACTOR ENCLOSURE Req'd Slate Colir power OPERABLE NWA 177 OPERABLE MIA OPERABLE N/R 217 OPERABLE W/R OPERABLE NIR 217 OPERABLE NMR OPERABLE NMR 217 OPERABLE MIR OPERABLE NMR 217 OPERABLE NMR OPERABLE N/R 217 OPERABLE NMR OPERABLE NMR 217 OPERABLE MIR OPERABLE N/R 217 OPERABLE NMR OPERABLE N/R 217 OPERABLE NMR OPERABLE M.R 253 OPERABLE NMR OPERABLE NMR 253 OPERABLE NMR OPERABLE N/A 177 OPERABLE WA Filler. Unit = "1" or Unit = "Common0 Sorted By Equip ID R-u Cu P.4 Page 72 Data" 6/9/95 Train Unit Line No.3 1 9554 3 1 9555 3 1 8556 3 1 9557 3 1 9558 3 1 9559 3 1 9560 3 1 9562 3 1 1102 3 1 7210 Class Eval Recfd Function 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 17 S ACTIVE 7 SR ACTIVE 7 R PASSIVE 7 R PASSIVE Equip ID PIMS ID PT-51-IN057 PT-051-iN057 PT-S2-INOSSA PT-052-INOSSA PT-52-INOSSC PT-052-I NOSSC PT-52-iNOS5E PT.OS2-1NO55E PT-52-IN055G PT-052-I N055G PT-56-I NOSSO FT-056-1NOSS0 PT-Se-i N055H PT.056-I NOSH PT-59-1 52A PT-059-152A PT-59-1 525 PT-059-1 529 SV-47-lFO009 SV-047-1 F009 SV-52-139 SV-052-139 SV-57-101 Swv.07101 System Notes WA NJA WA NIA WA N/A WA WA N/A CRD SPI CS. SP FILL CAC 74W w IIIIIICK GENERATING STATION IPEEE PROJECT UNIT 1 &COMMON SUCCESS PATH COMPONENT LIST (SPOL)Equip Desriplion Drawing No. Room No.Room Elev ROB MotherComp Building RHR PUMP SUCT SHUTDOWN CLG NIA 304E 217 REACTOR CORE SPRAY PUMP A DISCH PRESS N/A 110 177 REACTOR ENCLOSURE CORE SPRAY PUMP B DISCH PRESS NWA 117 177 REACTOR ENCLOSURE CORE SPRAY PUMP C DISCH PRESS N/A 113 177 REACTOR ENCLOSURE CORE SPRAY PUMP D DISCH PRESS NWA 114 177 REACTOR ENCLOSURE HPCI TURBINE EXHAUST PRESS NIA 200 201 REACTOR ENCLOSURE HPCI TURBINE EXHAUST PRESS NIA 200 201 REACTOR ENCLOSURE LONG TERM N2 SUPPLY TO ADS SYS NZA 402W 263 REACTOR ENCLOSURE LONG TERM N2 SUPPLY TO ADS SYS NIA 402E 253 REACTOR ENCLOSURE CR0 SCRAM DISCHARGE ISOLATION M-47. SHT 1 402 PILOT SOLENOID VALVE 253 REACTOR ENCLOSURE Lr-14GA(H)

LT-141(H)

SUPP POOL LEVEL M-52. SHT 1 118 ROOT VALVE 177 REACTOR ENCLOSURE PT-101 LT-52-140ANL)

LT-62-141(L)

SUPP M-57, SHT 1 207 POOL ATMOS 201 REACTOR ENCLOSURE Document No. 0067-0008I50=

AtIMI1din A Revision I Riwii Noon slate Motive power Support System Supp Sys "ag Equip Elev Retd State Conir power OPERABLE N/A 217 OPERABLE NIA OPERABLE WA 177 OPERABLE WA OPERABLE NIA 177 OPERABLE WA OPERABLE N/A 177 OPERABLE NWA OPERABLE N/A 177 OPERABLE WA OPERABLE NWA 201 OPERABLE NWA OPERABLE N/A 201 OPERABLE N/A OPERABLE N/A 263 OPERABLE N/A OPERABLE NIA 253 OPERABLE N/A ENERGIZED NIR 253 DEENERGIZED N/R OPEN N/A 177 OPEN 10Y101,1AD102 OPEN WA 201 OPEN 1OYI01. 1AD102 T Rlier Unit = "1"or Unit = "Common' Sorted By Equip ID U 3;U@j Doument No. W40I.0G014MM Altadmnent A Hailrl 1 Page 73 Dat.: 6/9/95 LMERICK GERA71NG STAION IPEEE PROJECT UNITICOMMON SUCCESS PATH.COMPONENT LIST (SPCL)Train Class. Equip ID System Equip Desc/ipjon Drawmg No.. Room No. Norm state Motive.power Support System Supp Sys dwg Unit Eval Rec'd Room Elev Equip Elev Line No. Function PIMS ID Notes 3 7211 6101 2 1 5101 1 5901 2 1 5951 59107 2*1 1 1.5904 2 1 910 2 5960 3 9553.3 9564 7 R PASSIVE 7 SR ACTIVE 8 B ACTIVE a B ACTIVE 8.A ACTIVE 8:B ACTIVE a B ACTIVE 8 B ACTIVE 8 B ACTIVE a B ACTIVE 17 S ACTIVE 17 S ACTIVE SV-57-1B3 SV-057-183 SV-59-1528 SV-059-152EI TO-al -i02A TO-081-1402A TD-81-1 02B T0-M8-1028 TD-81-102C TO-081-102C TD-81-1020 TD-081402D TD-Ni -102E TO-091-102E TO-91-1 02F T04814-102F 70-81-102G.

TD01-1a-I02G TO-8i -.10H TO-081-102H TE-41-1OIA TE-041-101A TE-41 -1018 TE-041-1 01B SPI PCIG.MISC.STRUCTURES

-WnAC MISC.STRUCTURES

-HVAC MISC.STRUCTURES-HVAC MISC STRUCTURES-HVAC MISC.STRUCTURES-HVAC MISC.STRUCTURES

-HVAC MISC..* STRUCTURES-HVAC MISC STRUCTURES

-HVAC NIA NIA ROB Mother Comp WETWELL H2102 SAMPLE ISOL PCIV N2 SUPPLY TO ADS SYS DIG 1A CELL VENTILATION AIR EXH FAN 1AV512 1AVSI2.DIG/1 CELL VENTILATION AIR EXt FAN.IBV512 IBV512 DIG IC CELL VENTILATION AIR EXH FAN.1CV512 iCV512 DG O1D CELL VENTILATION AIR EXH FAN 1DV512 1DV612 DIG 1A CELL VENTILATION.AIR EXH FAN IEV512 IEV512 DIG IB CELL VENTILATION AIR EXH FAN 1FV512 1FV512 DIG IC CEL..VENTILATION AIR EXH FAN IGV512 IGVS12 DIG ID CELL VENTILATION AIR EXH FAN IHV512 IHV512 SUPP POOL TEMP DIV I SUPP POOL TEMP DIV I M-57, SH"2 M-59, SHT 1 M-81, Sht 1 M-81, Sht 1 M-61, Sht I M-81, Sht 1 M 81. Sht 1 M-81. Sht I M-8. Sht f1 M,81. Sht I N/A WA Building 309W 217 REACTOR ENCL4.OSURE 304E 217 REACTOR ENCLOSURE 31.iA 217 DIESEL GENERATOR ENCLOSURE 311B 217 DIESEL GENERATOR ENCLOSURE 311C 217 DIESEL GENERATOR ENCLOSURE 317D 217 DIESEL GENERATOR ENCLOSURE 311A 217 DIESEL GENERATOR ENCLOSURE 3118 217 DIESEL GENERATOR ENCLOSURE 31.1C 217 DIESEL ENCLOSURE 3110 217 DIESEL GENERATOR.ENCLOSURE 101 182 REACTOR ENCLOSURE 101 182 REACTOR ENCLOSURE Reqfd State OPEN 217 OPEN CLOSED 217 OPEN OPEN/CLOsED 217 OPEN/CLOSED OPEN/CLOSED 211 OPEN/CLOSED OPEN/CLOSED 217 OPEN/CLOSED OPEN/CLOSED

217 OPEN/CLOSED

OPEN/CLOSED OPEN/CLOSED OPEN/CLOSED 217 OPEN/CLOSED OPENICLOSED 217 OPEN/CI.0SF 0 217 OPEN/CLOSED OPERABLE 217 OPERABLE OPERABLE 217 OPERABLE Co~ntrPower NIA IAA1102 NIR*10YI04 lOY205 lOY207 lOY207 lOY193 IDY164 10Y164 1DY206 lOY206 10Y207 10Y207 1O'I'63 lO0Y164 10YI64 N/A N/A W/A W/A Fltet. Unit =r"1or Unit ="Common" Sorted By Equip !0 c A 0, Paeo 74 Date: 6191%5 UMERICI GENERATING STATION IPEEE PROJECT UNiT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Document No. OW 006~S5.OM P~ftiA ResteM 1 Train Class Equip ID system Equip Description Drawing No. Room No. Norm state Motive powr Support System Supp SYS dwg Unit Eval Reqfd Room Elev Equip Bev Line No. Funcion PIMS In Noles ROB Mother Comp susstn Req'd State Contr power 3 17 TE-41-101C NIA SUPP POOL TEMP DIV I NIA 101 OPERABLE N/A 1 S 182 217 9565 ACTIVE TE-041-101C REACTOR OPERABLE WA ENCLOSURE 3 17 TE-41-101D NZA SUPP POOLTEMP DIV I N/A 101 OPERABLE NIA I S 182 217 9588 ACTIVE TE-O41-101D REACTOR OPERABLE WA ENCLOSURE 3 17 TE-41-101E N/A SUPP POOL TEMP DIV I NfA 101 OPERABLE NWA 1 8 182 217 9567 ACTIVE TE-041-IOIE REACTOR OPERABLE N/A ENCLOSURE 3 17 TE41-101F WA SUPP POOL TEMP DIV I N/A 101 OPERABLE NIA 1 S 182 217 9568 ACTIVE TE-O41-101F REACTOR OPERABLE N/A ENCLOSURE 3 17 TE-41-101G W/A SUPP POOLTEMP DIV1 NIA 101 OPERABLE N/A 1 S 182 217 95F9 ACTIVE TE-041-IOIG REACTOR OPERABLE NJA E.NCL.OSURE 3 17 TE-41-101H WA SUPP POOL TEMP DIV N/A 101 OPERABLE N/A 1 S 182 217 9570 ACTIVE TE-041-ID1H REACTOR OPERABLE N/A ENCLOSURE 3 17 TE-41-103A NIA SUPPPOOLTEMPDIVII N/A 101 OPERABLE N/A 1 S 182 217 9571 ACTIVE TE-041-1O3A REA-TOR OPERABLE WA ENCLOSURE 3 17 TE-41-103B WA SULPP POOL TEMP DIVIt WA 101 OPERABLE WA 1 S 182 217 9572 ACTIVE TE-041-1038 REACTOR OPERABLE N/A ENCLOSURE 3 17 TE-41-103C WA SUPP POOL TEMP DIV It N/A 101 OPERABLE N/A 1 S 182 217 9573 ACTIVE TE-041-103C REACTOR OPERABLE N/A ENCLOSURE 3 17 TE-41-1030 WA SUPP POOL TEMP DIV If N/A 101 OPERABLE NWA 1 182 217 g574 ACTIVE TE-041-103D REACTOR OPERABLE N/A ENCLOSURE 3 17 TE-41-103E WA SUPP POOL TEMP DIV JI NIA 101 OPERABLE N/A 1 S 152 217 9575 ACTIVE TE.041-103E REACTOR OPERABLE N/A ENCLOSURE 3 17 TE-41-103F N/A SUPP POOL TEMP DIV U N/A 101 OPERABLE N/A IS 182 217 9576 ACTIVE TE.O41-103F REACTOR OPERABLE N/A ENCLOSURE:1A Filter, Undt="1"or Unit = "Common" Sorted By Equip ID I. ... ,ý- .;-7 , r. -7. = = 7 ---- -0.

arC)'C C 0 UMERICK GENERATING STATION IPEEE PROJECT UNIT 1 & COMMON SUCCESS PATH COMPONENT LIST (SPOL)Doameart No. OCP.UUO Alteci.mentA Revision I Page 75 Dale. 6/9195 Train Class Equip ID System Equip Description Drawing No. Room No. Norm state Mouve power Support System Supp Sys dwg Unit Eval Req'd Room ESlv Equip Elav Line No. Fundton PIMS ID Notes ROB Mother Comp Building Rec'd State Contr power 3 17 TE-41-103G NWA SUPP POOL TEMP DIV II N/A 101 OPERABLE NIA 1 S 182 217 9577 ACTIVE m'on41 -103G REACTOR OPERABLE NWA ENCLOSURE 3 17 TE-41-103H WA SUPP POOL TEMP D1V II NIA 101 OPERABLE N/A I S 182 217 9578 ACTIVE TE-041-103H REACTOR OPERABLE WA ENCLOSURE 3 17 TE-1-1i1 N/A RHR HEAT EXCH A DISCH TO LIQUID WVA 203 OPERABLE WA 1 $ RADWASTE 201 201 9579 ACTIVE TE.O51-151 REACTOR OPERABLE WA ENCLOSURE 3 17 TE-76-121A N/A ROIC PUMP ROOM UNIT COOLER IAV208 WA 108 OPERABLE W/A 1 B 177 177 9580 ACTIVE TE"078-121A 1AV208 REACTOR OPERABLE WA ENCLOSURE 3 17 TE-76-121B NIA RCIC PUMP ROOM UNITCOOLER 1BV208 N/A 108 OPERABLE WA I 8 177 177 9581 ACTIVE TE-075-121B 1BV208 REACTOR OPERABLE NWA ENCLOSURE 3 17 TE-76-122A N/A HPCI PUMP ROOM UNIT COOLER 1AV209 N/A 109 OPERABLE NWA 1 B 177 177 9582 ACTIVE TE-C76-122A 1AV209 REACTOR OPERABLE NWA ENCLOSURE 3 17 TE-76-122B WA HPCI PUMP ROOM UNIT COOLER 1BV209 NIA 109 OPERABLE WA I B 177 177 9583 ACTIVE TE-076-122B 1BV209 REACTOR OPERABLE WA ENCLOSURE 3 17 TE-76-12aA WA RHR PUMP ROOM UNIT COOLER IAV210 NIA 102 OPERABLE NWA 1 a 177 177 9584 ACTIVE TE-076-123A 2AV210 REACTOR OPERABLE WA ENCLOSURE 3 17 TE-76-123B NWA RHR PUMP ROOM UNIT COOLER 1BV210 N/A 103 OPERABLE NIA 1 B 177 177 9585 ACTIVE TE-O75-123B 1BV210 REACTOR OPERABLE WVA ENCLOSURE 3 17 "E-76-123C NIA RHR PUMP ROOM UNIT COOLER iCV210 WA 102 OPERABLE N/A 1 B 177 177 9586 ACTIVE TE-O76-123C 1CV210 REACTOR OPERABLE NIA ENCLOSURE 3 17 TE-76-123D N/A RHR PUMP ROOM UNIT COOLER lDV210 NIA 103 OPERABLE NWA I S 177 177 95117 ACTIVE TE.07-123D lDV210 R.REACTOR OPERABLE NWA AV1 ENCLOSURE 3 17 TE-76-123E NIA RHR PUMP ROOM UNIT COOLER 1EV210 NIA 102 OPERABLE NIA I B 177 177 9588 ACTIVE TE-076-123E IEV210 REACTOR OPERABLE N/A ENCLOSURE Fitter Unit "" sor Unit a "Common" Sorted By Equip 1D 91 G Page 76 Date: 6//195 W UMERICK GENERATING STATION IPEEE PROJECT UNITI & COMMON SUCCESS PATH COMPONENT UST (SPCL)Documnert No. 00574OUBM Revislwt I Train Class Equip ID System Equip Description Drawing No. Room No. Norm state Motive power Support System Supp Sys dwg unit Eval Req'd Room Elav EqUp Elev Lie No. Function PIMS ID Notes ROB Mother Camp Building Reqd State Conk" power 3 17 TE-76-123F WA RHR PUMP ROOM UNIT COOLER IFV210 WA 103 OPERABLE WA 1 5 177 177 9589 ACTIVE TE.076-123F 1FV21D REACTOR OPERABLE WA ENCLOSURE 3 17 TE-76-123G WA RHR PUMP ROOM UNIT COOLER IGV210 WA 102 OPERABLE N/A 1B 177 177 O590 ACTIVE TE-076-123G IGV210 REACTOR OPERABLE N/A ENCLOSUfRE 3 17 TE-76-12314 N/A RHR PUMP ROOM UNIT COOLER 1HV210 NIA 103 OPERABLE N/A I B 177 177 9591 ACTIVE TE-076-123H IHV210 REACTOR OPERABLE NIA ENCLOSURE 3 17 TE-76-124A N/A CORE SPRAY PUMP ROOM UNIT NIA 110 OPERABLE N/A 1 B COOLER 1AV211 177 177 9M ACTIE TE-016-124A IAV211 REACTOR OPERABLE WA ENCLOSURE 3 17 TE-76-124B N/A CORE SPRAY PUMP ROOM UNIT NIA 117 OPERABLE N/A IB COOLER IBV211 177 177 9593 ACTIVE TE-07r.124B 1BV211 REACTOR OPERABLE WA ENCLOSURE 3 17 TE-76-124C WA CORE SPRAY PUMP ROOM UNIT NIA 113 OPERABLE WA 1 a COOLER 1CV211 177 177 00 ACOTIVE TE.-076-124C ICV211 REACTOR OPERABLE N/A ENCLOSURE 3 17 TE-76-124D WA CORE SPRAY PUMP ROOM UNI NIA 114 OPERABLE N/A I a COOLER IDV211 177 177 9601 ACTIVE TE-076-124D 1DV211 REACTOR OPERABLE WVA ENCLOSURE 3 17 TE-78-124E N/A CORE SPRAY PUb PROOM UNIT N/A 110 OPERABLE NIA 1 B COOLER IEV211 177 177 9W2 ACTIVE TE-076-124E 1EV211 REACTOR OPERABLE WA ENCLOSURE 3 17 TE-76-124F NIA CORE SPRAY PUMP ROOM UNIT NIA 117 OPERABLE N/A I B COOLER 1FV211 177 177 9603 ACTIVE TE-076-124F 1FV211 REACTOR OPERABLE N/A ENCLOSURE 3 17 TE-76-124G NIA CORE SPRAY PUMP ROOM UNIT WA 113 OPERABLE NIA 1 B COOLER I GV211 177 177 9604 ACTIVE TE-076-124G 1GV211 REACTOR OPERABLE WA ENCLOSURE 3 17 TE-7B-124H WA CORE SPRAY PUMP ROOM UNIT N/A 114 OPERABLE N/A 1 B COOLER 1HV211 177 177 K05 ACTIVE TE-076-124H 1HV211 REACTOR OPERABLE WA ENCLOSURE 3 17 TE-81-040A N/A SPRAY POND AIR SUP FAN aAV543 N/A 1000 OPERABLE NWA Common S 265 9622 ACTIVE TE-081-040A SPRAY POND PUMP OPERABLE WA STRUCTURE Filer Unit = 1" or Unit = "Common" Sorted By Equip ID V I.Jr Page 77 Date: 6W5 40 e UMERICK GENERATING STAnCH IINE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST ISPCL)DOcumard No.0W8U8 MidneA Revisbi 1 Tmfl Class Equip ID System Equip Desciption Drawing No. Room No. Norm stie Motve power Support System Supp Sys dwg Unit Eval Ree'd Roam Elev Equip Eley Line No. Function PIMS ID Notes ROB Mother Comp Building Reafd Slate Contrpower 3 17 TE-61-O40B WA SPRAY POND AIR SUP FAN 0BV543 N/A 1005 OPERABLE N/A Common S 268 9623 ACTIVE TE-OBI-O4DB SPRAY POND PUMP OPERABLE N/A STRUCTURE 3 17 TE.81-041A WA SPRAY POND AIR SUP FAN 0AV543 N/A 1000 OPERABLE NZA Common S28 9624 ACTIVE TE-O81-041A OSPRY POND PUMP OPERABLE WA brTRUCTURE 3 17 TE-81-041B NIA SPRAY POND AIR SUP FAN 0BV543 N/A 1005 OPERABLE NIA Common 8 268 9625 ACTIVE TE-081-041B 08V543 SPRAY POND PUMP OPERABLE NIA STRUCTURE 3 17 TI-41-101 SPI SUPPRESSION POOL TEMP DIV I M41. SHT 2 533 OPERABLE WA B BR 269 269 7212 ACTIVE TI-041-101 10C626 CONTROL OPERABLE I1YII STRUCTURE 3 17 TI-41-102 NUCLEAR SUPPRESSION POOL TEMP INDICATOR M-41, SHT2 E40 OPERABLE N/A I BR BOILER 289 289 7213 ACTIVE TI-041-102 1DC201 CONTROL OPERABLE 1AD102 STRUCTURE 3 17 TI-41-103 SPI SUPPRESSION POOL TEMP DIV II M-41, SHT 2 533 OPERABLE NZA I ER 269 269 7214 ACTIVE TI-041-1O3 10C526 CONTROL OPERABLE l0Y102 STRUCTURE 3 17 TI-50-140B NIA RCIC TURBINE BEARING OIL TEMP N/A 108 OPERABLE N/A 1 B COUPLING END 177 177 9606 ACTIVE TI-050-140B 10S212 REAC2TOR OPERABLE WA ENCLOSURE 3 17 TISH-120-121A N/A DIESEL OIL DAY TANK IAT528 HIGH N/A 31ZA OPERABLE WA 1 B TEMP STOP XFER PUMP 217 9607 ACTIVE T1SHD2O-121A IAT528 DIESEL GENERATOR OPERABLE N/A 3 17 TISH-20-1218 N/IA DIESEL OIL DAYTANK 1BT528 HIGH NWA 312B OPERABLE N/A I B TEMP STOP XFER PUMP 217 9608 ACTIVE TISH.020-121B IBT528 OPERABLE N/A 3 17 TISH-20-121C N/A DIESEL OIL DAY TANK 1CT528 HIGH N/A 312C OPERABLE N/A 1 B TEMP STOP XFER PUMP 217 9609 ACTIVE TISH-020-121C 1CT528 OIESELOENERATOR OPERABLE N/A 3 17 TISH-20-121D NIA DIESEL OIL DAYTANK 1DT528 HIGH WA 312D OPERABLE WA IB TEMP STOP XFER PUMP 217 9610 ACTIVE TISH-020-121D 1DT52B DIESEL GENERATOR OPERABLE WA 3 17 XR-42-1R623A NUCLEAR BOILER WIDE RANGE REACTOR PRESSURE M-42, 6HT 1 533 OPERABLE 1OY10I 1 BR INST. (LV/PX) 269 269 7102 ACTIVE XR-042-1RS23A 10C601 CCNTROL OPERABLE 10Y1011. IAD102 STRUCTUREUnit "I" or Unit = 'Common* Sorted By Equip WD

,

S. Page 78 Date: 61995 Train Unit_. Line No.S 3* -1 7105 3 I 1103.t 3 1104 J 3 2207 5902.2 5952 1 2 5908 2 1..5905 2 I.* 5955* I II 5911 14 5961 6 Document No. BoUTW411I..0M AtlactmentA Revison I UMERICK GENERATING STATION IPEEE PROJECT UNIT I & COMMON SUCCESS PATH COMPONENT LIST (SPCL)Class Equip ID System Equip Description Drawing No. Room No. Norm slate Motwe power Suppor ,ysrern S upp Sys dwg Eva] Xeqfd Function 17 BR ACTIVE 5 S ACTIVE 5 S ACTIVE 20 S PASSIVE a B ACTIVE B B ACTIVE 8 B ACTIVE a ACTIVE B ACTIVE a B ACTIVE a 8 ACTIVE a B ACTIVE PIMS ID XR-42-I R623B XR-042-1R523B XV-47.1FC 1^XV-047-1F010 XV IFOl XV-047-1F011O XY-42-1D002 XY-042-1D002 ZC-81-102A ZC-081-102A ZC-81-102B ZC-081I102B ZC-81-102C ZC-081 -102C ZC-81-1020 ZC-Ca1l -102l ZC-81-102E ZC-01-102E ZC.81 -1 02 W0-0814-021 ZC-81-102G ZC.0-81-102G ZC,81-102H ZC-081-1021-1 Notes ROB Mother Camp NUCLEAR BOILER WIDE RANGE REACTOR PRESSURE M-42. SHT I INST. (LVIPX)100501 CR0 SCRAM DISCRHARGE VOLUME PIPING M.-47 SHT I VENT SOV PCIV CRD SCRAM DISCHARGE VOLUME PIPING M-47, SHT I DRAIN SOV PCIV NUCLEAR BOILER NUCLEAR BOILER VESSEL CONDENSING M-42, Shl 1 INST. CHAMBER MISC*. 013 IA CELL VENTILATION AIR EXH FAN M-81, Shlt 1 STRUCTURES-IAV512 UVAC IAV512 MISC. DIG I0 CELL VENTILATION AIR EXH FAN M-81. Shf I STRUCTURES-1BV512 NVAC S IBVSI2 MISC. DIG IC CELL VENTILATION AIR EXH FAN M-81.Sht 1 STRUCTURES

-ICV512-VAC 6 1CVS12 MISC. DIG I D CELL VENTILATION AIR EXH FAN m-ai, Sht I STRUCTURES

-IDV512 HVAC 6 1DV512 MiSC. DIG 1A CELL VENTILATION AIR EXH FAN WE-1, Shl I STRUCTURES

-1EV512 I-VAC 6 IEV512 MISC. DIG 1B CELL VENTILATION AIR EXH FAN M-81, ShN 1 STRUCTURES

-1FV512 HVAC 6 1FV512 MISC. DIG IC CELL VENTILATION AIR EXH FAN mi-8i, ShIt 1 STRUCTURES-1GV512 6 IGV512 MISC. DIG 1D CELL VENTILATION AIR EXH FAN M-l. Sht I STRUCTURES-IHVS12 HVAC 6 IHV512 Room Elsv Equip Elev Building Reqd Slate 533 OPERABLE 269 269 CONTROL OPERABLE 8TRUCT1RE 402 OPEN 253 280 REACTOR CLOSED ENCLOSURE 307 OPEN 217 253 REACTOR CLOSED ENCLOSURE 490O NIA 237 253 REACTOR N/A ENCLOSURE 311A OPERABLE 217 217 DIESEL GENERATOR OPERABLE ENCLOSURE 3119 OPERABLE 217 217 DIESEL GENERATOR OPERABLE ENCLOSURE 311C OPERABLE 217 217 01555 GSNERATOR OPFRABLE ENCLOSURE 311D OPERABLE 217 217 DIESELOENERATOR OPERABLE ENCLOSURE 311A OPERABLE 217 217 OPERABLE ENCLOSURE 3118 OPERABLE 217 217 ODSELGENERATOR OPERABLE ENCLOSURE 3110 OPERABLE 217 217 DESELGENERATOR OPERABLE ENCLOSURE 311D OPERABLE 217 217 DIESEL GENERATOR OPERABLE ENCLOSURE Conkr power 10Y102 10Y102 NIR NMR MIR NIR NIA MIA NIR N/R N.R NMR NMR N/R NIR N/R N/R NM NMR NMR NMR NMR NIR Filter. Unit = "I ot Unit a 'Common" Sorted By Equip 1D Ppop 7 LoaIICE4EAh 4TTO IEEE PROJECT car e DOW BMWS UNWT I &COMMON Auuel SUCCESS PATH COMPONlENT LIST (SPCIJRLl)e Train Gloss Eqtip 0 svntan EqUIP Dto-Wan Drawinga No. Room No& INMIAH daa olu pom &9Wom Syotmo SoppSwo du Unit E COReQu- Romn Etw EquipEkev Line NO Fleunco PINS ID Nalln ROBl Meowilar en* Bjtah RetfdSWDt Contpow" NOTES-KEY 1 Either HV-11-123 or HV-11-121 must close 2 Either HV-11-128 or HV-11-124 must remain dosed 3 Either HV-11-055B or V-1 1-51B must remain closed 4 Either l'V-1-1128 or HV-11425 must close 5 Potential rule of the box 6 Valve locked closed, breaker locked open 7 Either HV-1 1-55A or HV-1 1-S1A must remain closed 9 Either WV-11 -223 or HV-1 1-221 must cose 9 Either -V.048 or HV- 1-043 must close 10 Either HV-I-I073 or W-i1-078 must Close 11 Locked closed 12 Motor operated check valve 13 Either HV-11-225 or WV-1I-22M must close 14 Preferred LPCI Injection path 15 Valve position Inconsequential for SPC mode 16 Alternate LPCI injection path 17 Preferred RHRSC Injection path 18 Alternate RHRSC Injection path 19 Either HV-11-121 or HV-11-123 must close 20 Locked open 21 Either HV-11-079 or V-1 1.049 must open 22 Either V-11.071 or HV-11-041 must open 23 Either HV-I 1-074 or HV-I1-044 must open 24 Either HV-tl-048 or HV-1 1-076 must open 25 Either HV-1 1-047 or V-1 1-077 must open 26 Required for 2 unit simultaneous shutdown 27 Apply rute of the box to SOVs (2 per PSV) controlled by 113 and 114 series hand switches 28 Control rod drive hydraulic control unit. Rule of the box 29 Main Control Room Indication.

Panel contains power supplies and Indicator lights required for LPR 's 30 Neutron monitoring tubs, typical of 172. Located In reactor, among fuel bundles 31 Operates IJPCI turbine governor valve 32 Operates HPCI turbine remote trip valve 33 Operates RCIC turbine governor valve 34 Operates RCIC turbine remote trip valve 35 Panel contains electronics and power supplies required for LPRM's 36 These components were deleted from the SPCL 37 This Is an In-line orifice plate. Componw-t not required.Limerick Generating Station Unit 1 MPR.3796.

Revision 1 Correspondence No.: RS-12-171 B-81 Exelon NTTF 2.3: Seismic Walkdown Seismic Walkdown Equipment List (SWEL)UNIT: LIMERICK UNIT 1 JPEER REVIEWER: g waner, NMPR PEER REVIEW TEAM LEADER: Patrick Butler, MPR LIMERICK OPERATIONS:

Wandon Shultz Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrqnnnrlPnrP-Nn -RR-19-171 B-82 Table B-1. SWEL for Unit 1 Unit Component ID Description IPEEE Class EPRI Class Building Elevation Location NTTF 2.3 Risk New or IPEEE Function Significant?

Replace? Enhancement?

1 10S211 HPCI Turbine (00) Other (00) Other Reactor Enclosure 177 Room 109 3 Y N N 1 10-S224-30-19 CRD Hydraulic Control Unit (00) Other (00) Other Reactor Enclosure 253 Room 1 N N N 402E 1 I0Al18 Switchgear, 4KV, 3PH, 3 (01) Motor Control Centers / Low (03) Medium Voltage, Control Structure 239 Room 432 3.4 Y N N Wire, 60Hz & Medium Voltage Switchgears Metal-Clad Switchgear 10B201 D114 Reactor Area (01) Motor Control Centers I Low (02) Low Voltage Roo Safeguard Load Center & Medium Voltage Switchgears Switchgear and Breaker Reactor Enclosure 313 Room 1,2,3,4,5 N N N IPanels 602W Reactor Area 480V (01) Motor Control Centers I Low (02) Low Voltage Room 1 10B204 Safeguard Load Center & Medium Voltage Switchgears Panels 506E 1.2,3.4,5 N N N D114 Reactor Area (01) Motor Control Centers/Low (01) Motor Control 1 10B211 Safeguard 480V Motor Centers and Wall- Reactor Enclosure 217 Room 1,2,3,4,5 Control Center & Medium Voltage Switchgears Mounted Contactors 304W D1 14-R-C Reactor Area (01) Motor Control Centers / Low (01) Motor Control 1 10B213 Safeguard 480V Motor & Medium Voltage Switchgears Centers and Wall- Reactor Enclosure 283 m 1,2,3,45 N N N Control Center Mounted Contactors 506W 1 10B214 D124 Reactor Area (01) Motor Control Centers / Low (01) Motor Control Safeguard 480V MCC & Medium Voltage Switchgears Centers and Wall- Reactor Enclosure 283 Room 306 1,2,3,4,5 N N N 1 1Mounted Contactors I 10B515 0114-D-G Diesel Gen. Area (01) Motor Control Centers / Low (01) Motor Control Diesel Generator Room Safeguard 480V MCC & Medium Voltage Switchgears Centers and onac- Building 31 1A Room Mounted ContactorsBudig27 31 1,345 N 1 10D202 Reactor Enclosure 250V DC (01) Motor Control Centers / Low (01) Motor Control Motor Control Center & Medium Voltage Switchgears i Centers and Wall- Reactor Enclosure 217 Room 1,2,3,4,5 N N N Mounted Contactors 304E 1 10X109 DIV IV 4KV Transformer (02) Transformers (04) Transformers Control Structure 239 Room 432 1,2,3,4,5 N N N 1 10X204 4KV-480V Transformer (02) Transformers (04) Transformers Reactor Enclosure 283 Room 506E 1,2,3,4,5 N N N 1 10X282 B Reactor Enclosure HVAC (02) Transformers (04) Transformers Control Structure 304 Room 619 1,2,3,4,5 N N N TransformerI 1 10P203 RCIC Pump (02) Horizontal Pumps (05) Horizontal Pumps Reactor Enclosure 177 Room 108 3 N N N 1 10P204 HPCI Pump (03) Horizontal Pumps (05) Horizontal Pumps Reactor Endosure 177 Room 109 3 Y N N 1 1AP202 RHR Pump (04) Vertical Pumps (06) Vertical Pumps Reactor Enclosure 177 Room 102 4 Y N N 1 1AP206 Core Spray Pump and Driver (04) Vertical Pumps (06) Vertical Pumps Reactor Enclosure 177 Room 110 3 N N N Diesel Generator Diesel Oil (04) Vencal Pumps (06) Ventcal Pumps Diesel Oil Storage Tank 1 1AP514 Pump (04) Underground Structure 206 Yard 1.2,3,4,5 N N N Lnýera Gemmrtk~a Stuior Onat MPR'e-ru, sevis I Cwourruerue No.: es-I 2.171 B-83 Table B-1. SWEL for Unit 1 Unit Component ID Description IPEEE Class EPRI Class Building Elevation Location NTrF 2.3 Risk New or IPEEE Function Significant?

Replace? Enhancement?

1 HV-011-042 HPCI PP RM CLR RET to (05) Fluid (Air/Hyd)

Valves (07) Pneumatic-Operated Reactor Enclosure 177 Room 109 3 N N N ESW Loop B Valves RHR PP RM CLR A Supply (0)Fud(r/y)Vve (0)PumtcOrtd 1 HV-11-104A Valve (05) Fluid (Air/Hyd)

Valves (07) Pneumatic-Operated Reactor Enclosure 177 & 191 Room 102 4 N N N ValveValves 1 HV-57-131 Suppression Pool Purge (05) Fluid (AirlHyd)

Valves (07) Pneumatic-Operated Reactor Enclosure 217 Room 309 5 N N N Inboard PCIV Valves (08) Motor-Operated and HV-55-1F003 HPCI Steam Outboard (06) Motor Operated Valve Solenoid-Operated Reactor Enclosure 217 & 238 Room 309 3 N Y N IIsolation Valve Vle___________Valves HV-051- 1A RHR HTX RHRSW Inlet (08) Motor-Operated and 1 1F014A Valve (06) Motor Operated Valves Solenoid-Operated Reactor Enclosure 201 Room 203 4 Y N N Valves ESW EDG JW Cooling (08) Motor-Operated and Diesel Generator 217 Room 12345 N N N SHV-11-132A S al (06) Motor Operated Valves Solenoid-Operated Building 311A Isolation Valve Valves (08) Motor-Operated and RCIC Suppression Pool (06) Motor Operated Valves Solenoid-Operated Reactor Enclosure 177 Room 108 3 N N N 1 V-4 -F0 9 Isolation ValveV l e Valves (08) Motor-Operated and HV-52-1F037 Core Spray Isolation Valve (06) Motor Operated Valves Solenoid-Operated Reactor Enclosure 283 Room 523 3 N N N (MOV outboard of Dreywll) Valves (08) Motor-Operated and IHV-55-F004 CST to HPCI Pump Suction (06) Motor Operated Valves Solenoid-Operated Reactor Enclosure 177 Room 109 3 N Y N Isolation Valve Valves (08) Motor-Operated and SV-47-1F009 CRD SCRAM Discharge (07) Solenoid Operated Valves Solenoid-Operated Reactor Enclosure 253 Room 402 1 N N N Isolation Pilot Solenoid Valve Vle Valves 1 IAV209 HPCI Pump & Turbine Room (08) Fans & Air Handlers (10) Air Handlers Reactor Enclosure 177 Room 109 3 N N N Cooler 1 1AV210 RHR Pump Room Unit Cooler (08) Fans & Air Handlers (10) Air Handlers Reactor Enclosure 191 Room 102 4 N N N 1 1AV512 DIESEL GENERATOR/

(08) Fans & Air Handlers (09) Fans Diesel Generator 217 Rm 1,2,3,4,5 Y N N Room Ventiliation Fan Building 311A 1CV211 C Core Spray Pump Room (08) Fans & Air Handlers (10) Air Handlers Reactor Enclosure 190 Room 113 3 N N N UVnit Cooler 1FV211 B Core Spray Pump Room (08) Fans & Air Handlers (10) Air Handlers Reactor Enclosure 177 Room 117 3 N N N Unit Cooler F 1 TD-081-102A Vent Air Exhaust Fan Damper (08) Fans & Air Handlers (10) Air Handlers Diesel Generator 217 Room 1,2,3,4.5 Y N N Building 311A B Diesel Generator Starting Diesel Generator Room 1ir CBmprese or B1 rg (10) Air Compressors (12) Air Compressors 217 1,2,3,4,5 N N N 1 1I53 Air Compressor B1 Buildingl 311 B Division IV SFGD VAC (14) Distribution Panels 1 10Y104 Instument Panel 10Y104 (12) Distribution Panels and Automatic Transfer Control Structure 239 Room 432 1.2,3,4,5 N N N Service Desc. Switches Lirmerrý OerIMa Sarano Und I MPR.3796.

R.WýIan C ... srnoe No. Rr:,O12-171 B-84 Table B-1. SWEL for Unit 1 Unit Component ID Description IPEEE Class EPRI Class Building Elevation Location NTTF 2.3 Risk New or IPEE Function Significant?

Replace? Enhancement?

BTurbine Enoloser 120 V (14) Distribution Panels P 1BD102 ower Distribution Panel (12) Distribution Panels and Automatic Transfer Reactor Enclosure 254 Room 452 1.2,3,4.5 N N N Switches (14) Distribution Panels I 1CD105 125V DC Fuse Box (12) Distribution Panels and Automatic Transfer Control Structure 217 Room 324 1,2,3.4.5 N N N Switches 1 1A2D101 125VDC Battery (13) Batteries

& Racks (15) Battery Racks Control Structure 239 Room 436 1,2,3,4,5 Y N N 1 1 lDD101 125V DC Battery (13) Batteries

& Racks (15) Battery Racks Control Structure 217 Room 323 1,2,3,4,5 Y N N I 1AD160 A RPS & UPS Distribution (14) Battery Chargers and (15) Battery Chargers and Control Structure 254 Room 452 2.3 N N N Panel Static Inverter Inverters Inverters 1 1DD103 125 VDC Battery Charger (14) Battery Chargers and (16) Battery Chargers and Control Structure 217 Room 323 1.2,3,4.5 N N N Inverters Inverters 1 1AG501 D11 Diesel Generator (15) Engine Generators (17) Engine Generators Diesel Generator 217 Room 1,2,3,4,5 Y N N Building 311A Diviion Cor Spry SytemRoom 10C001 Diison IrCore Spray System (16) Instruments on Racks (18) Instrument Racks Reactor Enclosure 217 W 3 N N N 1lC027 Located Behind HCUs next to Room 23 the Drywell Personnel Hatch (16) Instruments on Racks (19) Instrument Racks Reactor Enctosure 253 402E , N N N 1 LI-52-140A Suppression Pool Level (16) Instruments on Racks (18) Instrument Racks Control Structure 269 RoomR 3,4 N N N (MCR)_______

1 TI-41-101 Suppression Pool Temp DIV I (16) Instruments on Racks (18) Instrument Racks Control Structure 289 Room 540 5 N N N 1 XR-42-1R623A Wide Range Reactor (16) Instruments on Racks (18) Instrument Racks Control Structure 269 Room 533 2 N N N Pressure (M R 2 FT-51.1N00 RHR HTX A & Pump A (17) Temperature Sensors/Local (18) Instrument Racks Reactor Enclosure 217 Room 4 N N N Discharge Flow Instruments (Not on Racks) 304W 1 LSHL-20-122A Diesel Oil Day Tank Hi / Low (17) Temperature Sensors/Local

8) Instrument Racks Diesel Generator Room N Level Instruments (Not on Racks) (I Structure 217 311A 1,2,3.5 1(17) Temperature Sensors/Loal (18) Instrument Racks Reactor Enclosure 253 Roo 3 N N N Instruments (Not on Racks) 402E (17) Temperature Sensors/Local (18) Instrument Racks Resel eneaor 253 Room 1,2 N N N 1 PDS-059-106B N2 Supl DSfSyse m (18) Instrument Racks Reactor Enclosure 253 4029 2.4 N N N Instruments (Not on Racks)1 PDSH-12-102B DHSriFeR Suction Pup (17) Temperature Sensors/Local (18) Instrument Racks Diesel Generator 217 Room 12345 N N N 1 A to RHR Sti Instruments (Not on Racks) Building 311B 51 R e -Differential (17) Temperature Sens Local (18) Instrument Racks Reactor Enclosure 253 Room 34 N N N I_ 1N060B Pressure Instruments (Nol on Racks) _______________

402E 1 PSL-12-102A RHR Service Water Pump (17) Temperature Sensors/Local (18) Instrument Racks Reactor Enclosure 195 Room 202 4 N N N L X A Instruments (Not on Racks)PT-42-103B Reactor Coolant Pressure (17) Temperature Sensors/Local (1)IsruetRckoecorEcourm5 N N N Instruments (Not on Racks) 4029IstumntRacs eato Eclour 23 02 1 TISH-20-121B Diesel Oil Day Tank 1CT528 (17) Temperature Sensors/Local (19) Temperature Diesel Generator Room 1,2,3,4,5 1 HighTempStopXFER Pump Instruments (Not on Racks) Sensors Building 312B Limedoc Generamtig Station Unit I MPRR3796, Reotaon 1 Co.eopondenc No" RS-12-171 B-85 Table B-1. SWEL for Unit 1 Unit Component ID Description IPEEE Class EPRI Class Building Elevation Location NTTF 2.3 Risk New or IPEEE Function Significant?

Replace? Enhancement?

1 10C602 Reactor Recirc panel (18) Control Panels & Cabinets (20) Instrumentation and Control Structure 269 Room 533 1,4 N N N Control Panels (MCR)1 10C603 Reactor Control Panel (18) Control Panels & Cabinets (20) Instrumo Control Structure 269 Rm 533 12,3 N N N Control Panels CnrlSutre 29 (MCR) 123 N NN 1 10C609 RPS Channel "A' Vertical (18) Control Panels & Cabinets (20) Instrumentation and Control Structure 289 Room 542 1,2,3 N N N Board Control Panels 1 10C626 ADS Control Room Panel (18) Control Panels & Cabinets (20) Instrumentation and Control Structure 269 Room 533 2 N N N Control Panels (MCR)1 10C647 Panel HPCI Vertical Board (18) Control Panels & Cabinets (20) Instrumentation and Control Structure 269 Room 5 3 N N N Control Panels (MCR)(20) Instrumentation and Diesel Generator Room 1,34. N NN 1 10TB-053 Rack / Panel (Terminal Box) (18) Control Panels & Cabinets 217(12345 N N N Control Panels Building 311A 1 3 Diesel Generator Enclosure (20) Instrumentation and Diesel Generator Room N N N 1 1AC563 HVAC Control Panel (18) Control Panels & Cabinets Control Panels Building 2 311A 1 1 1AD106 125/250V DC Current (18) Control Panels & Cabinets (20) Instrumentation and Control Structure 239 Room 435 1,2,3.4,5 N N N Transducer Panel Control Panels 1 IAG502 Dl1 EDG Excitation System (18) Control Panels & Cabinets (20) Instmentation and Diesel Generator 217 Room 1,23,4.5 N N N Cabinet Control Panels Building 311A 1 IAJ860 ESS DIV 1 (18) Control Panels & Cabinets (20) Instrumentation and Diesel Oil Storage Tank 206 Yard 1,2.3.4.5 N N N 1 _____J8 ___0 ESSDV__1___onoPaels&

_abiet Control Panels Underground Structure (20) Instrumentation and Room 2 NN 1 1AS921 MSRV Postion Monitor (18) Control Panels & Cabinets Control Panels Reactor Enclosure 253 m 2 N N N 1 1CC208 Unit Cooler Control Panel (18) Control Panels & Cabinets (20) Instrumentation and Reactor Enclosure 201 Room 208 3,4 N N Control Panels 1 1DC661 Panel D Safegard System (18) Control Panels & Cabinets (20) Instrumentation and Control Structure 269 Room 533 1,2,34.5 N N N Vertical Board _ Control Panels (MCR)1 1AE205 Residual Heat Removal Heat (19) Vertical Tanks or Heat (21) Tanks and Heat Reactor Enclosure 177 Room 102 4 Y Y N Exchanger Exchangers Exchangers B Diesel Generator Starting (19) Vertical Tanks or Heat (21) Tanks and Heat Diesel Generator 217 Room 1,2,3,4,5 N N N 1 1BIT558 Air Reservoir B1 Exchangers iExchangers Building 37311m 1 1BE205 RHR Heat Eshaniger (19) Vertical Tanks or Heat (21) Tanks and Heat Reactor Enclosure 177 Room 103 4 Y Y N 1 1BE205 e Exchangers Exchangers I (19) Vertical Tanks or Heat (21) Tanks and Heat Room 1 1BS252-1 B PCIGADS Exchangers Exchangers Reactor Enclosure 217 3E 2 N N N 1 1BT528 B Diesel Generator Day Tank (19) Vertical Tanks or Heat (21) Tanks and Heat Diesel Generator 217 Room 1,2.3.4.5 N N N 1_BT28 B __seGeaoraTn Exchangers iExchangers Building 312B 1 1AS575 Diesel Generator Exhaust (20) Horizontal Tanks or Heat (21) Tanks and Heat Diesel Generator 217 Room 1.2,3,4,5 N N N Silencer Exchangers Exchangers Building 311A 1 IAT564 Diesel Generator Jacket (20) Horizontal Tanks or Heat (21) Tanks and Heat Diesel Generator 217 Room 1,2,3.4,5 N N N 1 _1AT5_4 Water Expansion Tanks Exchangers Exchangers Building 311A O~encr i-Mg OS n u,4 MMPR379. R.W I t~rfloT-dtýx*

.: 50-12-17i B-86 Table B-2. SWEL for Unit 0 (common)Unit Component ID Description IPEEE Class EPRI Class Building Equip Location NTIF 2.3 Risk New or IPEEE Elev Function Significant?

Replace? Enhancement?

Control Enclosure Safeguard 440V (01) Motor Control Centers I Low & (01) Motor Control Centers aMCC Medium Voltage Switchgears and Wall-Mounted Control Structure 304 Room 619E 1,2,3,4,5 N N N Contactors 0 00B519 Spray Pond 440VAC Power MCC (01) Motor Control Centers / Low & (01) Motor Control Centers and Wall-Mounted Spray Pond 8 om 00 123l, Medium Voltage Switchgears Contactors Building 0 01X566 DIV I Spray Pond Pump Structure (02) Transformers (04) Transformers Spray Pond 268 Room 1000 1.2,3,4,5 N N N 120V AC Instrument Panel XFMR Building 0 OAP162 Control Room HVAC Chilled Water (03) Horizontal Pumps (05) Horizontal Pumps Control Structure 200 Room 258 1,2,3,4,5 N N N PumpI 0 0AP506 RHR Service Water Pump (04) Vertical Pumps (06) Vertical Pumps Spray Pond 268 Room 1000 4 Y N N Building 0 0AP548 Emergency Service Water Pump (04) Vertical Pumps (06) Vertical Pumps Spray Pond 268 Room 1000 1,2,3,4,5 Y N N Building 0 HV-078-021B Outside Air to MCR Isolation Valve (05) Fluid (Air/Hyd)

Valves (07) Pneumatic-Operated Control Structure 304 Room 619 1,2,3,4,5 N N N Valves 0 HV-12-032A Spray Nozzles A Inlet (06) Motor Operated Valves (08) Motor-Operated and Spray Pond 256 Room 1010 1,2,3,4,5 Y N N Solenoid-Operated Valves Building 0 OV543 B' Spray Pond PP. Structure Air Fans & Air Handlers ( Fans Spray Pond 268 Room 1005 1,2,3,4,5 Y N N Supply Fan (08) Building 2 R I 0 HD-078-027A Control Room Intake Damper (08) Fans & Air Handlers (10) Air Handlers Control Structure 304 Room 619 1,2,3,4,5 N N N 0 HD-081-041A Spray Pond Intake Fan Damper (08) Fans & Air Handlers (10) Air Handlers Spray Pond Building 268 Room 1005 4 Y N N 0 OAK112 Control Structure Chiller (09) Chillers (11) Chillers Control Structure 200 Room 258 1,2,3.4,5 N N N 0 PSH-12-004A RHR Service Water Pump 0A506 (17) Temperature Sensors/Local (18) Instrument Racks Spray Pond 268 Room 1000 1,2,3,4,5 N N N Loop A Instruments (Not on Racks) Building 0 AC564 Control Panel Spray Pond Pump (18) Control Panels & CaCinets (20) Instrumentation and Spray Pond 268 Room 1000 1,2,3,4,5 N N N)Stuctura Air Supply Fan Control Panels Building (20)ur Instrumentatio n an Ror93 0 0CC667 ESW Division Ill Control Panel (18) Control Panels & Cabinets (20) Instrumentation and Control Structure 269 Room 533 4 N N N I Control Panels (MCR )_III Unwia Orallnu Sualon unft 1 MMa37se, Remson 1 CO-Wenodonc.

So.. RS-1 2-1 71 B-87 Table B-3. Deferred to RFO: Inaccessible, or Requires Removal of Insulation to see Anchorage NTTF 2.3 Risk New or IPEEE Unit Component ID Description IPEEE Class EPRI Class Building Elevation Location Function Significent?

Replace? Enhancement?

1 HV-41-1F022A Inboard Main Steam (05) Fluid (Air/Hyd)

Valves (07) Pneumatic-Operated Reactor 279 Room 400 5 N N N Isolation Valve Valves Enclosure (DW) 29 Ro 0 I HV-41-IF028A Outboard Main Steam (05) Fluid (Air/Hyd)

Valves (07) Pneumatic-Operated Reactor Isolation Valve Valves Enclosure_279_Room515_NNN 1 HV- 41-1F074A FDWTR Inboard Isolation (05) Fluid (Air/Hyd)

Valves (07) Pneumatic-Operated Reactor 279 Room 518 5 N N N Valve Valves Enclosure (DV)1 HV-54-lF04 1A LPCI INJ HDR Testablea (07) Pneumatic-Operated Reactor 279 Room 518 4 N N N AlCHK (05) Fluid (Air/Hyd)

Valves Valves Enclosure (DVV 8 o I PSV41 Main Steam Line (07) Pneumatic-Operated Reactor S1FV13E Safety/Relief Valve on MSL (05) Fluid (Air/Hyd)

Valves Valves Enclosure 286 Room 400 2 N N N Reactor 1 1AV212 DW Chiller Fan (08) Fans & Air Handlers (09) Fans En aosure (DVV 253 TED 5 N N N 1 TE-41-101D Suppression Pool Temp DIV (17) Temperature Sensors/Local (19) Temperature Sensors Reactor Enc 182 Room 101 4.5 N N N 1 Instruments (Not on Racks) (supp Pool)1 10E210 HPCI Turbine Barometric (20) Horizontal Tanks or Heat (21) Tanks and Heat Reactor N Condensor Exchangers Exchangers Enclosure 177 Room 109 3. N N E Main Steam Relief Valve (20) Horizontal Tanks or Heat (21) Tanks and Heat Reactor 1 1ET003 (MSRV) Accumulator Tank Exchangers Exchangers Enclosure (DVW) 286 Room 400 2 N N N (20) Horizontal Tanks or Heat (21) Tanks and Heat Reactor 1 T003 MSRV Accumulator Tank Exchangers Exchangers Enclosure (DV) 273 Room 400 2 N N N Lm,erZc Se Inern OSflun tinS I MPR-3798.

R.miWo I Cov Mesn -v N..i RS-t 24171 B-88 C Seismic Walkdown Checklists (SWCs)Below are the names and signatures of the personnel who performed the seismic walkdowns.

Thomas King Craig Swanner Mojtaba Oghbaei James Wiggin Caroline Schlaseman At. qyh~7a~-The order of the Seismic Walkdown Checklists (SWCs) for Unit 1 is shown in Table C-1 below and the order of the SWCs for Unit 0 (common) is shown in Table C-2.The "Anchorage Configuration Confirmation" column is described in Section 5.2.1 of this report. The last column in Tables C-1 and C-2 provides the corresponding Area Walk-By Checklist (AWC). (AWCs are included in Appendix D of this report.) AWC identifiers with asterisks

(*) indicate the second or subsequent SWEL item included with a specific Area Walk-By.Limerick Generating Station Unit 1 C-1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 Table C-1. Unit 1 Seismic Walkdown Checklists (SWCs)Anchorage AWC -Component ID Description Configuration UI-xx Confirmed?

1OA1 18 Switchgear, 4KV, 3PH, 3 Wire, 60Hz N 24*10B201 D114 Reactor Area Safeguard Load Center Y 2 1 0B204 Reactor Area 480V Safeguard Load Center Y 6 10B211 D1 14 Reactor Area Safeguard 480V Motor Control y 32*Center 10B213 D1 14-R-C Reactor Area Safeguard 480V Motor Y 4 Control Center 10B214 D124 Reactor Area Safeguard 480V MCC Y 5 1OB515 D114-D-G Diesel Gen. Area Safeguard 480V MCC Y 3 10C001 Division I Core Spray System Instrument Rack Y 29 10C027 Located Behind HCUs next to the Drywell Personnel y 31*Hatch 1 0C602 Reactor Recirc Panel N 35 10C603 Reactor Control Panel N 35*1 0C609 RPS Channel "A" Vertical Board N 38 1 0C626 ADS Control Room Panel N 37*10C647 Panel HPCI Vertical Board N 37 1 0D202 Reactor Enclosure 250V DC Motor Control Center Y 7 10P203 RCIC Pump Y 10 10P204 HPCI Pump Y 18*10S211 HPCI Turbine Y 18*10-S224-30-19 CRD Hydraulic Control Unit N 1 1OTB-053 Rack / Panel (Terminal Box) N 3*10X109 DIV IV 4KV Transformer N 9 1 0X204 4KV-480V Transformer Y 6*1 0X282 B Reactor Enclosure HVAC Transformer N 8 Division IV SFGD VAC Instument Panel 10Y104 10Y 104 N 24 Service Desc.1A2D101 125VDC Battery Y 27 1AC563 Diesel Generator Enclosure HVAC Control Panel N 43*1AD106 125/250V DC Current Transducer Panel N 34 1AD160 A RPS & UPS Distribution Panel Static Inverter N 28 1AE205 Residual Heat Removal Heat Exchanger Y 14*1AG501 DII Diesel Generator Y 3*1AG502 Dll EDG Excitation System Cabinet N 3*1AJ860 ESS DIV I N 12*1AP202 RHR Pump Y 14*1AP206 Core Spray Pump and Driver Y 11 1AP514 Diesel Generator Diesel Oil Pump N 12 Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 C-2 Table C-1. Unit 1 Seismic Walkdown Checklists (SWCs)Anchorage AWC -Component ID Description Configuration UI-xx Confirmed?

1AS575 Diesel Generator Exhaust Silencer Y 3*1AS921 MSRV Postion Monitor N 36 1AT564 Diesel Generator Jacket Water Expansion Tanks Y 43 1AV209 HPCI Pump & Turbine Room Cooler Y 18*1AV210 RHR Pump Room Unit Cooler Y 14*1AV512 DIESEL GENERATOR/

Room Ventiliation Fan Y 43*1 B1 K513 B Diesel Generator Starting Air Compressor B1 Y 22 1B1T558 B Diesel Generator Starting Air Reservoir B1 Y 22*1BD102 Turbine Encloser 120 V Power Distribution Panel N 25 1 BE205 RHR Heat Exhanger Y 42 1BS252-1 B PCIG/ADS Nitrogen Bottles Y 41 1 BT528 B Diesel Generator Day Tank Y 40 1CC208 Unit Cooler Control Panel Y 39 1CD105 125V DC Fuse Box N 23 1CV21 1 C Core Spray Pump Room Unit Cooler Y 21 1DC661 Panel D Safegard System Vertical Board N 37*lDD101 125V DC Battery Y 26 lDD103 125 VDC Battery Charger Y 26*1 FV21 1 B Core Spray Pump Room Unit Cooler F Y 20 FT-51-1N001 RHR HTX A & Pump A Discharge Flow Y 32 HV-011-042 HPCI PP RM CLR RET to ESW Loop B N/A 18*HV-0511- A RHR HTX RHRSW Inlet Valve N/A 16 1FO14A HV-1 1-104A RHR PP RM CLR A Supply Valve N/A 14 HV-11-132A ESW EDG JW Cooling Isolation Valve N/A 3*HV-49-1 F029 RCIC Suppression Pool Isolation Valve N/A 10*HV-52-1 F037 Core Spray Isolation Valve (MOV outboard of N/A 17 Drywell)HV-55-1F003 HPCI Steam Outboard Isolation Valve N/A 15 HV-55-1F004 CST to HPCI Pump Suction Isolation Valve N/A 18 HV-57-131 Suppression Pool Purge Inboard PCIV N/A 15" LI-52-140A Suppression Pool Level N 37*LSHL-20-122A Diesel Oil Day Tank Hi / Low Level N/A 3*LT-42-115B Reactor Level Y 31 *PDS-059-106B N2 Supply to ADS System Y 1*PDSH-20-122B D/G Oil XFER Suction N 22*PDT LPCI Line Differential Pressure Y 31 1 N060B PSL-12-102A RHR Service Water Pump Loop A to RHR HTX A Y 33 Limerick Generatlng Station unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 C-3 Table C-1. Unit 1 Seismic Walkdown Checklists (SWCs)Anchorage AWC -Component ID Description Configuration Ul-xx Confirmed?

PT-42-103B Reactor Coolant Pressure Y 31*SV-47-1 F009 CRD SCRAM Discharge Isolation Pilot Solenoid N/A 19 Valve TD-081-102A Vent Air Exhaust Fan Damper N/A 43*TI-41-101 Suppression Pool Temp DIV I N/A 30 TISH-20-121B Diesel Oil Day Tank 1CT528 High Temp Stop XFER N/A 40*Pump XR-42-1R623A Wide Range Reactor Pressure N 37*Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 C-4 Sheet 1 of 2 Status: (2 N U Seismic Walkdown Checklist (SWC)Equipment ID No. Equip. ClasS12 0A.-C.A Equipment Description SW, &I -(ezw Location:

Bldg. , FloorE1. El 2-3 Room, Area .i'.Manufacturer, Model, Etc. (optional but recommended)

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

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

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

FWOLdeAd3

-.t CeOrn eAY +o jl-, 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YOJ NE;'* NEI Yý NO UI- N/A" UrI N/Al Y$ND. U[:] N/Ar YO NEIUO]N/A))j Yg NO UO ,2 Enter the equipment class name from Appendix B: Classes of Equipment.

4 C-3 >Limerick Generating Station Unit 1 MPR-3796, Revision 1 f.nrrPnnnr1~nr.P Nn' RR-19-171 C-5 Sheet 2 of 2 Equipment ID No. 10 A I I Equip. Class'2 01 (A1 CCS A .L'4 oji.4~A , , Equipment Description i-kr P ,4& g(V, 3 4 Ao0 1.Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

YU ND UD N/ACl 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, Y 1 4 NO UD N/A["]and masonry block walls not likely to collapse onto the equipment?

1ý Le- ee-t , Y gei. 0 akd voj C.-,o-.6 P Iw.o o&Ie z-1 9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YP( N- UD N/A]YV( NEI UC Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Date: Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrPnnnrlP~nrn Nn ' RR-19-171 C-6 Equipment ID: 10A118 Limerick Generating Station Unit 1 MPR-3796, Revision 1 Cnrr.,nnndrnr-.

Nn " RR-19-171 C-7 Sheet 1 of 2 Status: 6 N U Seismic Walkdown Checklist (SWC)Equipment ID No. 10B201 Equip. Class12 (01) Motor Control Centers / Low & Medium Voltage Switchgears Equipment Description Dl 14 Reactor Area Safeguard Load Center Location:

Bldg. Reactor Floor El. 313 Room, Area Room 602W Enclosure Manufacturer, Model, Etc. (optional but recommended)

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

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

Ypý N(: 2. Is the anchorage free of bent, broken, missing or loose hardware?

Y0 NE UQ N/AE 3. Is the anchorage free of corrosion that is more than mild surface YDýNED UD N/AE1 oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YK N[ UE N/AE'5. Is the anchorage configuration consistent with plant documentation?

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

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

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

<C-3 )Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrPqnnnr1nnr.P Nn " PR-19-171 C-8 Sheet 2 of 2 Equipment ID No. 10B201 Equip. Classl2 (01) Motor Control Centers / Low & Medium Voltage Switchgears Equipment Description Dl 14 Reactor Area Safeguard Load Center Interaction Effects 7. Are soft targets free fro_, impact by nearby equipment or structures?.j~J 0~ j4 or~I YX NEI UD N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YX NDI UDI N/AD and masonry block walls not likely to collapse onto the equipment?

IvFlorme;4e 4u6 rnsý94 ccje dtfJ 4~bIp 64Y n S11~7IC~Ti~lte on) 4vp lacW .- 'place 9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YX ND UD N/A['I Y NEI UD1 Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

NI/A Evaluated by:/ -' -" I a Date: Q-'-/Qj Limerick Generating Station Unit 1 MPR-3796, Revision 1 rTnrrPmnnnrlPnr Nn -RR-19-171 C-9 Equipment ID: 10B201 Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrrmnnrnPnr.P Nn* RR-12-171 C-1 0 Equipment ID: 10B201 Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrmnnndlnrA.

Nn

RR-12-171 C-ll Equipment ID: 10B201 I Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrr-.qnnnlPdnr.P.

Nn* R.R-19-171 C-12 Equipment ID: 10B201 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrP.nnndPnrP Nn -R.-19-171 C-1 3 Sheet 1 of 2 Status:(Y N U Seismic Walkdown Checklist (SWC)Equipment ID No. I 0B204 Equip. Class12 (01) Motor Control Centers / Low & Medium Voltage Switchgears Equipment Description Reactor Area 480V Safeguard Load Center Location:

Bldg. Reactor Floor El. 283 Room, Area Room 506E Enclosure Manufacturer, Model, Etc. (optional but recommended)

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown 6f an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings.

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

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)-KAC ' O # E-o1o-0 R&evy. II 6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

YX NEI YXgf NE UE N/AO YK NE UD N/AE 4 NEI UD N/AE Y41 NEI UO N/AE-Y14NEIUO 12 Enter the equipment class name from Appendix B: Classes of Equipment.

< C-3 >Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrP.nnns1PnrP Nn -Rq-12-171 C-14 Sheet 2 of 2 Equipment ID No. 10B204 Equip. Class1 2 (01) Motor Control Centers / Low & Medium Voltage Switchgears Equipment Description Reactor Area 480V Safeguard Load Center Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

-*Ato 56' A6Vr-YX NIl UD N/AD 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, YX NO and masonry block walls not likely to collapse onto the equipment?

'EIVOMCceA~

4ures, blo LewJcv, e I0-1 UD N/AD r7O 9. Do attached lines have adequate flexibility to avoid damage?YP% ND UD N/AD 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YX ND UD-Other Adverse Conditions 1I. Have you looked for and found no other seismic conditions that could YX ND UD adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

.....weLJeA 6d T- 1z '1tv1/2 welgcl e 3L()Evaluated by I Date: 7 4 AP Limerick Generating Station Unit 1 C-15 MPR-3796, Revision 1 Cnrr.qnnndPJnr.P Nn- RR-19-171 Equipment ID: 10B204 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrfnnndPnr.P Nn RS-19-171 C-16 Equipment ID: 10B204 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrPnnndPnr,-

Nn ' RR-19-171 C-17 Equipment ID: 10B204 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrnTP.nnndPnrP.

Nn -RR-19-171 C-18 Equipment ID: 10B204 V Limerick Generating Station Unit 1 MPR-3796, Revision 1 (,nrrp._nnnifnr.p Nn ' RR-19-171 C-19 Equipment ID: 10B204 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrPnnndPnrP Nn

RR-19-171 C-20 Sheet 1 of 2 Status:( / N U Seismic Walkdown Checklist (SWC)Equipment ID No. 10B211 Equip. Classla (01) Motor Control Centers / Low & Medium Voltage Switchgears Equipment Description D114 Reactor Area Safeguard 480V IM CC-.Location:

Bldg. Reactor Floor El. 217 Room, Area Room 304W EncWlosure Manufacturer, Model, Etc. (optional but recommended)

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

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

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

4. Is the anchorage free of visible cracks in the concrete near the anchors?5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

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

YX NEI UQ= N/A=Y NFl Uf- N/A-3 Y' NEI UE] N/AO-) NOl UE- N/A'-Y~d NEI UEJ 1 2 Enter the equipment class name from Appendix B: Classes of Equipment.

<C-3>Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.orrPqnnndPnr.P Nn

R5-12-171 C-21 Sheet 2 of 2 Equipment ID No. 10B211 Equip. ClassU2 (01) Motor Control Centers / Low & Medium Voltage Switchgears Equipment Description D114 Reactor Area Safeguard 480V iMr CC Interaction Effects qt( 0 1"( 7. Are soft targets free from impact by nearby equipment or structures?

X NXU[ N/AD-No " G 8. Are overhead equipment, distribution systems, ceiling tiles and lighting, '0 N/A0 and masonry block walls not likely to collapse onto the equipment?

._ .*, bloack mllne N 5ea t a rty toa daa e?.f w Y4A ar'4 NI'N D 9. Do attached lines have adequ~ate flexibility to avoid damage? YX' NEI UD N/AO Q( 00141vtý'YKM)911 10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Other Adverse Conditions

11. Have you looked for and found no other seismic conditions that could Y)< ND U[: adversely affect the safety functions of the equipment?

Comments (Additional pages may be added as necessary)

'v/A Evaluated by 6(I 9 Date:< C-4 >Limerick Generating Station Unit 1 MPR-3796, Revision 1 ,nrrP~nnnrdPnrP" Nn -RR-19-171 C-22 Equipment ID: 10B211 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrqnnndPnrP Nn

R9-19-171 C-23 Equipment ID: 10B211 Limerick Generating Station Unit 1 C-24 MPR-3796, Revision 1 rnrrPnnnrPnrP Nn " RR-19-171 Sheet I of 2 Statuis:)

N U Seismic Walkdown Checklist (SWC)Equipment ID No. 10B213 Equip. Class 1 2 (01) Motor Control Centers / Low & Medium Voltage Switchgears Equipment Description D114-R-C Reactor Area Safeguard 480V Motor Control Center Location:

Bldg. Reactor Floor El. 283 Room, Area Room 506W Enclosure Manufacturer, Model, Etc. (optional but recommended)

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

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

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

Yt NEI U[Dl N/AEl oti cýmu0rely o.iei lo Ioot 3. Is the anchorage free of corrosion that is more than mild surface oxidation?

YVNO Ur- N/ADl 4. Is the anchorage free of visible cracks in the concrete near the anchors? YdN'- UrQ N/AD 5. Is the anchorage configuration consistent with plant documentation?(Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.), mdc- s 0 - ,soil-- C.- Rev, 10r.6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

Yt Nn UD N/AD 14 9R onU Ybf NED UE1 12 Enter the equipment class name from Appendix B: Classes of Equipment.

<C-3 >Limerick Generating Station Unit 1 MPR-3796, Revision 1 Nn

RR-12-171 C-25 Sheet 2 of 2 Equipment ID No. 10B213 Equip. Class'2 (01) Motor Control Centers / Low & Medium Voltage Switchgears Equipment Description D114-R-C Reactor Area Safeguard 480V Motor Control Center Interaction Effects 7. Are soft targets free from impact by nearby equipment or structures?

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

W-C-7o Rev, O ac 6W-C-5b v.9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?YK NEI UD N/AO YM NEI UD N/A'YK NE UE N/AO YXNO UO Other Adverse Conditions

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

Comment (A-i3tion 5al 4paere ay +or aWO 1 e asneedssary)

Comments (Additional pages may be added as necessary)

Al/A Evaluated by: (~~4~0~ji Date: ] /0 f I~a Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrP nnnrPnrNn" RR-19-171 C-26 Equipment ID: 10B213 I Limerick Generating Station Unit 1 MPR-3796, Revision 1 f.nrrPmnnndPne.P Nn. PR.-19-171 C-27 Equipment ID: 10B213 Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnrrPqnnnrlPnr.p Nn -RP.-19-171 C-28 Sheet 1 of 2 Status: ON U Seismic Walkdown Checklist (SWC)Equipment ID No. 10B214 Equip. Class12 (01) Motor Control Centers / Low & Medium Voltage Switchgears Equipment Description D124 Reactor Area Safeguard 480VMCC Location:

Bldg. Reactor Floor El. 283 Room, Area Room 306 Enclosure Manufacturer, Model, Etc. (optional but recommended)

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

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

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

YX NO UE N/A[3. Is the anchorage free of corrosion that is more than mild surface Y& NOI UE- N/A[]oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? YJX NEl UE N/AU 5. Is the anchorage configuration consistent with plant documentation?

YXNEi Ul] N/AE" (Note: This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

H R 6. Based on the above anchorage evaluations, is the anchorage free of Y) NEI UE:i potentially adverse seismic conditions?

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

<0C-3 >Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrPmnnndfnrAp N n* R.R-19-171 C-29 Sheet 2 of 2 Equipment ID No. 10B214 Equip. Class1 2 (01) Motor Control Centers / Low & Medium Voltage Switchgears Equipment Description D124 Reactor Area Safeguard 480VMCC Intera ction Effects .9 ( #w'" 7. Are soft targets free from impact by nearby equipment or structures?

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

9. Do attached lines have adequate flexibility to avoid damage?10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?Y$N U0 N/AD1 1* UE- N/A[D]g !vA YXND UE- N/AD YXND UI'Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by:.Date: Limerick Generating Station Unit 1 MPR-3796, Revision 1 rnr-mqnnndpnrn.p Nn

RR-19-171 C-30 Equipment ID: 10B214 Limerick Generating Station Unit 1 MPR-3796, Revision 1 Nn -RR-19-171 C-31 Equipment ID: 10B214 Limerick Generating Station Unit 1 MPR-3796, Revision 1 Nn -RR-1'-171 C-32 Equipment ID: 10B214 Limerick Generating Station Unit 1 MPR-3796, Revision 1 r.nrrPqnnnriPnr.P Nn " RR-19-171 C-33

@@ Line 108: / Line 108: @@
 : 1) defines the process used to develop the Seismic Walkdown Equipment List (SWEL) for Limerick Generating Station Unit 1.In accordance with Reference 1, a SWEL is comprised of two groups of items: 1. SWEL 1 is a sample of items needed to safely shut down the reactor and maintain containment integrity 2. SWEL 2 is a list of spent fuel pool related items 4.2 SWEL I -SAMPLE OF REQUIRED ITEMS FOR THE FIVE SAFETY FUNCTIONS The Limerick Unit I Seismic Individual Plant Examination for External Events (IPEEE)Success Path Component Lists (SPCL) (Reference
 : 3) is considered the "Base List" and is provided in Appendix B of this report. To ensure the SPCL Base List meets the EPRI Seismic Walkdown Guidance, the SPCL was compared with the screens described in the following sections.4.2.1 Screen #1 -Seismic Category I As described in Reference 1, only items that have a defined seismic licensing basis are to be included in SWEL 1. The seismic classification was identified for each item on the IPEEE SPCL, and items that were not Seismic Category I were removed from consideration for inclusion in SWEL 1. Seismic classification was determined through a review of current design and licensing basis documentation.
-.2.2 Screen #2 -Equipment or Systems This screen narrowed the scope of items to include only those that do not regularly undergo inspections to confirm that their configuration is consistent with the plant licensing basis. This screen removed Seismic Category I Structures, Containment Penetrations, Seismic Category I Piping Systems, cable/conduit raceways and HVAC ductwork from consideration for inclusion in SWEL 1.Limerick Generating Station Unit 1 4-1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 4.2.3 Screen #3 -Support for the 5 Safety Functions This screen narrowed the scope of items included on the SWEL 1 to only those associated with maintaining the following five safety functions:
+====4.2.2 Screen====
+#2 -Equipment or Systems This screen narrowed the scope of items to include only those that do not regularly undergo inspections to confirm that their configuration is consistent with the plant licensing basis. This screen removed Seismic Category I Structures, Containment Penetrations, Seismic Category I Piping Systems, cable/conduit raceways and HVAC ductwork from consideration for inclusion in SWEL 1.Limerick Generating Station Unit 1 4-1 MPR-3796, Revision 1 Correspondence No.: RS-12-171
+====4.2.3 Screen====
+#3 -Support for the 5 Safety Functions This screen narrowed the scope of items included on the SWEL 1 to only those associated with maintaining the following five safety functions:
 : 1. Reactor Reactivity Control 2. Reactor Coolant Pressure Control 3. Reactor Coolant Inventory Control 4. Decay Heat Removal 5. Containment Function The first four functions are associated with bringing the reactor to a safe shutdown condition.
 The fifth function is associated with maintaining containment integrity.
@@ Line 160: / Line 165: @@
 Additionally, one technical question was posed about whether a Limerick Generating Station Unit 1 8-1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 wheeled cart with lead shielding blankets would slide or tip over during a seismic event.This issue was addressed in IR 01416573 and has been closed as shown in Table 5-2.8.4 REVIEW OF LICENSING BASIS EVALUATIONS As discussed in Sections 5 and 6 of this report, the issues identified during the seismic walkdowns and area walk-bys did not threaten the ability of Seismic Category I equipment for perform its safety functions.
 The specific items that have been entered in the Limerick Corrective Action Program (CAP) were reviewed, and no concerns with the assessments or proposed resolutions were identified.
-.5 REVIEW OF SUBMITTAL REPORT The signature of the Peer Review Team Leader on the cover of this report indicates a satisfactory review and resolution of any comments and confirms that all necessary elements of the peer review were completed.
+===8.5 REVIEW===
+OF SUBMITTAL REPORT The signature of the Peer Review Team Leader on the cover of this report indicates a satisfactory review and resolution of any comments and confirms that all necessary elements of the peer review were completed.
 Limerick Generating Station Unit 1 MPR-3796, Revision 1 Correspondence No.: RS-12-171 8-2 9 References Reference drawings related to the walkdown of SWEL items are documented on the Seismic Walkdown Checklists (SWCs) in Appendix C, and if applicable, on the Area Walk-By Checklists (AWCs) in Appendix D.1. EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012.2. Limerick Generating Station Updated Final Safety Analysis Report (UFSAR), Revision 16.3. PECO Document No. N-OOE-1 17-00010, Success Path Components List (SPCL) for Limerick Generating Station Unit 1 and Common, Revision 0.4. EPRI NP-6041-SL, A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1), dated August 1991.5. L-S-52, Spent Fuel Pool Cooling and Cleanup System, Revision 4.6. Drawing M-0053, Sheet 1, P&ID Fuel Pool Cooling & Cleanup (Unit 1 & Common), Revision 48.7. Drawing M-0053, Sheet 2, P&ID Fuel Pool Cooling & Cleanup (Unit 1), Revision 48.8. Drawing M-0051, Sheet 1, P&ID Residual Heat Removal (Unit 1), Revision 65.9. Drawing M-0051, Sheet 3, P&ID Residual Heat Removal (Unit 1), Revision 67.10. Drawing No. C-0246, Sheet 1, Reactor Building Units 1 & 2 Pool Liners and Accessories Surge Tank Section & Details, Revision 13.11. Drawing No. M-01 22, Equipment Location Reactor Enclosure Unit 1 Plan At EL.352'-O", Revision 17.12. Drawing No. C-0234, Reactor Building Unit 1 Pool Liners and Accessories Spent Fuel Pool Wall Liner Elevations, Revision 22.13. PECO Energy Company, Limerick Generating Station Units 1 and 2, Individual Plant Examination for External Events, June 1995.14. NRC Letter (B. C. Buckley) to PECO (J. A. Hutton), Review of Individual Plant Examination of External Events (IPEEE) Submittal, Limerick Generating Station, Units 1 and 2, (TAC NOS. M83636 AND M83637), dated February 23, 2000.Limerick Generating Station Unit 1 9-1 MPR-3796, Revision 1 Correspondence No.: RS-12-171
 : 15. Drawing HCC-1 01-6, Isometric

ML12342A103: Difference between revisions

Revision as of 04:56, 13 October 2018

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ML12342A103: Difference between revisions

Revision as of 04:56, 13 October 2018

Text

1.1 BACKGROUND

4.2.2 Screen

4.2.3 Screen

8.5 REVIEW

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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SUMMARY

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