ML13003A025

Report No. MPR-3815, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page B-104

ML13003A025
Person / Time
Site:	Peach Bottom
Issue date:	11/16/2012
From:	Schlaseman C S MPR Associates
To:	Office of Nuclear Reactor Regulation, Exelon Generation Co
References
RS-12-173 MPR-3815, Rev 3
Download: ML13003A025 (157)

Text

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 Peach Bottom Atomic Power Station, Unit 2, Report Number: MPR-3815, Revision 3 (732 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 PEACH BOTTOM ATOMIC POWER STATION UNIT 2 1848 Lay Road, Delta, PA 17314 Facility Operating License No. DPR-44 NRC Docket No. STN 50-277 Correspondence No.: RS-12-173 N Exeton 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-3815, Revision 3 Printed Name Preparer Caroline Ppe Schieseman Reviewe. Benjamin Frazier Approver John Simons Peer Review Team Leader Patrick Buter Lead Responsible Engineer Jesse Lucas Branch Manager:.

Jeffrey For Senior Manager Design Engineering:

Michael Weldman Corporate Acceptance:

Jefry Clark Slanature'¶?4kDWBUA4L

~NS~t201 11116/2012 11116/2012 11116/2012 11/16/2012 7~5T IMPR ASSOCIATES INC, EN G I NE ER S NTTF 2.3 Seismic Walkdown of Peach Bottom Atomic Power Station Unit 2 MPR-3815 Revision 3 November 2012 QUALITY ASSURANCE DOCUMENT This document has been prepared, reviewed, and approved in accordance with the Quality Assurance requirements of 1OCFR50 Appendix B and/or ASME NQA-1, as specified in the MPR Nuclear Quality Assurance Program.Prepared by: Caroline S ScNerfan Reviewed by M. Vrazier Approved by:

w,, Joi$r W. Simons'T Peer Review Team Leader:-... ý&" 10ýL Patrick J. Butler Principal Contributors Mojtaba Oghbaei Craig B. Swanner James N. Wiggin Kevin Gantz Prepared for Exelon Generation Company, LLC A"' Exelon 320 KING STREET ALEXANDRIA, VA 22314-3230 703-519-0200 FAX: 703-519-0224 http:\\www.mpr.com RECORD OF REVISIONS Revision [ Affected Pages Description 0 1 2 3 All All All All Initial Issue Minor editorial changes were made throughout the report.The formatting and text of Tables 5-2, 5-3, 7-2, and E-2 were changed.Some photos were removed from Appendix C due to security concerns.Incorporated station's TVT comments.Modified the text in Table 7-2 for 2AC65/2BC65.

Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 Contents Tables .......................................................................................................................................

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

..... iv I Introduction

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

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 Seism ic Class I SSCs ...........................................................................

2-1 3 Personnel Qualifications

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

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

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

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

4-3 4.4 Com posite SW EL ..................................................................................................

4-4 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

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

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

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

8-1 8.4 Review of Licensing Basis Evaluations

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

8-2 8.5 Review of Subm ittal Report ...................................................................................

8-2 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 Contents (cont'd.)9 References

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

9-1 Appendices A Project Personnel Resumes and SWE Certificates

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

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

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

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

F-1 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 Hi Tables T able 3-1. P e rso nne l R o les ......................................................................................................

3-1 Table 5-1. Anchorage Configuration Confirmation

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

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

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

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

5-4 Table 7-1. PBAPS Unit 2 and Common IPEEE Seismic Vulnerabilities Resolutions

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

7-2 Table 7-2. PBAPS Unit 2 and Common IPEEE Seismic Vulnerabilities Resolved by Analysis .7-6 T able B -1. S W E L for U nit 2 ...................................................................................................

B -98 Table B-2. SWEL for Unit 0 (common) ................................................................................

B-102 Table B-3. Deferred to Electrical Bus Outage: Electrical Safety Concern .......................

B-104 Table C-1. Unit 2 Seismic Walkdown Checklists (SWCs) ........................................................

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

C-338 Table D-1. Unit 2 Area Walk-By Checklists (AWCs) ...........................................................

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

D-65 Table E-1. Summary of Inaccessible Equipment

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

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

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

E-2 Table E-3. Assessment of Unit 0 Electrical Cabinet Internal Inspections

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

E-4 Peach Bottom Atomic Power Station Unit 2 iii MPR-3815, Revision 3 Correspondence No.: RS-12-173 Executive Summary PURPOSE This report documents the seismic walkdowns performed at Peach Bottom Atomic Power Station (PBAPS) Unit 2 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 issues, whether they rise to this level or not, 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. IPEEE seismic commitments are identified, resolutions documented, and confirmatory checks made during these walkdowns are documented. (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 PBAPS Unit 2, including the items selected that are common to both Units 2 and 3, e.g., emergency cooling tower equipment, is comprised of 114 items. Of this list, 113 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. The walkdown for the remaining 1 item was deferred to a future Peach Bottom Atomic Power Station Unit 2 iv MPR-3815, Revision 3 Correspondence No.: RS-12-173 electrical bus outage. 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 51 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 2) and E-3 (for common equipment) list all electrical items that require assessment.

Accessibility of equipment, basis for accessibility determination, completion date of internal inspections, tracking number (if internal inspection has not yet been performed) and inspection results are provided in these tables.None of the issues identified during the walkdowns of PBAPS Unit 2 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 missing mounting fasteners, were identified and entered into the plant's Corrective Action Program (CAP). A total of 9 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.

All seismic vulnerabilities identified during the IPEEE (or A-46) program are summarized in Tables 7-1 and 7-2, including resolutions and confirmatory checks made during these walkdowns.

All IPEEE seismic vulnerabilities for Peach Bottom Unit 2 have been resolved.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:* One inaccessible equipment item will need to be walked down during an electrical bus outage." 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 outage.2. None of the 113 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 nine (9) 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.Peach Bottom Atomic Power Station Unit 2 v MPR-3815, Revision 3 Correspondence No.: RS-12-173 I 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 Peach Bottom Atomic Power Station Unit 2.1.2 PLANT OVERVIEW The Peach Bottom Atomic Power Station (PBAPS) consists of two boiling water reactor (BWR) generating units, located in southeastern Pennsylvania.

Both units have GE Mark I containments, are rated at 3514 MWt power, and were designed and constructed by Bechtel (PBAPS Updated Final Safety Analysis Report (UFSAR) (Reference 2), Section 1.1). PBAPS Unit 2 received its full-power license in August 1973 (Facility Operating License No. DPR-44 (Reference 9)).1.3 APPROACH The EPRI Seismic Walkdown Guidance (Reference

1) is used for the PBAPS Unit 2 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 Peach Bottom Atomic Power Station Unit 2 1-1 MPR-3815, Revision 3 Correspondence No.: RS-12-173 2 Seismic Licensing Basis 2.1 SAFE SHUTDOWN EARTHQUAKE (SSE)The PBAPS design of Seismic Class I structures are based on a dynamic analysis using the spectrum response curves developed for the site. The structures are analyzed for the maximum credible earthquake (MCE) which considers a maximum horizontal ground acceleration of 0.12g (Reference 2, Section C.2.2). The vertical ground acceleration associated with the MCE is 2/3 of the horizontal acceleration which is 0.08g (Reference 2, Section C.2.2). Critical plant structures were designed in accordance with the response spectra based on data developed from the seismology studies performed for the site. It was concluded that the solid rock foundation is subject to only minor earthquake activity and it is expected to respond well with no adverse effects (Reference 2, Section 1.6.1.1.7).

2.2 DESIGN

OF SEISMIC CLASS I SSCs Generic Letter 87-02 issued on February 19, 1987 and Supplement No. 1 issued May 22, 1992, list PBAPS Unit 2 as an USI A-46 Plant (Table A, Category 3). Seismic Class I mechanical and electrical equipment at PBAPS are qualified using rational stress analysis, empirical methods, or the Seismic Qualification User's Group (SQUG) Generic Implementation Plan (GIP) methodology (Reference 2, Section C.5.1). The use of the SQUG method is limited to the listed equipment classes and cannot be used for equipment PBAPS has specifically committed to the NRC to qualify to IEEE 344-75 (Reference 2, Section C.5.1.3).Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 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 Engineer Operations Engineer Reviewer Reviewer Reviewer (SWE) Reviewer B. Frazier X X X X C. Swanner X X X(Note 1)M. Oghbaei X X J. Wiggin X X K. Gantz X X C. Schlaseman X P. Butler X(Note 2)J. Hanley X (Exelon)Notes: 1. Peer Review Team Member for SWEL review.2. 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, Ben Frazier, 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. Frazier 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. Frazier'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." Peach Bottom Atomic Power Station Unit 2 3-1 MPR-3815, Revision 3 Correspondence No.: RS-12-173 In addition to the MPR personnel listed above, Exelon Plant Operations, J. Hanley, reviewed the SWEL. Mr. Hanley is a former licensed Senior Reactor Operator (SRO) at another station, currently holds an SRO Certification at PBAPS, and currently supports operator training.

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.Peach Bottom Atomic Power Station Unit 2 3-2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 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 PBAPS Unit 2.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 1 -SAMPLE OF REQUIRED ITEMS FOR THE FIVE SAFETY FUNCTIONS The PBAPS Safe Shutdown Equipment List (SSEL) (Reference

3) is considered the"Base List 1" and is provided in Appendix B of this report. To ensure the SSEL Base List 1 meets the EPRI Seismic Walkdown Guidance, the SSEL was compared with the screens described in the following sections.

It is noted that the PBAPS SSEL does not specifically address the containment function.

Therefore the SSEL was reviewed for components having at least one safety-related containment function.

The number of SSEL components with a containment function was considered sufficient for selecting a sample of equipment representing the containment function.4.2.1 Screen #1 -Seismic Class 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 SSEL, and items that were not Seismic Class 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

1. 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 Class I Structures, Containment Penetrations, and Seismic Class I Piping Systems from consideration for inclusion in SWEL 1. Cable/conduit raceways and HVAC ductwork are addressed in area walkbys and not as discrete components in SWEL 1.Peach Bottom Atomic Power Station Unit 2 4-1 MPR-3815, Revision 3 Correspondence No.: RS-12-173

4.2.3 Screen

1. 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.

Reference 3 (Page 5) identifies the primary and backup systems that are applicable to each of the first four safety function.

Reference 3 also identifies the support systems for those safety functions (e.g., emergency diesel generators).

Components on the SSEL that are essential to the containment function were identified as part of this project because, as noted above, the SSEL did not specifically include equipment for containment function.4.2.4 Screen #4- Sample Considerations The items selected from the Base List 1 SSEL for inclusion in SWEL 1 are shown in Tables B-1 (Unit 2) and B-2 (Unit 0, common equipment for both Units 2 and 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 Class 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 SSEL 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 (High Pressure Service Water System and Emergency Service Water System).Note, however, that the Reference 1 Appendix E table of generic BWR safety function systems includes some systems that are not applicable for PBAPS Unit 2 because the SSEL was not required to include all potential shutdown paths, and some systems do not exist at PBAPS (e.g., Isolation Condenser).

2. Major new and replacement equipment The equipment included on SWEL 1 does not include items that have been recently modified or replaced.

Due to the amount of modifications performed in the 1990's Peach Bottom Atomic Power Station Unit 2 4-2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 as part of SQUG and IPEEE programs, PBAPS Unit 2 has not made significant modifications to Seismic Class 1 equipment recently.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 equipment used in the SSEL, which are the same as the equipment classes used in Reference

1. At least one piece of equipment from each class is included on SWEL 1, except for Class 11, "Chillers;" Class 12, "Air Compressors," and Class 13,"Motor Generators." There is no Class 2 Low Voltage Switchgear (LVS) equipment in the Unit 2 SWEL, but there is one Class 2 LVS in the Unit 0 (common) SWEL.No Seismic Class I chillers, air compressors, or motor generators were included in the SSEL, 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 Screen House, Pump Structure, Diesel Generator Structure (common to both units), Emergency Cooling Tower (common to both units), Turbine Building, Reactor Building, and Drywell.5. Equipment enhanced due to vulnerabilities identified during the IPEEE program As discussed in Section 7 of this report, a significant number of IPEEE seismic-related plant improvements were implemented, or were committed to be implemented for PBAPS Unit 2. Table 7-1 shows that all committed changes were made and identifies the sample of this equipment that was included in the SWEL.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 from the internal plant PRA were used (Reference 5, Tables 2 and 4). The LOOP scenario from the internal plant PRA includes lists of the 20 pieces of equipment for Unit 2 with the highest F-V risk ranking (0.017 and above) and highest RAW risk ranking (23.6 and above). The lists of risk-significant components for the LOOP PRA (Reference 5)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, equipment access was considered when selecting the sample components.

Equipment 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.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.Peach Bottom Atomic Power Station Unit 2 4-3 MPR-3815, Revision 3 Correspondence No.: RS-12-173

4.3.1 Screen

1. 1 -Seismic Class I Only Seismic Class 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 Class I equipment for PBAPS Unit 2 (Reference 2, Appendix C and Reference 6). Therefore, no Seismic Class I items are included in SWEL 2.It is noted that the spent fuel pool cooling and clean-up system is cross-connected to the RHR system (Reference 6, E-2, 3). This is done with a spool piece and does not result in any spent fuel pool cooling and clean-up components being safety-related.

4.3.2 Screen

1. 2- Equipment or Systems This screen considers only those items from Screen #1 that are appropriate for an equipment walkdown process. Since no Seismic Class I items are included in SWEL 2, no items meet the Screen #2 requirement.

4.3.3 Screen

1. 3- Sample Considerations Sample considerations do not apply because no Seismic Class I items meet the Screen #1 requirement.

4.3.4 Screen

1. 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 PBAPS Unit 2 SFP design information, there are no connections to the fuel storage pool which could allow the fuel pool to be drained below 10 feet above the top of active fuel (Reference 2, Section 10.3.4.2 and Reference 6). The spent fuel pool cooling and clean-up return lines are the only lines that extend below this level but are equipped with siphon breaker holes to prevent inadvertent pool drainage (Reference 6, Note 3). Therefore, no items are required to be added to SWEL 2 to address rapid drain down.4.4 COMPOSITE SWEL As described in Section 4.1 above, the final Seismic Walkdown Equipment List (SWEL)for PBAPS Unit 2 is the combined SWEL 1 and SWEL 2. For PBAPS Unit 2, there are Peach Bottom Atomic Power Station Unit 2 4-4 MPR-3815, Revision 3 Correspondence No.: RS-12-173 no items in SWEL 2, so the composite SWEL is the same as SWEL 1. Appendix B.includes the composite SWEL.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 4-5 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 equipment included in the Seismic Walkdowns is shown on the PBAPS Unit 2 SWEL and Unit 0 (common equipment with Unit 3) SWEL in Appendix B.A Seismic Walkdown Checklist (SWC) from Appendix C of Reference 1 was completed for each item on the SWEL, except for the deferred item 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 all 84 items on the PBAPS Unit 2 SWEL, plus 29 of the 30 items on the Unit 0 (common) SWEL, for a total of 113 items, not including the 1 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 documentation.

The second to last column of Tables C-1 and C-2 show which items are line-mounted and therefore do not count in the anchorage confirmation total (marked "N/A"). Items evaluated for consistency with design documentation are marked "Y"; those that were not compared with design documentation 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 documents used in each confirmation.

Peach Bottom Atomic Power Station Unit 2 5-1 MPR-3815, Revision 3 Correspondence No.: RS-12-173 Table 5-1. Anchorage Configuration Confirmation Unit 2 or Unit 0 No. of SWEL N/A Items Required to Items Items Confirm?(Common)? (A) (B) (A-B)12 Confirmed 2 84 17 34 34 0 (Common) 29 4 13 17 Unit2and 113 21 47 51 Common 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.

Table 5-2. Issues Identified during Seismic Walkdowns Action Actions Component ID Description of Issue Request Complete ID YIN(Notes 1, 2)20C003, The MCR ceiling's restraint system is IR 01428651 No 20C004C, consistent with design documentation 20C005A, but the design basis Calculation G-20C006C, L12 106-1 could not be located from 3-113, L12-3-86, records management or Iron LI-8027, LR/TR- Mountain.

This issue is to 8123B, (also re-constitute design analysis to AWC-U0-7) supplement existing calculation 26-5/Z-12, specifically at MCR ceiling perimeter, during NTTF 2.1 seismic re-evaluation.

20C003 There is a missing anchor bolt at the IR 01425673 No base of the cabinet (in the first panel).Judged acceptable for seismic as-is, but inconsistent with design documentation.

2BE055, Anchorage for ECCS room coolers IR 01437853 No 2BE056, 2GE058 does not match drawings but does (Note 3)match calculation.

Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 5-2 Table 5-2. Issues Identified during Seismic Walkdowns Action Actions Component ID Description of Issue Request Complete ID YIN(Notes 1, 2)2AC065, 2BC065 Inconsistency between as-built IR 01429745 No configuration of 2AC065 and 2BC065 instrument racks and calculation PS-0930.OAG12, OBG12, Inconsistency between the OAG12, IR 01438055 No OCG12, 0DG12 OBG12, OCG12, and ODG12 anchor bolt size and vendor document E-5-155.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.3. IR 01411581 was originally identified on the SWCs as being applicable to this issue. Upon further investigation IR 01437853 was written to fully capture the issue.5.3 AREA WALK-BYS In accordance with Reference 1, Area Walk-bys were performed for each room or area within a large room 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 PBAPS Unit 2 and Unit 0 (common).

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 31 AWCs were completed for Unit 2, plus 13 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-found condition was determined to be functional.'

Table 5-3 at the end of this section provides a summary of the issues identified in the Area Walk-Bys.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 5-3 Table 5-3. Issues Identified during Area Walk-Bys Action Actions Component Description of Issue Request Complete ID/Area ID y/N(Notes 1, 2)AWC-U0-1 Open S-hook noted on light fixture above IR 01413285 Yes HV-0-48-503B.

AWC-U2-2 There is a missing anchor bolt at the base of IR 01425994 No the 20C032 cabinet. Judged acceptable for seismic as-is but missing bolt should be replaced.AWC-U2-27 Fire protection pipe support near HPCI IR 01425997 Yes pump missing one of four bolts. Judged acceptable for seismic as-is, but missing bolt should be replaced.AWC-U2-22 Seismic housekeeping, unrestrained ladder IR 01406272 Yes 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.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 5-4 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.

Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 6-1 7 IPEEE Vulnerabilities Resolution Report The Individual Plant Examination of External Events (IPEEE) report for PBAPS (Reference

7) and the NRC Safety Evaluation on the IPEEE report (Reference 8), identified a number of seismic vulnerabilities.

This occurs since the IPEEE reviews were performed in parallel with the original SQUG seismic verification of various equipment.

Each of the seismic vulnerabilities identified in Reference 7 were verified to be implemented and closed out per AR No. Al 056479 (Reference 10). Additionally many of the identified IPEEE vulnerabilities were verified to be implemented during the seismic walkdowns.

Table 7-1 below lists identified IPEEE (and A-46) vulnerabilities, indicates how eachone was resolved, and identifies the specific items that were verified in the field during the walkdowns.

Table 7-2 lists the PBAPS Unit 2 and Common IPEEE seismic vulnerabilities that were previously resolved by analysis.

There are no outstanding IPEEE vulnerabilities and all previously identified IPEEE vulnerabilities have been resolved.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 7-1 Table 7-1. PBAPS Unit 2 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from A/R Sample Component Walkdown# A1056479 Resolution 00B97 Interaction concerns.

Breaker hoist will be restrained or Work completed under work order C0188074 on None 00898 removed. August 1, 2000.00B99 20B10/11/12/13 Some cubicles missing plug welds to embedded Add missing plug welds. Work completed for plug welds under work orders None angle. Breaker hoist will be restrained or C0181066, and C0181068 on August 1, 2000, Bn removed. and under work orders C0181067 and C0181069 Breaker hoists are interaction concern, not on October 16, 2000.prevented from tipping. Modification will replace with ventilated dry Work completed for breaker hoist under work Adjacent oil filled transformers are unanchored.

type transformers that are properly order C01f82465 on August 1, 2000.anchored.

A walkdown was performed on April 24, 1997 to verify that all of the new transformers were installed for MOD 5099.00B94/95196 Unanchored switchgear and transformers.

Switchgear will be anchored.

Work completed for anchorage under work orders None C0189242 and C01 89243 on August 1, 2000, and Interaction concern with breaker hoist. Hoist will be restrained or removed. C01 89244 on October 16, 2000.Work completed for breaker hoist under work orders C0188074 on August 1, 2000.20A15/16/17/18 Door latching mechanisms are only engaged at Latches will be fastened and neoprene .Work completed under work order C0179957 on 20A15 and 20A16 included in center of door. Latching bolts at top and bottom pads may be provided, August 1, 2000 and work order C0183982 on walkdown sample.are not engaged. October 16, 2000.Spare breakers will be removed or Confirmed door latch issue 20A16,17,18 have spare breakers which are not secured. Per Item 4, p. 17 of A1056479, as of August 1, resolved.adequately secured. 2000, spare breakers removed and will not be stored in switchgear rooms per procedure SO 54.7.C. No PIMS work recorded for removal of spare breakers.20X133/150 30KVA transformer coils are missing 2 of 4 Perform evaluation of coil anchorage and ECR PB 97-02258 has been completed.

CALC N/A -no need for field holding bolts, modify it required.

PS-0947 reviewed the transformers and confirmation.

concluded that the outlier conditions are seismically acceptable (September 29, 1997).20X30/31/32/33 Oil filled transformers are unanchored.

Replace with ASS 1000KVA VPE A walkdown was performed on April 24, 1997 to 20X30, 20X032, and 20X033 ventilated dry type transformer properly verify that all of the new transformers were included in walkdown sample.anchored.

installed for MOD 5099.Confirmed issue resolved.00X103 Anchorage of transformer coils to enclosure Vendor drawings will be reviewed and ECR PB 97-02258 has been completed.

CALC None support surface indeterminate, evaluated and if necessary anchorage will PS-0947 reviewed the transformers and be reworked to comply. concluded that the outlier conditions are seismically acceptable (September 29, 1997).Peach ottom Atomic Power Station Uni 2 MPR-3815, Revsion 3 Correspondence No.: RS2-173 7-2 Table 7-1. PBAPS Unit 2 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from AIR Sample Component Walkdown# A1056479 Resolution OAX26/0BX26/OCX26 Anchorage could not be verified.

Transformer will be anchored.

Work completed under work order C0189169 on None August 1, 2000.2AP4212BP42/2CP42/2DP42 Pump casing and shaft are greater than 20 ft. Analytic evaluation proved pump casings Analysis completed as of IPEEE submittal May 2CP042 and 0BP057 included in 0AP57/0BP57 Non-tied down yard gantry crank could fall on and shafts acceptable.

1996. walkdown sample.pump house. Yard crane will be restrained when not in Work completed under A/R Al 188705 on August Confirmed issue resolved.use. 1,2000.MO-33-0498 Valve has interaction concern with radiation Support for radiation element outlet will be Work completed under work order C01l82155 on MO-0-33-0498 included in element outlet, modified.

August 1, 2000. walkdowo sample.Confirmed issue resolved.A02-03-33 Distances from pipe centerline to top of valve Review documentation and perform ECR PB 97-02258 has been completed.

CALC N/A -no need for field operator is outside of experience database.

analysis if required to demonstrate seismic PS-0947 reviewed the valve and concluded that confirmation.

capacity, the outlier condition is seismically acceptable (September 29, 1997).M02-13-4487 Valve operator weights and/or centerline Review documentation and perform ECR PB 97-02258 has been completed.

CALC None distances are outside of the experience analysis if required to demonstrate seismic PS-0947 reviewed the MOV and concluded that database, adequacy.

the outlier conditions are seismically acceptable (September 29, 1997).0AV035/36 Overhead ducts need to be reviewed as part of Evaluate overhead systems and modify as ECR 97-00992 was taken to approved (and 0AV036, 0BV035, and 0BV036 0BV035/36 the IPEEE for seismic adequacy.

required or develop suitable operator complete) status on July 24, 1997. The required included in walkdown sample.actions, physical (MOD) work in the plant was tracked by A1056479-12.

No issues identified with overhead ducting.00F043 Overhead ducts are an interaction concem. Evaluate overhead systems and modify as ECR 97-00992 was taken to approved (and None required or develop suitable operator complete) status on July 24, 1997. The required actions, physical (MOD) work in the plant was tracked by Al 056479-12.

0AV034 Attached heating piping at upper nozzles is Evaluate steam piping and modify if ECR 97-00992 was taken to approved (and None poorly supported, required.

Evaluate overhead systems and complete) status on July 24, 1997. The required modify as required or develop suitable physical (MOD) work in the plant was tracked by Overhead ducts are an interaction concern. oyerator actions. Al 056479-12.

P02-0223-1 Tubing from Delta P switches may be impacted Conduit will be supported by method which Work completed under work order C0193836 on P02-0223-3 included in P02-0223-3 by conduit. Conduit is supported by beam dues not rely on friction to transfer vertical August 1, 2000. walkdown sample.clamps, load.Confirmed issue resolved.Peach ottom Ato mi PoIr Sution Unk 2 MPR-3t15, Revision 3 Correspondence No.: RS-12-173 7-3 Table 7-1. PBAPS Unit 2 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from A/R Sample Component Walkdown I A1056479 Resolution 20D21/22/23 Depth of panels are less than that which is Top supports will be provided and existing Work completed under work order C0190182 on None included in earthquake experience database.

floor anchorage will be evaluated and December 14, 2000.modified as required.Anchor bolts have 2 1/4" eccentricity and in addition, corner plates are too flexible and do not provide an adequate load path.2ADO1/2BDO1/2CDOl/2DD01 Batteries are more than 450 lbs. (actual weight Review of existing data showed that the Work completed under work order C0193773 on 2AD01 and 2BD01 included in 700 lbs.) which is outside experience database.

batteries are qualified to IEEE-323 (1974) August 1, 2000. walkdown sample.Also, end rails are not snug with batteries.

Also and IEEE-344 (1975).overhead fluorescent lights are suspended with Confirmed issue resolved.chains having open S-hooks. A snug fit will be provided at end rails and the S-hooks will be closed.20D37 Interaction concerns.

Drip shield will be installed.

Work completed under work order C0184003 on 20D37 included in walkdown August 1, 2000. sample.These are housekeeping issues; large number of Area will be cleaned up and any material drums, eye wash on wooden table, liquid that must remain will be restrained.

As of on August 1, 2000, loose items removed. Confirmed issue resolved.processing equipment and roof pipe with victaulic No PIMS record of work.joints in the vicinity.

Also, Inverter 20037 does not have drip shield installed.

0AG1210BG12/0CG12/0DG12 Interaction concerns with overhead crane Overhead crane controller will be tied Work completed on crane controller under work 0AG012 and ODG012 included controller.

down when not in used. order C01 93768 on August 1, 2000. in walkdown sample.Local panel on vibration isolators without lateral Vibration isolators will be modified to Work completed on vibration isolators under work Confirmed issue resolved.capacity.

Vibratie disolatorg will bSE. modfieo orders Co0181161, C0161153, C0181159, and preclude dislodging in SSE. 00179951 on August 1, 2000.DPS-20224-1 Interaction with tubing to sensor on duct. Conduit will be supported by method which Work completed under work order C0193836 on None DPS-20224-3 does not rely on friction to transfer vertical August 1, 2000.load.0AG13/0BG13/OCG13/0DG13 Interaction concerns exist regarding overhead Overhead crane controller will be tied Work completed under work order C0193768 on OAC097 included in walkdown OAC097/0BC097/OCCO97 crane controller, down when not in use. August 1, 2000. sample.ODC097 Confirmed issue resolved.0OC29A/B/C/D Interaction concerns with housekeeping issues in Items will be removed or restrained.

Work completed under work order C0183590 on 00C29B included in walkdown 20C124 the Control Room. August 1, 2000. sample.Confirmed issue resolved.Peach Bottom Atomic Power Station Un 2 MPR-3815, Revislon 3 Conespondenoe No.: RS-12-In 7-4 Table 7-1. PBAPS Unit 2 and Common IPEEE Seismic Vulnerabilities Resolutions Component ID Issue Planned Resolution Resolution from AIR Sample Component Walkdown# A1056479 Resolution 20C32/33 Cabinets are not bolted to the adjacent cabinet. Adjacent cabinets will be tied together front Work completed under work order C0190182 on 20C722A included in walkdown 20C722A/B Interaction concerns exist with adjacent non- and back. December 14, 2000. sample.safety cabinets.20C818 Table will be blocked and located so Confirmed issue resolved.20C819 tipping will not cause impact.Cushioning will be provided between adjacent non-safety cabinet and impact loading will be evaluated.

20C139 Interaction concern with attached procedure Cable will be lengthened so if book falls, it Work completed under work order C0193836 on None book. will not hit panel. August 1, 2000.Pipe stanchion s Lateral load criteria not met. Install knee brace at top of stanchion at Work completed under work orders C0189101, None -issue not applicable to Rx. Bldg. 195' midspan of raceway and attach to floor or C0189160, and C0190050 on August 1, 2000. this walkdowo.RW Bldg. 165' install lateral supports.El. 165' Mech. Equipment Room Various duct and interaction issues including aux. Perform evaluation of overhead systems Work completed under work orders C0190892, None HVAC ducting steam piping, and modify as required or develop suitable C0187741, C0191039, and C0182488 on August operator actions. 2, 2000, and under work order C0195436 on December 18, 2000.f Peach Botom Amti Powe Stion UnMt 2 MPRun815, Reolsion 3 so: RS-12-173 7-5 Table 7-2. PBAPS Unit 2 and Common IPEEE Seismic Vulnerabilities Resolved by Analysis Component ID Issue Planned Resolution Actual Resolution of Condition Resolution Date 20B36 Anchorage evaluation required.

Evaluate anchorage.

Anchorage evaluation completed and anchorage 5/1997 00B53 of MCCs are adequate.00B54 00B55 0OB56 A02-01-08OA/B/C/D Distance from pipe centerline to top of valve Evaluate centerline distance of valve Calculations show valves have acceptable 2/1996 A02-01-086A/B/C/D operator is outside of experience database.

operators.

seismic capacities.

M02-10-016A/B/C/D Valve operator weights and/or centerline Evaluate weight and centerline distance of Emisting documentation review indicates valves 5/1996 M02-23-019 distances are outside of the experience database, valve operators.

are qualified to an acceptable seismic M02-23-025 acceleration.

M02-10-025N/B M02-13-027 M02-13-131 M02-30-2233A/B Cast iron yoke. Evaluate suitability of cast iron yoke. Existing documentation was reviewed and 5/1996 components were determined to be seismically adequate.SV-81301B Component could not be located, therefore the Evaluate component.

Drawing review was performed and component 5/1996 caveats and interaction effects could not be determined to be seismically adequate.verified.2AC65/2BC65 Anchorage does not screen. Evaluate anchorage.

Evaluation of anchorage was performed and 5/1997 documented in calculation number PS-0930, Rev. 0. During the field waekdowe, the as-found configuration for 2AC65 and 2BC65 was found to be inconsistent with calculation, but determined to be acceptable.

See Section 5.2.2 of this report.2AE24/2BE24/2CE24/2DE24 Heat exchanger anchorage evaluation is Evaluate anchorage.

Review of RHR Heat Exchanger modification 1/2004 unknown. calculations evaluated anchorage capacity for the RHR Heat Exchangers and found them to be seismically adequate.MPe.3815,eeoioion3 corepNdenc No., RS-1 2-173 7-6 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 31% 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 did not require any clarifications be added to the SWC and AWC forms reviewed.Peach Bottom Atomic Power Station Unit 2 8-1 MPR-3815, Revision 3 Correspondence No.: RS-12-173

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 Class I equipment to perform their safety functions.

The specific items that have been entered in the PBAPS 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.

Peach Bottom Atomic Power Station Unit 2 8-2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 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. Peach Bottom Atomic Power Station Updated Final Safety Analysis Report (UFSAR), Revision 23.3. PECO Document No. NE-1 17-51, Safe Shutdown Equipment List (SSEL) for Peach Bottom Atomic Power Station, Revision 0.4. Not used.5. Exelon Document No. PB-MISC-009, Risk Ranking to Support NTTF 2.3 Seismic Walkdowns, Revision 0.6. PBAPS Drawing No. M-363, P & I Diagram -Fuel Pool Cooling and Clean-up, Sheet 1, Revision 40.7. PECO Energy Company, Peach Bottom Atomic Power Station Units 2 and 3, Individual Plant Examination for External Events, May 1996.8. NRC Letter (B. C. Buckley) to PECO (J. A. Hutton), Review of Peach Bottom Atomic Power Station, Units 2 and 3, Individual Plant Examination of External Events Submittal (TAC NOS. M83657 AND M83658), dated November 22, 1999.9. Facility Operating License No. DPR-44, NRC Docket No. 50-277, Amendment No. 268, Dated August 8, 2007.10. PBAPS Action Request Al 056479, Last updated 12/20/2000.

Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 9-1 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.Benjamin Frazier Kevin Gantz Craig Swanner Mojtaba Oghbaei James Wiggin Caroline Schlaseman Patrick Butler A-2 A-5 A-7 A-10 A-13 A-16 A-19 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 A-1

• MPR ASSOCIATES INC.E N GINE F R S Benjamin M. Frazier EXPERIENC6E

SUMMARY

2007 -Present 2003 -2007 MPR Associates, Inc.United States Navy Since joining MPR in 2007, Mr. Frazier has been involved in a number of projects for the commercial nuclear industry.

He has considerable experience with commercial grade dedication of mechanical components, concrete, and testing services.Prior to employment at MPR, Mr. Frazier gained experience onboard a nuclear powered ballistic missile submarine.

Mr. Frazier operated the propulsion plant and was responsible for major system repairs. Mr.Frazier was a maintenance work group supervisor during two maintenance periods including an extended period in drydock. The work performed under his supervision during these periods included replacement of a primary system valve, diesel generator repairs, extensive system restart testing, and numerous plant start-ups and shut-downs as lead supervisor.

ACCOMPLISHMENTS

SUMMARY

Inspections and Testing Developed and implemented inspection and test procedures for pressure vessels, completed process systems, structural supports, reinforced concrete, and concrete anchorages.

Anchorage testing includes testing for cast in place anchors and post installation anchors.Commercial Grade Dedication Certified MPR Commercial Grade Dedication Subject Matter Expert (Mechanical)

Developed and implemented the commercial grade dedication documents for testing services, pressure vessels, pipes, unlisted components, reinforced concrete, and structural supports.Work included development of specifications, development of failure modes and effects analyses (FMEAs), critical characteristics, resolution of design and manufacturing non-conformances, and development and implementation of inspection and test plans (see below).Component Design and Analysis Performed design work for various components including pressure vessels, heat exchangers, piping systems, pipe repair assemblies, and concrete anchorages.

Work included the development of specifications, drawings, and/or calculations.

Independent Design Reviews Performed independent design reviews for various components including a diesel generator voltage regulator modification, a shaft anti-rotation device, and the first of a kind implementation of a gravity fed piping system used to remove detritus from a circulating water intake structure.

Failure Analyses Evaluated the failure of Emergency Diesel Generator (EDG) air system components and its effects on the capability of the EDG to carry design basis loads.Fatigue Analyses Performed fatigue analyses of feed pump drive train components and reactor coolant pump seal injection piping.Piping System Thermal-Hydraulic Evaluation Evaluated the Service Water System for a Nuclear Power Plant for all design basis accident conditions using a thermal-hydraulic model.Boric Acid Degradation Managed MPR project to evaluate the effects of boric acid degradation on a reinforced concrete spent fuel pool structure.

Pressure Locking/Thermal Binding Analyses Evaluated safety related flex wedge valves for the effects of pressure locking due to seat leakage and for the effects of transient induced thermal binding.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnrrPqnnndP.nrA.

Nn " RS-12-173 A-2 Benjamin M. Frazier Page 2 EDUCATION United States Naval Academy, B.S. Mechanical Engineering, 2003 (With Merit)United States Navy Nuclear Power Officer Training Program, 2004 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 Commercial Grade Dedication Subject Matter Expert (Mechanical), 2011 Level II Inspector (Mechanical), 2011 Lead Auditor, 2012 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 flnrrA~nnnrIpnr.n Nn -RPR-1 9-1 7T A-3 mPl2l IELECTRIC POWER RESEARCH INSTITUTE Certificate of Completion Benjamin Frazier Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns July 3, 2012 Date Caroline S. Schlaseman, P.E.Instructor MPR-3815, Revision 3 Correspondence No.: RS-12-173 A-4 5MPR ASSOCIATES INC.E N G I N E F R S Kevin Gantz EXPERIENCE

SUMMARY

January 2008 -Present MPR Associates, Inc.Kevin began employment at MPR in January of 2008. Since joining, he has been primarily involved in stress analysis of nuclear power plant structures and plant component evaluations to ASME Boiler & Pressure Vessel Code Requirements.

His experience includes thermal and structural finite element stress analysis.ACCOMPLISHMENTS

SUMMARY

Stress Analysis of Generation II1+ Reactor Internals Performed multiple stress analysis of three-dimensional solid models using the ANSYS finite element code to demonstrate conformance with Section III, Subsection NG of the ASME Boiler &Pressure Vessel code. This analysis involved both thermal and structural analysis, including analysis of fatigue using the ANSYS fatigue module. Hydraulic, thermal, seismic, and flow induced vibration loads were evaluated.

Development of a Flow Induced Vibration System Model for Generation II1+ Reactor Developed and refined a flow induced vibration model to support the design of the reactor internals of a Generation II1+ reactor. The model included the reactor pressure vessel, core support structures, and other reactor vessel internals components.

The model included representations of the hydrodynamic mass in the reactor and accounted for fluid-structure interaction effects.Pressure Vessel ASME Code Analyses for Replacement Components Performed several stress analyses using hand calculation methods and the ANSYS finite element code to demonstrate conformance with ASME Boiler& Pressure Vessel Code Section III and Section VIII acceptance criteria.

Examples of vessels analyzed include heat exchangers, filter housings, and pump blocks.Building Design Basis Calculation Review to Address Potential Decreased Strength from Alkali-Silica Reaction in Concrete Reviewed existing design basis calculations for several buildings at a nuclear power plant to quantify the existing margin to accommodate a potential decrease in concrete strength from Alkali-Silica Reaction.

In cases where documented margin was not sufficient, evaluations were performed to remove unnecessary conservatism from the evaluations and increase margin.Replacement EDG Seismic Analysis Used the ANSYS finite element code to analyze a solid model of a replacement Emergency Diesel Generator for seismic loads. Component attachments were also evaluated for seismic loads using hand calculations.

Crystal River 3 Repaired Containment Design Basis Analysis Used the ANSYS finite element code to evaluate the CR3 post-tensioned containment to plant design basis acceptance criteria after a planned repair. The repair was performed to restore a temporary steam generator installation opening and to repair a delaminated region of concrete.

The analysis involved evaluating repair alternatives, detensioning and retensioning schemes, containment stress under design basis loading conditions and accounted for effects such as thermal gradients, creep, shrinkage, and tendon prestress losses.EDUCATION Virginia Tech, M.S. Mechanical Engineering, 2005-2007 Virginia Tech, B.S. Mechanical Engineering, 2002-2006 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 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rTnrrPqnnnrlPnrnP Nn

• RR-1-173 A-5 I= I 1ELECTRIC POWER Eprail RESEARCH INSTITUTE Certificate of Completion Kevin Gantz Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns July 3, 2012 Date Caroline S. Schlaseman, P.E.Instructor MPR-3815, Revision 3 Correspondence No.: RS-12-173 A-6

• MPR ASSOCIATES INC.F N GIN F F RS 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 0CFR50 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)Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnr"Pqnnndenr.P Nn

• RR-19-171 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-7 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 (Summa Cum Laude)Minors in Physics and Mathematics 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.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 A-8 Crnrrpqnnnr1Pnr'P Nn RR-1A2-171 IIPIELECTRIC POWER RESEARCH INSTITUTE Certificate of Completion Craig Swanner Training on Near Term Task Force Recommendation 2.3 -Plant Seismic Walkdowns July 3, 2012 Date Caroline S. Schlaseman, P.E.Instructor I - 1 -, -... I MPR-3815, Revision 3 Correspondence No.: RS-12-173 A-9

• MPR ASSOCIATES INC.EN GIN F F RS 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.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnrrP.nnnrIn-nP.

Nn

• RR-17-17.A-10 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.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnrrqnnndPnrP.

Nn

• R.-19-171 A-11 I ,cELECTRIC POWER raei 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 MPR-3815, Revision 3 Correspondence No.: RS-12-173 A-1 2

• MPR ASSOCIATES INC.E N GIN EFR 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 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 f.nrrP.qnnnds-.nrP Nn* RR29--173 A-1 3 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.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 r.nrrqnnndPnr.n Nn

• R.-1 9-17.A-14 ELECTRIC POWER azeI~U 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

-, -u- -,-MPR-3815, Revision 3 Correspondence No.: RS-12-173 A-15 UMPR 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 OCFR71 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.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 r.nrrqnnndnP.r.P Nn* RR-19-17.A-16 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, tomado 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.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 A-17 rnrrPqnnnt1dnnr Nn -R.A-1-171 ELECTRIC POWER RESEARCH HiSTITUTE 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 MPR-3815, Revision 3 Correspondence No.: RS-12-173 A-18 WMPR ASSOCIATES INC.ENGINEERS 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 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 flnrrPqnnndPnrP.

Nn "R-1 9-173 A-19 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.

Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 A-20 rnrrPqnrnriPnr.P Nn ' RR- 9-17.1 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 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 A-21 Nn ' R,-1 -17.3 B Equipment Lists The following documents are included in this appendix:* Base List (95 pages)" SWEL Signature Page* Table B-i: SWEL for Unit 2* Table B-2: SWEL for Unit 0 (common)Note that there are no items in the SWEL 2 for PBAPS Unit 2.* Table B-3: Deferred to Electrical Bus Outage: Electrical Safety Concern Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 B-1 DATE: 3128=95 DOCUMENT NO. 0067.00084-D00t PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 1 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG CI Equip ID Sysuem Equip Descripbon Drawkv No. Loc Cods Norm date Moo" power Support System Unit Eval reqm? PIUS Io Notes ROB Mow Camp Room Elv Desh Ste Conlr power Supp Sys dwg Line No Functon Bujilfn 3 0 16A-23205A SRV ADS BACKUP N2 SUPPLY CHK W TO M-351. SHT I 0AN2-27 OPERABLE NIA 2 WIA RV-2-2-071A 154 2102 PASSIVE CHK-2-ISA-23205A Drywall .U2 OPERABLE NWA 3 0 16A,232055 SRV ADS BACKUP N2 SUPPLY CHK W TO M-351. SHT I DiW2-29 OPERABLE NWA 2 N/A RV-2-2071B 164 2107 PASSIVE CHK.2-1IA.232058 Drywa -U2 OPERABLE NIA 3 0 16A-23205C SRV ADS BACKUP N2 SUPPLY CHK W TO "-351, SHT I O/2-27 OPERABLE N/A 2 NIA RV-2-2-071C 154 2112 PASSIVE CHK-2-15A-23206C Dqye .U2 OPERABLE N/A 3 0 1SA.23205G SRV ADS BACKUP N2 SUPPLY CHK W TO M-351, SHT 2 D/W2-35 OPERABLE NWA 2 NWA RV-2-2-071G 154 2123 PASSIVE CHK.2-16A-23205G Drywal -U2 OPERABLE NWA 3 0 1&6,23205K SRV ADS BACIKP N2 SUPPLY CHK W TO M-351. SHT 2 DNW2-34 OPERABLE WA 2 N/A RV-2-2-O71K 164 2132 PASSIVE CHK-2-16A-23205K Drywe -U2 OPERABLE N/A 1 0 2-06-09M8 RCIC FEEDWATER CHECK VALVE LOOP 8 M-351. SHT 2 R2-30 OPEN NIA 2 NIA OUTER 135 3134 PASSIVE CHK-2.4-968 Reactor Bldg -U2 CLOSED NIA 1 0 2-10.177 RHR-8 HIGH PRESSURE SERVICE WATER TO M-315. SHT I R2-6 CLOSED NZA 2 NfA RHR CROSSTIE CHECK VALVE 091 4208 PASSIVE CHK-2-Io-177 Reas" Bldg -U2 CLOSED N/A 2 0 2-1O-184A RHR-A RHR PRESSURING LINE INNER CHECK M-36i. SHT 1 R2-24 CLOSED N/A 2 NIA VALVE TO RHR LOOP A 135 4116 PASSIVE CHK-2-10-164A Reactor BId.1 2 CLOSED NIA 1 0 2-10-1848 RHR-8 RHR PRESSURING UNE INNER CHECK "I351. SHT 2 R2.26 CLOSED N/A 2 N/A VALVE TO RHR LOOP 8 135 4215 PASSIVE CHK-2-10-1848 Reactor Bldg -U2 CLOSED N/A 0 2-ID.48A RHR-C RHR PUMP 2AP035 DISCHARGE CHECK M-361. SHT I R2-S CLOSED NIA 2 NIA VALVE 091 4306 PASSIVE CKK-2-1048A 3 Reaclor 8ldg -U2 OPERABLE NIA 1 0 2-10-488 RHR-D RHR PUMP 20P035 DISCHARGE CHECK M-31, SGiT 2 R2-6 CLOSED N/A 2 N/A VALVE 091 4407 PASSIVE CHK-2-10.488 3 Reacor Bldg -U2 OPERABLE NIA 2 0 2-10.48C RHR.A RHR PUMP 2CP035 DISCHARGE CHECK "-3I. SHT 1 R2-7 CLOSED NWA t 2 NIA VALVE 091 4110 PASSIVE CHK-2-10448C Reac Bldg -U2 OPERABLE N/A 1 0 2-10.480 RHR.8 RHR PUMP 2DP035 DISCHARGE CHECK M-361, SHT 2 R2-0 CLOSED N/A 2 WA VALVE 091 4210 PASSIVE CHK-2.10-48D Reactor BMg -U2 OPERABLE WA Peach Bottom Atomic Power Station Unit 2 B-2 MPR-3815, Revision 3 C'nrr..nnndf.nrn.

Kin. Rq-12-173 DOCUMENT NO. 006740054001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3aM PAGE 2 Norm sate Moive Pow Supper System Desired State CorW IXover Supp Sys owg TRAIN SQUG CI Equip ID Eval retd? Plus 10 system Nues Equip Descripon ROB Morner Camp Drawing No.Loc Code Room Elev Line No Funcion Building 3 0 2-16-257A SRV INSTR N2 CHECK VALVE TO RV-2-2-071A M-351, SHT 1 DAI2-27 OPERABLE NIA 2 WA 164 2103 PASSIVE CHK-2-16-257A Dywell -U2 CLOSED NIA 3 0 2-16-2578 SRV INSTR N2 CHECK VALVE TO RV-2-2-071B M-351, SHT 1 011N2-29 OPERABLE WA 2 NIA 154 2108 PASSIVE CHK-2-16-257B Drywae -U2 CLOSED NWA 3 0 2-16-257C SRV INSTR N2 CHECK VALVE TO RV.2-2-071C 1-351, SHT 1 ONO2-26 OPERABLE NWA 2 NWA 154 2113 PASSIVE CHK-2-16-257C -U2 CLOSED NWA 3 0 2-16-257G SRV INSTR N2 CHECK VALVE TO RV-2-2-071G M-351. SHIT 2 DNV2-35 OPERABLE NWA 2 NA 154 2124 PASSIVE CHK-2-16-257G Dryweall -U2 OPERABLE NIA 3 0 2-16-257K SRV INSTR N2 CHECK VALVE TO RV-2-2-071K M-351, SHT 2 D/W2-34 OPERABLE N/A 2 WA 154 2133 OPERABLE CHK-2-16-257K Drywall -U2 OPERABLE N/A 2 0 2-32-502A HPSW HPSW 2AP042 DISCHARGE CHECK W-315. SHT 1 P1t4i OPERABLE NWA 2 WZA VALVE 111 5518 PASSIVE CHK-2-32-502A Pump House OPERABLE NWA 1 0 2-32-402 HPSW HPSW 2BPO42 DISCHARGE CHECK M-315. SHIT 1 PIHM OPERABLE NWA 2 WIA VALVE 111 5620 PASSIVE CHK.2-32-502B Pump House OPERABLE NWA 2 0 2-32-502C HPSW HPSW 2CP042 DISCHARGE CHECK M-315. SHT 1 P/H.6 OPERABLE NIA 2 NWA VALVE 111 5522 PASSIVE CHK-2-32-502C Pump House OPERABLE WA 1 0 2-32-502D HPSW HPSW 2DPO42 DISCHARGE CHECK M-315, SlHT P/H-6 OPERABLE WA 2 WIA VALVE 111 5524 PASSIVE CHK-2-32-5020 Pump House OPERABLE WA 3 0 2-33-514 ESW SERVICE WATER TO ESW CROSS TIE Li-315, SlHT T2-45 WIA N/A 2 NIA CHECK VALVE 116 5563 PASSIVE CHK-2.33-514 Tubine Bldg -U2 CLOSED WA 3 0 2-3A-13 CR0 HYDRAULIC CONTROL UNITS, TYPICAL M-357. SHlT I R2-24 OPERABLE NWA 2 S OF 185 135 1100 ACTIVE U2 HCU 02-19 1 Reador Bldg -U2 OPERABLE WA 1 0 2-6-96A HPCI FEEOWATER CHECK VALVE LOOP A M-351. SHT I R2.30 OPEN WA 2 N/A OUTER 13S 3233 PASSIVE CHK-2-06-96A Reactor Bldg -U2 CLOSED WA 2 0 2AS769 RHR.2A RHR PP 2AP035 SUCTION STRAINER M-361, SHT I Torus OPERABLE WA 2 S 4100 PASSIVE 1II Torus Proper -U2 OPERABLE WA 2AS769 U-361, M-4578, Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnrrP.mnnndPnnr--

Nn

• RR-12-173 B-3 DATE: 3/28/96 DOCUMENT NO. 0067.00084-0001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 3 REVISION 2 SAFE SHUTDOWN EOUIPMENT UST TRA SOUG Cl Equp ID System Equi Descrition Orawing No. Loc Code Norn state Motive power Support System Uni Eval re~d? PIMS ID Notes ROB Mother Camp Roon Elev Desed SIe Cor power Supp Sys dw9 Line No Fwucion B.Ali 1 0 28S769 RHR-2B RHR PP 2BP035 SUCTION STRAINER M-351, SHT 2 Torus OPERABLE NIA 2 S tll 4200 PASSIVE 28S769 Torus Proper -U2 OPERABLE N/A M-31. M4578.2 0 2CS769 RHR-2C RHR PP 2CP035 SUCTION STRAINER M-361. SHT I Torus OPERABLE N/A 2 S 111 4300 PASSIVE 2CS769 3 Twig Proper -U2 OPERABLE N/A M-381, M-4578.1 0 2OS769 RHR-2D RHR PP 20P035 SUCTION STRAINER M-361, SHIT 2 Torus OPERABLE N/A 2 S 111 4400 PASSIVE 2DS769 3 Torus Proper -U2 OPERABLE N/A M-361, M-4578, 2 0 A02-10-46A RHR-A RHR LOOP A CHECK VALVE M-381, SHT 1 D/W2-21 CLOSED N/A 2 S 134 4118L2211 PASSIVE AO-2-10-046A DryweU -U2 OPERABLE N/A M-1-H-21-7 1 0 A02-10-46B RPHR4 RHR LOOP B CHECK VALVE M-361. SHT 2 DNV2-16 CLOSED WA 2 S 134 4217 PASSIVE AO-2-10-046B Orywell .U2 OPERABLE N/A M-1-H-21-7 3 0 A02-14-013A CS CORE SPRAY LOOP A CHECK VALVE M-362 SHIT I ODV2-21 CLOSED NIR 2 N/A 134 2214 PASSIVE AO-2-14-013A Drywal -U2 CLOSED NwR 3 0 A02-14-013B CS CORE SPRAY LOOP B CHECK VALVE M-362. SHT 1 DMW2-16 CLOSED NIR 2 NZA 134 2215 PASSIVE AO-2-14-013B Drywell -U2 CLOSED N/R 1 0 A02-23-018 HPCI HPCI DISCHARGE CHECK VALVE M-365. SHlT 1 R2-30 OPERABLE N/A 2 S 135 3232 PASSIVE AO-2-23-018 Reactor Bldg -U2 OPERABLE N/A Vendor 16097)02 3 0 M02-10-020 RHR-A RHR LOOPS A/B X-TIE M-361, SHT I R2-93 CLOSED N/A 2 N/A 116 4108.4207 PASSIVE MO-2-10.20 11 Reactor Bdg -U2 CLOSED N/A 2 0 M02-io-033 RHR-A HEAD SPRAY OUTBOARD ISOLATION M-36t, SHIT 1 R2-33 CLOSED N/R 2 N/A VALVE 165 4111 PASSIVE MO-2-104)33 11 Reactor Sldg -U2 CLOSED NMR 3 0 M02-48-2213 ESW UNIT 2 ESW PUMP SLUICE GATE M-330 S/14-4 OPEN N/R 2 R 116 5631 PASSIVE MO-2-33-2213 Screen House OPEN NIR 3 0 PCV-8917A BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M-333. SHT I R2-22 OPERABLE N/A 2 S BACKUP SUPPLY TO ADS 6105 ACTIVE PCV-2-16A-8917A Reactor Bldg -U2 OPERABLE N/A 3 0 PCV-8917B BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M-333, SHIT I R2-22 OPERABLE N/A 2 S BACKUP SUPPLY TOADS 135 6106 ACTIVE PCV-2-16A-89178 Reactor Bldg -U2 OPERABLE N/A Peach Bottom Atomic Power Station Unit 2 B-MPR-3815, Revision 3 (onrrP.mnnndi.nrP.-

Nn " RS-12-1773 DOCUMENT NO. 006740084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST I Norn state Mott" power Suppot System DesOe State Car, power S4PP Sys dy9 DATE: 3128L96 PAGE 4 TRAIN Ur*SQUG CI Equs tD Eval req'd? PIMS ID System Notes EqRBP D*5oiptio ROB Moliw Camp DrewkV No.Loc Code Room Etev Lie No Fwuction 3 0 PCV-8917C BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M-333. SHT I R2-22 OPERABLE N/A 2 S BACKUP SUPPLY TO ADS 135 6107 ACTIVE PCV-2-16A-8917C ReaO" Bldg -U2 OPERABLE NIA 1 0 PS02-23-006 HPCI HPCI TURBINE EXHAUST RUPTURE DISC M.3686, SHT I R2-13 OPERABLE WA 2 NIA 088 3206 PASSIVE PSD-2-23.006 Reactor Bfdg -U2 OPERABLE WA 1 0 SUCTION HPCI HPCI SUCTION STRAINER M-365. SHT I Tons OPERABLE NWA 2 a STRAINER-2HPCI 111 3220 PASSIVE Reactor Bldg -12 OPERABLE WA 3 0 VRV2-2-8096A SRV VACUUM RELIEF VALVE FOR MAIN M-351, SHT I DAW2-26 OPERABLE WA I 2 S STEAM LINE RELIEF WA 158 2104 ACTIVE VRV-2-02-8096A Dwall -U2 OPERABLE NWA M120-75-1 3 0 VRV2-2-60968 SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHlT I D/W2-29 OPERABLE NWA 2 S STEAM LINE RELIEF W B 158 2109 ACTIVE VRV-2-0240968 DrOy9w -12 OPERABLE NWA M120-75-1 3 0 VRV2-2-8096C SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT I DW2-26 OPERABLE NWA 2 S STEAM LINE RELIEF WC 158 2114 ACTIVE VRV-2-024-096C Drywea -U2 OPERABLE NWA M120-75-1 3 0 VRV2-2-8096D SRV VACUUM RELIEF VALVE FOR MAIN M-351, SHlT 1 DAN2-27 OPERABLE NWA 2 S STEAM UNE RELIEF W 0 158 2116 ACTIVE VRV-2-02-80960 Drywal -U2 OPERABLE WA M120-75-1 3 0 VRV2.2-096E SRV VACUUM RELIEF VALVE FOR MAIN M-351, SHT I DW2-29 OPERABLE WA 2 S STEAM UNE RELIEF WE 158 2118 ACTIVE VRV-2-02-8096E Dywa'l -U2 OPERABLE NWA M120-75-1 3 0 VRV2-2-8096F SRV VACUUM RELIEF VALVE FOR MAIN "I.51 SHIT 1 DN2-29 OPERABLE NWA 2 S STEAM LINE RELIEF W F Ise 2120 ACTIVE VRV-2-024.096F Dywell -U2 OPERABLE NWA M120-75-1 3 0 VRV2.241096G SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 2 DN2-35 OPERABLE N/A 2 S STEAM LINE RELIEF W G 158 2126 ACTIVE VRV-2.02-86G "we" -U2 OPERABLE NWA M120-75-1 3 0 VRV2-2-809&H SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 2 D0Y2-34 OPERABLE N/A 2 S STEAM UNE RELIEFWH 158 2127 ACTIVE VRV-2-02096H Oywell -U2 OPERABLE WIA*M120-75-1 3 0 VRV22.28096J SRV VACUUM RELIEF VALVE FOR MAIN M4-351, SHlT 2 DmW2-32 OEAL /2 5 STEAM LINE RELIEF W J 1sa 2129 ACTIVE VRV-.2-O-096J Dywell -112 OPERABLE W/A M120-75-1 3 0 VRV2-2809K SRV VACUUM RELIEF VALVE FOR MAIN 1451. SHT 2 DmN2-34 OPERABLE NWA 2 S STEAM LINE RELIEF W K 158 Drywell -U2 OPERABLE NIA 2134 ACTIVE VRV-2-02-.806K M120-75-1 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnrr..nnndvlnrv.

Nn

• RR-19-173 B-5 DOCUMENT NO. 00674)008440001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3a25196 PAGE 6 Norm state Molwve power Support System Desied State Conyr power Supp Sys dwg TRAIN Und SOUG Ci Equip 10 Eval reAd? PIMS ID system Notes Equip Descrption ROB Molhe Camp Drawing No.Loc Code Room Elev Lue No Function Buddig 3 0 VRV2.2-8096L SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 2 DNW2-32 OPERABLE NIA 2 s STEAM LNE RELIEF W L a 2136 ACTIVE VRV.2-0248096 Oywal -U2 OPERABLE MIA M120-75-1 1 0 VRV2-23C-140A HPCI HPCI TURBINE EXHAUST TO, TORUS M-365. SHT I R2-92 OPERABLE NIA 2 NIA VACUUM RELIEF VALVE 116 3215 PASSIVE VRV-2-23C-140A Reactor Bdg -2 OPERABLE NIA 1 0 VRV2-23C-1400 HPCI HPCI TURBINE EXHAUST TO, TORUS M-365, SHT 1 R2-92 OPERABLE MIA 2 WA VACUUM REUEF VALVE 116 3216 PASSIVE VRV-2-23C-1408 Reactor BldgU ,2 OPERABLE MIA 1 0 VRV2-23C-140C HPCI HPCI TURBINE EXHAUST TO. TORUS M4365. SHT I R2-92 OPERABLE NWA 2 WA VACUUM RELIEF VALVE 116 3217 PASSIVE VRV-2-23C-140C Reactor Bldg -U2 OPERABLE N/A 1 0 VRV2-23C-1400 HPCI HPCI TURBINE EXHAUST TO, TORUS M-365, SHT 1 R2-92 OPERABLE NIA 2 NIA VACUUM RELIEF VALVE 116 3218 PASSIVE VRV-2-23C-1400 Reactor Sdg -U2 OPERABLE NIA 1 0 VRV2-23C-4998A HPCI HPCI TURBINE EXHAUST VACUUM. M-366. SHT I R2-13 CLOSED NIA 2 NWA RELIEF VALVE 088 3207 PASSIVE VRV-2-23C-499A Reactor Bldg -U2 CLOSED NIA 1 0 VRV2-23C-49988 HPCI HPCI TURBINE EXHAUST VACUUM M-366, SHT I R2-13 CLOSED NIA 2 NWA RELIEF VALVE 081 3208 PASSIVE VRV-2-23C-49988 Reactor B6dg -U2 CLOSED WA 3 1 20836 EPS-2A 480 V REACTOR AREA EL. 165' MCC E-1615 R2.41 ENERGIZED 2081013 2 S 20836 (E124-"-C) 165 8000 ACTIVE E124-R-C (20836) Reactor Bldg -U2 ENERGIZED 3 1 20837 EPS-28 480V REACTOR AREA EL. 165' MCC E-1615 R2.23 ENERGIZED 2081113 2 S 20837 (24t.RB) 135 8000 ACTIVE E224-R-9 (20837) Reactor Bldg -U2 ENERGIZED 3 1 20338 EPS-2C 480V RADWASTE AREAEL 135' MCC E-1617 R2-29 ENERGIZED 2091213 2 S 20838 (E324-R-8) 135 8000 ACTIVE E324.R-8 (20938) Reactor t -L2 ENERGIZED 3 1 20839 EPS-2D 480V RADWASTE AREAEL 116' MCC E-1617 T2-44 ENERGIZED 20B1313 2 S 20839 (E424-WA) 116 8000 ACTIVE E424-W-A (20839) Turbne f -U2 ENERGIZED 3 1 20859 EPS-2A 480V TURBINE AREA EL 135' MCC E-1615 T2.71 ENERGIZED 2081014 2 S 20859 (E124-T-8) 135 8000 ACTIVE E124-T-B (20959) TurbMe Bldg -U2 ENERGIZED 3 1 20860 EPS-2B 480 V TURBINE AREA EL 135' MCC E-1615 T2-71 ENERGIZED 2081114 S ACTIVE 20860 (E224-T.8) 135 Turbine Bldg -U2 ENERGIZED E224-T-8 (20B60)Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 C'nrrt-qnnnrdP.nr.c Nn -R5-19-17.3 B-6 DATE: 312M88 PAGE 6 DOCUMENT NO. 0061400"84-1O0 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST REVISiON 2 TRAIN Uni SOUG CI EQ* tD, Evel rectd Pima45to Function System Notes Equip Descrition ROB Motrier Comp, orawing No.Loc Code Room Elev Bulng Norm state Desired State Motive pow"r Support System Stpp Sys d" 3 1 2001)1 EPS-28 (200011) RX BUILDING DC MOTOR E-26. SHT 1 R2-26 ENERGIZED 28DI8 20018 2 S CONTROL CENTER 135 E 8213 ACTIVE 208-R-B Reactor Sldg -U2 ENERGIZED 3 2 20810 EPS-2A 480 V 8US E 124 E-1615 R2-41 ENERGIZED 2OX30 2081012 2 S 165RZ 8000 ACTIVE 208010 Reactor Sldg -U2 ENERGIZED 3 2 2081012 EPS-2A BREAKER TO E124 480V BUS (LC20B1O)

E-1815 R2.41 CLOSED 20BI0 2 SR 165 ecco PASSIVE E-73 (1012) 20810 Reactor Bldg -U2 CLOSED 3 2 2051013 EPS-2A BREAKER TO 480 V MCC 20836(E124-R-C)

E-1615 R2-41 CLOSED 20810 2 BR 165 8000 PASSIVE E124(1013) 20810 Reactor BUg -12 CLOSED 3 2 2081014 EPS-2A BREAKER TO 480 V MCC 2085 E-1615 R2.41 CLOSED 20810 2 BR (E124-T-8) 165 8000 PASSIVE E124(1014) 20810 React" Bdg -U2 CLOSED 3 2 2081021 EPS-2A BREAKER TO MCC 00B53 E-1615 R2-41 CLOSED 20810 2 SR 165 8000 PASSIVE E-67 (1021) 20810 Reactor Blg -U2 CLOSED 3 2 2081022 EPS-2A BREAKER TO MCC 00862 E-1615 R2-41 CLOSED 20810 2 BR 165 8000 PASSIVE E-124 (1022) 20810 Reactor BUg -U2 CLOSED 3 2 20811 EPS-28 480 V BUS E224 E-1615 R2-116 ENERGIZED 20X31 2081112 2 S 165.8o0m ACTIVE 20B011 Reactor Bldg U2 ENERGIZED 3 2 2081112 EPS-28 BREAKER TO E224 480 V BUS (LC20811)

E-1615 R2-116 CLOSED 20811 2 BR 165 8000 PASSIVE E-124(1022) 20811 Reactor fg -tU2 CLOSED 3 2 2081113 EPS-28 BREAKER TO 480 V MCC 20837 E-1615 R2-116 CLOSED 20811 2 BR (E224-R-8) 165 8000 PASSIVE E224(1113) 20811 Reactor Blg -U2 CLOSED 3 2 2081114 EPS-28 BREAKER TO 480 V MCC 20B60 E-1615 R2-116 CLOSED 20811 2 OR (E224-T-B) 165 8000 PASSIVE E224(1114) 20811 Reactor ldg -U2 CLOSED 3 2 2081122 EPS-28 BREAKER TO MCC 00B61 E-1615 R2-116 CLOSED 20811 2 BR 165 8000 PASSIVE E-224 (1122) 20811 Reactor BSlg -U2 CLOSED 3 2 S ACTIVE 20812 EPS-2C 480 V BUS E324 E-1617 R2-41 ENERGIZED 20X32 165 Reactor Bldg -U2 ENERGIZED 2081212 E-324(20812)

Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 onrrp.nnndn.nr.p Nn

• RS-12-173 B-7 DOCUMENT NO. 0067-000840001 REVISION 2 PEACH BOTrOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm stale Motive power Deied State Conw, power DATE: 3128196 PAGE 7 TRAIN Unit SOUG CI Equip ID Eval reqd? PIMS 10 system Notes Equdp Deaaipti-ROB Mother Comp .Drewbig No.Loc Code Room Elev Sumort System SUPP Sys deg Line No Funwdon 3 2 2081212 EPS-2C BREAKER TO E324 480 V BUS (LC20B12)

E-1617 R2-41 CLOSED 20812 2 BR 165 8000 PASSIVE E-324 (1212) 20812 Reactor SOg -U2 CLOSED 3 2 2081213 EPS-2C BREAKER TO 411V MCC 20838 E-1617 R2-41 CLOSED 20812 2 BR (E324-R-8) 165 8000 PASSIVE E324(1213) 20812 Reactor Bldg- U2 CLOSED 3 2 2081221 EPS-2C BREAKER TO MCC 00D55 E-1617 R2-41 CLOSED 20812 2 BR 166 8000 PASSIVE E-324 (1221) 20812 Reactor Bldg -U2 CLOSED 3 2 2081222 EPS-2C BREAKER TO MCC 00849 E-1617 R241 CLOSED 20812 2 8R 165 8000 PASSIVE E-324 (1222) 20812 Reactor CLOSED 3 2 20B13 EPS-2D 480 V BUS E424 E-1617 R2-116 ENERGIZED 20X33 2OB1312 2 S 165 8000 ACTIVE E-424(20813)

Reactor Bldg -U2 ENERGIZED 3 2 2081312 EPS-2D BREAKER TO E424 480 V BUS (LC20BI 3) E-1617 R2-116 CLOSED 20813 2 BR 165 8000 PASSIVE E.424 (1312) 20813 Reactor Bidg. U2 CLOSED -3 2 2081313 EPS-2D BREAKER TO 480 V MCC 2039 E-1617 R2-116 CLOSED 2081313 2 BR (E424-W-A) 165 8000 PASSIVE E424(1313) 20813 Reactor Sidg -U2 CLOSED -3 2 2081322 EPS-2D BREAKER TO MCC 00BS0 E-1617 R2-16 CLOSED 20813 2 BR 165 8amo PASSIVE E-424 (1322) 20813 Resctor Bdg -U2 CLOSED 3 3 20AIS EPS-2A (20A015) EMERG AUX SWITCHGEAR E.8 T2-171 ENERGIZED 20A1503 20A1503 2 S 135 8100 ACTIVE 20A015 Turbine Bldg -U2 ENERGIZED 3 3 20A1501 EPS-2A E312 BKR FROM XFMR 0X04 E-8 T2-171 OPEN 20A15 2 BR 135 8101 PASSIVE 20A1501 20A15 Twbine ldg -U2 OPEN 20021 3 3 20A1503 EPS-2A E12 BKR FROM El DIG OAG12 E-8 12-171 OPEN OAGIS 2 BR 135 8102 ACTIVE 20A1503 20A15 Twtbw Blg -U2 CLOSED 20021 3 3 20A1505 EPS-2A E124 BKR TO XFMR 20X30 E.8 12-171 CLOSED 20A15 2 BR 135 8103 ACTIVE 20A1505 20A15 Twbbine Bldg U2 OPERABLE 20021 3 3 20A1506 EPS-2A BREAKER TO A RHR PUMP 2AP35 E-8 12-171 OPEN 20AI5 2 BR 8104 ACTIVE 135 Turbine g .U2 OPENICLOSED 20021 20A1506 20A15 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (,nrrp.,nnndepnA.

Nn -RS-19-17.3 B-8 DOCUMENT NO. 0067-00084-001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Motiv po~we Conlr power DATE: 3128186 PAGE 8 TRAIN SOUG CI Eval req'd?Equip ID PIMS ID System Notes Equip Descption ROB Mother Comp Drawing No.Loc Code Room Elev Norm state Desied State Support System Supp Sys dw" Line No Functon Buiwldir 3 3 20At507 EPS-2A BREAKER TO A HP SER WATER PUMP E-8 12-171 OPEN 20A15 2 R2AP42 135 8105 ACTIVE 20A1507 20A15 Turbile Bldg -U2 CLOSED 20021 3 3 20A1 508 EPS-2A E212 BKR FROM XFMR 0AX04 E-8 T2-471 CLOSED 20A15 2 BR 135 8106 ACTIVE 2GA1508 20AlS Turbine Blg. U2 CLOSED/OPEN 20021 3 3 20A16 EPS-28 (20A016) EMERG AUX SWITCHGEAR E-8 T2-71 ENERGIZED 20A1606 20A1606 2 S 135 8200 ACTIVE E22 Turbine Bldg .U2 ENERGIZED 3 3 20A1601 EPS-28 E322 BKR FROM XFMR 0BX04 E-8 12-71 OPEN 204A16 2 BR 135 8201 PASSIVE E22 (1601) 20A16 Turbine Blg -U2 OPEN 200306 3 3 20A1602 EPS.2 BREAKER TO B RHR PUMP 28P35 E-8 T2-71 OPEN 20A16 2 BR 135 8202 ACTIVE E22 (1602) 20A16 Turbine Bldg -U2 OPEN/CLOSED 20022 28030S 3 3 20A1605 EPS-2B E224 8KR TO XFMR 20X31 E-8 12-71 CLOSED 20A16 2 BR 135 8204 ACTIVE E22 (1605) 20A16 Tturbne Bldg -U2 OPERABLE 20D22 280306 3 3 20A1606 EPS-21 E22 8KR FROM E2 D/G BGI2 E-8 T2.71 OPEN OBG12 2 BR 135 8205 ACTIVE E22 (1606) 20A16 Turbine Bidg -U2 CLOSED 20022 28D306 3 3 20A1607 EPS-28 TO a HP SERV WATER PUMP E.8 T2.71 OPEN 20A16 2 BR 2BP42 135 8206 ACTIVE E22 (1607) 20A16 Turbine Bldg .U2 CLOSED 20D22 280306 3 3 20A1608 EPS-2B E222 BR FROM XFMR OAXO4 E-8 T2-71 CLOSED 20A16 2 OR 135 8207 ACTIVE E22 (1608) 20A16 Turbine Bldg -U2 CLOSED/OPEN 2BD306 3 3 20A17 EPS-2C (20A017) EMERG AUX SWITC.GEAR E-8 T2-170 ENERGIZED 20A1 704 20A1704 2 S 135 20A1708 8300 ACTIVE E32 Turbine Bldg. U2 ENERGIZED 3 3 20A1701 EPS-2C E332 8KR FROM XFMR 0HX04 E-8 12-170 OPEN 20A17 2 OR 135 8301 PASSIVE E32 (1701) 201A7 Tubine Blg -U2 OPEN 30023 3 3 20A1702 EPS-2C BREAKER TO C RHR PUMP 2CP35 E-8 12-170 OPEN 20A17 2 BR 135 8302 ACTIVE E32 (1702) 20A17 Turinne Bldg -U2 OPENICLOSED 30023 3 3 20A1704 EPS-2C E32 8KR FROM E3 DIG OCGI2 E-8 T2-170 OPEN OCG12 BR ACTIVE 8303 E32 (1704)20A17 135 Turbine Bldg -Ur2 CLOSED 30D23 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (lnrrm.nnndp.nr'..

Nn

• RS.;1-173 B-9 DOCUMENT NO. 0067-00084-0D01 REVISION 2 TRAIN SOUG C4 Eqp ID UnA Eval reqd? PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3r20196 PAGE 9 Norm state Motive power Support System Desine StSte Contr powr Supp Sys d"g System Name Equ"p Dasaan ROB MoOe CompNo.Loc Code Room Elev Line No Functo BuinO 3 3 20A1705 EPS-2C E324 BR TO XFMR 2OX32 E-8 T2-170 CLOSED 20A17 2 BR 135 8304 ACTIVE E32 (1705) 20AI7 Tutfne Bldg -U2 OPERABLE 30023 3 3 20A1707 EPS-2C BREAKER TO C HP SERV WATER PUMP E-8 T2-170 OPEN 204A7 2 OR 2CP42 135 8306 ACTIVE E32 (1707) 20A17 Twbine BIdg -U2 CLOSED 30D23 3 3 20A1708 EPS-2C E232 BKR FROM XFMR OAX04 E-8 T2-170 CLOSED 20A17 2 8R 135 8307 ACTIVE E32 (1708) 20A17 Twbine Bldg -U2 CLOSEDIOPEN 30D23 3 3 20A18 EPS-20 (20A018) EMERG AUX SWITCHGEAR E-8 T2-172 ON 20A1807 20A1807 2 S 135 a4"0 ACTIVE E42 Tuwe Bldg -U2 ON 3 3 20A1801 EPS-20 E342 BKR FROM XFMR 08XD4 E-8 12-172 OPEN 20A18 2 BR 135 8401 PASSIVE E42 (1801) 20418 Turbine Bldg -U2 OPEN 3D0306 3 3 20A1802 EPS-2D BREAKER TO D RHR PUMP 2DP35 E-8 T2-172 OPEN 20A18 2 BR 135 8402 ACTIVE E42 (1802) 20A18 Turbk* Bldg -U2 OPEWCLOSED 30024 300306 3 3 2041804 EPS-2D BREAKER TO D HP SER WATER PUMP E-8 12.172 OPEN 20AI8 2 BR 2DP42 135 8403 ACTIVE E42 (1804) 20A18 Turbin Bldg -U2 CLOSED 30024 30D306 3 3 20A1806 FPS-2D E424 8KR TO YFMR 20X33 E-8 T2-172 CLOSED 20A18 2 OR 135 8404 ACTIVE E42 (1808) 20A18 Tuwtdie Bldg -U2 OPERABLE 30D24 300306 3 3 20A1807 EPS-20 E42 8KR FROM E4 DIG 00G12 E-8 12-172 OPEN 0DG12 2 SR 135 8405 ACTIVE E42 (1807) 20MA1 Twbko Bldg -U2 CLOSED 30D24 3D0306 3 3 20A1808 EPS-2D E242 BKRFROM XFMR 0AX04 E-8 T2.172 CLOSED 20A18 2 BR 135 8406 ACTIVE E42 (1808) 20A18 Tuibine Bdg -U2 CLOSEDIOPEN 3DD308 3 4 20X133 EPS-2A PANEL 20Y33 TRANSFORMER E-28. SHT. 1 T2-171 ENERGIZED 20859 2 S 135 8000 ACTIVE 20X133 Turbine Bldg -U2 ENERGIZED 3 4 20X135 EPS-2C PANEL 20Y35 TRANSFORMER E-28, SHT I R2-29 ENERGIZED 20838 2 S 135 8001 ACTIVE 20X135 Reactor 8adg -U2 ENERGIZED 3 4 201(150 EPS-2A PANEL 20Y5O TRANSFORMER E-28, SHT. I 12-171 ENERGIZED 20836 S ACTIVE 135 Twbne Bldg -U2 ENERGIZED 20X150 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrrp..nnndi.nnp.

Nn -RS-19-173 B-10 DOCUMENT NO. 0067-000"4=O01 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm atsle Molie power Desired State Co power DATE: 3128196 PAGE 10 TRAIN SOUG CI Equip ID Eval reqd? PIMS in System Notes Equi Oescripion ROB Mother Comp Drawing No.Loc Code Room Elev Suppor System Swp Sys dwg Line No Fution Building 3 4 20X30 EPS-2A LOAD CENTER XFMR E124 E-1615 R2-41 ENERGIZED 20A1S05 2 S 165 8000 ACTIVE 20X030 Reactor Bldg -U2 ENERGIZED ABB Son Rep 3 4 20X31 EPS-26 LOAD CENTER XFMR E224 E-1615 R2-116 ENERGIZED 20A1605 2 S 165 8000 ACTIVE 20X031 Reactor 81dg -U2 ENERGIZED ABB Seb Rep 3 4 20X32 EPS-2C LOAD CENTER XFMR E324 E.1617 R2.41 ENERGIZED 20A1705 2 S 165 8000 ACTIVE E-1617(20X32)

Reactor Bldg -U2 ENERGIZED ABB Seis Rep 3 4 20X33 EPS-20 LOAD CENTER XFMR E424 E-1617 R2-116 ENERGIZED 20A1805 2 S 165 8000 ACTIVE E-1617(20X33)

Reactor B19 -U2 ENERGIZED ABS Seis Rep 1 20K02 HPCI HPCI GLAND SEAL CDSR VACUUM PUMP M-368, SHIT I R2-13 OFF 20011 2 BR 08 3211 ACTIVE 20K002 20E33 Reactor Bldg -U2 ON 5 20P26 HPCI HPCI AUXILIARY LUBE OIL PUMP M-366. SHT 1 R2-13 OFF 2001 2 BR 8 ACTIVE 20P026 20E33 Reactor Bldg -U2 ON 1 S 20P28 HPCI HPCI GLAND SEAL CONDENSER COND M-366, SlIT I R2-13 OFF 20Dll 2 BR PUMP 088 3214 ACTIVE 20P028 20E33 Reactor Bldg -U2 ON I 20P33 HPCI HPCI BOOSTER PUMP M-366, SHT 1 R2-13 OFF N/A 2 B 088 3226 ACTIVE 20P033 20P38 Reactor Bldg -U2 OPERABLE NfA 1 20P38 HPCI HPCI PUMP M-388. SHT 1 R2-13 OFF NWA 2 S O88 3227 ACTIVE 20P038 Reacto Bld -g U2 OPERABLE NWA Vendor E.4707 t 5 20S37 HPCi "UT HPCI TURBINE U-366, SHT 1 R2-13 OPERABLE N/A 2 S 088 3205 ACTIVE 20S037 Reactor Bldg -U2 OPERABLE NWA 2 5 2AP35 RHR-A RHR PUMP A M-361, SHlT 1 R2-5 OFF 20A15 20A1506 2 S 091 4103 ACTIVE 2AP035 Reactor Blg -U2 OFFION M-I-H-41-2, S-1 146 1 6 2BP35 RHR43 RHR PUMP B M-361, SHT 2 R2-6 OFF 20AI6 20A6 2 S 091 4203 ACTIVE 2OP035 Reactor Blq -U2 OFF/ONl i Mo1-H-41-2, S-114 2 5 2CP35 RHR-C RHR PUMP C M-361. SHT 1 R2-7 OFF 20A17 20A1702 S ACTIVE 2CP035 3 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3.nrrp.osnnndp.nr.

Nn

• RS-12-173 091 Reactor Bldg -U2 OFFION M-1-H-41-2, S-1146 B-11 DATE: 3=2196 PAGE 11 DOCUMENT NO. 0067.00840001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN UnO Line No SOUG CI Eval Wed?Fur'iction Equp tD P111510 system-Notes Ecqip Descripon ROB Mothr Comp Orawig Nix Lot Code Room Eley Bu06nge Norm stale mati pow Desired State Con* power Supor System Supp Sys dwg 1 2DP35 RHRO RHR PUMP D M-381. SHT 2 R2-8 OFF 20A18 1 20AI802 2 S 091 4403 ACTIVE 2DP035 3 Reactor Bdg -U2 OFF/ON M-14441-2,5S1 W 2 6 2AP42 HPEW HIGH PRESSURE SERVICE WATER M-315. SHT I P/H-" OFF 20A1507 2 S PUMP A I11 N 5517 ACTIVE 2AP042 Punp House ON E 11-11-29.

EB-100-1 1 6 28P42 HPSW HIGH PRESSURE SERVICE WATER M-315. SHT 1 P/H-6 OFF 20A1607 2 "S PUMPE 111 6519 ACTIVE 28P042 Pugnp House ON M-11-29, E8-108-1 lOP 6 2CP42 HPSW HIGH PRESSURE SERVICE WATER M-315. SHT 1 PIH-6 OFF 20A1707 2 S PUMP C 111 5521 ACTIVE 2CP042 3 Pump House ON M-11-29. ES-lOS-1 20P 6 20P42 tPSW HIGH PRESSURE SERVICE WATER M-315, SHT 1 P/H4 OFF 20A1804 2 S PUMP 0 111 5523 ACTIVE 2DP042 3 Pump House ON M 3 7 A02-O)lBOA MSIV A MAIN STEAM LINE INBOARD M-351, SHT 1 D/W2-18 OPEN NIA SV2-16-08OA-1 2 S ISOLATION VALVE 134 SV2-16-4OSA-2 2200 ACTIVE AO-2-01A-080A Drywe! -U2 CLOSED N/A 3 7 A02-014NM08 MSIV 8 MAIN STEAM LINE INBOARD M-351. SHT I DNY2-18 OPEN N/A SV2-16-0808-1 2 S ISOLATION VALVE 134 SV2-16-0808-2 2202 ACTIVE AO-2-01A-0803 Drwet -U2 CLOSED N/A M-1-R-1 2/1.2 3 7 A02-0t-C.OC MSIV C MAIN ST EAM LINE INBOARD M-351. SHT 2 DM2-19 OPEN WA SV2-164080C-1 2 S ISOLATION VALVE 134 SV2-16-O08C-2 2204 ACTIVE AO-2-O1A-080C Drywal -U2 CLOSED N/A M-1-R.12/'1.2 3 7 AO2-01-080D MSIV D MAIN STEAM LINE INBOARD M-351. SlHT 2 D/W2-20 OPEN N/A SV2-16-O5OD-1 2 S ISOLATION VALVE 134 SV2-16-0800-2 2206 ACTIVE AO-2.-OtAO-8D Dyl -U2 CLOSED N/A M-1-R-12/1.2 3 7 A02-01-OSSA MSIV A MAIN STEAM LINE OUTBOARD M-351, SHT I R2-3D OPEN N/A SV2-16-OSSA-1 2 S ISOLATION VALVE 135 SV2-16-086A-2 2201 ACTIVE AO-2-01A-086A Reactor Bldg -U2 CLOSED N/A M-1-R-12i1,2 3 7 A02-01-OS6 MSIV B MAIN STEAM LINE OUTBOARD M-351, SHT I R2-30 OPEN N/A SV2-16-086-11 2 S ISOLATION VALVE 135 SV2-18-086B-2 2203 ACTIVE AO-2-OIA-086B Reactor Bldg -12 CLOSED N/A M-1-R-1211.2 3 7 A02'01.)(IC MSIV C MAIN STEAM UNE OUTBOARD M-351. SHT 2 R2-30 OPEN N/A SV2-16-086C-l 2 8 ISOLATION VALVE 135 SV2-16-086C-2 2205 ACTIVE AO-2-OIA-086C Reactor Bldg -U2 CLOSED N/A " M-I-R-12/1,2 3.2 S ACTIVE AO2,o1.085D MSrV AO-2-oiA4086D O MAIN STEAM LINE OUTBOARD ISOLATION VALVE M-351, SHT 2 R2-30 OPEN 135 Reactor Bdg -U2 CLOSED WA N/A SV2-1S-0SS-1 SV2-16-M8D-2 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (.nrrP-nondp.nr.-

No -RS-19-17.3 B-12 DOCUMENT NO. 03674-0084-001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm sate Motve power Owed Stale Cnt powe DATE: 3128/9 PAGE 12 TRAIN UnA SOUG CI Eval fwd?Equ ID PIMS ED System Notes EQup Oescr~tion ROB 10011w Comop Drawing No.Loc Code Room Elav Stoporl Systern Supp Sy's d*g Line No Function _ __ld_ _ _ _ _3 7 A02.03-32A CRD SCRAM DISCHARGE VOLUME INBOARD M-356. SHT 1 R2-26 OPEN WA SV2-3-32A 2 S ISOLATION VENT W 135 i 1102 ACTIVE AO-2403-032A Reactor Bldg -U2 CLOSED NIA 1 M0-I-0-11-3 3 7 A02-03-32B CRD SCRAM DISCHARGE VOLUME INBOARD M%356. SKT I R12-24 OPEN N/A SV2-3-328 2 S ISOLATION VENT W 135 1104 ACTIVE AO-2.03-032B Reactor Bldg -U2 CLOSED NIA 10-1-0-11-3 3 7 A02-03-33 CRD SCRAM DISCHARGE VOLUME INBOARD M.-356, SHT i R2-22 OPEN NIA SV2-3-33 2 S ISOLATION DRAIN W 135 1110 ACTIVE AO-2-03-033 Reactor B U -J2 CLOSED NWA vendor 6-9M207-52 3 7 A02-03-35A CRO SCRAM DISCHARGE VOLUME M-356. SHT I R2-26 OPEN NIA SV2-3-35A 2 S OUTBOARD ISOLATION VENT W 135 1106 ACTIVE AO.2-03,055A Reactor Bldg U2 CLOSED NIA M.1-0-162 3 7 A02-03-35M CRD SCRAM DISCHARGE VOLUME M-350. SHT 1 R2-24 OPEN NWA SV2-3-358 2 S OUTBOARD ISOLATION VENT W 135 1108 ACTIVE AO-203.4)35B Reaclor Bldg -U2 CLOSED WIA M.1-0-162 3 7 A024n-36 CRD SCRAM DISCHARGE VOLUME M-356, SNT I R2-22 OPEN WA SV2-3-36 2 S OUTBOARD ISOLATION DRAIN W 135 1112 ACTIVE AO-2-03-038 Reactor Bldg -U2 CLOSED NWA 1 7 H02-23C-4512 HPCI HPCI TURBINE GOVERNOR.

CONTROL M-368. SHT 1 R2-13 OPEN NWA 2 a VALVE Gas 3204 ACTIVE HO-2-23C.4512 20S37 Reactor Bldg -U2 OPERABLE N/A 1 7 H02-23C-4513 HPCI HPCI TURBINE STOP VALVE M1-66, SHT I R2.13 OPEN NWA SV2-23A-4543 2 B 088 3203 ACTIVE HO-2.23C-4513 20S37 Reactor Bldg -U2 OPEN NIA I M-14J20 1 7 PCV2-238-50 HPCI HPCI COOLING WATER TO LO. COOLER M-366. SlT 1 R2-13 OPERABLE NWA 2 S AND GLAND SEAL CDSR 088 3213 PASSIVE PCV-2-23-O50 Reactor Bldg. U2 OPERABLE NWA 3 7 RV2.02-071A SRV A SAFETY REUEF VALVE M-351. SHT 1 DIW2-27 CLOSED 20021 2 SR t54'-T 2100 ACTIVE RV-2-02-071A 4 Drywlel -U2 OPENICLOSED M-1-R-1-12.

M-I-R-5-4, 3 7 RV2.02-O?18 SRV 8 SAFETY RELIEF VALVE M-351, SHT 1 DNW2-27 CLOSED 20021 2 SR 154-2106 ACTIVE RV-2-02-071B 4 Drywal -U2 OPENICLOSED M-i-R-1-12, M-1-R-5-4, 3 7 RV2.02-071C SRV C SAFETY RELIEF VALVE M-351. SHT I 0DAN2-27 CLOSED 20D21 2 SR 154W-9D 2110 ACTIVE RV-2.02-071C 4 Drywell -U2 OPENICLOSED M-3-R.t-12.

M-l-R-S-4 3 7 RtV2-02-0710 SRV O SAFETY RELIEF VALVE M0-351, SHT 1 0/W2-27 CLOSED 20021 INSTR. N2 SR ACTIVE 2115 RV-2-02-0710 4 154,-a" Dywal -U2 OPEN/CLOSED M-1-R-l-12.

M-1-R-5-4, B-13 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 C'nrrp.qnnndp.nr.-

Nn -RS-1 -173 DOCUMENT NO. 006740084-O001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: &2M PAGE 13 TRAIN S3UG Ci EquipID Evel raeqd? P1145 ID Norm stale Motive power Desired State Cony power System Notes Equip Descrition ROB Mothear Camp Draywb No.Loc Code Room Elev Support System Supp Sys "e0 Line No Friction Buildb'3 7 RV2-02.071E SRV E SAFETY RELIEF VALVE M-351, SHT 1 DJW2-27 CLOSED 20D21 INSTR. N2 2 SR 154'.9" 2117 ACTIVE RV-2-02.071E 4 Oryll -U2 OPENICLOSED W1M-1--12.

M.1-R-5-4.

3 7 RV2-12-O71F SRV F SAFETY RELIEF VALVE 1-351, SHT I ODW2.27 CLOSED 20021 INSTR. N2 2 SR 154-9 I 2119 ACTIVE RV.2-02.071F 4 DrOfwl -U2 OPENfCLOSEO

-M-1.R-1-12.

M-t.R.,S-4, 3 7 RV2-02-071G SRV G SAFETY RELIEF VALVE M-451, SHT 2 D/W2-27 CLOSED 20021 2 SR 1S4S-9" 2121 ACTIVE RV-2-02-O710 4 Drywall -U2 OPENICLOSED 3 7 RV2.02-0711H SRV H SAFETY RELIEF VALVE M14-51, SlIT 2 ONW2-27 CLOSED 20D21 INSTR. N42 2 SR 154'c*215 ACTIVE RV-2-02-071H 4 Drywall -U2OPENICLOSED, 1M-1-R-1-12, M-1-R-5-4.

3 7 RV2-02-071H SRV J SAFETY RELIEF VALVE I-351. SHT 2 01W2-27 CLOSED 20D21 T INSTR. N2 2 SR 154W.9" 2128 ACTIVE RV-2-02-071J 4 Drywel -U2 OPEN/CLOSED M-1-R-1-12.

M-1-R-5-4, 3 7 RV2-02-071K SRV K SAFETY RELIEF VALVE M-351, SHIT 2 OAW2-27 CLOSED 20D21 TR-2 SR 154C-9" 2130 ACTIVE RV-202-.071K 4 Dryweal -U2 OPEN/CLOSED M-I-R-l-12, M-l-R-5-4, 3 7 RV2-02-071L SRV L SAFETY RELIEF VALVE M-351. SHT 2 DA12-27 CLOSED 20021 INSTR. N2 2 SR 154'-9" 2135 ACTIVE RV-2.02-071L 4 Drywell -U2 OPEN/CLOSED M-1-R--12, M-1-R-5-4, 1 7 RV2-23-034 HPCR HPCI PUMP SUCTION HEADER RELIEF M-368. SlIT I R2-13 OPERABLE HWA N 2 S VALVE 058 3225 PASSIVE RV-2-238.034 Reactor aldg -U2 OPERABLE N/A DS-M-20413 2 a CV2-10-2677A RHR-A RHR PUMP 2AP035 DISCHARGE M-361, SHT I R2-5 OPEN NIR 2 N/A CONTROL VALVE 091 4107 PASSIVE CV-2-10-2877A 8 Reactor Bldg -U2 OPEN NIR 1 8 CV2-10-26770 RHR-O RHR PUMP 2DP035 DISCHARGE M-361. SHIT 2 R2-8 OPEN NMR 2 H/A CONTROL VALVE 091 4406 PASSIVE CV-2-10-2677D

3.8 Reactor

Bldg. U2 OPEN NMR 3 a M02-02-74 MSIV MAIN STEAM LINES INBOARD DRAIN M-351. SHT I DAW2-18 CLOSED NMR 2 R ISOL VALVE 134 2208 PASSIVE MO-2-O1A.074 Dwall -U2 CLOSED MR 1 8 M02-06.029A HPCI FEEDWATER STOP VALVE l-351. SHlT 1 DM12-33 OPEN N/R 2 R 154 3235 PASSIVE MO-2-06.029A Drywal -U2 OPEN N/R 1 8 MO206.038A HPCI FW LONG PATH RECIRC ISOLATION M-351. SHT I R2-30 CLOSED NIR 2 R VALVE 135 PASSIVE MO-2-08-038A Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn -R.;-19-173 Reactor Bldg -U2 CLOSED NIR B-14 DOCUMENT NO. 006740040008 1 REVISION 2 PEACH 01TTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm alwee Mowv power Desared State Cont power DATE: 3128M96 PAGE 14 TRAIN SOUG CI EquO ID Eval req'd? PIMS ID System Notes Equip Oescriptlort ROB Mother camp Drawtg No.Loc Code Room Elw Support System Supp Sys dwo Line No Funcion Building 2 8 M02.1o-013A RHR-A RHR PUMP 2AP035 TORUS SUCTION M-361, SHT I R2-5 OPEN NIR 2 R 091 4101 PASSIVE MO-2-10-013A Reactor Bldg -U2 OPEN N/R I a M02-10).13B RHR-S RIR PUMP 2BP035 TORUS SUCTION M-361. SHT 2 R2-6 OPEN N/R 2 R 091 4201 PASSIVE MO-2-10-0139 Reactor Bldg- U2 OPEN NIR 2 8 MO2-10013C RHR-C RHR PUMP 2CP035 TORUS SUCTION M-361, SHT I R2-7 OPEN N/R 2 R 091 4301 PASSIVE MO-2-10-013C 3 Reactor Bldg -U2 OPEN NJR 1 8 MO2-10.0t3D RHR-D RHR PUMP 20P035 TORUS SUCTION M-361. SHT 2 R2-8 OPEN N/R 2 R 091 4401 PASSIVE MO-2-10-013D 3 Reactor Bldg -U2 OPEN NIR 2 8 M02-10.0lSA RHR-A RHR PUMP 2AP035 SHUTDOWN M-361, SHIT 1 R2-5 CLOSED NfR 2 R COOLING SUCTION 091 4102 PASSIVE MO-2.10-015A Reactr Blg -U2 CLOSED NIR 1 8 M02-10-0158 RHR-8 RHR PUMP 2BP035 SHUTDOWN M-3"1. SHT 2 R2-18 CLOSED N/R 2 R COOLING SUCTION 116 4202 PASSIVE MO-2.10-O01B Reactor dg -U2 CLOSED NMR 2 8 M02-10-015C RHR.C RHR PUMP 2CP035 SHUTDOWN M-361. SHT 1 R2-17 CLOSED NiR 2 R COOLING SUCTION 116 4302 PASSIVE MO-2-10-01SC 3 Reator Bldg -U2 CLOSED N/R 8 M02.1"O150 RHR-O RHR PUMP 2DP035 SHUTDOWN M-361, SHT 2 R2-8 CLOSED NWR 2 R COOUNG SUCTION 091 4402 PASSIVE MO-2-10-015D 3 Reactor Bldg -U2 CLOSED NIR 2 BA M02-10-016A RHR-A RAR PUMP 2AP035 MINIMUM FLOW M-3M1. SHIT I R2-5 CLOSED 20B36 2 SR VALVE 091 4104 ACTIVE MO-2-10-016A Reactor Blg -U2 OPENICLOSED M-102B-49 1 SA M02-10-0168 RHR-8 RHR PUMP 2BP035 MINIMUM FLOW I4-3.I, SHT 2 R2- CLOSED 20937 2 SR VALVE 091 4204 ACTIVE MO-2-10-016B Reactor Bldg -U2 OPEN/CLOSED M-1028-49 2 8A M02.10-016C RHR-C RHR PUMP 2CP035 MINIMUM FLOW M-361, SHT I R2-7 CLOSED 20838 2 SR VALVE 091 4304 ACTIVE MO-2-10-016C 3 Reactor Bldg -U2 OPEN/CLOSED M-1028-49 1 &A M02-10-0160 RKR-D RHR PUMP 2DP035 MINIMUM FLOW M-361, SHT 2 R2-8 CLOSED 2083,9 2 SR VALVE 091 4404 ACTIVE MO-2-10-016D 3 Reactor Bldg -U2 OPENICLOSED M2 14-1029-49 3 8 M02-10-018 RHR RHR SHUTDOWN COOLING SUCT I-361. SHT I D/W2-17 CLOSED WA 2 R INBOARD ISOLATION VALVE 134 2212 PASSIVE MO-2-10-018 Drywal -U2 CLOSED N/R Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrre.nnndP.nr..

Nn -RS-19-17 B-15 DOCUMENT NO. 0067400684-0001 REVISION 2 TRAIN SOUG CI Equip ID Unit Eva] req'd? PtMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EGUIPMENT LIST DATE: 3=28111 PAGE 15 Norm state Motive power Support System Desmd State Cori power Supp Sys dwg Equip Deacripion ROB Mother Comp Drawing No.Loc Code Room Elvv Line No Function Adg 2 SA M02-10.025A RHR-A RHR LOOP A INBOARD DISCHARGE M-361. SHT I R2-25 CLOSED 2063 2 SR VALVE M 4117 ACTIVE MO-2-10.025A 10 Reactor Bldg -U2 CLOSEDIOPEN I M-1-4-31-4 1 8A M02-10.0)25 R4R-B RHR LOOP 8 INBOARD DISCHARGE M-381. SHT 2 R2.27 CLOSED 20B39 2 SR VALVE 135 4216 ACTIVE M0-2-10-0258 10 Reactor Bldg -U2 CLOSED/PEN 2 8 M02-10.026A RHR-A RHR LOOP A DAN SPRAY OUTBOARD M-351, SHlT I R2-25 CLOSED NIR 2 R ISOLATION VALVE 135 4112 PASSIVE Reactor Bldg -U2 CLOSED NIR 1 a M02-10-0265 RHR-B RHR LOOP 8 ODW SPRAY OUTBOARD M-361. SHT 2 R2-27 CLOSED NIR 2 R ISOLATION VALVE 135 4211 PASSIVE MO-2-10.O268 Reactor Bldg -U2 CLOSED NIR 2 8A MO210-O34A RHR-A RHR LOOP A FULL FLOW TEST VALVE M-361. SHT 1 R2-110 CLOSED 20838 2 SR (SUPPRESSON POOL COOUNG) 125 4114 ACTIVE MO-2-10-034A 9 Reactor Bldg -U2 CLOSEDWOPEN M-102B-62 B BA M02-10.0348 RHR-8 RHR LOOP 8 FULL FLOWTEST VALVE M-361. SIT 2 R2-105 CLOSED 20B39 2 SR 125 4213 ACTIVE MO-2-10.034B 9 Reactor Sift -U2 OPEN M-102B-62 2 BA M02-10-039A RHR-A RHR LOOP A TORUS HEADER M-361. SHT 1 R2-110 CLOSED 20B38 r 2 SR 125 4113 ACTIVE MO-2-10-039A 9 Reactor Bldg -U2 CLOSEDIOPEN M-"--32 I SA M02-10-0398 RHR-8 RHR LOOP 8 TORUS HEADER M-361. SHT 2 R2-104 CLOSED 20839 2 SR 125 4212 ACTIVE MO-2-10.0398 9 Reactor Bidg -U2 OPENWCLOSED M-14l-32 2 8 M02-10.154A RHR-A RHR LOOP A OUTBOARD DISCHARGE M.-361. SHlT I R2-99 OPEN NIR 2 R VALVE t1e 4115 PASSIVE MO-2-10-154A Reactor Bdg .U2 OPEN N/R 1 8 M02-10-1548 RpR-8 RHR LOOP B OUTBOARD DISCHARGE M-361, SHT 2 R2-93 OPEN N/R 2 R VALVE 116 4214 PASSIVE M0-2-10-1548 Reactor Bldg -U2 OPEN MIR 1 8 M02-10-176 HPSW HPSW TO RIR EMERGENCY OUTER M-315, SHT I R2-6 CLOSED MIR 2 R CROSS-TIE 091 5516 PASSIVE MO-2-10-176 Reacto Of -U2 CLOSED N/R 2 8A M02-10-89A HPSW RHR HX 2AE024 HPSWOUTLET VALVE M-315. SHT 1 R2-16 CLOSED 20838 2 SR 116 5512 ACTIVE MO-2-10.089A Reactor Bldg -U2 OPENICLOSED M M-102I-TI 1 A MO02-10.89B HPSWN RHR HX 29E024 HPSW OUTLET VALVE M-315. SNIT I R2-18 CLOSED 20837 2 5513 SR ACTIVE 116 Reactor Bldg -U2 OPEN/CLOSED MO-2-1040898 M-1029-60 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn

• RR-12-173 B-16 DOCUMENT NO. 00674-00840001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3r2=16 PAGE 16 Norm state Motive power Suppoul System Dealed State Contr power Sup Sys dwg TRAIN SOUG CI Equip ID Eval reu'd? PIMS ID system Notes Equip DesoVd-ROB Mother Camp Drawing No.Loc Code Roam Elav Line No Function Building 2 BA M02-10-89C HPSW RHR HX 2CE024 HPSW OUTLET VALVE M-315, SHT I R2-17 CLOSED 20838 2 SR 116 I 5514 ACTIVE MO-2-10400gc Reactor BUg -U2 CLOSEDWOPEN M-102B-60 1 SA M02-10-49 HPSW RHR HX 2DE024 HPSW OUTLET VALVE M-315, SHT I R2-19 CLOSED 20B39 2 SR 116 5515 ACTIVE MO-2-104 Reator BOg -U2 CLOSEDIOPEN M-1021-60 3 8A M02-12-015 MSIV RWCU INLET INBOARD ISOLATION M-354, SHT I DNV2-28 OPEN 20B36 -2 SR VALVE 134 2209 ACTIVE MO.2-12.015 Dieyal -U2 CLOSED M-1028-33 3 8A M02-12-018 MSIV RWCU INLET OUTBOARD ISOLATION M-354, SHT I R2-33 OPEN 20D0i 2 SR VALVE 165 2210 ACTIVE MO-2-12-018 Reactor Bldg -U2 CLOSED M-1028-33 I 8&A M02-23.0I4 "MC HPCI TURBINE STEAM SUPPLY VALVE M-365f, SHT I R2-13 CLOSED 20Oll 2 SR 088 3202 ACTIVE MO,-2-23-014 Reactor Bldg -U2 OPEN M-1028-42 1 8 M02-23-015 HPCI HPCI TURBINE STEAM LINE INBOARD M-365. SHlT 1 DMW2-17 OPEN NIR 2 R ISOLATION VALVE 134 3200 PASSIVE MO-2-23-015 DryweD -U2 OPEN N/R 1 a M02-23-016 HPCI HPCI TURBINE STEAM LINE OUTBOARD m-365. SIHT I R2-27 OPEN N/R 2 R ISOLATION VALVE 135 3201 PASSIVE MO-2-23-016 Reactor Bldg -U2 OPEN NR 1 BA M02-23-017 HPCI HPCi CONDENSATE STORAGE TANK 1-365, SHT 1 R2-13 OPEN 20011 2 SR SUCTION 08 3224 ACTIVE MO-2-23-017 Reador 2g 2 OPEN/CLOSED 1 BA M02-23-019 HPCI HPCI DISCHARGE TO FEEDWATER LINE M-365, SHT 1 R2-30 CLOSED 20011 2 SR A 135 3231 ACTIVE MO-2-23-019 Reactor Ot -U2 OPEN M 19-1028.29-?

1 8 M02-23-020 HPCI HPCI PUMP DISCHARGE VALVE M-365. SlIT I R2-13 OPEN NIR 2 R 58 3229 PASSIVE MO-2-23-020 Reactor Bldg -U2 OPEN N/R 1 8 M02-23-021 HPCI HPCI FULL FLOW TEST VALVE M-365. SHT I R2-4 CLOSED N/R 2 R 092 3230 PASSIVE MO-2-23-021 Reactor Bldg -U2 CLOSED NIR B 8A M02-234025 HPCI HPCI MINIMUM FLOW VALVE M1-365, SHT I R2-13 CLOSED 20011 2 SR 088 3228 ACTIVE MO-2-23-025 Reactor Bldg -U2 OPEN/CLOSED

-I SA M02-23-057 NPCI HPCI TORUS SUCTION OUTBOARD M-365. SHT 1 R2-13 CLOSED 20011 SR ACTIVE ISOLATION VALVE 088 Reactor Bidg -U2 OPEN 3222 MO-2-23-057 M-102B-33F-1 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrrm.-nnnrlPdnr.

Nn ' RR-19-17.1 B-17 DATE: 3r18MG PAGE 17 DOCUMENT NO. 006740034.0001 REVISION 2 TRAIN SOUG CI Equip ID Und Eval reqd? PU1,S ID Line No Function PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST system Notes Equip Derm p ROB Mo~w Coamp Drw" No.LOC Code Room Elevstate Motive power Desired State Conw power Support System St4PP SYS dwo B 8A M02-23458 HPCI HPCI TORUS SUCTION INBOARD M-365, SHT 1 R2-13 CLOSED 20011 I 2 SR ISOLATION VALVE 088 1 3221 ACTIVE MO-2-23.058 Reactor B8d9 -U2 OPEN2 M-102B-33F.1 1 8 M02-23C-4244A HPCI HPCI TURBINE EXHAUST LINE VACUUM M-365, SIlT 1 R2-94 OPEN NIR 2 R BREAKER ISOL VALVE 116 3219 PASSIVE MO-2-238-4245 14 Reactor Sodg-U2 -N NIR 3 &A M02-30-2233A ESW & HPSW UNIT 2 A SLUICE GATE M-330 S/N-4 OPEN 00562 2 SR 116 5627 ACTIVE MO-2-30-2233A Screen House CLOSED C.316 3 8A M02-30-22338 ESW & HPSW UNIT 2 B SLUICE GATE M-330 SM-4 OPEN 00861 2 SR 116 5628 ACTIVE MO-2-30-22338 screw House CLOSED C-316 3 OP 8 M02-32-2344 HPSW HPSW LOOPS 2A TO 2B CROSSTIE M-315, SiT 1 PA"- CLOSED NIR 2 SR 111 5538 ACTIVE MO-2-32-2344 5 PumpHose CLOSED NIR 3 SA M02-32-2486 HPSW HPSW RETURN VALVE TO DISCHARGE M-330 DIG-2 OPEN 00854 2 SR POND 121 5610 ACTIVE MO-2-32-2486 Diesel Generator CLOSED-M-1028-125 SH5 3 BA M02-32-2803 HPSW HPSW RETURN VALVE TO EMERGENCY M-330 DIG-2 CLOSED 00B55 2 SR COOLING TOWER 121 5612 ACTIVE M0-2-32-2803 Diesel Generator OPEN 3 8 M02-33-2972 ESW & HPSW U/2 SAFEGUARDS AND RBCW HX iSOL M-315, SHT 5 T2-45 OPEN N/R 2 R FROM ESW PUMP 08P057 116 5564 PASSIVE M0-2-33-2972 Turbne Bkg -U2 OPEN NIR 3 BA M02-48-2804A ESW & HPSW Ur2 HPSW DISCH INLET OUTER M-330 ECT-1 CLOSED 00898 2 SR 114 5633 ACTIVE MO-2-48-2804A Emergency Cooieng OPEN Towers 3 BA M02-48-2804B ESW & HPSW U/2 HPSW BAY INLET INNER M-330 ECT-1 CLOSED 00899 2 SR 114 5634 ACTIVE MO-2-48-28048 Emergency Coin .OPEN-Towers 3 88 SV-8130A BACKUP INST N2 BACKUP NITROGEN TO ADS A SUPPLY M-333. SHT 1 R2-23 DEENERGIZED 20Y35 2 SR 135 6100 ACTIVE SV-2-16A-8130A Reaor Bldg -U2 ENERGIZED 3 8B SV-8130B BACKUP INST N2 BACKUP NITROGEN TO ADS 8 SUPPLY M-333. SHT I R2-23 DEENERGIZED 00Y03 2 SR 135 6101 ACTIVE SV-2-16A-8130B Reactor Bldg -U2 ENERGIZED 8 BR.ACTIVE SV2-16-080A-1 MSIV SV-2-16-080A-l TO AO-2-O1A.080A A02-01-O80A DN12-18 134 Drysva -U2 ENERGIZED N/R DEENERGIZED NIR 2216 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3

n. Nn

• RS-19-173 B-18 DOCUMENT NO. 0067.00084-0001 REVISION 2 TRAIN SQUG CI Equip ID Unit Eval reqd? PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Motive power C.r,* P.w DATE: 328196 PAGE 18 system Notes Equip Descrition ROB Mother Comp Drawing No, Loc Code Room Eysv Norm statn Desired State Support System Supp Sys dwg Line No Function Building 3 8 SV2.16.OSOA.2 MSIV AC SOLENOID FOR NITROGEN SUPPLY I-351. SHT I DOW2-18 ENERGIZED NR 2 BR TO AO-2-01A-O8A 134 2217 ACTIVE SV-2-16.08OA-2 A02-0143M0A OrA -U2 DEENERGIZED NJR 3 8 SV2.18-0808-1 MSIV BACKUP DC SOLENOID FOR N2 SUPPLY M4-351, SHT I ODN2-18 ENERGIZED NIR 2 BR TO AO2-01A.08B 134 2228 ACTIVE SV-2-16-080B-1 A02-014008

= Dtw -U2 DEENERGIZED NR 3 8 SV2-16-0608-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY M-351, SIIT I ODN2-18 ENERGIZED N/R 2 DR TO AO-2-OIA.080B 134 2229 ACTIVE SV-2-18-OS.O-2 A02-01-0800 ODywal -D2 EENERGIZED NWR 3 8 SV2-16.080C-1 MSIV BACKUP DC SOLENOID FOR N2 SUPPLY M-351. SHT 2 DNV2-19 ENERGIZED N/R 2 BR TO AO-2-OIA.080C 134 2222 ACTIVE SV-2-16.080C-1 A02-01-O80C Dywell -U2 DEENERGIZED NMR 3 8 SV2-16-080C-2 MS AC SOLENOID FOR NITROGEN SUPPLY M-351. SHT 2 DO12-19 ENERGIZED N/R 2 8R TO AO-2-OIA-080C 134 2223 ACTIVE SV.2- 6-.080C-2 A02-01-O80C Orywe" -U2 DEENERGIZED NMR 3 8 SV2-16.O8001-MSN BACKUP DC SOLENOID FOR N2 SUPPLY M-351, SHT 2 DIW2-20 ENERGIZED NIR 2 BR TO AO-2-01A-0800 134 2234 ACTIVE SV-2-16-0800-A02.01-0800 Drywal -U2 DEENERGIZED NMR 3 8 SV2-16-080D-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY M4-351. SHT 2 DAN2-20 ENERGIZED NMR 2 8R TO AO-2-O1A-OBD 134 2235 ACTIVE SV-2-16-080D-2 A02-01-OW00 Dywefl -U2 DEENERGIZED NMR 8I SV2-23A.4543 HPCI HPCI TURBINE STOP VALVE REMOTE M-366, SHT 1 R2-13 CLOSED 20022 2 BR TRIP VALVE 088 ACTIVE SV-2-23A-4543 20S37 Reactor Bldg -U2 OPEN 1 88 SV2-23C-54 HPCI HPCI TURBINE EXHAUST DRAIN POT M-368, SHT I R2-13 CLOSED 20022 2 SR DRAIN SOLENOID VALVE 088 3209 ACTIVE SV-2-23-054 Reactor Bbg -U2 OPEN -M-205-0-21 3 8 SV2-3-32A CRD INSTR AIR SOLENOID VALVE FOR M-356. SHT 1 R2-22 ENERGIZED N/R 2 BR AO.2-03-032A 135 1103 ACTIVE SV-2-03-032A A02-03-32A Reactor Bldg -L2 DEENERGIZED NMR 3 a SV2.3-328 CRD INSTR AIR SOLENOID VALVE FOR M-356, SHIT I R2-22 ENERGIZED NIR 2 BR AO-2.03.032B 135 1105 ACTIVE SV-2-03-O32B A02-03-32B Reacto" Bldg. -U2 DEENERGIZED NMR 3 8 SV2-3-33 CRD INSTR AIR SOLENOID VALVE FOR M-356, SHT 1 R2-22 ENERGIZED NMR 2 BR AO-2-03033 135 1111 ACTIVE SV.2-03-033 A02-03-33 Reacto Bldg -U2 DEENERGIZED NMR 3 8 SV2-3-35A CRD INSTR AIR SOLENOID VALVE FOR M-356. SIHT 1 R2-22 ENERGIZED NIR 2 1107 BR ACTIVE SV-2-03-035A Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (,nrrA..nnndr.nrP.

Nn

• Rt-12-17.'3 AO-2-03-3A A02-03-35A 135 Reactor Bldg -U2 DEENERGIZED NMR B-19 DATE: 3128196 PAGE 19 DOCUMENT NO. 0067400844001 REVISION 2 TRAIN SOUG Ci Equip ID UEval reqd? PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST system Notes Equip Desor"o ROB Mother Comp Loc Code Room EIev Builtbli-Norm state Motive oW Support System Desired State Con pmr Supp Sys dwg Line No Functon 3 8 SV2-3-58 CRD INSTR AIR SOLENOID VALVE FOR M-356, SHT 1 R222 ENERGIZED N/4k 2 BR A0-2-03-0135 1109 ACTIVE SV-2-03-035B A02-03-35 Reactor Bldg. U2 DEENERGIZED N/R 3 8 SV2-3-W3 CRO INSTR AIR SOLENOID VALVE FOR M-356. SHT 1 R2-22 ENERGIZED N/R 2 BR AO-2-03-03 135 1113 ACTIVE SV-2-03-038 A02-03-36 Reactor Bldg -U2 DEENERGIZED N/R 3 a SV2-36-086A-1 MSrV BACKUP DC SOLENOID FOR I/A SUPPLY M-351. SHT I R2-30 ENERGIZED N/R 2 BR TO AO-2-OIA-085A 135 2219 ACTIVE SV-2.3684&A1 A02-01-486A Reactor Bldg. U2 DEENERGIZED NJR 3 8 SV2-38.88A-2 MSIV AC SOLENOID FOR I/A SUPPLY TO M-351, SHT I R2-30 ENERGIZED NAR 2 BR AO-2-OIA-=A 135 2220 ACTIVE SV.2-36B-086A-2 A02-O1-086A Reactor Bldg. U2 DEENERGIZED NMR 3 8 SV2-36-086B-1 MSIV BACKUP DC SOLENOID FOR I/A SUPLY M-351, SHT I R2-30 ENERGIZED N/R 2 BR TO AO-2-IA-081A 8 135 2231 ACTIVE A02-O1-086B Reactor Bldg. U2 DEENERGIZED NJR 3 8 SV2-38-08SB-2 MSIV AC SOLENOID FOR I/A SUPPLY TO M-351. SHT 1 R2-30 ENERGIZED N/R 2 BR AO-2-OIA-06B 135 2232 ACTIVE SV-2-368-0868,2 A02-O1-0O6B Reactor Bldg. DU2 EENERGIZED NIR 3 8 SV2-3-64 -1 MS1V BACKUP OC SOLENOID FOR VA SUPPLY M-351, SHT2 R2-30 ENERGIZED NWR 2 BR TO AO-2-01A-086C 135 2225 ACTIVE SV-2-M368086C-1 AO2.OI-088C React Bldg -U2 DEENERGIZED N/R 3 B SV2.36-088C-2 MSIV AC SOLENOID FOR I/A SUPPLY TO M-351. SHT 2 R2-30 ENERGIZED NIR 2 BR AO-2A-086C 135DEENERGZED N 2226 ACTIVE SV-2-368.086C-2 A02-01-086C Reacor Bldg- U2 3 8 5V2-36-0860-1 MSIV BACKUP DC SOLENOID FOR VA SUPPLY M-351, SHT 2 R2-30 ENERGIZED WR 2 BR TO AO-2-01A,088D t35 2237 ACTIVE SV-2-36B-086D-1 A02-OI-0860 Reactor Bidg .U2 DEENERGIZEO W/3 8 SV2.36-086D.2 MSIV AC SOLENOID FOR I/A SUPPLY TO ",-351 SHlT 2 R2-30 ENERGIZED WR 2 BR A04-01A-860 135 2238 ACTIVE SV-2-368B-086-2 A0241-0850 Reactor Bldg .U2 DEENERGIZED NWR 1 9 2AV060 HPSWNHVAC HPSW PUMP ROOM SUPPLY FAN A M-.396 SHT 1 P/H-6 AUTO 2 SR 112 ACTIVE Pump House ON 1 9 2AV083 HPSW HVAC HPSW PUMP ROOM EXHAUST FAN A M-396, SHIT I P/1t4 AUTO 2 SR 112 ACTIVE Pump House ON 9 SR ACTIVE 2BV060 HPSW HVAC HPSW PUMP ROOM SUPPLY FAN 8 M-3S6 SHT I P/H14 112 Pump House AUTO ON Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (,nrrPr.nnndPnrA.

Nn RS-1 2-1773 B-20 DOCUMENT NO. 006740054.0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EnUIPMENT LIST DATE: 3128M96 PAGE 20 Norm a Motive power Support Syslm Desred State Cog* power Supp Sys "g TRAIN Unit SQUG CI Equi ID Eval req'd? PIMS ID SywtEm Notes ERu Desrtirona ROD Mothe Camnp Drawing No.Loc Code Room Elev 1 9 28V083 HPSW WVAC HPSW PUMP ROOM EXHAUST FAN 8 M-396. SHT I PIN-6 AUTO 2 SR 112 ACTIVE Pup HOuse ON 3 10 2AE55 ESW RCIC PUMP ROOM COOUNG COIL A M-315. SHT 5 R2-14 NZA NWR 2 S 91.6 5561 PASSIVE 2AE065 Pao Reactor Bldg -U2 WA NIR M-77 Series 3 10 2AE56 ESW HPCI PUMP ROOM COOLING COIL A M-315, SHT 2 R2-13 NIA NIR 2 S 9146 5551 PASSIVE 2AE056 Pao ReaOor Bidg -U2 MAN7R M-77 ,Seris 3 10 2AE57 ESW A CORE SPRAY ROOM COOLING COIL A M.-315, SHT S R2-9 NZA NR -2 S 91-6 56W PASSIVE 2AE057 POO Rescor Bldg -U2 NZA N/R M-77 Series 3 10 2AE58 ESW A RHR ROOM COOLING COIL A M-315, SHIT 2 R2-16 IVA NMR 2 S 1116 5543 PASSIVE 2AE05B P80 Reactr Oldg -U2 NA MR M-77 Series 3 10 28E55 ESW RCIC PUMP ROOM COOLING COIL B M-315, SHT 5 R2-14 NIA NAR 2 S 91-6 5562 PASSIVE 2BE055 Pao Reactor Bid9 -U2 NIA NAR M-77 Series 3 10 28E56 ESW HPCI PUMP ROOM COOLING COIL S M-315. SHT 2 R2-13 NIA NAR 2 S 91-4 5552 PASSIVE 2BE06 P8O Reactor Bldg -U2 NWA N/R M-77 Series 3 10 28E57 ESW A CORE SPRAY ROOM COOLING COIL 8 M-315. SHT 5 12-9 NWA N/R 2 S 9146 5554 PASSIVE 28E057 P80 Reactor Bldg. U2 NIA NAR M-77 Series 3 10 28E58 ESW A RHR ROOM COOUNG COIL B M-315, SHT 2 R2-5 NIA NMR 2 S 9146 5544 PASSIVE 2BE058 P80 Reactor Bldg. U2 N/A NAR M-77 Series 3 10 2CES? ESW C CORE SPRAY ROOM COOLING COIL C M-31. SHT S R2.11 NIA NAR 2 S 9146 555z PASSIVE 2CE057 Pao Reactor g -U2 N/A NAR W-77 Series 3 to 2CE58 ESW C RHR ROOM COOLING COIL C M-315, SHT 2 R2-7 NIA NAR 2 S 9146 5545 PASSIVE 2CE058 POO Reactor Bklg -U2 N/A NIR 1M-77 Series 3 10 20E57 ESW C CORE SPRAY ROOM COOUNG COIL O M-315. SHT 5 R2-11 NIA NR j 2 S 914 I 5556 PASSIVE 2DE057 P8O Reactor Bldg -U2 NIA MR M-77 Series 3 10 2DE58 ESW C RHR ROOM COOUNG COIL 0 M-315. SHT 2 R2-7 NWA N/R S PASSIVE 9146 Reactor Bldg -U2 N/A NMR 5546 2DE058 P80 M-77 Series Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn

• RR-1 9-173 B-21 DOCUMENT NO. 0067-0084-4001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EGUIPMENT LIST Norm state Motive power Desired State Cati power DATE; 3r2819 PAGE 21 REVISION 2 TRAIN SOUG CI Equi ID Evaleetid?

PIMS ID System Notes Equip Desciption ROB Mother Camp Drawing No.Loc Code Room Elev SuPPor System Supp Sys dwg Lku No Function Bundkv 3 10 2EE57 ESW B CORE SPRAY ROOM COOLING COIL E M-31S. SHT 5 R2-10 NIA NIR 2 S 91.6 5557 PASSIVE 2EE057 PBO Reactor Bldg -U2 NIA NIR M-77 Series 3 10 2EESO ESW 8 RHR ROOM COOLING COIL E M-315, SHT 2 R2-6 N/A NMR 2 S 91-6 5547 PASSIVE 2EE058 PBO Reactor Bldg- U2 NA N/R-77 series 3 10 2FE57 ESW B CORE SPRAY ROOM COOLING COIL F M-315, SHT 5 R2-10 NIA NAR 2 S 91-6 5558 PASSIVE 2FE057 PBO Reactor B6dg -L2 WA NWR M-77 series 3 10 2FE58 ESW B RHR ROOM COOLING COIL F M-315. SHT 2 R2-6 NIA NIR 2 $ 9146 5548 PASSIVE 2FE058 PIO Reactor Bldg -U2 WA NJR M-77 Series 3 10 2GE57 ESW D CORE SPRAY ROOM COOLING COIL G M-315. SNT 5 R2-12 NIA NR.2 S 9146 5559 PASSIVE 2GE057 PBO Reactr B -U2 NIA N/R M-77 Series 3 10 2GE58 ESW 0 RHR ROOM COOLING COIL G M-315. SHT 2 R2-19 NIA NMR 2 S Ila 5549 PASSIVE 268058 PEO Reactor Bldg -U2 WA NSR M-77 Series 3 10 2HE57 ESW 0 CORE SPRAY ROOM COQUNG COIL H M-315, SHIT 5 R2-12 N/A NAR 2 5 91-6 560 PASSIVE 21HE057 POO Reactor B9 -U2 NIA NIR M-77 Series 3 10 2HE58 ESW D RHR ROOM COOLING COIL H M-315. SHT 2 R2-8 NWA NAR 2 S 9146 5550 PASSIVE 2HE068 PBO Reactor 6 -U2 NWA NAR M-77 Series 1 10 P020223-1 HPSW IVAC HPSW PUMP ROOM W" LOOP SUPPLY M-396, SHT 1 P1H-6 OPEN 2S DAMPER 112 ACTIVE Pump House OPEN 1 10 P020223-2 HPSW HVAC HPSW PUMP ROOM 9 LOOP EXHAUST M-39%. SlIT 1 P1H-6 OPEN 2S DAMPER 112 ACTIVE Pump House OPEN 10 P020223-3 RPSW HVAC HPSW PUMP ROOM A" LOOP SUPPLY M-396. SHT 1 P11.6 CLOSED 2 5 DAMPER 112 ACTIE Pnmp House CLOSEDIOPEN 1 10 P020223-4 HPSW HVAC HPSW PUMP ROOM 'A, LOOP EXHAUST Ij.396, SHT I P/H-6 CLOSED i 2S DAMPER 112 ACTIVE Pump House CLOSEDWOPEN 3 14 20021 EPS-2A 125V OC STATION DISTRIBUTION PANEL E-26. SHT 1 T2.81 ENERGIZED 2AD03 2AD19 S ACTIVE ISO Tibne ebg -U2 ENERGIZED 8113 20D021 E-16-1-8 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (.nrmpnnnplnnr.

Nn

• R'-19-173 B-22 DATE: 312896 PAGE 22 DOCUMENT NO. 0067400841-00l REVISION 2 PEACH BoTrOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN Urot SOUG CI Equip ID Eval rer'd? PIMS ID Function SYSteM NOWe Equip oeaartion ROB Mother Comp Drawft No.Loc Cod.Room Elev ouflki Norm state Moo"ve power Desired State Conw power Supperl System Supp Sys dwg 3 14 20022 EPS-28 125V DC STATION DISTRIBUTION PANEL E-26. SHT I T2.81 ENERGIZED 28003 28019 2 S 150 8214 ACTIVE 200022 Turbine B9i -U2 ENERGIZED S E~i-16--3 14 20023 EPS-2C 125VDC STATION DISTRIBUTION PANEL E-26. SIT I T2-81 ENERGIZED 2C003 2CD19 2 S 150 8312 ACTIVE 200023 Turbne Wd -UW ENERGIZED E-16.1-8 3 14 20S315 EPS-28 BYPASSAISOLATION SWITCH E.28, SHT. I T2-81 ENERGIZED 20037 2 SR 150 8000 ACTIVE 20S315 Turtine Bldg -U2 ENERGIZED 3 14 20Y33 EPS-2A 120VAC DISTRIBUTION PANEL E-28. SHT. 1 T2-81 ENERGIZED 20X133 2 S 150 8000 ACTIVE 20YO33 Turbne Bldg -U2 ENERGIZED 3 14 20Y35 EPS-2C 120VAC DISTRIBUTION PANEL E-28, SHT I R2-29 ENERGIZED 20X135 2 S 135 8001 ACTIVE 20Y035 Reacor BIg. -U2 ENERGIZED 3 14 20Y50 EPS-28 120VAC DISTRIBUTION PANEL E-28, SHT. I T2.81 ENERGIZED 20008 20037 2 S 150 20X150 8000 ACTIVE 20Y060 Turine Bldg -U2 ENERGIZED 3 14 2AD17 EPS-2A 250 VOLT FUSE BOX E-26, SIlT 1 T2.169 ENERGIZED WA 2AD01 2 S 135 8108 ACTIVE 2AD017 Tu Bldg -U2 ENERGIZED EI6-2-4 3 14 2AD19 EPS-2A 250 VOLT FUSE BOX E-25, SHIT I T2-169 ENERGIZED W/A 2A017 2 5 135 2AD03 0109 ACTIVE 2AD019 Turine Bldg -U2 ENERGIZED EI1-246 3 14 28D17 EPS-28 250 VOLT FUSE BOX E-28. SHlT I T2-169 ENERGIZED WA 28001 2 S 135 820 ACTIVE 260017 Turbine Setg -V2 ENERGIZED E1W-2-6 3 14 28018 EPS-28 2DPB 250V DC DISTRIBUTION PANEL E-28. SHT I T2-169 ENERGIZED 28003 28D17 2 S 2018 135 2D017 8212 ACTIVE 2B0018 Turbine Bldg -U2 ENERGIZED 2DD03 E16-2-6 3 14 28019 EPS-28 250 VOLT FUSE BOX E-25, SHT 1 T2-169 ENERGIZED WA 28017 2 S 135 280003 8210 ACTIVE 280019 Turbine Bldg -U2 ENERGIZED E16-2-8 3 14 280306 EPS-28 125VDC DIST. PANEL (280306) E-26. SHT I T2.71 ENERGIZED 28003 2 S 135 8000 ACTIVE 280D306 Turbine Bldg- U2 ENERGIZED U2 ONLY??3 14 2CD17 EPS-2C 250 VOLT FUSE BOX E-26. SHlT 1 "212-69 ENERGIZED WUA I 2CD01 S ACTIVE 136 Turbine Sldg-.U2 ENERGIZED 8309 2CD017 EIS-2-6 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 C'nrrpqnnnfipnrn.

No

• RS-19-17.1 B-23 DOCUMENT NO. 0067400840001 REVISION 2 TRAIN SQUG CI Equip I Unit Eval reWd? PIMS IC PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST CWpower DATE: 3/2*156 PAGE 23 System Notes Equip 0Ds=0(on ROB Motler Cosnp DrwigNo.LoG Code Room Elov Norm State Desked State Support Systm Supp Sys dwg Line No Function Buldfr 3 14 2CD19 EPS-2C 250 VOLT FUSE BOX E-26, SHT 1 T2-169 ENERGIZED WA 2AD17 2 S 135 8310 ACTIVE 2CD019 Turbine lgt -U2 ENERGIZED E E16-2-6 3 14 2DD17 EPS-2D 250 VOLT DC FUSE BOX E-26. SHT 1 12-169 ENERGIZED WA 20001 2 S 135 8408 ACTIVE 210017 Turbine Bldg .U2 ENERGIZED E16-2.6 3 14 2DD19 EPS-2D 250 VOLT FUSE BOX E-26, SHT I T2-169 ENERGIZED WA 28017 2 S 135 2D0003 8409 ACTIVE 2DD019 Tuwbine Bldg -U2 ENERGIZED E16-2-6 3 15 2ADOt EPS-2A 2A" 125V OC BATTERY E-26. SHT 1 T2-70 ENERGIZED 2AD03 2 S 135 8107 ACTIVE 2AD01I Turbine Bldg. U2 ENERGIZED E-13-34 to 37.3 15 28001 EPS-28 W2 125V DC BATTERY E-25. SlIT 1 T2-169 ENERGIZED 28D03 2 S 135 8208 ACTIVE 28D001 Twbine Bldg -U2 ENERGIZED E-13-34 t037.3 15 2CD01 EPS-2C '2C 125VDC BATTERY E-26. S1iT 1 T2-70 ENERGIZED 2C003 2 S 135 830a ACTIVE 2CD001 Turtne Bldg -U2 ENERGIZED

-E-1 3-34 to 37.3 15 20001 EPS-2D *2D* 125V DC BATTERY E-26, SHT 1 T2-169 ENERGIZED 20003 2 S 135 8407 ACTIVE 2DD001 Turbine Bldg -U2 ENERGIZED E-13-34 to 37.3 16 20D37 EPS-28 STATIC INVERTER E-28, SlIT. 1 T2-73 ENERGIZED 20D00 2 SR 135 20X150 8000 ACTIVE 200037 Turbine g. U2 ENERGIZED 6280-E45 3 16 2AD03 EPS-2A 2A 125V STATION BATTERY CHARGER E-26. SHT 1 T2-171 ON 20859(N)2 S 135 8110 ACTIVE 2AD003 Turbine Bldg -U2 ON 30859(A)NE-102 3 16 28003 EPS-28 -28" 125V STATION BATTERY CHARGER E-26. SHT 1 12-171 ON 20V00(N) 28S455 2 S 135 8211 ACTIVE 28D003 Turbine Bldg -U2 ON 30860(A)NE-102 3 iB 2CD03 EPS-2C 2C 125V STATION BATTERY CHARGER E-26, SHT I T2-171 ON 20838 2 S 135 831l ACTIVE 2C0003 Turbie Bldg -U2 ON NE-102 3 16 2D003 EPS-20 '20" 125V STATION BATTERY CHARGER E-28. SHT 1 1T2-172 ON 20839(N) 20S456 2 S 135 8410 ACTIVE 2DD003 Turbine Bidg -U2 ON 3iB60(A)NE-102 3 18 20C87 EPS HPCI INSTRUMENT RACK R2-15 OPERABLE NIA S ACTIVE 088 Reactor Bldg -U2 OPERABLE WA 20C087 M-1-EE-180.

M-580 B-24 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn -RS-19-17'.

DOCUMENT NO. 0067400=4-,001 REVISION 2 TRAIN SOUGCI UnE Eval Wrd?Lble No Functin PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST Drawing No Motive powe Sutpot System Conar power SUPP Sys dwg DATE: 3128M6 PAGE 24 EquiP ID PIMS ID System Notes Equ Desotton ROB MotherCamp Loo Code Roam Elev Nom eIate Desred State 3 18 2OC95 EPS RCIC INSTRUMENT RACK R2-15 OPERABLE N/A 2 S O88 am00 ACTIVE 20C095 Reactor Bdg -U2 OPERABLE WA MI-EE-188 3 is 2AC65 EPS RX VESSEL LVL AND PRESSURE INST R2-40 OPERABLE WA 2 S RACKA 165 8000 ACTIVE 2AC065 Reactor Bldg -U2 OPERABLE WA M..I.EE.168, M-I-EE.170 3 I8 2AC91 EPS JET PUMP INST RACK A R2-81 OPERABLE WA 2 S 135 8000 ACTIVE 2AC091 Reactor Bldg -U2 OPERABLE NIA 3 Is 2BC65 EPS RX VESSEL LVL AND PRESSURE INST R2-40 OPERABLE NIA 2 S RACK B 165 8000 ACTIVE 2BC05 Reacor Bldg -U2 OPERABLE NIA M-1-EE-168, M-I-EE-170 3 18 28C91 EPS JET PUMP INST RACK B R2-29 OPERABLE N/A 2 S 135 8000 ACTIVE 28C091 Reactor B1O -U2 OPERABLE NIA 1 18 OPS2=24-1 HPSW HVAC HPSW PUMP ROOM I SUPPLY PLENUM M-398. SHT I P1H-8 OPERABLE 2 S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE Pump House OPERABLE I I8 0PS20224-2 HPSWHVAC HPSWPUMP ROOM I EXHAUST PLENUM M-396, SHT 1 PIM-8 OPERABLE 2 S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE Pump House OPERABLE 1 18 DPS20224-3 HPSW`HVAC HPSW PUMP ROOM I SUPPLY PLENUM M-398. SHT t P/1-" OPERABLE 2 S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE Pump House OPERABLE I 18 DPS20224-4 HPSW HVAC HPSW PUMP ROOM I EXHAUST PLENUM M-396. SHT 1 P1rl-8 OPERABLE -2 S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE Pump H OPERABLE 1 18 LS2 PROC MON INSTM SUPPRESSION POOL UMIT SWITCH AY M-365, SHT I OPERABLE 2 BR VALVE M02-13-039 ACTIVE M02-13-039 OPERABLE 1 18 LS2 PROC MON INSTM SUPPRESSION POOL UIMT SWITCH AY M-385. SKT I OPERABLE 2 BR VALVE M02-13041 ACTIVE M02-13-041 OPERABLE 1 18 LS2-23-57 PROC MON INSTM SUPPRESSION POOL LIMIT SWITCH ON m1-39, 5HT I OPERABLE 2 BR VALVE MO2-23 ACTIVE M02-23-57 OPERABLE 1 18 L52-23-58 PROC MON INSTM SUPPRESSION POOL LIMIT SWITCH ON g-359. SHT 1 OPERABLE BR VALVE MO2-ZI-ACTIVE M02-23-58 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn ' RR-12-173 OPERABLE B-25 DATE: 3128198 PAGE 25 DOCUMENT NO. 006740084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SQUG CA Eqtip ID Eval reqd? PIM$ ID Sysr Notes Equ* Descr~Hdw ROD Moliwr Comnp Drwing No.Loc Code Room Elev Norm state Motve power Desired State Coaml power Support System Supp Sys dwg Line no Funcfion Buildng I 18 LS2-23-74 PROC MON INSTm CONDENSATE STORAGE TANK LEVEL M-309, SHT 1 T2-55 OPERABLE 2 SR SWITCH 135 ACTIVE Turb elg -U2 OPERABLE 18 LS2-23-75 PROC MON INSTM CONDENSATE STORAGE TANK LEVEL M-OO. SHT I T2-55 OPERABLE 2SR SWITCH 135 ACTIVE Totbre Bldg -U2 OPERABLE I 18 LS2,23-91A PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-359. SHT 1 R2-10 OPERABLE 2 SR 91-6 ACTIVE Reacor Bldg -U2 OPERABLE I 18 LS2-23-918 PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-359, SHT 1 R2.10 OPERABLE 2 SR 91-6 ACTIVE Reactor Bldg -U2 OPERABLE 3 18 LT8027A PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-365. SiT I R2-10 OPERABLE 20Y33 2 S FOR LR-8027 091 7129 ACTIVE LT-8027A Reactor Bldg. U2 OPERABLE 3 18 LT-D0278 PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-365. SHlT 1 R2-10 OPERABLE 20Y50 2 S FOR .1-8027 091 7127 ACTIVE LT-87B Reactor Blq -U2 OPERABLE 3 Is LT-8123A PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-355, SHT I R2-10 OPERABLE 20Y35 2 SFOR LI.6123A 091 7128 ACTIVE LT-8123A Reactor Bldg. U2 OPERABLE 3 1s LT-81 238 PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-365. SHT I R2-6 OPERABLE 00YO3 2 S FOR LR-81238 091 7130 ACTIVE LT-8123B Reactor Bldg -U2 OPERABLE 3 18 LT-8453 PROC MON INSTM CONDENSATE STORAGE TANK LEVEL M-309, SHT 1 B/SI OPERABLE 20Y50 2 N/A TRANSMITTER FOR LI-8453 116 7132 ACTIVE LT-8453 Level NRF Transfer A Cooling Tower OPERABLE kiLction win be poed I 18 LT2-t3-170 PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-365. SkT 1 T2-14 OPERABLE 2 SR FOR RCIC INITIATION 116 ACTIVE Tturbne Blg -U2 OPERABLE 18 LT2-13-171 PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-365. SHT 1 T2-14 OPERABLE 2 SR FOR RCIC INITIATION 116 ACTIVE Turbine Bdg -.2 OPERABLE 3 18 LT2-2-3.1 PROC MON INSTM REACTOR VESSEL WATER LEVEL M-352. SHT 1 R2.40 OPERABLE 20Y33 2 B TRANSMITTER FOR L12-2-321-8 166 7131 ACTIVE LT-2,02-3-061 2ACOSS Reat b -U2 OPERABLE 3 18 PT-2508B PROC MON INSTM CONTAINMENT ATMOS M-367, SHT I R2-53 OPERABLE 20023 S ACTIVE PRESS TRANSMITTER FOR PR-2508 195 20Y35 Reactor Blg -U2 OPERABLE PT-2508B Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 No RR-19'-17.I B-26 DATE: 3/2M96 PAGE 26 DOCUMENT NO.

REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG CA Equip ID Evel red? PUMS ID Furdon system Notes Equip Descrition ROB Moater camp Drawing No.Laoc Code Room Elev R"nM Nom state Desied State Moti power Conlr power Suppod System Supp Sys dwg 3 18 PT-4805 PROC MON INSTM ORYWELL PRESSURE TRANSMITTER M-367. SHT 1 R2-20 OPERABLE 20Y50 2 S FOR PR-4805 116 7141 ACTIVE PT4-05 Reactor Bdg -U2 OPERABLE 3 18 PT-8102A PROC MON DISTM ORYWELL PRESSURE TRANSMITTER M-351, SHT I R2-63 OPERABLE 20Y35 2 a FOR PR-1102A 165 7135 ACTIVE PTaIO2A 2AC65 Reactor dg -U2 OPERABLE 3 1i PT-81026 PROC MON INSTM ORYWELL PRESSURE TRANSMITTER MP361. SBHT2 R2-3 OPERABLE 00Y03 2 B FOR PR-8102B 165 7137 ACTIVE PT-81028 2C65 Reactor Bdg -U2 OPERABLE 3 18 PT-102C PROC MON INSTM DRYWELL PRESSURE TRANSMITTER M-361, SHT I R2-63 OPERABLE 20Y35 2 B FOR PR-6102A 165 7134 ACTIVE PT-8102C 2AC65 Reactor Bdg -U2 OPERABLE 3 18 PT-81020 PROC MON INSTM DRYWELL PRESSURE TRANSMITTER M-361. SHT 2 R2-63 OPERABLE 00Y03 2 a FOR PR81O2B 165 7136 ACTIVE PT-81020 2BC65 Reactor Bldg -U2 OPERABLE 3 18 PT2-2-3-404A PROC MON INSTm REACTOR PRESSURE TRANSMI1TER M-352, SHT i R2-40 OPERABLE 20Y35 2 B FOR PR2.2-3404A 165 7138 ACTIVE PT.2-C2-3-404A 2AC065 Reactor Bldg -U2 OPERABLE 3 18 PT2-2-3-4048 PROC MON INSTM REACTOR PRESSURE TRANSMITTER M-52. SHT 2 R2-40 OPERABLE 00Y03 2 8 FOR PR2-2-3-404B 165 7139 ACTIVE PT-2-02-3-4040 28C065 Reactor 81dg -U2 OPERABLE 3 18 PT24.65A PROC MON INSTM REACTOR WIDE RANGE PRESSURE M-352, SHT I R2-40 OPERABLE 20Y50 2 B TRANSMITTER FOR P12-6-90A 165 7132 ACTIVE PT.2-06-053A 2AC065 Reactor Bldg -U2 OPERABLE 3 18 PT2-6-53B PROC MON INSTM REACTOR WIDE RANGE PRESSURE M-352, SHT 2 R2-40 OPERABLE 20Y50 2 a TRANSMITTER FOR P12--90B 165 7133 ACTIVE PT-24XM53B 28C065 Reactor Bldg. U2 OPERABLE I I 18 TIC20223 HPSW HVAC; HPSW PUMP ROOM EXHAUST TEMP M-396. SHT 1 P/h" OPERABLE 2 S INDICATING CONTROLLER 112 ACTIVE Pump House OPERABLE Ii TS20224-1 HPSWHVAC HPSW PUMP ROOM"A" LOOP M-396. SHT 1 PIH-6 OPERABLE 2S AUTOMATIC TEMPERATURE SENSOR 112 ACTIVE Pump House OPERABLE 1 18 TS20224-2 HPSW HVAC HPSW PUMP ROOM 1 LOOP M-396. SHT I PI'-l OPERABLE A S AUTOMATIC TEMPERATURE SENSOR 112 ACTIVE Pump HoOOM OPERABLE 18 S ACTIVE TT20223 HPSW HVAC TEMPERATURE TRANSMITTER M-396. SHT I PlH-8 112 Pump Houos OPERABLE OPERABLE Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 C'nrmr..nnndrInc.j.

Nn

• RS-19-173 B-27 DATE: 3I28/W PAGE 27 DOCUMENT NO. 0067-00084-0001 REVISION 2 TRAIN SQUG Ci Uni Eval eo'd?Line No Function PEACH BOTrOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST EWO ID PIMS ID system Notes Equip Desc~rition ROD Modwe Comp, Drawinq No.Loc COe Room Eyv Budking Norm stale Desired State MGMn power Coant power Suppot System Supp Sys dWg 3 20 206324 EPS M02-23-015 MOTOR CONTROL POWER T2-67 OPERABLE N/A 2 S TRANSFER SWITCH 135 a000 ACTIVE 209324 Turbine Bldg -U2 OPERABLE N/A 3 20 20C003 EPS REACTOR AND CONTAINMENT COOLING 12-100 OPERABLE N/A 2 S AND ISOLATION 165 8000 ACTIVE 20CO03 Turbine Sdg -U2 OPERABLE N/A 3 20 20C004C EPS RCIC CONTROL PANEL T2-100 OPERABLE MIA 2 S 165 8000 ACTIVE 20C004C Turbine Bldg -U2 OPERABLE WA 3 20 20C005A EPS REACTOR MANUAL CONTROL PANEL T12-100 OPERABLE N/A 2 S 165 Mo ACTIVE 20COOSA Turbine Blg -U2 OPERABLE N/A 3 20 20COOC EPS MAIN CONTROL ROOM CONSOLE T12-100 OPERABLE NWA 2 B 165 8000 ACTIVE 20C00SC 20CODSA Tuibi Bldg -U? OPERABLE N/A 3 20 20C012 EPS PLANT SERVICES CONSOLE 12-100 OPERABLE WA 2 S 165 8000 ACTIVE 20C012 Turbine Bldg -U2 OPERABLE N/A E-17-4212 3 20 20C024 EPS CRT AND RFPT TEST PANEL 12-100 OPERABLE N/A 2 S 165 8000 ACTIVE 20C124 Turbine Bldg .2 OPERABLE N/A 1 20 2OCt39 HPSWHVAC HPSW PUMP ROOM LOCAL CONTROL E202 P11.8 OPERABLE B62 2 S PANEL 112 ACTIVE P House OPERABLE 3 20 20C32 EPS ENGINEERING SUB SYSTEM I RELAY 1"2-81 OPERABLE WA 2 S CABINET 150 a000 ACTIVE 20C032 Turbine Bldg -U2 OPERABLE N/A S-1198/1-3.

M-1 -EE-241 3 20 20C33 EPS ENGINEERING SUB SYSTEM II RELAY T12-81 OPERABLE N/A 2 S CABINET 150 80 ACTIVE 20C033 Turbine Bbg -U2 OPERABLE N/A S-119811-3.

M-I -EE-241 3 20 20C34 EPS RCIC RELAY PANEL T2-81 OPERABLE N/A 2 S 150 6000 ACTIVE 20C034 Turbine Bldg -U2 OPERABLE N/A S-1198/1-3.

M-1-EE-84-24 3 20 20C39 EPS HPCI RELAY CABINET T12-81 OPERABLE NWA 2 S 150 8000 ACTIVE 20C039 Turbine Bldg -U2 OPERABLE NWA S-1198/1-3 M-1-EE-98 3 2 8000 20 20C722A EPS S ACTIVE 20C722A Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 C'nrmr.%nnndAnr.Pr Nn ' R5q-1-173 ACISUMENT MANIO PAINE INSTRUMENTATION PANEL 12-81 150 Turbine Bldg -U2 OPERABLE WA OPERABLE N/A S-1198/1-3, M-1-EE-405 B-28 DOCUMENT NO. 00674008440001 REVISION 2 TRAIN SOUG CI Urkit Eval reqad?Line No Function PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST Motive power Cortr power DATE: 3128196 PAGE 28 Equip to PIMS ID Notes Equip Desription ROB Mother Comp Drawing No.Loc Code Room Elev suding Norm state Desked State SLfipWI System Supp Sys dwg 3 20 20C722B EPS ACCIDENT MONITORING T2-81 OPERABLE MA 2 S INSTRUMENTATION PANEL 150 amW ACTIVE 20C7228 Turbine Bldg -U2 OPERABLE NIA S-1196l1 -3. M-1-EE-405 3 20 20041 EPS HPCI GLAND SEAL CONDENSER VACUUM .R2-13 OPERABLE NIA 2 S PUMP STARTER 068 8000 ACTIVE 20D041 Rea or Bldg -U2 OPERABLE WA 3 20 20D42 EPS HPCI GLAND SEAL CONDENSER VACUUM .R2-13 OPERABLE NWA 2 a PUMP STARTER 088 8a00 ACTIVE 202 2D41 Reactor Bldg -U2 OPERABLE NWA 3 20 20043 EPS HPCI AUX LUBE OIL PUMP STARTER R2-13 OPERABLE N/A 2 B 068 8000 ACTIVE 200043 20041 Reactor Bldg -U2 OPERABLE NWA U2 ONLY??1 20 20S37-PANEL HPCI "U2 HPCI TURBINE M-36M, SHT I R2-13 OPERABLE NWA 2 S O8 ACTIVE 20S037-PANEL Reactor Bldg -U2 OPERABLE NIA 3 20 2AC265 EPS RESERVOIR FLOW PUMP BAY MO-2804A ECT-1 OPERABLE NIA 2 S 114 8000 ACTIVE 2AC265 Emergency Coaling OPERABLE NIA Tower 62A-O-117-49-3 3 20 2AC272 EPS HPCI STEAM LEAK DETECTION CABINET T12-100 OPERABLE NWA 2 S 165 8000 ACTIVE 2AC272 Turbine Bldg -U2 OPERABLE WA M241-10 3 20 2SC265 EPS RESERVOIR FLOW PUMP BAY MO-2804B ECT-1 OPERABLE N/A 2 S 114 8000 ACTIVE 2SC265 Emergency Coolig OPERABLE WA Tower 62A-O-1 17-49.3 3 20 2BC272 EPS HPCI STEAM LEAK DETECTION CABINET T2-100 OPERABLE N/A f 2 S 165 8000 ACTIVE 2BC272 Turbne Bldg -U2 OPERABLE NIA I M241-10 3 20 2CC133 EPS FAN ROOM H&V RELAY PANEL R/N-32 OPERABLE NIA 2 S 165 8000 ACTIVE 2CC133 Radwaste Bldg OPERABLE NWA U2 ONLY??3 20 LI.802" PROC MON INSTM TORUS WATER LEVEL M-365, SlIT I T2-100 OPERABLE 20Y50 LT-8027B 2 BR 165 7100 ACTIVE LI-8027 20C003 Turbine Bldg -U2 OPERABLE 3 20 LI-8123A PROC MON INSTM WIDE RANGE SUPPRESSION POOL M-365, SHT 1 T2-100 OPERABLE 20Y35 LT-8123A 2 BR LEVEL INDICATOR 165 7101 ACTIVE LI.8123A 20C003 Turine Blgi -U2 OPERABLE 3 20 LI.8453 PROC MON INSTM CST LEVEL INDICATOR M-309, SliT 2 T2-100 OPERABLE 20Y50 LT-8453 2 7102 OR ACTIVE LI-8453 20C004C Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrrn.qnnnd-nr.P.

Nn -RS-12-173 165 Turbine Bidg- U2 OPERABLE B-29 DOCUMENT NO. 0067-00084-O001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3128196 PAGE 29 Norm state Motive pow j Suppwr System Desired State COW power supp Sys deg TRAIN Unit SQUG C! Equip ID Evel reqd? PIMS ID System Notes Equip oeSariion ROB MotherCxnip DrswbV No.LoC Code Room Elev Lbe No Funcxt Buf 3 20 L12-2-3-113 PROC MON INSTM REACTOR WATER LEVEL M-352, SlT 5 12.100 OPERABLE 20Y50 LT2-2-3-113 2 BR 165 7124 ACTIVE LI-2-02-3-113 20C003 Twrbkie Bldg -U2 OPERABLE 3 20 L12-2-3-5A PROC MON INSTM REACTOR VESSEL HIGH WATER M-M32. SHT 5 12-100 OPERABLE 20Y35 LT2.2-3-72A OR 73A 2 BR 165 7125 ACTIVE LI-2-02-3-OOA 20COOSA Turbine B1dg- U2 OPERABLE 3 20 L12-2.3-M8 PROC MON INSTIM REACTOR VESSEL HIGH WATER M4362, SHT 5 T2-100 OPERABLE 00Y03 LT2-2-3-72B OR 738 2 BR 165 7126 ACTIVE LI-2-02-3-085 20C005A Ttubkwe Bldg -u2 OPERABLE 3 20 L12-2-3-86 PROC MON INSTM REACTOR VESSEL HIGH WATER M-352, SHT i T2-100 OPERABLE 20Y33 LT2-2-3.61 2 BR 165 7107 ACTIVE LI-2-02-3-088 20C003A Turblne Bteg. U2 OPERABLE 3 20 LR-=027 PROC MON INSTM TORUS WATER LEVEL M-.365 SHT 1 T2-100 OPERABLE 20Y33 LT-07A 2 BR 165 7102 ACTIVE LR.8027 20C003 Turbine Bldg -U2 OPERABLE 3 20 LR-81238 PROC MON INSTM TORUS WATER LEVELITEMPERATURE M-385, SHT 1 T2.100 OPERABLE 00Y03 LT-81238 2 OR RECORDER 165 7103 ACTIVE LR/TR-81238 20C003 Tubne Bdg. -U2 OPERABLE 3 20 LR2-2-3-110A PROC MON INSTM REACTOR WATER LEVEL WIDE RANGE M-52, SlIT 5 2-I00 OPERABLE 20Y35 LT2-2-3-72C OR 73C 2 BR 165 7104 ACTIVE LR-2-02-3-110A 20C004C Turbne Bl -U2 OPERABLE 3 20 LR2.2-3-i1OB PROC MON INSTM REACTOR WATER LEVEL WIDE RANGE M-352, SHT 5 T2-100 OPERABLE 00Y03 LT2-2-3-720 OR 730 2 BR 165 7105 ACTIVE LR-2-02-3-1108 20C003 Turbiwne Bdg .U2 OPERABLE 3 20 P12.6-4A PROC MON INSTM REACTOR WIDE RANGE PRESS IND M-352. SNT 1 12-100 OPERABLE 20Y50 PT2-6-53A 2 BR 165 7108 ACTIVE PI-2-06-09OA 20C00SA Tuibine Oft -Ur2 OPERABLE 3 20 P12-6-906 PROC MON INSTM REACTOR WIDE RANGE PRESS IND M-352. SHT 2 12-100 OPERABLE 20Y50 PT2-6-53B 2 OR 165 I 7109 ACTIVE PI-2-06.090B 20C005C Turbie Bldg -U2 OPERABLE 3 20 PR-2508 PROC MON INSTM CONTAIN ATMOS DRYWELL PRESS m-367. SlIT 1 12-100 OPERABLE 20Y35 PT-2508B 2 BR 165 20023 7110 ACTIVE PR-2506 20C003 Turine Oft -U2 OPERABLE 3 20 PR-4805 PROC MON INSTM CONTAINMENT PRESSURE " 7, SHT 1 12-100 OPERABLE 20Y50 PT-4805 2 BR 165 7111 ACTIVE PR-4805 20C003 Turbine Bldg -U2 OPERABLE 3 20 PR-8102A PROC MON INSTM DRYWELL PRESSURE M-451, SHT 1 12-100 OPERABLE 20Y35 PT-8102A 2 BR 7112 ACTIVE PR-8102A 20C003 165 Twtne Bldg -U2 OPERABLE PT-8102C Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 ,nrrP.nnndrrn-.P No ' RS-12-17.1 B-30 DOCUMENT NO. 0067400184-0001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm slte Motive powerl State Coa power DATE: 31288 PAGE 30 REVISION 2 TRAIN SOUG C) Equip ID Eval req'd? PIMS ID System Notes Equip Description ROB Mothe Camp Orewke No.LoC Code Room Elv Support System Suwp Sys otwg Line No Function Suing 3 20 PR-8102B PROC MON INSTM 0RYWELL PRESSURE M-361. SHT 2 12.100 OPERABLE 00Y03 PT-8102B 2 BR 165 PT-81020 7113 ACTIVE PR-81028B 20C003 Turbine Bldg -U2 OPERABLE 3 20 PR2.24-404A PROC MON INSTM REACTOR PRESSIRPV WATER LEVEL M-352. SHT 1 T2-100 (CO4C) OPERABLE 20Y35 PT2-2-3-404A 2 BR 165 7114 ACTIVE PRILR-2-02-3-404A 20C004C TWbne Bldg -U2 OPERABLE 3 20 pP.2-2-3-404 PROC MON INSTM REACTOR PRESSURE M.352, SHT 2 12.100 OPERABLE 00Y03 PT2-2.3-404B 2 BR 165 7115 ACTIVE PR-2-02-3-404B 20C003 Tuiine Bldg -U2 OPERABLE 3 20 PR2-6-96 PROC MON INSTM REACTOR LEVEIJSTM FLOW RATIO M-352. SHT 5 T2-100 OPERABLE 20Y50 PT2-6-105 2 BR 165 7106 ACTIVE PRILR-2-0560 20COOSA Turbine Bldg -U2 OPERABLE 3 20 TIS-2-2-71A PROC MON INSTM TORUS WATER TEMPERATURE M4361. SKT 1 T2-100 OPERABLE 20Y35 TE2-2-71A1 2 BR INDICATING SWITCH 165 THRU 7118 ACTIVE TIS-2-02-071A 20C124 Turbine Bldg -U2 OPERABLE TE2-2-71N1 3 20 TIS-2-2-718 PROC MON INSTNI TORUS WATER TEMPERATURE M-361, SlT 2 T2-400 OPERABLE 00Y03 TE2-2-71A2 2 BR INDICATING SWITCH 165 THRU 7119 ACTIVE TIS-2-02-0718 20C024 Turbine Bldg -U2 OPERABLE TE2-2-71N2 1 21 20E105 "Pei HPCI TURB LUBE OIL COOLER (23-2) M-366, SHT I R2.13 OPERABLE N/A 2 8 -88 3212 PASSIVE 20E105 6116194 Reactor Bfdg -U2 OPERABLE WA Vendcor Dwg 210M806A3 1 21 20E33 HPCI HPCI GLAND SEAL CONDENSER (23-2) M-366. SHT I R2-13 OPERABLE NWA 2 S 088 3210 PASSIVE 20E033 Reactor Bldg -U2 OPERABLE WA 3 21 2AE124 ESW 2A RHR PUMP SEAL COOLER M-315, SHT 2 R2-5 NIA NIR -2 B 091 5539 PASSIVE 2AE124 2AP35 Reactor Bldg -W2 NIA NWR 2 21 2AE24 RHRA RHR HEAT EXCHANGER A M-361. SHT 1 R2-16 OPERABLE WA -2 S 116 4106.5525 PASSIVE 2AE024 Reactor Bldg -U2 OPERABLE NWA M-1 -H-4-7, M-4'4-12-5, 3 21 2AS377 BACKUP INST N2 BACK-UP N2 SUPPLY TO ADS RVS M-333. SHT 1 R2.66 OPERABLE NWA 2 S 135 6102 PASSIVE 2AS3T Reactor Bldg -U2 OPERABLE WA 8M-1786-5 3 21 2AT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 1 DAW2-27 OPERABLE NIA I NSTR. IN2 2 S RV-71A 154 2101 PASSIVE 2AT545 Orywle -U2 OPERABLE NWA 3P133 3 21 2BE124 ESW "29 RIR PUMP SEAL COOLER 81-315, SHlT 2 R2-6 N/A NIR B PASSIVE 28E124 091 Reactor BkIg -U2 NWA NIR 2BP35 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Conrri.snnd.nr-.P.

Nn -RS-19-173 B-31 DOCUMENT NO. 006740084-D001 REVISION 2 TRAIN SQUOCI Equip ID Unit Eval reqd? PIMS LD PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm slate Motv power Desked State Corr power DATE: 3128196 PAGE 31 System Notes Equip Description ROB Mother Camw Oraming No.Loc Code Room Elev Support System Supp SyS dWg Line No Functti Buddingr 1 21 28E24 RHR-8 RHR HEAT EXCHANGER B M-361, SHT 2 R2-18 OPERABLE N/A 2 S 116 4206.5527 PASSIVE 2BE024 Reactor Bldg -U2 OPERABLE N/A M-"-4.7, M-H.12-S.3 21 2BS377 BACKUP INST N2 BACK-UP N2 SUPPLY TO ADS RVS M-333, SHT I R2-23 OPERABLE NIA 2 S 135 E 2BS377 Reactor Bidg- U2 OPERABLE NWA 6103 PASSIVE 2S37M1W M-1786-5 3 21 2BT545 SRV INSTRUMENT Nf2 ACCUMULATOR FOR M-35t1 SHT I DA2-27 OPERABLE NZA INSTR. N2 2 S RV-71B 154 2106 PASSIVE 2BT545 Drei -U2 OPERABLE NIA 3 21 2CE124 ESW "2CRHR PUMP SEAL COOLER M-315, SHT 2 R2-7 NIA N/R 2 a 091 5540 PASSIVE 2CE124 2CP35 Reactorldg. .U2 WIA NIR 2 21 2CE24 RHR-A RHR HEAT EXCHANGER C M-361. SHT I R2.17 NWA NWA 2 S 091 4109. 5526 PASSIVE 2CE024 Reactor Bidg .U2 OPERABLE NWA M-I-H-4-7, M-I-H-12-S.

3 21 2C5377 BACKUP INST N2 BACKUP NITROGEN SUPPLY FOR ADS M-333, SHlT 1 R2-23 OPERABLE WUA 2 S 135 6104 PASSIVE 2CS377 Reactor Bldg -U2 OPERABLE WA M17W5 3 21 2CT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351, SHTI r2-27 OPERABLE NWA INSTR. N2 2 S RV-71C 154 2111 PASSIVE 2CT545 Dywll -U2 OPERABLE NWA M-333 3 21 2DE124 ESW '2[" RHR PUMP SEAL COOLER M-315, SHT 2 R2-8 NWA NIR 2 a 091 5542 PASSIVE 2DE124 20P35 Reactor Bldg .U2 NIA NIR 1 21 2DE24 RHR-8 RHR HEAT EXCHANGER 0 M-361. SHT 2 R2-19 WA NIA 2 S 116 4209,5528 PASSIVE 2DE024 Reactor Bld -U2 OPERABLE NWA M-I -H-4-?. M-l-H-12-5, 3 21 2GT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 2 D02-35 OPERABLE WUA INSTR. N2 2 S RV-71G 154 2122 PASSIVE 2GT545 DrywU -LU2 OPERABLE NIA M-33 3 21 2KT545 SRV INSTRUMENT N2 ACCUMULATOR M-351. SHT 2 DA%2-34 OPERABLE NWA INSTR. N2 2 S 154 2131 PASSIVE 2KT545 Dye- U2 OPERABLE WNA R 0 16A.33205A SRV ADS BACKUP N2 SUPPLY CHK W TO M-351. SHT 3 DANV3-27 OPERABLE WA -3 NWA RV-3-2-071A 154 2103 PASSIVE CHK.3. 6A-33205A Drwld .U3 OPERABLE NWA 3 0 16A-332058 SRV ADS BACKUP N2 SUPPLY CHK W TO M-351. SHT 3 DN3.29 OPERABLE NWA RV-3-2-071B 2109 PASSIVE CHX-3-16A-332058 Drywll -U3 OPERABLE WA Peach Bottom Atomic Power Station Unit 2 B-32 MPR-3815, Revision 3 (lnrrpqnnndipnr.pn Nn RR-19-173 DOCUMENT NO. 0067.00084-,001 REVISION 2 TRAIN SOUG CI Equip ID Unit Eval reqd? P1IS 10 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm~ slate Motive power Desired Slate Corn power DATE: 3128196 PAGE 32 System Notes Equip Description ROB Mothe Comp Drawing No, Loc Code Room Elev Support System Supp, Sys dwg Li No Function Builov 3 0 26 SRV ADS BACKUP N2 SUPPLY CHK W TO M.351, SHT 3 0lW3-27 OPERABLE N/A 3 0 RV-3-2-071C 154 3 NIA Dye 3OEAL I 2115 PASSIVE CHK-3.ISA-33205C DweII-U3 OPERABLE WA 3 0 16A-33205G SRV ADS BACKUP N2 SUPPLY CHK W TO M-351, SHT 4 DJW3.35 OPERABLE N/A 3 N/A RV-3-2.)71G 164 2127 PASSIVE CHK-3.16A.33205G Dwell -U3 OPERABLE N/A 3 0 16A-33205K SRV ADS BACKUP N2 SUPPLY CHK W TO M-351, SHT 4 D/W3-34 OPERABLE N/A 3 N/A RV-3-2-071K 154 2137 PASSIVE CHK-3-15A-33205K Drywel -U3 OPERABLE WA 1 0 3.06-0965 RCIC FEEDWATER CHECK VALVE LOOP B M-351, SHT 4 R3-30 OPEN N/A 3 N/A OUTER 135 3134 PASSIVE CHK-3-O6-968 Reato Sidg-U3 CLOSED N/A 2 0 3.10-177 RHR-C HIGH PRESSURE SERVICE WATER TO M-315. SHIT 3 R3-7 CLOSED NIA 3 N/A RHR CROSSTIE CHECK VALVE 091 4309 PASSIVE CHK-3-10-177 Reactor Bidg -U3 CLOSED WA 2 0 3-10-184A RHR-C RHR PRESSURING LINE INNER CHECK M-361, SHT 3 R3-24 CLOSED N/A 3 W/A VALVE TO RHR LOOP A 135 4315 PASSIVE CHK-3.10-184A Reactor Bldg -U3 CLOSED N/A 1 0 3-10-1848 RHR.O RHR PRESSURING LINE INNER CHECK M-361. SHT 4 R3-26 CLOSED NIA 3 N/A VALVE TO RHR LOOP 8 135 4415 PASSIVE CHK.3-10.184B Reactor Bldg -U3 2 0 3-10-48A RHR-C RHR PUMP 3AP035 DISCHARGE CHECK M-361. SHT 3 R3-5 CLOSED NIA 3 N/A VALVE 091 4308 PASSIVE CHK-3-10-48A Reactor Bldg -U3 OPERABLE NIA 1 0 3-10-488 RHR-D RHR PUMP 3BP035 DISCHARGE CHECK "I31. SHT 4 R3-6 CLOSED NIA 3 NIA VALVE 091 4410 PASSIVE CHK-3-10-488 Reactor Bldg -U3 OPERABLE N/A 2 0 3-10.48C RHR-A RHR PUMP 3CP035 DISCHARGE CHECK M-361. SHT 3 R3-7 CLOSED N/A 3 N/A VALVE 091 4107 PASSIVE CHK-3-10-48C 3 Reactor Bldg .U3 OPERABLE NIA 2 0 3-10-480 RHR-B RHR PUMP 3DP035 DISCHARGE CHECK I-381. SHlT 4 R3-8 CLOSED N/A 3 NIA VALVE 091 4206 PASSIVE CHK-3-10-48D 3 Reac Bldg -U3 OPERABLE NIA 3 0 3-16-257A SRV INSTR N2 CHECK VALVE TO RV-3-2-071A M-351. SHT 3 1O9-27 OPERABLE NIA 3 NIA 154 2104 PASSIVE CHK-3-16-257A Drwall -U3 OPERABLE NIA 3 0 3.16-257 SRV INSTR N2 CHECK VALVE TO RV-3-2-071B M.351. SHT 3 DmW3-29 OPERABLE NIA NIA PASSIVE CHK-3.16-257B 2110 154 Drywe- U3 OPERABLE WA Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 f.nrmr.nnndnnrp.

No

• RS-12-173 B-33 DOCUMENT N4O.

REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm s Motie power.Desied Stel Col* power DATE: 3128/16 PAGE 33 TRAIN SOUG Cl Equip ID Eval re~d7 PIMS ID System Notes Equip Desorltiorl ROB Modur CampW Drawft No.Loc Code Room Elev Suppor System Supp Sys dwg Lkne No Function Builbig 3 0 3-16-257C SRV INSTR N2 CHECK VALVE TO RV-3-2-071C M-351. SHT 3 DlW3-26 OPERABLE NWA 3 WA 154 2116 PASSIVE CHK-3-16-257C Drywell .U3 OPERABLE N/A 3 0 3-16-257G SRV INSTR N2 CHECK VALVE TO RV-3-2-07 G M-351. SHT 4 OAN3-35 OPERABLE NWA 3 NWA 154 2128 PASSIVE CHK-3-16-257G Dorn -U3 OPERABLE WA 3 0 3-16-257K SRY INSTR N2 CHECK VALVE TO RV-3-2-071K M4-51, SHT4 DAN3-34 OPERABLE NWA 3 NWA 154 2130 PASSIVE CHK-3-16-257K D'.eu -U3 OPERABLE NWA 2 0 3-32-502A HPSW HPSW 3AP042 DISCHARGE CHECK M-315, SHT 3 P/H-9 OPERABLE N/A 3 NWA VALVE 111 5598 PASSIVE Pumnp House OPERABLE WIA 1 0 3-32-MB KPSW HPSW3SP042 DISCHARGE CHECK M-315, SHT 3 Pr"- OPERABLE WA 3 WA VALVE II I 5600 PASSIVE CHIK-3-32-502B Pump House OPERABLE NWA 2 0 3-32-=50C HPSW HPSW 3CP042 DISCHARGE CHECK M-315. SHT 3 P/H-9 OPERABLE N/A 3 NWA VALVE 111 5602 PASSIVE CHK-3-32-502C pump Hoeus OPERABLE NWA 1 0 3-32-502=

HPSW HPSW3DP042 DISCHARGE CHECK M1415, SHT 3 PMH- OPERABLE NIA 3 NWA VALVE 111 5604 PASSIVE CHK-332-502D Pump House OPERABLE NWA 3 0 3-33-514 ESW SERVICE WATER TO ESW CROSS TiE M-315. SHT 4 T3-45 NIA NWA 3 NWA CHECK VALVE 116 5591 PASSIVE CHK.3-33-514 Turbine Bldg -U3 CLOSED NIA 3 0 3-3A-13 CRD HYDRAULIC CONTROL UNITS, TYPICAL MW.357 SHIT 2 R3-24 OPERABLE NIA 3 S OF 185 135 1100 ACTIVE U3 HCU 02-19 1 Reactor Bldg -U3 OPERABLE N/A 1 0 34-95A HPCI FEEDWATER CHECK VALVE LOOP A M-351. SHT 3 R3-30 OPEN WA -3 NWA OUTER 135 3233 PASSIVE CHK-346-96A Reactor Bldg -U3 CLOSED WA 2 0 3AS769 RHR-3A RHR PP 3AP035 SUCTION STRAINER I-361. SHT 3 Tons OPERABLE NWA 3 S 111 4100 PASSIVE 3AS769 3 Torus Prope -U3 OPERABLE NWA M-361. M-4578.1 0 38S769 RHR-38 RHR PP 3BP035 SUCTION STRAINER M-361. SHT 4 ToMu OPERABLE NWA 3 S III 4200 PASSIVE 38S769 3 Tomus Proper -U3 OPERABLE WA M-3111, M-4578.2 0 3CS769 RHR-3C RHR PP 3CP035 SUCTION STRAINER M-361. SHT 3 ToMs OPERABLE NWA I AS PASSIVE 3CS769 III TomusProper.

U3 OPERABLE WA M-361. M-4578.Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (',nrr..qnnndPrnr-P No

• RS-19-17,1 B-34 DOCUMENT NO. 0067400804)001 REVISION 2 TRAIN SOUG CI Equp UD LIM Eval reqd? PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3128196 PAGE 34 Norm slate Motive power Support System Desed Slate Con porer Supp Sys dwg System Notes EquRO DMesripCo ROB Modhw Comp Drawik No.Ioc Code Room Elev Line No Function' Buadt 1 0 3DS769 RHR-30 RHR PP 3OP035 SUCTION STRAINER M-351. SHT 4 Torus OPERABLE N/A 3 S 111 4400 PASSIVE 305769 Tows Proper -U3 OPERABLE N/A M-31. M-4578, 3 0 A03-10-0466 MSIV RHR LOOP B CHECK VALVE M-361. SHT 4 D&W3-16 CLOSED NIR 3 N/A 134 2213 PASSIVE AO-3-10-0468 ryWa' -U3 CLOSED MR 14-I-H-1-7 2 0 A03-10-46A RHR-C RHR LOOP A CHECK VALVE M-381, SHT 3 0A&43-21 CLOSED WA 3 S 134 4317 PASSIVE AG-3-10-046A DwM -1,3 OPERABLE WA M-1144-217 1 0 A03-10-460 RHR-O RHR LOOP 8 CHECK VALVE M-361. SHiT 4 DAW-16 CLOSED NIA 3 S 134 4417 PASSIVE AO-3-10.046B DrywU -U3 OPERABLE WA M-t-H-21-7 3 0 A03-14-013A CS CORE SPRAY LOOP A CHECK VALVE M-382. SHT 2 DNW3-21 CLOSED NIR 3 WA 134 2214 PASSIVE AO-3-14-013A Drywel. U3 CLOSED NIR 3 0 A03-14-0130 CS CORE SPRAY LOOP B CHECK VALVE M1-362, SHT 2 0DV3-.1 CLOSED N/R 3 N/A 134 2215 PASSIVE AO-3-14-013 Drywall -U3 CLOSED N/R 1 0 A03-23-018 HPCI HPCI DISCHARGE CHECK VALVE M-365. SKT 2 R3-30 OPERABLE WA 3 S 135 3232 PASSIVE AO-3-23-018 Reactor Bldg -U3 OPERABLE WA Vendor 16097-02 3 0 M03-10-020 RHR-C RHR LOOPS AVB X-TIE M-381, SPIT 3 R3-91 CLOSED WA 3 WA 116 4310,4408 PASSIVE MO-3-10-020 11 Reactor Blg. U3 CLOSED WA 3 0 M03-48-3213 ESW UNIT 3 ESW PUMP SLUICE GATE M-33= S-14-4 OPEN NIR 3 R 116 5632 PASSIVE MO-3-33-3213 Screen House OPEN NIR 3 0 PCV-9917A BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M.333. SHiT 2 R3-23 OPERABLE NWA 3 S BACKUP SUPPLY TO ADS 135 6105 ACTIVE PCV-3-t6A-9917A Reactor Bldg -U3 OPERABLE WA 3 0 PCV-99178 BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M-333. SHT 2 R3-23 OPERABLE WA 3 S BACKUP SUPPLY TO AIDS 135 6106 ACTIVE PCV-3-16A-9917B Reactor Bldg -U3 OPERABLE WA 3 0 PCV.9917C BACKUP INST N2 NITROGEN PRESS CTRL VALVE FOR M-333. SHT 2 R3.23 OPERABLE WA 3 S BACKUP SUPPLY TOADS 135 6107 ACTIVE PCV,3-16A-9917C Reactor Ofg -U3 OPERABLE NIA 1 0 PS03-23-006 HPCI HPCI TURBINE EXHAUST RUPTURE DISC M-366, SHT 4 R3-113 OPERABLE NIA NIA PASSIVE PSD-3-23-006 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnrr..nndrpn.', Non" R-q-19-173 088 Reactor Bldg -U3 OPERABLE WA B-35 DATE: 2128M98 DOCUMENT NO. 0067-0084-0001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 35 REVISION a SAFE SHUTDOWN EQUIPMENT UST TRAIN SOUG CI Eqip ID System Eqi Desolilon Draw No. Loo Code Norm slat Motive power SuIpport System Unft Eval reod? PIMS I1 Nots ROB MoIW CoCmp Rom Elev Desird s Comtirp"We Supp Sys dwg Line No Function SundV 1 0 SUCTION HPCI HPCI SUCTION STRAINER M-365. SHT 2 Tons OPERABLE N/A 3 S STRAINER-3HPCI 111 3220 PASSIVE Reacd Bg. -U3 OPERABLE W/A 3 0 VRV3-2-9096A SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 3 ONY3-26 OPERABLE N/A 3 8 STEAM LINE RELIEF W A 154 2105 ACTIVE VRV-3.02-9096A DryweU -U3 OPERABLE NIA M120-75-1 3 a VRV3-2-9096B SRV VACUUM RELIEF VALVE FOR MAIN M-435. SHT 3 DWV3-29 OPERABLE N/A 3 8 STEAM LINE RELIEF W B 154 2111 ACTIVE VRV-3-02-G0968 Dre -1U3 OPERABLE N/A M120-75-1 3 0 VRV3-2-9096C SRV VACUUM REUEF VALVE FOR MAIN M-351. SHIT 3 ONm3-26 OPERABLE N/A 3 $ STEAM LINE RELIEF W C 154 2117 ACTIVE VRV-3-02.9096C Orywel -U3 OPERABLE WA M120-75-1 3 VRV3-2-9096D SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHlT 3 D/W3-27 OPERABLE N/A 3 S STEAM UNE RELIEF W 0 154 2119 ACTIVE VRV-3-02-S096D OMywC -U3 OPERABLE N/A M120-75-1 3 0 VRV3-2-9096E SRV VACUUM RELIEF VALVE FOR MAIN M4151. SHT 3 DAW3-29 OPERABLE N/A 3 STEAM LINE RELIEF W E 154 2121 ACTIVE VRV-3-02-9096E OMeM -U3 OPERABLE N/A I M120-75-1 3 0 VRV3-2-9096F SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 3 DANV3-29 OPERABLE N/A 3 S STEAM LINE REUEF W F 154 2123 ACTIVE VRV-3-2-9096F Drywj -U3 OPERABLE N/A M120-75-1 3 0 VRV3-2-9096G SRV VACUUM RELIEF VALVE FOR MAIN "I-1. SWr 4 NVW3-35 OPERABLE N/A 3 8 STEAM LINE RELIEF W G 154 2129 ACTIVE VRV-3-02-9096G Drywell -U3 OPERABLE N/A M120-75-1 3 0 VRV3-2-S06H SRV VACUUM RELIEF VALVE FOR MAIN M4-351, SHT 4 DAV3-35 OPERABLE N/A 3 3 STEAM LINE RELIEF W H 154 2131 ACTIVE VRV-3-02-9096H 0rywel -U3 OPERABLE N/A I M120-75-1 3 0 VRV3-2-9096J SRV VACUUM RELIEF VALVE FOR MAIN M-351. SHT 4 DAN3-32 OPERABLE N/A 3 S STEAM LINE RELIEF W J 154 2133 ACTIVE VRV-3-02-9096J Drywae -U3 OPERABLE N/A M120-75-1 3 0 VRV3-2-90966K SRV VACUUM RELIEF VALVE FOR MAIN M-351, SHT 4 OAV3-34 OPERABLE N/A 3 S STEAM LINE RELIEF W K 154 2139 ACTIVE VRV-3-02-9096K 0Di* -U3 OPERABLE WA M120-75-1 3 0 VRV3-2-9096L SRV VACUUM RELIEF VALVE FOR MAIN M-351, SHT 4 ONG-31 OPERABLE N/A -3 a STEAM LINE RELIEF W L 154 2141 ACTIVE VRV-3-02-9096L OiywI -U3 OPERABLE N/A 1M120-75-1 1 0 VRV3-23C-140A HPCI HPCA TURBINE EXHAUST TO. TORUS M-365. SHT 2 R3-99 OPERABLE N/A i 3 N/A VACUUM RELIEF VALVE 116 3215 PASSIVE VRV-3-23C-140A Reactor Otg -U3 OPERABLE N/A Peach Bottom Atomic Power Station Unit 2 B-36 MPR-3815, Revision 3 (.nrrP.qnnndnPnr..

N -RS-12-173 DOCUMENT NO.

REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm slate Motive power Deaso state Cont power DATE: 3128/96 PAGE 36 TRAIN Unit SOUG CI Equip ID Evalrectd?

PIMS ID System Equip Desription ROB Moti Comp Drawing No.Loo Code Room ElevSystem Supp Sys *,g Line No Function BuudN 1 0 VRV3-23C-1408 HPCI HPCI TURBINE EXHAUST TO. TORUS M-365. SliT 2 R3.99 OPERABLE NIA 3 NIA VACUUM RELIEF VALVE lie 3216 PASSIVE VRV-3-23C-1408 Reactor Bldg -U3 OPERABLE NIA 1 0 VRV3-23C-140C HPCI HPCI TURBINE EXHAUST TO. TORUS M-365. SHT 2 R3-99 OPERABLE NIA 3 NWA VACUUM RELIEF VALVE 116 3217 PASSIVE VRV-3-23C-140C Reactor Bldg. U3 OPERABLE NIA 1 0 VRV3-23C-1401 HPCI HPCI TURBINE EXHAUST TO TORUS M-365. SHT 2 R3-99 OPERABLE NIA 3 NIA VACUUM RELIEF VALVE 116 3218 PASSIVE VRV-3-23C-1400 Reactor Bldg -U3 OPERABLE NIA 1 0 VRV3-23C-599BA HPCI HPCI TURBINE EXHAUST VACUUM. M4386. SHT 4 R3-13 CLOSED NIA 3 N/A RELIEF VALVE 088 3207 PASSIVE VRV-3-23C-.998A Reactor Bldg -U3 CLOSED NIA 1 0 VRV3-23C-5998B HPCI HPCI TURBINE EXHAUST VACUUM. M-366. SHT 4 R3-13 CLOSED NIA 3 NIA RELIEF VALVE 088 3208 PASSIVE VRV-3-23C-59M8 Reactor Et9 .U3 CLOSED N/A 3 1 30836 EPS-3A 480V RADWASTE AREA EL 116 MCC E-1715 T3.44 ENERGIZED 3081013 3 S 30936 (E134-W-A) 116 a0mO ACTIVE E134W-A"30836)

Twuine Bldg -U3 ENERGIZED E-11-143 3 1 30037 EPS-3B 480V REACTOR AREA EL 113S MCC E-1715 R3-23 ENERGIZED 30B1113 3 S 30837(E234-R-0) 135 a000 ACTIVE E234-R-B(30B37)

Reactor B13 5 U3 ENERGIZED E-11-144 3 I 303 EPS-3C 480V REACTOR AREA EL 135" MCC E-1717 R3-22 ENERGIZED 3081213 3 S 30838(E334-R-8) 135 8000 ACTIVE E334-R-B(3083B)

Reactor Blg -.3 ENERGIZED E-11-145 3 1 30B39 EPS-30 480 V REACTOR AREA EL 135 MCC E-1717 R3-23 ENERGIZED 3081313 3 S 30833 (E434-R-8) 135 8000 ACTIVE E434-R-B(30839)

Reactor Bldg -U3 ENERGIZED E-11-146 3 1 30659 EPS-3A 480 V TURBINE AREA EL 135 MCC E-1715 T3-171 ENERGIZED 3081014 3 S 30B59(E134-T-8) 135 o0o ACTIVE E134-T-8(30859)

Tibine Blg -U3 ENERGIZED 3 1 30860 EPS-3B 480V TURBINE AREA EL 135 1MCC E-1715 T3-171 ENERGIZED 3081114 3 S 308(E234-T-8) 135 80a0 ACTIVE E234-T.8(30B60)

Tufdte Btdg -u3 ENERGIZED 3 1 30011 EPS-38 (300111) RX BUILDING DC MOTOR E.27, SHT S R3-26 ENERGIZED 3BDOI 38D18 3 S CONTROL CENTER 135 8613 ACTIVE 3DB-R-B Reacto Bldg .U3 ENERGIZED E-11-157 3 2 30810 EPS-3A 480 VBUS E134 E-1715 R3-t16 ENERGIZED 30X30 3081012 S ACTIVE 165 Reactor Bldg -U3 ENERGIZED 308010 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (Corr'qnnnde.nr.p.

No

• RS-12-173 B-37 DOCUMENT NO. 0047-0084-D001 REVISION 2 TRIN SQUG CI Equ" ID UaiI Eval re~d? PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENTL UST DATE: 3128/96 PAGE 37 Norm state Motive power Suppo Systemn Desired State Conlr power i Supp Sys dwg System Notes Equip Description ROB Moter Camp Drawvig No.Loc Code Room Eloe Line No Function BulldOg 3 2 301012 EPS-3A BREAKER TO E134 480 V BUS (LC300I) E-1715 R3-116 CLOSED 30810 3 OR 165 B000 PASSIVE 3081012 30610 Reactor Bldg -U3 CLOSED 3 2 30B1013 EPS-3A BREAKER TO 480 V RADWASTE AREA E-1715 R3.116 CLOSED 30810 3 8R EL 11V MCC 30036 (E134-W-A) 165 8000 PASSIVE 3081013 30810 or Bldg -U3 CLOSED 3 2 3081014 EPS-3A BREAKER TO 460 V TURBINE AREA EL. E-1715 R3-116 CLOSED 30W0S 3 BR 135' MCC 30059 (E134.T-8) 165 8000 PASSIVE 3081014 30810 Reactor Bldg .U3 CLOSED 3 2 30011 EPS-38 480 V BUS E234 E-1715 R3-41 ENERGIZED 30X31 3081112 3 S 165 8000 ACTIVE 308011 Reactor Bldg -U3 ENERGIZED E-10-80 3 2 3081112 EPS.38 BREAKER TO E234 480 V BUS (LC30811)

E-1715 R3-41 CLOSED 30811 3 BR 165 8000 PASSIVE 3081112 30811 Reactor Bldg -U3 CLOSED 3 2 3081113 EPS-38 BREAKER TO 480 V REACTOR AREA EL E-1715 R3-41 CLOSED 30811 3 OR 135' MCC 30837 (E234-R4-)

165 8000 PASSIVE 3001113 30811 Reactor Bldg -U3 CLOSED 3 2 3081114 EPS-3M BREAKER TO 480 V TURBINE AREA EL E-1715 R3-41 CLOSED 30011 3 BR 135' MCC 3080 (E234-T-S) 165 8000 PASSIVE 3001114 30811 Reactor Blg -U3 CLOSED 3 2 3081121 EPS-3B SREAKER TO 480 V E2 DIG MCC OB54 E-1715 R3-41 CLOSED 30811 3 BR (E234-D.A) 165 8000 PASSIVE 3081121 30811 Reactor Bld1 -U3 CLOSED 3 2 30812 EPS-3C 480 V BUS E334 E-1717 R3-115 ENERGIZED 30X32 3081212 3 S 165 8000 ACTIVE 308012 Reactor Bldg -U3 ENERGIZED 3 2 3051212 EPS-3C BREAKER TO E334 480 V BUS (LC30812)

E-1717 R3-115 CLOSED 30812 3 OR 165 8OOO PASSIVE 3081212 30812 Reactor Bldg -U3 CLOSED 3 2 3081213 EPS-3C BREAKER TO 480 V REACTOR AREA EL E-1717 R3-115 CLOSED 30812 3 R 13'9 MCC 30838 (E334-R-8) 165 8000 PASSIVE 3001213 30812 Reactor udg -U3 CLOSED 3 2 30013 EPS-30 480 V BUS E434 E-1717 R3-41 ENERGIZED 30X33 3081312 3 S 165 8000 ACTIVE 30B013 Reactor Brdg -U3 ENERGIZED 3 2 3081312 EPS-3D BREAKER TO E434 480 V BUS (LC30913)

E-1717 R3-41 CLOSED 30B13 BR PASSIVE 30B1312 30813 165 Reactor Bldg -J3 CLOSED Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 CnrrP..nnndP.nnP Nn

• R5-1 2-173 B-38 DOCUMENT NO. 006740064.1001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EOUIPMENT LIST Norm lsto Morre p""m Desied State Conk powe DATE: 3r/8 PAGE 38 REVISION 2 TRAIN SOUG CI Equp ID Eval read? PIMS ID System Note Equip Desuition ROB Mo0W Corp Drawiev NO.Loc Code Room Eiev Siuipoi System SUPP SYS "ag Lne No FundiBon B 3 2 3081313 EPS-30 BREAKER TO 480 V REACTOR AREA EL. E-1717 R3-41 CLOSED 30813 3 511 13 MCC 30839 (E434-R-B) 165 8000 PASSIVE 3081313 30813 Reator 81d -U3 CLOSED 3 2 3081321 EPS-3D BREAKER TO 480 V E4 D/G MCC OO856 E-1717 R3.41 CLOSED 30813 3 BR (E434-O-A) 165 8000 PASSIVE E.67(1321) 30813 Reacd B4g -U3 CLOSED 3 3 30A15 EPS-3A (30A015) EMERG AUX SWITCHGEAR E-12 T3-171 ENERGIZED 30A1503 30A1503 3 $ 135 8500 ACTIVE E13 Turbine Bdg. U3 ENERGIZED 3 3 30A1501 EPS-3A E313 8KR FROM XFMR 0BX04 E-12 T3-171 CLOSED 30A1S 3 BR 135 850) ACTIVE E13(1501) 30A15 Turbine Bdg -U3 CLOSED/OPEN 20021 3 3 30A1502 EPS.3A E13A BKR (EM CLG TiR) TO XMFR E-12 T3-171 CLOSED 30A15 3 BR OAX26 135 8502 ACTIVE E13 (1502) 30A15 Turbine Bldg -U3 OPERABLE 20D21 3 3 30A1503 EPS.3A E13 BKR FROM El DIG OAG12 E-12 T3-171 OPEN OAG12 3 BR 135 8503 ACTIVE E13 (1503) 30At5 Turbine Bdg -U3 CLOSED 20D21 3 3 30A1505 EPS.3A E134 BKR TO XFMR 30X30 E-12 T3-171 CLOSED 30A15 3 OR 135 8504 ACTIVE E13 (1505) 30A15 Tunwne Bldgb U3 OPERABLE 20021 3 3 30A506 EPS-3A BREAKER TO 3A RHR PUMP 3AP35 E-12 T3.171 OPEN 3OA1S 3 BR 135 8505 ACTIVE E13 (1506) 30A15 Turbne Bd. L.U3 OPEN/CLOSED 20021 3 3 30A1507 EPS-3A BREAKER TO 3AHP SER WATER PUMP E-12 T3.171 OPEN 30A15 3 BR 3AP42 135 8506 ACTIVE E13 (1507) 30A15 Turbine BlO -U3 CLOSED 20D21 3 3 30A1508 EPS-3A E213 BKR FROM XFMR OAX04 E-12 T3-171 OPEN 30A15 3 OR 135 8507 PASSIVE E13 (1508) 30A15 TurWb Bldg -U3 OPEN 20D21 3 3 30A16 EPS.38 (30A016) EMERG AUX SWITCHGEAR E-12 T3-171 ENERGIZED 30A1606 30A1606 3 S 135 86W0 ACTIVE E23 Turbine Blg -U3 ENERGIZED 3 3 30A1601 EPS-3B E323 BKR FROM XFMR 0X04 E-12 T3-71 CLOSED 30A16 T 3 OR 135 8601 ACTIVE E23 (1601) 30A16 Turtire Bldg -U3 CLOSED/OPEN 2BD306 3 3 30A1602 EPS-38 BREAKER TO 38 RHR PUMP 38P35 E-12 T3-71 OPEN 30A16 BR ACTIVE 135 Turbine Bldg -U3 E23 (1602)30A16 OPEN/CLOSED 20022 200306 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 C.nrrP..nnndrPnrP.

Nn -R.-12-173 B-39 DATE: 3128196 PAGE 39 DOCUMENT NO. 0067008404-801 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EOUIPMENT LIST TRAIN Unit SOUGCI EquipIto Eval req~d7 PIMS to Furpotiori System Not"s ROB Moth Comp Drwing No.Lao Code Roam Eif BuldbV Norm state Motive power Deske Slate Conal powe Support System Supp Sys dwg 3 3 30A1605: EPS-3B E234 BREAKER TO XFMR 30X31 E-12 T3-71 CLOSED 30A16 3 BR 135 8603 ACTIVE E23 (1605) 30A16 TuLLtne 1g9 -U3 OPERABLE 20022 280306 3 3 30A1606 EPS-38 E23 SR FROM E2 DIG 08G12 E-12 T3-71 OPEN 0BG12 3 BR 135 8604 ACTIVE F23(1606) 30AI6 Twbine Bldg. U3 CLOSED 20022 28D306 3 3 30A1607 EPS-38 BREAKER TO 38 HP SER WATER PUMP E.12 T3-71 OPEN 30A16 3 BR 30P42 135 8806 ACTIVE E23 (1607) 30A16 Tuabie Bg. -U3 CLOSED 20D22 280306 3 3 30A1600 EPS-3S E223 BKR FROM XFMR OAX04 E-12 T3-71 OPEN 30A16 3 OR 135 8606 PASSIVE E23 (1608) 30A16 Tukwne Bldg -U3 OPEN 28D306 3 3 30A1609 EPS-38 E23A BKR (EM CLG TWR) TO XFMR E-12 T3-71 CLOSED 30A16 3 OR 08X26 135 8607 ACTIVE E23(1609) 30A16 Tubim Bldg -U3 OPERABLE 20022 280306 3 3 30A17 EPS-3C (30A017) EMERG AUX SWITCHGEAR E-12 13-170 ENERGIZED 30A1704 30A1704 3 S 135 8700 ACTIVE E33 Turbinie O8d -U3 ENERGIZED 3 3 30A1701 EPS-3C BKR E333 FROM XFMR 08X04 E-12 T3-170 CLOSED 30A17 3 BR 135 8701 ACTIVE E33 (1701) 30A17 T nbie* edg. -U3 CLOSED/OPEN 30023 3 3 30A1702 EPS-3C BREAKER TO 3C RHR PUMP 3CP35 E-12 T3-170 OPEN 30A17 3 BR 135 8702 ACTIVE E33 (1702) 30A17 Turbine Bldg -U3 OPENICLOSED 30023 3 3 30A1704 EPS-3C E33 BKR FROM E3 DIG OCGi2 E-12 T3-170 OPEN OCG12 3 BR 135 8703 ACTIVE E33 (1704) 3OA17 Tubkn Bldg -U3 CLOSED 30023 3 3 30A1705 EPS-3C E334 8CR TO XFMR 30X32 E-12 T3-170 CLOSED 30A17 3 BR 135 8704 ACTIVE E33 (1706) 30A17 Tuttn Bldg -U3 OPERABLE 30023 3 3 30A1707 EPS-3C BREAKER TO 3C HP SERV WATER E-12 T3.170 OPEN 30A11?3 BR PUMP 3CP42 135 8705 ACTIVE E33 (1707) 30A17 Tuatine Bldg -U3 CLOSED 30D23 3 3 30A1708 EPS-3C E223 8KR FROM XFMR OAX04 E-12 13-170 OPEN 30A17 3 OR -135 8706 PASSIVE E33 (1708) 30A17 l iyw -U3 OPEN 30D23 3 30A18 EPS-3D (30A018) EMERG AUX SWITCHGEAR E-12 T3-172 ENERGIZED 30A1807 135 Turbine Bklg -U3 ENERGIZED 30A1807 ACTIVE E43 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 ConrrP.mnnndp.nr.-

Nn

• R- 9-17.3 B-40 DATE: 3128196 PAGE 40 DOCUMENT NO. 0067000844.*01 REVISION 2 TRAIN SOUG CI Equip ID Una Eval reqd? PIMS IO Line No Funtcion PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EOUIPMENT LIST system Notes EqBUp DeOlCion ROB Moterw Camp Drawg No.Loc Code Room Elev BLdkng Nom state Moitiv power Desired Slate Com power Support System Supp Sys dwg 3 3 30A1801 EPS-3D E343 BKR FROM XFMR 0BX04 E-12 T3-172 CLOSED 30A18 3 BR 135 8801 ACTIVE E43 (1801) 30A18 Turbine Bldg. (U3 CLOSEDIOPEN 30D306 3 3 30A1802 EPS-30 BREAXER TO 3D RHR PUMP 3DP35 E-12 T3-172 OPEN 30A18 3 BR 135 8802 ACTIVE E43 (1802) 30A18 Turbie Bldg -U3 OPENICLOSED 30024 30D306 3 3 35A1804 EPS-3D BREAKER TO 3D HP SER WATER PUMP E-12 T3-172 OPEN 305A!8 3 BR 3DP42 135 8803 ACTIVE E43 (1804) 30A18 Twbina Bldg -U3 CLOSED 300243 3OD306 3 3 30A1805 EPS-3D E43A BKR (EM CLG 1WR) TO XFMR E-12 T3-172 CLOSED 30A18 3 BR OGX28 135 8804 ACTIVE E43 (1805) 30A18 Tuibino Bldg -U3 OPERABLE 30024 300306 3 3 30A1806 EPS-3D E434 BKR TO XFMR 30X33 E-12 T3-172 CLOSED 30A18 3 BR 135 8805 ACTIVE E43 (1806) 30A18 Tubine Bldg .U3 OPERABLE 30024 30D306 3 3 30A1807 EPS-30 E438KRFROME40DGOG12 E-12 T3-172 OPEN 00D12 3 BR 135 8806 ACTIVE E43 (1807) 30A18 Turbine Bldg -U13 CLOSED 30D24 30D306 3 3 30A1808 EPS-30 E243 BKR FROM XFMR OAXO04 E-12 T3-172 OPEN 30A1B 8807 PASSIVE E43 (1808) 3OA1e Tmbina Bldg -U3 OPEN 300306 3 4 30X133 EPS-3A PANEL 30Y33 TRANSFORMER E-29 T3-81 ENERGIZED 30859 3 S 150 8000 ACTIVE 30X133 Turbine Bldg -U3 ENERGIZED 3 4 30X135 EPS-3C PANEL 30Y35 TRANSFORMER E-29 R3.29 ENERGIZED 30838 3 S 135 8001 ACTIVE 30X135 Reactor OW9 -L13 ENERGIZED E123513. SPEC E1313 3 4 30X150 EPS-3A PANEL 30Y50 TRANSFORMER E-29 T3-171 ENERGIZED 30859 3 S 135 8000 ACTIVE 30X150 Tobine Bldg -U3 ENERGIZED 3 4 30X30 EPS-3A E134 LOAD CENTER XFMR (30X30) E-1715 R3.116 ENERGIZED 30A1505 3 S 165 8a0 ACTIVE 30X030 Reactor Bldg -13 ENERGIZED ABB Seis Rep 3 4 30X31 EPS-38 E234 LOAD CENTER XFMR (30X31) E-1715 R3-41 ENERGIZED 30A1605 3 S 165 8000 ACTIVE 30X031 Reactor Big .U3 ENERGIZED AEB Sets Rep 4 S ACTIVE 30X32 30X032 EPS-3C E334 LOAD CENTER XFMR (30X32)E-1 717 R3-115 ENERGIZED 30A1705 165 Reactor Bldg -U3 ENERGIZED ABB Sob Rep Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (,nrr.qnnnrlnnrp.n Nn , RS-1-173 B-41 DOCUMENT NO. 0007-0840001 PEACH BOTTOM ATOMIC STATION UNIT$ 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST REVISION 2 TRAIN Nonn Iate Motive powe Desired State Ctx* power DATE: 312811 PAGE 41 SOUG C4 Eq* IDl Eval Wod? PIUS ID, System Notes Eq* Desarp*ti ROB Mote Comp Drawing No.Loc Code Room Elev Support System Supp Sys deg Line No Fuxtnj Butidig 3 4 30X33 EPS-30 E434 LOAD CENTER XFMR (30X33) E-1717 R3-41 ENERGIZED 30A1806 3 S 165 8000 ACTIVE 30X033 Reactor Bdg. U3 ENERGIZED 1 ABB Sais Rep 1 5 301(2 HPCI HPCI GLAND SEAL CDSR VACUUM PUMP M-366, SHT4 R3-13 OFF 30011 3 BR 088 3211 ACTIVE 301002 30E33 Reactor Bldg -U3 ON 1 5. 30P26 HPCI HPCI AUXILIARY LUBE OIL PUMP M-368. SHT4 R3-13 OFF 300D1 -3 BR 088 ACTIVE 30P026 30E33 Reactor Bldg -U3 ON 1 5 30P28 HPCI HPCI GLAND SEAL CONDENSER COND M4366, SHT 4 R3-13 OFF 30D11 3 BR PUMP 088 3214 ACTIVE 30P028 30E33 Reacld Bdg -U3 ON 1 30P33 HPCI HPCI BOOSTER PUMP M-366, SHT 4 R3-13 OFF NIA 3 0 088 3226 ACTIVE 30P033 30P38 Reactor Bkg- -U3 OPERABLE NIA 1 5 30P38 HPCI HPCI PUMP M-366, SHT 4 R3-13 OFF NIA 3 S 088 3227 ACTIVE 30P038 Reactor Bdg. -U3 OPERABLE NIA Vendor E-,4707 5 30S37 IIPCI 1J3 HPCI TURBINE M-366, SHT 4 R3-13 OPERABLE WA 3 S 088 3205 ACTIVE 30S037 Reactor Bldg -U3 OPERABLE WA 2 5 3AP35 RHR-A RHRPUMPA M-361, SHT 3 R3-5 OFF 30A15 30A1506 3 SR 091 4103 ACTIVE 3AP035 3 Reactor Bldg -U3 OFFION MW1-H-41-2.

S-i146 1 5 38P35 RHR-8 RHR PUMP B M-361, SHIT 4 R3-6 OFF 30A16 30A1602 3 SR 091 4203 ACTIVE 38P035 3 Reator Bldg -U3 OFFION M-144-41-2, S-1146 2 5 3CP35 RHR-C RHR PUMP C M-361. SlIT 3 R3.7 OFF 30A17 30A1702 3 SR 091 4303 ACTIVE 3CPW5 Reactor Bldg -U3 OFFION M-1-H-41.2, S-1146 1 5 3OP35 RHR-O RHR PUMP D M-361, SlIT 4 R3-8 OFF 30A18 30A1802 3 SR 091 4403 ACTIVE 3DP035 Reactor Bldg -U3 OFFION M-1-H-41.2.

S-1148 2 6 3AP42 HPSW HIGH PRESSURE SERVICE WATER M-315. SHT 3 P/H-9 OFF 3OA15 330A1507 3 S PUMPA 111 5597 ACTIVE 3AP042 3 Pump Houe ON M-11-29. E8.108-1 1 6 38P42 HPSW HIGH PRESSURE SERVICE WATER M-315. SHT 3 Pf"-9 OFF 30A16 30A1607 S ACTIVE PUMP B ill Pum~p House ON 5599 3BP042 j M-1 1-29, E8-108-l B-42 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn

• R.-12-173 DOCUMENT NO. 00674=084-D001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Mod" power Desed State Cow pftw DATE: 3/28M PAGE 42 TRAIN Unit SOUG CI Equip ID Eval reld? PIMS ID FunctionNotes Equip Descrition ROD #4011wr Camp Drawing No.Loc Code Room Elev Buctidng Support System Supp Sys dwg 2 6 3CP42 HPSW HIGH PRESSURE SERVICE WATER M-315, SHT 3 P/H-S OFF 30A17 30A1707 3 S PUMP C I11 5601 ACTIVE 3CP042 PMP House ON M-11-29, ES-108-1 1 6 3DP42 HPSW HIGH PRESSURE SERVICE WATER M-315, SHT 3 PMH-9 OFF 30A18 30A1804 3 S PUMP D 11t V603 ACTIVE 3DP042 Pump House ON M-11-29. ES-100.1 3 7 A03-O1-050A MSIV A MAIN STEAM LINE INBOARD M-351. SHT 3 D/W3-18 OPEN MIA SV3-15-OSOA-1 3 S ISOLATION VALVE 134 SV3-1B.O8GA-2 2200 ACTIVE AO-3.01A,4OOA Drywell. U3 CLOSED N/A I M-1,-R-1211,2 3 7 A03-01-0808 MSIV MAIN STEAM LINE INBOARD M-351. SIT 3 OW3-118 OPEN NIA SV3-16-OSOB-1 3 S ISOLATION VALVE 134 2202 ACTIVE AO-3.UIA-OOB Orwell. U3 CLOSED WA M-1-R-12/112 3 7 A03-01-80C MSIV C MAIN STEAM LINE INBOARD I-351, SHT 4 DAW3-19 OPEN NIA SV3-16-080C-1 3 S ISOLATION VALVE 134 SV3-16-080C-2 2204 ACTIVE AO-3-1IA,00C Dryw0"" -U3 CLOSED NIA M-i-R-12/1,2 3 7 A03-01-OOD MSIV 0 MAIN STEAM LINE INBOARD M-351, SHT 4 D/N3-20 OPEN N/A SV3-16-080D-1 3 S ISOLATION VALVE 134 SV3-164000-2 2206 ACTIVE AO-3-0tA-080D Driel -Ull CLOSED NWA M-1-R-12J1.2 3 7 A03-0-14A MSIV A MAIN STEAM UNE OUTBOARD M-351, SHlT 3 R3-30 OPEN N/A SV3-16-086A-1 3 S ISOLATION VALVE 135 SV3-16408A-2 2201 ACTIVE AO-3-0IA-086A Reactor Bldg -U3 CLOSED N/A M-1.R.12/1,2 3 7 AO3-01-086 MSIV G MAIN STEAM LINE OUTBOARD M-351. SHT 3 R3-30 OPEN N/A SV3-16-086B-1 3 S ISOLATION VALVE 135 SV3-1S-08S-2 2203 ACTIVE AO-3-OIA-088B Reactor Bldg -U3 CLOSED NWA M-1-R-12/1.2 3 7 A03-01-086C MSIV C MAIN STEAM LINE OUTBOARD M-351. SHT 4 R3-30 OPEN WA SV3-16.086C-1 3 S ISOLATION VALVE 135 SV3-160066C-2 2205 ACTIVE AO-3-01A-086C Reacor Bldg -.3 CLOSED WfA M-I-R-12/t,2 3 7 A03-01-0860 MS0 D MAIN STEAM LINE OUTBOARD M-351, SHT 4 R3-30 OPEN WA SV3-16-0850-1 3 S ISOLATION VALVE 135 SV3-16-O86D-2 2207 ACTIVE AO-3-OIA-086D Reactor Bldg -U3 CLOSED NWA M-1-R-1211.2 3 7 A03-03-32A CRO SCRAM DISCHARGE VOLUME INBOARD M1-3,5 SHT I R3-22 OPEN N/A SV3-3-32A 3 S ISOLATION VENT W 135 1102 ACTIVE AO-3-03-O32A Reactor BlUg -U3 CLOSED N/A M-1-D-11-3 3 7 A03-03-32B CRD SCRAM DISCHARGE VOLUME INBOARD M-356. SHT 1 R3-23 OPEN N/A SV3-3-32B 3 S ISOLATION VENT W 135 1104 ACTIVE AO-340-3B Reactor Bldg -U3 CLOSED N/A M-1-0-11-3 3 7 3 S 1110 ACTIVE A034)3-33 AO-3-03-M3 CR0 SCRAM DISCHARGE VOLUME INBOARD ISOLATION DRAIN W M-356, SlIT 2 R3-22 OPEN 135 Reactor Bldg -U3 CLOSED NIA N/A SV3-3-33 vendor 6-9M207-52 B-43 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn

• RR-1 9-173 DATE: 312&196 PAGE 43 DOCUMENT NO. 006740084-D001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST REVISION 2 TRAIN SQUG CI Equip ID Eval reqd? PIMS ID Funticon System Notes Equip Descripion ROB MOliw Conp Loc Code Room Elev Noun state Defed State Motve powe Corn powN 54t~ System&ipp Sys dwo 3 7 A03-03-35A CRD SCRAM DISCHARGE VOLUME Ma35. SET 1 R3-26 OPEN NIA 3 S OUTBOARD ISOLATION VENT W 135 1106 ACTIVE AO-3-03-035A Reacto BJdg. U3 CLOSED NIA 1' I 3 7 AO3-03-358 CRD SCRAM DISCHARGE VOLUME M-358, SHT I R3-24 OPEN NIA SV3-3-3S8 3 S OUTBOARD ISOLATION VENT W 135 1108 ACTIVE AO-304)30B t Bldg -U3 CLOSED NfA M4-1-D-162 3 7 A0340-M CRD SCRAM DISCHARGE VOLUME M-356, SHT 2 R3-22 OPEN NIA SV3-3-38 3 S OUTBOARD ISOLATION DRAIN W 135 1112 ACTIVE AO-3-0386 Reacto Bldg -U3 CLOSED NIA 1 7 H03-23C-5512 HPCI HPCI TURBINE GOVERNOR CONTROL M-366, ST 4 R3-13 OPEN NIA 3 a VALVE 088 3204 ACTIVE HO-3.23C-5512 30S37 Reactor Bldg -U3 OPERABLE WA 1 7 H03-23C-5613 HPCI HPCI TURBINE STOP VALVE M-366, SHT 4 R3-13 OPEN NIA SV3-23A-5543 3 a 088 3203 ACTIVE HO-3-23C-5513 30S37 Reactor Bldg -U3 OPEN WA M-t-J-20 1 7 PCV3.238-50 HPCI HPCI COOLING WATER TO LO, COOLER M-366, SHT 4 R3-13 OPERABLE NWA 3 S AND GLAND SEAL CDSR 088 3213 PASSIVE PCV-3-23-050 Reactor Ofdg -U3 OPERABLE NWA 3 7 RV3-02.071A SRV A SAFETY RELIEF VALVE M-351, SHT 3 DAN3-27 CLOSED 30023 3 SR 154 2100 ACTIVE RV-3-02-071A 4 Otyweg -U3 OPEN/CLOSED M-1-R-1-12.

M.1-.R.-54, 3 7 RV3.02-071B SRV B SAFETY RELIEF VALVE M4-351. SHIT 3 D/W3.29 CLOSED 30D23 3 SR 154 2106 ACTIVE RV-3-02-071B 4 Dryweal -U3 OPENICLOSED M-I-R-1-12, M-t1-R-5-4.

3. 7 RV3.02.071C SRV C SAFETY RELIEF VALVE M-351. SHT 3 DIW3-26 CLOSED 30D23 3 SR 154 2112 ACTIVE RV-3-02-071C 4 OtyweU -U3 OPENICLOSED M-1-R-1-12, M-I-R-5-4.

3 7 RV3-02-071D SRV 0 SAFETY RELIEF VALVE M-351, SHT 3 DW3.-26 CLOSED 30023 INSTR. N2 3 SR 154 2118 ACTIVE RV-3-02-071D 4 Orywall -U3 OPENICLOSED M-1-R.1-12, M-1-R-5-4, 3 7 RV3.02-071E SRV E SAFETY RELIEF VALVE M4-351, SHT 3 D/W3-29 CLOSED 30D23 INSTR. N2 3 SR 154 2120 ACTIVE RV-3.02-071E 4 ODywoU -U3 OPENICLOSED M-1-R-1-12, M-1-R-5-4.

3 7 RV3.02.071F SRV F SAFETY RELIEF VALVE M-351, SHT 3 DMW3-29 CLOSED 30023 INSTR. N2 3 SR 154 2122 ACTIVE RV-3-02-071F 4 Dryweo -U3 OPENICLOSEO M-1-R-1-12.

M.I-R-5-4, 3 7 RV3-02.071G SRV G SAFETY RELIEF VALVE M-351 SHT 4 Dfl3-29 CLOSED 3OD23 SR ACTIVE RV-3-02-071G 4...... 9 .....154 Drywell -U3 OPENICLOSED 2124#4-1 -R-1-12, Ml .R-S-4, B-44 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 ('nrrP..qnnnriPnrP, Nn -RR-1 2-173 DATE: 3rIW PAGE 44 DOCUMENT NO, 0067.00084-000 REVISION 2 TRAIN SOUG Cl Equip IO Unit Eval rqd? PIMS ID Line No Function PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST System Notes Equip Desciption ROB Mowhe Comp Draving No.Loc Code Room Elev Buiding Norm diate Desked State Motve poer Con* power Support System Supp Sys deg 3 7 RV3-02-071H SRV H SAFETY RELIEF VALVE "I351, SHT 4 D0N3-5 CLOSED 30D23 tINSTR. N2 3 SR 154 2130 ACTIVE RV-3-02.071H 4 Ortwell -U3 OPEN/CLOSED M-1-R-1-12.

M-1-R-6-4.

3 7 RV3-02-071J SRV J SAFETY RELIEF VALVE M-351. SHT 4 DNM3-32 CLOSED 30023 INSTR. N2 3 SR 154 2132 ACTIVE RV-30271J 4 Diywen -U3 OPENICLOSED M-1-R-l-12, M-1-R-54.3 7 RV3-02-071K SRV K SAFETY RELIEF VALVE M-351, SHT 4 DN/3-34 CLOSED 30D23 3 SR 154 2134 ACTIVE RV-3-02-071K 4 Dryweal .U3 OPENICLOSED M-I-R-1-12, M-1 -R-5-4.3 7 RV3.02-071 L SRV L SAFETY RELIEF VALVE M-351, SHIT 4 DAW3-32 CLOSED 30023 INSTR N2 3 SR 154 2140 ACTIVE RV-3-02-071L 4 DrywU .U3 OPENICLOSED

.M-1-R-l-12.

M-1-R-S-4, 1 7 RV3-23-034 HPCI HPCI PUMP SUCTION HEADER RELIEF M-386. SHIT 4 R3-13 OPERABLE N/A 3 S VALVE 08 3225 PASSIVE RV-3-238-034 Reactor Bldg -U3 OPERABLE NIA DS-M-20413 2 8 CV3-10-3677A RHR-A RHR PUMP 3AP035 DISCHARGE M-361. SHT 3 R3-5 OPEN NIR 3 NIA CONTROL VALVE 091 4106 PASSIVE CV-3-10-3W77A

3.8 Reactor

B61 -U3 OPEN NJR 1 8 CV3-1D-36770 RHR-D RHR PUMP 3OP035 DISCHARGE M-361, SHT 4 R3-8 OPEN N/R 3 NIA CONTROL VALVE 091 4406 PASSIVE CV -387"7D 8 Reactor Bldg -U3 OPEN N/R 3 a M03-02-74 MSIV MAIN STEAM LINES INBOARD DRAIN M-351. SHIT 3 DNV3-19 CLOSED NIR 3 R ISOL VALVE 134 2208 PASSIVE MO-3.41A-074 Drywall -U3 CLOSED N,__1 8 M03-0B6. HPCI FEEDWATER STOP VALVE 1-351, SHT 3 DM3-29 OPEN NIR 3 R 154 3236 PASSIVE MO-3-064)29A Orwe -U3 OPEN NIR 1 8 M03-06-038A HPCI FW LONG PATH RECIRC ISOLATION M-351. SHIT 3 R3-30 CLOSED NTR 3 R VALVE 135 3234 PASSIVE MO-3.6-138A Reactor Bldg -U3 CLOSED NfR 2 8 M03-10-013A RHR-A RHR PUMP 3AP035 TORUS SUCTION M-361, SHT 3 R3-5 OPEN NIR 3 R ISOLATION W 091 4101 PASSIVE MO-3-10-013A 3 Reactor Bldg -U3 OPEN NIR I a M03-10-0138 RHR-B RHR PUMP 3OP035 TO'RUS SUCTION M-3111, SHT 4 R3-6 OPEN N/R 3 R ISOLATION W 091 4201 PASSIVE MO-3-10-0136 3 Reactor Bidg -U3 OPEN N/R 2 8 M03-10-013C RHR-C RHR PUMP 3CP035 TORUS SUCTION M-381, SHT 3 R3-7 OPEN N/R R PASSIVE MO-3-10-13C ISOLAIO IiN VW 091 Reactor Bldg -U3 OPEN 4301 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 ('nrrP.%nnndPn.nr.

Nn" Rf-19-173 B-45 DOCUMENT NO. 8011.000.4-001 REVISION 2 TRAIN SOUG CI Equip ID Unit Eval reqd? PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Motive power Desired State Coi powe DATE: 3M2M86 PAGE 45 Syste Notes EquIP DescriPtin ROB MotOer Comp Drawing No.Loc Code Room Elev Support System Supp Sys dwg Lrle No Funtion Building 1 8 M03-10-013D RHR-O RHR PUMP 3OP035 TORUS SUCTION M-361. SHT 4 R3-8 OPEN N/R 3 R ISOLATION W 091 4401 PASSIVE MO-3-10-013D Reactor Bldg -U3 OPEN N/R 2 a MO3-1 001 A RHR-A RHR PUMP 3AP035 SHUTDOWN M-361, SHT 3 R3-5 CLOSED NIR 3 R COOUNG SUCTION 091 4102 PASSIVE MO-3-10-O15A 3 Read"or Bldg -U3 CLOSED NIR 1 8 M03-1001S8 RHR-8 RHR PUMP 3SP035 SUCTION FOR M-361. SHT 4 R3-t8 CLOSED NIR 3 R SHUTDOWN CLG 116 4202 PASSIVE MO-3-10.015B 3 Reacor SM9 -U3 CLOSED NIR 2 8 M03-1O-015C RHR-C RHR PUMP 3CP035 SUCTION FOR I-361. SHT 3 R3-17 CLOSED NIR 3 R SHUTDOWN CLG 116 4302 PASSIVE MO-3-10O015C Reactor Bldg -U3 CLOSED NIR 1 M03-10-0150 RHR-O RHR PUMP 3DP035 SUCTION FOR M-361. SHT 4 R3-8 CLOSED NIR 3 R SHUTDOWN CLO 091 4402 PASSIVE MO-3-t0-015D Reactor Bldg -U3 CLOSED NJR 2 BA M03-10O16A RHR-A RHR PUMP 3AP035 MIN FLOW RECIRC M-361. SHT 3 R3-5 CLOSED 30836 3 SR BLOCK VALVE 091 4104 ACTIVE MO-3-10-016A 3 Reactor Bldg -U3 OPENICLOSED M-1021-49 B SA M03-10-0168 RHR-8 RHR PUMP 38P035 MIN FLOW RECIRC M-361. SH4T 4 R3.6 CLOSED 30837 3 SR BLOCK VALVE O91 4204 ACTIVE MO-3-10D016B 3 Reactor Bldg -U3 OPENICLOSED M-1026-49 2 GA M03-10.016C RHR-C RHR PUMP 3CP035 MIN FLOW RECiRC M-381. SHT 3 R3-7 CLOSED 30B38 3 SR BLOCK VALVE 091 4304 ACTIVE MO-3-10-016C Reactor Bldg -U3 OPENtCLOSED M-102B49 1 SA M03-100160 RHR.D RHR PUMP 3DP035 MIN FLOW RECIRC M-361. SHT 4 R3-8 CLOSED 30839 3 SR BLOCK VALVE 091 4404 ACTIVE MO-3-10-016D Read"o Bdg -U3 OPENICLOSED M-f028-49 3 B M03-10-018 RHR RHR PUMPS SUCTION FOR SHUTDOWN "-38I, SHT 3 0/W3-15 CLOSED NIR 3 R COOLING INBO ISOL 134 2212 PASSIVE MO-3-401O1B ll -U3 CLOSED NIR 2 BA M03-10-025A RHR-C RHR INNER INJECTION VALVE TO M-361. SHT 3 R3-25 CLOSED 30836 3 SR RECIRC LOOP A 135 4316 ACTIVE MO-3-10-025A 10 Reactor Bldg -U3 CLOSED/OPEN M-I-H-31-5 I 8A M03-10-0258 RHR-D RHR INNER INJECTION VALVE TO M-361. SHT 4 R3-27 CLOSED 30839 3 SR RECIRC LOOP 8 135 4416 ACTIVE MO.3-10-4258 10 Reactor Bldg -U3 CLOSEDIOPEN M-1-H-31-5 2 8 MO34lO42MA RHR-C RHR CONTAINMENT SPRAY OUTER M-361, SHT 3 R3-25 CLOSED NMR 3 R 4311 PASSIVE ISOLATION VALVE 135 Reactor B8dg -U3 CLOSED NIR MO-3-10426A Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (,nrr.pqnnnnrn.n Nn " RR-12-173 B-46 DOCUMENT NO. 0967-00084.DOO1 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3128191 PAGE 46 Nrm state Motive power Support System esd State Coam power Supp Sys dwg TRAIN Unit SOUG CI Equtp ID Eval reqcd? PIMS ID Systm Notes Equlp Desci"o ROB Mother COmp Draw"g No.Loc COde Room Elev Line No Function Buildkg 1 0 M03-10-0268 RHR-O RHR CONTAINMENT SPRAY OUTER M-361, SHT 4 R3-27 CLOSED N/R 3 R ISOLATION VALVE 135 4411 PASSIVE MO-3-1002 Reactor Bldg -U3 CLOSED N/R 2 8A M03-1O-034A RHR-C RHR LOOP A FULL FLOW TEST LINE M-3"1. SHT 3 R3-110 CLOSED 30838 3 SR BLOCK W 125 4313 ACTIVE MO-3-1.034A 9 Reactor 8ldg. U3 CLOSEDIOPEN M4-102,42 1 aA M03-10)0348 RHR-O RMR LOOP S FULL FLOW TEST UNE M-361. SflT 4 R3-105 CLOSED 30839 3 SR BLOCK VALVE 125 4413 ACTIVE MO-3-10.0348 9 Reactor 81g -U3 CLOSED/OPEN 2 BA M03-10-039A RHR-C RHR LOOP A OUTER BLOCK FOR M-361, SHT 3 R3-98 CLOSED 30838 3 SR TORUS COOLING SPRAY 116 4312 ACTIVE MO-3-10-039A 9 Reactor 8Blg -U3 CLOSEDIOPEN I &A M03-10-0398 RHR-D RHR LOOP 8 OUTER BLOCK FOR "I361, SKT 4 R3.93 CLOSED 30839 3 SR TORUS COOLING SPRAY 116 4412 ACTIVE MO-3.1.0398 9 Reactor BMlg -U3 CLOSED/OPEN M-l-H-32 2 8 M03-10-154A RKR-C RHR LOOP A RECIRC OUTER INJECTION l-381. SHT 3 R3-99 OPEN N/R 3 R VALVE 116 4314 PASSIVE MO-3-10-154A Reactor 8Mg -U3 OPEN N/R 1 8 M03-10-1548 RHR-O RHR LOOP B RECIRC OUTER INJECTION M-361, SHT 4 R3-92 OPEN NIR 3 R VALVE 116 4414 PASSIVE MO-3-10-1548 Reactor Bldg -U3 OPEN NIR 2 8 M03-0-I176 HPSW HPSW TO RHR SYSTEM OUTER M-315. SHT 3 R3-? CLOSED NIR 3 R CROSS-TIE 091 6596 PASSIVE MO-3-10-176 Reactor 8Mdg -U3 CLOSED N/R 2 IA M03.10.89A HPSW RHR HiX 3AE024 HPSW OUTLET VALVE M-315. SHT 3 R3-16 CLOSED 30836 3 SR 116 5595 ACTIVE MO-3-10.D89A Reactor Bldg -U3 CLOSED/OPEN I IA M03-10.898 HPSW RHR HX 3BE024 HPSW OUTLET VALVE M-315. SlT 3 R3-18 CLOSED 30837 3 SR 116 5594 ACTIVE MO-3-10-89B Reactor Og -U3 CLOSED/OPEN 1 2 8A M03-10419C HPSW RHR HX 3CE024 HPSW OUTLET VALVE M-315, SHT 3 R3-17 CLOSED 30838 3 SR 116 5593 ACTIVE MO-3-10-089C Reactor 8Mg -U3 OPEN/CLOSED

-M-102860 I SA M03-10-49D HPSW RHR HX 3DE024 HPSW OUTLET VALVE M-315. SHT 3 R3-19 CLOSED 30839 3 SR 116 5592 ACTIVE MO-3-104)890 Reactor Bldg .U3 OPEN/CLOSED 3 BA M03-12-015 MSIV RWCU INLET INBOARD ISOLATION M-354. SHT 2 DIW3-25 OPEN 30836 VALVE ACTIVE MO-3-12-015 1D4 Drya~ll- U3 CLOSED 6..1028-33 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 C'nrrp..nnndp.nr'.

Nn " RR-1 2-17.3 B-47 DATE: 3128/96 PAGE 47 DOCUMENT NO. 00474000844DO01 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG CI Equip ID Eval meted? PIMS I0 system Notes Equip Description ROB MoUw Comp, Drawing No.Loc Code Room Elev Noom state Molly. power Oosied Stat. Contr power Suppot System SuPP Sys dw, Lie No Function Buldig 3 BA M03-12-018 USIV RWCU INLET OUTBOARD ISOLATION M-364. Sl4T 2 R3-33 OPEN 30D11 3 SR VALVE 1s 2210 ACTIVE MO-3-12-018 Reactor BIdg -U3 CLOSED M-t026-33 I 1A M03-234014 HPCI HPCI TURBINE STEAM SUPPLY VALVE M-365. SHT 2 R3-13 CLOSED 3010111 3 SR 089 3202 ACTIVE M0-3-23-014 Reactor BM9 -U3 OPEN M-1028-42 1 8 M03-23.015 HPCI HPCI TURBINE STEAM LINE INBOARD M-365. SHT 2 0tW3-15 OPEN NIR 3 R ISOLATION VALVE 134 3200 PASSIVE MO-3-23-01S Drywall .U3 OPEN NfR I a M03-23-016 HPCI HPCI TURBINE STEAM UNE OUTBOARD M-365. SlT 2 R3-27 OPEN N/R 3 R ISOLATION VALVE 135 -3201 PASSIVE MO-3-23-018 Reactor Bldlg -U.3 OPEN NIR !I GA L403-23-017 IHPCI HPCI CONDENSATE STORAGE TANK M-aS5. SilT 2 R3-13 OPEN 30D11 3 SR SUCTION 08-3224 ACTIVE MO-3-23-017 Reactor Bldg -U3 OPENICLOSED I BA M03-23-019 HPCI HPCI DISCHARGE TO FEEDWATER LINE M-365, SHT 2 R3-30 CLOSED 30D11 3 SR A 135 3231 ACTIVE MO-3-23-019 Reactor BO -U3 OPEN M-1028-29-7 1 a M03-23-020 HPCI HPCI PUMP DISCHARGE VALVE M-365, SHT 2 R3-13 OPEN NIR -3 R 088 3229 PASSIVE M03-23-020 Reactor Bdg -U3 OPEN NIR 1 a M03-23-021 HPCI HPCI FULL FLOW TEST VALVE M-365.;SHT 2 R3-96 CLOSED NIR 3 R 116 3230 PASSIVE MO-3-23-021 Reactor Bidg -U3 CLOSED IR I BA MO3-23-025 HPCI HPCI MINIMUM FLOW VALVE M-365. SHT 2 R3-13 CLOSED 30011 3 SR 068 3228 ACTIVE MO-3-23-025 Reactor Bldg -U3 OPENICLOSED M-1-J-44-4 B GA M03-23-057 HPCI HPCI TORUS SUCTION OUTBOARD M-365. SHT 2 R3-13 CLOSED 30011 3 SR ISOLATION VALVE O88 3222 ACTIVE MO-3-23-057 Reactor Bldg -U3 OPEN M-102B-33F-1 1 BA M03-23-058 HPCI HPCI TORUS SUCTION INBOARD M-365. SHIT 2 R3-13 CLOSED 30D01 3 SR ISOLATION VALVE 058 3221 ACTIVE M0-3-23-058 Reactor Bdg -U3 OPEN M-102B-33F-1 1 MO3-23C.5244A HPCI HPCI TURBINE EXHAUST LINE VACUUM M-365, SHT 2 R3-98 OPEN NJR 3 R BREAKER VALVE 116 3219 PASSIVE MO-3-238-5445 13 Reactor Bid9 -U3 OPEN NJR 3 &A M03-30-3233A ESW & HPSW UNIT 3 A SLUICE GATE M-330 S/M.4 OPEN 00862 116 Screen House CLOSED ACTIVE MO-3-30-3233A C-316 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn -RR-12-17.1 B-48 DOCUMENT NO. 006740084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Motive power Dosired Stale Cow power DATE: 3125196 PAGE 48 TRAIN unt SOUG CI Equip ID Eval reqd? PIMS ID System Notes Equi Destipfion ROB Mother Comp Drawing No.Loc Code Room Elev Support System Supp Sys dwo Line No Function Buiding 3 &A M03-30-32338 ESW & HPSW UNIT 3 9 SLUICE GATE M-330 SIH4 OPEN 00861 3 SR 118 5630 ACTIVE MO.4-340-32338 Screen House CLOSED C-316 3 &A M03-32-3488 HPSW HPSW RETURN VALVE TO DISCHARGE M-330 DIG-2 OPEN 00854 3 SR POND 121 5611 ACTIVE MO-3-32-3486 Disel G CLOSED M-1028-125 SH5 3 8A M03-32-3803 HPSW HPSW RETURN VALVE TO EMERGENCY M=-330 DG.2 CLOSED 00856 3 SR COOLING TOW.ER 121 5613 ACTIVE MO-3-32-3803 Diesel Generator OPEN 3 8 M03-33-3344 ESW & HPSW HPSW LOOP 3A TO LOOP 38 CROSSTIE M-315. SHT 3 PM-9 CLOSED NIR 3 SR 111 5609 ACTIVE MO.3-32-3344 5 Pump Hloue CLOSED NIR 3 M M03-33-3972 ESW & HPSW U/3 SAFEGUARDS AND RBCW HX ISOL M-315, SHT 4 T3-45 OPEN N/R 3 R FROM ESW PUMP ORPO57 116 5590 PASSIVE MO-3-33-3972 Turbine Bldg -U3 OPEN N/R 3 &A M03-48-3804A ESW & HPSW U/3 HPSW SAY INLET OUTER M-330 ECT-1 CLOSED 00838 3 SR 114 5635 ACTIVE MO-3-48-3804A Emergency Coolng OPEN Towers 3 BA M03-48-38048 ESW& HPSW U/3 HPSW BAY INLET INNER M-330 ECT-l CLOSED 00897 3 SR 114 5S38 ACTIVE MO-3-48-38040 Emergency Cooling OPEN Towers 3 8B SV-9130A BACKUP INST N2 ADS BACKUP NITROGEN A HDR SUPPLY M-333. SHT 2 R3-23 DEENERGIZED 30Y35 3 SR TO DRY'AELL 135 6100 ACTIVE SV-316A-9130A Reactor Bldg. U3 ENERGIZED 3 8S SV-91308 BACKUP INST N2 ADS BACKUP NITROGEN B HDR SUPPLY M-333. SHT 2 R3-25 DEENERGIZED 00Y03 3 SR TO DRYWELL M 6101 ACTIVE SV-3-16A-9130B Reactor Skig -U3 ENERGIZED 3 8 SV3-16S080A-1 MSIV BACKUP DC SOLENOID FOR N2 SUPPLY M-351, SHT 3 DM13.18 ENERGIZED NIR 3 BR TO AO-3-.OIA.OGA 134 2216 ACTIVE SV-3-16-080A-1 AO3-O1-080A OryweU -U3 DEENERGIZED N/R 3 8 SV3-1-SBOA-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY I-351. SHlT 3 DMW3-18 ENERGIZED NIR 3 OR TO AO-3-OIA-OA 134 2217 ACTIVE SV-3-16-080A-2 A03-01-080A OrOwen -U3 0EENERGIZED N/R 3 8 SV3-16-O80B-1 MSIV BACKUP DC SOLENOID FOR N2 SUPPLY M-351, SHT 3 DN3-1 ENERGIZED NIR 3 BR TO AO-3-01A-080B 134 2228 ACTIVE SV-3-16-0808-1 A3-OI-080B ryw -U DEENERGIZED NR 3 8 SV3-16-0808-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY I-351. SHT 3 DMW3-18 ENERGIZED NIR BR ACTIVE TO AO-3-0iA4)080 A03-01-0808 134 Drwall- U3 DEENERGIZED NIR 2229 SV-3-16-080B-2 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn -RS-19-17-1 B-49 DATE: 32811 PAGE 49 DOCUMENT NO. 0067-0084.001 REVISION 2 TRAIN SOUG CI Equip ID Unit Eval reqrd? PIMS ID PEACH.BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST System Notes Equip Descripion ROB Metter Comp Drawft No.Loc Code Room Elev Buwif Nomstale, Moiv~e powr Desied state Centr poer Support System Supp Sys dag Lkne No Fiunion 3 8 SV3-16-O0BC-l MSiv BACKUP DC SOLENOID FOR N2 SUPPLY M-351. SHT 4 DIW3-19 ENERGIZED NIR 3 BR TO AO-3-01A-0ODC 134 2222 ACTIVE SV-3-164O80C-1 A03-01-080C Drywell -U3 DEENERGIZED N/R 3 8 SV3.16.0800C-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY M-351. SHT 4 D/W3-19 ENERGIZED NIR 3 OR TO AO-3A-O1OC 134 2223 ACTIVE SV-3-16-8OOC-2 A03-01-8OC 0Orrel -U3 DEENERGIZED N/R 3 8 SV3-16-0800-1 MSIV BACKUP DC SOLENOID FOR N2 SUPPLY M-35!, SHT 4 DAV3-20 ENERGIZED MIR 3 BR TOAO--IAAO1OD34 2234 ACTIVE SV-3-16-OBOD-1 AO3-O1-O8D Dwall -U3 DEENERGIZED NWR 3 8 SV3-16-060D-2 MSIV AC SOLENOID FOR NITROGEN SUPPLY M-351. SHT 4 D/W3-20 ENERGIZED N/R 3 BR TO AO-3-OIA-OS0D 134 2235 ACTIVE SV-3-16-08OD-2 A3-01-080)D DwoeU -U3 DEENERGIZED N/R IB SV3-23A-5543 HPCI HPCI TURBINE STOP VALVE REMOTE M-366 SHT 4 R3-13 CLOSED 30022 3 BR TRIP VALVE Gas ACTIVE SV.3-23A-5543 30S37 Reactor Bldg -1J3 OPEN 1 8 SV3-23C-54 HPCI HPCI TURBINE EXHAUST HDR DRAIN M-366, SlIT 4 R3-13 CLOSED 30022 3 SR POTS DRAIN VALVE 088 3209 ACTIVE SV.3-.23-054 Reactor Bidg -U3 OPEN M4-205-0-21 3 a SV3-3-32A CRD INSTR AIR SOLENOID VALVE FOR M.M35. SHT 2 R3-22 ENERGIZED N/R 3 BR AO.3-03-O32A 135 1103 ACTIVE SV-3-03-O32A A03-03-32A Reactor Bldg -U3 DEENERGIZED IfR 3 8 SV3-3-32B CRO INSTR AIR SOLENOID VALVE FOR M-356, SHT 2 R3-23 ENERGIZED NIR 3 OR AO-3-O3-032B M 1105 ACTIVE SV-3.03-32B A03-03-32B Reacor Bldg -U3 DEENERGIZED N/R 3 as SV3-3-33 CRD INSTR AIR SOLENOID VALVE FOR M-358. SHT 2 R3-22 ENERGIZED N/R 3 SR AO-3O3.3 135 tilt ACTIVE SV-3-03-033 A03-03-33 Reactor Bldg -U3 DEENERGIZED NIA 3 a SV3-3-35A CRD INSTR AIR SOLENOID VALVE FOR M-356, SIHT 2 R3-26 ENERGIZED N/R 3 R AO-3-03-035A 135 1107 ACTIVE SV-3.03-035A A03-35A Reactor Bldg -U3 DEENERGIZED N/R 3 a SV3-3-35B CRD INSTR AIR SOLENOID VALVE FOR M-356. SHT 2 R3-23 ENERGIZED N/R 3 BR AO-3-03-0358 135 1109 ACTIVE SV-3-03-035B A03-03-35B Reactor Bldg -U3 DEENERGIZED N/R 3 a SV3,3-36 CR0 INSTR AIR SOLENOID VALVE FOR M-3S6. SHIT 2 R3-22 ENERGIZED N/R 3 BR , AO-3-036 135 1113 ACTIVE SV-3-03-036 A03-3-36 Reactor Bd -U3 DEENERGIZED N/R 3 3 2219 a SV3-36-086A-1 MSIV BR ACTIVE SV-3-36B-086A-1 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn

• RR-12-173 TO AO-3-OlA-OBSA A03-01-085A M-351, SHT 3 R3-30 ENERGIZED N/R 135 Reactor Bidg. U3 DEENERGIZED N/-B-50 DOCUMENT NO. 006740084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST N sml $ae Motive power Oested State Contr power DATE:3I2fl9M PAGE 60 TRAIN tact S0UG CI Equip ID Eval req'd? PIMS ID System Notes Equip Descipuon ROD MWate Comp mwkig No.Loc Code Room Elev Support System Supp Sys dwg Lle No Function Buildirv 3 6 SV3-35-08BA-2 MSIV AC SOLENOID FOR VA SUPPLY TO M-35f, SHT 3 R3-30 ENERGIZED N/R 3 OR AO-3IA-016A 135 2220 ACTIVE SV-3-36B-086AQ A03.O1.-OSA ReaCtOr bg -U3 DEENERGIZED NJR 3 a SV3-36-086B-1 MSIV BACKJP DC SOLENOID FOR I/A SUPPLY M-351, SHT 3 R3-30 ENERGIZED NAR 3 BR TOAO-01A-0868 135 2231 ACTIVE SV-3-34W-.

A03-01.088 Reector Blqd -U3 DEENERGIZED NIR 3 8 SV3-36-0868-2 MSIV AC SOLENOID FOR VA SUPPLY TO M-351, SHT 3 R3-30 ENERGIZED NIR 3 OR AO-3-0IA-0868 135 2232 ACTIVE SV-3-366-0868-2 A03.41-068 Reactor Bldg -U3 DEENERGIZED NIR 3 8 SV3-35O-8SC-1 MSIV BACKUP DC SOLENOID FOR VA SUPPLY M-351. SHlT 4 R3-30 ENERGIZED N/R 3 SR TO AO-3-0IA-086C 135 2225 ACTIVE SV-3-360-086C-1 AO3-01-06C Reactor Bldg -U3 DEENERGIZED NIR 3 8 SV3-36-086C-2 M$yV AC SOLENOID FOR VA SUPPLY TO 0-351, SHT 4 R3-30 ENERGIZED WR 3 OR AO-3-01AO66C 135 2226 ACTIVE SV-3-358-66C-2 A03-01-066C Reactor Bldg -U3 DEENERGIZED NIR 3 8 5V3-308D-I MSIV BACKUP DC SOLENOID FOR VA SUPPLY M-351. SHT 4 R3-30 ENERGIZED NWR 3 SR TO AO-3-OIA-088D 135 2237 ACTIVE SV-3-368-M8D-1 A03-01-0860 Reactor Bldg -U3 DEENERGIZED MIR 3 8 SV3-36-086-2 MSIV AC SOLENOID FOR VA SUPPLY TO M-351. SHlT 4 R3.30 ENERGIZED NWR 3 OR AO-3-"IA-08MD 135 2238 ACTIVE SV-34.36B.O8D-2 A03-01-08WW Reac"or Bdg -U3 DEENERGIZED WIR 9 3AV060 HPSW HVAC HPSW PUMP ROOM SUPPLY FAN A M-395. SHIT 1 PIN-9 AUTO 3 SR 112 ACTIVE Pump House ON 1 9 3AV083 HPSWHVAC HPSW PUMP ROOM EXHAUST FAN A M-36, SHlT 1 P/H-9 AUTO 3 SR 112 ACTIVE Pump House ON 9 38V060' HPSW HVAC KPSW PUMP ROOM SUPPLY FAN B M-396. SHT 1 P/l-S AUTO 3 SR 112 ACTIVE Pump House ON 1 9 3BV083 HPSW HVAC HPSW PUMP ROOM EXHAUST FAN B M-396, SHT I PIH-9 AUTO 3 SR 112 ACTIVE Pump House ON 3 10 3AE55 ESW RCIC PUMP ROOM COOLING COIL A M-315, SHlT 4 R3-14 NIA NWR 3 S 91-6 5586 PASSIVE 3AE055 P80 Reactor Bldg -U3 WA N/R I M-77 Series 3 10 3AE56 ESW HPCI PUMP ROOM COOLING COIL. A M-315. SIlT 4 R3-13 N/A NWR A/3 5587 S PASSIVE 3AE056 Pao Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 CnrrA..nond~nrn Nn

• RS-19-17.3 9146 Reactor Bldg -L3 WA WR M-77 Series B-51 DATE: 3r2896 PAGE 61 DOCUMENT NO.

PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EOUIPMENT LIST REVISION 2 TRAIN SOUG CI Equip ID Evalrq(d?

PIUS tD Function Syslerm Notes Equip Oesciption ROB Morne Comp Drawing NO.Loc Code Roon Elev Norm state Motive power Suppo System Desird State Cntr power Supp Sys dwg 3 10 3AE57 ESW A CORE SPRAY ROOM COOLING COIL A M-315. SHT 4 R3-9 N/A N/R 3 S 91-6 5577 PASSIVE 3AE057 PBO Reactor BWg -U3 N/A NtIR M-77 Series 3 10 3AE58 ESW A RHR ROOM COOLING COIL A M-315, SHT 4 R3-16 N/A N/R 3 S 116 5565 PASSIVE 3AE068 PO80 Reer oBldg -U3 N/A MIR NI-?? Series 3 10 38255 ESW RCIC PUMP ROOM COOLING COIL 8 M-315. SHT 4 R3-14 N/A NIR 3 S 91-6 558s PASIVE 38E055 PBO Reactor ldg -U3 NIA NJR M-7T Series 3 10 3BE56 ESW HPCI PUMP ROOM COOLING COIL B M-315. SHT 4 R3-13 N/A N/R 3 S 9146 5588 PASSIVE 38E056 POO Reactor Bldg. U3 N/A NIR M-"7 Series 3 10 38E57 ESW A CORE SPRAY ROOM COOLING COIL 8 M-315, S4T 4 R3-9 N/A MIR 3 S 91-6 5578 PASSIVE 3BE057 P8O Reactor Bldg. U3 N/A N/R M-77 Series 3 10 3BE58 ESW A RHR ROOM COOLING COIL B M-315, SHT 4 R3-5 N/A N/R 3 S 9146 55We PASSIVE 38E058 POO Reactor Bldg -U3 N/A N/R NI-?? Series 3 10 3CE57 ESW C CORE SPRAY ROOM COOLING COIL C M-315 SHT 4 R3-11 N/A N/R 3 S 91-6 5579 PASSIVE 3CE057 PRO Reactor Bldg. U3 NWA N/R M-77 Seris 3 10 3CE58 ESW C RHR ROOM COOLING COIL C M-315. SHT 4 R3-7 N/A N/R 3 S 914-6 5567 PASSIVE 3CE068 Pao Reactor Bldg -U3 N/A N/R M-77 Series 3 10 30E57 ESW C CORE SPRAY ROOM COOUNG COIL 0 M-315. SHT 4 R3-11 N/A N/R 3 S 91-6 5580 PASSIVE 3DE057 P8O Reactor Bldg -U3 NA N/R M-T/ Sad"e 3 10 3DE58 ESW C RHR ROOM COOUNG COIL 0 M-315, SHIT 4 R3-7 N/A N/R 3 S 91-6 5568 PASSIVE 3DE058 PBO Reactor Bldg -U3 N/A N/R M-77 Sodas 3 10 3EE57 ESW B CORE SPRAY ROOM COOLING COIL E M-315. SHT 4 R3-10 N/A N/R 3 S 9146 5581 PASSIVE 3EE057 POO React" Bldg -U3 N/A N/R M-77 Series 3 10 3EE55 ESW B RHR ROOM COOLING COIL E M-315, SHT 4 R3-6 N/A N/R -3 S 91-6 5569 PASSIVE 3EE058 Pao Reactor Bldg -U3 N/A N/R 1,-77 Series 10 3FE57 S PASSIVE 3FE05?ESW Pao 8 CORE SPRAY ROOM COOLING COIL F M-315, SHT 4 R3-10 N/A 91-6 Reactor Btdg -U3 N/A N/R N/R-77 Series Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 ('nrrA.,nnndr.nr'.

No

• R'-12-173 B-52 DOCUMENT NO. Oo7.o00a4.0001 REVISION 2 TRAIN SOUG Cl Equip ID Urdl Evs reqrd? PIMS IO Lie No Function PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3/28/96 PAGE 52 System Notes Equilp Descripon ROB Mother Comp Drawing No.Loc Code Room Elev auk"dng Norm state Moie power Desired Slate Coa* power Support System Supp Sys dwg 3 10 3FE58 ESW B RHR'ROOM COOLING COIL F M-315, SHT 4 R3-6 NIA MIR 3 S 9146 5570 PASSIVE 3FE058 P8O Reactor Bldg -U3 N/A NAR M-77 Seris 3 10 3GE57 ESW 0 CORE SPRAY ROOM COOLING COIL G M-315. SHT 4 R3-12 N/A NIR 3 S 9146 5583 PASSIVE 3GE057 Pao Reactor dg. -U3 N/A NOR 3 10 3GE6O ESW D RHR ROOM COOLING COIL G M-315. SHT 4 R3-19 N/A NIR 3 S 116 5571 PASSIVE 3GE058 Pao Reactor Bldg- U3 NA N/R M-77 Series 3 10 3HE57 ESW 0 CORE SPRAY ROOM COOLING COIL H M-315. SHT 4 R3-12 N/A NAR 3 S 91.6&8 PASSIVE 3NE057 Pao Reactor Bldg -U3 N/A NIR M-77 Series 3 10 3HESS ESW 0 RHR ROOM COOLING COIL H M-315. SHT 4 R3-8 WA N/R 3 S 91-6 5572 PASSIVE 3HE058 P80 Reactor Bldg -U3 WA N/R M-77 Series 1 10 P030223-1 RPSW HVAC HPSW PUMP ROOM " LOOP SUPPLY M-396, SlIT 1 P/H- OPEN 3 S DAMPER 112 ACTIVE Pump House OPEN 1 10 P030223-2 " HPSWHVAC HPSW PUMP ROOM "B LOOP EXHAUST M.396. SHT 1 P/H-9 CLOSED 3 S DAMPER 112 ACTIVE Pump House CLOSEDOPEN 1 10 P030223-3 HPSW HVAC HPSW PUMP ROOM WA LOOP SUPPLY M-39, SHT 1 P/H-9 OPEN i 3 S DAMPER 112 ACTIVE Pump House OPEN 10 P030223-4 HPSW NVAC HPSW PUMP ROOM A" LOOP EXHAUST M-3,6. SHT I P/Hl9 CLOSED 3 S DAMPER 112 ACTIVE Pump House CLOSED/OPEN 3 14 30022 EPS-38 3PPS DISTRIBUTION PANEL 125VDC E-27. SHT I T3-81 ENERGIZED 38103 39D19 3 S 150 8000 ACTIVE 30D022 Turbine Bdg -U3 ENERGIZED

-E-18.-8.3 14 30023 EPS-3C 3PPC DISTRIBUTION PANEL 125V OC E-27. SHT I T3.81 ENERGIZED 3C003 3C019 3 S ISO 8711 ACTIVE 30DO23 Turbine BMg -U3 ENERGIZED E-16-i-3 14 30024 EPS-30 3PPD 125V DC DISTRIBUTION PANEL E-27, SHT 1 T3-81 ENERGIZED 3DD03 30019 3 S ISO 8813 ACTIVE 300024 Turbine Bdg9. U3 ENERGIZED E-16-1-8 0 3 8000 14 SR ACTIVE 3S31S 3OS315 S.P-38 BYPASSISOLATION SWITCH E-29 T3-81 ENERGIZED 30D37 150 Tudbine Bldg -U3 ENERGIZED Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrr.%nnnrnipnr.

Nn

• RS-12-173 B-53 DATE: 3128190 DOCUMENT NO. 0087410084-0001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 53 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG C1 Equi ID System Equpp Oescrqipti Drawing No. Loc Coda Norm state Motive power Support System Unit Eval reqd? PIMS ID Notes ROB Mo1ier Comnp Room Einv esiW State Contr power Supp Sys dwg Line NO FuinBM 3 14 30Y33 EPS-3A 120VAC DISTRIBUTION PANEL E-29 13-81 ENERGIZED 30X133 3 S 150 8000 ACTIVE 30Y033 TuWrni Bidg -U3 ENERGIZED 3 14 3DY35 EPS-3C 120VAC DISTRIBUTION PANEL E-29 R3-29 ENERGIZED 30X135 I 3 S 135 8001 ACTIVE 30Y035 Reactor Bldg -U3 ENERGIZED

-3 14 30Y50 EPS-38 120VAC DISTRIBUTION PANEL E-29 T3-81 ENERGIZED 30006 30037 3 S 150 30X150 8000 ACTIVE 30Y050 Turbine Bldg -U3 ENERGIZED 3 14 38o17 EPS-3B 250 VOLT FUSE BOX E-27. SHIT 1 T3-70 ENERGIZED NIA 38001 3 S 135 8609 ACTIVE 380017 Tubins Bld9 -U3 ENERGIZED E16-2-6 3 14 38D18 EPS-3B 3DPB DISTRIBUTION PANEL, 250V DC E-27, SlIT 1 T3-70 ENERGIZED 38003 3BD17 3 S 135 30017 8812 ACTIVE 38D018 TwbbBinldg

-U3 ENERGIZED 30003 E16-2-6 3 14 3BD19 EPS-38 250 VOLT FUSE BOX E-27, SHT 1 T3-70 ENERGIZED N/A 3B017 3 S 135 8810 ACTIVE 380019 Tuobe Bldg -U3 ENERGIZED E16-2-6 3 14 3C017 EPS-3C 250 VOLT FUSE BOX E-27. SHT 1 T3-70 ENERGIZED NWA 3CO01 3 S 135 8708 ACTIVE 3CO017 Turbire Bldg -U3 ENERGIZED E16-2-6 3 14 3C019 EPS-3C 250 VOLT FUSE BOX E-27. SHT 1 T3-70 ENERGIZED WIA 3CO17 3 S 135 8709 ACTIVE 3CO019 Turbine Bldg -U3 ENERGIZED EIS-2-6 3 14 30017 EPS-3D 250 VOLT FUSE BOX E-27. SHT 1 T3-70 ENERGIZED NWA 30001 3 S 135 8so0 ACTIVE 30D017 Turbite Bldg -U3 ENERGIZED E16-2-6 3 14 30019 EPS-3D 250 VOLT FUSE BOX E-27. SHT I T3-70 ENERGIZED NWA 3D017 3 S 135 8811 ACTIVE 30D019 Turbine Sdg -U3 ENERGIZED E16.2-6 3 14 300306 EPS-30 125VOC DIST. PANEL (3PPO) E-27. SHT 2 T3-172 ENERGIZED 3DO03 3 S 135 8000 ACTIVE 300306 Tutbie Bldg -U3 ENERGIZED U3 ONLY??3 15 3ADOI EPS-3A 3A BATTERY 125V DC E-27. SHT 1 T3-70 ENERGIZED 3AD03 3 S 135 8000 ACTIVE 3AD(Oi Turbine Bldg -U3 ENERGIZED E-13-34 to 37, 3 15 38001 EPS-38 W3B BATTERY 125V DC E-27. SHT 1 T3-169 ENERGIZED 3BD03-3 S 135 8608 ACTIVE 380001

• Turbine Blg -U3 ENERGIZED E-13-34 to37, Peach Bottom Atomic Power Station Unit 2 B-54 MPR-3815, Revision 3 Nn " RS-12-173 DOCUMENT NO. 0067-00084-001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3125M/PAGE 54 Norm State Moave Power Support System 0e0ired Stat. Contr powar Supp Sys dwg TRAIN SQUG CI Equp ID Eval rqd? PIMS ID System Notes ER" Desopotio ROB Mother Cornp Dfawft No.Loc Code Room Elev Lm No Funcin Bdtng 3 15 3C001 EPS-3C 3C BATTERY 125V DC E-27. SHT 1 T3-70 ENERGIZED 3C003 3 S 135 8707 ACTIVE 3CDO01 Turbine B"dg-U3 ENERGIZED E-0-34 to 37.3 15 30i01 EPS-3D "30 BATTERY 125VDC E.27. SHT 1 T3-169 ENERGIZED 3DD03 3 S 135 8809 ACTIVE 30D001 Turbine Bldg -U3 ENERGIZED t E-13-34 to 37.3 16 30037 EPS-38 STATIC INVERTER E-29 T3-74 ENERGIZED 30008 3 SR 135 30X150 6 am0 ACTIVE 300037 Turbine Bldg -U3 ENERGIZED 6280-E45 3 16 3A003 EPS-3A "3A 125V STATION BATTERY dHARGER E-27. SHT 1 T3-170 ON 30859(N)3 S 135 8000 ACTIVE 3AD003 Turbine SMc -U3 ON 20859(A)NE-102 3 18 38003 EPS-38 38CR BATTERY CHARGER 125V OC E-27. SHT 1 T3-171 ON 30880 3 S 135 8611 'ACTIVE 36DO03 " STun ldg. U3 ON NE.102 3 16 3CO03 EPS-3C 38CC BATTERY CHARGER. 125V, OC E-27. SHT 1 T3-170 ON 30838(N) 3CS456 3 S 135 30S704 8710 ACTIVE 3CD003 Tubne Bldg -U3 ON 00849(A)NE.102 3 16 30003 EPS-30 3BCD BATTERY CHARGER. 125V DC E-27, SHT I T3-172 ON 30B39(N) 30S709 3 5 135 8812 ACTIVE 3D0003 Turbine k -U3 ON 00850(A)NE-102 3 18 30C87 EPS HPCI INSTRUMENT RACK R3.15 ENERGIZED NIA 3 S 088 8000 ACTIVE 30C087 Reactor Bldg -U3 ENERGIZED NIA M-1-EE-180.

M-580 3 18 30C95 EPS RCIC INSTRUMENT RACK R3-15 OPERABLE WA 3 S O88 8000 ACTIVE 30C095 Reactor Bldg -U3 OPERABLE NWA M1.EE-168 3 18 3AC65 EPS RPS INSTRUMENT RACK R3.40 OPERABLE WA 3 S 165 8am0 ACTIVE 3AC065 Reactor 1g0 -U3 OPERABLE WVA M.-1EE-168.

M-1-EE-170 3 18 3AC91 EPS JET PUMP INST RACK A R3"81 OPERABLE NIA 3 S 135 8000 ACTIVE 3AC091 Reactor Bl- U3 OPERABLE WA 3 18 3BC65 EPS RPS INSTRUMENT RACK R3-29 OPERABLE NIA 3 S 135 8000 ACTIVE 3BC065 ReactorB U3 OPERABLE WUA M-1-EE-168.

M-1-EE-170 3 18 3BC91 EPS JET PUMP INST RACK 6 R3-29 OPERABLE NWA 3 S 135 8amO ACTIVE 38C09i Reactor Weg -U3 OPERABLE WA Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnrrp.qnnndnpnr'.

Nn ' RS-19-173 B-55 DOCUMENT NO. 0067-0005640001 REVISION 2 TRAIN SQUG CI Equip ID Ud Eval re'd? PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST I NOm= sMte MMw powerI Desgred Slate Cony power DATE: 3=M61s PAGE 55 System Notes Equip Descron ROB Mote Comp Drawing No.Lac Code Room Elev Sup~port System Supp Sirs dw Lira No Furxbon Building I16 0PS30224-1 HPSW HVAC HPSW PUMP ROOM I SUPPLY PLENUM M-396, SHT I PIN-9 OPERABLE 3S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE Pump Houn OPERABLE 1 18 DPS30224-2 HPSW HVAC HPSW PUMP ROOM I EXHAUST PLENUM M-396, SHT 1 PIH-9 OPERABLE 3 S DIFFERENTIAL PRESSURE SENSOR 112 ACTIVE PuMwp H OPERABLE 1 8 0PI30224.3 HPSW HVAC HPSW PUMP ROOM I SUPPLY PLENUM M-396, SHT I P/H-9 OPERABLE 3 S DIFFERENTIAL PRESSURE SENSOR 112 ACTWE Pump House OPERABLE 1 18 DPS30224-4 HPSW HVAC HPSW PUMP ROOM I EXHAUST PLENUM M.396, SHT 1 PIN-9 OPERABLE 3 S DIFFERENTIAL PRESSURE SENSOR 112 ACTVE Pump House OPERABLE 1 1t LS3 PROC MON INSTM SUPPRESSION POOL LIMIT SWITCH AY M-385, SHT 2 OPERABLE 3 OR VALVE M03-13-041 ACTIVE M03-13-041 OPERABLE 1 1 LS3 PROC MON INSTM SUPPRESSION POOL LIMIT SWITCH AY M-365, SHT 2 OPERABLE 3 BR VALVE MO3-13-039 ACTIVE M03-13-039 OPERABLE I 18 LS3-23-57 PROC MON INSTM SUPPRESSION POOL LIMIT SWITCH ON M-35, SHT 2 OPERABLE 3 OR VALVE 1803-23-57 ACTIVE M03-23-57 OPERABLE I 18 LS3-23-58 PROC MON INSTM SUPPRESSION POOL LIMIT SWITCH ON M459. SHT 2 OPERABLE 3 BR VALVE M03-23-58 ACTIVE M03-23-"8 OPERABLE 1 16 LS3-23-74 PROC MON INSTM CONDENSATE STORAGE TANK LEVEL M-309. SHT 2 T3-55 OPERABLE 3 SR SWITCH 135 ACTIVE Tufbi BIdg -U3 OPERABLE 1 18 LS3-23-75 PROC MON INSTM CONDENSATE STORAGE TANK LEVEL M-309. SHT 2 T3-55 OPERABLE 3 SR SWITCH 135 ACTIVE Turirne Blg -U3 OPERABLE " I Is LS3-23-91A PROC MON INSTM SUPPRESSION POOL LEVEL SWVTCH M-359, SHT 2 R3-11 OPERABLE 3 SR 91-6 ACTIVE Reactor Blg -U3 OPERABLE I 18 LS3-23-918 PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-359. SHT 2 R3-11 OPERABLE -3 SR 91-6 ACTIVE Reactor Bldg -U3 OPERABLE 3 1i LT-9027A PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-365. SHT 2 C-Corn Spray OPERABLE 30Y33 3 7129 s ACTIVE LT-9027A Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rorrP.nnndp.nr.c Nn " RR-19-173 FOR LR-9027 091 Rea"to Bldg.- U3 OPERABLE B-56 DOCUMENT NO. 006740084.00012 TRAIN SOUG CC Equip ID unit Eva reqid? PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Motive power Desired State Conm power DATE: 3roM PAGE 56 System Notes Equi Desciption ROB MotlOComp DrMeg No.Loc Code Room Elev SPoft SystemSys "g Line No Functio Buitd 3 18 LT-90278 PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-365. SHT 2 C-Cor Spray OPERABLE 30YSO 3 S FOR LI-9027 091 7127 ACTIVE LT.9027B Reactor BOkg -U3 OPERABLE 3 18 LT-9123A PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M365, SHT 2 R3.1- OPERABLE 3OY3S 3 S FOR LI-9123A 091 7128 ACTIVE LT4123A Reactor Bldg -U3 OPERABLE 3 LT-91238 PROC MON INSTM TORUS WATER LEVEL TRANSMITTER M-385. SHT 2 R24 OPERABLE 30Y50 3 S FOR LR-S1238 091 7130 ACTIVE LT-91238 Reactor Blg -U3 OPERABLE 3 18 LT-9453 PROC MON INSTM CONDENSATE STORAGE TANK LEVEL M-309. SHT 2 R3-20 OPERABLE 3OY50 3 WA TRANSMIrTER FOR LI-9453 116 7132 ACTIVE LT-9453 LeIe NHR. Transfer Reactor Bldg -U3 OPERABLE function will be picked Ck Ioc u.p 18 LT3.13-170 PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-365, SHT 2 13-17 OPERABLE 3 SR FOR RCIC INITIATION 116 ACTIVE Tudrine Bldg -U3 OPERABLE 1 18 LT3-13-171 PROC MON INSTM SUPPRESSION POOL LEVEL SWITCH M-365. SHT 2 T3-17 OPERABLE 3 SR FOR RCIC INITIATION 116 ACTIVE Turbine Bldg -U3 OPERABLE 3 18 LT3-2-3-61 PROC MON INSTM REACT VESSEL WATER LEVEL M-352. SHT 3 R3-40 OPERABLE 30Y33 3 B TRANSMITTER FOR U3-2-86 165 7131 ACTIVE LT-3-02-3-061 3AC085 Reactor Bldg -U3 OPERABLE 1 18 PS30224-1 HPSW HVAC HPSW PUMP ROOM "A" LOOP M-396, SHT 1 P/H-9 OPERABLE 3 S PRESSURE SWITCH 112 ACTIVE Pump House OPERABLE I 18 PS30224-2 HPSW HVAC HPSWPUMP ROOM "B LOOP, M-398. SHT I P/1-9 OPERABLE 3 S PRESSURE SWITCH 112 ACTIVE Punp Hausa OPERABLE 3 18 PT-35088 PROC MON INSTM CONTAINMENT ATMOS DRYWELL M-367. SHT 2 R3-53 OPERABLE 30Y35 3 S PRESS TRANSMITTER FOR PR-3508 195 30D23 7139 ACTIVE PT-3508B Reactor Bldg -U3 OPERABLE 3 18 PT-5805 PROC MON INSTM DRYWELL PRESSURE TRANSMITTER M-367. SHT 2 R3-21 OPERABLE 30Y50 3 S FOR PR-5805 116 7140 ACTIVE PT-585 Reacor Bldg.- U3 OPERABLE 3 AI PT-9102A PROC MON INSTM DRYWELL PRESSURE TRANSMITTER M-381. SHT 3 R3-40 OPERABLE 30Y35 3 BFOR PR-910A 165 7136 ACTIVE PT-9102A 3AC065 React Bldg -1U3 OPERABLE P 3 18 PT-9102C PROC MON INSTM DRYWELL PRESSURE TRANSM'nfTER M-361, SHT 3 R3-40 OPERABLE 30Y35 B ACTIVE FOR PR-9102A 3ACO6S 165 Reactor Bid -U3 OPERABLE PT-9102C Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnrrn.qnnndP.nr.A No

• RS-19-173 B-57 DOCUMENT NO. 00674-00(4-D(01 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EMUIPMENT LIST DATE: 3121196 PAGE 57 Norm state Motve power Suppwt System Desred State Corer power SUP SYS d*g TRAIN Urd SOUG CI Eqp ID Eval recrd? PRAS ID System NotesDescralon ROB Mother Comp Drawng Mo.Lee Code Room Elev Line No Function Buid 3 I PT3-2.3-404A PROC MON INSTm REACTOR PRESSURE TRANSMITTER M-352. SHT 3 R3-40 OPERABLE 30Y35 3 a FOR PR3-2--404A 165 713? ACTIVE PT-3.02.3-404A 3AC065 Reactor 8Idg -U3 OPERABLE 3 18 PT3-2.3-404B PROC MON INSTM REACTOR PRESSURE TRANSMITTER M-352. SHT 4 R3-29 OPERABLE 00Y03 3 B FOR PR3-2-3-4048 135 7138 ACTIVE PT-3-02-3-404B 3BC065 Reactor Bldg -U3 OPERABLE 3 18 PT34-53A PROC MON INSTM REACTOR WIDE RANGE PRESSURE M-352. SHT 3 R3-40 OPERABLE 30Y50 3 a TRANSMITTER FOR P*34-90A 165 7133 ACTIVE PT-.3.0-..3A 3AC65 Reactor Bd. -U3 OPERABLE 3 18 PT3-6-38 PROC MON INSTM REACTOR WIDE RANGE PRESSURE M-52, SHT 4 R3-29 OPERABLE 30Y50 3 B TRANSMITTER FOR P134-908 135 7134 ACTIVE PT-386-053B 38C65 Reactor Bldg -U3 OPERABLE 1 18 TIC30223 HPSW IVAC HPSW PUMP ROOM EXHAUST TEMP M4396, SHT 1 PIH-9 OPERABLE 3S INDICATING CONTROLLER 112 ACTIVE Pump House OPERABLE i18 TC30224-1 HPSW HVAC HPSW PUMP ROOM `A LOOP TEMP M-396. SHT I P9-9 OPERABLE 3S INDICATING CONTROLLER 112 ACTIVE Pump House OPERABLE I 18 TIC30224-2 HPSW HVAC HPSW PUMP ROOM "8" LOOP TEMP M-396. SHT I PIN-9 OPERABLE 3 S INDICATING CONTROLLER 112 ACTIVE Pump House OPERABLE I I5 TT30223 HPSW`HVAC HPSW PUMP ROOM EXHAUST M396. SHT 1 PMH-9 OPERABLE S TEMPERATURE TRANSMITTER 112 ACTIVE Pump House OPERABLE 3 20 309324 EPS M03-23,015 MOTOR CONTROL POWER T3-67 OPERABLE NIA 3 S TRANSFER SWITCH 135 8000 ACTIVE 30B324 Turbine Bldg -U3 OPERABLE N/A U3 ONLY??3 20 30C003 EPS REACTOR AND CONTAINMENT COOLING T3-100 OPERABLE WA 3 8 AND ISOLATION 165 8000 ACTIVE 30C003 Turbhe Bldg. U3 OPERABLE N/A 3 20 30C004C EPS RCIC VERTICAL BOARD 1T3-100 OPERABLE WA 3 S 165 8000 ACTIVE 30C004C Turbine Bdg -U3 OPERABLE WA 3 20 30C005A EPS REACTOR MANUAL CONTROL PANEL 1T3-100 OPERABLE NIA 3 S 165 8000 ACTIVE 30C005A Turbkne Bldg -U3 OPERABLE NWA 3 20 30C006C EPS MAIN CONTROL ROOM CONSOLE -"3-100 OPERABLE NIA B ACTIVE 3OC006C Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 CnrmP.nnndrnnP.

Nn

• R.-12-173

-30COOSA 168 Turtn. Bldg. U3 OPERABLE WA B-58 DATE: 312896 DOCUMENT NO. 006740034-4001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 6 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG CI Equip ID System Equip Descalpi-Drawing Nck Loc Code Norm ate Motive power support System unit Eval reqd' PIMS ID Notes ROB Mother Comp Room Elev DesireCor w Supp Sy dw Line No Function ou" 3 20 30C012 EPS PLANT SERVICES CONSOLE T3-100 OPERABLE NIA 3 S 165 sa00 ACTIVE 30C012 Turbine Bldg. U3 OPERABLE NIA !E-17-4212 3 20 30C124 EPS CRT AND RFPT TEST PANEL 13-100 OPERABLE NIA 3 S 165 8000 ACTIVE 30C124 Tulbine Bldg -U3 OPERABLE NIA 1 20 30C139 HPSW HVAC HPSW PUMP ROOM LOCAL CONTROL E202 PfI-I ENERGIZED 88l 3S PANEL 112 ACTIVE Purmp House ENERGIZED 3 20 30C32 EPS ENGINEERING SUB SYSTEM I RELAY T3-81 OPERABLE WA 3 S CABINET 150 8000 ACTIVE 30C032 Tuibine Bldg -U3 OPERABLE NWA S-1198/1-3.

M-1-EE-241 3 20 30C33 EPS ENGINEERING SUB SYSTEM II RELAY T3-81 OPERABLE NIA T 3 S CABINET ISO 6000 ACTIVE 30C=33 Tubine ldg -U3 OPERABLE NIA S-119811-3.

M-i-EE-241 3 20 30C34 EPS RCIC RELAY PANEL T3-81 OPERABLE NWA 3 S 150 8000 ACTIVE 30C034 Turbine Bldg -U3 OPERABLE NWA S-1 198/11-3, M-1-EE-84-24 3 20 30C39 EPS HPCI RELAY CABINET T3-81 OPERABLE NWA 3 S 150 60O0 ACTIVE 30C039 Turbine Bldg -U3 OPERABLE NWA S-1198M13, M-1-EE-98 3 20 30C722A EPS ACCIDENT MONITORING T3-81 OPERABLE WA 3 S INSTRUMENTATION PANEL ISO 6000 ACTIVE 30C722A Turbine BSlg -U3 OPERABLE WA S-119811-3.

M-1-EE-405 3 20 30C722B EPS ACCIDENT MONITORING

-T3-81 OPERABLE NIA 3 S INSTRUMENTATION PANEL ISO 8000 ACTIVE 30C7220 Tuibine Bldg -U3 OPERABLE NWA S-1198/-3, M-1-EE-406 3 20 30041 EPS HPCI GLAND SEAL CONDENSER VACUUM -R3-13 OPERABLE WA 3 S PUMP STARTER 08 8000 ACTIVE 300041 React BkIg -U3 OPERABLE NA 3 20 30D42 EPS HPCI GLAND SEAL CONDENSER VACUUM .R3-13 OPERABLE NWA 3 a PUMP STARTER 086 60(0 ACTIVE 300042 30D41 Reactor Bldg -LU3 OPERABLE NWA 3 20 30043 EPS HPCI AUX LUBE OIL PUMP STARTER R3-13 OPERABLE NWA 3 a 088 8000 ACTIVE 200043 30D41 Reactor Bldg -U3 OPERABLE WA U2 ONLY??.1 20 30S37-PANEL HPCI 13W HPCI TURBINE R3-13 OPERABLE NWA 3 S 088 ACTIVE 3DS037 -PANEL Reactor Mdg -U3 OPERABLE N/A M-368 Peach Bottom Atomic Power Station Unit 2 B-59 MPR-3815, Revision 3 fnrrm.nnndr.nr.p Nn " Rq-I2-173 DATE: 3/26196 DOCUMENT NO. 0067-00084-O001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 69 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG CI Equip ID System Equip Description Drwkng NO. Loc Code Nom State Motive power support System Unit Eval req'd? PIMS M NOWe ROB Mother Comp Room EOev Deird stae Contr power SupP Sys d"g 1ne No Function Bu g 3 20 3AC265 EPS RESERVOIR FLOW PUMP BAY MO-3804A ECT-1 OPERABLE NWA 3 S 114 000 ACTIVE 3AC25 Emergecy Cooling OPERABLE IVA Tower 62A-0-11749-3 3 20 3AC272 EPS HPCI STEAM LEAK DETECTION CABINET T3-100 OPERABLE NWA 3 S 165 8m ACTIVE 3AC272 Turbine Bldg -U3 OPERABLE WA 3 20 3BC265 EPS RESERVOIR FLOW PUMP BAY MO-3804B ECT-1 OPERABLE NJA 3 S 114 3000 ACTIVE 3SC265 Emergency Cooling OPERABLE NWA Tower 62A-O-117-49-3 3 20 3SC272 EPS HPCI STEAM LEAK DETECTION CABINET -T3-100 OPERABLE NWA 3 S 165 3000 ACTIVE 3BC272 Turbine Bldg -U3 OPERABLE WIA M241-10 3 20 LJ-9027 PROC MON INSTM TORUS WATER LEVEL M-385, SHT 2 T3-100 OPERABLE 30Y33 LT-9027B 3 BR 165 7101 ACTIVE LI-027 30C003 Turbine ldg -13 OPERABLE 3 20 LI-9123A -- PROC MON INSTM WIDE RANGE SUPPRESSION POOL M-365, SHT 2 T3-100 OPERABLE 30Y35 LT-9123A 3 BR LEVEL INDICATOR 165 7100 ACTIVE LI-9123A 30C003 Turbine Bldg -U3 OPERABLE 3 20 L1-9453 PROC MON INSTM CST LEVEL INDICATOR M-309. SHT 2 T3-100 OPERABLE 30Y50 LT-9453 3 BR 165 7102 ACTIVE LI-9453 30C004C Turbine Btdg -U3 OPERABLE 3 20 1.3-2-3-113 PROC MON INSTM REACTOR WATER LEVEL M-352, SHT 6 T3-100 OPERABLE 30Y50 LT3-2-3-113 3 SR 165 7103 ACTIVE LI-3-02-3-113 30C003 Turbine Bldg -U3 OPERABLE 3 20 L13-2-3-85A PROC MON INSTM REACTOR VESSEL HIGH WATER M-352. SHT 6 T3-100 OPERABLE 30Y35 LT3-2-3-72A OR 73A 3 BR 165 7104 ACTIVE 1.13-023-109A 30COOSA Turbine Bldg -U3 OPERABLE 3 20 U3-2-3-858 PROC MON INSTM REACTOR VESSEL HIGH WATER M-352 SHT 6 T3-100 OPERABLE 00Y03 LT3-2-3-72B OR 736 3 BR 165 7105 ACTIVE U-.3-02-3-085B 30C006A Turbie Bldg -U3 OPERABLE 3 20 L13-2-3-8B PROC MON INSTM REACTOR VESSEL H4GH WATER M-35Z SHT 3 13-100 OPERABLE 30Y33 LT3-2-3-61 (C65A)3 BR 165 7106 ACTIVE U-3-02.3-086 3003 Tuwine ldg -U3 OPERABLE 3 20 LR-9027 PROC MON INSTM TORUS WATER LEVEL RECORDER M-365, SHT 2 T3.100 OPERABLE 30Y33 LT-9027A 3 BR 165 7107 ACTIVE LR-9027 30C003 Turhe BSlg -U3 OPERABLE 3 20 LR-9123B PROC MON INSTM TORUS WATER LEVEL/TEMPERATURE M-365, SHT 2 T3-100 OPERABLE 00Y03 LT-9123B 3 BR RECORDER 165 7106 ACTIVE LRrTR-9123B 30C003 Turbine Bldg -U3 OPERABLE Peach Bottom Atomic Power Station Unit 2 B-60 MPR-3815, Revision 3 (nrr ..qnnndl nrP. Nn

• RS-19-173 DOCUMENT NO. 006-4)0084-DI REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Mowe powe Desired State Canm power DATE: 3128M16 PAGE 60 TRAIN Unit SOUG CI Equip ID Eva8 read? PIMS ID System Notes Equip Description ROB Moter Camp DrBwbg No.Loc Code Rowm EOev Support System Supp Sys dWg Line No Functim Bikt 3 20 LR3-2-3-110A PROC MON INSTM REACTOR WATER LEVEL WIDE RANGE M-352. SHT 6 T3-100 OPERABLE 3OY35 LT3-2-3-72C OR 73C 3 BR 165 7109 ACTIVE LR-3.02-3-tt0A 30CO04C Turbine 8idg -U3 OPERABLE 3 20 LR3-2-3-1108 PROC MON INSTM REACTOR WATER LEVEL WIDE RANGE M-352, SHT 6 T3-100 OPERABLE 00Y03 LT3-2-3-720 OR 730 3 BR 165 7110 ACTIVE LR-3-02-3-110B 30C0O3 Turbine Bldg -U3 OPERABLE 3 20 P134--0A PROC MON INSTM REACTOR WIDE RANGE PRESS IN0 M-35 ST 3 T3-100 OPERABLE 30YS0 PT3,-53A 3 BR 165 7111 ACTIVE PI-3-B.090A 30COOSA Turbine 81dg. -U3 OPERABLE 3 20 Pi3-6-SOB PROC MON INSTM REACTOR WIDE RANGE PRESS IND M-352. SHT 4 T3-100 OPERABLE 30YSO PT3-6536 3 BR 165 7112 ACTIVE PI-3-06-090B 30C006C Tutrine Bldg. U3 OPERABLE 3 20 PR-3508 PROC MON INSTM CONTAIN ATMOS DRYWELL PRESS M-367. SHT 2 T3-100 OPERABLE 30023 PT-35080 3 BR 165 30Y35 7113 ACTIVE PR-3508 30CO03 Turbine Bldg -U3 OPERABLE 3 20 PR-5805 PROC MON INSTM CONTAINMENT PRESSURE M-367, SHT 2 T3-100 OPERABLE 3OY50 PT-5805 3 BR 165 7114 ACTIVE PR-50O 30CO03 Turbine Bldg -U3 OPERABLE 3 20 PR-9102A PROC MON INSTM 0RYWELL PRESSURE RECORDER M-361. SHT 3 T3-100 OPERABLE OY3SS I PT-9102A 3 BR 165 PT-9102C 7115 ACTIVE PR-9102A 30CO03 Tutne BIdg -U3 OPERABLE 3 20 PRP-2-3-404A PROC MON INSTM REACTOR PRESSiRPV WATER LEVEL M-352. SHT 3 T3-100 OPERABLE 30Y35 PT3-2-3-404A 3 BR 165 7116 ACTIVE PRILR-3-02-3-404A 30C004C Turbine Bg9 -U3 OPERABLE 3 20 PR3-2-.3404B PROC MON INSTM REACTOR PRESSURE M-352, SHIT 4 T3-100 OPERABLE 00Y03 PT3-2-3-4048 3 BR 165 7117 ACTIVE PR-3-02-3-404B 30C0X3 Turbine Bl9 -U3 OPERABLE 3 20 PR3-4-96 PROC MON INSTM REACTOR LEVEIJSTM FLOW RATIO M-352= SHT 6 T3-100 OPERABLE 30YSO PT34.105 3 BR 165 7118 ACTIVE PRAR-3-06-096 30COOSA Tune Bldg -U3 OPERABLE 3 20 TIS-3-2-71A PROC MON LISTM TORUS WATER TEMPERATURE

"-61. SHT 4 T"3-10O OPERABLE 30Y35 I TE3-2-71A1 THRU 3 OR INDICATING SWITCH 165 TE3-2-71N1 7123 ACTIVE TIS-3-02-071A 30C124 Tuwine Btg -U3 OPERABLE 3 20 TIS-3-2-71B PROC MON INSTM TORUS WATER TEMPERATURE M-361. SIT 3 T3-100 OPERABLE 00Y03 I TE3-2-71A2 THRU 3 BR INDICATING SWITCH 1651I TE3-2-71N2 7124 ACTIVE TIS-3-02-0718 30C124 Turbine Bldg -U3 OPERABLE 1 21 30EI05 HPCI HPCI TURD LUBE OIL COOLER (23-2) M-366, S-IT 4 R3-13 OPERABLE N/A a PASSIVE 30EIGS 088 Reactor Bldg -U3 6116/94 OPERABLE WiA Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnorr..nnndP.nr.P No

• Rq-12-173

-Vendor Dwg 210M806A3 B-61 ATE: W DOCUMENT NO. 0067-0084DOOO PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 61 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SQUG CI Eqdp to System DescrMon Drawbn Noý Loc Code Norm sa Motive power Support System Urd Eval rectd? PIMS I0 Notes ROB Mother Comp Room lev Stte Coort powe Supp Sys dwg Lkl No Fuction Building 1 21 30E33 HPCI HPCI GLAND SEAL CONDENSER (23-2) M-36S. SHT 4 R3.13 OPERABLE NWA 3 S 008 3210 PASSIVE 30E033 Reactor Bdg. -U3 OPERABLE WA 1 21 30T10 RCICIHPCI CONDENSATE STORAGE TANK M-309. SHT 2 aImB OPERABLE MIA 3 NIA 116 3115, 3223 PASSIVE 301010 A Cooling Tower OPERABLE NIA 3 21 3AE124 ESW 3A" RHR PUMP SEAL COOLER M-315. SHT 4 R3-5 NWA NIR 3 B 091 5573 PASSIVE 3AE124 3AP35 Reactor BI9 -U3 NIA NIR 2 21 3AE24 RHR-C RHR HEAT EXCHANGER A M-3"1, SHT 3 R3-16 WA NIA 3 S 091 4307. 5605 PASSIVE 3AE024 Reator Bldkg. U3 OPERABLE NWA 3 21 3AS377 BACKUP INST N2 BACK-UP N2 SUPPLY TO ADS RVS M-333. SHT 2 R3-23 OPERABLE NIA 3 S 135 6102. PASSIVE 3AS377 Reactor 8Bdg .U3 OPERABLE NWA M-1786-S 3 21 3AT540 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 3 OAN3-27 OPERABLE N/A 3 S RV-71A 154 2102 PASSIVE 3AT540 Or, ell -U3 OPERABLE NWA M-=27 3 21 3AT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-.351, SHT 3 DJW3-27 OPERABLE NWA INSTR. N2 3 S RV-71A 154 2101 PASSIVE 3AT545 Onyweg -U3 OPERABLE NWA M-C"-.M-33 3 21 3BE124 ESW 3BRHR PUMP SEAL COOLER M-315. SHT4 R3-6 NWA NJR 3 B 091 5574 PASSIVE 38E124 38P35 Reactor Bid9 -U3 NWA NfR 1 21 38E24 RHR-O RHR HEAT EXCHANGER B M-361. SHT 4 R3-18 NIA NWA 3 S 091 4409. 5607 PASSIVE 3BE024 Reactor Bldg -U3 OPERABLE WA M-1-H-4-7.

M-14-12-5.

3 21 38S377 BACKUP INST N2 BACK-UP N2 SUPPLY TO ADS RVS M.333. SHT 2 R3-23 OPERABLE NWA 3 S 135 6103 PASSIVE 3BS377 Reactor Bidg. U3 OPERABLE WIA M-1788-5 3 21 38T540 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351, SHT 3 DWM3-27 OPERABLE WA 3 3 RV-71B 154 2108 PASSIVE 38T540 Oiwell -U3 OPERABLE NWA M-3237 3 21 3BT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 3 D0m3-27 OPERABLE NWA I INSTR. N2 3 S RV-718 154 2107 PASSIVE 3BT545 (rywI -U3 OPERABLE AM-333 3 21 3CE124 ESW "3C"RHR PUMP SEAL COOLER M-315, SHT 4 R3-7 NWA NIR 3 B 091 5575 PASSIVE 3CE124 3CP35 Reactor 1dg -U3 NWA N/R Peach Bottom Atomic Power Station Unit 2 B-62 MPR-3815, Revision 3 rnrrp.qnnnrp.nr.

Nn

• RS-12-173 DATE: 3/28198 DOCUMENT NO. 006740084-1-00 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 62 REVISION 2 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SQUG CI Equip 10 System Equip Desmi0 Drawlng No. Loc Code Nonm state Momive power SuPPW System Urd Eval roqrd? PIMS ID Notes ROB MoWl Comp Room Elev D W State Conir power Supp Sys deg Line No Function Builda 2 21 3CE24 RHR-C RHR HEAT EXCHANGER C M-361. SHT 3 R3-17 OPERABLE NIA 3 S 091 4306. 5606 PASSIVE 3CE024 Reactor Bldg -U3 OPERABLE N/A M1-1-4-4-7, M1"1-112-5.

3 21 3CS377 BACKUP INST N42 SACK-UP N2 SUPPLY TO ADS RVS =-333. SHT 2 R3-23 OPERABLE NIA 3 S 135 6104 PASSIVE 3CS3?7 Reactor Bldg. U3 OPERABLE WA 11-1786-5 3 21 3CT540 SRV INSTRUMENT N2 ACCUMULATOR FOR 1-351, SHT 3 D/W3-27 OPERABLE WA 3 $ RV-71C 154 2114 PASSIVE 3CT540 Oywull -U3 OPERABLE NIA M-3237 3 21 3CTS45 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 3 DNV3-27 OPERABLE NWA INSTR. N2 3 S RV-71C 154 2113 PASSIVE 3CT545 Drywall -U3 OPERABLE NWA 11-333 3 21 3DE124 ESW "D RHR PUMP SEAL COOLER M-315. SHT 4 R3-8 WA NIR 3 B 091 6576 PASSIVE 3DE124 3OP35 Reactor Okdl -U3 NIA NIR 1 21 30E24 RHR-D RHR HEAT EXCHANGER 0 M-361, SHT4 R3-19 OPERABLE NIA 3 S 091 4407. 5M0 PASSIVE 3DE024 Reacto Skdg -U3 OPERABLE NIA I M-1-H4-7,M-l-H-12-5.

3 21 3GT540 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 4 DN3.27 OPERABLE WA i 3 S RV-71G 154 2126 PASSIVE 3GT540 DMMwet -U3 OPERABLE NIA M-3237 2i 3GY545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 4 01V3-35 OPERABLE NWA INSTRN2 3 S RV-71G 154 2125 PASSIVE 3GT545 Drywell -U3 OPERABLE NWA M-M3 3 21 3KT540 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351, SHT4 DAVW-27 OPERABLE N/A 3 S RV-71K 154 2136 PASSIVE 3KT540 DweS -U3 OPERABLE N/A M-3237 3 21 3KT545 SRV INSTRUMENT N2 ACCUMULATOR FOR M-351. SHT 4 DAN3-34 OPERABLE NWA INSTR. N2 3 S RV-71K 154 2135 PASSIVE 3KT545 Dywell -U3 OPERABLE N/A M-333 3 0 0-48-506 ESW & HPSW EMERGENCY COOUNG WATER PUMP M-330 ECT-2 CLOSED NIA COMMON NWA 0OP186 DISCH CHECK W 153 5626 PASSIVE CHK.0-48.56O Emelrgency CooWg CLOSED NWA Towers 3 0 0AF349 SDG-A -FUEL OIL El DIG FUEL OIL INLET FILTER M-377. SHT 4 DfG-3 OPERABLE NWA COMMON B 127 6148 PASSIVE 0AF349 OAG12 Diesel Generator OPERABLE NWA 3 0 08F349 SOG.8 -FUEL OIL E2 D/G FUEL OIL INLET FILTER M-377. SHT 4 DIG-5 OPERABLE NWA COMMON B 127 5248 PASSIVE 08F349 08G12 Diesel Generator OPERABLE WA Peach Bottom Atomic Power Station Unit 2 B-63 MPR-3815, Revision 3 Cnrr..nnnd.nr.f.

No

• RS-19-173 DATE- 3/28/96 DOCUMENT NO. 0067-00M4-O001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 63 REVISION 2 SAFE SHUTDOWN EOUIPMENT LIST TRAIN SOUG CI Equip ID System Eqtdp Desaripton Daw No. Loc Code Norm sMe Motive power Suppod System Unit Eval reld? PIMS ID Notes ROB Modw Comfp Room Elev state Contr power Supp Sys dwg Line No Function Building 3 0 OCF349 SDG-C -FUEL OIL E3 D/G FUEL OIL INLET FILTER M-377. S14T 4 DIG-7 OPERABLE WA COMMON 8 127 5W PASSIVE 0CF349 OCGt2 Diesel Generator OPERABLE NIA 3 0 0DF349 SDG-0 -FUEL OIL E4 DIG FUEL OIL INLET FILTER M-377, SHT 4 DIG-S OPERABLE NIA COMMON 8 127 6448 PASSIVE 0DF349 ODG12 Diesel Generator OPERABLE WA 3 0 52C-10075A SDG-A. STARTING El DIG STARTING AIR RSVR (AUTO) M-377, SlIT 1 D/G-3 OPERABLE NIA COMMON NWA AIR 08T095 INLET CHECK 127 510t PASSIVE CHK-0-52C-10075A Diesel Generat" OPERABLE NIA 3 0 52C-100758 SG-0 -STARTING E2 DIG STARTING AIR RSVR (AUTO) M-377. SliT I DIG- OPERABLE WA COMMON NWA AIR 0OTO9S INLET CHECK 127 8201 PASSIVE CHK-O-52C-100758 Diesel Generator OPERABLE WA 3 0 52C-10075C SDG-C -STARTING E3 DIG STARTING AIR RSVR (AUTO) M-3T7. SHT i DIG-7 OPERABLE WA COMMON NWA AIR OFT0S5 INLET CHECK 127 5301 PASSIVE CHK-0-62C-10075C Diesl Geneator OPERABLE WA 3 0 52C-100760 SDG-0 -STARTING E4 DIG STARTING AIR RSVR (AUTO) M-377, S"lT I D/G-9 OPERABLE WA COMMON NWA AIR OlTO95 INLET CHECK 127 5401 PASSIVE CHK-0-52C-100750 Diesel Generator OPERABLE WA 3 0 BS-52D-0570A SDG-A -FUEL OIL El D0G FUEL OIL PUMPS SUCTION M-377, SHT 4 DIG-3 OPERABLE N/A COMMON a STReR 127 5145 PASSIVE SS-0570A 0AG12 Diesel Generator OPERABLE WA 3 0 9S-52-045708 SG-B -FUEL OIL E2 DIG FUEL OIL PUMPS SUCTION M-377. SHT 4 D/G-5 OPERABLE WA COMMON B STRNR 127 5245 PASSIVE 6S-05708 08G12 Diesel Generator OPERABLE WA 3 0 BS-52D.0570C SDG-C -FUEL OIL E3 DIG FUEL OIL PUMPS SUCTION M-377. SlIT 4 D/G-7 OPERABLE WA COMMON a STRNR 127 5345 PASSIVE BS-0570C OCG12 Diesel Generator OPERABLE WA 3 0 BS-520.05700 SOG-O -FUEL OIL E4 DIG FUEL OIL. PUMPS SUCTION M-377, SliT 4 01,-9 OPERABLE WIA COMMON a STRNR 127 5445 PASSIVE BS-070D. 0DG12 Diesel Generator OPERABLE NWA 3 0 CHtKOT8-17977 HVAC SECORY 1A INNER CHK O8V035 OAV034 + M-399. SHT 4 RNW-32 OPEN WA COMMON WA 0BVO34 FANS PO WS 165 5911 ACTIVE CHK.4-35B-17977 Radwaste Bldg CLOSED MIA 3 0 CHKD-368-17991 WVAC PRI I/A INNER CHK TO 08V035 OAV034. M-399. Slt I RPW-32 OPEN WA -COMMON NWA OBV034 FANS PO WS 165 6904 ACTIVE CHK-0-368-17991 Rad sW8t8 Bldg CLOSED NIA 3 0 CHKO-36B-18056 HVAC BA/I VA INNER CHK W FOR C(AB)V034 M-399, SlIT I RNW-32 OPEN WVA COMMON NWA INLET+OUT DMPRS 165 5909 ACTIVE CHK-0-36B-180566 Raedwaste Bldg CLOSED WA Peach Bottom Atomic Power Station Unit 2 B-64 MPR-3815, Revision 3 ( nrrP.qnnondPnrP, K-n RS-12-173 DOCUMENT NO. 0067-00084-0001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3128/9=PAGE 64 Noam state Mv power Suppor System Ceswed State Contr power Supp Sys dwg REVISION I TRAIN SOUG CI Equi ID Evwl rewd? PIMS ID System Notes Equip Descrip RO Mother Com Dm" No.Loc Code Room E8ev Line No FurKtion Bueldn 3 0 NIA SDG-A DIESEL "Ar EXHAUST SILENCER M-377, SHT 5 DIG-3 OPERABLE NIA COMMON S 127 5149 PASSIVE Diesel Generator OPERABLE N/A Vendor 11914759 4 3 0 WA SOG-S DIESEL 8 EXHAUST SILENCER M-377. SlIT 5 DIG-5 OPERABLE NWA COMMON S 127 5249 PASSIVE Oiesel Generator OPERABLE N/A V Vendor 11914759)3 0 WA SDG-C DIESEL VC EXHAUST SILENCER M-377. SlIT 5 DIG-7 OPERABLE NIA COMMON S 127 5349 PASSIVE Diesel Genendt OPERABLE NWA Vendor 11914759 3 0 W/A SDG-D DIESEL "D EXHAUST SILENCER M-377. SHT 5 01"-9 OPERABLE NIA COMMON S 127 5449 PASSIVE Diesel Generator OPERABLE NIA Vendor 11914759 3 0 RVO-36-00779 HVAC INSTR AIR RELIEF VALVE FOR M-389, SHIT 4 RNW-32 CLOSED WA COMMON B PO-O-40W-00031-01+00031-02 165 5923 PASSIVE RV-O-3IB-00779 PO-0-40W-00031-01100031-02 Radwaste Bldg CLOSED NIA 3 0 RVO-368-00780 HVAC INSTR AIR REUEF VALVE FOR M-399. SHT 4 RNW-32 CLOSED NWA COMMON B PO-O-4-W-00032-01

+00032-02 165 5925 PASSIVE RV-O-368.00780 PO.0-4-W-O0032-O1 100032-02 Radwaste Bg CLOSED NWA 3 0 RVD-36B-00784 WVAC INSTR AIR RELIEF VALVE FOR M-399. SHT 4 RM-32 CLOSED W&A COMMON 8 PO-O408-00025-01.00025-02 165 5922 PASSIVE RV-O368O0784 PO-0.4 00W-6.01100025-02 Radiwasta Bdg CLOSED N/A 3 0 RVO-36800812 HVAC INSTR AIR RELIEF VALVE FOR M-399, SHT 1 RAW-32 CLOSED WA COMMON S PO-0-40W-0-019.O100019.02 165 5919 PASSIVE RV-O-368-00812 PO.)-40W40001 ICOM9M2" Radwaste Bldg CLOSED NWA 3 0 RVO-36B-00813 HVAC INSTR AIR RELIEF VALVE FOR M-399, SHT I RPW-32 CLOSED NWA COMMON B PO-.04W-0020-010020-02 165 5920 PASSIVE RV-O-358.00813 PO-0-40W-00020-0 1000204)2 Radwaste Bldg CLOSED NWA 3 0 RVO-3684.0814 HVAC INSTR AIR RELIEF VALVE FOR M-399. SHT 4 RNW-32 CLOSED NWA COMMON a PO.04OW,.0026u01+0026-02 165 5921 PASSIVE RV.)-368.0014 PO-0-40W-00028-01100026-02 Rafwaste Bldg CLOSED WA 3 1 00849 EPS 480 V TURBINE AREA MCC 00849 E-1621 T2-172 ENERGIZED 2O81222 COMMON S (E324-T-B) 135 8000 ACTIVE 00849 Twbine g. U2 ENERGIZED E-11-5O 3 1 00850 EPS 480 V TURBINE AREA MCC 00850 E-1621 T3-172 ENERGIZED 2081322 COMMON S (E424-T-8) 135 8000 ACTIVE 00850 Tune Bldg. U2 ENERGIZED E-D1-51,E-11-197 3 1 00853 EPS 480 VI E10G MCC 00B53(E124-O-A) 8-1619 0/G-4 ENERGIZED 2081021 COMMON S 8000 ACTIVE 00B53 127 Diesel Generator ENERGIZED E-1 1-106 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn" RS-19-17.3 B-65 DATE: 3/28/9 PAGE 65 DOCUMENT NO. 00574)0084-49t1 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAN Untit SOUG CI Equip ID Eval read? PIMS ID System Notes Equi Oescripio ROB Mother CWmp DrawingNo.

Loc Code Room Eoev Build" Mora state Motive power Desired State Cowe power Support Systm Supp Sys d"w 3 1 00854 EPS 480 V E2 DG MCC 00854 (E234-0-A)

E-1619 01G-6 ENERGIZED 3081121 COMMON S 127 8000 ACTIVE E234 Disel Generator ENERI E-11.109 3 1 00856 EPS 480 V E3 D0G MCC 00855 (E324-0-A)

E-1619 D0G-8 ENERGIZED 20B1221 COMMON S 127 8000 ACTIVE E324 Diee Generator ENERGIZED I E-11-106 3 1 00056 EPS 480 V E4 DIG MCC 0056 (E434-0.A)

E-1619 DIG-t0 ENERGIZED 3081321 COMMON S 127 8000 ACTIVE E434 Diese! Generator ENERGIZED E-11-107 3 1 00861 EPS 480 V PUMP STRUCTURE MCC 00861 E-1621 U-2 ENERGIZED 20B1122 COMMON S (E224-P-A) ill 8000 ACTIVE 00861 Pump House ENERGIZED E-11-110.

E-11-278 3 1 00862 EPS 480 V PUMP STRUCTURE MCC 00882 E.1621 U-3 ENERGIZED 2081022 COMMON S (E124-P-A) 111 8000 ACTIVE 0062p House ENERGIZED E-10-31 3 1 00897 EPS 480 V MCC 00897 (E13A4.EC-A)

E-1627 ECT-3 ENERGIZED 0089414 COMMON S 153 8000 ACTIVE 00897 Emergency Cooing ENERGIZED

-Towers E-11-161, E-11-278 3 1 00898 EPS 480 V MCC 00898 (E23A4-EC-A)

E-1627 ECT-4 ENERGIZED 0086M14 -COMMON S 153 8000 ACTIVE 0096O Emergency Cooi ENERGIZED Towers E-1 1-162 3 I 00899 EPS 480 V MCC 00899 (E43A4-EC-A)

E-1627 ECT-5 ENERGIZED 0089614 COMMON S 153 8000 ACTIVE 00899 Emergency Cooin ENERGIZED

-Towers E-11-163 3 2 00894 EPS 480V6USE13A4 E-1627 ECT-3 ENERGIZED 0AX26 0089412 COMMON S 153 8000 ACTIVE 00894 Emergecy Cooing ENERGIZED Towers 3 2 0089412 EPS BREAKER TO E13A4 480 V BUS (LC0094 E-1627 ECT-3 CLOSED 00894 W COMMON BR 153 I 8000 PASSIVE E-73 (9412) 00894 Emergercy Cooig CLOSED -Towers 3 2 0089413 EPS BREAKER TO EMERG. CLG. TOWER E-1627 ECT-3 OPEN 00894 COMMON BR FAN 08K32 153 8000 ACTIVE E-321(9413) 00894 Emergency Cooig OPEN/CLOSED Towers 3 2 0089414 EPS BREAKER TO 480V MCC 00897 E-1627 ECT-3 CLOSED 00894 COMMON OR (13A4-EC-A) 153 8000 PASSIVE E-67(9414) 00894 Emergen-cy Coolin CLOSED -Towers 3 2 COMMON S 8000 ACTIVE 00895 00895 EPS 480 V BUS E23A4 E-1627 ECT-4 153 Emergency Cooft Towers ENERGIZED ODBX26 ENERGIZED 0089512 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (,nrrP.snndP.nrP.

Nn -RS-12-173 B-66 DATE: 3128=96 PAGE 66 DOCUMENT NO. OOST.0084-DO01 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN E2UIPMENT LST TRAIN Und$OUG CI E"ui to Evel ee~d? PUMS to Function system Notes Ecqp ODescrio ROB Mohie Comp or"" fN Lao Code Room Elev Norm state Desied State Motve power Contr power support System Supp Sys dwg 3 2 0089512 EPS BREAKER TO E23A4 480V BUS (LC00895 E.1627 ECT-4 CLOSED 00895 COMMON BR 153 8000 PASSIVE E-73 (9512) 00895 Emergency Coofg CLOSED Towers 3 2 0089513 EPS BREAKER TO EMERG. CLG. TOWER E-1627 ECT-4 OPEN 00695 COMMON BR FAN 0AK32 153 8000 ACTIVE E-321(9513) 00895 Emergency Coolg OPENICLOSED Towers 3 2 008614 EPS BREAKER TO 480 V MCC 00898 E-1627 ECT-4 CLOSED 00195 COMMON BR (23A4-EC-A) 153 8000 PASSIVE E-67(9514) 00B95 Emergency CoolIng CLOSED -Towers 3 2 00896 EPS 480 V BUS E43A4 E-1627 ECT-5 ENERGIZED 0CX26 0089612 COMMON S 153 BOW ACTIVE o0096 Emergency Coog ENERGIZED Towers 3 2 0089612 EPS BREAKER TO E43A4 480 V BUS (LC00898 E-1627 ECT-5 CLOSED 00B96 COMMON SR 153 8000 PASSIVE E-73 (9612) 00896 Emergency Coolofg CLOSED Towers 3 2 0089613 EPS BREAKER TO EMERG, CLG. TOWER E-1627 ECT-5 OPEN 00896 COMMON BR FAN 0CK32 153 8000 ACTIVE E-321(9613) 00896 Emergency Cooding OPENICLOSED Towers 3 2 0089614 EPS BREAKER TO 480 V MCC 00899 E-1627 ECT-5 CLOSED 00B96 COMMON BR (43A4-EC-A) 153 8000 PASSIVE E-67(9614) 009B6 Emergency Cooling CLOSED Towers 3 3 20Ai603 EPS-28 BREAKER TO A EMER SERV WVTR PP E-8 T2-71 OPEN 20A16 COMMON BR 0AP57 135 8203 ACTIVE E22 (1603) 20A16 Ttubie Bldg -1U2 CLOSED 20022 28D306 3 3 2GA1609 EPS-2B 8KR TO EMERG. SERV. WATER E-8 T2.71 OPEN 20A16 COMMON BR BOOSTER PUMP (OAP153) 135 8207A ACTIVE E22 (1609) 20A16 TutinsBldg

-U2 OPENICLOSED 20D22 20D306 3 3 20A1706 EPS-2C BREAKER TO B EMERG SERV WATER E-8 T2-170 OPEN 20A17 COMMON BR PUMP 0BP57 135 8305 ACTIVE E32 (1706) 20A17 Tuabine BWg -U2 CLOSED 30023 3 3 20A1709 EPS-2C E232 B1R TO EMERG. SERV. WATER E-8 T2-170 OPEN 20A17 COMMON BR BOOSTER PUMP (0BP163) 135 6307A ACTIVE E32 (1709) 20A17 Tuttine Bldg -U2 OPENICLOSED 30023 3 4 00X103 EPS PANEL 00Y03 TRANSFORMER E-28, SHT I RAN-21 ENERGIZED 008501 COMMON S 135 8001 ACTIVE 00X103 Radwaste Bg ENERGIZED 3 4 COMMON S OAX26 EPS E-i3A4(0AX2S)

LOAD CENTER XFMR (OAX26)E-1627 ECT-3 ENERGIZED 30AIS02 I -8000 ACTIVE 153 Emergency Cooling ENERGIZED Towers Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn

• RR-1 9-173 -B-67 DOCUMENT NO. 007-0004-)001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Motive power Desied State Comi power DATE: 3&28J96 PAGE 67 TRAIN SQUG CI E" ID Eval req'd? PIMS ID Syslem Note EqROB hsaipion ROB Moither camtp ODawbg No.Loc Code Room Elmw Support System Supp Sys dwg Line No Func BionA g 3 4 0SX26 EPS LOAD CENTER XFMR (00=26) E-1627 ECT-4 ENERGIZED 30A1609 COMMON S 153 8000 ACTIVE E-23A4(08X26)

Emergency Coofiln ENERGIZED Towers 3 4 0CX26 EPS LOAD CENTER XFMIR (OCX26) E-1627 ECT-5 ENERGIZED 30A1805 COMMON S 153 8000 ACTIVE E-43A4(0CX2=)

Emergency CoofIng ENERGIZED Towers 3 5 QAP163 ESW EMERGENCY SERVICE WATER M-330 DIG-1 OFF 20A16 20A1609 COMMON S BOOSTER PUMP A 121 5621 ACTIVE OAP163 Diesel Generator OFFION 3 5 0AP164 SDGA -DIESEL El DIG AIR COOLANT AUXILIARY PUMP M-377. SHT 2 0/G-4 OPERABLE NIA COMMON S COOUNG 127 C125 PASSIVE 0AP164 O est Generator OPERABLE NIA 3 5 OAP165 SG-A -DIESEL El D/G JACKET COOLANT STANDBY M-377. SHT 2 DIG-3 OPERABLE NIA COMMON B COOLING CIRC PUMP 127 5126 PASSIVE OAP166 Diesel Generator OPERABLE N/A 3 5 0AP166 SOG-A -DIESEL El DIG JACKET COOLANT AUX PUMP M-377. SHT 2 DI04 OPERABLE WA COMMON S COOLING 127 5124 PASSIVE OAP166 Diesel Generator OPERABLE N/A Vendor 44058120 3 5 OAP1B7 S$G-A -LUBE OIL El DIG LUBE OIL AUXILIARY PUMP M-377. SHT 3 DIG-3 OPERABLE N/A COMMON S 127 5132 ACTIVE 0AP167 Diesel Generator OPERABLE N/A Vendor NV-412 3 5 0AP168 SOG-A -FUEL OIL E1 DIG FUEL OIL AUXILIARY PUMP (OC) M-377. SHT 4 DIG-3 OFF OAD13 COMMON BR 127 5147 ACTIVE OAP168 0AG12 Diesel Generator OFF/ON 3 5 0AP172 SG-A -LUSE OIL El DIG LUBE OIL STANDBY CIRC PUMP M-377, SHT 3 Boa-3 OPERABLE N/A COMMON a 127 S130 PASSIVE 0AP172 Diesel Generator OPERABLE N/A 3 5 0AP173 SG0-A -LUBE OIL El DIG LUBE OIL PRE LUBE PUMP M-377. SHT 3 0/G-3 OPERABLE N/A COMMON B 127 5135 PASSIVE OAP173 Diesel Generator OPERABLE N/A 3 5 0AP382 SDG-A -LUBE OIL El D/G LUBE OIL ENGINE DRIVEN PUMP M-377, SHIT 3 D/G-3 OPERABLE NWA COMMON B 127 5133 ACTIVE 0AP382 0AG12 Diesel Generator OPERABLE NIA 3 5 OAP60 SDG-A -FUEL OIL El 10G FUEL OIL TRANSFER PUMP M.377. SliT 4 O/G-3 OFF 00853 LS-0566A COMMON SR 127 5142 ACTIVE 0APOS0 Diesel Generator OFFION SPEC M-81 3 5 OSP063 ESW EMERGENCY SERVICE WATER M-330 D/G-1 OFF 20A17 20A1709 I oBOOSTER PUMP B Diesel Generator OFF/ON 5622 ACTIVE OBPI63 M-19-14-4 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (,nrrpf.lnrnpnr.p, Nn " RS-19-173

-B-68 DOCUMENT NO. 006?40084-Oo01 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Motive powr Desired State Contr power DATE: 326 PAGE 68 TRAIN Und SQUG CI Eqip* ID Eval qd040 PIMS ID System Notes Equip Desciption ROB Motge Comp Ing No.Loc Code Room Sev SI4PoPt system S'spp SYS deg Line No Function Building 3 5 08PI64 SDG-B -DIESEL E2 D/G AIR COOLANT AUXILIARY PUMP M-377, SHT 2 DIG-6 OPERABLE NZA COMMON S COOLING 127 5225 PASSIVE 0BP164 Dieset Generator OPERABLE NIA 3 5 0P165 SDG-B -DIESEL E2 DIG JACKET COOLANT STANDBY M.-377, SHT 2 DIG-S OPERABLE NWA COMMON a COOLING CIRC PUMP 127 S PASSIVE 0P Diesel Generator OPERABLE WA 3 5 06P1166 SG-B -DIESEL E2 DIG JACKET COOLANT AUX PUMP M-377. SHT 2 O/G- OPERABLE NWA COMMON S COOLING 127 5224 PASSIVE 0SP166 Diesel Generator OPERABLE NWA Vendor 44058120 3 5 OSPI67 SOG-B -LUBE OIL E2 DIG LUSE OIL AUXILIARY PUMP M-377, SHT 3 D/G-S OPERABLE NWA COMMON S 127 5232 ACTIVE 08PIS7 Diese Generator OPERABLE NWA Vendo NV-412 3 5 OSPI68 SOG-B -FUEL OIL E2 DIG FUEL OIL AUXILIARY PUMP (OC) M-377. SHT 4 DIG-5 OFF 08013 COMMON SR 127 5247 ACTIVE 0BP168 OBG12 Diese Generator OFF/ON 3 5 0BP172 SDG-a -LUSE OIL E2 D/G LUBE OIL STANDBY CIRC PUMP M-377, SlIT 3 DIG-5 OPERABLE NWA COMMON B 127 5230 PASSIVE DBP172 Diesel Generator OPERABLE NIA 3 5 0OP173 SOG-B -LUBE OIL E2 DIG LUBE OIL PRE LUBE PUMP M-377. SHT 3 DIG-5 OPERABLE NWA COMMON B 127 5235 PASSIVE 0BP173 Diesel Generator OPERABLE NIA 3 5 0P362 SDGa- -LUBE OIL E2 DIG LUSE OIL ENGINE DRIVEN PUMP M-371. SHT 3 D0G-S OPERABLE WA COMMON B 127 5233 ACTIVE 0BP382 08G12 Diesel Generator OPERABLE WA 3 5 08o61 SDG-B -FUEL OIL E2 DIG FUEL OIL TRANSFER PUMP M-377, SlIT 4 DIG-5 OFF 00854 LS-05568 COMMON SR 127 5242 ACTIVE OSPOGO Diesel Generator OFF/ON SPEC M-81 3 5 0CP164 SDG-C -DIESEL E3 DIG AIR COOLANT AUXILIARY PUMP M-377, SlIT 2 DoG- 'OPERABLE NIA COMMON S COOLING 127 5325 PASSIVE OCP164 Diesel Generator OPERABLE WA 3 5 OCP165 SDG-C -DIESEL E3 DIG JACKET COOLANT STANDBY M-377, SHT 2 DIG-7 OPERABLE NIA I!COMMON B COOLING CIRC PUMP 127 5326 PASSIVE 0CP165 Diesel Generator OPERABLE NIA 3 5 OCP166 SDG-C -DIESEL E3 DIG JACKET COOLANT AUX PUMP M-377, SlIT 2 DIG-B OPERABLE N/A COMMON S COOLING 127 5324 PASSIVE OCP166 Diesel Generator OPERABLE NIA Vendor 44058120 3 5 0CP167 SDG-C -LUBE OIL E3 DIG LUBE OIL AUXILIARY PUMP M-377. SHT 3 DIG-7 OPERABLE NWA COMMON S 127 Diesel Generator OPERABLE NWA 5332 ACTIVE OCP167 Vendor NV-412 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrrp.nnndrpnnr.

Nn ' RS-1 2-173 B-69 DATE: 3128M9 PAGE 69 DOCUMENT NO. 0067-00084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN SOUG C! EquO ID Eval reqd? PIMS ID System Rates Equip Descrition ROB Modmer Coamp Drawin No.LoC Code Roon Elev Norm state Mode powe SuppoW System Desired Stat Conr power SuLP Sys dwg Line No Fjncion Buildin 3 5 0CP168 SOG-C -FUEL OIL E3 D/I FUEL OIL AUXILIARY PUMP (DC) M-377. SHT 4 DIG-? OFF 0C013 -COMMON BR 127 5347 ACTIVE 0CP168 0C012 Oiese Generator OFF/ON 3 5 OCP172 SDG-C -LUBE OIL E3 DIG LUBE OIL STANDBY CIRC PUMP M-377, SNT 3 O/G-7 OPERABLE N/A COMMON B 127 5330 PASSIVE 0CPI72 Diesel Generator OPERABLE N/A 3 5 0CP173 SDG-C -LUBE OIL E3 DIG LUSE OIL PRE LUBE PUMP M-377, SHT 3 O/G-7 OPERABLE N/A COMMON B 127 5335 PASSIVE 0CP173 Diesel Generator OPERABLE N/A 3 5 0CP382 SDG-C -LUBE OIL E3 D/G LUBE OIL ENGINE DRIVEN PUMP M-377, SHT 3 D/G-? OPERABLE N/A COMMON B 127 6m33 ACTIVE 0CP382 0CG12 Diesel Generator OPERABLE NIA.3 5 6CP60 SOG-C -FUEL OIL E3 DIG FUEL OIL TRANSFER PUMP M-3T7, SHT 4 DIG-7 OFF 00855 LS-0666C COMMON SR 127 5342 ACTIVE OCFP060 Diesel Generator OFF/ON SPEC M-81 3 5 00P164 SOG.0 -DIESEL E4 DOG AIR COOLANT AUXILIARY PUMP M-377, SHT 2 O/IG-10 OPERABLE N/A -COMMON S COOLING 127 5425 PASSIVE 0OP164 Disel Generator OPERABLE N/A 3 5 ODPI65 SDG4) -DIESEL E4 DIG JACKET COOLANT STANDBY M-377. SHT 2 DIG-9 OPERABLE N/A T COMMON B COOLING CIRC PUMP 127 5426 PASSIVE OPI65 Diesel Generator OPERABLE N/A 3 5 0OP 166 SD"-. -DIESEL E4 DJG JACKET COOLANT AUX PUMP M-377, SHT 2 D/G-tO OPERABLE NA -COMMON S COOLING 127 5424 PASSIVE 0OPI6 Dies0 l Generator OPERABLE N/A Vendor 44056120 3 5 0OPI67 SOG-0 -LUBE OIL E4 DIG LUBE OIL AUXILIARY PUMP M-377, SliT 3 D/G-9 OPERABLE N/A -COMMON S 127 5432 ACTIVE 0DP167 Oiesme Generator OPERABLE N/A Vendor NW-412 3 5 0OP168 S0G-D -FUEL OIL E4 D/G FUEL OIL AUXILIARY PUMP (DC) M-377. SHT 4 010-9 OFF 00013 COMMON BR 127 5447 ACTIVE O0P168 0DG12 Diesel Generator OFF/ON -3 5 OOP12 SDG-D -LUBE OIL E4 DIG LUBE OIL STANDBY CIRC PUMP M-377. SHlT 3 D0.G-9 OPERABLE N/A COMMON B 127 5430 PASSIVE 0DP172 Diesel Generator OPERABLE N/A 3 5 0DP173 SDG-D -LUBE OIL E4 DIG LUBE OIL PRE LUBE PUMP M-377, SKlT 3 O/G-9 OPERABLE N/A COMMON B 127 5435 PASSIVE 00P173 Diesel Generator OPERABLE N/A 3 5 00P382 SOG-D -LUBE OIL E4 DIG LUBE OIL ENGINE DRIVEN PUMP M-377, SHT 3 O/G-9 OPERABLE N/A COMMON B 5433 ACTIVE 127 Diesel Generator OPERABLE N/A 0DP382 0OG12 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrrp..nnndrn-nr.

Nn

• RR-1 2-17.1 B-70 DATE: 3P2W96 PAGE 70 DOCUMENT NO. 0067-00384-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST TRAIN Unit Line No SOUG Ci Equip ID Eval mqtd? PIMS ID Function Notes EuO DesMetiiorn ROB Mattle COMPNo.Loc Code Room Elev Bufilng NOM slate Desied State Mo"le p"wm Cony power Support system Supp Sys dWg 3 5 COP60 SDG-O -FUEL OIL E4 D/G FUEL OIL TRANSFER PUMP M-377, SHT 4 ODG-9 OFF 00B58 LS-05660 COMMON SR 127 5442 ACTIVE 01P060 ODesel Generaor OFFION SPEC M-81 3 5 N/A SOG-A- DIESEL AIR COOLANT PUMP. ENGINE DRIVEN M-377. SHT 2 DIG -3/4 OPERABLE N/A COMMON B COOLING 127 5118 ACTIVE OAGI2 Diesel Generator OPERABLE N/A 3 5 N/A SOG-A -DIESEL JACKET COOLANT PUMP, ENGINE M-377. SHT 2 D/G -314 OPERABLE N/A T COMMON B COOLING ORIVEN 127 5121 ACTIVE CAG12 Diesel Generator OPERABLE N/A 3 5 N/A SDG-B -DIESEL AIR COOLANT PUMP, ENGINE DRIVEN M-377. SHT 2 DIG -56 OPERABLE N/A COMMON a COOLING 127 5218 ACTIVE 08G12 Diesel Generator OPERABLE N/A 3 5 N/A SOG-8 -DIESEL JACKET COOLANT PUMP. ENGINE M-377. SHT 2 DIG -Sra OPERABLE N/A COMMON B COOLING DRIVEN 127 5221 ACTIVE 0BG12 Diesel Gewerator OPERABLE N/A 3 W N/A SDG-C -DIESEL AIR COOLANT PUMP. ENGINE DRIVEN M-377. SHT 2 DIG -7/8 OPERABLE N/A COMMON 8 COOLING 127 5318 ACTIVE OCGI2 Diesel Gerwator OPERABLE N/A 3 5 N/A SDG-C -DIESEL JACKET COOLANT PUMP. ENGINE M-377, SHT 2 DIG -718 OPERABLE N/A COMMON B COOLING DRIVEN 127 5321 ACTIVE OCG12 Diesel Generator OPERABLE N/A 3 5 N/A SDG-O -DIESEL AIR COOLANT PUMP, ENGINE DRIVEN M-377, SHT 2 DIG- 9/10 OPERABLE N/A COMMON a COOLING 127 5418 ACTIVE ODG12 Diesel Generatro OPERABLE N/A 3 5 N/A SDG-O -DIESEL JACKET COOLANT PUMP. ENGINE M-377. SHT 2 D/G -9/10 OPERABLE N/A COMMON B COOLING DRIVEN 127 5421 ACTIVE ODG12 Diesel Generat OPERABLE N/A 3 5 N/A SDG.A -FUEL OIL FUEL OIL PUMP. SHAFT DRIVEN M-377. SHT 4 O/G-3 OPERABLE N/A-COMMON a 127 5146 ACTIVE OAG12 Diesel Gendeato OPERABLE N/A 3 5 NIA SOG-8 -FUEL OIL FUEL OIL PUMP, SHAFT DRIVEN M-377, SHT 4 D/G-S OPERABLE N/A COMMON 8 127 5246 ACTIVE OBG12 Diesel Generator OPERABLE N/A 3 5 N/A SDG-C -FUEL OIL FUEL OIL PUMP. SHAFT DRIVEN M-3T". SHT 4 DIG-7 OPERABLE N/A COMMON B 127 5346 ACTIVE OCG12 Diesel Generator OPERABLE N/A 3 5 COMMON B N/A SDGO -FUEL OIL FUEL OIL PUMP. SHAFT DRIVEN M-377, SHT 4 DG49 127 Diesel Generaor OPERABLE N/A OPERABLE N/A 5446 ACTIVE 00G12 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrr-.'nnndpnr.p.

Nn

• R5-12-173 B-71 DOCUMENT NO. 0067400504-DOO REVISION I PEACH BOlTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EOUIPMENT LIST-DATE: 3/28196 PAGE 71 Norm state Motive power Support System Desied State Corer power Supp Sys dwg TRAIN Unr SOUG Cl Equip ID Eva] reld? PIMS ID System Notes Equip Descripion ROB Motmer Comp Orawing No.Loc Code Room Elev Line No Function Building 3 6 OAP57 ESW EMERGENCY SERVICE WATER PUMP A W-315. SlT I P/H-8 OFF 20A16 20A1603 COMMON S 111 5537 ACTIVE 0APS07 Pnmp House ON -*l M-11-29. E-8-109-1 3 6 08P57 ESW EMERGENCY SERVICE WATER PUMP B M-315. SHT4 PIN-a OFF 20A17 20A1706 COMMON S 11 O1 5589 ACTIVE OBP057 Pump House ON M 3 7 AO-33.0241A ESW ESW OUTLET BLOCK VALVE FROM M-315, SHT I DIG-3 CLOSED N/A T SV-368-0241A COMMON S DIESEL GEN E l COOLERS 127 5530 ACTIVE A0O4-3$.041A Diesel Generator OPEN N/A vendor 6-9M207-52 3 7 AO-33-02418 ESW ESW OUTLET BLOCK VALVE FROM M-315. SHIT I DIG-S CLOSED N/A -SV-358-02418 COMMON S DIESEL GEN E2 COOLERS 127 5532 ACTIVE AO-0-33-0241B Diesel Generawo OPEN, N/A S vendor 6..gM207-52 3 7 AO-33-0241C ESW ESW OUTLET BLOCK VALVE FROM M-315. SHIT 1 D/G-7 CLOSED N/A SV-368-0241C COMMON S DIESEL GEN E3 COOLERS 127 5534 ACTIVE AO-O.33-0241C Diese Generator OPEN N/A vendor 6-9M207-52 3 7 AO-33-02410 ESW ESW OUTLET BLOCK VALVE FROM M-315. SHT I D/G-9 CLOSED N/A SV-368-0241D COMMON S DIESEL GEN E4 COOLERS 127 5536 ACTIVE AO-0-33-0241D Diesel Generator OPEN N/A vendo6-9M207-52 3 7 AO-52C-7231A SDG-A -STARTING El DIG AIR START SOLENOID VALVE M-377. SHlT 1 D/0-3 CLOSED NWA SV-52C-7233A COMMON S AR 127 5104 ACTIVE AO-O-52C-7231A Diesel Generator OPEN N/A 3 7 AO-52C-7231B SO-8 -STARTING E2 DIG AIR START SOLENOID VALVE M-377. SHIT 1 D/G-5 CLOSED N/A SV-52C-7233B COMMON S AIR 127 5204 ACTIVE AO-o-52C-7231B Diesel Generator OPEN N/A 3 7 AO-52C-7231C SOG-C -STARTING E3 D/G AIR START SOLENOID VALVE M-377, SHT I DIG-7 CLOSED N/A SV-52C-7233C COMMON S AIR 127 5304 ACTIVE AO-0-52C-7231C Diesel Generator OPEN N/A 3 7 AO-52C-7231D SDG-0 -STARTING E4 D/G AIR START SOLENOID VALVE M-377. SrT I D0G-9 CLOSED N/A SV-52C-7233D COMMON S AIR 127 5404 ACTIVE AO-O-52C-7231D Diesel Generator OPEN N/A 3 7 AO-52C-7232A SDG-A -STARTING El DIG AIR START SOLENOID VALVE M-377. SHT I D/G-3 CLOSED N/A SV-52C-7234A COMMON S AIR 127 5105 ACTIVE AO-0-52C-7232A Diesel Generator OPEN N/A 3 7 AO-52C-7232B SDG-B -STARTING E2 DIG AIR START SOLENOID VALVE M-377. SHT 1 DIG-S CLOSED N/A SV-52C-72348 COMMON S AIR 127 5205 ACTIVE AOO.-52C-7232B Diesel Generator OPEN N/A 3 7 AO-52C-7232C S0G-C -STARTING E3 DIG AIR START SOLENOID VALVE M-377. SHT 1 0/G-7 CLOSED N/A SV-52C-7234C COMMON S AIR 127 06 ACTIVE AO-62C-7232C Diesel Generator OPEN NIA Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn

• RR-12-173 B-72 DOCUMENT NO. 006740900844O1 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3rA6 PAGE 72 Norm state Motive power SUpPOA System Desked State CoM power Supp Sys dwg TRAIN Unit SOUG CI Equip ID Eval eqd*? PIMS ID Systm Notes Equip DesCiption ROB MoVW Camp Drawing No.Loc Code Room Elev Line No Function Bud 3 7 AO-52C.7232D SG-O -STARTING E4 D/G AIR START SOLENOID VALVE M-377. SHT 1 D/G-9 CLOSED NWA SV-52C.7234D COMMON S AIR 127 5405 ACTIVE AO.0-52C-72320 Diesel Gereator OPEN NfA 3 7 AV-368-00016 HVAC EMERG SWGR& BTRY RMS SUPPLY M-399, SHT 1 RA/-32 OPERABLE WA COMMON a VENT PNEUMATIC RELAY 165 5907 ACTIVE AV-00016 00F043 Radwaste BIg OPERABLE NIA 3 7 PCV-40W-7008SA HVAC 11N2 B/U SUP PRESS CRTL VLV FOR M-399. SHT I RNW-29 OPERABLE WA COMMON S 08V035 AND OA(B)V034 165 5901 ACTIVE PCV.O-40W-70088A Radw*mse 8ldg OPERABLE NIA 3 7 PCV.40W-700888 HVAC U/N2 B/ SUP PRESS CRTL VLV FOR M-399., SHT I RW-29 OPERABLE NIA COMMON S 0BV035 AND OA(B)V034 165 5903 ACTIVE PCV-O-40W-700888 Radwaste Bag OPERABLE NWA 3 7 PCV.40W-70089A HVAC UN2 BIU SUPPRESS CRTL VLV FOR M-399, SHT 4 RNW-32 OPERABLE NWA COMMON S 0AV035 AND OA(B)V036 Ra5s 5914 ACTIVE PCV-O-40W-70089A Radwasto Bldg OPERABLE N/A 3 7 PCV-40W-70089B HVAC I/N2 BRJ SUP PRESS CRTL VLV FOR M-399. SHT 4 RNV-32 OPERABLE NWA COMMON S OAV035 AND 0A(B)V035 165 5916 ACTIVE PCV-O-40W.70089B Radwasle Bldg OPERABLE NA 3 7 PO-40W-00803-01 HVAC EMERG SWGR + BATTERY ROOMS M-399, SlIT I RPW-32 CLOSED/OPEN N/A WIVAC N2 COMMON 8 VENT SUP FAN 0BV034 INLET 165 5809 ACTIVE PO.-040W-00803-01 PO.40W-00020-01 Radwaste Bldg OPEN N/A M-399. SHT 1 3 7 PO,40W-00803-02 HVAC EMERG SWGR + BATTERY ROOMS M-399. SlIT I RAW-32 CLOSED/OPEN N/A HVAC N2 COMMON B VENT SUP FAN 0BV034 INLET 165 5810 ACTIVE PO-0-40W-00803-02 P0O.4-W.O0020-01 RIdwaste Bldg OPEN WA M-399. SHT 1 3 7 PO-40W-00803-03 HVAC EMERG SWGR + BATTERY ROOMS M-399. SlIT 1 RNV-32 CLOSED/OPEN NWA HVAC N2 COMMON B VENT SUP FAN 06VO34 INLET 165 5812 ACTIVE PO-0,40W-4)0803-03 P-O0-40W-00020-01 Radwaste Bldg OPEN N/A M-399. SHT 1 3 7 PO-40W-00808 HVAC EMERG SVR + BATTERY ROOMS M-399, SHT I RMN-32 OPEN NWA WIAC N2 COMMON B VENT SUP FAN 0AV034 OUTLET 165 5808 PASSIVE PO)-040W-00808 PO-O.40W.19.02 Radwaste BOf OPEN NWA M-399. SHT 1 3 7 PO-40W-00809 HVAC EMERG SWGR + BATTERY ROOMS M-399. SHIT 1 RAN-32 CLOSED NWA HVAC N2 COMMON B VENT SUP FAN 06V034 OUTLET 165 5816 ACTIVE PO.O-40W-008o9 PO-,40W-0002002 Radwatse Bldg OPEN NIA M-399. SHT 1 3 7 PO-40W-00815-01 HVAC EMERGENCY SWITCHGEAR VENT M-399. SNT 4 RNV-32 OPEN NIA HVAC N2 COMMON B EXHAUST FAN OAV035 INLET 165 5824 PASSIVE P.O--40W-0M81501 P04-40W-00025-01 Radwaste Bldg OPEN NWA 3-399. SEET 4 3 7 PO-40W-.00516-OI I'IVAC EMERGENCY SWITCHGEAR VENT M-399, SlIT 4 RNq-32 CLOSED NWA HVAC N2 COMMON B 5829 ACTIVE EXHAUST FAN 0BVO35 INLET Po-040W-00O284 165 Radwaste Bldg OPEN NWA PO--40W-00816-01 M-399. SHT 4 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn

• RR-12-173 B-73 DOCUMENT NO. 0067,000840001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Motave powet Desinedl Swate Cont power DATE: 312/96 PAGE 73 TRAIN Uni SOUG CI Equp ID Eval reqcd? PIMS ID System EqL;Ip Descption ROB Moitor Camp Drswin No.Loc Code Room Elev Support System S4pp Sys twg Line No Fundion B&iding 3 7 PO-40W-00816-02 HVAC EMERGENCY SW1TCHGEAR VENT M-399, SHT 4 RMA-32 CLOSED N/A HVAC N2 COMMON B EXHAUST FAN 08V035 OUTLET 5832 ACTIVE PO-o.40W-00816-02 PO04)OW00026.02 Radwaste Bld OPEN N/A M 3 7 PO.40W-0822-01 HVAC EMERG SWGR + BATTERY ROOMS M-399, SNT 1 RNW-32 OPEN NIA HVAC N2 COMMON B VENT SUP FAN 0AV034 INLET 165 5801 PASSIVE PO-G040OW..(822-01 P0-0-4iW-019-01 RadwaeM Bl OPEN N/A M-399, SHT 1 3 7 PO-40W.O0822-02 HVAC EMERG SWGR + BATTERY ROOMS M-399. SHT I RNV-32 OPEN N/A [ NVAC N2 COMMON a VENT SUP FAN 0AV034 INLET 165£802 PASSIVE PO-o.40-0082202 PO.0-40W-00019-01 Radwaste Bldg OPEN N/A M-399, SHT 1 3 7 PO-40W-00822-03 HVAC EMERG SWG + BATTERY ROOMS M-399, SlT 1 RAN-32 OPEN N/A HVAC N2 COMMON B VENT SUP FAN 0AV034 INLET 165 5803 PASSIVE P-03 POO40W-O0019-01 Radwaste Bldg OPEN N/A M-399, SHT I 3 7 RV-40W-7149A HVAC 8/U 1AN2 RELF VLV FOR 08V035 AND M-399, SHT 1 RNW-29 CLOSED N/A COMMON S 0(A.B)V034 FANS PO VVS 165 5918 PASSIVE RV-O4OW-7149A Radwaste Bldg CLOSED N/A 3 7 RV-40W-71498 HVAC B/U 11N2 RELF VLV FOR 0AV035 AND M-399. SNT 4 PJW-32 CLOSED N/A COMMON S O(A.B)V036 FANS PO WS 165 5924 PASSIVE RV-0-40W-71498 Radwaste Og CLOSED N/A 3 7 TCV-52E-7239A SOG-A -DIESEL El DIG .ACET COOLANT 3-WAY M.377, SHT 2 D/G-3 OPEN/CLOSED N/A COMMON B COOLING THERMOSTATIC CONTROL VALVE 127 5122 ACTIVE TCV-O-52E-7239A OAGO12 Diesel Generator OPEN/CLOSED N/A 3 7 TCV-52E-72398 SDG-8 -DIESEL E2 DiG JACKET COOLANT 3-WAY M-377. SlIT 2 DIG-5 OPEN/CLOSED N/A COMMON B COOLING THERMOSTATIC CONTROL VALVE 127 5222 ACTIVE TCV.D-52E-72398 08G012 Diesel Generator OPEN/CLOSED N/A 3 7 TCV-52E-7239C SDG-C -DIESEL E3 DIG JACKIET COOLANT 3-WAY M-377. SHiT 2 D/G-7 OPEN/CLOSED N/A COMMON B COOLING THERMOSTATIC CONTROL VALVE 127 5322 ACTIVE TCV-0-52E-7239C OCGO12 Diesel Generator OPEN/CLOSED N/A 3 7 TCV-52E-7239D SDG4O -DIESEL E4 DIG JACKET COOLANT 3-WAY M-377, SHT 2 DIG-. OPEN/CLOSED N/A COMMON B COOLING THERMOSTATIC CONTROL VALVE 127 5422 ACTIVE TCV-0-.2E-72390 0OGO12 Diesel Generator OPEN/CLOSED N/A 3 7 TCV-52F-7238A SDG-A -DIESEL El DIG AIR COOLANT 3-WAY M-377, SHT 2 DIG-3 OPEN/CLOSED N/A COMMON B COOLING THERMOSTATIC CONTROL VALVE 127 5117 ACTIVE TCV-0-52F-7238A OAGO12 Dies Gerwator OPEN/CLOSED N/A 3 7 TCV-52F.7238S SDG-8 -DIESEL E2 DIG AIR COOLANT 3-WAY M-377. SliT 2 D/G-5 OPEN/CLOSED N/A -COMMON B COOLING THERMOSTATIC CONTROL VALVE 127 5217 ACTIVE TCV.O.52F-7238B 08G012 Diesel Generatlor OPEN/CLOSED N/A 3 7 TCV-52F-7238C SDG-C

• DIESEL E3 DIG AIR COOLANT 3-WAY M-377. SHT 2 D/G-7 OPEN/CLOSED N/A COMMON B 5317 ACTIVE COOLING THERMOSTATIC CONTROL VALVE 127 Diesel Generator OPEN/CLOSED N/A TCV-O-52F-7238C 0CG012 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 C'nrrpn-nnndfinrn.t No

• Rq-19-173 B-74 DOCUMENT NO. 006740084-0001 REVISION 2 TRAIN SOUG Cl PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Drawing No.DATE: WAM PAGE 74 Norm mate Motive power Support System Desired State Conw power Supp Sys dwg Equo [D System Uni Eval reqd? PIMS ID Eqcup Descripton ROB Mother Comp Loc Code Room Elev Line No Function Builing 3 7 TCV.52F-72380 SOG-D -DIESEL E4 DIG AIR COOLANT 3-WAY M-377. SHT 2 DIG-9 OPEN/CLOSED N/A COMMON 8 COOLING THERMOSTATIC CONTROL VALVE 127 5417 ACTIVE TCV-.-52F-7238D O(DG012 Diesel Generator OPEN/CLOSED WA 3 7 TCV-52G-7240A SDG-A -LUBE OIL El DIG LUSE OIL 3-WAY M-377. SHT 3 D/G-3 OPEN/CLOSED NWA COMMON 0 THERMOSTATIC CONTROL VALVE 127 5138 ACTIVE TCV-0-52G.7240A OAGOI2 Diesel Generator OPEN WA 3 7 TCV.52G-7240B SDG-B -LUSE OIL E2 D/G LUBE OIL 3-WAY M-377. SHT 3 D/G-5 OPEN/CLOSED NIA COMMON B THERMOSTATIC CONTROL VALVE 127 5238 ACTIVE TCV-0.52G-7240B 08G012 Diesel Generator OPEN NIA 3 7 TCV-52G-7240C SDG-C -LUBE OIL E3 DIG LUSE OIL 3-WAY M-377. SlT 3 D/G-7 OPEN/CLOSED NWA COMMON B THERMOSTATIC CONTROL VALVE 127 5338 ACTIVE TCV-O-52G-7240C OCGO12 D Genera" OPEN WA 3 7 TCV-52G.7240D SG-O -LUBE OIL E4 DIG LUBE OIL 3-WAY M-377. SKT 3 DIG-9 OPEN/CLOSED WA COMMON B THERMOSTATIC CONTROL VALVE 127 5438 ACTIVE TCV4O-52G-7240D 00G012 Diesel Genertor OPEN WA 3 SA MO-33-0498 ESW EMERGENCY SERVICE WATER RETURN M-330 DIG-2 OPEN 00856 COMMON SR TODISCHPOND 121 5620 ACTIVE MO-0-33-0498 Diesel Generator CLOSED -3 8A MO-48-0501A ESW ESWA INLET TO ECT RESERVOIR M-330 ECT-1 OPEN 00898 COMMON SR 114 5623 ACTIVE MO-0-480501A Emergency Cooing OPEN/CLOSED 3 8A MO-48.001B ESW ESW B INLET TO ECT RESERVOIR M-330 ECT-1 CLOSED 00897 COMMON SR 114 5624 ACTIVE MO-o048-0501B Emergency Cooling OPEN/CLOSED Towers 3 GA MO-48-OSOIC ESW ESW C INLET TO ECT RESERVOIR M-330 ECT-1 CLOSED 00899 COMMON SR 114 5625 ACTIVE M048-5C Emergncy Cooing OPEN/CLOSED

-Towers 3 a MO-48-0502A HPSW HPSWA INLET TO ECT RESERVOIR M-330 ECT-1 OPEN NIR COMMON R 114 5&14 PASSIVE MO--48.0502A Emergency Cooling OPEN NJR Towers 3 8 MO-48.05-M8 HPSW HPSW B INLET TO ECT RESERVOIR M-330 ECT-1 OPEN NIR COMMON R 114 5615 PASSIVE MO-O48-00B Emergency Cooling OPEN NR Towers 3 BA MO-48-0502C HPSW HPSW C INLET TO ECT RESERVOIR M-330 ECT-1 CLOSED 00899 COMMON SR 114 56`16 ACTIVE MO-0-480502C Emergenry Coo"g OPEN -Towers 3 a SV-00540-I SIDG-A -INSTRUMENT AIR BLOCK VALVE FOR M-385 DJG-4 DEENERGIZED 00853 COMMON BR 5114 ACTIVE VENTILATION PUO-4(IF-00540-01 CIAV9I 127 Diesel Generator DEE/IENER SV4-38-00640-01 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (,nrrp.qnnninrlp.

Nn

• RR-12-17.3 B-75 DOCUMENT NO. 0067-00104-O001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3/28196 PAGE 75 Norm state Mouve power Sppord System Desired Slate Cord power Supp Sys og TRAIN Unit SOUG CI Equip ID Eval reqd? PIMS ID Systm Notes Equip Description ROB Mother Comip Drawing No.Loc Code Room Elev LineNo Function awidin 3 8 SV-00540-2 SOG-8 -INSTRUMENT AIR BLOCK VALVE FOR M-385 O/G-6 DEENERGIZED 00854 COMMON BR VENTILATION POO.40F.)00540-M 127 5214 ACTIVE SV-0-368-0040-02 08V91 Diesel Generator DEENIENER 3 8 SV-00540-3

$OG.C -INSTRUMENT AIR BLOCK VALVE FOR M-385 O/G-8 DEENERGIZED 00855 COMMON BR VENTILATION P0-40F-DV540-03 127 5314 ACTIVE SV.O-360-00540-03 OCV91 Diesel Generator DEENIENER 3 S SVP00X40-4 SDG.- -INSTRUMENT AIR BLOCK VALVE FOR M-385 DIG-10 DEENERGIZED 00856 COMMON BR VENTILATION PO-O-40F4W540-04 127 5414 ACTIVE SV-O-368-00540-04 0DV91 Diesel Generator DEEN/ENER 3 Be SV-368-0(019 HVAC I/A SOLENOID VALVE FOR M1-399. SHT I R/W-32 ENER/DEEN 00849 OAV34 COMMON SR PO-O40W-O0019-01

+ 00019-02.

808, 822-01. 165 5905 ACTIVE SV.O-368-02019 Radwaste Bldg ENERGIZED

-M-119-48 3 88 SV-388-00020 HVAC VA SOLENOID VALVE FOR M-399. SHT I RAN-32 DEEN/ENER 00850 OBV34 COMMON SR PO04)W-0021

+ 000204)7 809,803-01, 165 598 ACTIVM SV-0-388-0002

-02.-03 Radwasta Bldg ENERGIZED

-M-119.48 3 88 SV-386-00025 HVAC I/A SOLENOID VALVE FOR M-399. SlT 4 RNW-32 ENER/DEEN 00849 OAV35 COMMON SR PO-.-40W.00025-0I

+ 00025-02 165 5912 ACTIVE SV-O.388-00025 Radwaste Bkg ENERGIZED M-119-48 3 88 SV-368-00026 WVAC IfA SOLENOID VALVE FOR M1-99. SHT 4 R/W-32 DEEN/ENER 00850 08V35 COMMON SR PO--4OW-OD)26-01

• 00026-0Z 00816-01 + 165 5912 ACTIVE SV--36-0002 00816-02 Radwaste Blsig ENERGIZED

-M-1 19-48 3 8 SV-3.B-00031 HVAC iiA SOLENOID VALVE FOR M-399, SHT 4 RNV-32 ENERJDEEN 00849 OAV36 COMMON B PO0--40W-00031-01

+ 00031-02 165 5917 ACTIVE SV-0-368-00031 PO-0-40W-00031-01 102 Radwaste Bldg ENERGIZED 3 88 SV-36B-00032 WVAC UA SOLENOID VALVE FOR M-399, SHT 4 RNV-32 DEENIENER 00850 08V36 COMMON SR PO-0.40W-00032-01

+ 00032-02 165 5917 ACTIVE SV-36B0 Radwaste Bldg ENERGIZED -I 3 88 SV-388-0241A ESW YA SOLENOID W FOR AO-0241A DIG El M-315. SHT 1 D/G-3 ENERGIZED N/R COMMON OR ESW OUTLET 127 5529 ACTIVE SV--360241A AO-33-0241A DieS Generator DEENERGIZED NIR 3 88 SV-368-0241B ESW VA SOLENOID W FOR AO-0241B D/G E2 M-315. SNT 1 0/I-5 ENERGIZED N/R COMMON OR ESW OUTLET 127 5531 ACTIVE SV-O-368-0241B AO-33-0241B Diesel Generator DEENERGIZED NJR 3 s8 SV.368-0241C ESW IA SOLENOID W FOR AO-0241C D/G E3 M-315, SHT 1 DIG-7 ENERGIZED NIR 1 COMMON BR ESW OUTLET 127 5533 ACTIVE SV-O-36B-0241C AO-33-0241C Diesel Generator DEENERGIZED NIR 3 8s SV.368-0241 D ESW YA SOLENOID W FOR AO-0241D D/G E4 M-315. SHT 1 D/G-9 ENERGIZED NiR COMMON OR 5535 ACTIVE ESW OUTLET AO-33-0241D 127 Diesel Generator DEENERGIZED MIR SV-0-368-02410 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnrrP..qnndpnrn

.Nn

• RS-19-173 B-76 DOCUMENT NO. 006-00084-40X1 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3=28196 PAGE 76 Norm slate Motive power Support System Desbud State Ca& power Supp Sys "eg REVISION 2 TRAIN Un4 SOUG CI Equip ID Eval reqfd? PIMS ID System Notes Eq* Descro ROB Mother Camp Drawing No.Loc Code Room Bev Line No Function Bulding 3 8 SV-52C-7233A SOG-A -STARTING El DIG AIR START SOLENOID VALVE M-377, SHT 1 DIG-3 DE-ENERGIZE OAD13 COMMON BR AIR (CONTROLS AO-7231A) 127 5106 ACTIVE SV.0-52C-7233A AO-52C-7231A Diesel Generator ENERGIZED 3 8 SV-52C-72336 SDG-B -STARTING E2 DIG AIR START SOLENOID VALVE M-377. SHT 1 D0G-" DE-ENERGIZE 0BD13 COMMON BR AIR (CONTROLS AO-72318) 127 5208 ACTIVE SV-0-52C-7233B AO-52C-7231B 0iesel Generator ENERGIZED 3 8 SV-52C-7233C SOG-C -STARTING E3 D/G AIR START SOLENOID VALVE M-377, SHT I D/G-7 DE-ENERGIZE 0C013 COMMON BR AIR (CONTROLS AO-7231C) 127 5306 ACTIVE SV-0-62C-7233C AO-52C-7231C Diesel Generator ENERGIZED 3 8 SV-52C-72330 SDG-O -STARTING E4 DIG AIR START SOLENOID VALVE M-377, SHlT I O/G-9 0E-ENERGIZE 0DD13 COMMON SR AIR (CONTROLS AO-7231D) 127 5406 ACTIVE SV-O-52C-72330 AO-52C-7231D Diesel Generator ENERGIZED 3 6 SV-52C-7234A SOG-A -STARTING El DIG AIR START SOLENOID VALVE M-377. SHlT 1 DIG-3 DE-ENERGIZE 0AD13 COMMON BR AIR (CONTROLS AO-7232A) 127 5107 ACTIVE SV-)-52C-7234A AO-52C-7232A Diesel Generatr ENERGIZED

-3 8 SV-52C-7234B SDG-B -STARTING E2 DIG AIR START SOLENOID VALVE M-377, SHT I D/G-5 0E-ENERGIZE 08013 COMMON BR AIR (CONTROLS AO-7232B) 127 5207 ACTIVE SV-O-52C-7234B AO-52C-7232B Diesel Generator ENERGIZE -3 8 SV-52C-7234C SDG-C -STARTING E3 D/G AIR START SOLENOID VALVE M-377, SHlT 1 DIG-7 0E-ENERGIZE 0CD13 COMMON OR AIR (CONTROLS AO-7232C) 127 5307 ACTIVE SV.O-52C-7234C AO-52C-7232C Diesel Generator ENERGIZED 3 8 SV-52C-72340 SDG-D -STARTING E4 DIG AIR START SOLENOID VALVE M-377. SNIT 1 DIG-9 DE-ENERGIZE 00013 COMMON BR AIR (CONTROLS AO-7232D) 127 5407 ACTIVE SV-O-52C-7234D AO-52C-72320 Diesel Genrwator ENERGIZE 3 9 0AK032 ESW & HPSW "Ar EMERGENCY COOLING TOWER FAN M-330 ECT-6 OFF 00895 t OD9513 COMMON S 195 5617 ACTIVE OAK032 Emergency Cooing OFFION Towers U'8-3-4 3 9 0AV035 HVAC EMERG SWITCHGEAR VENTILATION M-399. Si-t 4 RAN-32 ONIOFF 00o49 COMMON SR EXHAUST FAN A 165 5825 ACTIVE 0AV35 Radwaste Bldg ON -3 9 GAV036 HVAC BATTERY ROOM EXHAUST FAN A M-399. SHT 4 RNV-32 ON/OFF 00849 COMMON SR 165 5818 ACTIVE 0AV038 Radwasto Blgl ON 3 9 OAV064 SOG-A -El DIG BUILDING VENTILATION SUPPLY M.85 D/G-13 OFF 00853 COMMON SR VENTILATION FAN A 151 5109 ACTIVE 0AV064 Diesel Generator ON S-979, M-51-57. 69 77 3 9 0AVO91 SDG-A -El DIG BUILDING VENT SUPPLEMENT M-385 DIG-14 OFF 00853 COMMON SR VENTILATION SUPPLY FAN 151 5113 ACTIVE GAV091 Diesel Genertor OFF/ON -VMAN M-70-35 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrre..nonndr.-.

Nol Rq-1 2-173 B-77 DOCUMENT NO. 0067-0084.0001 REVISION 2 TRAIN SOUG a Equip ID Eval req'd? PINS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST DATE: 3r2=PAGE 77 Norm state Natife power Support System Desired State Contr power &Vpp Sys dwg System Notes Equp DesrCaptlo ROB Mother Camnp Drawing No.Loc Code Room Elev Line No Fwution Budding 3 9 OBK032 ESW& HPSW "B EMERGENCY COOUNG TOWER FAN M-330 ECT.6 OFF 00894 0089413 COMMON S 195 5618 ACTrVE 0eK032 Emergency Cooat OFF/ON Towers M78-3-4 3 9 OBV035 HVAC EMERG SWITCHGEAR VENTILATION M-399. SNT 4 R/W-32 OFF/ON 00850 COMMON SR EXHAUST FAN B 165 O 5821 ACTIVE 08VO35 Radwaste Bldg O 3 9 OUVOM HVAC BATTERY ROOM EXHAUST FAN 8 ,-399, SHT 4 R/W-32 OFFION 00550 I COMMON SR 165 5830 ACTIVE 0OV036 Redwaste Bldg ON 3 9 OBV054 SOG-B -E2 DfG BUILDING VENTILATION SUPPLY m-385 D0G-.1 OFF 00854 COMMON SR VENTILATION FAN 6 151 5209 ACTIVE 08VO64 Diesel Generator ON S-979, M-51-57, 69. 77 3 9 OaV091 SDG- -. E2 BIG BUILDING VENT SUPPLEMENT M-385 DIG-16 OFF 00854 COMMON SR VENTILATION SUPPLY FAN 151 5213 ACTIVE 08V091 oiesel Generator OFF/ON M VMAN M-70-35 3 9 OCKD32 ESW & HPSW C" EMERGENCY COOLING TOWER FAN M-330 ECT4 OFF 00896 0089613 COMMON S 1965 5619 ACTIVE OCK032 Emergency Cooting OFF/ON Towers M78-3-4 3,9 OgV064 SDG-C. E3 DIG BUJLDWG VENTILATION SUPPLY M-3W5 DIG-17 OFF 00855 COMMON SR VENTILATION FAN C 151 6309 ACTIVE 0CV064 ew eGeemetor ON S-979. M-51-57. 69. 77 3 9 0CV091 SDG-C -E3 D/G BUILDING VENT SUPPLEMENT 1385 IG-18 OFF 00855 COMMON SR VENTILATION SUPPLY FAN 151 5313 ACTIVE 0CV091 Diesel Generator OFF/ON VMAN M-70-35 3 9 0VC064 SDG-0 .E4 DIG BUILDING VENTILATION SUPPLY M-385 0/G-19 OFF 00556 COMMON SR VENTILATION FAN 0 151 5409 ACTIVE 0OV064 Diesel Generator ON S-979, M-51-57, 69. 77 3 9 ODVO91 SDG-D- E4 D/G BUILDING VENT SUPPLEMENT M-385 0/G-20 OFF 00B56 COMMON SR VENTILATION SUPPLY FAN 151 5413 ACTIVE OOV091 Diesel Generator OFFION VMAN M-70-35 3 10 00F043 HVAC EMERG SWGR VENT SUPPLY M-399. SHT 1 RNW-32 OPERABLE N/A COMMON S ROLL-FILTIER 165 5800 PASSIVE 00F043 Redwaste Sl0g NWA N/A 3 10 0AV034 HVAC EMERG SWGR AND BTRY ROOM M-399. SHT I RAN-32 ON/OFF 00849 COMMON SR VENTILATION SUPPLY FAN A 165 5806 ACTIVE OAV034 Radwaste Bld ON S-982 3 10 08V034 HVAC EMERG SWGR AND BTRY ROOM M-399, SHT I R/W-32 OFF/ON 00850 rnuunu a VENTILATION SUPPLY FAN B 5814 ACTIVE 0BV034 0AV034 Radwaste Bldg ON S-982 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (,nrr..nnndrinr.f-Nn

• R.S-1-173 B-78 DOCUMENT NO. 006740084-001 REVISION 2 TRAIN SOUG CI Equip I Unit Eval rec'd? PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EGUIPMENT LIST DATE: 312896 PAGE 78 Norm stats Motive power Suppor system Oesired Slate Cowt power Supp Sys "o System Notes Equip Description ROB Motner Comp Drawing No.Loc Code Room Elev Line No Functin on 3 10 PO-00272-1 SDGA- MASTER FOR El DIG BLDG VENT SUP M.385 D/G-13 CLOSED NIA COMMON S VENTILATION FAN OAV064 OUTSIDE AIR DAMPER 151 110 ACTIVE PO-0-40F-00272-01 Diesel Genarator OPEN N/A 3 10 P-00272-2 SOG A- MASTER FOR El D/G BLDG VENT SUP M-385 0/0-13 OPEN N/A COMMON S VENTILATION FAN OAV064 RETURN AIR DAMPER 151 5111 ACTIVE PO-4OF-00272-02 Diesel Generator CLOSED N/A 3 to P0-00273-1 SOGB- MASTER FOR E2 DIG BLDG VENT SUP M-385 DIG-iS CLOSED N/A COMMON S VENTILATION FAN 08V064 OUTSIDE AIR DAMPER 151 5210 ACTIVE PO-0-40F-00273-01 Diesel Generator OPEN NIA 3 10 PO-00273-2 SDG B -MASTER FOR E2 D/G BLDG VENT SUP M-385 D/G-t5 OPEN NZA COMMON S VENTILATION FAN 08V064 RETURN AIR DAMPER 151 5211 ACTIVE PO-0-40F-O273-02 Diesel Generator CLOSED WA 3 10 P04)0274-1 S6G C- MASTER FOR E3 DIG BLDG VENT SUP M-385 DIG-17 CLOSED N/A COMMON S VENTILATION FAN 0CV064 OUTSIDE AIR DAMPER 151 6310 ACTIVE PO-O..F..274-0Diesel Generator OPEN WA 3 10 PO-00274-2 SDGC- MASTER FOR E3 DIG BLDG VENT SUP M-385 D/G-17 OPEN N/A COMMON S VENTILATION FAN OCV064 RETURN AIR DAMPER 151 5311 ACTIVE PO--4F-00274-02 Diesel Generator CLOSED N/A 3 10 PO-00275-1 SOG0- MASTER FOR E4 DIG BLDG VENT SUP M-385 DIG-19 CLOSED N/A COMMON S VENTILATION FAN 00V064 OUTSIDE AIR DAMPER 151 5410 ACTIVE PO-O-40F-00275-01 Diesel Generator OPEN N/A 3 10 PO-00275-2 SOG D- MASTER FOR E4 D/G BLDG VENT SUP M-385 D0G-19 OPEN N/A COMMON S VENTILATION FAN ODVOS4 RETURN AIR DAMPER 151 5411 ACTIVE PO-.O40F-00275-02 Diesel Generator CLOSED N/A 3 10 PO-00540-1 S6GA- El DIG BLDG VENT SUPPLEMENTAL SUP M-385 D/G-4 CLOSED N/A COMMON S VENTILATION FAN GAVOSI DAMPER 127 5115 ACTIVE PO-O-40F-00540-01 Diesel Generator OPEN N/A 3 10 PO-00540-2 SDG B -E2 DIG BLDG VENT SUPPLEMENTAL SUP M-385 DIG-S CLOSED N/A COMMON S VENTILATION FAN 08V091 DAMPER 127 5216 ACTIVE PO-0-40F-0054O-02 Diesel Generator OPEN N/A 3 10 PO-00540-3 SOG C -E3 DIG BLDG VENT SUPPLEMENTAL SUP M-385 DIG-8 CLOSED N/A COMMON S VENTILATION FAN OCV091 DAMPER 127 5315 ACTIVE PO-O40F-00540-03 0iesel Generator OPEN N/A 3 10 PO-00540.4 SDG 0- E4 DIG BLDG VENT SUPPLEMENTAL SUP M-385 DIG-1 CLOSED N/A COMMON 8 VENTILATION FAN ODV091 DAMPER in 5415 ACTIVE PO-0.4OF-0054O.O4 Diesel Generator OPEN N/A 3 10 PO.40W-OO17-02 HVAC MASTER FOR EMERG SWGR1BTRY RMS M-399, SHIT 4 RNV-32 OPEN N/A COMMON S 5833 ACTIVE VENT EXH TO CR ROOF DAMPER 165 Radwaste sBd CLOSED N/A PO-O-4OW-OW017-02 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrrp.mnnndr.nr-p Nno RS-19-173 B-79 DOCUMENT NO. 006740084-ODo1 PEACH 8OTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Motive power Desired State Co., po.e DATE: 3/a9 PAGE 79 REVISION 2 TRAIN SQUG cI Eve] fqd?Equip PIMS ID System No"s Equip Descrptor ROB Mothe Camp Drawng No.Loc Code Room Elev S& ort System Supp Sys dwg Life No Function BulUig 3 10 PO-400019.01 WVAC EMERG SWGR + BATTERY ROOMS M-399. SHT I R/W-32 OPEN/CLOSED N/A HVAC N2 COMMON S VENT SUP FAN OAV034 INLET DAMPER 165 SV-O-36B-00019 5804 ACTIVE PO.0-40W*0019.01 Radwaste Bldg OPEN N/A M-399. SHT 1 3 10 PO-40WOWO 9-02 KVAC EMERG SWGR + BATTERY ROOMS M-399, SHT i RJW-32 OPENICLOSED N/A HVAC N2 COMMON S VENT SUP FAN 0AV034 OUTLET 165 SV-0-368.-001S 5W07 ACTIVM PO4) 19.02 Radwaste Bldg OPEN N/A M-399, SHT 1 3 10 PO-4WOVr#0020.1 WVAC EMERG SWGR + BATTERY ROOMS M-399. SHT 1 RNV-32 CLOSED/OPEN N/A HVAC N2 COMMON S VENT SUP FAN 08V034 INLET DAMPER 165 SV.0-3S8-00020 5811 ACTIVE P-0-40W-0X)020-01 Radwaste Bldg OPEN N/A M-399, SliT i 3 10 PO-40W0002002 WVAC EMERG SWGR + BATTERY ROOMS M-399, S14T I RNV-32 CLOSED/OPEN N/A HVAC N2 COMMON S VENT SUP FAN 08V034 OUTLET DAMPER 165 SV-O-36B-00020 58s5 ACTIVE PO-40W-000204)2 Radwaste Bldg OPEN N/A M-399, SHT 1 3 10 PO-40W00025O1 HVAC EMERGENCY SWITCHGEAR VENT M-399. SHIT 4 R/W-32 OPEN N/A HVAC N2 COMMON S EXHAUST FAN OAV035 INLET DAMPER 165 SV-0I-368-0025 5623 PASSIVE PO4)4W00025-.01 Radaste BMg OPEN N/A M-399. SHT 4 3 10 PO-40W4-00025.02 NVAC EMERGENCY SWITCHGEAR VENT M-399. SHT 4 RNV-32 OPEN N/A HVAC N2 COMMON S EXHAUST FAN OAV035 OUTLET DAMPER 165 SV-0-368-00025 5826 PASSIVE PO-O-40W.0002502 Radwaste Bldg OPEN N/A M-399. SHT 4 3 10 PO4WV4)00261 HVAC EMERGENCY SWITCHGEAR VENT M-399, SHT 4 R/V-32 CLOSED N/A HVAC N2 COMMON S EXHAUST FAN OBVO35 INLET DAMPER 165 SV-0-368-00026 5628 ACTIVE PO-O-40W.00025.01 Radwaste Bldg OPEN N/A M-99. SlIT 4 3 10 PO-40W-O0026-02 HVAC EMERGENCY SWITCHGEAR VENT M-399, SlIT 4 RNV-32 CLOSED N/A HVAC N2 COMMON S EXHAUST FAN 08V035 OUTLET DAMPER 165 SV--368-00026 5831 ACTIVE PO-O-40W-00026-02 Radwaste Bldg OPEN N/A M-399, SHT 4 3 10 PO-40W-0031-01 HVAC BATTERY ROOM VENT EXHAUST FAN M-399. SHT 4 R/W-32 OPEN/CLOSED N/A HVAC N2 COMMON S OAV03= INLET DAMPER 165 SV-0-368-00031 5W17 ACTIVE PO-0-40W-00031-01 Radwaste BUDg OPEN N/A M-399. SHT 4 3 10 PO-40W-(4X31.02 HVAC BATrERY ROOM VENT EXHAUST FAN M-399. SHT 4 RAW-32 OPEN/CLOSED N/A F HVAC N2 COMMON S OAV036 OUTLET DAMPER 165 SV.0-36B-00031 5619 ACTIVE PO-O-40W-00031.2 Radwaste Bldg OPEN N/A M-399. SlIT 4 3 10 PO-40W00032-01 HVAC BATTERY ROOM VENT EXHAUST FAN M-399, SlIT 4 RNW-32 CLOSED/OPEN N/A HVAC N2 COMMON S 08V036 INLET DAMPER 165 SV-0-36B-00032 5620 ACTIVE PO--40W.00032-01 Radfaste Bldg OPEN N/A M-399, SlIT 4 3 10 PO-40W-00032-02 HVAC BATTERY ROOM VENT EXHAUST FAN 11-399, SlIT 4 R/W-32 CLOSED/OPEN N/A HVAC N2 COMMON S OBV03S OUTLET DAMPER 1651 SV,-O-368,O0032 5622 ACTIVE P--000302Rdat l OPEN N/A M-399. SHfT 4 3 14 00Y03 EPS 120VAC DISTRIBUTION PANEL E-286 SHT 1 RIN-21 ENERGIZED 00X103 -COMMON S 135 1 8001 ACTIVE 00Y003 Radwaste Bldg ENERGIZED Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 florr..nondp.nr.j Nn

• RR-1-1773 B-80 DOCUMENT NO. 007-01110004=1 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3128196 PAGE 80 Noam state Motive power Sump System Desired State Cony power Supp Sys dwg TRAIN Uni SQUG CI Equip ID Eval req'd? PIMS ID System Not"s Equip Des- on ROB Mothe Camp Drawing No.Loc Code Room Elev Line No Function Buiding 3 14 0AD13 EPS 125VDC DIST. PANEL (0A013) E-26. SHT 2 010-4 ENERGIZED 20D21 COMMON S 127 8000 ACTIVE OAD13 Diesel Generator ENERGIZED 3 14 0B013 EPS 125VDC DIST. PANEL (08D13) E-26. SHT 2 D0G-6 ENERGIZED 30023 COMMON S 127 8000 ACTIVE 0BD13 Diesel Generator ENERGIZED

-3 14 00O13 EPS 125VOC DIST. PANEL (OCD13) E-26. SHT 2 DIG-8 ENERGIZED 280306 COMMON S 127 8000 ACTIVE 0C013 Diesel Generator ENERGIZED 3 14 00013 EPS 12SVDC DIST. PANEL (0DD13) E-26. SHT 2 DIG-10 ENERGIZED 3D0306 COMMON S 127 8000 ACTIVE 00013 Diesel Generator ENERGIZED 3 17 OAG12 SDG-A E1 STANDBY DIESEL GENERATOR E-8 D/G-3 OFF OAD13 COMMON SR 127 8001 ACTIVE 0AG012 Diesel Generator ON 6280-ES-155-1 3 17 08012 SDG48 E2 STANDBY DIESEL GENERATOR E-8 DIG-5 OFF 08D13 COMMON SR 127 8003 ACTIVE 08GO12 Diesel Generator ON 6280-E5-155-1 3 17 0CG12 SOG-C E3 STANDBY DIESEL GENERATOR E-8 DIG-7 OFF 0CO13 COMMON SR 127 8006 ACTIVE OCGO12 Diesel Generator ON 6280-E5-155-1 3 17 0OG12 SDG-, E4 STANDBY DIESEL GENERATOR E-8 D/G-9 OFF 0OD13 COMMON SR 127 8009 ACTIVE 000012 Diesel Generator ON 6280-E5-155-1 3 IS PC-36B-00016 HVAC EMERG SWGR AIR SUPPLY PRESS M-399, SHT 1 RPW-32 OPERABLE NIA COMMON 8 CONTROL (HIGHEST PRESSURE RELAY) 165 5906 ACTIVE PC-00016 0OF043 Radwaste Bldg OPERABLE NIA SK-M-651 3 19 HD-550A SDG-A El DIG CARDOX HEAT DETECTOR M-46-24. SHT 2 01G-3 OPERABLE N/A COMMON S 127 ACTIVE HD-550A Diesel Generator OPERABLE N/A M-713-1.1 3 19 HD-550B S0G-A El DIG CARDOX HEAT DETECTOR M-46-24. SHIT 2 0/G-3 OPERABLE NWA COMMON S 127 ACTIVE HD-55(B Diesel Generator OPERABLE NIA M-713.-1 3 19 HID-551A SDG-A El DIG CAROOX HEAT DETECTOR M-46-24, SHT 2 D1G-3 OPERABLE NIA COMMON S 127 ACTIVE HD-551A Diesel Generator OPERABLE WA M-3H132-1-1 3 19 HD-551B SDG-.A El1 DIG CARDOX HEAT DETECTOR M-46-24. SHlT 2 01G-3 OPERABLE N/A COMMON S ACTIVE 127 Diesel Generator OPERABLE NIA HD-5518 M-713-1-1 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrrpnondi.nrtA Nn.: RS-12-1 73 B-81 DOCUMENT NO. 0067-00084-D001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Support System Supp Sys dwg DATE: 3W25M6 PAGE S1 TRAIN Uni SOUG CI Equi IQ Eva[ racd? PIMS ID Function System Notes Equip Desaton ROB Mother Camp Drawing No.Loc Codo Room Elev Norm state DOesired Slate Motioe pmer Cor* poorer 3 19 HD-552A SDG-A El D/G CARDOX HEAT DETECTOR M-46-24, SHT 2 0/G-3 OPERABLE N/A COMMON S 127 ACTIVE HD-552A Desel Generator OPERABLE N/A M1-713-1-I 3 19 HD-552B SDG-A El D/G CARDOX HEAT DETECTOR M-46-24. SHT 2 D/0-3 OPERABLE N/A COMMON S 127 ACTIVE HD-552B Diesel Generator OPERABLE N/A 11-713-1-1 3 19 HD-553A SDG-A El D/G CARDOX HEAT DETECTOR M-45-24, SHT 2 O/0-3 OPERABLE N/A COMMON S 127 ACTIVE HD-553A Diesel Generator OPERABLE N/A M M1-713-1-1 3 19 HD-553B SOG-A El DIG CARDOX HEAT DETECTOR M1-4-24, SHT 2 0/G-3 OPERABLE N/A 1 COMMON S 127 ACTIVE. HD-5538 Diesel Generator OPERABLE N/A M-713-1-1 3 19 HO-554A SDG-A El 01G CARDOX HEAT DETECTOR M-46-24. SHT 2 D/1.3 OPERABLE N/A COMMON S 127 ACTIVE HD-554A Diesel Generator OPERABLE NZA M-713-1-1 3 19 HO-5548 SOG-A El D/G CARDOX HEAT DETECTOR M-46-24, SHT 2 D/G-3 OPERABLE N/A COMMON S 127 ACTIVE HD-554B Diesel Generator OPERABLE N/A M-713-1-1 3 19 I-D-555A SOG-A El DIG CARDOX HEAT DETECTOR M-48-24, SHT 2 D0G-3 OPERABLE N/A COMMON S 127 ACTIVE HD-555A Diesel Generator OPERABLE N/A M-713-1-1 3 19 HD-5558 SDG-A El DIG CARDOX HEAT DETECTOR M-46-24, SHT 2 DIG-3 OPERABLE N/A COMMON S 127 ACTIVE HO-5558 Diesel Generator OPERABLE N/A M-713-1-4 3 19 SDG-A El DIG CARDOX HEAT DETECTOR M-46-24. SHT 2 O/G-3 OPERABLE N/A COMMON S 127 ACTIVE HD-556A Diesel Generator OPERABLE N/A M-713-1-1 3 19 HD-556WB SG-A El D/G CARDOX HEAT DETECTOR M-46-24. SHT 2 0/G-3 OPERABLE N/A COMMON S 127 ACTIVE HD-5568 Diesel Generator OPERABLE N/A M-713-1-1 3 1s HD-557A SOG-A El D/G CARDOX HEAT DETECTOR M-46-24, SlT 2 D/G-3 OPERABLE N/A COMMON S 127 ACTIVE HD-557A Diesel Generator OPERABLE N/A M-713-1-1 3 19 0D-557B SDG-A El DIG CARDOX HEAT DETECTOR M-46-24, SilT 2 D/G-3 OPERABLE N/A COMMON S 127 ACTIVE HD-557B Diesel Geneator OPERABLE N/A 1M-713-1-1 3 19 COMMON S ACTIVE MD-796A HO-796A SDG4-E2 DIG CARDOX HEAT DETECTOR M,.46-24, SHT 3 D/G-5 OPERABLE N/A 127 Diesel Generator OPERABLE N/A M-713-1-1 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn "R--12-173 B-82 DOCUMENT NO. 0067-0084-O401 REVISION 2 TRAIN SUG CI Equip ID Unit Eva neqd? PIMSI D PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LOST DATE: 3128/96 PAGE 82 Nosm State Motive power SUiPP Syster Deske State Compower Stutp Sys dwg System Notes Equip Descipelon ROB Comp Drawing NoQ Loc Code Room EIev Lne No Fundtbi Buaili9 3 19 HD47968 SDG-B E2 I/G CARDOX HEAT DETECTOR M-46-24, SHIT 3 DIG-S OPERABLE N/A COMMON S 127 ACTIVE 140-7968 Diesel Generator OPERABLE N/A 3 19 HD-797A SDG-8 E2 D/G CAROOX HEAT DETECTOR M-46-24. SHT 3 D/G-5 OPERABLE N/A COMMON S 127 ACTIVE HD-797A Diesel Generator OPERABLE N/A M-713-1-1 3 19 HtD-7975 SDG-4 E2 D/G CARDOX HEAT DETECTOR M-46-24, SHT 3 D/G-5 OPERABLE N/A COMMON S 127 ACTIVE HD-7978 Diesel Generator OPERABLE N/A M-713-1-1 3 19 HD-79aA SDG-B E2 DIG CARDOX HEAT DETECTOR M-46-24, SHlT 3 DIG-5 OPERABLE N/A COMMON S 127 ACTIVE HD-798A Diesel Generator OPERABLE N/A M-713-1-1 3 19 HD-7988 SDG-8 E2 DIG CARDOX HEAT DETECTOR M-46-24, SHT 3 D/G-5 OPERABLE NIA COMMON S 127 ACTIVE HD-798B Diesel Genertor OPERABLE NIA M-713-1-1 3 19 HD-79TA SDG-8 E2 DIG CARDOX HEAT DETECTOR M-46-24. SHT 3 D/G-5 OPERABLE N/A COMMON S 127 ACTIVE HO-799A Diese Generator OPERABLE N/A M-713-1-1 3 19 HD-7998 SG-B E2 D/G CARDOX HEAT DETECTOR M-46-24, SHT 3 D/G-5 OPERABLE N/A COMMON S 127 ACTIVE HD-7998 Diesel Generator OPERABLE N/A M-713-1-1 3 19 HD-800A SDG-B E2 DIG CARDOX HEAT DETECTOR M-46-24, SPIT 3 D/G-5 OPERABLE NIA COMMON S 127 ACTIVE HD-80CDA Diesel Generator OPERABLE N/A M-713-1-1 3 19 HD-800B SDG-8 E2 O/G CARDOX HEAT DETECTOR M.46-24, SHlT 3 DIG-S OPERABLE N/A COMMON $ 127 ACTIVE HD-SODB Diesel Generator OPERABLE N/A M-713-1-1 3 19 HD-801A SDG-4 E2 DIG CAROOX HEAT DETECTOR M-48-24, SHT 3 DIG-S OPERABLE N/A COMMON S 127 ACTIVE HD-801A Diesel Generator OPERABLE NIA M-713-1-t 3 19 HD-801B SDG-B E2 DIG CARDOX HEAT DETECTOR M-46-24, SHT 3 DIG-5 OPERABLE N/A COMMON S 127 ACTIVE HD-801B Diesel Genert OPERABLE N/A M-713-1-1 3 19 HD-802A SDG-B E2 DIG CARDOX HEAT DETECTOR M-46-24. SHT 3 DIG-S OPERABLE N/A COMMON S 127 M-713-1-1 ACTIVE HD-02-A Diesel Generator OPERABLE NIA 3 19 HD40-202 SDG-B E2 DIG CARDOX HEAT DETECTOR M-46-24, SHT 3 DIG-S OPERABLE N/A-COMMON S ACTIVE 127 Diesel Generator OPERABLE N/A HD4-028 M-713-1-1 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (,nrmr..nnnc1.nr.P.

Nn -RR-19ý173 B-83 DOCUMENT NO. 0067000840001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm stae Momve power Supporl System Desred State C power Supp Sys daw DATE: /28/W9 PAGE 83 TRAIN Unit SQUG CI Equp I Eval reqd? PIMS ID sytm NoWes Equip Descripton ROB Mother Camp Drawing No.Loc Code Room Elev Lire No Fuwido Buid~ing 3 19 HD-803A SOG-B E2 DIG CARDOX HEAT DETECTOR M-46-24, SHT 3 /CG-5 OPERABLE NIA COMMON S 127 ACTIVE HD-803A Diesel Generator OPERABLE NZA M-713.-1-1 3 19 HD-6038 SDG-8 E2 D/G CARDOX HEAT DETECTOR M-46-24. SHT 3 D/G-S OPERABLE N/A COMMON S 127 ACTIVE HD-M03B Diesel Generator OPERABLE NIA M-713-1-1 3 19 HD4O4A SDG-C E3 DIG CARDOX HEAT DETECTOR M-46-24, SHT 4 DIG-7 OPERABLE NIA COMMON S 127 ACTIVE NDO-4A Diesel Generator OPERABLE N/A M-713-1-1 3 19 ND-B048 SDG-C E3 DIG CARDOX HEAT DETECTOR M48-24. SHT 4 D/G-7 OPERABLE N/A COMMON S 127 ACTIVE HD-804B Diesel Generator OPERABLE NIA M-713-1-1 3 19 HD-805A SOG-C E3 DIG CARDOX HEAT DETECTOR M-46-24, SHT 4 D/G-7 OPERABLE N/A COMMON S 127 ACTIVE HD-805A Diesel Generator OPERABLE N/A M-713-1-1 3 19 HD10058 SDG-C E30/G CARDOX HEAT DETECTOR M-48-24, SHT 4 D/G-7 OPERABLE NIA COMMON S 127 ACTIVE HD.OOSB Diesel Generator OPERABLE WfA M-713-1-1 3 19 HD-806A SDG-C E3 DIG CARDOX HEAT DETECTOR M-46-24, SHT 4 DIG-7 OPERABLE N/A COMMON S 127 ACTIVE HO-806A Diesel Generator OPERABLE WA M-713-1-1 3 19 HD-806B SDG-C E3 DIG CARDOX HEAT DETECTOR M-46-24. SHT 4 DIG-7 OPERABLE N/A.COMMON S 127 ACTIVE 1H4-068 Diesel Generator OPERABLE N/A M-713-1-1 3 19 HD-S07A SDG-C E3 DIG CARDOX HEAT DETECTOR M-46-24, SHT 4 DIG-7 OPERABLE N/A COMMON S 127 ACTIVE HD-807A Diesel Generator OPERABLE NIA M-713-1-1 3 19 0D-8078 SOG-C E3 DIG CARDOX HEAT DETECTOR M-46-24, SHT 4 DIG-7 OPERABLE N/A COMMON S 127 ACTIVE HD-8078 Diesel Genermator OPERABLE N/A M-713-1-1 3 19 HD-808A SDG-C E3 DIG CARDOX HEAT DETECTOR M-46-24, SHT 4 DIG-7 OPERABLE N/A T COMMON S 127 ACTIVE HD-808A Diesel Generator OPERABLE N/A M-713-1-1 3 19 SDG-C E3 DIG CARDOX HEAT DETECTOR 4-48-24, SHT 4 ODG-7 OPERABLE NIA COMMON S 127 ACTIVE HO-8088 Diesel Generator OPERABLE NIA M-713-1-1 3 19 HO-809A SOG-C E3 DIG CARDOX HEAT DETECTOR M-46-24. SHT 4 DIG-7 OPERABLE N/A COMMON S ACTIVE 127 Diesel Generator OPERABLE N/A HD-809A M-713-1-1 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnrrP.n;nnndp.nrt-p Nn -RS-12-173 B-84 DOCUMENT NO. 006740084-D001 REVISION 2 TRAIN SQUG Ci Equip ID Und Eval reqd? PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SALE SHUTDOWN EQUIPMENT LIST Noam ste Mobve power SuPPMi System Deshwd State Cofr pow Sup SYS dwo DATE: 3121V96 PAGE 84 System Notes Equip Desriopan ROB McOll Camp Drawing No.Loc Code Room Elev LIM No Fumsdbn 8uLgdkV 3 19 HD-0096 SDG-C F3 DIG CARDOX HEAT DETECTOR M-46-24. SHT 4 DIG-7 OPERABLE N/A 1 COMMON S 127 ACTIVE HD-098 DSiesel Generator OPERABLE N/A M M-713-1-1 3 is HD-810A SOG-C E3 DIG CARDOX HEAT DETECTOR M-46-24. SHT 4 D/G-7 OPERABLE N/A COMMON S 127 ACTIVE HD-81A Diesel Genemor OPERABLE N/A M-713-1-1 3 19 H0-8108 SOG-C E3 DIG CARDOX HEAT DETECTOR M-46-24. SHT 4 DIG-7 OPERABLE N/A COMMON S 127 ACTIVE HD-810B Diesel oeresatw OPERABLE N/A 3 19 HD-811A SDG-C E3 DIG CARDOX HEAT DETECTOR M-48-24. SHT 4 DIG-7 OPERABLE NIA COMMON S 127 ACTIVE HD-811A Diesel Cenem OPERABLE NIA M-713-1-1 3 19 HD-SI1B SDG-C E3 DIG CARDOX HEAT DETECTOR M.46-24. SHT 4 DIG-7 OPERABLE N/A COMMON S 127 ACTIVE HD-8118 Diesel Generator OPERABLE N/A M-713-1.1 3 19 HD-812A SDG-O E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT 5 DIG-9 OPERABLE N/A COMMON S 127 ACTIVE HD-812A Diesel Generator OPERABLE NIA M-713-1-1 3 19 HD-0128 S0G-D E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT 5 DIG-9 OPERABLE N/A COMMON S 127 ACTIVE HO-8128 Diesel Genwratm OPERABLE N/A M-713-1-1 3 19 HO-813A SDG-D E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT 5 DIG-S OPERABLE N/A COMMON S 127 ACTIVE HD-813A Diesel Ger, ealo OPERABLE N/A M-713-1.1 3 19 HD-8136 SDG-0 E4 DIG CARDOX HEAT DETECTOR M-48-24. SHT 5 DIG-S OPERABLE N/A COMMON S 127 ACTIVE ND-8139 Diesel Generator OPERABLE N/A M-713-1-1 3 19 HD-814A SDG.O E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT S DIG-9 OPERABLE N/A -COMMON S 127 ACTIVE HD-814A Diesel Geret~or OPERABLE N/A M-713-1-1 3 19 KD-8148 SDG-O E4 DIG CARDOX HEAT DETECTOR M-46-24, SHT 5 DIG-9 OPERABLE N/A COMMON S 127 ACTIVE. HO-814B Diesel Generwator OPERABLE NZA M-713-1-i 3 19 H0-815A SDG$0 E4 DIG CARDOX HEAT DETECTOR M-46-24, SHIT 5 DIG-9 OPERABLE N/A i COMMON S 127 ACTIVE HD-8ISA Diesel Generator OPERABLE N/A 3 M-D713-1-1 3 19 HD-8150 SDG-D E4 DIG CARDOX HEAT DETECTOR M-48-24. SHT 5 DIG-9 OPERABLE W/A COMMON S ACTIVE 127 Diesel Generstor OPERABLE N/A HD-8158 M-713-1-1 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 (nrrP.nnndPn.n.

Nn o Rq-12-173 B-85 DOCUMENT NO. 0067.4084-DOO1 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Nonm stale Motive power Support System Desired State Cord, power Su~pp sys dwg DATE: 3M28136 PAGE 85 TRAK SOUO CI -Equip 1 Evel reqd? PINIS ID Syste NOWe Equip Oescription ROB Motht Comp Drawtig No.Loc Code Room Etev Lin No Functionr 3 19 HD-816A S0DG0 E4 DIG CARDOX HEAT DETECTOR M-46-24, SHT S DIG-9 OPERABLE NIA COMMON S 127 ACTIVE HD-816A Diesel Genrator OPERABLE WA M-713-1-1 3 19 HD-8168 SOG-0 E4 D/G CAROOX HEAT DETECTOR M-46-24. SHT 5 DIG-9 OPERABLE EVA COMMON S 127 ACTIVE HD8168 Diesel Genernlor OPERABLE WfA M-713-1-1 3 19 HD-817A SOG-O E4 DIG CARDOX HEAT DETECTOR M-46-24, SHlT S DIG-9 OPERABLE NIA COMMON S 127 O ACTIVE HD-817A Diesel Gneator M-713-1.1 3 19 HD-817B SOG-D E4 0/G CARDOX HEAT DETECTOR M-46-24. SHT 5 O/G-9 OPERABLE WA COMMON S 127 ACTIVE HD-0178 Diesel Generator OPERABLE WA 3 19 HD-&IaA SDG-O E4 DIG CARDOX HEAT DETECTOR -M-46-24, SHT 5 D/G-9 OPERABLE WA COMMON S 127 ACTIVE HD-OIBA Diesel Generator OPERABLE WfA M-713-1-1 3 19 HD-B188 SDG-D E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT 5 DIG-9 OPERABLE WfA COMMON S 127 ACTIVE H""ISO Diesel Gonorat OPERABLE WA~M-713-1-1 3 19 HD-SIBA SDG-O E4 DIG CARDOX HEAT DETECTOR M-46-24, SHT 5 DIG-9 OPERABLE IA 1 COMMON S 127 ACTIVE HD-1B9A Diesal Geneator OPERABLE WA M-713-1-1 3 is H0-4i-s SDG-D E4 DIG CARDOX HEAT DETECTOR M-46-24. SHT 5 oDr, OPERABLE WIA COMMON S 127 ACTIVE HD-819B Diesel Generator OPERABLE MIA M-713-1-1 3 20 00C29A EPS EMERGENCY PROTECTION RELAY T2.100 OPERABLE WA COMMON S BOARD 165 8000 ACTIVE 0OC029A Tubine BOk:g -U2 OPERABLE WIA E-7-30. E17-539-1 3 20 00C298 EPS EMERGENCY PROTECTION RELAY T2-100 OPERABLE WA COMMON S BOARD 185 8000 ACTIVE (C0029B Turbine Bldg -U2 OPERABLE WA E-7-30. E17-539-1 3 20 0OC29C EPS EMERGENCY PROTECTION RELAY T2-400 OPERABLE NWA COMMON $ BOARD 165 8000 ACTIVE 00C029C Turbine Bldg -U2 OPERABLE WA I E-7-30, El7-539-1 3 20 00C290 EPS EMERGENCY PROTECTION RELAY T2-100 OPERABLE WA COMMON S BOARD 165 8000 ACTIVE 00CO29D Turbine BlIg -U2 OPERABLE NIA E-7-30. El7-539-1 3 20 0AC097 SOG-A DIESEL GENERATOR OAG12 CONTROL 01DG-3 OPERABLE NWA r-nuurul e PANEL , ACTIVE Diesel Generat OPERABLE -N/A OAC097 Peach Bottom Atomic Power Station Unit 2 B-86 MPR-3815, Revision 3 (.nrrmP.nnnrdne.r.

Nn -RS-19-173 DOCUMENT NO. 0067-00084-0001 REVISION 2 TRAIN SOUG C1 Equip 1 LW Eval rectd? PIOS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3128196 PAGE 86 Nonor state Motive power Supqo System Desirec State Contr power SuqP Sys dwg System Notes EOBM Desclpllon ROB Motiler Cormp ODrwbi No.Loc Code Room Elev Lin No Function Buidbng 3 20 0AC142 SG-A STANDBY DIESEL ENGINE CONTROL A D/G-3 OPERABLE NIA COMMON a PANEL 127 ACTIVE 0AC142 OAGI2 Diesel Generator OPERABLE NIA 3 20 0AC216 SDG-A DIESEL C02 SYSTEM ELECTRICAL DIG-3 OPERABLE NIA COMMON S CONTROL (20S102) 127 ACTIVE 0AC216 Diesel Generator OPERABLE NWA M-713 3 20 0AC479 SDG A- El 0/G ROOM SUPPLY TEMP CONTROL M-385 D/G-13 OPERABLE WA COMMON S VENTILATION 151 5112 ACTIVE TIC-00272 Diesel Generatr OPERABLE NIA 3 20 OAGi3 SDG-A El DIG P.T. AND EXCITATION E-8 O/G-4 OFF OAD13 COMMON SR EQUIPMENT 127 8002 ACTIVE OAGO13 Diesel Generator ON E-5-35-7 3 20 08CO97 SDG-B DIESEL GENERATOR 08G12 CONTROL DIG-6 OPERABLE NWA COMMON 5 PANEL 127 ACTIVE 0BC097 Diesel Generato OPERABLE NIA 3 20 08C142 SDG-B STANDBY DIESEL ENGINE CONTROL B DIG-S OPERABLE NIA COMMON a PANEL 127 ACTIVE 0BC142 08412 Diesel Generator OPERABLE NWA 3 20 08C216 SDG-8 DIESEL C02 SYSTEM ELECTRICAL DIG-S OPERABLE NWA COMMON S CONTROL (20SI02) 127 ACTIVE 0BC216 Diesel Generstor OPERABLE WA 3 20 08C479 SDG B -E2 DIG ROOM SUPPLY TEMP CONTROL M-385 DIG-15 OPERABLE NWA COMMON S VENTILATION 151 5212 ACTIVE TIC-00273 Diesel Generator OPERABLE WIA 3 20 08G13 S0G-8 E2 DIG P.T. AND EXCITATION E-8 DIG-6 OFF 08013 COMMON SR EQUIPMENT 127 8006 ACTIVE 08G013 Diesel Generator ON E-6-35-7 3 20 OCCO97 SOG-C DIESEL GENERATOR 0CG12 CONTROL DG-8 OPERABLE NWA COMMON S PANEL 127 ACTIVE 0CC097 Diesel Generator OPERABLE NWA 3 20 0CC142 SOG-C STANDBY DIESEL ENGINE CONTROL C ODG-? OPERABLE NWA COMMON a PANEL 127 ACTIVE 0CC142 0CG12 Diesel Generator OPERABLE NWA 3 20 0CC216 SDG-C DIESEL C02 SYSTEM ELECTRICAL DIG-7 OPERABLE NWA COMMON S CONTROL (20S102) 127 ACTIVE OCC216 Diesel Generator OPERABLE NWA M-713 3 20 0CC479 SOG C -E3 DIG ROOM SUPPLY TEMP CONTROL M-3115 IG-17 OPERABLE NIA COMMON S 5312 ACTIVE VENTILATION 151 Diesel Generator OPERABLE NIA TIC-00274 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrre.qnnndiAnr..

Nn

• R5-19-173

-B-87 DOCUMENT NO. 0067-0084-3001 REVISION 2 TRAIN SQUG CI Equip ID Unit Eval reqd? PIMS ID PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 326 PAGE 87 Norm s Motive power Suppora System Desiod State Cortr power SuPP Sys dwg System Notes Equip Desoription ROB Molitor Comp DOm"ing No.Loc Code Room Elev Line No Furmoion Building 3 20 OCGt3 S0G-C E3 D/G P.T. AND EXCITATION E-4 D/G-8 OFF OCDI3 COMMON SR EQUIPMENT 127 8006 ACTIVE 0CGO13 Diesel Generator ON E E-5-35-7 3 20 ODC097 SG-D DIESEL GENERATOR ODG12 CONTROL DIG-ID OPERABLE NIA COMMON S PANEL 127 ACTIVE ODC097A Diesel Generator OPERABLE NIA 3 20 0DCt42 SDG-O STANDBY DIESEL ENGINE CONTROL 0 DIG-9 OPERABLE N/A COMMON B PANEL 127 ACTIVE 0DC142 0DG12 Diesel Generator OPERABLE WIA 3 20 00D218 SOG.O DIESEL C02 SYSTEM ELECTRICAL D/G-9 OPERABLE NIA COMMON s CONTROL (201102) 127 ACTIVE 00C216 Diesel Generator OPERABLE NIA M-713 3 20 00C479 SDGD- E4 DIG ROOM SUPPLY TEMP CONTROL M-385 DIG-19 OPERABLE WA COMMON S VENTILATION 151 5412 ACTIVE TIC-00275 Diesel Generatw OPERABLE NIA 3 20 0DG13 SDG-O E4 DIG P.T. AND EXCITATION E-8 DIG-10 OFF 00D13 COMMON SR EQUIPMENT 127 8011 ACTIVE 0OG013 Disel Generator ON E-&-35-7 3 20 LIC-62G-7250A SDG-A. LUBE OIL El DIG LUBE OIL SUMP LEVEL M-377, SHT 3 DIG-4 OPERABLE NWA COMMON B REGULATOR 127 5129 ACTIVE LIC-7250A 6 OAG12 Diesel Generator OPERABLE NWA 3 20 LIC-52G-7250B SDG-B -LUBE OIL E2 D/G LUBE OIL SUMP LEVEL M-377, SHT 3 O4G-6 OPERABLE N/A COMMON B REGULATOR 127 5229 ACTIVE LIC-72508 6 0BG12 Diesel Generator OPERABLE NWA 3 20 LIC-52G.7250C SDG-C. LUBE OIL E3 DIG LUSE OIL SUMP LEVEL M-377. SHIT 3 D/G.8 OPERABLE NWA COMMON B REGULATOR 127 5329 ACTIVE LIC-7250C 6 0CG12 Diesel Generator OPERABLE NWA 3 20 LIC-52G-7250 SDG-O -LUBE OIL E4 DIG LUBE OIL SUMP LEVEL M-377, SHT 3 DIG-10 OPERABLE NIA COMMON B REGULATOR 127 5429 ACTIVE LIC-72500 6 00G12 Diesel Generator OPERABLE NWA 3 20 LS-0566A SDG-A- FUEL OIL El DIG FUEL OIL DAY TANK LEVEL M-377. SHT 4 DIG-3 OPERABLE NIA COMMON B SWITCH FOR OAT40 127 5144 ACTIVE LS-0566A OAT40 Diesel Generator OPERABLE NWA 3 20 LS-0566B SDG FUEL OIL E2 DIG FUEL OIL DAY TANK LEVEL M-377, SHT 4 DoG-" OPERABLE NWA COMMON B SWITCH FOR O8T40 127 5244 ACTIVE LS-0566B 08T40 Diesel Generator OPERABLE NWA 3 20 LS-0566C SDG-C FUEL OIL E3 DIG FUEL OIL DAY TANK LEVEL M-377. SHT4 DIG-7 OPERABLE WA COMMON B SWITCH FOR OCT40 127 5344 ACTIVE LS-0566C OCT40 Diesel Generator OPERABLE N/A Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 CnrrP..nnnd.nr..

Nn

• RR-19-173 B-88 DOCUMENT NO. 0067-0084-0001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Motive power SuWM System Desied State Conf power supp Sys fto DATE: Y2/2 PAGE 68 TRAIN SOUG CA Equ ID Eve recrd? PIMS ID System Notes Eq*i DescgOtion ROB MDOlh Canp Orawirg No.Loc Code Room Elev Line No Function Buddn0 3 20 LS-05660 SOG-0 -FUEL OIL E4 DIG FUEL OIL DAY TANK LEVEL M-377, SHlT 4 DIG-9 OPERABLE NIA COMMON a SWITCH FOR OOT40 127 5444 ACTIVE LS-05660 OCT40 Diesel Generato OPERABLE NIA 3 20 PS-0623A SD0.A El DIG CRANKCASE PRESSURE SWITCH M-377, SHT 3 DIG-3 OPERABLE NIA COMMON B 127 ACTIVE PS-0623A OAG12 Diesel Generator OPERABLE NIA 3 20 PS-0623B SG08 E2 DIG CRANKCASE PRESSURE SWITCH M-377, SHT 3 DIG-S OPERABLE NIA COMMON B 127 ACTIVE PS-O6= 0DG12 Diesel Generator OPERABLE NIA 3 20 PS-06230 SO-C E3 DIG CRANKCASE PRESSURE SWITCH M-377, SHT 3 01G-7 OPERABLE N/A COMMON B 127 ACTIVE PS-0623C 0C012 Diesel Generator OPERABLE NWA 3 20 PS-06230 S0G-D E4 DIG CRANKCASE PRESSURE SWITCH M-377, SHT 3 D/G-9 OPERABLE NIA COMMON B 127 ACTIVE PS-O6230 0OG12 Diesel Generator OPERABLE NIA 3 20 PS.0624A S0G-A Et DIG CRANKCASE PRESSURE SWffTCH M-377, SHT3 D/G-3 OPERABLE WA COMMON B 127 ACTIVE PS-O624A OAG12 Diesel Generator OPERABLE NIA 3 20 PS-06248 SOG-B E2 DIG CRANKCASE PRESSURE SWITCH M-377, SHT 3 DIG-S OPERABLE WA COMMON a 127 ACTIVE PS-06248 00012 Diesel Generator OPERABLE NIA 3 20 PS-0624C SD"-C E3 D0G CRANKCASE PRESSURE SWITCH M-377, SHlT 3 D/G-7 OPERABLE N/A COMMON B 127 ACTIVE PS-0624C 0CG12 Diesel Generatr OPERABLE NIA 3 20 PS-06240 SDGO- E4 DIG CRANKCASE PRESSURE SWITCH M-377, SHT 3 DIG-9 OPERABLE WA COMMON a 127 ACTIVE PS-06240 0DG12 Diesel Generator OPERABLE N/A 3 20 PS-0625A SOG-A El DIG CRANKCASE PRESSURE SWITCH M-377. SHT 3 DIG-3 OPERABLE N/A COMMON a 127 ACTIVE PS-0625A CIAG12 Diesel Generator OPERABLE NWA 3 20 PS-06258 SD0-a E2 DIG CRANKCASE PRESSURE SWITCH M-377, SHT 3 D/G-5 OPERABLE N/A COMMON 6 127 ACTIVE PS-6258 OBG12 Generator OPERABLE NWA 3 20 PS-06250 SOG-C E3 DIG CRANKCASE PRESSURE SWITCH M-377. SHT 3 DIG-7 OPERABLE N/A COMMON B 127 ACTIVE PS-0625C 0CG12 Diesel Generator OPERABLE NIA 3 20 PS.06250 SDG-0 E4 DIG CRANKCASE PRESSURE SWITCH M-377. SHlT 3 DIG-9 OPERABLE WIA COMMON B ACTIVE 127 Diesel Generator PS-06250 00G12 OPERABLE N/A Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 rnrrps.nnnflp.nr.,.

Nn

• Rq-19-173 B-89 DOCUMENT NO. 0067,000a4-O001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST DATE: 3X2IM98 PAGE B9 Norm stale Motive power Support System Desied State Conk power Supp Sys dwg REVISION 2 TRAIN SQUG CI Equip ID Evl Feq'd? PIMS ID System Notes Equip Desa3ton ROB MoWher Camp Drawing No.Loc Code Room Eiev Line No Function BuDC-g 3 20 TIC-00272 SOG A- El DIG ROOM SUPPLY TEMP CONTROL M-385 DIG-13 OPERABLE WA COMMON B VENTILATION 151 5112 ACTIVE TIC-00272 Diesel Generator OPERABLE WA 3 20 TIC-00273 SOG B- E2 DIG ROOM SUPPLY TEMP CONTROL M-3.5 DIG-15 OPERABLE WA COMMON B VENTILATION 151 5212 ACTIVE TIC-00273 Desel Generator OPERABLE WA 3 20 TIC.0t274 SDG C- E3 DIG ROOM SUPPLY TEMP CONTROL M-3W5 DIG- 7 OPERABLE WA COMMON B VENTILATION 151 5312 ACTIVE TIC-00274 Diesel Generator OPERABLE NIA 3 20 TIC-00276 SOG D -E4 DIG ROOM SUPPLY TEMP CONTROL M.3B5 DIG-19 OPERABLE WA COMMON B VENTILATION 151$412 ACTIVE TIC.O0275 Diesel Generator OPERABLE N/A 3 20 TS-0567A SOG-A El DIG LUSE OIL TEMPERATURE HI M-377. SHT 3 DIG-3 OPERABLE WA COMMON 8 127 ACTIVE TS-0487A Diesel Generator OPERABLE NIA 3 20 TSO587B SDG-S E2 DIG LUSE OIL TEMPERATURE HI M-377. SNT 3 D1G-5 OPERABLE WA COMMON B 127 ACTIVE TS-0587B Diesel Generator OPERABLE NWA 3 20 TS-0587C SOG-C E3 DIG LUBE OIL TEMPERATURE HI M-377. SHT 3 DIG-7 OPERABLE WA COMMON B 127 ACTIVE TS-05B7C Diesel Generator OPERABLE WA 3 20 TS-0587D SDG-O E4 DIG LUBE OIL TEMPERATURE HI M-377, SHT 3 DIG-9 OPERABLE NWA COMMON B 127 ACTIVE TS-0587D Diesel Generator OPERABLE NIA 3 20 TS.OS8BA SDG-A El DIG LUBE OIL TEMPERATURE HI M-377, SHT 3 DIG-3 OPERABLE WA COMMON B 127 ACTIVE TS-)SSBA Diesel Generator OPERABLE WA 3 20 TS-0588B -SDG-8 E2 DIG LUBE OIL TEMPERATURE HI M-377, SHT 3 DIG-5 OPERABLE WA COMMON B 127 ACTIVE TS-0568B Diesel Generator OPERABLE NWA 3 20 TS-05=8C SG-C E3 DIG LUSE OIL TEMPERATURE HI M.377. SHIT 3 DIG-7 OPERABLE WA COMMON B 127 ACTIVE TS-0588C Diesel Generator OPERABLE WA 3 20 TS-05BBO SDG-0 E4 DIG LUBE OIL TEMPERATURE HI M-377. SHT 3 DIG-9 OPERABLE NWA COMMON B 127 ACTIVE TS-.0588D Diesel Generator OPERABLE NWA 3 20 TS-0589A SDG-A El DIG LUBE OIL TEMPERATURE HI M-377. SHT 3 DIG-3 OPERABLE NIA COMMON B ACTIVE 127 Diesel Generator OPERABLE NIA TS-O5BA Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Cnrr..qnnndiPnr.c Nn

• R5R-1-173 B-90 DOCUMENT NO. 0067-00084001 REVISION 2 TRAIN SOUG CI Equip ID Unit Eval read? PIMS ID PEACH BOTTOM ATOMIC STATION UNIT$ 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Norm state Motive power Stotpaf System Doesired State Con& power Sup Sys dwg DATE: 3rW96 PAGE 90 Systam Notes Equip Deosription ROB MOWhe Camnp Drawing No.Loc Code RoaM Elev Line No Function B.di 3 20 TS,0589B SDG-B E2 DIG LUBE OIL TEMPERATURE HI M-377. SHT 3 DIG-S OPERABLE N/A COMMON B 127 O ACTIVE TS-05898 Dies GeSne OPERABLE NIA 3 20 TS-0589C SOG-C E3 DIG LUSE OIL TEMPERATURE HI 19-377, SHT 3 D/G-7 OPERABLE WA COMMON a 127 ACTIVE TS-0589C Diesel Generator OPERABLE WA 3 20 TS-05890 SOG-O E4 DIG LUBE OI. TEMPERATURE HI M-377, SHT 3 DIG-$ OPERABLE N/A COMMON B 127 ACTIVE TS-05890 Diesel Generator OPERABLE NWA 3 20 TS-OSMA SDO-A El DIG JACKET COOLANT M-377. SHT 2 DIG-3 OPERABLE WA COMMON a TEMPERATURE HI 127 ACTIVE TS-0605A Diesel Generaor OPERABLE N/A 3 20 TS-06068 SOG-8 E2 DIG JACKET COOLANT M-377, SHT 2 DIG-S OPERABLE NWA COMMON B TEMPERATURE HI 127 ACTIVE TS.6OSW Diesel Generao OPERABLE WfA 3 20 TS-0605C SDG-C E3 DIG JACKET COOLANT M-377, SHT 2 DIG-7 OPERABLE NIA COMMON B TEMPERATURE HI 127 ACTIVE TS-OBO5C Diesel Genwrat OPERABLE WA 3 20 TS-06050 SDG-O E4 DIG JACKET COOLANT M-377, Sl4T 2 DI- OPERABLE NIA COMMON B TEMPERATURE HI 127 ACTIVE TS-06050 Diesel Generator OPERABLE N/A 3 20 TS-OSOSA SOD-A El DIG JACKET COOLANT M-377, SHT 2 D/G-3 OPERABLE WA COMMON a TEMPERATURE HI 127 ACTIVE TS-0606A Diesel Generwator OPERABLE NWA 3 20 TS-0606B SOG-B E2 DIG JACKET COOLANT M-377. SHT 2 D/G-S OPERABLE N/A COMMON B TEMPERATURE HI 127 ACTIVE TS-0606B Diesel Generator OPERABLE N/A 3 20 TS-0606C SOG-C E3 DIG JACKET COOLANT M-377, SHT 2 DIG-7 OPERABLE WA COMMON B TEMPERATURE HI 127 ACTIVE Diesel Generator OPERABLE N/A 3 20 TS.O6060 SDG-O E4 DIG JACKET COOLANT M-377. SHT 2 OIG-S OPERABLE N/A COMMON a TEMPERATURE HI 127 ACTIVE TS-06060 Diesel Generator OPERABLE N/A 3 20 TS-0607A SOG-A El DIG JACKET COOLANT M-377. SHT 2 0/G-3 OPERABLE WA COMMON B TEMPERATURE HI 127 ACTIVE TS.0607A Diesel Generator OPERABLE WA j 3 20 TS-0607B SDG-8 E2 DIG JACKET COOLANT M-377, SHT 2 DIG-S OPERABLE NIA COMMON a TEMPERATURE HI 127 ACTIVE TS-0607B Diesel Generator OPERABLE NIA Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn

• RR-19-173 B-91 DATE: 3128/96 DOCUMENT NO. 0067-00084-0001 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 PAGE 91 REVISION 2 SAFE SHUTDOWN ECUIPMENT LIST TRAIN SOUG CI Equip ID System Equip Deosriplion DrawingNo.

o Code Norm state Motive power Support system uni Evaj fetd? PIMS ID Notes ROD Motte Comp Room Elev Desred Ste cone power Supp Sys d"g Line No Function Buldig 3 20 TS-0607C SDG-C E3 DIG JACKET COOLANT M-377, SHT 2 DOG-7 OPERABLE NIA COMMON a TEMPERATURE HI 127 ACTIVE TS-0607C Diesel Generator OPERABLE NIA 3 20 TS-05070 SDG-D E4 DIG JACKET COOLANT M-377, SHT 2 DIG-9 OPERABLE WA COMMON B TEMPERATURE HI 127 ACTIVE TS-0.07D Diesel Generator OPERABLE NWA 3 21 OAE073 HVAC EMERG SWGR VENT SUP HEATING M-399. SHT I PJW-32 OFF NWA COMMON a COIL A 165 5805 PASSIVE OAE073 0AV034 Radwaste Bldg WA WA 3 21 OAE126 SDG-A -LUBE OIL El DIG LUBE OIL STANDBY HEATER M-377. SHT 3 D/G-3 OPERABLE NIA COMMON B 127 5131 PASSIVE OAE126 Diesel Generator OPERABLE NfA 3 21 0AE376 SG.A -DIESEL El DIG JACKET COOLANT COOLER M-377, SHT 2 DIG-3 OPERABLE NIA COMMON B COOLING 127 5123. 5500 PASSIVE 0AE376 Diesel Generator OPERABLE WA Vendor 11905551 3 21 OAE377 SDG-A -LUBE OIL El DIG LUBE OIL COOLER M-377, SHT 3 DIG-B OPERABLE NWA COMMON B 127 5139. 5501 PASSIVE 0AE3T7 Diesel Generator OPERABLE WA Vendor 11905551 3 21 OAE378 SDG-A -DIESEL El DIG AIR COOLANT COOLER M-377. SHT 2 D/G-3 OPERABLE NIA COMMON B COOLING 127 5116.5502 PASSIVE 0AE378 Diesel Generlator OPERABLE -NA Vendor 11905551 3 21 0AS384 HVAC BACKUP NITROGEN TO 08VO35 AND M-399. SNT 1 RNW-29 OPERABLE NWA COMMON S 0A&8V034 FAN DAMPERS 165 5900 PASSIVE 0AS384 Rswaste OBdg OPERABLE NIA M-2801-3.M-1876 3 21 OAS385 HVAC BACKUP NITROGEN TO 08V036 AND M-BB9. SHT 4 RIW-32 OPERABLE WA COMMON B OA&BV035 FAN DAMPERS 165 5913 PASSIVE 0AS385 08S385 Radwaste Bldg OPERABLE MIA M-2801-3.M-1876 3 21 DAT096 SG0-A -LUBE OIL El DIG LUBE OIL STORAGE TANK M-377. SHT 3 DIG-3 OPERABLE WA Ti COMMON S 127 5127 ACTIVE 0ATO96 7 Diesel Generator OPERABLE MIA 3 21 OAT097 SDG-A- DIESEL El DIG COOLANT EXPANSION TANK M-377, SHlT 2 DIG-4 OPERABLE WA COMMON S COOLING 127 5120 PASSIVE AT1097 Diesel Generator OPERABLE NIA E,-5-38-4 3 21 OAT38 SDG-A -FUEL OIL DIESEL FUEL OIL STORAGE TANK M-.3T, SHT 4 YARD OPERABLE WA COMMON S 113 5140 PASSIVE 0ATO38 Diesel Generator OPERABLE NWA Vendor M-6214. C-64 3 21 OAT40 SDG-A -FUEL OIL El DIG FUEL OIL DAY TANK M-377. SHT 4 DIG-3 OPERABLE NIA COMMON S 127 5143 PASSIVE 0AT040 Diesel Generator OPERABLE WA E-5-36-5 Peach Bottom Atomic Power Station Unit 2 B-92 MPR-3815, Revision 3 CnrrP.snnr1PnA.n Nn " RS-12-173 DOCUMENT NO. 006740(084-0X01 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT LIST Namstte Mokepmeer suppor Systern Desiecl tate cord po- Supp Sys dwg DATE: 312M/96 PAGE 92 TRAIN SOUG Cl EquipD Eval re(d? PIMS ID SystN Note$Equip Desaiption ROB Comp ovwrinQg No Loc Code.Room Elev Line No Fundion Budiing 3 21 08E073 HVAC EMERG SWGR VENT SUP HEATING M-399. SHlT 1 RIW-32 OFF N/A -COMMON a COIL B 165 5813 PASSIVE 0BE073 0BV034 Radwaste BldgA A 3 21 08E126 SDG-B -LUBE OIL E20/G LUBE OIL STANDBY HEATER M-377, S.t 3 D/G-5 OPERABLE N/A I COMMON a 127 5231 PASSIVE OBE126 Diesel Generator OPERABLE NA 3 21 0BE378 SDG-B -DIESEL E2 DIG JACKET COOLANT COOLER M-377, SWlt 2 D/G-5 OPERABLE NWA COMMON a COOLING 127 5223, 5503 PASSIVE 0BE376 Diesel GeCanerlor OPERABLE NIA Vendor 11905551 3 21 OSE377 SDG-B -LUBE OIL E2 D/G LUBE OIL COOLER M-377, SHT 3 DIG-3 OPERABLE NWA COMMON B 127 5239, 5504 PASSIVE 0BE377 Oiese Generator OPERABLE NIA Vendor 11905551 3 21 08E370 SDG-8 -DIESEL E2 DIG AIR COOLANT COOLER M-377. SHlT 2 DIG-" OPERABLE N/A COMMON 1 COOLING 127 6216, 55M PASSIVE 0E378 Diosel Generator OPERABLE WA Vendor 11905551 3 21 0BS385 HVAC BACKUP NITROGEN TO OAV035 AND M-399, SHT 4 R/WI-32 OPERABLE WA COMMON S 0A&BV036 FAN DAMPERS 165 5902,5915 PASSIVE 0BS385 Radwaste 8ldg OPERABLE NWA M-2801-3.M-1876 3 21 08T096 SOG-S -LUBE OIL E2 DIG LUBE OIL STORAGE TANK M-377, SHT 3 0IG-S OPERABLE WA COMMON S 127 5227 ACTIVE 08TO96 7 Diesel Generator OPERABLE WA E-5-40 3 21 OBT097 SO" -DIESEL E2 DIG COOLANT EXPANSION TANK M-377, SHT 2 DIG-6 OPERABLE NIA COMMON S COOLING 127 5220 PASSIVE 0T097 Diesel Generator OPERABLE NWA E-5-38-4 3 21 0BT38 SDG-B -FUEL OIL DIESEL FUEL OIL STORAGE TANK M-7, -HT 4 YARD OPERABLE WA COMMON S 113 5240 PASSIVE 081038 Diesel Generator OPERABLE NWA Vendor 1-4214. C-64 3 21 0BT40 SOG-8 -FUEL OIL E2 DIG FUEL OIL DAY TANK M-377, SHT4 D/G-5 OPERABLE NWA COMMON S 127 5243 PASSIVE 08T040 Diesl Genator OPERABLE NWA E-5-36-5 3 21 OBT95 SOG-A -STARTING El DIG STARTING AIR RESERVOIR M-377, SHT 1 DIG-3 OPERABLE N/A COMMON S AIR (AUTOMATIC START) 127 5100 PASSIVE 08T095 Diesel Generator OPERABLE WA E-5-11-6 3 21 0CE126 SDG-C -LUSE OIL E3 DIG LUBE OIL STANDBY HEATER M-377, SHT 3 DIG-7 OPERABLE NWA COMMON B 127.5331 PASSIVE 0CE126 Diesel Generator OPERABLE WA 3 21 0CE376 SDG-C -DIESEL E3 D/G JACKET COOLANT COOLER M-377. SHlT 2 D0G-7 OPERABLE N/A COMMON 5323,5608 B PASSIVE 0CE376 COOLING 127 Diesel Generator OPERABLE NIA Vendor 11905551 B-93 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 CnrrP.nnnd~nr.P.

Nn

• RS-12-173 DOCUMENT NO. 0867400840001 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST DATE: 3/28/96 PAGE 93 Norm state Motive power Su~pt SysteM Desired Sloe Ca power Supp Sys d"g TRAIN unit SOUG CI Eqwip ID Eva[ rqd? PIMS ID Syrem Notes EquR DesMolhion ROB Mother Camp Dr"et No.Lao Code Room Elev Lira No Function BSulding 3 21 0CE377 SDG-C -LUSE OIL E3 DIG LUSE OIL COOLER M-377, SHT 3 D/G-3 OPERABLE NA I COMMON B 127 5339.5507 PASSIVE 0CE377 Diesel Generator OPERABLE NIA Vendor 11905551 3 21 0CE378 SDG-C -DIESEL E3 D/G AIR COOLANT COOLER M.377, SlT 2 D/G-7 OPERABLE N/A COMMON B COOLING 127 5316.5508 PASSIVE 0CE378 Diesel Generator OPERABLE NIA Vendor 11905551 3 21 OCT096 SDG-C -LUBE OIL E3 D/G LUBE OIL STORAGE TANK M-377. SHT 3 DOG-7 OPERABLE NIA COMMON 5 127 5327 ACTIVE 0CT096 7 Diesel Generator OPERABLE NWA E-5-40 3 21 0CT097 SDG-C -DIESEL E3 D/G COOLANT EXPANSION TANK M-377, SHT 2 DIG-S OPERABLE WA COMMON S COOLING 127 5320 PASSIVE 0CT097 Diesel Generator OPERABLE NWA E-5-38-4 3 21 OCT38 SDG-C -FUEL OIL DIESEL FUEL OIL STORAGE TANK M-377. SHT 4 YARD OPERABLE NWA COMMON S 113 5340 PASSIVE OCT038 Diesel Generator OPERABLE NWA Vendor M-6214. C.64 3 21 OCT40 SDG-C -FUEL OIL E3 DIG FUEL OIL DAY TANK M-377. SHIT 4 DIG-7 OPERABLE NWA COMMON S 127 5343 PASSIVE 0CT040 DieseG Generator OPERABLE NWA E-5-36-4 3 21 0OE126 SDG-D -LUSE OIL E4 D/G LUBE OIL STANDBY HEATER M-377. SHlT 3 D/G-9 OPERABLE WA T COMMON e 127 5431 PASSIVE 00E126 Diesel Generator OPERABLE NWA 3 2i 00E376 SOC-D -DIESEL £4 D0G JACKET COOLANT COOLER M-377, SHlT 2 D/G-9 OPERABLE N/A COMMON B COOLING 127 5423, 5509 PASSIVE 0DE376 Diesel Geneator OPERABLE WA Vendor 11905551 3 21 0DE377 S .O" -LUBE OIL E4 DIG LUBE OIL COOLER M-377, SHT 3 D/G-3 OPERABLE NWA COMMON B 127 5439. 5510 PASSIVE 0E377 Diesel Generator OPERABLE WIA Vendor 11905551 3 21 0OE378 S0G-D -DIESEL E4 D/G AIR COOLANT COOLER M-377. SHT 2 Di- OPERABLE NWA COMMON B COOLING 127 5416,5511 PASSIVE 00E378 Diesel C atm r OPERABLE NWA Vendor 11905551 3 21 ODT096 SDOG-O -LUSE OIL E4 D/G LUBE OIL STORAGE TANK M-377. SHT 3 0/0-9 OPERABLE NWA COMMON S 127 5427 ACTIVE ODT096 7 Diesel G OPERABLE NWA E-5-40 3 21 0OT097 S0G-D -DIESEL E4 D/G COOLANT EXPANSION TANK M-377. SHT 2 D/G-10 OPERABLE WA COMMON S COOLING 127 5420 PASSIVE ODT097 Diesel Generator OPERABLE NWA E 38-4 3 21 00T38 SDG-D -FUEL OIL DIESEL FUEL OIL. STORAGE TANK M-377, SHlT 4 YARD OPERABLE N/A-COMMON S 5440 PASSIVE 0OT038 113 Diesel Generator OPERABLE NIA Vendor M-6214, C.64 B-94 Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Conrrpq.nnndp.nr.p Nn " RR-19-173 DOCUMENT NO. 0067-0084-0001 REVISION 2 TRAIN SOUG CI Unit Eval Line No FurAtn Equ ID PIMS I E"u De~aaWU ROB MOWhe Comip PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 SAFE SHUTDOWN EQUIPMENT UST Orawkg No.icc Code Room Eiev Bulft Motive pmer StLpos System Cont* poer Su~pP Sys dwo DATE: 3128116 PAGE 94 Norm elas Desired State 3. 21 ODT40 SDG-O -FUEL OIL E4DIG FUEL OIL DAY TANK M-377, SHT 4 01G-" OPERABLE NIA COMMON S 127 5443 PASSIVE ODT040 Oiese Generaew OPERABLE WA 6-E4-43-3 21 0DT95 SDG-4 -STARTING E2 DIG STARTING AIR RESERVOIR M-377. SHT 1 D/G-S OPERABLE NIA COMMON S AIR (AUTOMATIC START) 127 s2m0 PASSIVE 0DT095 Dis Genrwa/ OPERABLE NIA E-5-11-6 3 21 OFT9S SDG-C- STARTING E3 DIG STARTING AIR RESERVOIR M-377, SHT 1 D/G-7 OPERABLE WA COMMON S AIR (AUTOMATIC START) 127 5300 PASSIVE OFT095 Diesel Generator OPERABLE NWA E.6-11-6 3 211 0HTS5 SDG.D -STARTING E4 DIG STARTING AIR RESERVOIR M-377. SHT I DIG-9 OPERABLE WA COMMON S AIR (AUTOMATIC START) 127 5400 PASSIVE OHT09S Diesel Generator OPERABLE WIA E.6-1t-6 3 21 NIA SDG-A -DIESEL TURBO COOLERS (2) M-377. SHT 2 DIG-3/4 OPERABLE WA COMMON a COOLING 127 5119 PASSIVE CAG12 Diesel Generator OPERABLE WA 3 21 NWA SDG-8 -DIESEL TURBO COOLERS (2) M-377. SliT 2 DIG -516 OPERABLE WA COMMON a COOLING 127 5219 PASSIVE 08G12 Diesl Generator OPERABLE WA 3 21 WA SOG-C -DIESEL TURBO COOLERS (2) M-377, SHT 2 DIG -7/8 OPERABLE WA COMMON B COOLING 127 5319 PASSIVE 0CGt2 Diesel Generator OPERABLE NWA 3 21 WA SDG-D -DIESEL TURBO COOLERS (2) M-377. SHT 2 DIG-W10 OPERABLE NWA COMMON 5419 a PASSIVE COOLING ODGI2 127 Diesel Generator OPERABLE NWA Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Nn

• R.-1 2-173 B-95 DOCUMENT NO. 006740034-O401 REVISION 2 PEACH BOTTOM ATOMIC STATION UNITS 2 AND 3 JSAFE SHUTDOWN EOUIPMENT LIST DATE' WAIN8 PAGE 95 NOTES-KEY:

I Control Rod Hydraulic Control Unit -Typical of 185 2 Control Rod Drive -Typical of 185 3 Included in SPCL for Grandfather Purposes Only 4 Solenoid-Valve Integra to Air-Opemaed-Valve Requires Review As Well 5 Open Valve to Cross-Tie Loops A and B of HPSW 6 Sight Glass 7 Seismic Fire Interaction S Valve Locked Open 9 Valve Opened for Suppression Pool Cooling 10 Valve Opened for LPCI and ASC 11 Valve Locked Closed 12 Seismic Cal I component, but not required for USI A-46 or IPEEE 13 The MechanIcal Equipment ID Is M03-23C-5244A and the Electrical Equipment ID Is M03-238-4245 14 The Mechanical Equipment ID is M02.23C-4244A and the Electrical Equipment ID Is M02-231-4245 15 Components listed with a "PBO" In the NOTES field are required for Pressure Boundary Only Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 No

• RS-19-17S B-96 Exelon NTTF 2.3: Seismic Walkdown Seismic Walkdown Equipment List (SWEL)UNIT: PEACH BOTTOM UNIT 2 PREPARER:

aeo-ý-c l Ben Fra ir, MPR PEER REVIEWER: ane, MPR PEER REVIEW TEAM LEADER: R:_____Patrick Butler, MPR PBAPS OPERATIONS REPRESENTATIVE:

Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 r.nrrp.fnnnrlinn..A Nn *R5-19-171 B-97 Table B-1. SWEL for Unit 2 Unit Component NTTF 2.3 Function Risk New or IPEEE UWEL ID Description EPRI Class Building Elevation Location Decay Risk Ne? E ee SWEL Reactivity Pressure Inventory Heat Containment Significant?

Replace? Enhancement?

2 20S037 HPCI Turbine (00) Other Reactor 88 R2-13 -- .--- X --- Y N N 2 HCU-30-23 Hydraulic Control Unit (00) Other Reactor 135 R2-24 X ---. ... --- N N N 2 20B324 MO-2-23-015 Motor Control (01) Motor Control Turbine 135 Recirc mg ... ... X --- N N N Power Transfer Switch Centers set room 2 20B325 RCIC INBD Iso. Valve (01) Motor Control Turbine 135 Recirc mg X ---.N N N_M02-13-15 Motor Controls Centers set room 2 20B338 Remote Motor Starter MO- (01) Motor Control Turbine 135 Recirc mg --- ...--- X --- N N N 2-10-16D Centers set room 2 20B037 Reactor Area MCC E224-R- (01) Motor Control Reactor 135 R2-23 X X X X X N N N B Centers 2 20B060 Turbine Area MCC E224-T- (01) Motor Control Turbine 135 T2-71 X X X X X N N N B Centers 2 20A015 Emergency 4kV Aux (03) Medium Turbine 135 T2-171 X X X X X N N Y Switchgear (E12) Voltage Switchgears 2 20A016 Emergency 4kV Aux (03) Medium Turbine 135 T2-71 X X X X X N N N Switchgear (E22) Voltage Switchgears 2 20X033 Load Center E424 (04) Transformers Reactor 165 R2-16 X X X X X Y N Y 2_ 20X033 Transformer 2 20X133 Panel 20Y33 Transformer (04) Transformers Turbine 135 T2-171 X X X X X N N N 2 20X30 Load Center Transformer (04) Transformers Reactor 165 R2-41 X X X X X Y N Y E124 2 20X032 Reactor Area Load Center (04) Transformers Reactor 165 R2-41 X X X X X N N Y 2_ 20X032 E324 Transformer 2 20P033(05)

Horizontal 2 220P033' HPCI Booster Pump, Pump pumps Reactor 88 R2-13 ---.. X ..... Y N N 20P036 & RCIC Pump & Turbine (05) Horizontal Reactor 88 R2-14 ---.. X .... Y N N 20S038 Pumps I 2 2BP037 Core Spray Pump B (06) Vertical Pumps Reactor 91 R2-10 --... .X -- --- N N N High Pressure Service (06) Vertical Pumps Pumpcture 2 2CP042 Water Pump C Structure 2 2DP035 RHR Pump D (06) Vertical Pumps Reactor 91 R2-8 --- .... X --- N N N 2 A02-03-033 Scram Discharge Volume (07) Fluid (Air/Hyd)

Reactor 135 R2-24 X .. ... ..... N N N Outboard Isolation Valve Valves 2 A02-03-036 Scram Discharge Volume (07) Fluid (Air/Hyd)

Reactor 135 R2-24 X .. ... ..... N N N Inboard Isolation Valve Valves 2 AI2-01-080A nboard Main Steam (07) Fluid (Air/Hyd)

Drywell 134 DNW2-18 .--- --- --- X N N N Isolation Valve A Valves 2 A02-01-080B Inboard Main Steam (07) Fluid (Air/Hyd)

Drywell 134 D/W 2-18 ---........

.X N N N Isolation Valve B Valves 2 A02-01-086A Outboard Main Steam (07) Fluid (Air/Hyd)

Reactor 135 R2-30 ..- ... ... ... X N N N Isolation Valve A Valves 2 H02-23C-4513 HPCI Turbine Stop Valve (07) Fluid (Air/Hyd)Valves IRatr 8 21 --Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 B-98 Table B-I. SWEL for Unit 2 Unit Component NTTF 2.3 Function Risk New or IPEEE SWEL ID Description EPRI Class Building Elevation Location Decay Significant?

Replace? Enhancement?

SWEL_ ID Reactivity Pressure Inventory Heat Containment (07) Fluid (Air/Hyd)

Drywell 155 D/W2-35 --- X --- N N N 2 RV2-02-071 G Safety Relief Valve G Valves _____2 RV2-02-071 K Safety Relief Valve K (07) Fluid (Air/Hyd)

Drywell 155 D/W2-35 --- X --- N N N 2_____ RyValves (08a) Motor 2 M02-06-029B Feedwater Stop Valve Operated Valves Drywell 154 D/W2-35 --- --- ...X N N N 2 M02-10-013D RHR Pump D Torus Suction (O8a) Motor Reactor 91 R2-8 --- ...--- X --- N N N Operated Valves 2 M02-10-015B RHR Pump B Shutdown (08a) Motor Reactor 116 R2-18 --- X --- N N N Cooling Suction (2BP035) Operated Valves RHR Shutdown Cooling (08a) Motor 2 M02-10-018 Suction Inboard Isolation aDrywll 134 D/V2-17 --- X --- N N N Valve Operated Valves 2 MO2-10-174 HPSW to RHR Emergency (08a) Motor Reactor 91 R2-6 --- X --- N N N Inner Cross-tie Operated Valves HPCI Turbine Steam (08a) Motor Reactor 88 R2-13 -.--- N N N 2 MO2-23-014 Supply Valve Operated Valves 2 M02 Unit 2 Sluice Gate A (08a) Motor Screen 116 S/H-4 X X X X X N N N 2233A Operated Valves House HPSW Return Valve to (08a) Motor Diesel 2 MO-2-32-2486 hPrW Pon Opera) Motor Generator 121 D/G-2 --.--- 7-- X --- N N N Discharge Pond Operated Valves Building 2 M02 HPSW Discharge Inlet (08a) Motor Emergency 2804A Outer Valve Operated Valves Cooling 114 ECT-1 --- --- --- X -- N N N Towers 2 SV2-23A-4543 HPCI Turbine Stop Valve (08b) Solenoid Reactor 88 12-13 --- X .N N N Remote Trip Valve Operated Valves 2 SV-2-3-33 Instrument Air Solenoid (08b) Solenoid Reactor 135 R2-22 X .... ...... N N N Valve Operated Valves 2 SV-2-3-36 Instrument Air Solenoid (08b) Solenoid -22 X --- .. .....-N---Valve Operated Valves Reactor 135 R2 N N 2 2AV060 HPSW Pump Room Supply (09) Fans Pump 112 P/H-6 ---.... X --- N N N Fan A Structure 2 2BE55 RCIC Pump Room Cooling (10) Air Handlers Reactor 88 R2-114 --- X .....--- N N N Coil B 2 2BE56 HPCI Pump Room Cooling (10) Air Handlers Reactor 88 R2-13 --- --- X ---. N N N Coil B 2 2EE57 Core Spray Room B (10) Air Handlers Reactor 91 R2-10 --- --- X --- --- N N N Cooling Coil E I 2FE57 Core Spray Room B (10) Air Handlers Reactor 91 R2-10 --- X .N N N Cooling Coil ( A RHR Room D Cooling Coil (10) Air Handlers Reactor 116 R2-19 --- X N N N 2 2GE58 G Peach Bottom Atomic Power Station Unit 2 B-99 MPR-3815, Revision 3 Correspondence No.: RS-12-173 Table B-1. SWEL for Unit 2 NTTF 2.3 Function Risk New or IPEEE Unit Component Description EPRI Class Building Elevation Location Decay Significant?

Replace? Enhancement?

SWEL ID Reactivity Pressure Inventory Heat Containment 2 POD-2-40H-HPSW Pump Room (10) Air Handlers Pump 20223-3 Outside Air Supply Damper Structure 112 P/H-6 X X X X X N N Y POD-2-40H-HPSW Pump Room Pump 2 20223-4 Exhaust Return to Room (10) Air Handlers Structure 112 P/H-6 X X X X X N N Y Damper 2 20Y050 120VAC Distribution Panel (14) Distribution Turbine 150 T2-81 X X X X X N N N 2C Panels 2 20Y35 120V AC Distribution Panel (14) Distribution Reactor 135 R2-20 X X X X X N N N 2C Panels 2 2AD025 125V DC Distribution Panel (14) Distribution Turbine 150 T2-81 X X X X X N N Y Panels 2 2AD01 125V DC Battery 2A (15) Batteries

& Turbine 135 T2-70 X X X X X Y N Y Racks 2 2BD01 125V DC Battery 2B (15) Batteries

& Turbine 135 T2-169 X X X X X Y N Y Racks (16) Battery 2 20D37 Static Inverter Chargers and Turbine 135 T2-73 X X X X X N N Y Inverters (16) Battery 2 2AD03 Battery Charger 2A Chargers and Turbine 135 T2-170 X X X X X Y N N Inverters (16) Battery 2 2DD03 Battery Charger 2D Chargers and Turbine 135 T2-172 X X X X X Y N N Inverters (18) Instruments on 2 20C87 HPCI Instrument Rack Racks / Not on Reactor 88 R2-15 --- --- X --- --- N N N Racks (18) Instruments on 2 20C95 RCIC Instrument Rack Racks / Not on Reactor 88 R2-15 --- --- X --- N N N Racks RX Vessel Level and (18) Instruments on 2 2AC65 Racks / Not on Reactor 165 R2-40 --- X X --- --- N N N Pressure Instrument Rack A Racks RX Vessel Level and (18) Instruments on 2 2BC65 Racks / Not on Reactor 165 R2-40 --- X X --- --- N N N Pressure Instrument Rack B Racks HPSW Pump Room DP (18) Instruments on 2 DP20224-4 Sensor Racks / Not on Structure 112 P/H-6 X X X X X N N N Racks I 2 LS2-2391B Suppression Pool Level (18) Instruments on Racks / Not on Reactor 91 R2-10 --- --- --- X N N N Racks I IIII Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 B-100 Table B-I. SWEL for Unit 2 Unit Component NTTF 2.3 Function Risk New or IPEEE SWEL ID Description EPRI Class Building Elevation Location Decay Significant?

Replace? Enhancement?

Reactivity Pressure Inventory Heat Containment Torus Water Level (18) Instruments on 2Transmitter for LR-8123A Racks / Not on Reactor 91 R2-10 --- --- --- X X N N N Racks Reactor Pressure (18) Instruments on 2 PT2-2-3-404A Racks / Not on Reactor 165 R2-40 -- X --- --- --- N N N TransmitterRak Racks Containment Drywell (18) Instruments on 2 PT-2508A Pressure Transmitter for Racks / Not on Reactor 195 R2-53 --- --- X N N N PR-2508 Racks Reactor Wide Range (18) Instruments on 2Pressure Transmitter Racks / Not on Reactor 165 R2-40 --- X -.--- --- N N N Racks 2 TS-20224-01 HPSW & ESW Equipment (19) Temperature Pump 112 P/H-6 X X X X X N N N Room TS Sensors Structure 2 TS-20224-02 HPSW & ESW Pump Room (19) Temperature Pump 112 P/H-6 X X X X X N N N Sensors Structure 2 20C003 Reactor and Containment (20) Control Panels Turbine 165 T2-100 --- -- X ... ... N N N Cooling and Isolation

& Cabinets 2 20C004C RCIC Control Panel (20) Control Panels Turbine 165 T2-100 -- .--- X --- .N N N& Cabinets 2 20CO05A Reactor Manual Control (20) Control Panels Turbine 165 T2-100 X ... ... .....- N N N Panel & Cabinets 2 20C006C Main Control Room (20) Control Panels Turbine 165 T2-100 X --- --- --- --- N N N Console & Cabinets 2 20C39 HPCI Relay Cabinet (20) Control Panels Turbine 150 T2-81 --- --- X .N N N& Cabinets -2 20C722A Accident Monitoring (20) Control Panels Turbine 150 T2-81 X .--- --- --- N N Y Instrumentation Panel & Cabinets 2 20D43 HPCI Aux Lube Oil Pump (20) Control Panels Reactor 88 R2-13 --- -- X --.--- N N N Starter & Cabinets 2 2SC270 Steam B Leak Monitor (20) Control Panels Turbine 165 T2-100 .. .--- X ...... N N N Cabinet & Cabinets 2 L12-2-3-113 Reactor Water Level (20) Control Panels Turbine 165 T2-100 --- X ... ... N N N& Cabinets 2 LI2-3-86 Reactor Vessel High Water (20) Control Panels Turbine 165 T2-100 --- --- X ...... N N N L12-3-8 R& Cabinets 2 LI-8027 Torus Water Level (20) Control Panels Turbine 165 T2-100 .... .. X X N N N& Cabinets Torus Water (20) Control Panels 2 LRITR-8123B Level/Temperature

& Cabinets Turbine 165 T2-100 ... ... ... X X N N N____Recorder

&Cbnt eHPC Turbine Lube Oil (21) Tanks or Heat 2 20E105 Exchangers Reactor 88 R2-13 -- --- X ----- N N N Cooler I(Vertical)

Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 B-101 Table B-1. SWEL for Unit 2 NTTF 2.3 Function Unit Component Description EPRI Class Building Elevation Location Decay Risk New or IPEEE SWEL ID Reactivity Pressure Inventory Heat Containment Significant?

Replace? Enhancement?

(21) Tanks or Heat 2 2BE24 RHR Heat Exchanger B Exchangers Reactor 116 R2-18 --- --- X --- N N N (Vertical)

(21) Tanks or Heat 2 2BS377 Back-up N2 Supply to ADS Exchangers Reactor 135 R2-23 --- X --- --- N N N (Vertical)

(21) Tanks or Heat 2 2DE24 RHR Heat Exchanger D Exchangers Reactor 91 R2-8 --- --- X --- N N N (Vertical)

(21) Tanks or Heat 2 2GT545 Instrument N2 Accumulator Exchangers Drywell 155 D/W2-35 X --- --- N N N I (Vertical)

(21) Tanks or Heat 2 2KT545 Instrument N2 Accumulator Exchangers Drywell 155 DM42-35 X --- --- N N N (Vertical)

Table B-2. SWEL for Unit 0 (common)Unit Component NTTF 2.3 Function Risk New or IPEEE SWEL ID Description EPRI Class Building Elevation Location Decay Significant?

Replace? Enhancement?

I _ Reactivity Pressure Inventory Heat Containment 0 00B061 Pump Structure MCC E224- (01) Motor Control Pump 112 P/H-6 X X X X X N N N P-A Center Structure El D/G Fuel Oil Transfer (05) Horizontal Diesel 0 OAP060 E1 DuG Generator 127 DIG-3 X X X X X Y N N 0Pump Pumps Building PEmergency Service Water (05) Horizontal Diesel 0 OAP163 Boos ter Pump Aorumns l Generator 127 DIG-1 X X X X X N N N Booster Pump A Pumps Building 0 ODP060 E4 D/G Fuel Oil Transfer (05) Horizontal Diesel Generator 127 DIG-9 X X X X X Y N N DPump Pumps Building 0 OBP057 Emergency Service Water (06) Vertical Pumps Pump 112 P/H-9 X X X X X N N Y 0 Pump B Structure ESW Outlet Block Valve Diesel 0 AO-33-0241D from Diesel Generator E4 (07) Fluid (Air/Hyd)

Generator 127 DIG-9 X X X X X N N N_ Coolers Valves Building TCV-0-52E-DIG Jacket Coolant 3-Way (07) Fluid (Air/Hyd)

Diesel 0 Generator 127 D/G-3 X X X X X N N N 7239A Thermostatic Control Valve Valves Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 correspondence No., RS-12-173 B-102 Table B-2. SWEL for Unit 0 (common)NTTF 2.3 Function Risk New or IPEEE Unit Component Description EPRI Class Building Elevation Location Decay Significant?

Replace? Enhancement?

SWEL ID Reactivity Pressure Inventory Heat Containment ESW Return to Discharge (08a) Motor Diesel 0 MO-0-33-0498 Generator 127 DIG-2 X X X X X Y N Y Pond Operated Valves Building ESW A Inlet to ECT (08a) Motor Emergency Reservoir Operated Valves Cooling 114 ECT-1 X X X X X N N N Resevi OTowers 0 OAV030 Control Room Emerg Vent Turbine 165 R-32 X X X X X N N N Supply Fan A (09) Fans 0 OAV036 Battery Room Exhaust Fan (09) Fans Radwaste 165 RNV-32 X X X X X N N N Diesel 0 0AV064 DIG Building Vent Supply (09) Fans Generator 151 D/G-19 X X X X X N N N Fan Building Emergency Cooling Tower Emergency 0 0BK032 Fan B C (09) Fans Cooling 195 ECT-6 X X X X X N N N Fan B _Towers 0 OBV030 Control Room Emergency (09) Fans Turbine 165 RNV-32 X X X X X N N N 0 0BY030 Ventilation Supply Fan B 0 0BV035 Emergency Switchgear Ventilation Exhaust Fan B (09) Fans Radwaste 165 RJW-32 X X X X X N N N 0 0BV036 Battery Room Exhaust Fan 0_ OV03 B (09) Fans Turbine 165 RJW-32 X X X X X N N N D/G Building Vent Supply Diesel 0 0DV064 Fan (09) Fans Generator 151 D/G-20 X X X X X N N N Fan Building PO-0-40F-Master for El EDG Building Diesel 00272-01 Vent Supply Fan Outside (10) Air Handlers Generator 151 D/G-19 X X X X X N N N Air Damper Building PO-0-40F-Master for El EDG Building Diesel 0 Vent Supply Fan Return Air (10) Air Handlers Generator 151 DIG-19 X X X X X N N N Damper Building El Standby Diesel (17) Engine Diesel 0 OAG012 e1eStor Gene Generator 127 DIG-3 X X X X X Y N Y 0 AO2 Generator Generators Bidn I Building 2 E4 Standby Diesel (17) Engine Diesel ne Generator 127 D/G-9 X X X X X Y N Y 0 0DG0I2 Generator Generators Building Diesel TS-0607D E4 DIG Jacket Coolant (19) Temperature Generator 127 D/G-9 X X X X X N N N Temperature Sensor Sensors Building 0 00C29B Emergency Protection (20) Control Panels Turbine 165 T2-100 N N Y___0_Relay Board & Cabinets Turbine 165IT2-100 X I ... .. I I IYII Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 B-103 Table B-2. SWEL for Unit 0 (common)Unit Component NTTF 2.3 Function Risk New or IPEEE SWEL ID Description EPRI Class Building Elevation Location Decay Significant?

Replace? Enhancement?

Reactivity Pressure Inventory Heat Containment 0 OAC097 Diesel Generator OAG12 (20) Control Panels Diesel Coto ae aiesGenerator 127 DIG-3 X X X X X N N N o A07 Control Panel & Cabinets Bidn Building 0 OAT096 El Diesel Generator Lube (21) Tanks or Heat Diesel Oil Storage Tank Exchangers Generator 127 D/G-3 X X X X X N N N (Horizontal)

Building El Diesel Generator Fuel (21) Tanks or Heat Diesel 0 OAT040 Oil Day Tank Exchangers Generator 127 DIG-3 X X X X X N N N I (Vertical)

Building 0 ODE377 E4 Diesel Generator Lube (21) Tanks or Heat Diesel Oil Cooler Exchangers Generator 127 DIG-9 X X X X X N N N (Vertical)

Building E4 Diesel Generator Fuel (21) Tanks or Heat Diesel 0 ODT40 Oil Day Tank Exchangers Generator 127 DIG-9 X X X X X N N N (Vertical)

Building E4 Diesel Generator (21) Tanks or Heat Diesel 0 OHT95 Starting Air Reseroir Exchangers Generator 127 DIG-9 X X X X X N N N StartingAirReseroeI l (Vertical)

Building I Table B-3. Deferred to Electrical Bus Outage: Electrical Safety Concern Peach Bottom Atomic Power Station Unit 2 MPR-3815, Revision 3 Correspondence No.: RS-12-173 B-104